ML20247G067

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Monthly Operating Repts for Aug 1989 for LaSalle Nuclear Power Station,Units 1 & 2
ML20247G067
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 08/31/1989
From: Diederich G, Thunstedt J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 8909180354
Download: ML20247G067 (25)
v • d • e


Text

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. _.J Commonwealth Edison J .?: . . .. l*" j '

LtSalle County Nuclear Station j Rural Route #1, Box 220 1 Marsellies, Illinois 61341 Telephone 815/357-6761 - '

i September 10, 1989 Director of Nuclear Reactor Regulation United States. Nuclear Regulatory Commission l Mail Station F1-137 Washington,-D.C. 20555' ATTN: Document Control Desk I Gentlemen:

l- Enclosed for your information is the monthl'y performance report covering LaSalle County Nuclear Power Station for A:1 gust, 1989.

Very truly yours, l

,,/ O M G4 J. Diederich Station Managez LaSalle County Station GJD/JWT/gsh h 'llulS9 Enclosure xc: A. B. Davis, NRC, Region III NRC Resident Inspector LaSalle Ill. Dept. of. Nuclear Safety P. Shemansti, NER Project Manager D. P. Galle, CECO D. L. Ferrar, CCCo INPO l<ecords Center L. J. Anastasia, AIP Coordinator, Nuclear Services J. E. Kuskey, GE Resident T. J. Kovach, Manager of Nuclear Licensing W. F. Naughton, Nuclear Tuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle Terry Novotney, INPO Coordinator, LaSalle Station l' T. A. Hammerich, Regulatory Assurance Supervisor J. W. Gieseker, Technical Staff Supervisor Central File 8909180354 890831 [ i PDR ADOCK 05000373 / )I ZCADTS R FDC N

7-___._ . _ . . . . _ . . _. _ .

4 LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT AUGUST 1989 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 ZCADTS

TABLE OF CONTENTS I. INTRODUCTION II. REPORT A.

SUMMARY

OF OPFRATING EXPERIENCE B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATEC MAINTENANCE

1. Amendments to Facility License or Technical Specifications
2. Changes to procedures which are described in the Safety Analysis Report
3. Tests and Experiments not covered in the Safety Analysis Report
4. Corrective Maintenance of Safety-Related Equipment
5. Completed Safety-Related Modifications C. LICENSEE EVENT REPORTS D. DATA TABULATIONS
1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS
1. Main Steam Relief Valve Operations
2. ECCS System Outages
3. Off-Site Dose Calculation Manual Changes
4. Major Changes to Radioactive Waste Treatment System
5. Indications of Fa31ed Fuel Elements l

ZCADTS I

4 I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.

Unit One was issued operating license number NPT-11 on April 17, 1982.

Initial criticality was achieved on June 21, 1982 and commercial power operation was commenced on January 1, 1984.

J This report was compiled by John W. Thunstedt, telephone number i (815)357-6761, extension 2463.

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  • II. ' MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE EAy Time Event 1 0000 Reactor critical, generator on-line, at 3330 MWT Load reductions due to Load Dispatcher requests are generally reported as part of Paragraph D.3 (Unit shutdowns and Power Reductions.)

4 0100 Reduced load to 2590 MWT for Heater-Drain problem.

8 1200 Returned to full power.

1700 Reduced load to 2971'for Generator Stator rectifier problem.

9 0300 Returned to full power.

16 0300 Reduced load to 2090 MWT for rod-set.

2200 Returned to full power.

23 0100 Reduced load to 2550 for Turbine feed pump repairs.

24 1700 f.eturned to full power.

27 0700 Reduced power to 1040 MWE to swap Condensate Pumps.

1200 Returned to full power.

30 0100 Reduced load to 1014 MWE for rod exercising.

1000 Returned to full power.

31 2400 Reactor critical, generator on-line at 1080 MWE.

ZCADTS

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  • B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED l . MAINTENANCE.

l

1. Amendments to-the Facility License or Technical Specification.

(None)

2. Changes to procedures which are described in the Safety Analysis Report.

(None)

3. Tests and Experiments not described in the Safety Analysis Report.

(None) i

4. Major corrective maintenance to Safety-Related Equipment.

(See Table 1)

5. Completed Safety-Related Modifications.

(None)

ZCADTS  :

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I A T LE N 4 C R O E - I B R Y T R C OT E N C F U m s R SA F e l O L t a J A s n A M r M e e F v t O l n a i E v S d U n e A e g C k a o m r a B D T .

