Text

Monthly Operating Repts for June 1996 for Quad Cities Nuclear Station,Units 1 & 2
	ML20115H017
Person / Time
Site:	Quad Cities
Issue date:	06/30/1996
From:	Moore K, Pearce L; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LWP-96-053, LWP-96-53, NUDOCS 9607220184
	Download: ML20115H017 (20)
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l LWP-96-053 July 10, 1996 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

SUBJECT:

Quad Cities Nuclear Station Units I and 2~

Monthly Performance Report i

NRC Docket Nos. 50-254 and 50-265 l

Enclosed for your information is the Monthly Performance Report covering 1

the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of June 1996.

Respectfully, Comed Quad-Cities Nuclear Power Station D.b. 4rd />

L. W. Pearce Station Manager LWP/dak Enclosure l

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H. Miller, Regional Administrator C. Miller, Senior Resident Inspector 96072201i3s 96063o PDR ADOCK 05000254 R

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT.

JUNE 1996 COMONWEALTH EDI. CON COMPAL'Y AND 1

MID-AMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 i

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TABLE OF CONTENTS I.

Introduction II.

Summary of Operating Experience A.

Unit One B.

Unit Two III.

Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintensnce A.

Amendments to Facility License or Technical Specifications B.

Facility or Procedure Changes Requiring NRC Approval C.

Tests and Experiments Requiring NRC Approval IV.

Licensee Event Reports V.

Data Tabulations A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions VI.

Unique Reporting Requirements A.

Main Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Data VII.

Refueling Information VIII.

Glossary e

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e I.

INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Mid-American 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 j

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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, respect.ively; 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 Kristal Moore and Debra Kelley, telephone number 309-654-2241, extensions 3070 and 2240, respectively.

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II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Quad Cities Unit One spent the month of June 1996 shutdown in Refuel Outage QlR14.

B.

Unit Two

_ Quad Cities Unit Two spent the month of June 1996 shutdown in Forced Outage Q2F41.

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III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE l

l A.

Amendments to Facility License or Technical Soecifications REVISED Technical Specification Amendment No.171 was issued on June 28, 1996 to Facility Operating License DPR-29 and Amendment No. 167 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station.

The issuance of these amendments contains the remaining TSUP open items from previous Quad Cities TS amendments issued by the NRC, along with additional administrative changes.

B.

Facility or Procedure Chanaes Reauirina NRC Acoroval Revision 1.8 to the Offsite Dose Calculation Manual (0DCM) was Onsite Reviewed and accepted on June 18, 1996. The changes effected Chapter 10, 11, 12 and Appendix F and are documented in Onsite Review Report number 96-12.

C.

Tests and Exneriments Reauirina NRC Anoroval i

There were no Tests or Experiments requiring NRC approval for the i

reporting period.

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's IV.

LICENSEE EVENT REPORTS l

The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirenents as set forth in sections 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

UNIT 1 Licensee Event Report Nia=har Daig Title of occurrence 96-008 6/7/96 The Technical Specification Required Pressure was not met during local leak rate testing due to a procedural deficiency.96-010 6/11/96 The gallery steel above the Main Primary Containment Equipment Hatch on Units 1 and 2 could have been degraded during a postulated Seismic Event due to inadequate design configuration control practices.

UNIT 2 Licensee Event Report Number Dalg Title of occurrence There were no licensee event reports for Unit 2 for this reporting period.

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V.

DATA TABULATIONS The following data tabulations are presented in this report:

A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions l

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APPENDIX C OPERATING DATA REPORT i

DOCKET NO.

50 154 UNTT One DATE July 10,1996 COMPLETED BY Kristol Moose TELEPHONE (309) 654-2241 OPERATING STATUS 0000 060196

1. REPORTING PERIOD: 2400 M3096 OROSS HOURS IN REPORTING PERIOD: 720

2. CURRENTLY AITritnet7mn POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789

3. POWER LEVELTO WHICH REB 118CTED(IF ANY)(MWe-Net): N/A j

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4. REASONS FOR RESTRICrlON (IF ANY)-

l THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACIOR WAS CRTTICAL 0.00 964.10 161427.60

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90 1

7. HOURS GENERATOR ON LINE 0.00 963.20 156722.40 B. UNIT RESERVE SMITTDOWN HOURS 0.00 0.00 909.20

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9. GROSS THERMAL ENERGY GENERATED (MWH)

- 0.00 2258399.50 340694197.10

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 7343 %.00 110345477.00

11. NET EIJICTRICAL ENERGY GENERATED (MWH) 0.00 699244.00 104173620.00 4

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12. REACTOR SERVICE FACTOR 0.00 22.08 76.04

13. REACTOR AVAILABILTTY FACTOR 0.00 22.08 77.65

14. UNTT SERVICE FACTOR 0.00 22.06 73.82

15. UNTT AVAILABILTTY FACTOR 0.00 22.06 74.25

16. UNTT CAPACTTY FACTOR (Uning MDC) 0.00 20.82 63.51

17. UNTT CAPACTTY FACTOR (Uning Design MWe) 0.00 20.29

'62.19

18. UNTr FORCED OITTAGE RATE 0.00 0.00 7.54

19. SHUIDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE AND DURATION OF EACH): Refuel 2/10/a6

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: 7/27/96

21. UNTTS IN TEST STATVS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INTTIAL CRTTICALITY INTTIAL ELECTRICTrY COMMERCIAL OPERATION 1.1 +9

