ML20058N668
| ML20058N668 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/31/1990 |
| From: | Dundek K, Kofron K COMMONWEALTH EDISON CO. |
| To: | NRC, NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 4957Z, BW-90-0811, BW-90-811, NUDOCS 9008140365 | |
| Download: ML20058N668 (27) | |
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Commonweenh Edison Braldwood Nuclear Pow r St: tion : Rbute C1, Box 84 1 Braceville. Illinois 60407 5 Telephone 815/458-2801 l l : l August 10, 1990 BW/90-0811 ! i Director, Office of Resource Management United States Nuclear Regulatory Commission Washington, D.C. 20555 i ATTN: Document Control Desk j Gentlemen: l l Enclosed for your information is the Monthly Performance , Report covering Braidwood Nuclear Powar Station for the period July 1 through July 31, 1990. Very truly yours, K. L. Kofron b I Station Manager Braidwood Nuclear Station 1 KLK/EHC/sjs (4957z) Attachments cc: A. B. Davis, NRC, Region III NRC Resident Inspector Braidwood Ill. Dept. of Nuclear Safety M. J. Hallace K. L. Graesser T. J. Kovach Nuclear Fuel Services, PHR Plant Support INPO Records Center Performance Monitoring Group Tech Staff Braidwood Station Mt h \ '
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Nuclear Group, Tech Staff Braidwood Station s \ S. Sands - USNRC S. C. Hunsader M N(((d(b
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D.R. Eggett-Nuclear Engineering Department {' g'. p 9008140365 900731 / \\ \ PDR ' ADOCK 05000456 R PDC
m BRAIDH000 NUCLEAR P0HER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT , COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-456 LICENSE NO. NPF-72 NRC DOCKET NO. 050-457, LICENSE NO. NPF-77 l i 1
l
. . I s 1 I. Monthly Report for Braidwood Unit 1 A. Sumarv of Operating Experience .
Braidwood Unit 1 operated routinely in July with no outages or significant power reductions. l W i i f i l I i f 1 l 1 l l (4957z/3) i
B. OPERATING DATA R EQRI DOCKET NO.: 50-456 UNIT: Braidwood 1 DATE: 08/10/90 COMPILED BY: K. M. Dundek TELEPHONE: (815)458-2801 l ext. 2480 , OPERATING STATUS
- 1. Reporting Period: July, 1990 Gross Hours: 744
- 2. Currently Authorized Power Level (MHt): 3411 Design Electrical Rating (MWe-gross): 1175
- i Design Electrical Rating (MHe-net): 1120
! Max Dependable Capacity (MHe-gross): 1175 l Max Dependable Capacity (MHe-net): 1120 l l 3. Power level to which restricted (If Any): None
- 4. Reasons for restriction (If Any): None :
THIS MONTH YR TO DATE CUMULATIVE
- 5. Report period Hours: 744 5087 17576 i
- 6. Hours Reactor Critical: 744- 5039.9 14137.1
- 7. RX Reserve Shutdown Hours: 0.0 0.0 0.0 !
- 8. Hours Generator on Line: 744 5019.2 13868.8
- 9. Unit Reserve Shutdown Hours: 0.0 0.0 0.0
- 10. Gross Thermal Energy (MHH): 2194767___ _16047264 40850472
- 11. Gross Elec. Energy (HUH): 783198 _1564954 14045021
- 12. Net Elec. Energy (MHH): 752160 5358828 13415999
- 13. Reactor Service Factor: 100 99.1 80 4_
- 14. Reactor Availability Factor: 100 99.1 80.4
- 15. Unit Service Factor: ,, 100 98.7 78.9
- 16. Unit Availability Factor: 100 98.7 78.9
- 17. Unit Capacity Factor (MDC net): 90.3 94.1 68.2
- 18. Unit Capacity Factor (DER net): 90.3 94.1 68 2_
- 19. Unit Forced Outage Rate: 0 1.3 3.9
- 20. Unit Forced Outage Hours: 0 67.8 568.1
- 21. Shutdowns Scheduled Over Next 6 Months: None
- 22. If Shutdown at End of Report Period, Estimated Date of Startup:
(4957z/4) t
i Ej C. AVERAGE DAILY UNIT NET PONER LEVEL LOG DOCKET NO.: 50-456 UNIT: Braidwood 1 DATE: 08/10/90 COMPILED BY: K. M. Dundek i TELEPHONE: (815)458-2801 l ext. 2480 MONTH: July, 1990
- 1. 1002 17. 1111
- 2. 1041 18. 1048 ,
- 3. 1063 19. 1061
- 4. 1097 20. 1043
- 5. 1073 21. 1038
- 6. 1000 22. 1000
- 7. 908 23, 1038 >
- 8. 829 24, 1043
- 9. 831 25. 1032 .
