ML20044C191

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Monthly Operating Repts for Feb 1993 for Byron Nuclear Power Station,Units 1 & 2
ML20044C191
Person / Time
Site: Byron  Constellation icon.png
Issue date: 02/28/1993
From: Colglazier R, Schwartz G
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-93-0138, BYRON-93-138, NUDOCS 9303180295
Download: ML20044C191 (16)
v • d • e


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' M):. Commonwealth Edison

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. March.11, 1993 I

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BYRON 93-0138

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2.7.200 (1.10.0101) j Director, Office:of Management Information and Program Control'

. United States Nuclear Regulatory Commission WashJngton, D.C..

20555 i

ATTN:

Document Control Desk j

~ Gent.lemen

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Enclosed for your_'information is the Monthly Performance Report

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covering' Byron Nuclear. Power Station for the period February 11

-j t.hrough February 28, 1993.

Sincerely, P

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LG Arv.

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.G..K.' Schwartz.

-Station Manager I

s Byron' Nuclear. Power. Station

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A.B.. Davis,.NRC, Region.III NRC. Resident Inspector Byron IL Dept. of Nuclear' Safety y.,.

-M.J. Wallace/E.D.~Eenigenburg'

-: Nuclear. Licensing Manager-

~. Nuclear; Fuel. Services, PWR' Plant Support-D.R -Eggett,. Station Nuclear Engineering-e

1NPO. Records Center J.B. Hickman a USNRC

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l BYRON NUCLEAR POWER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT COMMOFWEALTH EDISON COMPANY NRC DOCKET NO. 050-454 NRC DOCKET NO. 050-455 LICENSE NO. NPF-37 LICENSE NO. NPF-66 (3927M/VS/031193/1)

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hignthly Report for Dyron UNIT l'for-the month of February 1993 b;

f 2LdBL4RDI.y_pf OperAtlJ2g_.fAPRIlgnce for Unit 1 The Unit began this reporting period in Mode:1 (Power Operations). The' power level varied'due to-load following requirements.

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' OPERATING DATA REPORT DOCKET NO.

050-454 t

UNIT: -Byron.One' DATES 03/10/93 COMPILED-BY:

R..Colglazier; TELEPHONE:

(815)234-5441

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x2282:

4 OPERATING STATUS y.

1.

Reporting Period:

February,-1993.

Gross Hours:

672

[

2.

Currently Authorized Power Levels 3411 (MWt)

Design Electrical Rating: 1175 (MWe-gross)

Design Electrical Rating: 1120 (MWe-net)

Max Dependable Capacity: 1105 (MWe-net)

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3.

Power Level to Which Restricted (If Any): Nono 4.

Reasons for Restriction (If Any): N/A i

THIS MONTH YR TO DATE CUMULATIVE

  • 5.

Report Period Hrs.

672 1416 65,353 3

6.

Rx Critical Hours 98.4 842.4 54s500.7 7.

Ex Reserve Shutdown Hours 0

0 38 j

8.

Hours Generator on Line 98.4 842.4

-53 869.2' 9.

Unit Reserve Shutdown Hours O-D.

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  • 10.' Gross Thermal Energy 1(MWH) 258,240--

2,641,131 163,097l422,

11. Gross Elec. Energy (MWH) 82,348

~889,469 54,9914,057-t

12. Net Elec. Energy (MWH) 78,156 857,714

.52,063iS80:

13. Reactor Service Factor 14.64
59.49 83.39f
14. Reactor Availability Factor 14.64 59.49E

'83.45~

15. Unit Service Factor 14.61 59.48 82.43
16. Unit Availability Factor 14.61 59.48 82.43
17. Unit Capacity Factor (MDC net) 10.53 54.82' 72.10
18. Unit Capacity Factor (DER net) 10.38 54.08 71.13-19.

Unit Forced Outage Hrs.

0 0.

1,403.4 j

20. Unit Forced Outage Rate 0

0.-

2.54 l

21. Shutdowns Scheduled Ove' Next 6 Months:- - Refueling Outage DIR05 2/5/93

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22. If Shutdown'at End of Repost Period, Estimated Date of Startup:

4/05/93>

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23. Units in Test Status (Prior to Commercial Operation):- None.

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  • Note - The cumulative numbers do'not_ reflect power generated prior to commercial service.

