SVP-99-007, Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With

Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With

ML20199E439
Person / Time
Site:	Quad Cities
Issue date:	12/31/1998
From:	Dimmette J, Hamilton L COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-97-02, GL-97-2, SVP-99-007, SVP-99-7, NUDOCS 9901200423
Download: ML20199E439 (11)

Text

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Commonw calth 14hmn romp.m3

, , Quad Chics Ge neratmg Nation

. . 2Tio 3 kith Asenue Nonh Cordos a. u 612 ;pr' 60 Tc130 ><,s un i SVP-99-007 January 14,1999 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk  !

Washington, DC 20555 Quad Cities Nuclear Power Station,' Units I 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 Perfom1ance Report covering the operation of Quad Cities Nuclear Power Station, Units One and Two, during the month of December 1998.

l If there are any questions or comments concerning this letter, please refer them to l

Mr. Charles Peterson, Regulatory Assurance Manager, at (309) 654-2241, extension 3609. 1 1

Sincerely, f ,

f _ Q( q l' fpp i . ,

l o 1 P. Dimmette, Jr.

Site Vice President L Quad Cities Station

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ec: Regional Administrator - NRC Region III ,

I NRC Senior Resident Inspector - Quad Cities Nuclear Power Station 1

MS $ Mil Eh*

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l QUAD CITIES NUCLEAR POWER STATION l UNITS 1 AND 2 l

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I MONTHLY PERFORMANCE REPORT DECEMBER 1998 1

l l COMMONWEALTH EDISON COMPANY l

l AND l-l- MIDAMERICAN ENERGY COMPANY l

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

LICENSE NOs uPR-29 AND DPR-30 l I

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! I l TABLE OF CONTENTS 1

I l I. Introduction l

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. II. Summary of Operating Experience l

l A.' Unit One ,

B. Unit Two l III. Operating Data Statistics l-l A. Operating Data Report for December - Quad Cities Unit One i j B. Operating Data Report for December- Quad Cities Unit Two i >

IV. Unit Shutdowns L - 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  !

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1 I. INTRODUCTION i

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 m 1

l 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 1,1971, and March 21,1972, respectively; pursuant to Docket Numbers 50-254 and $0-265. 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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II.

SUMMARY

OF OPERATING EXPERIENCE i i

A. Unit One i Quad Cities Unit One began the month of December in continuation of the Q1Ri5 refuel outage. On December 4,1998, at 2:44 a.m., ihe reactor went critical. On December 5,1998 at 5:06 a.m., the generator was synchronieM. to the grid. On December 5, at 10:05 a.m., the main turbine was tripped for overspeed testing. Testing was completed, and at 11:03 a.m. on December 5,1998, the generator was  ;

I synchronized to the grid. Scram timing was perfonned, rod pattern adjustments were made, and full power was achieved on December 8,1998. Unit One operated  :

throughout the remainder of the month at full power with minor down power operations )

for routine maintenance and surveillance testing. l i

B. Unit Two  !

l Quad Cities Unit Two began the month of December operating at full power. Unit Two ,

operated throughout the month at full power with minor down power operations for routine maintenance and surveillance testing. l 1

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III. OPERATING DATA STATISTICS A. Unit One Operating Data Report for December 1998 DOCKET NO.: 50-254 DATE: January 13,1999 COMPLETED BY: Lynne Hamilton TELEPIIONE: (309) 654-2241 OPERATING STATUS 0000 120198

1. REPORTING PERIOD: 2400 123198 GROSS IlOURS IN REPORTING PERIOD: 744

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

3. NU$1BER OF IIOURS REACTOR WAS CRITICAL 669.30 4421.30 176796.70

4. REACTOR RESERVE SliUTDOWN llOURS 0.00 0.00 3421.90

5. HOURS GENERATOR ON LINE 642.00 4300.10 171595.40

6. UNIT RESERVE SilUTDOWN IIOURS 0.00 0.00 909.20

7. GROSS TIIERMAL ENERGY GENERATED (MV'll) 1498632.48 10311252.00 375748494.60

8. GROSS ELECTRICAL ENERGY GENERATED (MWil) 490299.00 3303974.00 121557343.00

9. NET ELECTRICAL ENERGY GENERATED (MWil) 467M5.00 3142884.00 109297853.00

10. REACTOR SERVICE FACTOR 89.96 50.47 75.48

11. REACTOR AVAILABILITY FACTOR 89 96 50.47 76.94

12. UNIT SERVICE FACTOR 86.29 49.09 73.26

13. UNIT AVAILABILITY FACTOR 86.29 49.09 73.65

14. UNIT CAPACITY FACTOR (Using MDC) 81.74 46.65 60.68

15. UNIT CAPACITY FACTOR (Using Design Mwe) 79.66 45.47 59.14

16. UNIT FORCED OUTAGE RATE 0.00 0.02 7.09 i

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sn. OPERATING DATA STATISTICS l B. Unit Two Operating Data Report for Decemb:r 1998 l 1

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DOCKET NO: 50-265 DATE: January 13,1999 COMPLETED BY: Lynne llamilton TELEPHONE: (309) 654-2241 OPERATING STATUS 0000 : 0198

1. REPORTING PERIOD- 2400 123198 GROSS IIOURS IN REPORTING PERIOD: 744 ,

2. CURRENTLY AUMtORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACITY . 169 j DESIGN ELECTRICAL RATING (MWe-NET): 789 Tills MONTil YEAR 10 DATE CUMULATIVE