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C. ' LICENSEE EVENT REPORTS l

j. . Lilt Number Data Description I

89-022-00 08/10/89 RCIC Isolation on High Flow Signal D. DATA TABULATIONS-

1. Operating Data Report (attached) 2 ., Average Daily Unit Power Level (attached)
3. Unit Shutdowns and Power Reductions (attached)

ZCADTS

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D51.OPEFITINGDATAREPDFT .'00CKET NG, 05 F373 l f a' 4 UNIT LASALLE ONE r_ . I ATE Sep teeber it ,' 1999 -

00hPLETED BY J.W.:THUNSTEDT TELEPHONE (515)-357-6761-OPERATINGSTATUS-ih)REPORTINGPERIDIn AULUST 1989 GRDSSHDURSINREPORTINGPERIOD: 744

' ')2. CURRENTLY AUTHORIZED f0WER LEVEL (MWil-~3,323 NAX DEFEND CAPACITY (MWe-Net): 'I,036 DESIGN ELECTRICAL'RAilNG MWe-Net) 1,075-

3.iPSER LEVEL TO WHICH RESTRICTED .(IF ANY) (hke-Net)i (None)-

[j. REASOF5 FOR RESTRICTION (IF ANT):  :(N/A)

REPORTING PERIOD EATA' THIS HUNTH . YEAR-TD-DATE CUMULATIVE

(

I

5. TIME REACTOR ERITICAL GOURS) 744.0 5,757.3 31,776.6
6. ' TIME REACTOR RESERVE SHUIDOW MOURS) 0.0 10.0' i,641.2 L 7. TIMECENERATORON-LIMEGOURS)' 744.0 5,747.1 31,061.6-L8. TIME ;EHERATOR RESERVE SHUTLOWN (HOURS) 0.0 0.0 1.0

' 9e THERMAL ENERGY GENERATED MWHt-Gren) 2,284,632 17,978,374 S6,756,952' 19.~ ELECTRICAL ENER;Y GENEFJLTED (ellHe-Gress) 755,334 6,062,267 08,708,021

'11. ELECTRICAL ENERGY GENERATED MWHrNet) 726,232 5,640,995 27A16,434 L12.EEACTORSERVICEFACTOR(!) 130.9 99.7 64.0

'13. REACTOR MAILABILITY FACTOR 1%) 100.6 90.7 67.3

14. SEPJICE FACTOR (%)' 100.0 95.6 62.5 L

L15. AVAILIPILITY FACTOR 11) 1 H. 0 98.6 42.5 Ii6. CAFACITY FACTER (USING MM) (%) 94.2 96.7 - *i3.3

[th CATACITY FACTDR1051HG DESIEN MWe) (I) 90.5 92.9 51.2'

$ 13.' FORC. ED CLTAGE TACTOR (%) 0.0 1.4 -10.2

19. SHUTD M S SCHEDJLED DVER THE NEXT 6 MONTHS (TYFE, DATE, AhD DUP.ATION OF EACH):

Rebeling 09 Sepiruber 1989 12 Wesh

20. IF SHUTI6!N AT END OF REPORT FERIOD, EETIMATED DATE OF STARTUP:

(N/A) a

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'- ", .,;. -",t' DCCKET N0.'050-373 UNIT LASALLE ONE

.~D.2 -AVERAGE' DAILY. UNIT POWER LEVEL (MWe-Net) LATE September ti, 1789 W:-- -> COMPLETED EY J.U. THUNSTELT '

.; ; 1 TELEfHONE (015)-357-6761 REFORTPERIDD: AUGUST 1987

' DAY.: ; POWER DAY POWER s

! 1,013 17 -i,650

~

-2 97B . 18 975 L

-3 968 19 955

4. S3B 20 920 5 -Bi? 21 1,652 6: 826 22 1,053 7 827 ~ 23 890-B 965 24 993 9 . i.,031 25 1,057 is 1,053 26 1,943 11 f,039 27 1,031 12 965 28 i,035 13- B65 27 1,039 14 995 30 1,018 15 1,04? - 31 1,097 16- 914

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k.,UFIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATIM CM DITION OF EVENT (None)
2. ECCS System Outages OUTAGE NO. EQUIPMENT PURPOSE

.(ilDkL-.Q) 0-254-89 "0" D/G Repair valve ODG006 0-270-89 "0" D/G Replace air-start solenoid 1HEIT 1) 1-486-89 IE12-F073B (RH) EQ inspection 1-487-89 lA D/G Calibrate relay 1-502-89 HPCS D/G Perform surveillance.