i 10, 832 26, 1045 11, 836 27. 1055 , 12, 916 2L. 1052
- 13. 1067 29. 1035
- 14. 1030 30, 1043
- 15. 1045 31, 1027
- 16. 1082 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. (4957z/5)
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D. UNIT SHUTDOHNS/ REDUCTIONS DOCKET NO.: 50-456 UNIT: Braidwood 1 . DATE: 08/10/90 4 COMPILED BY: K. M. Dundek TELEPHONE: (815)458-2801 ext. 2480 REPORT PERIOD: July, 1990 - No DAE TYPE !!Q!JRS REASON METHOD LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE None
SUMMARY
TYPE REASON METHOD SYSTEM & COMPONENT F-Forced A-Equipment Failure Maint or Test 1 - Manual Exhibit F & N S-Scheduled B-Maint or Test 2 - Manual Scram Instructions for Preparation of C-Refueling 3 - Auto Scram Data Entry Sheet D-Regulatory Restriction 4 - Continued Licensee Event Report E-Operator Training & License Examination 5 - Reduced Load (LER) File (NUREG-0161) F-Administration 9 - Other G-Oper Error H-Other (4957z/6)
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N O IT TN PE IV RE C SF EO D N O I T TI ND AN LO PC I t . i s EN . n n PO M U o YI C i TT 0
- t A 0 a
r &U _ S T o _ T e p OC t . N NA - E M o s E e e g _ R v n I l a U a h O v D c E E R f ST d e EA e G i VU t N l LT a I e AC r t T R VA e n R / n e O y e m P t g h E e c R f e a a e t E S E s t U T n A O A e e ) I D n c e 7 N . o i e / U 1 N L S z 7 5 9 E 2 4 (
F. LICENSEE EVENT REPORTS - UNIT 1 The following is a tabular summary of all Licensee Event Reports submitted during the reporting period, July 1 through July 31, 1990. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73. Licensee Event Report Report Number DAlg Title of Occurrence 90-009 07-09-90 Failure to perform containment air lock leak test within the allowable time due to programmatic deficiency. (4957z/8)
I. Monthly Report for Braidwood Unit 2 , A. Summarv of Operatina Exoerience i Braidwood Unit 2 operated routinely in July with no ' outages or significant power -reductions. i r-t 1 l f k i (4957z/9)
, _ . ___ . m. , .. . . . . ., ,, - ..,4m
l B. '. OPERATING DATA REPORT DOCKET NO.: 50-457 UNIT: Braidwood 2 DATE: 08/10/90 ' COMPILED BY: K. M. Dundek TELEPHONE: (815)458-2801 ext. 2480 OPERATING STATUS
- 1. Reporting Period: July, 1990 Gross Hours: 744
- 2. Currently Authorized Power Level (MHt): 3411 Design Electrical Rating (MHe-gross): 1175 Design Electrical Rating (MHe-net): 1120
, Max Dependable Capacity (MHe-gross): 1175 Max Dependable Capacity (MHe-net): 1120
- 3. Power level to which restricted (If Any): None '
- 4. Reasons for restriction (If Any): None THIS MONTH YR TO DATE CUMULATIVE l
- 5. Report period Hours: 744 _.
