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Category:MONTHLY OPERATING ANALYSIS REPORT
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[Table view] Category:TEXT-SAFETY REPORT
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Comm Ed Byron Nuclear Power Station,Unit 1 Cycle 9 Startup Rept ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20202F6181998-12-31031 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function ML20206B4001998-12-31031 December 1998 Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations ML20199E6371998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Byron Station,Units 1 & 2.With ML20202F6021998-12-31031 December 1998 Cycle 9 COLR in ITS Format & W(Z) Function ML20196K6731998-12-31031 December 1998 10CFR50.59 Summary Rept for 1998 ML20207H7731998-11-30030 November 1998 Rev 0 to WCAP-15125, Evaluation of Pressurized Thermal Shock for Byron,Unit 1 ML20207H8011998-11-30030 November 1998 Rev 0 to WCAP-15124, Byron Unit 1 Heatup & Cooldown Limit Curves for Normal Operation ML20198D1501998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195F8321998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Byron Nuclear Power Station,Units 1 & 2.With 05000454/LER-1998-018, Corrected LER 98-018-00:on 980912,inoperable Unit 1 DG Was Noted.Caused by Low Lube Oil Pressure Condition.Immediately Entered Into Lcoar for AC Sources TS 3.8.1.1,Action a1998-10-0909 October 1998 Corrected LER 98-018-00:on 980912,inoperable Unit 1 DG Was Noted.Caused by Low Lube Oil Pressure Condition.Immediately Entered Into Lcoar for AC Sources TS 3.8.1.1,Action a ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20154L5501998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20197C9051998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20151Z9651998-08-31031 August 1998 Revised MOR for Aug 1998 for Byron Nuclear Power Station. Rept Now Includes Page 9 Which Was Omitted from Previously Issued Rept ML20238F6551998-08-28028 August 1998 SE Authorizing Licensee Request for Relief NR-20,Rev 1 & NR-25,Rev 0 Re Relief from Examination Requirement of Applicable ASME BPV Code,Section XI for First ISI Interval Exams ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237B3361998-08-14014 August 1998 B2R07 ISI Summary Rept,Spring 1998 Outage, 961005-980518 ML20237B4841998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Byron Nuclear Power Station Units 1 & 2 1999-09-30
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I BYRON NUCLEAR POWER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT COMMONWEALTH EDISDN COMPANY
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NRC DOCKET NO. 050-454 NRC DOCKET NO. 050-455 LICENSE NO. NPF-37 LICENSE NO. NPF-60 l
8701210464 861231 l PDR ADOCK 05000454
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- y' I. _ Monthly Report for Byron Unit 1
'A. Summary'of Operating Experience for' Unit 1- .
l The Unit was at power for the entire reporting period. There were no' reactor trips or~ forced reductions of power. The unit began ,
"coastdown", starting power reduction, on December 23, 1986 in i preparatior. for an anticipated February 1987 refueling outage., ,
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B. OPERATING DATA REPORT DOCKET NO.: 050-454 UNIT: Byron One DATE: 01/10/87 COMPILED BY: D. J. Spitzer TELEPHONE: (815)234-5441 x2023 ,
OPERATING STATUS
- l. Reporting Period: December 1986. Gross Hours: 744 -
- 2. Currently Authorized Power Level (MWt): 3411 Design Electrical Rating: 1175 (MWe-gross) l Design Electrical Rating: 1120 (MWe-net) .
Max Dependable Capacity (MWe-net): NOT DETERMINED
- 3. Power Level to Which Restricted (If Any): 1105 (MWe-gross) . .
- 4. Reasons for Restriction (If Any): Reduction of Hot Leg Temperature for Primary Water Stress Corrosion Cracking Concerns.