1-502-!.9 HPCS D/G Perform surveillance 1-503-89 IE22-FV319 (DG) Rebuild Limitorque 1-526-89 1E12-F068A (RH) Replace packing 1-529-89 1E12-F073A (RH) Inspect torque switch 1-533-89 1E12-F074A Inspect torque switch

3. Off-Site Dose Calculation Manual (See Attachment B)
4. Major changes to Radioactive Waste Treatment Systems.

(None)

5. Indications of Failed Fuel E3ements.

A small pin-hole leak has been identified.

ZCADTS

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.' ATTACHMENT B  !

.' - i l

Revisions to the Offsite Dose Calculation Manual (ODCH) are reportable to the NRC in accordance with stations' technical specifications. The document contains the models for the public dose assessment from gaseous effluents, liquid discharges, and direct radiation. In 1988, in response to the NRC's request to make the ODCM a more readable document as well as to incorporate certain changes, Commonwealth Edison rewrote its ODCH. This document, renumbered to Revision 0, March,1989, will be submitted under separate cover. This summary describes the principal non-edited changes.

MAJOR CHANGES I

The NRC, in NuReg 0472 Rev. 3. Draft 7, has identified the child's thyroid and not the infant's as the most sensitive organ from the inhalation of l airborne effluents. Dresden, LaSalle, and Quad Cities Stations' 10CFR20 l instantaneous release rate limits have been revised to restrict the dose rate  !

to the child's thyroid to less or equal to 1500 mrem /yr. I Hydrogen addition to the primary coolant increases the boiling water reactors' turbine N-16 shyshine by a magnitude of 5. This phenomenon is now included in the ODCM formulation. In addition the sky shine calculation is written for LaSalle County Station as well as revised in Dresden and Quad Cities.

MINOR CHANGES Host of the ODCM documentation has been either clarified, corrected or deleted. '

Plume depletion, terrain factors and heat content were not accounted for in the original for D/Q. X/Q and plume rise calculations. They are described irs the revised document.

It was implied that the X/Q dose factors were calculated assuming a mono-energetic gamma energy having an average gamma ray energy per disintegration for each radionuclides. Also, it was assumed that the corrected tissue absorptions were made using a tissue energy absorption coefficient equivalent to this same average gamma ray energy for each radionuclides. Actually, the dose factors and the tissue energy absorption coefficients referenced were calculated using the photon energy spectra for each radionuclides. The tissue energy absorptions coefficients are negligible and have been deleted from the text.

Formulas and parameters for determining the maximum permissible concentrations (HPC's) have been eliminated from the section on radioactivity in storage tanks. The maximum limits, in curies, are found in the site specific sections.

8076E/3 1

.. ATTACHMENT B

,.' ,. (Cont.)

The potential direct radiation dose from stations' interim radwaste storage facilities is discussed. The radwaste containers will have a contact dose rate of 5 R/hr and the expected radiation levels will be minimal at the site boundary.

The distance dependent parameters were adjusted to the values reported in the

'88 census for nearest residents and/or nearest milch animal. This also affected the D/0 tables and BHR turbine N-16 shyshine calculation.

The time of travel from the station liquid discharge to the nearest community water supply was reevaluated for Braidwood and Quad Cities.

ODCM Revision 0, March 1989 has received approvals by all six onsite review committees and the CECO offsite review per the Technical Specifications.

Changes to the ODCM computer program required by this document are in the process of being implemented now and should be fully available by November 1, 1989.

