ML20214E323
ML20214E323 | |
Person / Time | |
---|---|
Site: | Byron |
Issue date: | 04/30/1987 |
From: | Ouerio R, Spitzer D COMMONWEALTH EDISON CO. |
To: | NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
References | |
BYRON-87-0571, BYRON-87-571, NUDOCS 8705220039 | |
Download: ML20214E323 (16) | |
Text
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BYRON NUCLEAR POWER STATION ,
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UNIT 1 AND UNIT'2 -
MONTHLY PERFORMANCE REPORT COMMONWEALTH EDISON' COMPANY' 4
2' NRC DOCKET NO.~ 050-454 NRC DOCKET NO. 050-455 4
LICENSE NO. NPF LICENSE NO. NPF-66 .
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- I. . Monthly R; port for Byron Unit 1-A. : Summary of Operating Experience for Unit 1 ,
- . The Unit began this reporting period in Mode 6 (Refueling). On 4/14/87 the. Unit entered Mode.5 (Cold Shutdown), and remained there through the end of this' reporting period.
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B. OPERATING DATA REPORT DOCKET NO.t 050-454 UNIT: Byron One l DATE: 05/10/87 COMPILED BY: D. J. Spitzer TELEPHONE: (815)234-5441 x2023 OPERATING STATUS
( :.
- 1. Reporting Period: April 1987. Grogs. Hours: 719
- 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 Level to Which Restricted (If Any):
- 4. Reasons for Restriction (If Any):
THIS MONTH YR TO DATE CUMULATIVE *
- 5. Report Period Hrs. ** 719 2879 14952
- 6. Rx Critical Hours 0 1057.8 10771.2
- 7. Rx Reserve Shutdown Hours 0 0 37.8
- 8. Hours Generator on Line 0 1056.8 10010.5
- 9. Unit Reserve Shutdown Hours 0 0 0
- 10. Gross Thermal Energy (MWH) 0 2210980 28756814
- 11. Gross Elec. Energy (MWH) 0 722844 9647076
- 12. Net Elec. Ensegy (MWH) - 9114 639960 9048861
- 13. Reactor Service Factor 0 36.7 72
- 14. Reactor Availability Factor 0 36.7 72.3
- 15. Unit Service Factor -
0 36.7 67
- 16. Unit Availability Factor 0 36.7 67
- 17. Unit Capacity Factor (MDC net) N/A N/A N/A
- 18. Unit Capacity Factor (DER net) 0 19.8 54
- 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: 05/24/87
- 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 comercial service.
Total reflects loss of one hour due to the time change.
(0625M/0062M) (4) i
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C. ~ AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: 050-454 UNIT: Byron One DATE: 05/10/87-.
COMPILED BY: D. J. Spitzer TELEPHONE: -(815)234-5441 x2023 MONTH: April, 1987 DAY- AVERAGE DAILY POWER LEVEL (MWe-Net)
- 29. -0 MW
- 30. 0 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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acooococoooococcococococco R: port Period April,.1987 UNIT SHUTDOWNS / REDUCTIONS *~ BYRON *~
-(UNIT 1) **************************- - -
7 No. Date -Type Hours Reason Method LER Number System Component Cause & Corrective Action to Prevent Recurrence 1 02/14/87 S 719 C' 4 Continuation of' scheduled. refueling outage. li 1
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-o Summary' . * ,
.cooseeeeeeemene l
!*ys TYPE Reason- Method System & Component o..
I F-Farced A-Equip Failure F-Admin -l-Manual Exhibit F & H S-Sched B-Maint or Test G-Oper Error Manual Scram . Instructions for
- j. C-Refueling H-Other' ,
3-Auto Scram Preparation'of D-Regulatory Restriction 4-Continued .' Data Entry Sheet E-Operator Training 5-Reduced Load. ' Licensee. Event Report .
& License Examination 9-Other iLER), File '(NUREG-0161)
(0625M/0062M) l (6_)
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E. ' UNIQUE REPORTING REQUIREMENTS (' UNIT 1)
- 1. Safety / Relief valve operations'for Unit One.