THIS MONTH 'IR TO DATE CUMULATIVE *
- 5. Report Period Hrs. 744 8760 11329
- 6. Rx Critical Hours 744 7823.9 9813.4
- 7. Rx Reserve Shutdown Hours ; O 21.7 37.8
- 8. Hours Generator on Line 744 7761.3 8953.7
- 9. Unit Reserve Shutdown Hours '
O O O
',10. Gross Thermal Energy (MWH) ' 2301166 23206642 26545834
- 11. Gross Elec. Energy (MWH) 769763 7835643 8924232
- 12. Net Elec. Energy (MWH) 729497 7396003 8408901
- 13. Reactor Service Factor 100 89.3 86.6
- 14. Reactor Availability Factor 100 89.6 87.0
- 15. Unit Service Factor 10J 88.6 79.0
- 16. Unit Availability Factor 100 88.6 79.0 l 17. Unit Capacity Factor (MDC net) N/A N/A N/A
- 18. Unit Capacity Factor (DER net) 87.5 75.4 66.3
- 19. Unit Forced Outage Hrs. 0 674.4 777
- 20. Unit Forced Outage Rate 0 8.0 8.0 l
- 11. Shutdowns Scheduled Over Next 6 Months: Scl led refueling outage to start 2/3 soul
- 22. If Shutdown.at End of Report Period, Ectimated Date of Startup: N/A
- 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.
(0625M/0062M)
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C. AVERAGE DAILY UNIT POWER LEVEL -
DOCKET NO.: 050-454 UNIT: Byron One DATE: 01/10/87 COMPILED BY: D. J. Spitzer TELEP110NE: (815)234-5441 x2023
)
MONTH: December, 1986 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
- 1. 1022 MW 17. 1009 MW i
- 2. 1090 MW 18. 936 MW
)
- 3. 1020 MW 19. 934 MW
- 4. 1020 MW 20. 1012 MW
- 5. 1018 MW 21. 1012 MW
- 6. 1015 MW 22. 1011 MW
- 7. 1015 MW 23. 997 MW
- 8. 1015 MW 24. 974 MW
- 9. 1015 MW 25. '
941 MW
- 10. 998 MW 26. 932 MW
- 11. '
998 MW 27. 932 MW
- 12. 1000 MW 28. 920 MW 13, 992 MW 29, 910 MW
- 14. 999 MW 30, 879 MW
- 15. 1005 MW 31. 825 MW
- 16. 1001 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.
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(0625M/0062M) ggg l
i
RIport Period December, 1986 UNIT SHUTDOWNS / REDUCTIONS' BYRON (UNIT 1) **************************
No. Date Type Hours Reason Method LER Number System Component Cause & Corrective Action to Prevent Recurrence No..s I
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- There were no unit shutdowns /re'duclions during the month of December.
Reason Method System & Component TYPE F-Forced 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 f (LER) File (NUREG-0161)
& License Examination 9-Other (0625M/0062M) ,
+ .
E. UNIQUE REPORTING REQUIREMENTS (UNIT 1) e
- 1. Safety / Relief valre operations for Unit One. .
VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT None 4
- 2. Licensee generated changes to ODCM. (Y/N)
No
- 3. Indications of failed fuel. (Y/N)
Yes. Iodine spikes during power changes indicate failed fuel. Judging from the extent of the spikes it is estimated that there are four to eight failed rodlets.
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- (0625M/0062M)
F. LICENSEE EVENT REPORTS (UNIT 11 The following is a tabular summary of all Licensee Event Reports for Byron -
Nuclear Power Station, Unit One, submitted during the reporting period, Decestber 1 through December 31, 1986. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.
Licensee Event Report Number Date Title of Occurrence 86-031-00 12-19-86 Failure to perfor:n post maintenance testing i
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(0625M/0062M)
II. Monthly R: port for. Byron Unit 2
- h. Summary ~of Operating Experience for Unit 2 .
Byron Unit 2 started this reporting period in Mode 5.(cold shutdown). On December 11, 1986, the unit entered Mode 4 (hot shutdown). On December 16, 1986, the unit entered Mode 3 (hot
,- standby). On December 18, 1986, the unit returned to Mode 4 due to an accummulator pressure boundary leak. On December 19, 1986, the
~
8 unit re-entered Mode 3 and remained in Mode 3 through the end of this reporting period.
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'B. OPERATING CATA REPORT DOCKET NO.: 050-455 UNIT: Byron Two DATE: 01/10/87 COMPILED BY: D. J. Spitzer TELEPHONE: (815)234-5441 x2023 OPERATING STATUS ,
i
- 1. Reporting Period: December 1986. Gross Hours: 744
- 2. Currently Authorized Power Level (MWt): 170 Max Depend Capacity 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): 58.75 (MWe-gross)
- 4. Reasons for' Restriction dIf Any): Condition of Facility Operating License NPF-60.
