Text

Monthly Operating Repts for Sept 1997 for Quad Cities Nuclear Station Units 1 & 2
	ML20211N696
Person / Time
Site:	Quad Cities
Issue date:	09/30/1997
From:	Pearce L, Sirles C; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LWP-97-100, NUDOCS 9710170077
	Download: ML20211N696 (20)
	v • d • e

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u munonw ralth lihwn Company e

8 QL6ad Citlen Generating Station 22710 2tKdh Atenue North

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corth n a. it. fi t 2 iz-9? io Tel.uruis 4 22 ii LWP-97-100 October 9, 1997 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report NRC Docket Nos. 50-254 and 50-165 Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power

?tation, Units one and Two, during the month of September, 1997.

Respectfully, Comed Quad-Cities Nuclear Pover Station l1 ff i\\

4 b00L L. W. Pearce Station Manager LWP/dak Enclosure cc:

A. Beach, Regional Administrator C. Miller, Senior Resident Inspector i

9710170077 970930 PDR ADOCK 05000254 l lff.l l,

A Uniosm Compan',

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

l MONTHLY PERFORMANCE REPORT i

SEPTEMBER 1997 COMMONWEALTH EDISON COMPANY AND L

MIDAMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265

-LICENSE NOS. DPR-29 AND DPR-30 TECHOP3WRC\\MOF.* Y RPT

_ ~ -. - _ _ _ _ -. _ _ _.

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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 Maintenance i

A.

. Amendments to Facility License or Technical Specifications B.

Facility or Procedure Changes Requiring NRC Approval C.

Tests and Experiments Roquiring 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.

C ntrol Rod Drive Scram Timing Data

.VII.

-Refueling Information VIII, Glossary 1TrHOPMNRCWoh"DILY RPT w..

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i I.

INTRODUCTION F

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 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 Sirles and Debra Kelley, telephone number 309-654-2241, extensions 3070 and'2240,

\\

respectively.

TECHOP300tC\\ MONTHLY,RPT

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II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One 4

Quad cities Unit One was on-linr. the entire month of September 1997.

On September 11, 1997 at 1303 hours0.0151 days 0.362 hours 0.00215 weeks 4.957915e-4 months , the Control Room received a " Gland Steam Condenser High Level" alarm.

After troubleshooting, a load drop was performed to adjust the level controller for the 1B Gland Steam condenser Level Control Valve.

On September 15, 1997 at 1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months a load drop was performed in preparation for a Drywell entry to add oil to 1A Recirc Pump Motor.

Also at this time the 1B Gland Steam Condenser Level Control Valve had failed.

The Condenser was isolated and the 1B Gland Steam Condenser L6 vel Control Valve was removed for repair.

On September 21, 1997 at 0225 hours0.0026 days 0.0625 hours 3.720238e-4 weeks 8.56125e-5 months a load drop was initiated for reinstallation of the 1B Gland Steam Condenser Level Control Valve and to work on the instrumentation.

B.

Unit Two Quad Cities Unit Two started the month of September 1997 on-line.

on September 27, 1997 at 1355 hours0.0157 days 0.376 hours 0.00224 weeks 5.155775e-4 months the turbine was tripped and at 1640 hours0.019 days 0.456 hours 0.00271 weeks 6.2402e-4 months the reactor was manually scrammed due to Safe shutdown issues.

Therefore Q2P01 planned outage started a week early. Prior to shutdown on September 20, 1997 at 9.300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months a load drop was performed for Main Steam Isolation Valve Timing and Main Turbine Surveillance.

A few other load drops were performed for Control Rod Shuffles and Turbine Weekly Testing, however the average daily power level remained at 80% or greater.

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't III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical Specifications There were no Amendments to th!: Facility License or Technical Specifications for the reporting period.

B.

Facility or Procedure Chances Reauirina NRC Acoroval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C.

Tests and Erneriments Reauirina NRC Acoroval There were no Tests or Experiments requiring NRC approval for the reporting period.

4 I

TECHOPbNRC\\ MONTHLY RPT

J IV.