VALVES- NO & TYPE PLANT DESCRIPTION-DATE ACTUATED ACTUATION CONDITION OF EVENT None
- 2. Licensee generated changes to ODCM. (Y/N)
No -
.3. Indications of failed fuel. (Y/N)
No. (Fuel reconstituted and core reloaded)
(0625M/0062M) (7)
F. ' 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, April 1.through April 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'# 3.
87-005-00 3-10-87 Failure to properly apply T.COAR on Continuous Fire Watch.
87-006-00 3/11/87 Fire Protection Surveillance Internal missed due_to i personnel error.
87-007-00 3/16/87 Fire Watch delayed by 20 min. .
due to personnel. error.
, 87-008-00 3/24/87 Control Room Ventilation Auto Start..
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! .iII. Monthly Report fcr Byron Unit 2 A. Summary cf Oper ting.Expericnca far Unit.2 During this reporting period, Byron Station's Unit 2 continued ~in the ~
Startup Testing Program, and achieved significant objectives toward' Comunercial Operations.
The Unit 2 testing' activities'lwere~ highlighted by the Rompletion, on '
~#
-4/24/87, of the 90% Testing Sequence Document.
The' Unit began this reporting period ~in Mode 4 (Hot Shutdown)
. i On 4/7/87, after a 9 day scheduled maintenance outage,' the Unit entered Mode 3 (Hot Standby). The reactor was taken critical and
' ' returned to Mode 1.(Power Operation)Lon 4/9/87.
.The plant was-declared "In Service" on 4/11/87. ,
On 4/13/87 the Unit was S'87% power. - The Unit operated at approximately 89% power until 4/27/87 when a reactor trip occurred ,
due to presrurizer-pressure channel #456 spiking low with channel.
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- 455 in the tripped condition for instrument maintenance surveillance testing. The unit was returned to 88% power by 4/30/87 and remained there for the rest of this' reporting period.
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- ; B. OPERATING DATA REPORT DOCKET NO.: 050-455 UNIT: Byron Two DATE: 05/10/87 COMPILED BY: D. J. Spitzer TELEPHONE: (815)234-5441 x2023
- OPERATING STATUS E. .-
- 1. Reporting Period: April 1987. Gross Hours: 719
- 2. Currently Authorized Power Level (MNt): 3411 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): The Unit is in startup and Power Ascension Test Phase.
THIS MONTH YR TO DATE CUMULATIVE *
- 5. Report Period Hrs. ** 719 2680'.4 2680.4
- 6. Rx Critical Hours 499.9 2232.9 2232.9
- 7. Rx Reserve Shutdown Hours 0 0 0
- 8. Hours Generator on Line 475.4 1551'.8 1551.8
- 9. Unit Reserve Shutdown Hours 0 0 0-
, 10. Gross Thermal Energy (MWH) 1246567 3025752 3025752
- 11. Gross Elec. Energy (MWH) 415160 943755. 943755
- 12. Net Elec. Energy (MWH) 388995 869295 869295 t 13. Reactor Service Factor N/A N/A N/A
- 14. Reactor Availability Factor N/A N/A N/A
- 15. Unit Service Factor N/A N/A N/A
- 16. Unit Availability Factor N/A1 _
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 1
- 21. Shutdowns Scheduled Over Next 6 Months: 6/02/8"'
- 22. If Shutdown at End of Report Period, Estimated Date of Startup:
- 23. Units in Test Status (Prior to Comercial Operation): (UNIT 2)
Forecast Achieved !
Initial Criticality 01/07/87 01/09/87 -l Initial Electricity 02/05/87 02/06/87 Commercial Operation 05/31/87
- Note - The cumulative numbe.r.s do not reflect power generated prior to commercial service.
- Total reflect's the loss of one hour due to the time change.
(0625M/0062M) (10)
,' . . C. ' AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. . 050-455.
UNIT . Byron Two DATE: 05/10/87 COMPILED BY: D. J. Spitzer TELEPHONE: -(815)234-5441 x2023 f .. MONTH: April, 1987
- g. _
DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
~
- 29. 5 MW
- 30. 603 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) e
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R: port Pariod' April, 1987 UNIT SHUTDOWNS / REDUCTIONS *-' BYRON '*
(UNIT 2) **************************
No. Date Type Hours Reason Method LER Number System Component Cause & Corrective Action to Prevent Recurrence (12) 03/31/87 S A 4 Continuation from March.
