SVP-99-148, Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With

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Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With
ML20209H467
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 06/30/1999
From: Dimmette J, Hamilton L
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
SVP-99-148, NUDOCS 9907200231
Download: ML20209H467 (10)
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,. Quad Citics Generating 5tation 2T10 Jf K,th As enue North coram a. it. (,i 2 mmo Tel 509 6%224 i I July 13,1999 SVP-99-148 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Monthly Operating Report in accordance with Generic Letter 97-02 and Technical Specification 6.9.5,

" Monthly Operating Reports," we are submitting the Monthly Operating Report for Quad Cities Nuclear Power Station, Units 1 and 2. This report covers the period June 1,1999, to June 30,1999.

Should you have any questions concerning this letter, please contact Mr. Chuck Peterson, Regulatory Assurance Manager, at (309) 654-2241 extension 3609.

Respe tfully,

/ vn M ..

Joel P. Dimmette, Jr. /

Site Vice President Quad Cities Nuclear Power Station Attachment ec: Regional Administrator- NRC Region lli NRC Senior Resident inspector- Quad Cities Nuclear Power Station  ;

'h 9907200231 990630 PDR ADOCK 05000254 /

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e e ATTACHMENT i

QUAD CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT COMMONWEALTH EDISON COMPANY AND MIDAMERICAN ENERGY COMPANY FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 NRC DOCKET NOS. 50-254 AND 50-265 i

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TABLE OF CONTENTS

1. - Introduction
11. Summary of Operating Experience A. Unit One -

B. Unit Two Ill. Operating Data Statistics A. Operating Data Report for June - Quad Cities Unit One B. Operating Data Report for June - Quad Cities Unit Two IV. Unit Shutdowns A. Unit One Shutdowns B. Unit Two Shutdowns l

V. Amendments t6 Facility License or Technical Specifications VI. Unique Reporting Requirements i

A. Main Steam Relief Valve Operations I

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l. 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 is jointly 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 construction contractor was United Engineers & Constructors. 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 of initial 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 Hamilton and Debra Kelley, telephone number 309-654-2241, extensions 3114 and 2240, respectively.

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II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One Quad Cities Unit One began the month of June operating at full power. On June 15,1999 a load drop occurred due to 1 A Feedwater Reg Valve Servo problems. The servo valve was replaced, and full power was achieved at 8:20 p.m. on June 16,1999. Unit One operated throughout the remainder of the month at full power with minor down power operations for routine maintenance and surveillance testing.

B. Unit Two Quad Cities Unit Two began the month of June operating at full power. Unit Two operated throughout the month at full power with minor down power operations for routine maintenance and surveillance testing.

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Ill. OPERATING DATA STATISTICS ,

A. Unit One Operating Data Report for June 1999 I

DOCKET NO.: 50-254 DATE: July 13,1999 COMPLETED BY: Lynne Hamilton TELEPHONE: (309)654-2241

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OPERATING STATUS l 0000 060199 1

1. REPORTING PERIOD: 2400 063099 GROSS HOURS IN REPORTING PERIOD: 720
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACITY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789 THIS MONTH YEAR TO DATE CUMULATIVE
3. NUMBER OF HOURS REACTOR WAS CRITICAL 720.00 3828.60 180625.30
4. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90
5. HOURS GENERATOR ON LINE 720.00 3793.20 175388.60
6. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20
7. GROSS THERMAL ENERGY GENERATED (MWH) 1782048.96 9412014.96 385160509.56
8. GROSS ELECTRICAL ENERGY GENERATED (MWH) 576725.00 3070537.00 124627880.00
9. NET ELECTRICAL ENERGY GENERATED (MWH) 549624.00 2926681.00 112224534.00
10. REACTOR SERVICE FACTOR 100.00 88.16 75.71
11. REACTOR AVAILABILITY FACTOR 100.00 88.16 77.14
12. UNIT SERVICE FACTOR 100.00 87.34 73.51
13. UNIT AVAILABILITY FACTOR 100.00 87.34 73.89 j
14. UNIT CAPACITY FACTOR (Using MDC) 99.27 87.63 61.17 l
15. UNIT CAPACITY FACTOR (Using Design Mwe) 96.75 85.41 59.62
16. UNIT FORCED OUTAGE RATE 0.00 0.00 6.95 l I

