ML19305B762
| ML19305B762 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 02/12/1980 |
| From: | Reeves E Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003200273 | |
| Download: ML19305B762 (6) | |
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ELUIU!!Y EGCHI;EE c0;y FEBRUARY I 2 G 0 Docket Hos. 50-295 and 50-304 D
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,M ju o 10. Ej LICENSEE: Commonwealth Edison. Company (CECO)
FACILITY: Zion Station Unit Nos. I and 2 SLGJECT:
MEETING
SUMMARY
ON CECO'S PROPOSAL TO INCEEASE T11E RADIAL PEAKING FACTOR, Fq FOR ZION STATION FRCH 1.86 TO 1,93 The itcensee (CECO) and Westinghouse Electric Corporatica (Westinghouse), the nuclear steam supply steam vendor, for Zion Station met with the NRC staff on January 10, 1980. The purpose of the meeting was to review CECO's proposals for an increase in Fq from 1.86 to 1.93 CECO addessed the items contained in the enclosed meeting agenda. The list of meeting attendees is also enclosed.
Discussion 1.
CECO (Lippitt) introduced Westinghouse (Leech) who provided responses to the NRC staff concerns telating to allowances for uncertanties in Table 1 of Westinghouse letter dated Febrsery 5,1974 (NS-RS-133).
2.
Westinghouse (Kopelic) discussed the treatment of fuel tenperatures used in the loss of Coolant Accident (LOCA) analysis.
3.
Westinghour ' (Leech) discussed the effect of fuel-clad gap on fuel centerline temperature.
Included were the number of data points bounded, the mean and standard deciation for thirteen instrumental fuel rods. The basis for selecting data for the temperature comparisons was stated to be WCAP-8720 i
NRC (Voglewede) expressed some concern that data presented included data not in the range of Fq operation at Zion Station.
4.
Westinghouse (Leech) then summarized with a review of previous sutaittals as fbilows:
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a.
The overall LOCA analysis is conservative.
b.
Factors thset contribute to tenperature uncertainties are conservatively accounted for in the LOCA analysis.
c.
Uncertainties in the fuel average temperature are lower than uncertainties in fuel centerline temperatures..
d.
Best estimate temperature predictions are conservative.
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2-Summary NRC (Voglewede) reviewed the NRC staff's independent study which indicates that the uncertainties proposed by CECO would be acceptable. However, we requested a femal submittal by CECO to document the infomation provided "at this meeting prior to NRC staff's final action on the CECO proposal.
Oc~;;nal signed by Edward A. Reeves, Project Manager Operating Reactors Branch #1 Division of Operating Reactors
Enclosures:
1.
Meeting Attendance 2.
Agenda cc: See next page O
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. cc: Robert J. Vollen, Escuire 109 North Dearborn Street
- c. Grimes Chicago,Iflinois 60602 T. Ippolito R. Aeic Dr. Cecil Lue-Hing V. isoonan Director of Research and Development G. Knignton Metropolitan Sanitary District L. Srinkaan of Greater Chicaco Prc;ect Manager 100 East Erie Street CIL)
Chicago, Illinois 60611 C!il (3)
C. Parrish/P. Kreutzer Zion-Benton Public L1urary District A RS (16) 2600 Emmaus Avenue idC Participants Zion, Illinois 60099 id!C TERA Mr. Phillip P. Steptoe icensee Isham, Lincoln and Seale Incrt Service List Counselors at Law One First National Plaza 42nd Floor Chicago, Illinois 60603 Susan N. Sekuler, Esquire Assistant Attorney General Environmental Control Division s
188 West Randolph Street, Suite 2315 Chicago, Illinois 60601 D
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Ms fGC PDR Local PCR f.sbl Reading tar Reading
- h. Denton E. Case D. Eisenhut R. Tedesco G. Zecn E. Grices W. Gamill L. Shao J. Miller R. /ollaer T. J. Carter A. Schwencer C. Ziemann P. Cneck G. Lainas C. Crutchfield
EllCLOSURE 1 CECO MEETI?lG ATTE?lDAf1CE
!1RC Edward Reeves Ralph Meyer John Voglewede Richard Lobel CECO A. Warren Lippitt Westinghouse W. J. Leech J. Skartka Steven Kpelic i
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ENCLOSURE 2 AGENDA FOR NRC/ CECO W MEETING ON ZION PEAKING FACTORS JANUARY 10, 1980 I.
REDUCTION OF AVERAGE FUEL TEMPERATURE DUE TO THE USE OF AS FABRICATED RATHER THAN DESIGN VAltlES.
A.
Licensee should provide:
1.
Table 1, page B.5-5 of Westinghouse letter NS-RS-133 dated 2/5/74.
2.
Table 1 as described above, but revised to consider current density and fuel model for design values.
3.
Table 1 as described above, but revised to consider current density and fuel model for as-fabricated values.
4 Statistical methods employed inderiving allowance for uncertainties in Table 1 (populations, sampling rate, batch to reload relation, etc.).
5.
Explanation of current allowance for uncertainty in sintering temperature for both design and as-fabricated case.
6.
Justification for probability basis on which the uncert inties due to manufacturing variations were deten '1ed, !f d;frerent from the 2a values listed on page B-5-4 of 'C.<S-133, 7.
Explanation of the temperature unctrtainty (190'F) on page 8.5-4 of NS-RS-133 and revised value, if any.
II. REDUCTION OF AVERAGE FUEL TEMPERATURES 00E TO ELIMINATION OF MODEL UNCERTAINTY A.
Licensee should provide:
1.
Explanation of the use of PAD-3.3 code output (wnere centerline temperature is used, where average temperature is used, where stored energy is used, where gap conductance is used, etc.) in other safety analyses.
2.
Figure 2 from Naughten to Denton letter dated Novenber 14, 1979 including total numbed of data points, number of data points bounded, mean, and standard deviation for:
a.
All 13 instrumented fuel rods, including all points from IFA-3, IFA-4 and IFA-10.
b.
All 13 instrumented fuel rods, excluding IFA-3, IFA-4 and 3 points from IFA-10.
c.
All 13 instrumented fuel rods, excluding IFA-3, IFA-4 and IFA-10.
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ENCLOSURE 2 9
2-3.
Justify the suffici3ncy of the data base selected.
B. 'NRC will provide preliminary evaluation of the reduction of average fuel temperatures due to the elimination of the model unc ertainty.
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