ML20211H764

Monthly Operating Repts for Jan 1987

ML20211H764
Person / Time
Site:	Byron
Issue date:	01/31/1987
From:	Querio R, Spitzer D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
87-0181, 87-181, NUDOCS 8702260278
Download: ML20211H764 (14)

Text

e 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 8702260278 870131 ADOCK 05000454 PDR PDR R

(0625M/0062M) (2)

I.

Monthly Report for Byron Unit 1 A.

Summary of Operating Experience for Unit 1 The Unit was at power for the entire reporting period. There were no reactor trips or forced reductions of power. The unit continued "coastdown", in anticipation of the February 15, 1987 refueling outage.

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B.

OPERATING DATA REPORT DOCKET NO.: 050-454 UNIT: Byron One DATE:

02/10/87 COMPILED BY:

D. J. Spitzer TELEPHONE:

(815)234-5441 x2023 i

OPERATING STATUS 1.

Reporting Period: January 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): 1105 (MWe-grcss) 4.

Reasons for Restriction (If Any): Reduction of Hot Leg Temperature for Primary Water Stress Corrosion Cracking Concerns, i

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THIS MONTH YR TO DATE CUMULATIVE

• 5.

Report Period Hrs.

744 744 12073 t

6.

Rx Critical Hours 744 744-10457.4 7.

Rx Reserve Shutdown Hours 0

0 37.8 8.

Hours Generator on Line 744 744 9697.7 i

9.

Unit Reserve Shutdown Hours 0

0 0

10. Gross Thermal Energy (MWH) 1687879 1687879 28233713

11. Gross Elec. Energy (MWH) 558710 558710 9482942 h

12. Net Elec. Energy (MWH) 519836 519836 8928737

13. Reactor Service Factor 100 100 86.6 b

14. Reactor Availability Factor 100 100 87.0

15. Unit Service Factor 100 100 80.3

16. Unit Availability Factor 100 100 80.3 l

17. Unit Capacity Factor (MDC net)

N/A N/A N/A i

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18. Unit Capacity Factor (DER net) 62.4 62.4 66

19. Unit Forced Outage Hrs.

0 0

777

20. Unit Forced Outage Rate 0

0 7.4

21. Shutdowns Scheduled Over Next 6 Months: Scheduled refueling outage to start 2/15/87

22. If Shutdown at End of Report Period, Estin ted Date of Startup: N/A

23. Units in Test Status (Prior to Comunercial Operation): See Unit 2 (II.B.23)

• Note - The cumulative numbers do not reflect power generated prior to commercial

service, i

(0625M/0062M) (4)

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

C.

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.:

050-454 UNIT: Byron One DATE: 02/10/87 COMPILED BY:

D. J. Spitzer TELEPHONE:

(815)234-5441 x2023 MONTil: January, 1987 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.

882 MW 17.

743 MW 2.

882 MW 18, 739 MW 3.

882 MW 19.

722 MW 4.

883 MW 20.

711 MW 5.

884 MW 21.

700 MW 6.

872 MW 22.

687 MW 7.

844 MW 23.

677 MW 8.

843 MW 24.

649 MW 9.

830 MW 25, 637 MW 10.

815 MW 26.

628 MW 11.

814 MW 27.

618 MW 12.

809 MW 28.

613 MW 13.

782 MW 29, 608 MW 14.

774 MW 30.

603 MW 15.

774 MW 31.

593 MW i

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16.

766 MW I

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 I

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)

R: port Period January, 1987 UNIT SHUTDOWNS / REDUCTIONS BYRON (UNIT 1) i No.

Date Type Hours Reason Method LER Number System Component Cause & Corrective Action to Prevent Recurrence 1

1/1 Thru S

744 H

5 Reduced load daily due to coastdown of Unit, 1/31/87 in preparation for February refueling outage.

l esco***********

Daily Power Reduction /Coastdown for February Refueling Outage, Summary coco ***********

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) (6) i i

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)

Yes.

Iodine spikes during pcver 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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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, January 1 through January 31, 1987. 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 87-001-00 1-11-87 Radioactive Release Tank not sampled prior to release as required by Technical Specification.

87-002-00 1-14-87 Main Control Room Ventilation Engineered Safety Feature Actuation due to misalignment of Radiation Monitor Checksource.

87-003-00 1-16-87 Continuous Fire Watch not established as required by Technical Specification.

(0625M/0062M) (8) 1

= -

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. II. Monthly Raport for Byron Unit 2 A.

Summary of Operating Experience for Unit 2 Byron Unit 2 started this reporting period in Mode 3-(Hot Shutdown). On January 9, 1987, the unit entered Mode 2 (Startup). This was Initial Criticality for Unit 2.