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9 Ill. OPERATING DATA STATISTICS B. Unit Two Operating Data Report for June 1999 DOCKET NO.: 50-265 DATE: July 13,1999 COMPLETED BY: Lynne Hamilton TELEPHONE: (309) 654-2241 OPERATING STATUS 0000 060199 i, REPORTING PERIOD: 2400 063099 GROSS HOURS IN REPORTING PERIOD: 720

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACITY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789 THIS MONTH YEAR TO DATE CUMULATIVE
3. NUMBER OF HOURS REACTOR WAS CRITICAL 720.00 4144.80 173741.90
4. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80
5. HOURS GENERATOR ON LINE 720.00 4120.30 169187.05 T UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 702.90
7. GROSS THERMAL ENERGY GENERATED (MWH) 1798035.12 10279784.40 371119867.26
8. GROSS ELECTRICAL ENERGY GENERATED (MWH) 576281.00 3326045.00 119075175.00
9. NET ELECTRICAL ENERGY GENERATED (MWH) 553404.00 3200242.00 112967286.00
10. REACTOR SERVICE FACTOR 100.00 95.44 73.30
11. REACTOR AVAILABILITY FACTOR 100.00 95.44 74.56
12. UNIT SERVICE FACTOR 100.00 94.87 71.38
13. UNIT AVAILABILITY FACTOR 100.00 94.87 71.68
14. UNIT CAPACITY FACTOR (Using MDC) 99.97 95.82 61.98
15. UNIT CAPACITY FACTOR (Using Design Mwe) 97.43 93.39 60.41
16. UNIT FORCF.D OUTAGE RATE 0.00 0.00 10.73 l

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IV. UNIT SHUTDOWNS A. Unit One Shutdowns for June 1999 ,

DOCKET NO.: 50-254 DATE: July 13,1999 COMPLETED BY: Lynne Hamilton i

TELEPHONE: (309) 654-2241 1 No. DATE TYPE DURATION REASO METHOD OF CORRECTIVE F OR (HOURS) N SHUTTING ACTIONS / COMMENTS S DOWN REACTOR None for the Month of June.

Legend:

(1) Reason.

A - Equipmei.t Failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory Restriction E - Operator Training / License Examination F - Administrative G - Operational Error (Explain)

H - Other (Explain)

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

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IV. UNIT SHUTDOWNS B. Unit TWO Shutdowns for June 1999 DOCKET NO.: 50-265 DATE: July 13,1999  !

COMPLETED BY: Lynne Hamilton l TELEPHONE: (309) 654-2241  !

No. DATE TYPE DURATION REASO METHOD OF CORRECTIVE F OR S (HOURS) N SHUTTING ACTIONS / COMMENTS l DOWN j REACTOR I None for the Month of June, 1

1 Legend:

(1) Reason A - Equipment Failure (Explain)

B - Maintenance or rest C - Refueling D - Regulatory Restriction E - Operator Training / License Examination F - Administrative G - Operational Error (Explain)

H - Other (Explain)

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

)

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V. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS Technical Specification Amendment No.188 was issued on June 25,1999 to Facility Operating License No. DPR-29 and Amendment No.185 to Facility Operating License No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively.

The amendments revise license conditions in each of the respective operating licenses to delete those license conditions that no longer apply, make an editorial change in the Unit 1 license, and provide clarifying information regarding the license condition in each license conceming equalizer valve restrictions.

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VI. UNIQUE REPORTING REQUIREMENTS 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 l

There were no Relief Valve Operations during the reporting period.

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