8076E/4 A . . ,

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l LASALLE NUCLEAR POL 40R STATION UNIT 2 MONTHLY PERFORMANCE REPCRT AUGUST, 1989 COMMONWEALTH EDISON COMP 97Y NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 ZCADTS

TABLE OF CONTENTS I. INTRODUCTION l II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

1. Amendments to Facility License or Technical Specifications
2. Changes to procedures which are described in the Safety Analysis Report.
3. Tests and Experiments not covered in the Safety Analysis Report.
4. Corrective Maintenance of Safety-Related Equipment
5. Completed Safety Related Modifications C. LICENSEE EVENT REPORTS D. DATA TABULATIONS
1. Operating Data Report
2. Average Daily Unit Power T,evel
3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS
1. Safety / Relief Valve Operations
2. ECCS System Outages
3. Off-Site Dose Calculation Manual Changes
4. Major Changes to Radioactive Maste Treatment System
5. Indications of Failed Fuel Elen<ents ZCADTS

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I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 107B Megawatts. Naste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.

Unit Two was issued operating license number NPF-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and commercial power operation was commenced on June 19, 1984.

This report was compiled by John W. Thunstedt, telephone number (815)357-6761 extension 2463.

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,I 4 1. MONTHLY' REPORT A.

SUMMARY

OF OPERATING EXPERIENCE P_ny Ilmn EYant 1 0000 Reactor critical, generator on-line at 3254MWT Load reductions due to Load Dispatcher requests are generally reported as part of Paragraph D.3 (Unit Shutdowns and Power Reductions.)

1600 Reduced load to 1260 MWT due to "B" Turbine-Driven Reactor feed pump trip.

2 0100 Increased power to 2850 MWT 3 0500 Reduced power to 2625 MWT for rod exercising 0600 Increased power to 2928 MWT 4 0900 Reduced load to 2880 to take "A" Turbine-Driven Reactor feed pump out of service.

6 0700 Returned to full-power.

9 0100 Reduced power to 2475 MWT for FCL rod pull.

2000 Returned to fu)1 power.

10 0400 R9duced load to 3103MWT for CRD erarcising.

0700 r.etttrned to full power.

14 1800 Reduced load to 3090 MWT for Generator Stator water problems.

15 1300 Retcrned to full power. j 2300 Reduced load to 3160 MWT for Generator Temperature problems.

17 2200 Returned to full power.

24 0240 . Reduced load to 3097 MWT for CRD exercising.

1000 Returned to full power.

25 2000 Began reducing load for scheduled outage to repair 2B Reactor Recirc Pump seal.

.l 26 0413 Reactor scram, cause unknown. 1 j

31 2400 Reactor sub-critical, generator off-line. j I

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  • B.- PLANT.OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AMD SAFETY RELATED

-MAINTENANCE.

1. Amendments to the Facility License or Technical Specification.

(None)

2. . Changes to procedures which are described in the Safety Analysis Report.

(None)

3. . Tests and Experiments not described in the Safety Analysis Report.

(None) 4 '. Major corrective maintenance to Safety-Related Equipment.

(See Table 1)

5. Completed Safety-Related. Modifications.

(None) l ZCADTS

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C. LICENSEE EVENT REPORTS.

L.ER Numhgr Date Description 89-011-00 08/26/89 Reactor Scram from Turbine stop valve not full open 89-012 08/29/89 Isolation of Shutdown Cooling i

1 f

D. DATA TABULATIONS

1. Operating Data Repost (Attached)
2. Average Daily Unit Power Level ( Atteched)
3. Unit Shutdowns and Power Reductions (Attached)

ZCADTS

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n ., < . r LP.i L DPERATING DATA REPORI DOCKET NO. f50-374

. UNIT LASALLE TWO DATE Septemter 11,1987-COMPLETED IY J.W.THUNSTEDT <

TELEPHONEiB15)-357-6761 10PERATINGSTATUS' 12.-. REPORTING PERIOD:' AUGUST 19E9 GROSS HOURS IN REPDRTING FERIOD: 744'

2. ECURRENTLY AUTHDEIZED FCWER LEVEL (Midt): 3,323 NAX DEPEND CAFACITY (HWe-Net): 1,036 DESIGN ELECTRICAL RATING'(NWe-Net) 1,070 '
  • 3; PGWER LEVEL TD kHICH RESTRICTED (If ANY) (NWe-Net): '(None)-
4. 4 REA50KS FOR RESTRICTION .(IF ANY): ' (N/A)