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,(3927M/VS/031193/3)

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R Ca__._AVIRAGE DAILX_UNII_I'RMER_LEYEL

~ 050-454>

DOCKET NO.

UNIT:

Byron One DATE:

03/10/93.

COMPILED BY.

R. Colglazier.

TELEPHONE:

(815)234-5441-x2282-MONTH: February, 1993 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.

954 MW 16.

-10_MW 2.

9Q9 MW 17.

-10 MW 3.

R98 MW 18.

-12 MW 4.

152._NW 19.

-12_J5W 5.

O MW 20.

-l'2 MW 6.

-12 MW 21.

-12 MW 7.

-11 MW 22.

-12 MW 8.

-10 }9f 23.

-12 MW 9.

-10 MW 24.

-12 MW-10.

-10 MW 25.

-11 MW 11.

-10_MW 26.

-12 MW-12. _ __,_

-10 MW

-27.

-12 MW 13.

-IDJJi

'2 8. _

-12 MW 14.

-10 MW 29.

l 15.

_. _-10_liW 30.

31.

- INSTRUCTIONS t

- on this form list the average' daily unit power leve1 1n MWe n t for eachfday

~

e in the_ reporting month.' -Compute to the' nearest-whole megawatt. These. figures _

will'be used to' plot a graph for;each reporting month.. Notelthat when maximum i

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 v. nit.

1 power: output sheet should be footnoted'to explain the apparent anomaly.

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- (3927M/VS/031193/4)*

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R; port Period February,.1993 UNIT SHUTDOWNS / REDUCTIONS BYRON (UNIT 1)

No..

Date Typ3_.JIours heason Method LER Number System Component Cause & Corrective Actiqp to Prevent Recurrence 2

2/05/93 S

573245 C

1 Began BIR05 cocco**********

- Summary Began BIR05 coccce*********

TYPE Reason Method System & Component F-Forced A-Equip Failure -F-Admin 1-Manual Exhibit F & H S-Sched B-Haint cr 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) i p

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Safety / Relief valve operations for Unit One.

K VALVES NO & TYPE PLANT DESCRIPTION-DATE AC111ATED ACTUATION CONDIE DH OLEVENT p

None

'hi 2.

Licensee generated changes to ODCM.

The Offsite Dose Calculation Manual (ODCM) was revised to address comments and recommendations provided by the Nuclear Regulatory Commission in their' q ;-

Safety Evaluation Report (SER) and Idaho National Engineering Laboratory in their Technical Evaluation Report (TER).

Two: primary modifications; were made based-on the SER/TER.t First, CECO will now calculate dose'for the teenager.

In the past CECO calculated doses.to adults, children and j

infants.

Inhalation and ingestion values were obtained from Regulatory <

sj Guide 1.109.

Secondly, the Radiological Effluents'and Monitoring Chapter of ODCM (Chapter.10) was rewritten to specifically reflect how effluent 1 values and setpoints are determined.

t In addition, the_ database of meteorological values utilized in'ODCM;

-i calculations were expanded from about three years.to_ ten years. This=

enhancement is based on the meteorology-at~each.given site and'provides a more representative basis of the meteorology for the. station' a

3.

Indications of.falled fuel.

Fuel Reliability Indicator

,t Yes FRI:

5.4E-4 pC1/cc 4.

10CTR50.46 Reporting Requirements:

Peak Clad. temperature (PCT)' changes r

resulting from change or errors to the ECCS evaluation model.

l 4

Current licensing basis PCT plus margin allocation (*F)

Lar.ge_Rtenk_LOCA Sma2LRIeak LOCA 2051.3 1601.6 L'

n.

Explain differences from previouc reports i^

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')~

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'per December 22,'199211etter from'Marcia A. Jackson to Dr. Thomas'E..

Murley.

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(3927M/VS/031193/6)

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GENERIC ODCM REVISION SUte4ARY 7

Effective Jan.' 1, 1993 CHAP _TER/ APPENDIX PAGES_

Tab 1'e of~ Contents 14 Chapter 3 5, 6 Chapter.4 25, 27, 28, 31, 32 Chapter 7 3

.i Chapter 8 2, 3 Reference 5, 6, 7, 81 Appendix A 2, 3, 4, 5, 7, 8,

9,-10,-12,.13, 14, 16, -

17, 18, 19, 2D,'23, 25,c26, 27, 28,'29,.

