ML20151E639
ML20151E639 | |
Person / Time | |
---|---|
Site: | Byron |
Issue date: | 06/30/1988 |
From: | Pleniewicz R, Spitzer D COMMONWEALTH EDISON CO. |
To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
References | |
BYRON-88-0685, BYRON-88-685, NUDOCS 8807260154 | |
Download: ML20151E639 (16) | |
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BYRCN NUCLEAR POWER STATION -l
-l UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT 1
l CCHMONWEALTH EDISON COMPANY i
NRC DOCKE" NO. 050-454 NRC DOCKET NO. 050-455 l
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l LICENSE NO. NPF-37 {
LICENSE NO. NPF-56 l
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n 8807260154 080630e PDR ^
7 ADOCK 030004 R PN
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- (0625M/0062M-2) g NY
,I. Monthly Ret,grt f o r Byrgp _._ Uni t 1 for_ the Inonth of June 1988 A. Summary of Onerating Experience for Unit 1 q i
1 The unit began this reporting period in Mode 5 (Cold Shutdown)'(This is a
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continuation of the cutage started in May, to repair a tube leak in the 1A Ste am Generator) The unit ~ remained in Mode 5 until 2228 on 6/9/88 when Mode 4 (Hot Shutdown) was entertd. The unit was taken critical at 0401 on 6/11/88 and synchronized to the grid at 0703 *he same day. The unit operated at power levels of up to 98% until 6/17/88 when power was reduced to approximately 50% to repair an EH leak. The problem was corrected the same day. The unit operated at power levels of up to 98% for the rest of the reporting period.
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I (0625M/0062M-3) f 1
', , gt _ OPERATING DATA REPORT
, DOCKET NO.: 050-454
, UNIT: Byron One DATE: 07/10/88' COMPILED BY: D. J. Spitzer' TELEPHONE: (815)234-5441 x2023 OPERATING STATUS
- 1. Reporting Period: June 1988. Gross Hours 720
- 2. Current.!y 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): 1097 (Mwe-net)
- 4. Reasons for Restriction (If Any): Steam Generator Split Flow (23MW)
THIS MONTH YR TO DATE CUMULATIVE *
- 5. Report Period Hrs. 720 4367 24456
- 6. Rx Critical Hours 475.9 3677.6 18989.6
- 7. Rx Reserve Shutdown Hours 0 0 L7.8
- 8. Hours Generator on Line 472.5 3663.9 18624.9
- 9. Unit Reserve Shutdown Hours 0 0 0
- 10. Gross Thermal Energy (MWH) 1417680 11389814 54985664
- 11. Gross Elsc. Energy (MWH) 477403 3797432 18423209
- 12. Net Elec. Energy (MWH) 447386 3580428 17319905
- 13. Reactor Service Factor 66.1 84.2 77.6
- 14. Reactor Availability Factor 66.1 84.2 77.8
- 15. Unit Service Factor 65.6 83.9 76.2
- 16. Unit Avtilability Factor 65.6 83.9 76.2
- 17. Unit Capacity Factor (MDC net) N/A N/A P/A .
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- 18. Unit Capacity Factor (DER net) 55.5 73.2 t'.2 s
- 19. Unit Forced Outage Hrs. 0 65.3 977.4
- 20. Unit Forced Outage Rate 0 1.8 5.0
- 21. Shutdowns Scheduled Over Next 6 Months: 09/03/8P i
- 22. If Shutdown at End of Report Period, Estimated Date of Startup:
- 23. Units in Test Status (Prior to Commercial Operation): Nono l
- Note - The cwnulstive numbers do not reflect power generated prior to commercie?
service.
l (0625M/0062M-4) j
C. AVERAGE DAILY UNIT POWER LEVEL
. DOCKET NO. 050-454
. UNIT: Byron One DATE: 07/10/88 COMPILED BY: D. J. Spitzer TELEPHONE: (815)234-5441 x2023 MONTH: June, 1988 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
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l INSTRUCTIQiS On this form list the average daily unit power level in MWe-Net for each day in the reporting month. Compete to the nearesc whole megawatt. These figures will be used to plot a graph for each reporting month. Nota that when maximum dependable capacity is used for tile net electrical ratir.g 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 shouJd be footnoted to explain the apparent anomaly.
( Od p 5Mt0062N-5)
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R3 port Period June, 1988 hNITSHUTDOWNS/ REDUCTIONS * ' BYRON
- i (UNIT 1) **************************
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No. Date Tvue Hours Reason Method LER Nn=her SysteR_ Component Cause & Corrective Action to Prevent Recurrence-l 7. 05/28/88 S 247.5 A 4 SG 1A S/G Outage for lA Steam Generator Tube Leak Repair (Continued from previous month)
1 ooce***********
- Susanary
- occe****s******
TYPE Reason Methnd System & Component F-Forced A-Equip Failure F-Admin 'l-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 Prep.sration 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)
( 0 525M/0062M-6 )
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UNIQUE IlERORTING REOUIREMENTS'(UNIT 1)'for the month of June 1988
- 1. Safety / Relief valve operations for Unit One.