5087 15658
- 6. Hours Reactor Critical: 744 3231 2 12366.5
- 7. RX Reserve Shutdown Hours: 0.0 0.0 0.0
- 8. Hours Generator on Line: 744 3177.4 1223]L2
- 9. Unit Reserve Shutdown Hours: 0.0 0.0 0.0
- 10. Gross Thermal Energy (MHH): 2415715 7723340 33564298
- 11. Gross Elec. Energy (MHH): 828611 -2594012 11485400
- 12. Net Elec. Energy (MHH): 797433 2446745- 10939720
- 13. Reactor Service Factor: 100 63.5 79.0
- 14. Reactor Availability Factor: 100 63.5 79.0
- 15. Unit Service Factor: 100 62.5 78.2 .
- 16. Unit Availability Factor: 100 62.5 78.2
- 17. Unit Capacity Factor (MDC net): 95.7 42.9 ______ 62.4
- 18. Unit Capacity Factor (DER net): 95.7 42.9 62.4 ;
- 19. Unit Forced Outage Rate: 0 4.4 4.8 l
- 20. Unit Forced Outage Hours: 0 __ 147.9 613.6 j
- 21. Shutdowns Scheouled Over Next 6 Months: None ;
- 22. If Shutdown at End of Report Period, Estimated Date of Startup: "
(4957z/10) l
i C. AVERAGE DAILY UNIT NET POWER LEVEL LOG DOCKET NO.: 50-457 UNIT: Braidwood 2 DATE: 08/10/90 COMPILED BY: K. M. Dundek TELEPHONE: (815)458-2801 ext. 2480 MONTH: July, 1990
- 1. 1059 17. __ 1111
- 2. 1007 18. 1056
- 3. 1104 19. 1091
- 4. 1118 20, 1103
- 5. 1112 21.- 1053 _
- 6. 1025 22. 1014 7, 1044 23. 1048 8, 1056 24, 1056
- 9. 1075 25, 1054
- 10. 1114 26, 1062
- 11. 1091 27. 1063 12, 1047 28. 1100
- 13. _1099 29, 1033
- 14. 1120 30, 1057 15, 1055 31, 1083 16, 1101 INSTRUCTIONS i On this form list the average daily unit power level in MHe-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. nom 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 1001,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. (4957z/11)
-l
D. UNIT SHUTD0HNS/ REDUCTIONS DOCKET NO.: 50-457 UNIT: Braidwood 2 .' ~ l DATE: 08/10/90 COMPILED BY: K. M. Dundek TELEPHONE: (815)458-2801 ext. 2480 REPORT PERIOD: July, 1990 i No . DAIE 11PE HOURS REASON M_FTHQQ T LER NUMBER iYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE None
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*S.UMMARY*
REASON METHOD SYSTEM & COMPONENT TYPE F-Forced A-Equipment Failure Maint or Test 1 - Manual Exhibit F & H S-Scheduled B-Maint or Test 2 - Manual Scram Instructions for Preparation of C-Refueling 3 - Auto Scram Data Entry Sheet D-Regulatory Restriction 4 - Continued Licensee Event Report E-Operator Training & License Examination 5 - Reduced Load (LER) File (NUREG-0161) F-Administration 9 - Other G-Oper Error H-Other (4957z/12)
E. UNIOUE REPORTING REOUIREMENTS - UNIT 2
- 1. Safety / Relief valve operations. 5 VALVES NO & TYPE PLANT DESCRIPTION DAIE ACTUATED ACTUATION CONDITIO_N 0F_ EVENT None
- 2. Licensee generated changes to 00CM.
