SVP-99-071, Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With

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

ML20205P938
Person / Time
Site:	Quad Cities
Issue date:	03/31/1999
From:	Dimmette J, Hamilton L COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-97-02, GL-97-2, SVP-99-071, SVP-99-71, NUDOCS 9904210039
Download: ML20205P938 (11)

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April 12,1999 U.S. Nuclear Regulatory Commission l ATTN: Document Control Desk l Washington, DC 20555 l l

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 Performance Report In accordance with NRC Generic Letter 97-02, and Technical Specification Section 6.9, l we are forwarding the Monthly Performance Report covering the operation of Quad i Cities Nuclear Power Station, Units One and Two, during the month of March 1999.

Should you have any questions concerning this letter, please contact Mr. Wally Beck, Aedng Regulatory Assurance Manager, at (309) 654-2241, extension 3100.

Respectfully, af) HYwd'

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Joel P. Dimmette, .  ;

Site Vice Preside Quad Cities Nuclear Power Station j

Enclosure cc: Regional Administrator - NRC Region ill NRC Senior Resident Inspector - Quad Cities Nuclear Power Station fbb

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9904210039990bi  !

PDR ADOCK 05000254 R PDR m A Umcom o>mpan>

l , e QUAD CITIES NUCLEAR POWER STATION' UNilS 1 AND 2 MONTHLY PERFORMANCE REPORT MARCH 1999 COMMONWEALTH EDISON COMPANY AND j MIDAMERICAN ENERGY COMPANY I

NRC DOCKET NOS. 50-254 AND 50-265 i

LICENSE NOS. DPR-29 AND DPR-30 4.

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• 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 March - Quad Cities Unit One B. Operating Data Report for March - Quad Cities Unit Two i

IV. Unit Shutdowns A. Unit One Shutdowns B. Unit Two Shutdowns I

V. Amendments to Facility License or Technical Specifications

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1 VI. Unique Reporting Requirements

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A. Main Steam Relief Valve Operations l

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g i I. 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 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 , i i '1, 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 Hamilton and Debra Kelley, telephone number 309-654-2241, extensions 3114 and 2240, respectively.

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, a II.

SUMMARY

OF OPERATING EXPERIENCE l

A. Unit One Quad Cities Unit One began the month of March 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 March synchronizing the main generator to the grid on March 1,1999, at 6:44 a.m. Rod pattem adjustments were made, and full power was achieved on March 2,1999. Unit Two operated throughout the remainder of the month at full power with minor down power operations for routine maintenance and surveillance testing.

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i i III. OPERATING DATA STATISTICS A. Unit One Operating Data Report for March 1999 DOCKET NO.: 50-254 DATE: April 7,1999 COMPLETED BY: Lynne Hamilton TELEPHONE: (309) 654-2241 OPERATING STATUS 0000 030199

1. REPOP. TING PERIOD: 2400 033199 GROSS IlOURS IN REPORTING PERIOD: 744

2. CURRENTLY AUTIIORIZED POWER LEVEL (MWO: 2511 MAX > DEPEND > CAFACITY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789 TlilS MONTil YEAR TO DATE CUMULATIVE

3. NUMBER OF IIOURS REACTOR WAS CRITICAL 744.00 2160.00 178956.70

4. REACTOR RESERVE SIIUTDOWN IIOURS 0.00 0.00 3421.90 l

5. IIOURS GENERATOR ON LINE 744.00 2160.00 173755.40

6. UNIT RESERVE SilUTDOWN llOURS 0.00 0.00 909.20

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7. GROSS TIIE'RMAL ENERGY GENERATED (MWil) 1850808.24 5394361.68 381142856.28

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8. GROSS ELECTRICAL ENERGY GENERATED (MWII) 605566.00 1764818.00 123322161.00 l

9. NET ELECTRICAL ENERGY GENERATED (MWil) 578701.00 1688241.00 110986094.00

10. REACTOR SE(VICE FACTOR 100.00 100.00 75.70 11, REACTOR A\ AILABILITY FACTOR 100.00 100.00 77.15

12. UNIT SERVICE FACTOR 100.00 100.00 73.50

13. UNIT AVAILABILITY FACTOR 100.00 100.00 73.89 l l

14. UNIT CAPACITY FACTOR (Using MDC) 101.15 101.M 61.05

15. UNIT CAPACITY FACTOR (Using Design Mwe) 98.58 99.06 59.50

16. UNIT FORCED OUTAGE RATE 0.00 0.00 7.01 TECilOP3WRC\ MAR 99 IXX2

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.< III. OPERATING DATA STATISTICS B. Unit Two Operating Data Report for March 1999 DOCKET NO: 50-265 DATE: April 7,1999 COMPLETED BY: Lynne Hamilton TELEPHONE: (309) 654-2241 OPERATING STATUS 0000 030199

