SVP-99-179, Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With

Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With

ML20212B515
Person / Time
Site:	Quad Cities
Issue date:	08/31/1999
From:	Dimmette J, Hamilton L COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-97-02, SVP-99-179, NUDOCS 9909200127
Download: ML20212B515 (11)

Text

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Quad ( ines Generaung Nahon 22'10 36h Ast nue Nir1h n>ra,n a. sua 2 u r io ict ym,s 4 22 u September 13,1999 SVP-99-179 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Quad Cities Nuclear Pt wer 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 ~

August 1,1999, to August 31,1999.

Should you have any questions concerning this letter, please contact Mr. C.C. l Peterson at (309) 654-2241, extension 3609. )

Respectfully,

, mt Joel P. Dimmette, Jr. )

Site Vice President i Quad Cities Nuclear Power Station Attachment  ;

.cc: Regional Administrator- NRC Region lli

NRC Senior Resident inspector- Quad Cities Nuclear Power Station

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' ATTACHMENT QUAD CITIES NUCLEAR POWER STATION UNITS 1 AND 2 i

MONTHLY OPERATING REPORT {

COMMONWEALTH EDISON COMPANY AND 1

MIDAMERICAN ENERGY COMPANY l

FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 NRC DOCKET NOS. 50-254 AND 50-265 l

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TABLE OF CONTENTS

1. Introduction ll. Summary of Operating Experience A. Unit One B. Unit Two Ill. Operating Data Statistics A. Operating Data Report for August- Quad Cities Unit One B. Operating Data Report for August - Quad Cities Unit Two IV. Unit Shutdowns l A. Unit One Shutdowns B. Unit Two Shutdowns l

V. Amendments to Facility License or Technical Specifications l

VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations l

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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 sebject 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. j 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 309-054-2241, extensions 3114 and 2240, respectively, TECHOP3iNRCWLY99 DOC J

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SUMMARY

OF OPERATING EXPERIENCE A. Unit One Quad Cities Unit One began the month of August operating at full power. Unit One operated throughout 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 August 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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1;f PPERATING DATA STATISTICS A. Unit One Operating Data Report for August 1999 DOCKET NO.: 50-254 DATE: September 13,1999 COMPLETED BY: Lynne Hamilton TELEPHONE: (309) 654-2241 OPERATING STATUS 0000 080199

1. REPORTING PERIOD: 2400 083199 GROSS HOURS IN REPORTING PERIOD: 744

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 744.00 5316.60 182113.30

4. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90

5. HOURS GENERATOR ON LINE 744.00 5281.20 176876.60

6. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

7. GROSS THERMAL ENERGY GENERATED (MWH) 1854565.20 13117805.76 388866300.36 598743.00 4265731.00 125823074.00 I

8. GROSS ELECTRICAL ENERGY GENERATED (MWH)

9. NET ELECTRICAL ENERGY GENERATED (MWH) 570488.00 4065187.00 113363040.00

10. REACTOR SERVICE FACTOR 100.00 91.18 75.86

11. REACTOR AVAILABILITY FACTOR 100.00 91.18 77.28

12. UNIT SERVICE FACTOR 100.00 90.57 73.68

13. UNIT AVAILABILITY FACTOR 100.00 90.57 74.06 14, UNIT CAPACITY FACTOR (Using MDC) 99.71 90.66 61.41

15. UNIT CAPACITY FACTOR (Using Design Mwe) 97.18 88.36 59.85

16. UNIT FORCED OUTAGE RATE 0.00 0.00 6.89 l

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Ill. OPERATING DATA STATISTICS B. Unit Two Operating Data Report for August 1999 DOCKET NO.: 50-265 DATE: September 13,1999 COMPLETED BY: Lynne Hamilton TELEPHONE: (309) 654-2241 OPERATING STATUS 0000 080199

1. REPORTING PERIOD: 2400 083199 GROSS HOURS IN REPORTING PERIOD: 744

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 744.00 5632.80 *175299.40

4. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80

5. HOURS GENERATOR ON LINE 744.00 5608.30 170675.05

6. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

7. GROSS THERMAL ENERGY GENERATED (MWH) 1853652.96 13995550.80 374835633.66

8. GROSS ELECTRICAL ENERGY GENERATED (MWH) 595031.00 4513482.00 120262612.00

9. NET ELECTRICAL ENERGY GENERATED (MWH) 571493.00 4340412.00 114107456.00

10. REACTOR SERVICE FACTOR 100.00 96.60 73.50

11. REACTOR AVAILABILITY FACTOR 100.00 96.60 74.75

12. UNIT SERVICE FACTOR 100.00 96.18 71.56

13. UNIT AVAILABILITY FACTOR 100.00 96.18 71.85 l

14. UNIT CAPACITY FACTOR (Using MDC) 99.89 96.80 62.21

15. UNIT CAPACITY FACTOR (Using Design Mwe) 97.36 94.34 60.64

16. UNIT FORCED OUTAGE RATE 0.00 0.00 10.65

' June of 1997 Reactor Critical hours was found to be in error. Therefore,69.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> has been added to the cumulative number of reactor critical hours, l

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1% UNIT SHUTDOWNS l

A. Unit One Shutdowns fOr August 1999 l

DOCKET NO.: 50-254 DATE: September 13,1999 COMPLETED BY: Lynne Hamilton TELEPHONE: (309) 654-2241 No. DATE TYPE DURATION REASO METHOD OF CORRECTIVE l

F OR (HOURS) N SHUTTING ACTIONS / COMMENTS S DOWN REACTOR None for the Month of August.

Legend:

(1) Reason A- Equipment Failure (Explain)

' B - Maintenance or Test i

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

H - Other (Explain)

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

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IV. UNIT SHUTDOWNS B. Unit TwO Shutdowns for August 1999 DOCKET NO.: 50-265 DATE: September 13,1999 COMPLETED BY: Lynne Hamilton TELEPHONE: (309)654-2241 No. DATE TYPE DURATION REASO METHOD OF CORRECTIVE F OR S (HOURS) N SHUTTING ACTIONS / COMMENTS DOWN REACTOR f None for the Month of August.

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l Legend; (1) Reason A- Equipment 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 Tnp/ Scram 4 - Continuation 5 - Other (Explain) l l

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V. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS Technical Specification Amendment No.189 was issued on August 4,1999 to Facility Operating License No. DPR-29 and Amendment No.186 to Facility Operating License No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively.

The amendments revise the Technical Specifications, Section 3/4.6.G " Leakage Detection Systems," to allow an alternate methodology for quantifying Reactor Coolant System (RCS) leakage when the normal RCS leakage detection system is inoperable. )

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VJ. 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 Ooerations There were no Relief Valve Operations during the reporting period.

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