ML20212P601

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Feb 1987
ML20212P601
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 02/28/1987
From: Diedrich G, Kirchner G
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8703160165
Download: ML20212P601 (40)


Text

.) .s I

i i

LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERPORMANCE REPORT

FEBRUARY 1987 CON 90NWEALTH EDISON COMPANY 4

NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 3

l l

i l

l l

1 hh316kigg g gd i

DOCUMENT ID 0043r/0005r

2 "

TATLE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT ONE 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. Facility or Procedure Changes Requiring NRC Approval
3. Tests and Experiments Requiring NRC Approval
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 B. 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 Failed Fuel Elements l

DOCUMENT ID 0043r/0005r

l- e I. INTRODUCTION The LaSalle County Nuclear Powet 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 cr==nnwealth Edison Company.

Unit one was issued operating license number NPF-ll on April 17, 1982.

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

This report was compiled by Gregory J. Kirchner, telephone number (815)357-6761, extension 245.

l l

l i

(

i o

DOCUMENT ID 0043r/0005r

i d

, II. MONTHLY REPORT POR UNIT ONE A. SUpWEARY OF OPERATING EXPERIENCE FOR UNIT ONE February 1-28. 1987 February, 0000 Hours. Subcritical, Generator Off Line.

February 2, 1600 Hours. Rx Critical 1710 Hours Turbine Generator Synched to grid, ramp at 45 MWe/hr. to 820 MWe, then 10 MWe/hr to 910 MWe.

February 4, 1806 Hours. Drop 40 MWe/hr. to 0-MWe to investigate 'B' l Rx Recirc. vibration problems.

February 5, 1855 Hours. Turbine Generator Off Line.

1930 Hours. Rx Subcritical February 9, 0110 Hours. Rx Suberitical 1220 Hours. Turbine Generator Synched to grid, fast ramp to 140 MWe.

February 13, 1700 Hours. Drop 50 HWe to 550 MWe for one half hour to obtain jet pump 81 data.

1720 Hours. Ramp back to 580 MWe at 100 MWe/hr February 17, 1845 Hours. Drop 20 MWe/hr for one hour to 570 MWe for further data on jet pump #1.

February 24, 1355 Hours. Ramp to 590 MWe to perform CRD Ex.

February 28, 1310 Hours. Drop 60 MWe to 520 MWe in order to gather recirc data, then immediately ramp to 580 MWe.

I 2400 Hours. Rx Critical, Turbine generator on line at 588 MWe.

l i

4 DOCUMENT ID 0043r/0005r

B. PLANT ON PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED g .r MAINTENANCE.

1. Amendments to Facility License or Technical Specification.

Amendment #48 - Alluwa, plant operation with control rod 10-47 withdrawn.

Amendment #49 - Allows Unit 1 Operation for 30 days with the Unit 2 Division 2 Diesel Inoperable for Maintenance / Modification Work.

2. Facility or Procedure changes requiring NRC approval.

There were no Facility or Procedural changes requiring NRC approval during this reporting period.

3. Tests and Experiments requiring NRC approval.

There were no Tests or Experiments requiring NRC approval during this reporting period.

4. Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a Summary of Safety-Related maintenance completed on Unit One during the reporting period. The headings indicated in this summary include:

Work Request number, Component Name, Cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.

5. Completed Safety Related Modifications.

The following Table (Table 2) presents a list of completed Modifications during this reporting period. Each entry will have a short synopsis explaining details involved with each modification.

DOCUMENT ID 0043r/0005r

- -- ,___ ~_ _ _ . __ . . _ _ _ _ . _ - _ . . _ _ _.

r TABLE 1 CORRECTIVE MAINTEDEWCE OF SAFETY RELATED EQUIPMENT UNIT #1 WORK REQUEST COMPONENT CAUSE OF MRLFUNCTION RESULTS AND 3FFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L53315 VC Filter / Inlet Failed Open Rebuild Actuator Installed one (1) 3/4" Damper OVC11YB shim. Assured proper operations.

L55152 ODG05J Terminal Terminal Box Damaged Replace Replaced Terminal Block Block No. 16 L55183 Damper OVE07YB Actuator does not move. Rebuild Actuator Rebuilt actuator in-stalled two (2) 1/2" I shins. Assured proper l operations.

l L56422 S/P Temp. Indicator No Indication. Repair / Replace Replaced indicator like l ITY-CM057CA/CB for like, and calibrated instrument.

l L57178 Reactor Vessel Spray Valve stem is bent. Isolate and Repair as New valve installed Flow Indicator gage. necessary. tested and no leaks IE12-N013 (Ft) observed. l 1

L59392 RWCU System Blowdown Low Instrument Vent Valve Replace and Test. Replaced vent valve IE31- i Flow Ft. IE31-N015 Leaks. NOIS, and performed pressure test. ,

, L63460 OVE03RB Damaged Motor Leads Fan Auto trips after 45 Sec. Replaced Motor.

l of Ops.

L63583 Aux control VC Relay Relay Chatters, Loose Repair / Replace Replaced Relay, and OFSY-VC043X Parts. assured proper Ops.

