ML20235N380
| ML20235N380 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 06/30/1987 |
| From: | Querio R, Spitzer D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| BYRON-87-0735, BYRON-87-735, NUDOCS 8707200044 | |
| Download: ML20235N380 (14) | |
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1 BYRON NUCLEAR POWER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT
, COMMONWEALTH EDISON. COMPANY
'h, NRC DOCKET NO. 050-454 NRC DOCKET NO. 050-455 .
9 LICENSE NO. NPF-37 LICENSE NO. NPF-66 e
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Monthly Report for Byron Unit 1 I.
A. Summary of Operating Experience for Unit 1 The Unit began this reporting period 13 Mode 2 (Startup). On June 2 the Unit entered Mode 1 (Power Operation). On June 2 Mode 2 was 3 reentered to perform turbine balancing. On June 3 Mode 1 was again entered and on the same day the unit was synchronized to the grid.
On June 3 the turbine was taken off the grid. Turbine overspeed ,,
tests and balancing efforts continued throughout the day of June 3 -
and the main turbine was returned to the grid at 2103. Power ,
ascension commenced slowly on June 4 and 5 holding for fuel preconditioning considerations and xenon. On June 6 power was increased to 48%. Power was naintained at 48% through June 10 when an increase to 68% was commenced. June 11 66% RX power was achieved and was maintained until June 13, when an increase to 84% was commenced. On June 14, 85% RX power 'was achieved and power was maintained at this level until June 15 when an increase to 98% was commenced. On June 15 the unit was ramped back down to 83% due to a circulating water pump trip. On June 16 an increase to 98% was initiated. On June 17, 98% RX power was achieved and maintained until June: 24 when power was increased to 100% for split flow "
testing. On June 24 the testing was completed and RX power was brought back down to 98%. On the 24th the #2 governor valve closed dropping approximately 2% RX power. The load was further reduced to 89% for testing of the governor valve. On June 24 the governor valve was restored and on the 25th an increase up to 98% was commenced. On June 25t.h a load reduction was commenced and at 75% RX power the 1A j CW box was isolated in search of a leak. On June 26 a power increase was commenced back to 98%. On June 28th and 29th in the morning
'y. hours the unit was ramped down to 80% per the load dispatcher. On l
June 29, during the day, the unit load was increased back up to 98%
where it stayed through the end of this reporting period.
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(0625M/0062M) (3)
B. OPERATING DATA REPORT DOCKET NO.: 050-454' UNIT: Byron One DATE: 07/10/87
"'* COMPILED BY: D. J. Spitzer TELEPHONE: (815)234-5441 x2023 i OPERATING STATUS l'. Reporting Period: June 1987. Gross' Hours: 720 Currently Authorized Power Level (MWt): 3411 -
2.
Design Electrical' Rating: 1175 (MWe-gross) :
Design Electrical Rating: 1120 (MWe-net)
Max Dependable Capacity (MWe-net): NOT DETERMINED
'3. Power Level to Which Restricted (If Any):
- 4. Reasons for Restriction (If Any):
7 THIS MONTH YR TO DATE CUMULATIVE *
.5. . Report Period Hrs. 720 - 4343 16416'
- 6. Rx Critical Hours 720 1872.8 11586.2
- 7. Rx Reserve Shutdown Hours 0 0 0 l
- 8. Hours Generator on Line 668.6 1725.4 10679.1
- 9. Unit Reserve Shutdown Hours 0 0 0
- 10. Gross Thermal Energy (MWH) 1703699 3914679 30460513
- 11. Gross Elec. Energy (MWH) 565596 1288440 10212672
- 12. Net Elec. Energy (MWH) 526993 1150986 9559887 -
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' 13. Reactor Service Factor I. 100 43.12 70.6 w
- 14. Reactor Availability Factor 100 43.12 70.6 ss 15. Unit Service Factor - 92.9 39.7 65.1
'J 16. Unit Availability Factor 92.9 39.7 65.1
- 17. Unit Capacity Factor (MDC net) N/A N/A N/A
- 18. Unit Capacity Factor (DER net) 65.4 23.7 52.0
- 19. Unit Forced Outage Hrs. 0 0 777
- 20. Unit Forced Outage Rate 0 0 7.2
- 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): See Unit 2 (II.B.23)
- Note - The cumulative numbers do not reflect power generated prior to commercial service.
i (0625M/00E2M) (4) .
