ML20101J421
| ML20101J421 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 12/19/1984 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8412310017 | |
| Download: ML20101J421 (4) | |
Text
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o DUKE POWER GOMPANY e.o. nox aanan CHAMLoTrE, N.O. 2a242 HAL H. TUCKEH ret.cruoxe vum resernewe (yo.3) ay 6fRM a
~~ ~ ~
December 19, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. l'iclear Regulatory Cotmission Washingcon, D. C. 20555 Attention:
Ms. E. G. Adensara, Chief Licensing Branch No. 4
Subject:
McGuire Nuclear Station - Docket No. 50-369/370 Catawba Nucicar Station - Docket No. 50-413/414 Response Request for Additional Information Regarding Topical Report DPC-NF-2010. " Nuclear Physics Metodology for Reload Design" In response to the request by telephone conference (between NRC, Duke and Brookhaven) on December 17, 1984 for additional information regarding the subject topical report, attached is Duke Power Company's revised answer to question number five, regarding pin power uncertainties.
If any additional information or discussion is desired, please feel free to call Scott Gewehr Duke Power Licensing at (704) 373-7581.
Very truly yours, l
k V g,/c Ital B. Tucker SAG /mjf Attachment cc:
Dr. John Carew Building 475 B Brookhaven National Laboratory Upton, N. Y. 11973 Mr. Jesse L. Riley, President Carolina Environmental Study Group 854 llenley Place Charlotte, North Carolina 28208 James P. O'Reilly, Regional Administrator U. S. Nuc1 car Regulatory Commission.
Region 11 101 Marietta Street, N. W., Euite 2900 Atlanta, Georgia 30323 J'* l l 0
O Mr. Harold R. Denton, Director December 19, 1984 Page Two cc:
Mr. Robert Guild, Esq.
P. O. Box 12097 Charleston, South Carolina 29412 Palmetto Alliance 2135 h Devine Street Columbia, South Carolina 29205 Mr. W. T. Orders Senior Resident Inspector McGuire Nuclear Station Senior Resident Inspector Route 2 Box.179N York, South Carolina 29745 Ms. L. L. Williams, Manager Nuclear Services Integration Division Westinghouse Electric Corp.
P. O. Box 2728 Pittsburgh, Pennsylvania 15230
Q.5 Duke Power Company's contention that no uncertainty in calculated pin powers needs to be accounted for has not been adequately established.
One of a set of standard problems, recently de-veloped at Brookhaven National Laboratory for a licensee to assess its ability to calculate typical PWR fuel assemblies, is attached.
The licensee's solution using PDQ07 will be an important means of determining the uncertainty in the calculated pin peaking factors.
Re:
A.5 Based upon the Duke solution to the BNL benchmark assembly problem, BNL has identified an underprediction of the peak pin power after about 15,000 MWDhrrU which increases to about 1%
at 40,000 MWD /MTU. As a result of a conferenca call held December 11, 1984 between BNL, NRC and Duke, it was determined that a two percent radial local uncertainty was conservative and would be applied in a statistical combination with the reliability f actors and engineering hot channel factor.
The three factors to be statistically combined to determine theFgUF factor to multiply the calculated F ;g are:
3 F E the. Engineering IIcat Flux Ilot Channel Factor, is 1.
allowance on heat flux for manufacturing tolerances.
This factor allows for local variations in enrichment, pellet density, and diameter.
It's numeric value is 1.03.
Fhg, the Observed Nucicar Reliability Factor for Fall.
2.
This f actor is developed in Section 11.5 and is 1.03.
It represents the ability of EPRI-N0DE-P to calculate assembly average power.
R RL, Radial Local Uncertainty or pin power uncertainty.
3.
It represents the ability of EPRI-CELL /PDQ07 to calculate the pin power in an assembly.
Determined to be 2%.
These factors are statistically combined as follows:
F E 1+N(.03)2 + (,03)2 + (.02)2 ' = 1.047.
Where SCUP is the statistically combined uncertainty factor.
These factors are statistically independent because they are cal-cuinted using dif ferent codes and represent different phenomenn.
The NRC has previously reviewed and approved the statical com-bination of the radial local uncertainty factor and the Fhg f actor in Northern States Power's report " Qualification of Reactor Physica Methods for Application to Prairie Island Units NSPNAD-8101NP',' December 1981.
In addition, the NRC has previously reviewed and approved the statistical combination of all three i
f actors in Westinghouse's " Improved Thermal Design Procedure",
j WCAP-8576, July 1975.
l
The three factors to be statistically combined to determine the F{CUF factor to multiply the calculated Fq by are:
E Fq, Engineering Heat Flux Hot Channel Factor, 1.03.
1.
R 2.
Fq, Assembly. Peak Axial Observed Nuclear Reliability Factor. This factor is developed in Section 11.5 and consists of a bias of (
) and a Eg_of 0.035.
M R
3.
RL, Radial Local Uncertainty or pin power uncertainty, 2%.
SCUF factor, where The factors are combined to determine the Fq SCUF is the statistically combined uncertainty factor, as follows:
SCUF 1 +1.375.031 +M(.03)2 + (.035)2 + (.02)2 1,o 73 F9 F [ will replace F$g in equation 6-2 and Fq will replace SCUF R
E Fq xp in equation 6-3.
q
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