ML20247D020
| ML20247D020 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/31/1989 |
| From: | Colehour L, Pleniewicz R COMMONWEALTH EDISON CO. |
| To: | NRC, NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BYRON-89-0860, BYRON-89-860, NUDOCS 8909140168 | |
| Download: ML20247D020 (18) | |
Text
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"N Commonwealth Edison f
j r
). Byron NucirarSt: tion
- j 4450 North German Church Road x
,' Byron, Illinois 61010 x-September'10, 1989 LTR:
BYRON 89-0860 FILE:
2.7.200 Director, Office of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C.
20555 ATTN Document Control Desk Gentlemen Enclosed for your information is the Monthly Performance Report covering Byron Nuclear Power Station for the period August 1 through August 31, 1989.
Sincerely,
/
R.
Pleniewicz Station Manager Byron Nuclear Power Station RP/ LLC /bb (0625M/0062M) cc:
A.B.
Davis, NRC, Region III NRC Resident Inspector Byron Ill. Dept. of Nuclear Safety T.J. Malmen/K.L. Graesser Lclear Licensing Manager Nuclear Fuel Services, PWR Plant Support L. Anastasia, Station Nuclear Engineering INPO Records Center L. Olshan - USNRC 8909140168 890831
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l BYRON NUCLEAR POWER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT COMMONWEALTH EDISON COMPANY NRC DOCKET NO.'050-454 NRC DOCKET NO. 050-455 LICENSE NO. NPF-37 LICENSE NO. NPF-66 l
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Monthly Report for Byron Unit I for the month of August 1989 i
A....SEDRAIy of Operating Experience for Unit l' The unit began this reporting period in Mode 1 (Power Operation) at approximately 100% power. The unit operated at power. levels of up to 100V for the reporting period.
i-I 4
(0625M/0062M-3) t__
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OPERATING DATA REECRI DOCKET NO.:
050-454 UNIT:
Byron One DATE: 09/10/89 COMPILED BY:
L. Colehour TELEPHUNF (815)234-5441 x2730 OPERATING STATUS 1.
Reporting Period: August 1989. Gross Hours:
744 2.
Currently Authorized Power Level: 3411 (MWt)
Design Electrical Rating: 1175 (MWe-gross)
Design Electrical Rating: 1120 (MWe-net)
Max Dependable Capacity: 1105 (MWe-net) 3.
Power Level to Which Restricted (If Any): N/A 4.
Reasons for Restriction (If Any):
THIS MONTH YR TO DATE CUMULATIVE
- 5.
Report Period Hrs.
744 5,831 34,704 6.
Rx Critical Hours 744 5,814 27,611 7.
Rx Reserve Shutdown Hours 0
0 38 8.
Hours Generator on Line 744 5,809 27,166 9.
Unit Reserve Shutdown Hours 0
0 0
- 10. Gross Thermal Energy (MWH) 2395156 18301282 81828595
- 11. Gross Elec. Energy (MWH) 812578 6229110 27541991
- 12. Net Elec. Energy (MWH) 770447 5903843 25936351
- 13. Reactor Service Factor 100 99.7 79.6
- 14. Reactor Availability Factor 100 99.7 79.7
- 15. Unit Service Factor 100 99.6 78.3
- 16. Unit Availability Factor 100 99.6 78.3
- 17. Unit Capacity Factor (MDC net) 93.7 91.6 67.6
- 18. Unit Capacity Factor (DER net) 92.5 90.4 66.7
- 19. Unit Forced Outage Hrs.
0 22 1057
- 20. Unit Forced Outage Rate 0
0.4 3.7
- 21. Shutdowns Scheduled Over Next 6 Months:
- 22. If Shutdown at End of Report Period, Estimated Date of Startupt
- 23. Units in Test Status (Prior to Commercial Operation): None
- Note - The cumulative numbers do not reflect power generated prior to commercial service.
(0625M/0062M-4)
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4.
'C.
' AVERAGE DAILY UNIT POWER LEVEL
DOCKET NO,:
050-454 f ~,
UNIT:.. Byron One DATE:- 09/10/89 COMPILED BY:
'L.= Colehourf TELEPHONE: -(815)234--5441-x2730 MONTH:- August,--1989 m
DAY.