1
'C. AVERAGE DAILY UNIT POWER t.EVEL DOCKET NO.: 050-454 UNIT: Byron One
. DATE: 07/10/87
' "2 COMPILED BY: D. J. Spitzer TELEPHONE: (815)234-5441 i x2023
' MONTH: June,.1987 ,.
DAY AVERAGE DAILY POWER LEV 5L (MWe-Net) i
- 5. 210 MW- 19. 1068 MW -
- 6. 386 MW- 20. 1071 MW
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- 29. 1022 MW
- 30. 1072 MW INSTRUCTIONS On this form list the average daily unit power level in MWe-Net for each day L 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-
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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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E.- UNIQUE REPORTING REQUIREMENTS (UNIT 1)
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- 1. Safety / Relief valve operations for Unit One.
VALVES- NO & TYPE PLANT DESCRIPTION 4
DATE ACTUATED ACTUATION ' CONDITION OF EVENT ePe
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- 3. Indications of failed fuel. (Y/N)-
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F. LICENSEE EVENT REPORTS (UNIT 1) j The following is a tabular summary of all Licensee Event Reports for Byron
- l. Nuclear Power Station, Unit One, submitted during the reporting period, June 1 through June 30, 1987. This information is provided pursuant to the
. . reportable occurrence reporting requirements as set forth in 10CFR 50.73.
Occurrence Licensee Event Report Number. Date Title of_ Occurrence
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Reactor tr,ip in Mode'5 on steam 013-00 '
5-1-87 -
generator level.
87-014-00 5/15/87 Misplugged tube in the ID steam generator due to a contractor personnel error.
87-015-00 5/26/87 Auto start of Aux Feed pump during surveilla'nce testing. -
87-016-00 5/26/87 Containment Spray isolation '
- valves found closed.
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(0625M/0062M) (8)
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. II. Monthly R:; port fcr Byr:;n Unit 2 A. Summary cf Operating Exp3rignes for Unit 2 The Unit began this reporting period in Mode 1 (Power Operation) at 89% %eactor power. The unit remained at 89% until June 5 when a power decrease was commenced for a planned unit outage. On June 5 the unit entered Mode 3 (Hot Standby) and on June 6 the unit entered '
Mode 4 (Hot Shutdown). The unit remained in Mode 4 until June 15 when it entered Mode 3. The unit stayed in , Mode 3 until June 19 when Mode 2: -(Startup) was attained. On June 19 Mode 1 was entered and the unit was brought on line. On June 20 the uni,t'was increased in power - .
to 49%, where it stayed until June 22, when power was increased to I 71%. On June 23 the unit was taken to 90% where it stayed until June 28, when power was taken to 97%. The unit stayed at 97% power until June 29 when a Main Feedwater pump trip initiated a manual reactor trip taking the unit into Mode 3. On June 30 the unit entered Mode 1 and w'as synchronized to the grid. The unit ended this reporting period in Mode 1 at 35% reactor power. .
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(0625M/0062M) (9)
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. B. OPERATZNG DATA REPORT DOCKET MO.: 050-455 UNIT: 3yron Two DATE: 07/10/87 COMPILED BY: D. J. Spitzer
"' TELEPHONE: (815)234-5441 x2023 i
OPERATING STATUS Reporting Period: June 1987. Gross Hours: 120 !
1.
