ML20127E452

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Dec 1992 for Byron Nuclear Power Station,Units 1 & 2
ML20127E452
Person / Time
Site: Byron  Constellation icon.png
Issue date: 12/31/1992
From: Ehle D, Schwartz G
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-93-0018, BYRON-93-18, NUDOCS 9301190317
Download: ML20127E452 (14)


Text

. .. _ __ _ _ .

'C

. C:mmonwsalth Edis:n O Byron Ni, clear Station =

C 4450 North Gerrnan Church Road

. Byron, Illinois 61010 January 11, 1993 LTR BYRON 93-0018 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, 1992.

Sincerely,

? /?

?!A G. K. Schwartz /

\

Station Manager C )

Byron Nuclear Power Station RP/DE/lh cc: A.B. Davis, NRC, Region III NRC Resident Inspector Byron Ill. Dept. of Nuclear Safety M. J. Wallace/E. D. Eenigenburg Nuclear Licensing Manager Nuclear Fuel Services,.PWR Plant Support D. R. Eggett, Station; Nuclear Engineering INPO Records Center-

.J. B. Hickman - USNRC F. Yost - Utility Data Institute, Inc.

l 190137 -

9301190317 DR- 921231 fk 'I ADOCK 05000434 1 j 1 PDR- 9 \

~

. , . 'j 4 7 9  %.

=!

i i

?

BYRON NUCLEAR POWER STATION UNIT 1 AND UNIT 2 MONTHLY PERTORMANCE REPORT COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-454 NRC DOCKET NO,! 050-455 LICENSE NO, NPF-37

. LICENSE NO NPF-66 S

(3767M/VS/1):

.- . . - - . .,_.~.-.~ .. . . . _ . . , . , . . . . . . . . . . . . = . . . . ~ , . . . - - .~- . _ _ .

. , . j

. +. -l l

~

I ., M9athl%.Emput_ lor ByIgn_UMLT 'l for_the' month of December-1992 h.i _SULVjf AIy. of Op_eratinglxperience for Unit 1

~

The Unit began this reporting period in. Mode =1 (Power Operations). The:

power level varied due to load following requirements.

C f

4 A

r i

J

.( 37 67M/ VS / 2 ) -

  • .-e , , , , e , , - - . . - . w -49 e yq - < p

D,_ OPERATIRG DATAEPDET DOCKET NO.:- 050-454 UNIT: Byron One DATE: 11/11/93 COMPILED BYt D. Ehle TELEPHONE: (815)234-5441 x2263 OPERATING STATUS

1. Reporting Period: December, 1992. 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): None
4. Reasons for Restriction (If Any): N/A THIS MONTH YR TO DATE CUMULATIVE *
5. Report Period Hrs. 744 8784 63,937
6. Rx Critical Hours 744 8731.4 53,658.3
7. Rx Reserve Shutdown llours 0 0 38
8. Ilours Generator on Line 744 8723.1 53,027
9. Unit Reserve Shutdown Hours 0 0 0
  • 10. Gross Thermal Energy (MWH) 2,310,799 27,652,711 160,456,291
11. Gross Elec. Energy (MWH) 751,701 9,328,339 54,101,588
12. Net Elec. Energy (MWH) 751,910 8,986,369 51,205,866 _

100

13. Reacter Service Factor 99.40 83.92
14. Reactor Availability Factor 100 99.40 83.98
15. Unit Service Factor 100 99.31 82.94
16. Unit Availability Factor 100 99.31 82.94
17. Unit Cepacity Factor (MDC not) 91.46 -92.58 72.48
18. Unit Capacity Factor (DER net) 90.23 91.34 71.51
19. Unit Forced Outage Hrs. 0 60.9 1,403.4
20. Unit Forced Outage Rate 0 .69 2.58
21. Shutdowns Scheduled Over Next 6 Months: Refueling Outage BIR05 2/5/93
22. If Shutdown at End of Report Period, Estimated Date of Startup: 4/10/93
23. Units in Test Status (Prior to Commercial Operation): None
  • Note - The cumulative numbers do not reflect power generated prior to commercial service.

(3767M/VS/3)

s

.C.._.AYERAGLDAILLUNILPDMER LEYEL DOCKET NO.: 050-454-UNIT. Byron One.