AVERAGE DAILY. POWER LEVEL (MWe-Net).
1; 1089 MW 16.
1100 MW 2.
'1024 MW
- 17. :
1060 MW
'3.
1077'MW-18.
1012 MW-
'4.
1072-MW 19. -
976 MW'
.5.
1085 MW 20.
977 MW 6.
1023 MW 21.
1017.MW l
7..
1015 MW' 22, 1088 MW~
l-8, 1009 MW 23.
1009 MW 9.
-1025 MW 24.
1021 MW 1:
10.
1038 MW 25, 1027 MW 11, 1003 MW 26, 1096 MW I
l-l 12.
'15.
1022 MW 30.
1026 MW 31, 1090 MW INSTRUCTIONS On this form list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line.) In such cases the average daily unit power output sheet should be footnoted to explain the apparent anomaly.
(0625M/0062M-5)
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UNIOUE REPORTING REQUIREMENTS (UNIT 1) for the month of Aucust 1989 1
1.
Safety / Relief valve operations for Unit One.
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1 VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ALiiVE11 faiRITION OF EVENT a
None 2.
Licensee generated changes to ODCM.
(Y/N)
~
Yes See attached.
3.
Indications of failed fuel.
(Y/N)
Yes Possibly one leaking fuel pin No steady state nominal power data is available, i
(0625M/0062M-7)
l gg,g,89
~13:4 NO.059 P003/004 ATTACHMENT 8 Revisions to the Offsite Dose Calculation Manual-(00CM) are report &ble to the NRC in accordance with stations' technical specifications.
The document contains the modelsl for the public dose assessment from gaseous effluents, liquid discharges, and direct radiation.
In 1988, in response to the NRC's request to seke thel 00CM a more readable document as well as to incorporate certain changes, Commonwealth Edison rewrote its ODCN. This document, renumbered to Revision 0, March, 1989, will be submitted under sep8 rate cover.
This summary describes the principal non-edited changes.
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The NRC, in NuReg 0472 Rev. 3 Draft 7 has identified the child's thyroid and not the infant's as the most sensitive organ from the inhalation of airborne effluents.
Dresden, LaSalle, and Quad Cities Stations' 10CFR20 instantaneous releane rate limits have been revised to restrict the dose rate to the child's thyr id to less or equal to 1500 ares /yr.
I Hydrogen addition t the primary coolant increases the boiling water reactors'
'i turbine N-16 shyshine by a magnitude of 5.
This phenomenon is nowitncluded in the 00CM formulation.
In add' tion the sky shine calculation is written for LaSalle County Station as well as revised in Dresden and Quad Citios.
4 NIIM DUWGES l
Most of the 00CM documentation has been either clarified, corrected or deleted.
Plume depletion, terrain factors and heat content were not accounted for in the original for D/0, X/Q and plume rise calculations.
They are d(scribed in the rev' sed document.-
ItwasimpliedthattheX/Qdosefactorswerecalculatedassumingal mono-i onergetic gamma energy having an average gamma ray energy per diseritogration for each radionuclides. Also, it was assumed that the corrected tissue absorptions were made using a tissue energy absorption coefficient: equivalent to this same average dose factors and the gamma ray energy for each radionuclides. Actually, the tissue energy absorption coefficients referenced were calculated using the photon energy spectra for each radionuclides.
The tissue energy absorptions coefficients are negligible and have been deleted from the text.
Formulas and parameters for determining the maximum permissible concentrations j
(NPC's) have >een eliminated from the section on radioactivity in storage tanks.
The maximumilimits, in curies, are found in the site specific sections.
J l
l 8076E/3
_ _ _ _ ~
/M/69 13:46 NO.059 P004/004 ATTACHMENT 8 (Cont.)
The potential direct radiation dose from stations' interim radwast<r storage facilities is discussed.
The radwaste containers will have a cont 8ct dose rate of 5 R/hr and the expected radiation levels will be minimal at the site boundary.
I The distance dependent parameters were adjusted to the values repolrted in
'88 census for nearest residents and/or nearest milch animal. This also affected the D/Q tables and BNR turbine N-16 shyshine calculation.'
The time of travel from the station liquid discharge to the neares community water supply was reevaluated for Braidwood and Quad cities.