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APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-265 UNrr Two DATE July 10.1996 COMPLETED RY Krissal Moose TELEPHONE (309) 654-2241 OPERATING STATUS 0000 060196

1. REPORTING PEIUOD: 2400 06.t006 GROSS HOURS IN REPORTING PERIOD 720

2. CURRElfrLY AUTHORIZED FOWER LEVEL (MWI): 2511 MAX > DEPEND > CAPACITY: 769 DESIGN ELECTRICA_L R.ATINC A!We-NRT): 789

3. POWER LEVELTO WHF.H RAsbOCTED (IF ANY)(MWe-Neo: N/A i

4. REASONS POR RES1RICI10N (IF ANY):

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5. NUMRER OF HOURS REACTOR WAS CRfDCAL 0.00 3133.90 157204.35 i

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80 i

7. HOURS GENERATOR ON LINE 0.00 3125.00 153024.55

8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 7688143.90 332029364.82 l

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10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 2465748.00 106611283.00 l

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11. NET ELhC11UCAL ENERGY GENERATED (MWH) 0.00 2369169.00 101022055.00 r

12. REAC1DR SERVICE FACTOR 0.00 71.76 74.60

13. REACTOR AVAILABILFTY FACTOR 0.00 71.76 76.01

14. UNrr SERVICE FACTOR 0.00 71.56 72.61

15. UNrr AVAILARILrrY FACTOR 0.00 71.56 72.95

16. UNrr CAPACTTY FACTOR (Using MDC) 0.00 70.55 62.34 4

17. UNTT CAPACTTY FACTOR (Using Design MWe) 0.00 68.76 60.76

18. UNTr FORCED OUTAGE RATE 100.00 28.44 10.77

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (IYPE DATE. AND DURATION OF EACH): N/A

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: Q2F41 - Stan Up 7/21/96

21. UNrrs IN TEST STATUS (PIUOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INrflAL CRTTICALrrY INTTIAL ELEC110CTTY COMMERCIAL OPERATION 1.1 +9 TBCHOPMNRCM40NTHLY.Rrr

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL

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DOCKET NO 50-254 i

UNIT One DATE July 10.1996 COMPLETED BY Kristal Moore TELEPHONE f309) 654-2241 MONTH June 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-9 17.

-9 2.

-9 18.

-8 3.

-9 19.

-9 4.

-8 20.

-7 5.

-8 21.

-8 I

6.

-9 22.

-8 7.

-9 23.

-8 i

8.

-9 24.

-8 9.

-9 25.

-7 10.

-9 26.

-7 11.

-9 27.

-8 12.

-9 28.

-8 13.

-9 29.

-8 14.

-9 30.

-9 15.

-9 31.

16.

-9 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line).

In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two DATE July 10.1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH June 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-8 17.

-8 2.

-8 18.

-8 3.

-8 19.

-8 4.

-8 20.

-7 5.

-8 21.

-7 6.

-8 22.

-8 7.

-8 23.

-8 8.

-8 24.

-8 9.

-8 25.

-6 10.

-8 26.

-7 11.

-8 27.

-7 12.

-8 28.

-8

13.,

-8 29.

-8 14.

- 8' 30.

-8 15.

-8 31.

16.

-8 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

These figures i

will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line).

In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-254 UNIT NAME One COMPLETED BY Kristal Moore DATE July 10. 1996 REPORT MONTH June 1996 TELEPHONE 309-654-2241 h

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DURATION EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS 9642 06/01/96 5

720.0 C

4 Continuation of QlRl4 Refuel Outage.

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DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE July 10, 1996 REPORT MONTH June, 1996 TELEPHONE 309-654-2241

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DURATION EVENT CORRECTIVE ACTIONS / COMMENTS i

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DATE (HOURS)

REPORT 96-05 64146 F

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2 Continuation of Force Outage Q2F41.

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UNIOUE REPORTING REOUIREMENTS i

The following items are included in this report based on prior commitments to the comission:

A.

Main Steam Relief Valve Ooerations There were no Main Steam Relief Valve Operations for the reporting period.

B.

Control Rod Drive Scram Timina Data for Units One and Two There was rio Control Rod Drive scram timing data for Units One and Two for the reporting period.

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VII.

REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E.

O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities and Zion Station--NRC Request for Refueling Information", dated January 18, 1978.

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'N QTP 300-532 Revisicn 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unit:

01 Reload:

14 Cycle:

15 2.

Scheduled cate for next refueling shutdown:

2/10/96 3.

Scheduled date for restart following refueling:

7/27/96 4.

Will refueling or resumption of operation thereafter require a Technical

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Specification change or other license amendment:

NO 5.

Scheduled date(s) for submitting proposed licensing action and supporting information:

6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

232 GE10 Fuel Bundles were loaded during QlR14.

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The number of fuel assemblies, a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

1933 8.

The present Itcensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

s a.

Licensed storage capacity for spent fuel:

3657 b.

Planned increase in licensed storage:

0 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capactty:

APPROVED (final)

OCT 3 01989 14/0395t

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QTP 300-532 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unit:

Q2 Reload:

13 Cycle:

14 2.

Scheduled date for next refueling shutdown:

2/01/97 3.

Scheduled date for restart following refueling:

4/23/97 4.

W111 refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:

YES l

5.

Scheduled date(s) for submitting proposed licensing action and supporting information:

August 1996 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

Approx. 216 Siemens 9X91X Power Corporation Fuel Bundles will be

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7.

The number of fuel assemblies, a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

7777 8.

The present Ilcensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is s

planned in number of fuel assemblies:

1 a.