LICENSEE EVENT REPORTS 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 requirements of 10CFR50.73.

e UNIT 1 Licensee Event Reoort Number Date Title of occurrengg 97-021 9/3/97 The Cause of Discrepancies Found Between The Safe Shutdown (SSD)

Procedures and The Fire Protection Report, Which Led to the Declaration that Nine SSD Paths were Inoperable, Is Unknown at this time.97-022 9/26/97 Discrepancy between Safe Shutdown Analysis and Procedures UNIT 2 Licensee Event R(cort Number Date Titlo of occurrence 97-011 9/6/97 Offgas Hydrogen Sampling Frequency was less than Required by Technical Specifications due to Inadequate Tracking of Actions Required for an Inoperable Explosive Gas Monitoring System.

NOTE:

Sequence of LER Numbers is out of order due to reuse of numbers.

TFIHOP3WRCM40ffTMLY.RFT

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 TscsonwacwormH,Y.BM -

APPENDIX C OPERATINO DATA REPORT DOCKET NO.

50-254 UNTT One DATE October 9,1997 COMPLETED BY Kridal Sirles TELEPHONE (309)654-2241 OPERATING STAUJS 0000 090197

1. REPORTING PERIOD: 2400 093097 GROSS IlOURS IN REPORTING TrRIOD: 720

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

3. POWER LEVELTO WHICH RESTRICTED (IF ANY)(MWe-Net): N/A

4. REASONS FOR RESTRICTION (IF ANY):

Tills MONTH YR TO DATE CUMULATIVE l

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 720.00 5932.10 170441.30

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421,90

7. HOURS GENERATOR ON LINE 720.00 5843.50 165372.40

8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENEROY GENERATED (MWil) 1618061.00 13745163.80 360918046.30

10. GROSS ELECTRICAL ENEROY GENERATED (MWII) 509711.00 4384157.00 1168a5587.00 ll. NET ELECTRICAL ENEROY OENERATED (MWil) 484573.00 4184444.00 110339413.00

12. REACTOR SERVICE FACTOR 100.00 90.55 76.34

13. REACTOR AVAILABILTTY FACTOR 100.00 90.55 77.87

14. UNTT SERVICE FACTOR 100.00 82.90 74.07

15. UNTT AVAILABILTTY FACTOR 100.00 89.20 74.48

16. UNTT CAPACTTY FACTOR (Using MDC) 87.52 83.06 64.27

17. UNIT CAPACTTY FACTOR (Using Design MWe) 85.30 80.96 62.64

18. UNTT FORCED OLTTAGE RATE 0.00 10.80 7.61

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): QlP01 173/98 -

1/24/98

20. IF SHITTDOWN AT END OF REPORT PERIOD < ESTIM ATED DATE OF STARTUP: N/A

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST AcillEVED INTTIAL CRITICALTTY INTTIAL ELECTRICTTr COMMERCIAL OPERATION 1.16-9 TECHOP)\\NRC\\ MONTHLY.Rrf l

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APPENDIX C OPERATING DATA REPORT

1. SOCKET NO.

50-265 UNIT Two DATE Odober 9,1997 COhlPLLTED BY Kristal Sirles TELEPilONE (309) 654-2241 OPERATING STATUS 0000 090197

1. REPORTING PERIOD: 2400 093097 GROSS HOURS IN REPORTING PERIOD: 720

2. CURRENTLY AUTHORIZED POWER LEVEL (MW ): 2511 MAX > DEPEND > CAPACITY: 769 DESIGN ELFCTRICAL RATING (MWe-NET): 789

3. POWER LEVEL TO WHI('" RESTRICTED (IF ANY) (MWe Net): N/A

4. REASONS FOR RESTRICrlON (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. hUMBER OF HOURS REACTOR WAS CRTTICAL 640.70 3780.50 164367.05

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 637.90 3720.50 159969.85

8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (Mw11) 1566983.70 8684167.50 348356256.32

10. GROSS ELECTRICAL i.NERGY GENERATED (MWil) 497581.00 2145407.00 Ii1762544.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 476814.00 2627737.00 105947458.00