ODCM Revision 0, March 1989 has received approvals by all six onsite review committees and the CECO offsite review per the Technical Specifications.
Changes to the computer program required by this document are in the process of being i lesented now and should be fully available by-November 1,1989.
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8076E/4
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LICENSEE EVENT REPORTS (UNIT 1)
The following is a tabular summary of all Licensee Event Reports for Byron Nuclear Power Station, Unit One, submitted during the reporting period, August 1 through August 31, 1989. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.
Occurrence Licensee Event Report Number Qgin Title of Occurrence 89-007 8/3/89 Control Room ventilation actuation due to voltage transient caused by lightening.
l l
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II. Monthly Report for Byron Unit 2 for the month of Auoust 1989 A.
Sumtrary of Ooeratino Experience for Unit 2
'Ihe unit began this reporting period in Mode 1 (Power Operation) at approximately 91% power.
The. unit operated at power levels of up to 91%
for the reporting period.
t (0625M/0062M-9)
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OPERATIEG DATA REPORT DOCKET NO.:
050-455
' UNIT - Byron Two DATE:,,09/10/89 COMPILED BY: L..Colehour; TELEPHCNE:
(815)234-5441.
x2730 OPERATING STATUS 1.
Reporting Period: August 1989. Gross. Hours 744 2.
' Currently Authorized Power Levels.3411-(MWt)
Design Electrical Rating: 1175 (MWe-gross)
~
Design Electrical Rating: 1120 (MWe-net)
Max Dependable Capacity: 1105 (MWe-net) 3.
Power Level to.Which Restricted (If Any): N/A 4.-
Reasons for Restriction'(If Any):
THIS MONTH YR TO DATE CUMULATIVE
- 5.
Report Period Mrs.
744 5831-17808
- 6.
Rx Critica1' Hours 744 4315-15320 7.
Rx Reserve Shutdown Hours 0
0 0
8.
Hours Generator on Line
'744 4241 14942 9.
Unit Reserve Shutdown Hours 0
0-0
- 10. Gross Thermal Energy (MWH) 1929930 10202102 37027519
- 11. Gross Elec. Energy (MWH) 666337
'3496987 12394904
- 12. Net Elec. Energy (MWH) 627108 3260777 11589603
- 13. Reactor Service Factor 100 74.0 86.0
- 14. Reactor Availability Factor 100 74.0 86.0
- 15. Unit Service Factor 100 72.7 83.9
- 16. Unit Availability Factor 100 72.7 83.9
- 17. Unit Capacity Factor (MDC net) 76.3 50.6 58.9
- 18. Unit Capacity Factor (DER net) 75.3 49.9 58.1
- 19. Unit Forced Outage Hrs.
0 169 632
- 20. Unit Forced Outage Rate 0
3.8 4.1
- 21. Shutdowns Scheduled Over Next 6 Months:
- 22. If Shutdown at End of Report Period, Estimated Date of Startup:
- 23. Units in Test Status (Prior to Commercial Operation): None
- Note - The cumulative numbers do not reflect power generated prior to commercial service.
(0625M/0062M-10)
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: '050-455^
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UNIT: Byron Two.
' 09/10/89 DATE COMPILED BY
,L.
Colehour.
r TELEPHONE:
(815)234-5441 x2730 MONTH: August, 1989 DAY AVERAGE DAILY POWER. LEVEL (MWe-Net)
.1.
857 MW 16.
862 MW 2.
938 MW' 17.
869 MW 3..-
916 MW 18.
758 MW 4.
892 MW' 19.
753 MW
'5.
871 MW 20.
651 MW' 6.
~688 MW' 21.
836 MW
. 7..
~847 MW 22.
910 MW' 8.
910 MW 23.
768 MW 9.
891 MW 24.
718 MW
' '10.
874 MW 25.
843 MW 11.
873 MW 26.
895 MW 12.
7 95 MW 27.
935 MW 13.
754 MW 28.
924 MW
.14.
788 MW 29.
908 MW
'15.
822 MW 30.
935 MW 31.
833 MW INSTRUCTIONS On this form list the average daily unit power level I 2 MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit there s..ay be occasions when the daily average power level exceeds the 100% line (or the restricted power level line.)
In such cases the average daily unit power output sheet should be footnoted to explain the apparent anomaly.
