ML20248J129

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Monthly Operating Repts for Sept 1989 for Braidwood Nuclear Power Station Units 1 & 2
ML20248J129
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 09/30/1989
From: Peterson M, Querio R
GULF STATES UTILITIES CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BW-89-1175, NUDOCS 8910130058
Download: ML20248J129 (16)
v • d • e


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October 6,1989 BW/89-1175 Director, Office of Resource Menagement

. United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the Monthly Performance Report covering Braidwood Nuclear Power Station for the period September 1 through September 30,1989.

Very truly yours, fR.Station E. Qued Manager Braidwood Nuclear Station REQ /EWC/sjs (4957z)

Attachments cc: A. B. Davis, NRC, Region III NRC Resident Inspector Braidwood Ill. Dept. of Nuclear Safety T. J. Maiman K. L. Graesser T. J. Kovach Nuclear Fuel Services, PWR Plant Support INPO Records Center Performance Monitoring Group, Tech Staff Braidwood Station Nuclear Group, Tech Staff Braidwood Station S. Sands - USNRC S. C. Hunsader l Production Services l

I 8910130058 890930 ' {i '

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BRAIDH00D NUCLEAR POWER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT COMMONWEALTH EDIS0N COMPANY NRC DOCKET NO. 050-456, LICENSE NO. NPF-72 NRC DOCKET NO. 050-457, LICENSE NO. NPF-77

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I. Monthly Report for'Braidwood Unit 1 A.- Summary of Ooeratino Experience The. unit entered the' month ~of September at approximately 47% power. The unit was in an extended coastdown'as it approached the refueling outage. The refueling outage began on September 2,1989 and-the unit remained off line the remainder of the month.

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! (4957z/3)

r . 13 7 -OPERATING DATA REPORT DOCKET NO.: 50-456 L '

UNIT: Braidwood 1 DATE: 10/06/89 D COMPILED BY: M. H. Peterson TELEPHONE: (815)458-2801 H ext. 2480 OPERATING STATUS

1. Reporting Period: September, 1989 Gross Hours: 720.0
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 (MWe-net): 1120
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: 720 6551 _10280
6. - Hours Reactor Critical.: 26.0 5103,3 8613.7
7. RX Reserve Shutdown Hours: 0.0 0.0 0.0
8. Hours Generator on Line: 24.2 5049.4 8460.8
9. Unit Reserve Shutdown Hours: 0.0 0.0 0.0
10. Gross-Thermal Energy (MHH): 36341 13574109 23944571-
11. Gross Elec. Energy (MHH): 10618 4602099 8191063
12. Net Elec. Energy (MHH): 1557 43767D3_ 7800927
13. Reactor Service Factor: 3.6 77.9 83.8
14. Reactor Availability Factor: 3.6 77.9 83.8
15. Unit Service Factor: 3.4 77.1 82.3
16. Unit Availability Factor: 3.4 77.1 82.3
17. Unit Capacity Factor (MDC net): 0.2 59.7 67.8
18. Unit Capacity Factor (DER net): 0.2 59.7 _ 67.8
19. Unit Forced Outage Rate: 0.0 3.5 5.6
20. Unit Forced Outage Hours: 0.0 182.3 500.3
21. Shutdowns Scheduled Over Next 6 Months: - Refueling Outage September 1989
22. If Shutdown at End of Report Period, Estimated Date of Startup: November 29. 1989 (4957z/4)

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4 LC., ' AVERAGE DAILY UNIT NET POWER LEVEL LOG DOCKET NO.: 50-456 4 UNIT: Braidwood-1 DATE: 10/06/89 -j COMPILED BY: M. W. Peterson i TELEPHONE: (815)458-2801 ext. 2480 MONTH: September, 1989

1. 407 17. -11
2. -11 18. -11
3. . -13 19. -11
4. -13 20. -11 -!
5. -11 21. -11
6. -11 22. -11
7. -12' 23. -11
8. -20 24. -11
9. -19 25. -11
10. -11 26. -11
11. -10 27. -11
12. -10 28. -11
13. -10 29. -11

.14. . -10 30. -10

15. -11 l
16. -11 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 E

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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F. LJCENSEE EVENT REPORTS - UNIT 1 The following is a tabular summary of all Licensee Event Reports submitted during the reporting period, September 1 through September 30, 1989. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73.

Licensee Event Renort Report Number DAlg Title of Occurrence 89-007 09-01-89 Containment ventilation Isolation Actuation signal due to failed HVPS in Fuel Handling Incident Rad Monitor.

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(4957z/8) ,

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LI. Monthly Report for Braidwood Unit 2

' < A. ' Summarv of Operatina Experience l-The' unit entered the month of September at full power. 'On September 7,1989 at 2033 a lightning strike tripped the

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unit. .The unit was brought back on-line on September 9, 1989. 'The unit. continued power operation through the end u of the month.