THIS MONTH fR TO DATE CUMULATIVE *
- 5. Report Period Hrs. 744 1464 1464
- 6. Rx Critical Hours 0 0 0
- 7. .Rx Reserve Shutdown Hours 0 0 0
- 8. Hours Generator.on Line 0 0 0
- 9. Unit Reserve Shutdown Hours 0 0 0
- 10. Gross Thermal Energy (MWH) 0 0 0
11. Gross Elec. Energy (MWH) 0 0 0
- 12. Net Elec. Energy (MWH) 0 0 0
- 13. Reactor Service Factor 0 0 0
- 14. Reactor Availability Factor O O O
- 15. Unit Service Factor -
O O O
- 16. Unit Availability Factor 0 0 0
- 17. Unit Capacity Factor (MDC net) -
N/A N/A N/A
- 18. Unit Capacity Factor (DER net) 0 0 0
- 19. Unit Forced Outage Hrs. 0 0 0
- 20. Unit Forced Outage Rate 0 0 0
- 21. Shutdowns Scheduled Over Next 6 Months: N/A
> 22. If Shutdown at End of Report Period, Estimated Date of Startup: N/A
- 23. Units in Test Status (Prior to Commercial Operation): (UNIT 2)
Forecast Achieved i Initial Criticality 01/08/87 01/09/87 Initial Electricity Commercial Operation
- Note - The cumulative numbers do not reflect power generated prior to commercial service.
(0625M/0062M)
. +, ,
C. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: 050-455 UNIT: Byron Two -
DATE: 01/10/87 COMPILED BY: 'D. J. Spitzer TELEPHONE: (815)234-5441 x2023 MONTH: December, 1986 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
- 1. O MW 17. O MW
- 2. O MW 18. O MW
- 3. O MW 19. _ 0 MW
- 4. O MW 20. O MW
- 5. _ 0 MW 21. O MW
- 6. O MW 22. O MW
- 7. O MW 23. O MW
- 8. O MW 24. O MW
- 9. O MW 25. O MW '
- 10. O MW 26. O MW
- 11. O MW
- 27. O MW
' i'2 . O MW 28. O MW
- 13. O MW 29. O MW
- 14. O MW 33. O MW
- 15. O MW 31. O MW
- 16. O 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)
R port Period December, 1986 UNIT SHUTDOWNS / REDUCTIONS
(UNIT 2) **************************
No. Date Type Hours Reason Method LER Number System Component Cause & Corrective Action to Prevent Recurrence N/A 1
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.l emee***********
TYPE Reason Method System & Component F-Forced 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) ,, ,
E. UNIQUE REPORTING REQUIREMENTS-(UNIT 2)-
- 1. Safety / Relief valve operations for Unit Two.
VALVES NO & TYPE PLANI DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT None
- 2. License,e generated changes to ODCM. (Y/N)
No
- 3. Indicat' ions of failed fuel. (Y/N)
No
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. =. - ._ - _. -_ - .. _ - . - . -
.-- -o-F. LICENSEE EVENT REPORTS (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, December 1 thecugh December 31, 1986. This information is provided pursuant-1 to the reportable occurrence reporting requirements as set forth in 10CFR
~ 50.73. .,
i Licensee Event Report Number Date Title of Occurrence.
1 86-001-00 12/19/86 Both trains of Component Cooling inoperable due to a personnel error in a relief valve setting.
86-002-00 12/18/86 Rod position indication mismatch requiring manual reactor trip due to failed circuit card.
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(0625M/0062M) t 9
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January 10, 1987 LTR: BYRON 87-0042 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 December 1 through December 31, 1986.
Douglas J. Spitzer (extens'_ ion 2023) has replaced Paul H. Dandrea as preparer of this report for the NRC Greybook.
~~
Very truly yours,
/ /,
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R. E. Querio Station Manager -
Byron Nuclear Power Station REQ /PHD/bb l
l cc: J.G. Keppler, NRC, Region III
( NRC Resident Inspector Byron Gary Wright, Ill. Dept. of Nuclear Safety l D.P. Galle T. J. Maiman D.L. Farrar
( Nuclear Fuel Services, PWR Plant Support i
, L. Anastasia, Station Nuclear Engineering
(
INPO Records Center ,
Thermal Group, Tech Staff Byron Station Nuclear Group, Tech Gtaff Byron Station L. Olshan - USNRC D. J. Spitzer (0625M/0062M)
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