(0625M/0062M-11)
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UNIOUE REPORTIN'G REQUIR N NTS (UNIT 2I for'the month of Auoust 1989
.lb M y
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1.; ' Safety / Relief valve-operations. for Unit Two.-
7 u
' VALVES-
' NO & TYPE
. PLANT.:
DESCRIPTION.
~
. DATE' ACTUATED ACTUAII(Ri1 CONDITICM OF EVENT s
'6 None-e
' : 2.". - Licensee generated changes to ODCM.' (Y/N) s
-'Yes See attachedD
.J.
3.
.Indicat. ions.'of failed fuel. '(Y/N),
.i yest No steady state nominal power data is available.
I S
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-(0625M/0062M-13)
.m_.___.
_.m.__
09/07/89 13:45 NO.059 P003/004 o
ATTA000ENT B Revisiofes to the Offsite Dose Calculation Manual (00CM) are report &ble to the NAC in accordance with stations' technical specifications. The document contains the models for the public dose assessment from gaseous effluents, liquid discharges, and direct radiation.
In 1988, in response.to the NRC's certain changes, Coml00CM a more readable document as well as to incorporate request to make thd monwealth Edison rewrote its 00CM.
This docungnt, renumbered to Revision O. March, 1989, will be submitted under seperate cover.
This summary describes the principal non-edited changes.
l MAaon tumcEs l
1 The NRC, in NuReg 0472. Rev. 3 Draft 7. has identified the child's thyroid and not the infant's as the most sensitive organ from the inhalatten of airborne effluents.l Dresden, LaSalle, and Quad Cities Stations' 16CFR20 instantaneous release rate limits have been revised to restrict the dose rate to the child's thyroid to less or equal to 1500 mres/yr.
Hydrogen addition to the primary coolant increases the boiling water reactors' turbine N-16 shyshine by a magnitude of 5.
This phenomenon is nowlincluded in the 00CM formulation.
In addition the sky shine calculation is written for LaSalle County Stat 4on as well as revised in Dresden and Quad Citins.
MIM DMIES Most of the ODCM documentation has been either clarified, corrected or deleted.
Plume depletion, terrain factors and heat content were not accounted for in the ort inal for D/Q, X/Q and plume rise calculations.
They are described in the rev sed document.
It was implied that the X/Q dose factors were calculated assuming a mono-energetic gamma energy having an average gamma ray energy per diseritogration for each radionuclides. Also, it was assumed that the corrected tissue absorptions were made using a tissue energy absorption coefficient l equivalent to this same average gamma ray energy for each radionuclides. Actually, the dose factors and the tissue energy absorption coefficients referenced were calculated using the photon energy spectra for each radionuclides. ;The tissue energy absorptions coefficients are negligible and have been deleted from the j
text.
Formulas and parameters for determining the maximum permissible concentrations (MPC's) have been eliminated from the section on radioactivity in storage tanks.
The maximum ilimits, in curies, are found in the site specific sections.
f l
l 4
8076E/3 i
094We9 23:46 NO.059 P004404 ATTACHMENT 8 (Cent.)
The potential direct radiation dose from stations' interim radwastie storage facilities is discussed. The radwaste containers will have a contact dose rate of 5 R/hr and the expected radiation levels will be minimal at the site boundary.
The distance dependent parameters were adjusted to the values repolrted in the
'88 census for nearest residents and/or nearest milch animal. This also affected the D/Q tables and BMR turbine N-16 shyshine calculation.'
The time of travel from the station liquid discharge to the nearest community water supply was reevaluated for Braidwood and Quad Cities.
00CM Revision 0, March 1989 has received approvals by all six onsi e review consiittees and the Ceco offsite review per the Technical Specifications.
Changes to the 00CM computer program required by this document are:in the process of being implemented now and should be fully available by '
November 1, 1989.
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' LICENSEE EVENT REPORTS (UNIT 2)
The following is a tabular summary of all Licensee Event Reports for 4
Byron Nuclear Power'Gtation, Unit Two, submitted during the reporting period, August 1 through August 31, 1989. This information is provided pursuant to the reportable occurrence reporting requirements as. set forth in 10CFR 50.73.
Occurrence Licenste Event Rgoort Number Date Title of Occurrence 1
[
NONE l'
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(0625M/0062M-14)
_ -