12. REACTOR SERVICE FACTOR 88.99 57.71 74.14

13. REACTOR AVAILABILrrY FACTOR 88.99 57.71 75.48

14. UNIT SERVICE FACTOR 88.60 56.79 72.15

15. UNir AVAILABILTTY FACTOR 88.60 56.79 72.47

16. UNTT C APACrrY FACTOR (Using MDC) 86.12 52.16 62.14

17. UNrr CAPACfrY FACTOR (Using Design MWe) 83.93 50.84 60.57

18. UNir FORCED OUTAGE RATE 0.00 0.31 10.95

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH): Q2P019/27/97 10/17/97

10. IF SHUrDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: N/A

21. UNTTS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST AcillEVED INTTIAL CRTrlCALrrY INITIAL ELECTRICTTY COMMERCIAL OPERATION l.16-9 TECHOP3WRCalOPrIHLY.PFT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET No 1Q-254 UNT.T One

-DATE October 9.

1997 COMPLETED BY Kristal Sirles TELEPHONE f309) 654-2241 MONTH september 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Met)

(HWe-Net) 1.

704 17, 236 l

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749 18.

497 3.

756 19.

753 IL 4.

73" 20.

757 1

5.

757 21.

484 6.

750 22.

697 7.

757 23, 760 8.-

757 24.

750

-9.

754 25.

761 10.-

758 26, 761 11.

620 27.

757 12, 434 28.

763 13.

600 29.

764 14.

75a 30.

767 15.

715 31.

16. --

61

. 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.

1.16 TEchoP3\\NRC\\ MONTHLY.RfT l

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Two DATE October 9.

1997.__

COMPLETED BY Kristal Qirles TELEPHONE (309) 654-2241 MONTH sent- % r 1997 DAY AVERAGE DAILY POWgR LEVEL DAY ' sRAGE DAILY POWZR LEVEL (MWe-Met)

(MWe-Net) 1.

740 17, 765 2.

759 18.

766 3.

759 19.

764 4.

764 20.

764 5.

763 21.

632

(

6.

763 22, 750 7.

709 23.

768 8.

764 24.

768 9.

765 25, 768 10.

766 26.

767 11.

768 27.

265 12.

770 28.

-9 13.

767 29.

-9 14.

71P 30.

-9 15.

766 31.

16.

764 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.

1.16-8 TECHoPMNMCWONTHLY.RTT l

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i APPENDIX D UNIT-SHUTDOWNS AND POWER REDUCTIONS

[_

DOCKET NO. 50-254

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' UNIT NAME-One COMPLETED BY 'Kristal Sirles DATE.

October 9, 1997 REPORT MONTH Sent-her 1997-TELEPHONE 309-654-2241 i

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LICENSEE O

j DURATION EVENT i

NO.

DATE (HOURS)

-REPORT CORRECTIVE ACTIONS / COMMENTS 97-11'-

9-11-97 F-0 A

5 IB Gland Steam condenser Level Control Valve Problems. 12 9 16-97 F

0 B

5 Load Dropped for Drywell Entry To Add Oil to I A Recirs Pump Motor.

97 13

-92197 F

0 A

5 1B Gland steam condenur Level Contrul Valve Problems.

4

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TliCHOP3WRCuechTHlY.RPT

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS

.)vcKET NO.

50-265 1

UNIT NAME Two COMPLETED BY Kristal Sirles j

DATE October 9.

1997 REPORT MONTH Eeotember 1997 TELEPHOiiE 309-654-2241 m

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LICENSEE O

DURATION EVENT CORRECTIVE ACTIONS / COMMENTS a

No.

DATE (HOURS)

REPORT 97 10 9-20-97 5

0.0 B

5 Main Steam isolation Valve Timing and Main Turbine Surveillance.

97-11 9-27-97 5

82.1 A

2 Planned Outage To Remove end Replace a Leaking Fuel Bundle Q2P01.

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e Wh TECHOP3\\NRC\\ MONTHLY,RPT

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t VI.

UNIOUE REPORTING REOUIREMENTS The following items are included in this report based on prior commitments to the commission:

i lA. Main Steam Relief Valve Operationg i

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

i B. Control Rod Drive Scram Timina Data for Units One and Two i

The basis for. reporting this data to the Nuclear Regulatory 1 -

Commission are specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2.

The following table is a complete summary of Units One and Two control Rod-Drive Scram timing for the reporting period.- All scram timing as performed with reactor pressure greater than 800 PSIG.

