SVP-98-346, Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With

Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With

ML20195F489
Person / Time
Site:	Quad Cities
Issue date:	10/31/1998
From:	Dimmette J, Hamilton L COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
SVP-98-346, NUDOCS 9811200010
Download: ML20195F489 (11)

Text

l Commonwealth lihmn Gimpany

. Quad Otles Generating $tation I

• 22710 2Mith Avenue North Cordova, 11.61212 9?40 Tri 309642211 l l

l SVP-98-346 November 13,1998 i 1

- U.S. Nuclear Regulatory Commission  !

Washington, DC 20555 I Attention: Document Control Desk

Subject:

Quad Cities Nuclear Power Station, Units 1 and 2 Monthly Performance Report ,

Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265 Enclosed for your information is the Monthly Performance Report covering the operation j of Quad Cities Nuclear Power Station, Units One and Two, during the month of j October 1998.

l If you have any questions or comments concerning this letter, please refer them to Mr. Charles Peterson, Regulatory Assurance Manager, at (309) 654-2241, extension 3609.

1 Sincer y, l n

All auwsfA%

cel P. Dimmette, Jr. /

Site Vice President Quad Cities Station Enclosure cc: Acting Regional Administrator, Region 111 7 i Senior Resident inspector, Quad Cities bM/ l 9811200010 981051 PDR ADOCK 05000254 R PM ,

i A Unicum Q)mpany l

6 9 QUAD CITIES NUCLEAR POWER STATION P

UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT OCTOBER 1998 COMMONWEALTH EDISON COMPANY AND MIDAMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 TECHOP3WRCumV8 DOC

TABLE OF CONTENTS

1. Introduction II. Summary of Operating Experience A. - Unit One B. Unit Two III. Operating Data Statistics A. Operating Data Report for October - Quad Cities Unit One B. Operating Data Report for. October- Quad Cities Unit Two IV. Unit Shutdowns A. Unit One Shutdowns B. Unit Two Shutdowns V. Amendments to Facility License or Technical Specifications VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations 2-

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1. INTRODUCTION Quad Cities Nuclear Power Station is composed of two Boiling Water Reactors and Steam Turbine / Generators, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station isjointly owned by Commonwealth Edison Company and MidAmerican Energy Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary constmetion contractor was United Engineers & Constmetors. The Mississippi River is the condenser cooling water source. The plant is subject to license numbers DPR-29 and DPR-30, issued October 1,1971, and March 21,1972, respectively; pursuant to Docket Numbers 50-254 and 50-265. The date ofinitial Reactor criticalities for Units One and Two, respectively were October 18,1971, and April 26,1972. Commercial generation of power began on February 18,1973 for Unit One and March 10,1973 for Unit Two.

This report was compiled by Lynne llamilton and Debra Kelley, telephone number 309-654-2241, extensions 3114 and 2240, respectively.

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l II. S_UMMARY OF OPERATING EXPERIENCE A. IJnit One Quad Cities Unit One began the month of October off-line due to the reactor scram in September. On October 1,1998, at 6:12 p.m., the reactor went critical. On October 2, 1998, at 3:40 a.m., the generator was synchronized to the grid. Unit One operated throughout the remainder of the month near full power with minor down power operations for routine maintenance and surveillance testing.

i B. Unit Two Quad Cities Unit Two began the month of October operating at full power. On October  ;

2, Unit Two power level was reduced to 88% power due to Feedwater Regulating Valve problems and on October 3, full power was achieved. On October 8,1998, at I 8:19 a.m., the generator was taken off-line followed by a reactor shutdown at 9:09 a.m.

for a forced outage to replace the 2B Recirculation Pump seal. On October 10,1998, ,

stanup activities commenced and the reactor went critical at 11:20 p.m. On October 11, 1 1998, at 10:39 a.m the generator was synchronized to the grid and full power was l achieved shortly thereatler. For the remainder of the month, Unit Two operated at full l power with minor down power operations for routine maintenance and surveillance testing. 1 4

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Ill. OPERATING DATA STATISTICS A. Unit One Operating Data Report for October 1998 DOCKET NO.: 50-254 DATE: November 10,1998 COMPLETED BY: Lynne Hamilton TELEPHONE: (309) 654-2241 OPERATING STATUS 0000 100198

1. REPORTING PERIOD: 2400 103198 GROSS IlOURS IN REPORTING PERIOD: 745

2. CURRENTLY AUTilORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACITY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789 TIIIS MONTil YEAR TO DATE CUMULATIVE