DATE: 01/11/93-COMPILED BY D. Ehle TELEPHONE: ( B15 ) 2 34 -5441 :.

x2263 I

MONTil: December, 1993 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

1. 10JLIM 16. 494 WA
2. 1033 3 1 17. 563 MW.

l

3. _ _ . 196LMW 18. 1087 MW _
4. 1Q83 MW 19. 1103 MW
5. 1102_MW 20, 1103 MW
6. _1Q92 MW __
21. 1101 MW
7. 103LMW 22. 1102 MW
8. 11DLMW 23 1102 MW-
9. 1191 MW 24, 1098 MW-
10. 1093 MW 25, 1097 MW
11. _ _ _ . . 19.9LMW 26. .1102 MW
12. _1012_MW _ 27. 1098 rd-
13. _ _ _lD.5LMW - 28. 1097 MW
14. . __ _ l.011 MW 29.- 1053 MW

,. 15. 31LMW 30. 765 MW 4

31. 771 MW-

. INSTRUCTIONS Ion ~this form list.the average daily unit power level'.in NWe-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 ret electrical rating of-the unit there:

.may be' occasions'when the daily average-power. level exceeds the 100%-line--

-(or the restricted power level;11ne.) .In such cases the average daily-unit power output-sheet should be-footnoted to explain the apparent anomaly.

(3767M/VS/4) ,

k 9

~n .

Report Period December, 1992 . UNIT SH'TIDOWNS/ REDUCTIONS

  • BYRON *

(UNIT 1) **************************

L No. Date '"

m a_ Honts Reason Method' LER Number System Component CAuse & Corrective Action to Prevent Recurrence ll_ 12/15 P' 16 A 5 FW During a surveillence the 1FWOO9D valve would not return to its full open position. Valve was closed and NWR written.

12 12/15. T 41' H 5 Unit experienced Chemistry problems due to load reduction for valve problem.

13- 12/29 F 18 A 5 ED The IC HD pump bearing temperature exceeded 200*F causing pump to be secured and load to be reduced.

-e*ee***********

  • Summary
  • TYPE Reason Method System & Comnonent 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) r (3767M/VS/5).

, . . - - ~ _ . . . . - - . ~ .. . _

- L.__.UH10UE . REPORT 1HQJEQUIREliUNIS_.IllRIT 11 far the month of DECE11 DER .1992 4

1. Safety / Relief' valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION l

~

DATE ACTUATED ACTUAILON CORDITIDE Of_EYENT -j i

None

2. Licensee generated changes to ODCM.

NONE

3. Indications of failed fuel.

Fuel Relicbility Indicator:

Yes FRI: 5.7E-4 pC1/cc

4. 10CFR50.46 Reporting Requirements: Peak Clad temperature (PCT)-changes resulting from change or errors to the ECCS evaluation model.

Current licensing basis PCT plus margin allocation (*F) i Large_BraaLLOCA Small_Irmak LOCA 2051.3 -1681.6 Explain differences from previous report:

The small break LOCA value changed to account for.. incorrect safety injection data for the centrifugal charging pump (166.5*) and uncertainty of the pressurizer-pressure initial condition during EGC operation (5*)

.per December 22, 1992 letter from Marcia A. Jackson to Dr. Thomas E.

Murley.

l-l 1-l-

l.

Il i.

-~

[(3767M/VS/6) 1

L_klCENSEE_lVIDI_PlEORTS (UNIT 11-The.following is a tabular. summary of all Licensee Event Reports:for Ilyron. Nuclear Power Station,: Unit One, submitted during the reporting period,_

December 1 through December 31, 1992. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CTR 50.73.

Occurrence Licensee _EvenLlepotLHumher Date Title of occutreme NONE l

(3767M/vs/7)

. _ . . . . . - . . . ~ , - - . , . . . , . ..-. .- -+ ... - . ~ . - , . - . . - . -, . . ~- ;_-.

l a

II. MonthiydersttJsIJyr.c2LjJlifT 2 for the month of December 1992 j Au.,...lWINEAIY 21_QPCIAtingJ1pe r i e n c e for Unit 2-The Unit began this reporting period in Mode'l (Power Operations). . .;

The power level varied due to load following requirements.

i

+

r

.f 4--.

( 3 7 67H/VS / 8 )

-I

L.__.DPIRAT111G_ RATA _EILTRT DOCKET NO.:' 050-455-UNIT: Byron Two DATE: 01/11/93 ,

COMPILED BY: D. Ehle TELEPHONE: (815)234-5441 x2263.

OPERATING STATUS

1. Reporting Periodt December, 1992. Gross Hourst 744
2. Currently Authorized Power Level 3411 (MWL)

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. Reacons for Restriction (If Any):

THIS MOKIH YR TO DATE CUMULATIVE *

5. Report Period Hrs. 744 8784 47,041 1
6. Rx Critical Hours 744- 7101.5. 40,335.6
7. Rx Reserve Shutdown Hours 0 0 0-
8. Hours Generator on Line 744 7030.2 39,805.3
9. Unit Reserve Shutdown Hours 0 0 0
10. Gross Thermal Energy (MWH) 2,286,284 21,231,737 112,750,457
11. Gross Elec. Energy (MWH) 783,116 7,259,169. 38,215,938
12. Net Elec. Energy (MWH) 759,245 6,983,751 36,160,759
13. Recctor Service Factor -100 80.85 85.75,
14. Reactor Availability Factor 100 80.85 85.75
15. Unit Service Factor 100 80.03- 84.62
16. Unit Availability Factor 100 80.03 184.62.
17. Unit Capacity Factor (MDC net) 92.35 71.95 69.57
18. Unit Capacity Factor (DER net) 91.12 70.99 68.63.

l 19. Unit Forced-Outage Hrs. 0 88.1- 1244 I

20. Unit Forced Outage Rate 0 1.24 3.03
21. Shutdowns-Scheduled Over Next 6 Monthst NONE
22. If Shutdown at End of Report Period, Estimated Date of Startup NONE I
23. Units in Test-Status-(Prior to Commercial Operation): None I
  • Note -'The cumulative numbers do not reflect' power

. generated prior to commercial service.