See Attachment ) (4957z/13) 1
. -. . . , , , - - = . . - . , - . - . - . , . .- - _ - - _
F. LICENSEE EVENT REPORTS - UNIT 2 The following is a tabular summary of all Licensee Event Reports submitted during the reporting period, July 1 through July 31, 1990. This information,is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73. Licensee Event Report Regati_ Number QA11 Title of Occurrence 90-010 07-03-90 Reactor Trip during plant startup from low steam generator water level due to a malfunctioning bypass feedwater regulating valve. 1 (4957z/14)
ATTACHMENT Revisions to the Offsite Dose Calculation Manual (ODCM) are reportable to the NRC in accordance with this station's technical specifications. Braidwood Station's Radiological Environmental Monitoring Program (REMP) has been updated primarily to incorporate public drinking water sampling at H11mington. Table F-1 lists aquatic environmental parameters associated with this nearest community water supply and has been submitted to initiate changes to the computer program for calculating dose from radioactive effluent liquid discharges. Other minor changes were to reinstate the intake _and discharge cooling water sampling. Also, substitute a new vegetable sampling location in place of a former location because the necessary produce for vegetable sampling was no longer grown at this location. The changes do not reduce the accuracy and reliability of the setpoint determinations or model methodologi. (4957z/15)
a DwAP 1305-371 R0 visit 3 2 Braidwood On-site Review and Investigation Report OSR Number 90" # I
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Requested bys r b <lsau bs r w d W Y N h N tY v k0 k N Disciplines Requiredt 5 A Nuclear Power Plant Technology DR Reactor Operations A DC Reactor Engineering DD Chemistry EE Radiation Protection DF Instrume3tation and Control DG chanical and Electrical Systems Participantst Ye* b bPU bAutrit S Ott A 7 Ft. Awe 9 ev 22 A hi. 90 PU OSR Henbership Approve M 4 a L 1> a te/2f/99 Technicah It4df i Supervisor / bate 10CFR50.59 Safety Evaluation is Required? - - - - - - - - - - - Y/N M _ If yes, attach completed documentation in accordance with SWAP 1205-6. Concurrence Required by Offsite Review? (per Section C.10) - - - Y/N M Findings and Reconenendations:
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n . Approved by Yd STATION MANAGER DATE APPROVED (Final) 0130(020190) 1 MAY 0 31990 BW ,g,,ggggg
BRAIDM000 REVISION 0.A DECEMBER 1989 GG ERIC BRAION000 AM EX INDEX PAGE REVISIM CHAPTER 11 11-1 0.A 11-11 0.A 11-111 0.A 11-iv 0.A 11-1 0 11-2 0 11-3 0 11-4 0 11-5 0 11-6 0.A 11-7 0.A 11-8 0 11-9 0.A 11-10 0.A . 11-11 0 i 11-12 0.A ' 11-13 0 11-14 0 11-15 0 11-16 0 11-17 0.A i 4 11-1 ,
- - . . . . . . . . . . . . . , . . ~ . . - __- . - -_ ..__. , __
. . BRAIDWOOD REVISION 0.A !
DECEMBER 1989 : s t CHAPTER 11 ENVIROIBEEMTAL RADIOLOGICAL 900NITORING , TABLE OF CONTENTS {P h 11 ENVIRONMENTAL RADIOLOGICAL MONITORING 11-1 f
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BRAIDWOOD REVISION 0.A *
, DECEMBER 1989 CHAPTER-11 LIST OF TABLES.
NUMBER TITLE PAGE L,- t l 11-1 Environmental Radiological Monitoring Program 11-2 11-2 Reporting Levels for Radioactivity 't Concentrations in. Environmental Samples 11-11 ; 11-3. . Detection Cap 5bilities'for Environmental ~ Sample Analysis . 11-12 i l l l-11-111 t
.- , BRAIDWOOD REVISION-0.A.