On January 30, 1987, Unit 2 received its full power license (NPF-66). On January 31, 1987 the unit entered Mode 1 (Power Operation) and remained in Mode 1 through the end of this reporting period.

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B.

OPERATING DATA REPORT DOCKET NO.:

050-455 UNIT: Byron Two DATE: 02/10/87 COMPILED BY:

D. J. Spitzer TELEPHONE:

(815)234-5441 x2023 OPERATING STATUS 1.

Reporting Period: January 1987. Gross Hours: 545.4 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): 58.75 (MWe-gross) 4.

Reasons for Restriction (If Any): Condition of Facility Operating License NPF-60, up until 1-30-87 at receipt of 100% license NPF-66.

The Unit is in startup and Power Assension Test Phase.

THIS MONTH YR TO DATE CUMULATIVE

• 5.

Report Period Hrs.

545.4 545.4 545.4 6.

Rx Critical Hours 440.6 440.6 440.6 7.

Rx Reserve Shutdown Hours N/A N/A N/A 8.

Hours Generator on Line N/A N/A N/A 9.

Unit Reserve Shutdown Hours N/A N/A N/A

10. Gross Thermal Energy (MWH)

N/A N/A N/A

11. Gross Elec. Energy (MWH)

N/A N/A N/A

12. Net Elec. Energy (MWH)

N/A N/A N/A

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/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: 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 Initial Criticality 01/07/87 01/09/87 Initial Electricity 02/05/87 02/06/87 Commercial Operation 05/31/87

• Note - The cumulative numbers do not reflect power generated prior to commercial service.

(0625M/0062M) (10)

C. -AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.:

050-455 UNIT: Byron Two DATE:

02/10/87 COMPILED BY:

D. J. Spitzer TELEPHONE:

(815)234-5441 x2023 MONTil: January, 1987 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.

O MW 17.

O MW 2.

O MW 18.

O MW 3.

O MW 19.

O MW 4.

O MW 20.

O MW 5.

O 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 12.

O MW 28.

O MW 13.

O MW 29.

O MW 14.

O MW 30.

O MW 15.

O MW 31.

O MW 16.

O MW INSTRUCTIONS f

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 l

will be used to plot a graph for each reporting month. Note that when maximum l

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 i

the restricted power level line.)

In such cases the average daily unit power j

output sheet should be footnoted to explain the apparent anomaly.

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(0625M/0062M) (11)

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• • • • • • • • • • • • • • • • • • • • • • • • a*

Rrport Period January, 1987 UNIT SHUTDOWNS / REDUCTIONS BYRON (UNIT 2)

I No.

Date Type Hours Reason Method LER Number System Component Cause & Corrective Action to Prevent Recurrence N/A come***********

i Summary oooce**enennen.

TYPE Reason Method System & Component F-Farced 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) (12)

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E.

UNIQUEREPORTINGREQUIREMENTS(ifdIT;h 1.

Safety / Relief valve operations for Unit Two.

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VALVES NO & TYPE PLANT GESCRIPTION DATE ACTUAT5D ACTUATION CONDITION

!OP'SVENT 2

01/03/87 2RY455A Pressurizer Moda 3 Valts lifted Porv 0% Power twice due To conditions caused by Start-Up Test

1. 2.63.82 2.

Licensee generated changes to ODCM.

(Y/N) j No i

I 3.

Indications of failed fuel.

(Y/N) y No 4

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4 F.

CENSEE 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, January 1 through January 31, 1987. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

D Licensee Event Report Number Date Title of Occurrence 87-001 01/15/87 Reactor Trip due to failed Reactor Coolant Resistance Thermal Detector.

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3 February 10, 1987 LTR:

BYRON 87-0181 File:

2.7.200 Director, Office of Management Information and Program Control

+

United States Nuclear Regulatory Commission Washington, D.C.

20555

.s.

ATTN:

Document Control Desk Gentlemen:

a Enclosed for your information is the Monthly Performance Report covering Byron Nuclear Power Station for the period January 1 through January 31, 1987.

Very truly yours, i

j' R. E. Querio Station Manager Byron Nuclear Power Station

/

REQ /PHD/bb cc:

J.G. Keppler, NRC, Region III NRC Resident Inspector Byron Gary Wright,'Ill. Dept. of Nuclear Safety D.P. Galle T. J. Maiman D.L. Farrt.r Nuclear Tuel Services, PWR Plant Support L. Anastasia, Station Nuclear Engineering INPO Records Center l

Thermal Group, Tech Staff Byron Station Nuclear Group, Tech Staff Byron Station L. Olshan - USNRC D. J. S itzer P

l (0625M/0062M) ( l_)

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