VALVES NO & TYPE PLANT, DESCRIPTION DATE AC'IUATED AC'IUATION CONDITION OF EVENT None r
- 2. Licensee generated changes to ODCM. (Y/N)
No
- 3. Indications of fa led fuel.
a (Y/N)
Yes. I131 = 2.3E-3 pcuries/gr.
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(0625M/0062M-7)
F.
' LICENSEE EVENT REPORTS ' 't1 NIT 1)
- Th3 following is a tabular summary of all-Licensee Event Reports for Byron Nuclear Power June June 1 through Station, 30, Unit 1988.One, submitted during the reporting period,-
This information is provided pursuant to _ the reportable occurrence reporting requirements ..s set forth in 10CFR 50.73.
Occurrence Licensee Event Report Number Date Title of Occurrence NONE
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(0615M/0062M-8)
, , II. Monthly Report for Byron Unit 2 for the month of June 1988 A. Summary o f Operatina Ext,9rlence for Unit 2 The unit begea this reporting period in Mode 1 at 94% power. On 6/2/88 at 0640 a reactor trip occurred due to high negative flux rate. The reactor was taken critical at 1244 on 6/3/88 and synchronized to the grid at 0841 on 6/4/88. The unit operated at power levels ot up to 95% until 6/23/88 when a shutdown for Steam Generator Chemistry was initiated. At 1654 the same day, the turbine was taken off line. The turbine was synchronised to the grid at 1348 on 6/24/88. The unit operated at power levels'of up to 96% for the rest of the reporting period.
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(0625M/0062M-9)
B. OPERATING DATA REPORT DCCKET NO.: 050-455 UNIT Byron Two DATE: 07/10/88-COMPILtD BY: D. J. Spitzer TELEPHONE: (815)234-5441 x2023 OPERATING STATUS
- 1. Reporting Period: June 1988. Gross Hours: 720
- 2. Currently Authorised 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 Pestricted (If Any): 1055 (HWe-net)
- 4. Reasons for Restriction (If Any): Steam Generator Split Flow. (65 MW)
THIS MONTH YR TO DATE CUMULATIVE *
- 5. Report Period Hrs. 720 4367 7560
- 6. Rx Critical Hours 689.9 4310.6 6639.8
- 7. Rx Reserve Shutdown Hours 0 0 0
- 8. Hours Generator on Line 649.1 4066.7 6347.1.
- 9. Unit Reserve Shutdown Houra 0 0 0
- 10. Gross Thermal Energy (MWH) 1944550 11760743 18232907
- 11. Gross Elec. Energy (MWH) 650789 3948922 6053233
- 12. Net Elec. Energy (MWH) 614699 3723877 5694778
- 13. Reactor Service Factor 95.8 98.7 87.8
- 14. Reactor Availability Factor 95.8 98.7 87.8
- 15. Unit Service Factor 90.2 93.1 84.0 !
- 16. Unit Avallebility Factor 90.2 93.1' 84.0
- 17. Unit Capacity Factor (MDC net) N/A N/A N/A !
- 18. Unit Capacity Factor (DER net) 76.2 76.1 67.3
- 19. Unit Forced Outage Mrs. 70.9 112.7 399.7
- 20. Unit Forced Outage Mate 9.8 2.7 5.9
- 21. Shutdowns Scheduled Cver Next S Months I
- 22. If Shutdown at End of Report Period. Estimated Date of Startup l
- 23. Units in Test Str.tus /. Prior to Commercial Operation): None l
- Note - The cumulative numbers do not reflect power generated prior to commercial service.
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(0625M/0062M-10?
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C. AVERAGE DAILY UNIT POWER LEVEL
, DOCKET NO.: 050-455
, UNIT: Byron Two DATE: 07/10/88 COMPILED BY: D. J. Spitzer TELEPHONE: (815)234-5441 x2023 MONTH: June, 1988 DAY AVERAGE DAILY. POWER LEVEL (MWe-Net)
- 3. -24 MW 18. _
974 MW
- 6. 1088 MN 21, 1012 MW I
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INSTRUCTICHS On this form list the average daily unit power level in NWe-Net for each day in the reporting month. Compute to the rearest whole megawatt. These figures will be used to plot a graph for each reporting month. Note that when max imum dependable capacity is tued for the net electrics 1 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) l
R: port Period June, 1988 UNIT SHUTDOWNS / REDUCTIONS
- BYRON *
(UNIT 2) ************************** .
No. Date Iygg Hours Reason Method TSR Nn=her System Component Cause & Corrective Action to Prevent Recurrence
- 10. 06/02/88 F 50 A 3 RD Unit 2 Reactor Trip from Power Range high negative flux rate.
- 11. 06/23/88 F 20.9 H 1 SG Steam Generator Cation Conductivity problems.
ecocemene******
o 3ununary
- ecoc**eemme****
TYPE Reason Method System & Comoonent 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-Ol61)
(0625M/0062M-12) l L_.._-:_--_--.----__-----_---_----------------------- - - - - ^- .