REPORTING PERIOD DATA r

THIS MONTH YEAR-TO-DATE CUMULATIVE

. 5. ; TIME REACTOR CRITICAL IHOURS) 628.1 4,501.2 28,277.2 T,6 IlhE REACTOR RESERVE.SHUTDDUN (HOURS) 0,0 f.0' 1,716.9

7'. TIME GENERATOR DN-LINE (HOLES) 627.0 4,748.5, 27,SM.5 B.- : NMEGENERATORRESERVESHUT00LW(H3URS) 0.0 :0.9' O.6
9. ;HERMALENERGYGENERATED(Et-Grus) 1.E92,160' 14 A74 904 804 414,512

' 19. QICWICAL ENERGY GEER.ATED WteCron). 643.536 W,734.263 26d37,601 K ELfliRICAL EERGY CEEATED (wetu SB'ai? 4,569 4 43 2N2if 093 4 i?[REACIDR SERVICE FACTOR (D - 54,4 62.3 66.3 i

.13. ECACIDR AVAILABILITY FAC73R (D S4.4 $2,3 7P.3 d 4. SERVICE FACTOR (!) B4.7 lia 65.2

15. AVAILIFILITY FACTOR (I). E4.3 Ei.4 65.2
i6. CAFACITY FACTDR (U$ING MDC) (%) 75.4 75.5 57.2 p17. CAFACITY FACTOR (USINC DESIGN MWe)-(%)- 72.5 72.6 55.0
18. F0ECED OUTAGE FACTOR (I) e.9 0.1 14.5 l19. EHdTDOWN3 $CHEDULED DVER THE NEXT 6 HNTHS (TYPE, DATE, MD DURATION OF [KH);

(Nene )

J29. IF SHUTIDWN AT END DF REPORT FERICD, ESTIMATED ? ATE OF STARTUF:

Serienber 30 1989 w-_x. 2 _ _ - . - - . - - - - - - - - - - - - - --.----__.--_--.-._..--.__--___-..--.___.--_.-..-----._.._--._..~__----,.__....-----n - - -- _ - - - - - _ - - - - - . _ . _ _ _ - -

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DOCKET NO. 050-374 y ,- UNIT LASALLE Ti0

. D.2 L AVERAGE Dn!LY UNIT POWER LEEL (MWe-Net) ' ~ DATE September-11, 1989 r0HPLETED lY J A THUN5TEIT-TELEPH3NE(215)-357-6761 REFORT TERIOD: AU;UST 1987.

, LAY TOWER ' IAY POWER

1' 063 17 973

'2 294 iB i,027 3 B76 19 1 ,01 9 '

4' _091 20 1,619

5. 803 21 1,022 6 . 957 22 1,028'

', 7 906 ' ' 23 '1,020 8 942 24 1.t25 -

9 1,035 25 128 le - se1B 26 6 11 1,614 27 -11 i

13 92  ?? -11 f

it, 1,069 30 -ti 0 15 1,695 31 -11 16 93 9

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E 1. Safety / Relief Valve Operations VALVES NO & TYPE PLANT DESCRIPTION DATE ACWATED ACTUATIONS CONDITION OF EVENT (None)-

l 2. ECCS System Outages QETAGE NO. IOUIPMENT PURPOSE 2--724-89 2DG035 Lubricate stem

'2-730-89 2B HPCS D/G Change Soakback filter 2-734-89 RCIC Turbine Replace oil 2-735-89 2E51-C005 (RI) Replace / repair cubicle door 2-736-89 RCIC Turbine Repair mechanical over-speed device 2-749-89 2DG035 Ensure LPCS Operability 2-751-89 2B D/G Replace fuel filter gauges and calibrate air-start pressure-reducer 2-812-89 2E51-F013 (RI) Inspect Limitorque operator

3. Off-Site Dose Calculation Manal

!,See Unit 1)

4. Major changes to Radioactive Wasts Treatment Systema.

(None)  !

5. Indications of Failed Fuel Elements.

(None) i l

I ZCADTS l1

____________________-__u_-_m__- -

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