(13)' 04/01/87 S 172 B 4 Planned maintenance outage. Previously scheduled for.
-04/01/87.
(14) 04/27/87 F 43.9 A 3 Reactor trip due_to pressurizer pressure Channel 456 failing low while Channel 455 was in the tripped condition for surveillance testing. Pressure transmitter.456_has been replaced.
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- Summary
- ococeeeeeeeeeen TYPE Reason- -
Method System & Component F-Ferced A-Equip Failure _'F-Admin 1-Manual Exhibit F & H ?
S-Sched B-Maint or Test G-Oper Error 2-Manual' Scram ' Instructions for-C-Refueling H-Other 3-Auto Scram Preparation of D-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event Report
& License Examination 9-Other_ (LER) File (NUREG-0161)
'(0625M/0062M) ( l_2 )
r E. UNIQUE REPORTING REQUIREMENTS (UNIT 2) li _ Safety / Relief valve operations for Unit Two.
VALVES NO & TYPE PLANT ' DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT NONE
- 2. Licensee generated changes to ODCM. (Y/N)
No
- 3. Indications of failed fuel. (Y/N) 9 No i
a (0625M/0062M)-(13) 2
F.' LICENSEE EVENT REPORTS (UNIT 2) .,-
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The following is a tabular' summary of all Licensee Event Reports for Byron.
Nuclear Power Station, Untt Two, submitted during the reporting period,
' April 1 through April 30, 1987. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.
~
L-. Occurrence -
Licensee hent Report Number Date Title of Occurrence -s F
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87-005-00 03/31/87- Reactor Trip on Generator.--
Motoring. ;- y I
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Attached is an amend:d copy cf March NBC.Grcybook Opertting ctetus.
- Line 12 han be:n changed to r:flect the carecct net Elcc. En3rgy. Tha unit current month number ir negative because of the' unit's Aux power
- i usage through the month. \This will result in a drop in Year to date and cumulative numbers.
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Line 18 numbers are changed as the net electrical: nun >bers are used.in this pi specific calculation. ,
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B. OPERATING DATA REPORT' .
DOCKET NO.:- 050-454~
UNIT: Byron One DATE: 04/10/87 COMPILED BY: D.-J. Spitzer TELEPHONE: .(815)234-5441 x2023 3,'.
OPERATING STATUS
- 1. Reporting Period: March 1987. Gross Hours: 744
- 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 Level to Which Restricted (If Any): '.
- 4. Reasons for Restriction (If Any):
THIS MONTH YR TO DATE CUMULATIVE *~
- 5. Report Period Hrs. 744 2160 14233
- 6. Rx Critical Hours 0 1057.8 10771.2
- 7. Rx Reserve Shutdown Hours 0 0 37.8
- 8. Bours Generator on Line 0 1056.8 10010.5
- 9. Unit Reserve Shutdown Hours 0 0 0
- 10. Gross Thermal Energy (MWH)- 0 2210980 28756814
- 11. Gross Elec. Energy (MWH) 0 722844 9647076
- 12. Net Elec. Energy (MWH) -9177 649074 9057975
- 13. Reactor Service Factor 0 49.0 75.7
- 14. Reactor Availability Factor 0 49.0 , 75.9
- 15. Unit Service Factor 0 48.9 70.3
- 16. Unit Availability Factor 0 48,9 70.3
- 17. Unit Capacity Factor (MDC net) N/A N/A N/A
- 18. Unit Capacity Factor (DER net) 0 26.8 56.8
- 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: 4/29/87
- 23. Units =in Test Status (Prior to Commercial Operation): See Unit 2 (II.B.23) i
- Note - The cumulative numbers do not reflect power generated _ prior to commercial service.
(0625M/0062M) (16) e
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- May 10, 1987
~
LTR: BYRON 87-0571 -
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. )
~ Gent 1emen:
Enclosed for your information is .the Monthly Performance . Report covering Byron ~
Nuclear Power Station.for-the period April 1 through April 30, 1987. ,
Very truly yours,
/
/ .
R. E. Querio Station Manager Byron Nuclear Power Station -
REQ /PHD/bb 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 Fuel 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. Olshan - USNRC D. J. Spitzer l
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