- 2. Currently Authorized Power Level (MWt): 3411 ,
Design Electrical Rating: 1175 (MWe-gross)
Design Electrical Rating: 1120 (MWe-net)
Max Dependable Capacity (MWe-net): NOT DETERMINED
- 3. Power L,evel to Which Restricted (If Any):
- 4. Reasons for Restrictio'n (If Any): The Unit is in Startup and Power Ascension -
Test Phase.
THIS MONTH YR TO DATE CUMULATIVE *
- 5. Report Period Hrs. 720 4144.4 4144.4
- 6. Rx Critical Hours ; 381.2 3324.7 3324.7
- 7. Rx Reserve Shutdown Hours 0 0 37.8
- 8. Hours Generator on Line 351 2608.2 2608.2
- 9. Unit Reserve Shutdown Hours 0 0 0
- 10. Gross Thermal Energy (MWH) 934938 5860105 5860105
- 11. Gross Elec. Energy (MWH) 316590 1905241 1905241 ,
- 12. Net Elec. Energy (MWH) 288146 1759800 1759800
- 13. Reactor Service Factor N/A N/A N/A 14.ReactorAvailabilityfactor N/A N/A N/A
- 15. Unit Service Factor N/A N/A N/A
- 16. Unit Availability Factor N/A N/A N/A
- 17. Unit Capacity Factor (MDC net) N/A N/A N/A
- 18. Unit Capacity Factor (DER net) N/A N/A N/A
- 19. Unit Forced Outage Hrs. N/A N/A N/A
- 20. Unit Forced Outage Rate N/A N/A N/A
- 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): (UNIT 2)
Forecast Achieved Initial Criticali.ty 01/07/87 01/09/87 Initial Electricity 02/05/87 02/06/87 Commercial Operation 05/31/07
- Note - The cumulative numbers do not reflect power generated prior to commercial service.
(0625M/0062M) (10)
. C. AVERAGE DAILY UNIT POWER LEVEL
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050-455.
DOCKET NO.
UNIT: Byron Two o DATE: 07/10/87 COMPILED BY: D. J. Spitzer..
IECEPHONE: (815)234-5441 x2023
- 4 MONTH
- June, 1987
' DAY AVERAGE DAILY POWER LEVEL C
.(MWe-Net)
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- 29. 401 MW
- 30. 39 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) (11)
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E. UNIQUE REPORTING REQUIREMENTS (UNIT 2)
- 1. Safety / Relief valve operations for Unit Two. -
-VALVES- NO & TYPE- PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT NONE
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- 2. Licensee generated changes to ODCM. (Y/N)
No ;
3.' Indications of failed fuel. (Y/N)'
No
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7 F. LICENSEE EVENT PSPORTS (UNIT 2)
The following is a tabular summary of all Licensee Event Reports for Byron Nuclear Power Station, Unit Two, submitted during the reporting period, ,
, June 1 through June 30, 1987. This' Information is provided pursuant to the l reportable occurrence reporting requirements as set forth in 10CER 50.73.
Occurrence ) '
Licensee Event Report Number Date Title of Occurrence ,,
87-007-00 05/04/87 Reactor Trip /AF Pump Start Due To Loss Of Instrument Bus 211.
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July 10, 1987 LTR: BYRON 87-0735 ~
File: 2.7.200
- Directd'r, Office of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Document Control Desk Gentlemen: _
t' Enclosed for your information is the Monthly Performance Report covering Byron Nuclear Power Station for the period June 1 through June 30, 1987.
Very truly yours, 1 i-t R. E. Querio Station Manager ~
Byron Nuclear Power Station N s
REQ /PHD/bg cc: A.B. Davis, NRC, Region III NRC Resident Inspector Byron Gary Wright, Ill. Dept. of Nuclear Safety D.P. Galle T. J. Maiman ,
D.L. Farrar Nuclear Puel Services, PWR Plant Support L. Anastasia, Station Nuclear Engineering INPO Records Center Thermal Group, Tech Staff Byron Station Nuclear Group, Tech Staff Byron Station L. 01shan - USNRC D. J Spitzer l 1
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