1.

s3767M/VS/9)

- Cm__AYERAGEL AILX_. UNIT _lMR_ LEVEL DOCKET NO.: 050-455 UNIT: Byron.Two DATE: 11/11/93:

COMPILED BY: D. Ehle TELEP110NE: (815)234-5441 x2263 MONTil: December, 1992 DAY AVERAGE DAILY POWER LEVEL

( MWe -Ne t. )

1. 1112_.lN 16. ,__.JQ92 MW
2. 1052 MW 17. 110E MW
3. 1098 MW 18. 1123 MW
4. 1097 MW 19. 915 MW
5. 964_MW 20. 1039 MW
6. 1119 MW '21. 1073 MW

'7. ll2hJW 22, 1080.MW .c 8, 1130_.MW 23. 1091 MW 3

9. 1113 MW 24. 10.01 MW
10. 1111JW 25. 746 MW
11. Ill5.JN 26. 112Q_1M
12. 1107 MW 27, 4 6D_.NW
13. 1035 MW- 28. 940 MW
14. 1031 MW 29, 1093 MW-
15. 1297 MW 30, 1051 MW .

31, 1040 MU INSTRUCTIONS -

On this form list tho' average daily unit power level:in MWo-Het 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 1004 line (or the restricted power level line.) In such cases the average. daily-unit:

~

' power _ output shtet should-be' footnoted to' explain the: apparent anomaly.

~(3767M/VS/10)

__=

i

  • BYECN
  • Report Period December, 1992 UNIT SHUTDOWNS /REDUCTICNS (UNIT 2)

Date Type Hours freasoE Method LER Number SyMfD CREp2 M Ca3;se & Corrective Actinp to Prevent Recurrence No.

F 5 Reduced load per SPSO.

6 12/25/92 Reduced load due to stability trip breakers out of 7 12/27/92 H 5 service.

  • o*************
  • Summary
  • o**************

Method System & Component j TYPE Rease l 1-Manual Exhibit F & H F-Forced A-Equip Failure F-Admin B-Maint or Test G-Oper Error 2-Manual Scram Instructions for S-Sched Preparation of C-Refueling B-Other 3-Auto Scram l 4-Continued Data Entry Sheet D-Regulatory Restriction Licensee Event Report E-Operator Tra.ning 5-Reduced Load

& License Examination 9-Other (LER) File (NUREG-0161)

(3767M/VS/11)

...s . .

.g.- * -

L_VH1DVfL.BIEDETING_R50VlPIMENTS (UNIT 2) Lor._themonth of Decesher idO2- l 1
1. Safety / Relief valve-operations for Unit Two. ,

i VALVES NO & TYPE PLANT DESCRIPTION PATE ACTUATED AC1VAIION CONDITIQH OF EVENT None

2. Licensee generated changes to ODCM. ,

NONE

3. Indications of failed fuel.

No. Fuel Reliability Indicator: FRI r 7.0E-5 pCi/CC

4. 10CFR50.46 Reporting Requirements: Peak Clad temperature (PCT) changes resulting from changes or errors to the ECCS evaluations model.

P Current licensing basis PCT-plus major allocations ('F)

Large._EtcaA_LQCA- Small Break _LQCA-2064.1 1681.6 Explain differences from previous report The small break LOCA value changed.to account for incorrect safety injection data for-the centrifugal charging pump (166.5*) and uncertainty of the_ '

pressurizer pressure initial condition during EGC operation (5') per December 22, 1992 letter from Marcia A. Jackson to Dr. Thomas E. Murley.

(3167M/VS/12)

- . _ . . _ . _ . . . _._..._.__.___.___..m. . . . . . . . __..,_....m. . ..__._. _ ... _.. _ , _ . . -

( _e-

~Et LICENSEI_IXENT REPORTS _{3RTIT 21 l LThe following is a_ tabular: summary of all Licensee Event Reports'for, Dyron Huclear Power Station, Unit Two,-submitted during the reporting period, .

December 1, 1992 through December 31, 1992._ This information'is provided pursuant-to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Licen6Re_ Event Report._Rumber Qcrur.IDDCR,RELS Iltle of._ Occurrence None e

J l

(

P s.

J A

d-.

(3767M/VS/13).

- , - -