1. REPORTING PERIOD: 2400 033199 GROSS IlOURS IN REPORTING PERIOD: 744

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

3. NUMBER OF IIOURS REACTOR WAS CRITICAL 744.00 1961.80 171558.90

4. REACTOR RESERVE SlIUTDOWN llOURS 0.00 0.00 2985.80

5. IIOURS GENERATOR ON LINE 737.30 1937.30 167004.05

6. UNIT RESERVE SilUTDOWN IIOURS 0.00 0.00 702.90

7. GROSS TIIERMAL ENERGY GENERATED (MWil) 1818739.20 4815374.88 365655457.74 i

8. GROSS ELECTRICAL ENERGY GENERATED (MWil) 588296 00 1561683.00 117310813.00 )1

9. NET ELECTRICAL ENERGY GENERATED (MWil) 566838.00 1503203.00 111270247.00 l

10. REACTOR SERVICE FACTOR 100.00 90.82 73.05 11, REACTOR AVAILABILITY FACTOR 100.00 90.82 74.33 i

! 12. UNIT SERVICE FACTOR 99.10 89.69 71.12

13. UNIT AVAILABILITY FACTOR 99.[0 89.69 71.41 )

14, UNIT CAPACITY FACTOR (Using MDC) 99.07 90.50 61.62

15. UNIT CAPACITY FACTOR (Using Design Mwe) 96.56 88.20 60.05 I

16. UNIT FORCED OUTAGE RATE 0.00 0.00 10.86 h

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1 IV. UNIT SHUTDOWNS

J A. Unit One Shutdowns for March 1999 i

DOCKET NO.: 50-254  !

1 DATE: April 7,1999 COMPLETED BY: Lynne Hamilton TELEPHONE: (309) 654-2241 No. DATE TYPE DURATION REASON METIIOD OF CORRECTIVE FOR (HOURS) SilUTilNG ACTIONS / COMMENTS S DOWN REACTOR Notie for the Month of March.

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Legend:  ;

(1) Reason l A - Equipment Failure (Explain)

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

II - Other (Explain)

(2) Metixx!

1 - Wnual 2 - Manual Trip / Scram 3 - Automatic Trip / Scram 4 - Cs niinuation 5 - Other (Explain) 7 TEC} TOP 3WRC\MARWDOC

IV. UNIT SHUTDOWNS s 4 B. Unit Two Shutdowns for March 1999 -

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~ DOCKET NO.: 50-265 DATE: April 7,1999 COMPLETED BY: Lynne Hamilton TELEPHONE: (309) 654-2241 i No. DATE TYPE DURATION REASON METHOD OF CORRECTIVE FORS (IlOURS) SIIUTilNG ACTIONS /CO% TALENTS  !

I DOWN REACTOR 9941 990301 S 6.7 B 4 Q2P02 Scheduled Surveillance Outage.

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(1) Reason A - Equipment Failure (Explam)

B - Maintenance or Test C - Refueling , '

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

II - Other (Explain)

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

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s V.' AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS l Technical Specification Amendment No.184 was issued on March 16,1999 to Facility Operating License No. DPR-29 and Amendment No.181 to Facility Operating License  !

No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively. l The amendments revise the respective facility Technical Specifications (TS) by adding a new Limiting Condition for Operations that provides an administrative enhancement by l allowing testing required to return equipment to service to be conducted under I administrative controls. I Technical Specification Amendment No.185 was issued on March 17,1999 to Facility Operating License No. DPR-29 and Amendment No.182 to Facility Operating License No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively.

The amendments change the Quad Cities Technical Specifications (TS) to reflect the l use of Siemens Power Cogoration ATRIUM-9B fuel. Specifically, the amendments incorporate the following into the TS: (a) new methodologies that will enhance operational flexibility and reduce the likelihood of future plant derates, I (b) administrative changes that eliminate the cycle-specific implementation of l ATRIUM-9B fuel and adopt Improved Standard Technical Specification language where appropriate, and (c) changes to the Minimum Critical Power Ratio.

1 Amendment No.182 for Quad Cities, Unit 1, was issued on December 3,1998, as an exigent amendment to accommodate these changes before restart fro n refueling outage QlR15. This new amendment deletes the unique Unit 1 pages issued in Amendment No.182 and provides identical pages for both units to support the common TS for Quad Cities, Units 1 and 2.

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Technical Specification Amendment No.186 was issued on March 26,1999 to Facility l Operating License No. DPR-29 and Amendment No.183 to Facility Operating License No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively.

The amendments change the Technical Specifications (TSs) by decreasing the Allowed Outage Time (AOT) from 67 days to 14 days for the Safe Shutdown Makeup Pump ,

(SSMP).

Technical Specification Amendment No.187 was issued on March 31,1999 to Facility Operating License No. DPR-29 and Amendment No.184 to Facility Operating License No. DPR-30 for Quad Cities Nuclear Power S'tation, Units 1 and 2, respectively.

The amendments revise Technical Specification (TS) Section 3/4.6, " Primary System Boundary" of Appendix A and associated bases to relocate the reactor coolant chemistry requirements to the Updated Final Safety Analysis Report (UFSAR) and applicable plant proceduies.

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\ t VI. UNIQUE REPORTING REQUIREMENTS l l

The following items are included in this report based on the requirements set forth in Technical Specification 6.9.A.5. ,1 A. Main Steam Relief Valve Operations There were no Relief Valve Operations during the reporting period.

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