30, 31, 32, 33,~34, 35,' 36,-37, 38, 39,'

41, 42, 44, 45, 47s 49, 50, 51, 52,;53,-

54, 56, 58, 59, 60 New Pagest' '45a,154a-Appendix D 1,l17,'18,'19, 20s 32 New Pagess. 4a, 4b, 4c,.13a, 13b', 13c Appendix E' 8, 26, 29, 30 f

New Pagest. Ba

. l 7

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'I (3927M/VS/031193/7)

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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, February 1,,1993 through February' 28,.1993.

This information is provided ~

pursuant to the reportable occurrence' reporting requirements as set forth 1n c

10CFR 50.73.

Occurrence I

LiCCRERe EvgRt Report liumher Date Iltle o'f OccMr.LeRCR LER: 454:93-001 2/01/93 Low temperature overpressure protection heatup/cooldown.

curves analysis. deficiency-LER:

454:93-002 2/26/93 VQ valves failed to close as required-during surveillance due to lifted lead.

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- II.' liQathly Repprt-for Byro T_2'for the month of February _1993 h......:.1 fammary of Operating Egpgrience for Unit 2 The UTit began this reporting period in Mode 3~(Power Operations).

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IOPERATING DATA REPORT DOCKET NO.*~

050-455.

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~ Byron Two I

UNIT:

DATE:

03/10/93 COMPILED BY::

R. Colglazierf TELEPHONE:

(815)234-5441' x2282-

. OPERATING STATUS-1.

Reporting Period:

February, 1993. ' Gross Hours - 672-7 2.

Currently Authorized Power Level: 3411 (MWt)

Design Electrical Ratingr 1175 (MWe-gross) a DesignElectricalRatings!1120(MWe-net) l Max Dependable Capacity: 1105 (MWe-net) b 3.

Power Level to Which Restricted (If Any): 'N/A 4.

Reasons for Restriction (if Any):

THIS MONTH YR TO DATE

' CUMULATIVE

  • i 5.

-Report Period Hrs.

672 1,416 48,457 6.

Rx Critical Hours 672 1,416 41,751.6 7.

Rx Reserve Shutdown Hours 0

0'

'O 8.

Hours Generator on Line 672' 1,416 41,221.3

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Unit Reserve Shutdown Hours 0

0 0

10. Gross-Thermal Energy-(MWH) 2,208,878 4,586,864.

117,337,321

-j

11. Gross Elec.-Energy.(MWH)-

759,503 1,574,665 39,790,603~

t

12. Het Elec. Energy (MWH) 744,994 1,537,301 37,698,066-
13. Reactor Service Factor 2001 100 86.16
14. Reactor Availability Factor 100 100-86'.16"
15. Unit Service Factor 100 100 T 85.07'
16. Unit Availability Factor 100 100 85.07-
17. Unit Capacity Factor (MDC net) 100.3 98.25 70.40
18. Unit Capacity Factor (DER net) 98.98 96.93 69.46
19. Unit Forced Outage Hrs.

0 0

1244;

20. Unit Forced Outage Rate 0

0 2.93

(

21. Shutdowns Scheduled Over Next 6 Months -
1 B2R04 08/28/93-
22. If Shutdown.at End.of Report Period, Estimated Date of Startup: NONE
23. Units in Test. Status { Prior to Commercial Operation) s None
  • Note - The cumulative numbero do.not reflect-power generated prior to commercial service.

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(3927M/VS/031193/10)

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. AVERAGE DAILY UNIX POWER LEVEL Lh DOCEET NO.

- 050-455-i k~ UNIT Byron Two :

DATE:

03/10/93' COMPILED.BY:

R. Colglazier.

F TELEPHONE:

(815)234-5441; 1

x2282-MONTH; February,-1993

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~

DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.

1092 MW 16.

1155 MW 2.

1108 MW 17.

1164 MW..

s 3,

1017 MW 18.

1123 MWI 1093 MW 19.

1113 MW 5,

1105 MW 20.

859 MW 6.

1071 MW 21, 1104 MW

+

7.

1089 MW 22.

1127 MW 8.

1104 MW 23.

1132 MW

.[

9.

1104 MW 24.

1123 MW' 10.

1161 104 25, 1126 MW 11.

1165 MW 26.

1121 MW 12.

1096 MW 27.

1104 MW 13.

1139 MW 28.

'1097 MW 14.

