ML20037A442
| ML20037A442 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/12/1974 |
| From: | Thies A DUKE POWER CO. |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20037A441 | List: |
| References | |
| NUDOCS 8001230660 | |
| Download: ML20037A442 (4) | |
Text
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AEC DIS
.31"rION FOR PART 50 DOCKET MATE &
T (TDiPORARY. FORM)
CONTROL NO:
2565 (O
FILE: MON REPT FILE P/0 FROM:
DATE OF DOC DATE REC'D LTR MEMO RPT CTdER Duke Power Company Charlotte, North Carolina A. C. Thies 3-12-74 4-2-74 X
TO:
ORIG CC OTHER SENT AEC PDR vyv Director 1 signed CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:
XXX 1
270 DESCRIPTION:
ENCLOSUPIS:
Ltr re our ltr 2-19-74 trans the following...
Report: January 4 February Plant & Component Operability & Availability...this rpt ACRTOWLEDGED to be used for Preparing Grey Book by Plans & Operations DO N.0T REMOV::
PLANT NAME:OCONEE UNITS 1 & 2 (1 cy encl rec'd)
FOR ACTION /IhTORVATION 4 5-7a nur EUTLER(L)
ISCWENCER(L)
ZIEMANN(L)
REGAN(E)
W/ Copies W/1 Copies info W/ Copies W/ Copies CLARK (L)
STOLZ(L)
DICKER (E)
/W. MAGEE W/ Copies W/ Copies W/ Copies W/2 Copies GOLLER(L)
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KNIGHION(E)
W/ Copies W/ Copies W/ Copies W/ Copies KNIEL(L)
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MUNTZING/ STAFF MACCARY KASTNER GEARIN (L)
CASE KNIGHT BALLARD GOULBOURNE (L)
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MORRIS LAINAS WILLIAMS (E)
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Director Office of Plans and Schedules Directorcte of Licensing Office of Regulation U. S. Atomic Energy Com:nission Washington, D. C.
20545 Re: Oconee Nuclear Station Units 1 and 2 Docket Nos. 50-269 and 50-270
Dear Sir:
Please find attached information requested in Mr. L. Manning Muntzing's letter of February 19, 1974 supplemented by his telefax of February 28, 1974. This information is submitted on the forms which you have pro-vided and covers the performance and operating status of Oconee Units 1 and 2 for the months of January and February 1974.
By copy of this letter to Mr. Muntzing, I am suggesting certain changes to definitions in your AEC Operating Status Report. The utility industry has for a number of years reported similar information to the Edison Electric Institute using standardized definitions of such terms as availability factors, capacity factors, and outage rates. These definitions are contained in the appendix to " Report on Equipment Availability for the 13-Year Period, 1960-1972," EEI Publication #73-46, issued December, 1973, a Report of the Equipment Availability Task Force of the Prime Movers Committee, Edison Electric Institute, 90 Park Avenue, New York, New York, 10016. A copy of this appendix is attached.
The use of standardized definitions has made possible the comparison and evaluation of power plant performance data from much of the utility industry. We believe that the adoption of the EEI standardized definitions would enable both you and us to better evaluate nuclear power plant per-formance and would facilitate comparison of nuclear and fossil power plants.
Specifically, the following suggestions are offered.
1.
Item 10 in the AEC Operating Status Report is " Reactor Availability Factor," which is defined as:
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,Direptor Office of Plans and Schedules Page 2 March 12, 1974 1
'I Reactor Availability Factor = Hours Reactor was Critical x 100 Gross Hours in Reporting Period This definition should correspond to what the EEI calls " Operating Availability Factor":
l Reactor Availability Factor = Reactor Availabic. Hours x 100 Period Bours Where: Available Hours = Time in hours during which a reactor is available or Service Hours plus Reserve Shutdown Hours.
Reserve Shutdown Hours = Number of hours for which a reactor is removed from service for economy or similar reasons but is still available.
Your present definition corresponds to what the EEI calls " Service Factor":
Service Factor = Service Hours x 100 Period Hours Where: Service Hours = Total number of hours that a unit was actually operated (i.e., the reactor was critical)
Period Hours = Clock hours in the period under consideration.
2.
The same general comments apply to plant availability factor which is -
Item 11 in your Operating Status Report.
3.
Your definition of " Plant Capacity Factor" (Item 12) generally matches the EEI definition, except that EEI does not specify net generation.-
However, this can be optional as far_as we are concerned. We do note, however, that your capacity factor uses " currently licensed power level" in the denominator.
The currently licensed thermal power level for Oconee is 2568 MWt; we do not have a currently licensed electrical power level. We have declared the maximum net dependable capability of our Oconee Unit 1 to be 871 MWe, even though the equivalent electrical power calculated from the thermal power was 886.3 MWe. The 871 HRe is the " commercial rating" of the unit, since this is what the generator will produce as net available to the system on a continuous basis.
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Director Offihe of Plans and Schedules Page 3 March 12, 1974 Ee believe that the 871 MWe marimum net dependable capability is the number that should be used in the denominator of your formula for plant capability factor. This mnrimum net dependable capability should also replace that portion of Item 2 of the Operating Status Report which requests currently authorized power level - MWe-NET.
4.
Your Item 13, which defines forced outage rate, is consistent with the EEI definition.
5.
To be consistent throughout the operating status report, the term
" Gross Hours in Reporting Period," should be replaced by the EEI term, " Period Bours."
Over the years, our industry has had some inconsistency in the definition of these various factors, and in recent years, EEI has been able to bring some order out of this chaos by publishing specific definitions which have been generally accepted by the utility industry. Duke Power Company urges the commission to standardize its definitions with those of the Edison Electric Institute to the extent practicable.
Very truly yo g,
Mb A. C. Thies ACT:vr Attachment ec: Mr. L. Manning Muntzing Mr. N. C. Moseley Mr. E. C. Kistner, Chairman Prime Movers Committee, EEI Mr. H. J. Young, Vice President
& Secretary, ETI