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(4957z/9)

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~ Bl. OPERATING DATA REPORT DOCKET NO.: 50-457 UNIT: Braidwood 2 DATE: 10/06/89 COMPILED BY: M. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 OPERATING STATUS

1. Reporting Period: September, 1989 Gross Hours: 720.0
2. Currently Authorized Power Level (MHt): 3411 Design Electrical Rating (MHe-gross): 1175 Design Electrical Rating (MHe-net): 1120 Max Dependable Capacity (MWe-gross): 1175 Max Dependable Capacity (MWe-net): 1120
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: 720 6551 8362
6. Hours Reactor Critical: 676.8 5409.1 6926.3
7. RX Reserve Shutdown Hours: ,

0.0 0.0 0.0

8. Hours Generator on Line: 672.2 5374.4 6851.8
9. Unit Reserve Shutdown Hours: 0.0 0.0 0.0
10. Gross Thermal Energy (MWH): 1908625 14804887 18882505
11. Gross Elec. Energy (MWH): 651484 4853111 6486675
12. Net Elec. Energy (MWH): 625009 4826636 6177576
13. Reactor Service Factor: 94 82.6 82.8
14. Reactor Availability Factor: 94 82.6 82.8
15. Unit Service Factor: 93.4 82.0 81.9
16. Unit Availability Factor: 93.4 82.0 81.9
17. Unit Capacity Factor (MDC net): 77.5 65.8 66.0
18. Unit Capacity Factor (DER net): 77.5 65.8 66.0
19. Unit Forced Outage Rate: 6.6 2.4 6.4
20. Unit Forced Outage Hours: 47.8 152.1 465.7
21. Shutdowns Scheduled Over Next 6 Months: Refueling Outage March,1990
22. If Shutdown at End of Report Period, Estimated Date of Startup:

(4957z/10)

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C. AVERAGE DAILY UNIT NET P0HER LEVEL LOG DOCKET NO.: 50-457 UNIT: Braidwood 2 DATE: 10/06/89 COMPILED BY: M. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 MONTH: September, 1989

1. *1125 17. 1007 k
2. 625 18. 1110 1
3. 545 19. 1015
4. 545 20. 1010
5. 887 21. 1045
6. 957 22. 1054
7. 834 23, 1029
8. -20 24. 746
9. 15 25. 1037
10. 284 26, 1022
11. 805 27, 1038
12. 1038 28. 1039
13. *1148 29. 1053
14. 998 30. 1011
15. 1022
16. 1004 I INSTRUCTIONS 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.

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.

  • Due to Condenser Efficiencies (4957z/11) l

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F. LICENSEE EVENT REPORTS - UNIL2 The following is a tabular summary of all Licensee Event. Reports submitted during the reporting period, September 1 through September 30, 1989. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73.

Licensee Event Reoort Reoort Number Data Title of Occurrence None i

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l (4957z/14) l

4 ATTACHMENT Revisions to the Offsite Dose Calculation Manual (DDCH) are reportable to the NRC in accordance with stations' technical specifications. The document contains the models for the public dose assessment from gaseous effluents,-

liquid discharges, and direct radiation. In 1988, in response to the NRC's request to make the ODCH a more readable document as well as to incorporate certain changes, Commonwealth Edison rewrote its ODCH. This document, renumbered to Revision 0, March, 1989, will be submitted under separate cover. This summary describes the principal non-edited changes.

MAJOR CHANGES The NRC, in NuReg 0472, Rev. 3 Draft 7, has identified the child's thyroid and not the infant's as the most sensitive organ from the inhalation of airborne effluents. Dresden, LaSalle, and Quad Cities Stations' 10CFR20 instantaneous-release rate limits have been revised to restrict the dose rate to the child's thyroid to less or equal to 1500 mrem /yr.

Hydrogen addition to the primary coolant increases the boiling water reactors' turbine N-16 shyshine by a magnitude of 5. This phenomenon is now included in the ODCM formulation. In addition the sky shine calculation is written for LaSalle County Station as well as revised in Dresden and Quad Cities.

MINOR. CHANGES Most of the ODCM documentation has been either clarified, corrected or deleted.

Plume depletion, terrain factors and heat content were not accounted for in the original for D/0, X/Q and plume rise calculations. They are described in the revised document.

It was implied that the X/Q dose factors were calculated assuming a mono-energetic gamma energy having an average gamma ray energy per disintegration for each radionuclides. Also, it was assumed that the corrected tissue absorptions were made using a tissue energy absorption coefficient equivalent to this same average gamma ray energy for each radionuclides. Actually, the dose factors and the tissue energy absorption coefficients referenced were calculated using the photon energy spectra for each radionuclides. The tissue energy absorptions coefficients are negligible and have been deleted from the text.

Formulas and parameters for determining the maximum permissible concentrations (HPC's) have been eliminated from the section on radioactivity in storage tanks. The maximum limits, in curies, are found in the site specific sections.

8076E/3

_ - _ _ - _ _ .-_ . _ _ _ _ - _ - _ _ _ - _ _ - _ _ - = _ _ _ _ _ _ _ _ _ . - - _ _ _ _

. ,. ATTACHMENT s '

(Cont.)

The potential direct radiation dose from stations' interim radwaste storage facilities is discussed.- The radwaste containers will have a contact dose rate-of 5 R/hr and the expected radiation levels will be minimal at the site boundary.

The distance dependent parameters were adjusted to the values reported in the

'88-census for nearest residents and/or nearest milch animal. This also affected the D/0 tables and BWR turbine N-16 shyshine calculation.

The time of travel from the station liquid discharge to the nearest community water supply was reevaluated for Eraidwood and Quad Cities.

ODCH Revision 0, March 1989 has received approvals by all.six onsite review committees and the CECO offsite review per the Technical Specifications.

Changes to the ODCH computer program required by this document are in the process of being implemented now and should be fully available by November 1, 1989.

1 8076E/4 1

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