1146 MW 29.

i.

15.

1157 MW 30.

31.

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 figurer-will'be used to plot a graph for..each reporting month. Note _that w' hen 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 eheet should'be footnoted to explain the. apparent anomaly.-

F

.(3927M/VS/031193/11(

~

JR: port-Period February, 1993 UNIT SHUTDOWNS / REDUCTIONS BYRCN (UNIT 2)

No.

Date' h.Bours Reason Methp_d MR Number System Component Cause & Corrective Action to Prevent Recurrence

'2 02/20/93 S

A 5

Reduced load to conduct TV/GV Surveillance caccC**********-

ce Surunary C0006**********

TYPE

.Egason-Method System & Component F-Forced

. A-Equip Failure F-Admin 1-Manual Exhibit F & H 5-Sched.

B-Maint or-Test G-Oper Error 2-Manual Scram Instructions for C-Refueling.

H-Other 3-Auto Screm-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) 9 19,27M/VS/031193/12).

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  • E E % UMIQUE_ REPORT 111G_ REQUIREMENTS (UNIT 2) Inr the 'monthaLIchruntr_1223 l

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Safety / Relief valve operations-for Unit ~Two.

VALVES NO & TYPE PLANT DESCRIPTION.

DAIE ACTUATED ACIUAIID1{

CQNDITION

'OF' EVENT d

None 2.

Licensee generated changes to ODCM.

The Offsite Dose Calculation Manual (ODCM) was revised to address comments-and recommendationsLprovided by the Nuclear Regulatory Commission in their Safety Evaluation Report (SER) and Idaho National Engineering Laboratory in

~

their Technical Evaluation Report (TER).

Two primary modifications were.made based on.the SER/TER. First, CECO will now calculate dose.for the teenager (

In the past CECO calculated doses to adults, children and-infants.--

Inhalation and ingestion values were obtained from Regulatory Guide 1.109.

Secondly, the Radiological. Effluents and Monitoring Chapter-of ODCM-(Chapter 1

10) was rewritten to specifically reflect how effluent values and setpoints' nre determined, t

In addition, the database of meteorological values utilized.in ODCM1 calculations were expanded-from about three; years to ten years.:'This enhancement ~1s based on the meteorology at each given. site and_provides'a y

more representative basis of the meteorology for the station.

3.

Indications of failed fuel.

No.

Fuel Reliability Indicatort FRI = 1.2E-4 pCi/CC t

4.

10CFR50.46 Reporting Requirements:

Peak Clad. temperature.(PCT) changes resulting from. changes or errors to.the ECCS evaluations model.

Current licensing basis PCT plus major allocations ('F)

' I, 9

Larse__RreALLOCA SmalLar.cAk LOCA

~"

2064.1 1481.6 Explain differences from previous reports 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.-

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b GENERIC ODCM REVISION

SUMMARY

E Effective Jan. 1, 1993 i

CHAEIERIAEEENDlX EAGES

[i'i Table of Contents 14 Chapter 3-5, 6

'l Chapter 4 25, 27, 28, 31, 12 i

Chapter 7 3

Chapter 8 2, 3 l

Reference 5,6,7,3 Appendix A 2,

3,.4, 5, 7, 8, 9,110s 12, 13, 14,:16,;

- f 17, 18, 19, 20, 23, 25i-26,R27, 2B; 2 9, ~

d 30,.31, 32,.33,'34, 35', 36, 37,-38,'39, i

41, 42, 44, 45,-47,'49, 50,-51,:52,.53, 54, 56, 58, 59, 60 New Pagest. '45a, 54a-Appendix D 1,

17, 18, 19, 20, 32-New Pagess' 4a, 4b,.4c,L13a, 13b, 13c Appendix E 8, 26, 29, 30 LNewlPagest. Ba 4

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' LICENSEE EVENT REPORTS'(UNIT 2)

The following;is a tab'ular summary of all Licens'ee Event Reports 1for

.'i l

Byron Nuclear Power Station, Unit.Two, submitted during the reporting period;._

3 February 1, 1993 through February 28, 1993..This'information is provided

~

pursuant to the reportable occurrence reporting requirements as set forth in.

'{

10CFR 50.73.

Licensee Event Regnrt Number Occurrence Date Title of Occurrenca LER 455:93-001 2/23/93

' Wiring error in SSPS testicircult:

on 3 of 4 trains.

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