I E. UN100E REPORTING REQUIREMENTS (UNIT 2) for the month of June 1988
- 1. Safety / Relief valve operations for Unit Two.
VALVES. NO & TYPE PLANT DESCRIPTION DATE ACTJATED ACTUATION CONDITION OF EVENT None
- 2. Licensee generated changes.to ODCM.- (Y/N)
No-
- 3. Indications of failed fuel. (Y/N)
Yes. Ii31 = 7.5E-3 pcuries/gr.
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(0625M/0062M-13) 1
F. LICENSEE EVENT REPORTS (UNIT 2)
The following is a tabular sumery of all Licensee Event Reports for Byron Nuclear Power Station, Unit Two, submitted during the reporting period, June 1 through June 30, 1988. This information' is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CTR 50.73.
Occurrence Licensee Event Retrort Number .Date Title of Occurrence f,8-004-00 5/6/88 -" Main Feedwater Pump Trip Due to Improper Isolation of Electrohydraulic Control Fluid Supply Resulting -in Reactor Trip" 88-005-00 5/6/88 "Technical Specification Violation Due to . Operational Mode Changes Made While Auxiliary Feedwater Pump Inoperable Due to Level Switch Failure" 88-006-00 6/2/88 "Reactor Trip Due to Control Rod Drop Caused by Intermittent Component Failure in the Rod ;
Drive System" j 82-007-00 6/3/88 "Feedwater Isolation Actuations
' Due to Steam Generator l Preheater Bypass Valve Failure l to Open." l 1
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FACILITY NAME (1) 000EF F* [
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tvron. Unit 2 811ielel d $] 1 i TEXf ~ Energy Industry Identiffcettee ggegen code ib
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A. PLANT CaeITIQMS PRIDE TO N r' ' M,:-
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& E, Event'Date/ Time ime/Reles - 1
'E fM Power C'ameadtten lk &~-Q l p'g 3g.;
Unit 2 feet 1 - i -
- 8. DESCRIPTION OF EVENT:
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On July 30, 1987, the 25 Diesel Geme m -wa. ' '
280$ 8.1.1.2.a-2. Per Techalcal 1.1 ? > * - '
and achieve rated speed, voltage , an6 t r. '.- '
achieve rated conditions. At 115 W . w, t '
Operatten Action Requirement (LC M bas i l' were inttIated and a Ceeper Emery ta'-
failure revealed that a regulater id4GP r i10- '" ' ' '
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stadt; was set leproperly due to e- e, e caused the slow start of the 25 Blesg> tr oJ : >
July 31, 1987 and at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> tes- ,tu '
to clear the LCOMt. The 25 06 starte$ tn'<-
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per the 'svrveillance. Thirtese atente 1, t " N FallerE*. This second fallers uma. fai' ors ,
st'
-laeperable.
- 2 A. 1 ,
y, +
.t Again{t_rowbiesheetingactivltiosame .h t i v i.,'<' - <r reprobatative. Based on clearesse Ing t o- , '
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with the eastte vender I r, r c * '
decided:te restart the 25 DE for e on a z Nr "
started, gradually leaded, and s. r. . -
meintenance run. It was decided to fr c +- ', <<
into the full lead run the dises&J ' 1 u r ' .< u . * ' -
replace'the turbocharger beges -
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Sased on the estimated lenysh of .the ea' - ** -
requirements, the return to serveep DG s " '
's. t:
therefore, exceeded the LCEAR rep '
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1196 hoeirs on August .f 2,19WM \j Cy^ 'h s
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On August 2.1987, knowley of h ~'I t t o -
Suppiy[9ffice ro p ted that U>it 'o i: - -
of the empected record damned - ' hts <n- '. rm Regulatory Commission OSC) 9er pdOgf d' %, '
The I K granted Byron Enforcenset np m i' ' r.,, -
wes operable, or unt119008 en Asper W
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.g Cdmnionwealth Edison _
i / ByronNucitarStation t
v '4450 North German Church Road '
N Byron, Illinois 61010 July 10, 1988 7
LTR ' SYRON 88-0685 Files 2.7.200 Director, Office of Management Information-and Program Control
- 4. United States Nuclear Regulatory Commission Washington, D.C. 20555 "
ATIN: Document Control Desk Gentlemen:
Enclosed for your information is the Monthly Performance Report covering Byron Nuclear Power Station for the period June 1 through June 30, 1988. *
, f very truly yours, i i t
s /f' 4 R. Pleniewicz /
Station Manager /
Byron Nuclear Powe Station f 4
RP/DJS/bb
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- cci A.B. Davis, NRC, Region III '
NRC Resident Inspector Byron Gary Wright, Ill. Dept. of Nuclear Safety T.J. Malman/K.L. Graesser ,
H. E. Bliss Nuclear Fuel Services, PWR Plant Support L. Anastasia, Station Nuclear Engineering
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