DECEMBER 1989 i CHAPTER 11 , LIST-OF FIGURES i I NUMBER TITLE .PAGE i 11-1 Fixed Air Sampling Sites and Outer Ring TLD Locations 11-15 11-2 Inner Ring.TLD Locations' 11-16 11-3 Ingestion and Waterborne Exposure Pathway: Sample Locations '11-17 a I t r I f i 11-iv
BRAIDH000 REVISION 0.A ; DECEMBER'1989.' Table 11-1 (Cont'd) , Exposure Pathway Sampling or Type and Frequency-Samplina or Monitorina Locations a
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and/or Sample Collection Freauency of Analysis t , 2. Direct Radiation Contro11 i (Cont'd) _; Two sets of TLDs at each of the air- -
.l borne pathway control locations- i
- specified in Part 1 of this table.
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Minimum of 2 TLDs per set. i 3. Materbornee l a. Public Mater B0-22, Hilmington, 5.0 mi NME'(8.0 km B) Meekly Gross beta and gamma , 1sotopic analyses-monthly compostte.- ! Tritium analysis or quarterly compostte.- )
- b. Surface 80-07, Kankakee River. upstream of Heekly- Gamma isotopic discharge, 5.4 mi E (8.4 km E)' analysis on monthly- 'i composite from each i- 80-10. Kankakee River downstream of : location. -Tritium i discharge, 5.0 mi ENE (8.0 km D) analysis on-quarterly;
- composite from each _ ,
location.
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! c. Ground / Hell 80-13, Braidwood City Hall Hell, Biweeklyf Gross beta and gamma 1.7 mi NME (2.7 km B) isotopic analysis on monthly composite. Tritium analysis on-quarterly composite.
.I-131' analysis biweekly when the dosei calculated for i consumptionisgreater!
than 1 ares /yr. 11-6
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BRAIDN000 REVISION 0.,A - DECEMBER 1989 . Table 11-1 (Cont'd) Sampilng or- Type and Frequency Exposure Pathway a Collection Frecuency of Analysis and/or Sample Samnlina or Monitorina Locations .
-3. Materbornee (Cont'd) .
Coolina Mater 80-08, Intake Pipe No. 3, 5.0 mi E (8.0 km E) Neekly~ Gross beta analysis
- d. Neekly BD-09, Discharge Pipe No. 4, 5.0 ml E .,
(8.0 km E) B0-10, Kankakee River downstream of Semiannually Camma isotopic
- e. Shorelins analysis on each Sediments discharge, 5.0 mi ENE (8.0 km D) sample.
- 4. Incestione ,
Semimonthly: 'Nay to October Camma isotopic and-
- a. Ellk Indicators I-131 analysis ~on each Nonthly:-. November to Apri1 BD-11, Norris Farm, 2.4 mi-E (3.9 km E) -sample.
BD-17, Trotter's Dalry, 4.8 mi NN (7.7 km Q) Controls BD-18, Biros Farm, 10.5 mi M (16.9 km N). 80-07. Kankakee' River upstream of discharge,- Three times a year (spring, r - isotopic
- b. fish . summer, and fall) analysis on edible 5.4 mi.E (8.7 km E) portions.
BD-10, Kankakee River downstream of discharge -5.0 mi ENE (8.0 km D). 80-14, Pinnick Farm, 1.8 mi'N (2.9 km A) AnnuallyJ Gamma isotopic
- c. Veaetables analysis on edible BD-15, Girot Farm, 1.4 mi N-(2.2 km A)-
80-16, Clark Farm, 3.3 al ENE (5.5 km D) portions. 11-7
e _ . . . - . - . . . . .. - . _ _ _ . l REVISION 0 A --
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BRAIDH000 DECEMBER 1989 . Table 11-1'(Cont'd) Exposure Pathway Sampling or Type and Frequency; i and/or Samnie S = lina or Monitorina Locationsa Collection Freauency of Analysis ' i
- 5. Land Use Census (Cont'd) ,
- 2. 2 to 5 miles Annually during grazing season ' Enumeration by using
! referenced information from county agricul-tural agencies or other reliable sources.. .I
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- 3. At dairies listed in Item 4.a. Annually during grazing season Inquire'as to feeding practices: =;
- a. Pasture only.