3. NUMBER OF HOURS REACTOR WAS CRITICAL 726.80 3607.30 175982.70

4. REACTOR RESERVE SHUTDOWN llOURS 0.00 0.00 3421.90

5. HOURS GENERATOR ON LINE 717.30 3513.90 170809.20

6. UNIT RESERVE SilUTDOWN HOURS 0.00 0.00 909.20

7. GROSS THERMAL ENERGY GENERATED (MWil) 1763297.76 8473373.76 373910616.36

8. GROSS ELECTRICAL ENERGY GENERATED (MWH) 573107.00 2704193.00 120957562.00

9. NET ELECTRICAL ENERGY GENERATED (MWH) 546663.00 2575796.00 108730765.00

10. REACTOR SERVICE FACTOR 97.56 49.44 75.60

11. REAC'IT)R AVAILABILITY FACTOR 97.56 49.44 77.07

12. UNIT SERVICE FACTOR 96.28 48.16 73.38

13. UNIT AVAILABILITY FACTOR 96.28 48.16 73.77

14. UNIT CAPACITY FACTOR (Using MDC) 95.42 45.91 60.74

15. UNIT CAPACITY FACTOR (Using Design Mwe) 93.00 44.75 59.20 l

16. UNIT FORCED OUTAGE RATE 3.72 0.03 7.12 i

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Ill. OPERATING DATA STATISTICS B. Unit Two Operating Data Report for October 1998 DOCKET NO.: 50-265 DATE: November 10,1998 COMPLETED BY: Lynne Hamilton TELEPHONE: (309) 654-2241 OPERATING STATUS 0000 100198

1. REPORTING PERIOD: 2400 103198 GROSS IlOURS IN REPORTING PERIOD: 745

2. CURRENTLY AUTilORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACITY: 769 DESIGN ELECTRICAL RATING (MWoNET): 789 Tills MONT11 YEAR TO DATE CUMULATIVE

3. NUMBER OF llOURS REACTOR WAS CRITICAL 682.80 3766.05 168133.10

4. REACTOR RESERVE SilUTDOWN HOURS 0.00 0.00 2985.80

5. HOURS GENERATOR ON LINE 670.70 3636.30 163606.15

6. UNIT RESERVE SilUTDOWN HOURS 0.00 0.00 702.90

7. GROSS THERMAL ENERGY GENERATED (MWil) 1646970.00 8822010.00 357178266.32

8. GROSS ELECTRICAL ENERGY GENERATED (MWil) 534915.00 2795140.00 114557684.00

9. NET ELECTRICAL ENERGY GENERATED (MWH) 512661.00 2672935.00 108620393.00

10. REACTOR SERVICE FACTOR 91.65 51.62 72.72

11. REACTOR AVAILABILITY FACTOR 91.65 51.62 74.01

12. UNIT SERVICE FACTOR 90.03 49.84 70.76

13. UNIT AVAILABILITY FACTOR 90.03 49.84 71.06

14. UNIT CAPACITY FACTOR (Using MDC) 89.48 47.64 61.09

15. UNIT CAPACITY FACTOR (Using Design Mwe) 87.22 46.43 59.54

16. UNIT FORCED OUTAGE RATE 9.97 4.67 11.05 l

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IV. UNIT SHUTDOWNS A. Unit One Shutdowns for October 1998 DOCKET NO.: 50-254  ;

l DATE: November 10,1998

! COMPLETED BY: Lynne Hamilton TELEPHONE: (309) 654-2241 No. DATE TYPE DURATION REASON METilOD OF CORRECTIVE FOR (IIOUdS) SilUTTING ACTIONS / COMMENTS S DOWN REACTOR 98-08 981001 F 27.7 G 4 LER 1-98-022 Reactor Scram on Low Water Level due to incorrectly valving out flow transmitter on I A Reactor Feed Pump _ j Legend:

(1) Reason A - Equipment Failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory Restriction E - Operator Training / License Examination

. F - Administrative 0 - Operational Error (Explain)

H - Other (Explain)

(2) Method 1 - Manual 2 - Manual Trip / Scram 3 - Automatic Trip / Scram 4 - Continuation 5 - Other (Explain) l' J

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IV. UNIT SHUTDOWNS B. Unit Two Shutdowns for October 1998 DOCKET NO.: 50-265 DATE: November 10,1998 COMPLETED BY: Lynne Hamilton -

TELEPHONE: (309) 654-2241 No. DATE TYPE DURATION REASON METilOD OF CORRECTIVE FORS (IlOURS) SIIUTTING ACTIONS /COM\ TENTS DOWN REACTOR 98 G 981008 F 74.3 8 2 Replace 2B Reactor Recire Pump Seal Legend:

(1) Reason A - Equipment Failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory Rentriction E - Operator Training /Lleense Examination F - Administrative G - Operational Ermr (Explain)

H - Other (Explain)

(2) Method 1 - Manual 2 - Manual Trip / Scram 3 - Automatic Trip /Seram 4 - Continuation

$ - Other (Explain)

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l V. Amendments to Facility License or Technical Specifications  :

Technical Specification Amendment No.181 was issued on October 8,1998 to Facility Operating License DPR-29 and Amendment No 179 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station.

The amendments will change several Technical Specification (TS) values to reflect design values. These TS values affect (1) 125/250 volts direct current (Vdc) electrolyte temperature; (2) control rod drive accumulator pressure; (3) standby liquid control solution temperature; (4) ultimate heat sink minimum water level; (5) shutdown suppression chamber level; and (6) a degraded voltage setpoint.

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.,';.,'. s VI. UNIOUE RIiPORTING REOUIREMENTS The following items are included in this report based on the requirements set forth in Technical Specification 6.9. A.5.

A. Main Steam Relief Valve Operations There were no Relief Valve Operations during the reporting period.

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