ML20204B157

Monthly Operating Repts for Feb 1999 for Quad Cities,Units 1 & 2.With

ML20204B157
Person / Time
Site:	Quad Cities
Issue date:	02/28/1999
From:	Dimmette J, Hamilton L COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-97-02, GL-97-2, NUDOCS 9903190361
Download: ML20204B157 (11)

Text

k InIn)On % cdltb k dl%OU $.O W f.Hl[ l Quad Citiemencrating Nation l 22710 206th Asenue North Cord,n a. it. 612 i2-9no Tel 309 65122 6 i SVP-99-052 March 15.1999

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U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Quad Cities Nuclear Power Station, Unit I and Unit 2 Facility Operating License Nos. DPR-29 and DPR-30 I NRC Docket Nos. 50-254 and 50-265 l l

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Subject:

Monthly Performance Report l

In accordance with NRC Generic Letter 97-02, and Technical Specification Section 6.9, we are forwarding the Monthly Performance Report covering the operation of Quad Cities

. Nuclear Power Station, Unit One and Unit Two, during the month of j February 1999.

i If there are any questions or comments concerning this letter, please refer them to Mr. Wally Beck, Acting Regulatory Assurance Managar, at (309) 654-2241, extension 3609.

Sincerely,

- O (AD -

Jael P. Dimmette, Jr. (

fite Vice President Quad Cities Nuclear Power Station j Enclosure cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Quad Cities Nuclear Power Station

, 9903190361 990228 a l

PDR ADOCK 05000254 I R PDR A tinicOm Company L j

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l 1 QUAD CITIES NUCLEAR POWER STATION l l

L UNITS 1 AND 2 I

l MONTHLY PERFORMANCE REPORT FEBRUARY 1999 l

! COMMONWEALTH EDISON COMPANY AND

, MIDAMERICAN ENERGY COMPANY

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NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 1

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l TABLE OF CONTENTS I. Introduction II. Summary of Operating Experience A. Unit One B. Unit Two 3 i

III. Operating Data Statistics A. Operating Data Report for February- Quad Cities Unit One A. Operating Data Report for February- Quad Cities Unit Two IV. Unit Shetdowns A. Unit One Shutdowns A. Unit Two Shutdowns IV. Amendments to Facility License or Technical Specifications VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations 3 I

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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 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 ofinitial Reactor criticahties for Units One and Two, respectively j 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 February 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 February operating at full power. On February 20,1999, at 12:02 a.m., the main turbine was tripped and the reactor was manually shutdown for the Q2P02 scheduled surveillance outage. On February 28, 1999, at 6:14 a.m., the reactor went critical. The main generator was synchronized to the grid on March 1,1999, at 6:44 a.m.

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Ill. OPERATING DATA STATISTICS I i

A. Unit One Operating Data Report for February 1999 l

DOCKET NO.: 50-254 DATE: March 10,1999 l COMPLETED BY: Lynne Hamilton I TELEPHONE: (309) 654-2241 OPERATING STATUS 0000 020199

1. REPORTING PERIOD: 2400 022899 GROSS IlOURS IN REPORTING PERIOD: 672

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

3. NUMBER OF llOURS REACTOR WAS CRITICAL 672.00 1416.00 178212.70 j

4. REACTOR RESERVE SilUTDOWN IlOURS 0.00 0.00 3421.90

5. IlOURS GENERATOR ON LINE 672.00 1416.00 173011.40

6. UNIT RESERVE SilUTDOWN llOURS 0.00 0.00 909.20

7. GROSS TIIERMAL ENERGY GENERATED (MWH) 1689107.52 3543553.44 379292048.04

8. GROSS ELECTRICAL ENERGY GENERATED (MWil) 548505.00 1159252.00 122716595.00

9. NET ELECTRICAL ENERGY GENERATED (MWil) 525512.00 1109540..)0 110407393.00

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. REACTOR SERVICE FACTOR 100.00 100.00 75.62

11. REACTOR AVAILABILITY FACTOR 100.00 100.00 77.08

12. UNIT SERVICE FACTOR 100.00 100.00 73.42

13. UNIT AVAILABILflY FACTOR 100.00 100.00 73.80

14. UNIT CAPACITY FACTOR (Using MDC) 101.69 101.90 60.93

15. UNIT CAPACITY FACTOR (Using Design Mwe) 99.11 99.31 59.38

16. UNIT FORCED OUTAGE RATE 0.00 0.00 7.03 l

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i 111. OPERATING DATA STATISTICS  !