TECHOP3\\NRCueONTHLY.RPT ~

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I S

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL

. ROD DRIVES, FROM 01/01/97 TO 09/30/97

-l l AVERAGE TIME IN SECONDS AT 4 l MAX. TIME l l

l INSERTED FROM FULLY WITHDRAWN l FOR 90%

l

! INSERTION !

DESCRIPTION i

NUMBER l

5 20 50 90 l

Technical Specification 3.3.C.1 &

'DATE

! OF RODS I O.375 ! O.900 2.00 3.5 7 sec.

3.3.C.2 (Averaae Scram Ta==etion Tims) t I

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I I

2/17/97 l

14 1 0.314 l 0.712 l 1.528 1.2.671 1

3.010 1 STT for Viton' Issue U-1 (Core Wid Ave. Times) l l

l l

l (J-14) l l

l l-l 1

l l

3/29-31/97 21 l 0.316 0.708 l 1.513 l 2.645 l

3.010 l STT for Tech Spse (19).(Core Wide Ave. Times) l

.l l

l l

l (J-14) l PMTV (2)-

l 1

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4/25/97 1

l 0.29 l 0.64

! 1.37 l 2.4 3.010 l Post Maintenance Test for Accumulator Replacment j

l l

(J-14)

! Unit 1 i

5/31/97 l

14 l 0.354 0.725 i 1.497

! 2.576 l

2.77 i STT for Viton Issue - U1

'l l

l l

(G-15) i i

l l

i-l l

l l

6/23/97 l

13

-l 0.297 l 0.681

! 1.478 j 2.615 l

2.95 l Post Outage Scram Test Timing and PMTV - U2 (M-12) l I

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6/29/97 l

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l 0.278 j O.630 j 1.348 l 2.350 l

2.46 l Post Outage Scram Testing and PMTV - U2 l

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l (P-6) i l

ll l

l 7/16/97 l

1 i O.280 0.630 1 1.324 l 2.306 l

2.306 l PMTV - U2-I j

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(N-6) l l

l l

l 7/20/97 32

! 0.312 ! O.701 l 1.497 l 2.617 l

2.67 l TS & SSPV Testing U-1 i

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l (G-15) 9/18/97 l

14 l 0.312 0.702 i'1.499 l 2.621 l

2.77 l STT for viton Issue U-1 l

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b VII.

REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested 11: a January 26, 1978, licensing memorandum J.

(78-24) from D.

E. O'Brien to C.

Raed, et al.,

titled "Dresden, Quad-Cities and Zion Station--NRC Request for Refueling Information", dated January 18, 1978.

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TECHOP3\\NRC\\MONTMLY.RTr'T

e-QTP 0300-S32 Rsvicion 3 April 1997 QUAD CITIES REFUELING INFORMATION REQUEST 1.

Units 01 Reload 14 cycle 15 2.

Sched led date for next refueling shutdown:

9/0F/98 3.

scheduled date for restart following refueling:

11/14/98 4.

Will refueling or resumption of operation thereafter require a Technical specification change or other license amendment:

Yes 5.

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

November, 1997 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 SPC 9X9IX Fuel Bundles QlR15 will be loaded.

7.

The number of fuel assemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pools 1933 8.

The present licensed 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:

Licensed storage capacity for spent fuel 3657 a.

b.

Planned increase in licensed storage:

0 9.

Tha projected data of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

2002 "l

(final) 1 l

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QTP 0300-532

-)

R3vicion 3 April 1997 QUAD CITIES REFUELING

~

INFORMATION REQUEST 1.

Units 02 Reload 14 Cycle:

15 2.

scheduled date for next refueling shutdown:

2/20/99 3.

scheduled date for restart following refueling:

3/27/99'

- 4.

Will refueling or resumption of operation thereafter require a Technical specification change or other license amendments

.Yes 5.

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

August, 1998 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:

N/A 7..

The number of fuel assemblies.

a.

Number of assemblies.in cores' 724 b.

1 Number of assemblies in spent fuel pool:

2943

' 8.

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

a.

Licensed storage capacity for spent fuel 3897 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 capacity:

2002 (final) 2