3. NUMBER OF llOURS REACTOR WAS CRiflCAL 744.00 5230.05 169597.10 l

4. REACTOR RESERVE S11UTDOWN llOURS 0.00 0.00 2985.80

5. IlOURS GENERATOR ON LINE 744.00 5096.90 165066.75 ;

6. UNIT RESERVE SliUTDOWN llOURS 0.00 ' O.00 702.90 7, GROSS TIIERMAL ENERGY GENERATED (MWil) 1867654.32 12483826.56 360840082.88

8. GROSS ELECTRICAL ENERGY GENERATED (MWII) 607909.00 3986586.00 115749130.00 ,

9. NET ELECTRICAL ENERGY GENERATED (MWII) 584988.00 3819586.00 109767044.00

10. REACTOR SERVICE FACTOR 100.00 ' 59.70 72.89

11. REACTOR AVAIL. ABILITY FACTOR 100.00 59.70 74.17

12. UNIT SERVICE FACTOR 100.00 58.18 70.94 l 13. UNIT AVAILABILITY FACTOR 100.00 58.18 71.24

14. UNIT CAPACITY FACTOR (Using MDC) 102.25 56.70 61.35

15. UNIT CAPACITY FACTOR (Using Design Mwe) 99.65 55.26 59.79

! 16. UNIT FORCED OUTAGE RATh 0.00 3.44 10.97 l

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IV. UNIT SHUTDOWNS L A. Unit One Shutdowns for December 1998 DOCKET NO.: 50-254 l DATE: Janumy 13,1999 l COMPLETED BY: Lyr.ne Hamilton TELEPHONE: (399) 654-2241 No. DATE TYPE JURATION REASON METHOD OF CORRECTIVE i FOR (HOWM SHUTI'ING ACTIONS / COMMENTS

S DOWN REACTOR 98-09 981201 S M1 C 4 Q1R15 Refuel Outage 98-10 981205 F .9 B 5 Main Turbine Tripped for Overspeed Tetting_

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(1) Reason A - Equipment Failure (Explain)

B - Maintenance or Test C - Refueling I D - Regulatory Restrictior.s E - Operator Trairdng/ License Examination l F- Administrative l G - Operational Error (Explain) f H - Other (Explain) l (2) Method 1 - Manual 2 - Manual Trip / Scram 3 - Automatic Trip / Scram

i. 4 - Continuanon 5 - Other (Explain) i' l

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IV.1ET SilUTDOWNS B. linit Two Shutdowns for December 1998 ,

DOCKET NO.: 4 265 DATE: Jr ary 13,1999 COMPLETED BY- Lynne Hainilton TELEPW)NE: '309) 654-2241 No. DATE TYPE DURATION REASON ME fHOD'OF CORRECTIVE FORS (HOURS) Sh'rITtNG ACTIONS / COMMENTS IXsvt W REA,":yR None for the Month of December ,

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Legend. 3 l (1) Reason  !

l A - Equipment Failure (Explain) j l B - Maintenance or Test j C - Rc*ielmg .

l D - Regulatory Restriction l E - Operator Training / License Examination l

F - Admmistrative G - Operational Error (Explain)

H - Other (Explain)

. (2) Method 1 - Manual 2 - Manual Tnp/ Scram 3 - Automatic Trip / Scram 4 - Continuation 5 - Other (Explatn) I

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4 I V. AMENDMENTS TO FACILITY LICENSE OR TECIINICAL SPECIFICATIONS Technical Specification Amendment No.182 was issued on December 3,1998 to Facility Operating License DPR-29 for the Quad Cities Nuclear Power Station, Unit 1.

4' The amendment changes the Quad Cities Technical Specifications (TS) to reflect the use of Siemens Power Corporation ATRIUM-9B fuel. Specifically the amendment incorporates the following into the TS: (a) new methodologies that will enhance i operational flexibility and reduce the likelihood of future plant derates, (b) l administrative changes that eliminate the cycle specific implementation of ATRIUM-98 fuel and adopt improved Standard Technical Specification language where appropriate, and (c) changes to the Minimum Critical Power Ratio. '

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VI. UNIOUE REPORTING REOUIREMENTS l

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 Relief valve operations during the reporting period are summarized in the following table.

l The table includes information as to which relief valve was actuated, how it was actuated, i and the circumstances resulting in its actuation.

Unit: 1 Date: 12/4/98 l

Valve Actuated No. & Tyne of Actuation i 1-0203-3A 2 Manual - Note (1) 1-0203-3B 1 Manual 1-0203-3C 1 Manual l 1-0203-3D 2 Manual - Note (1) 1-0203-3E 2 Manual - Note (1) l Plant Conditions: Reactor Pressure - 320 psig i

Description of Events: QCOS 0203-03 Main Steam Relief Valves Operability Test All valves were tested due to maintenance performed during Q1R15. Baseline timing was reset on the 1-0203-3A,3B, and 3E valves.

l Note (1): PIF Q1998-05458 documented the issues that arose during the performance of QCOS 0203-03. The Apparent Cause Evaluation further explains the results and retesting performed. The 1-0203-3A valve was retested to verify close timing of the valve. The 1-0203-3D valve was retested to verify proper bypass valve response. The 1-0203-3E valve t

was retested due to the SER printout not working. The valve was thus timed with a stopwatch. All valves were retested with satisfactory results.

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