I B. . Unit Two Operating Data Report fbr February 1999 l

l l DOCKET NO: 50-265 DATE: March 10,1999 j COMPLETED BY: Lynne Hamilton L TELEPHONE: '(309) 654-2241 i OPERATING STATUS 0000 020199- l l- 1. REPORTING PERIOD: 2400 022899 GROSS IlOURS IN REPORTING PERIOD: 672

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

3. NUMBER OF !!OURS REACTOR WAS CRITICAL 473.80 1217.80 170814.90 l 4. REACTOR RESERVE SIIUTDOWN llOURS 0.00 0.00 2985.80

5. IlOURS GENERATOR ON LINE 456.00 1200.00 166266.75

6. UNIT RESERVE SIIUTDOWN IIOURS 0.00 0.00 702.90

7. GROSS TilERMAL ENERGY GENERATED (MWII) I133241.36 2996635.68 363836718.54 l

8. GROSS ELECTRICAL ENERGY GENERATED (MWII) 368002.00 973387.00 116722517.00

9. NET ELECTRICAL ENERGY GENERATED (MWil) 352657.00 936365.00 110703409.00

10. REACTOR SERVICE FACTOR 70.51 86.00 72.97 l l 11. REACTOR AVAILABILITY FACTOR 70.51 86.00 74.24

! 12, " NIT SERVICE FACTOR 67.86 84.75 71.03 3, 55f AVAltT61LITY FACTOR 67.86 84.75 71.33

14. UNIT CAPACITY FACTOR (Using MDC) 68.24 85.99 61.50

! 15. UNIT CAPACITY FACTOR (Using Design Mwe) 66.51 83.81 59.94 l

16. UNIT FORCED OUTAGE RATE 0.00 0.00 10.90 I

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ly. ~ UNIT SHUTDOWNS 1

A. Unit One Shutdowns for February 1999 i l

DOCKET NO.: 50-254

'DATE: Maren 10,1999 COMPLETED BY: Lynne Hamilton TELEPHONE: (309) 654-2241 i

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No. TYPE DlNATION REASON METilOD OF CORRECTIVE FOR (llOURS) SillrITlhG ACTIONS /CO.\DIENTS l S DOWN REACTOR, None for the Month of Febntary.

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1.egend:

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(1) Reason - i

.' A - Equipment Fature (Explain) )

B - Maintenance or Tesi - -l C - Refueling

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. D - Regulatory Restrcction )

E - Operator Train:ng' License Etantination

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F - Administrative .

J G - Operational Error (Explain)

II - Other (Esplain) ,

(2) Method 1 - Manual l

2 - Manual Trip / Scram 3 - Automatic Trip /Seram 4 - Contir;uation 5 - Other / Explain)

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ly. UNIT SHUTDOWNS B. Unit Two Shutdowns for February 1999

i. DOCKET NO.: 50-265

! DATE: March 10,1999 l COMPLETED BY: Lynne Hamilton l TELEPHONE: -(309) 654-2241 No. DATE TYPE. DURATION REASON METilOD OF CORRECTIVE FORS (HOURS) SHtTITING ACTIONS / COMMENTS DOMN

[ REACTOR i

994)! 990220 S 216.0 B 2 Q2P02 Schedyled Surveillance l Outage.

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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 - Operational Error (Explain)

I il - Other (Explain)

! (2) Methtx!

!  ! - Manual 2 - Manual Trip / Scram 3 - Automatic Trip /Scrain Continuauon 5 - Other (Explain) i

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V. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS i Technical Specification Amendment No.183 was issued on February 8,1999 to Facility l Operating License No. DPR-29 and Amendment No.180 to Facility Operating License i No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively.

The amendments relocate the requirement to remove Reactor Protection System (RPS) shorting links to the Updated Final Safety Analysis Report (UFSAR). Currently, the Technical Specifications (TSs) require the shorting links to be removed from the RPS circuitry prior to and during the time any control rod is withdrawn unless adequate SHUTDOWN MARGIN (SDM) has been demonstrated and the "one-rod-out" Refuel mode switch interlock has been demonstrated OPERABLE (an exception exists that allows shorting links to remain installed while in MODE 5 for control rod removal per Specification 3.10.1 and 310.J). Removal of the shorting links enables a non-coincident scram based on high neutron flux as detected by any neutron monitor. The changes l affect TS Sections 3/41.A " Reactor Protection System (RPS),3/4.10.B," Refueling l Operations, Instrumentation," and 3/4.12.B, " SHUTDOWN MARGIN Demonstrations."

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VI. UNIQUE REPORTING R"QUIREMENTS l The following items are included in this report based on the requirements set forth in Technical Specification 6.9.A.5.

l- A. Main Steam Relief Valve Operations Relief valve operations during the reportin'g period are summaraed in the following table.

The table includes information as to which relief valve was actuated, how it was actuated, l and the circumstances resulting in its actuation. I Unit: Two Date: February 28,1999 Valve Actuated: No. & Type of Actuation:

2-0203-3A 1 Manual Plant Conditions: Reactor Pressure - 320 psig Description of Events: QCOS 0203-03 " Main Steam Relief Valve Operability Test".

The valve was tested due to replacement during Q2P02.

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