L b. Feed;and chop F only. .. I c. Pasture and feed;
- if both, ask j farmer to estimate i fraction of food' l from pasture
i
.<25%,- 25-501, 50-751, er >75%.
i l 11-9 +
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BRAIDH00D REVISION 0.A . . DECEMBER 1989 , . , i Table 11-1 (Cont'd) . f ! Exposure Pathway Sampling or' Type and 7requency and/or Sample Samolina or Monitorina Locationsa Collection Freauency of A'alysis
- b. Nearest Resident In all 16 sectors up to 5 miles. Annually
-i a
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See Table D-16 for definitions of sector codes used with kilometer distances. b See Figure 11-1, " Fixed Air Sampling Sites and' Outer Ring TLD Locations." . c See Figure 11-2, " Inner Ring TLD Locations." d Perform gamma isotopic analysis on each sample when gross beta activity is greater. than (>) 10 times the yearly mean of '
^
control samples. ~
# See Figure 11-3, " Ingestion and Naterborne Exposure Pathway Sample Locations."
- f Stweekly means every.two weeks.
J i 11-10 l
BRAIDWOOD REVISION-0.A. '. ' DECEMBER 1989'i TABLE 11-3 Detection Capabilities for Environmental Sample Analysis. i Lower Limit of Detection (LLD)a Water Airborne Particulate Fish ~ Milk Food Products Sediment I Analysis (pCi/L) or Gases (pCi/m3) (pCi/kg, wet) (pCi/L) (pCi/kg, wet) (pCi/kg, dry)' Gross Beta 4 0.01 H-3 2000b t Mn-54 15 130 Fe-59 30 260 l Co-58,60 15 130 Zn-65 30 260 Zr-Nb 15 . I-131 1c 0.07. 3 .60 Cs-134 15 0.05 130 15 60 150-Cs-137 18 0.06 150 18 80 180 ; Ba-La-140 15 '15 11 'l _ - . . - , :-.- . _ . . , . . _ . - . . . = _ .-. ,_ _ _ _ , _ _
,': ., *. REVISION 0.A-. DECEMBER 1989 s D D
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Kankab.ee River Braidwood *
/$4 e 3 IL113 10
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- 16 e ,
6 Location it, !
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*--10.5 miles e,.. .i.uon eBraidwood ,,,
Station g
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Braceville g , V vO County Line Rd. s. Gardner I Essex F. 7 Rice Rd. T ; South Wilmington o Scale 3 0 1 2 3 4 5 Miles i . i e i e i 0 1 2 4 -6 8 10 Kilometers 0FFSITE DOSE CALCULATION MANUAL. BRAIDWOOD STATION FIGURE 113 INGESTION AND WATERBORNE EXPOSURE PATHWAY SAMPLE LOCATIONS - l-
- US[-395 11-17
BRAIDWOOD~ REVISION 0.A
. DECEMBER 1989 Table-F-1 Aquatic Environment Dose Parameters Water and Fish Incestion Parameters Parametera Value UW , water usage, L/hr 0.042 U,f fish consumption, kg/hr. 2.4E-3 1/MW, 1/Mf -
0.25, 1.0 FW, cfs 5.6323 i F,f cfs 5.63E3 tf, hrb 24 tW, hre 3 Limits on Radioactivity in Unorotected Outdoor Tanksd Primary Water Storage Tank 1 2000 Cie Outside Temporary Tank i 10 Cia (per Technical Specification 3.11.1.4) a The parameters are defined in Section A.2.1 of Appendix A. b tf (hr) = 24 hr (all stations) for the fish ingestion pathway ctW (hr) = 3 hr (distance to Wilmington is 4 river miles; flow rate of 1.4 mph assumed) d See Section A.2.4 of Appendix A. e Tritium and dissolved or entrained noble gases are excluded from this limit. F-2 l}}