DOCUMENT ID 0043r/0005r

TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT UNIT #1 COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION WORK REQUEST ON SAFE PLANT OPERATION L63833 MSIV-LCS Inst. Root Packing Leaking Steam. Repack. Repacked Valve.

Stop IE32-F309 L63834 B-MSL lE32-F302E Packing Leaking Steam. Repack. Repacked Valve L63834 B-MSL lE32-F302E Packing Leaking Steam. Repack. Repacked Valve .

)

L63836 C-MSL lE32-F302J Packing Leaking Steam. Repack. Repacked Valve l L63846 LPRM Down Scale Alarm Bad Alarm Relay. Alarm is up with no LPRMS Replaced burned out LPRM IH13-P603 A407 Downscale. Lamps. Assure proper Ops. i l

L64258 *A* RHR Press. Alarm appears to have Alarm ccs:les in at normal water Installed new min. flow l leg pump pressure. oriface, and calibrated. l Switch l#12-N512A drifted upwards.

VC/VE *B* Train Min. Actuator does not cycle. Troubleshoot Found oil level too high l L64386 l Flow Supply Damper and bad limit switch.

OvC52YB Reduced oil level and re-placed limit switch.

Damper OVCl2YA Damper does not cycle. Repair. Adjusted limit switch, L64406 assured proper operation.

Paper does not advance. Repair. Replaced drive motor L64588 S/P Temp. Rec.

assured proper ops.

Damper OVC21YB Repair. Adjusted Travel limit L64816 Failed Closed.

switch and assured proper OPS.

DOCUMENT ID 0043r/0005r

~

_3 TABLE 1 CORRECTIVE MRINTENANCE OF SAFETY RELATED BQUIPfENT -

UNIT 81 IdORK REQUEST COPE 80NENT CRUSE OF MRLFUNCTION RESULTS AND EFFBCTS W IVE ACTION ON SAFE PLANT OPERATION L64%2 cont. Monitoring Loose Bolts on Solenoid Torque Bolts. Torqued Bolts to 60 in Isol. ICM027 Cover. Ibs.

L64%6 'O' DG Oil Ptsap Bad 74 Relay. Replace. Replaced bad 74 Relay.

L65065 'B' IRM IC51-K601B May cause 1/2 Scram and Bad Power Supply. Calibrated Regulator Rod Block. Voltage. Verified proper Operation.

L65063 Acetamulator S435 Valve Leaks. Replace (111) Cartridge. Installed new valve like IC11-D001-111 for like.

L65072 HCU 46-47 Valve Leaks. Replace (111) Cartridge. Installed new valve like ICll-D001-111 for like.

L65089 HCU 50-43 Valve Leaks. Replace (111) Cartridge. Installed new valve like ICll-D001-Ill for like.

L65139 *B' IRM 1/2 Scram on Inop. Trip. Troubleshoot. Replaced failed preregu-lator on the +20 VDC side, verified proper OPS.

L65185 RCIC Discharge Reading Downscale. Bad Transmitter. Replaced with a new Press. IE51-N004 calibrated transmitter.

L63271 *A* VC Compressor Loud Metal - Metal bang- Dissassemble Repair. Replaced connecting rod OVC05CA ing noise. bearing, piston and pin assembly.

DOCUMENT ID 0043r/0005r

TABLE 1 CORRECTIVE MRINTENMICE OF SAFETY RELATED BQUIPMENT UNIT #1 UORK REQUEST col @ONIDIT CAUSE OF MRLFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L65315 *A* LPRM Meter Reads high about 60L Troubleshoot. Replaced E12, first IC51-K605GU level multiplexer Cord.

Verified proper operation.

L65439 Secondary Cont. Isol Damper failed to indicate Bad Limit Switch. Replaced limit switc.%

Damper IVR04YA full closed. verified proper OPS.

L65463 RR Loop 'B' Thermo- Damaged Flex Replace. Replaced the seal tight couple /RTD fitting / seals. Verified reads correctly.

L65601 ITR-CM037 Printer Does nor mark the chart. . Adjust. Adjusted printer head.

Head Verified proper OPS.

L65660 1TR-CM037 Recorder Point #10 reads Adjust. Replaced output fuse and downscale. calibrated.

DOCUMENT ID 0043r/0005r

a TABLE 2 CWLETED SAFETY RELATED MODIFICATIONS MODIFICATION NUMBER
A brief synopsis of incorporated modification objectives with final design resolution. Also, state reviewed or unreviewed safety questions.

The following is a list of the Safety Related Modifications completed from February 1, 1987 through February 28, 1987.

M-1-0-83-820 - This Modification was to modify the shielded entries into the Reactor Building and replace door #299 with a high power rifle bullet resistant and, 3-hour rated fire door. There were no unreviewed safety questions.

5:1-0-84-015 - This modification was to add separate cooling water supply lines to the OPP 0lPA/PB Fire Pumps and Diesel Engines.

1 i

i l

I I

DOCUMENT ID 0043r/0005r

a
-  ;

i g a ,

s 2 , .

, C. LICHNSBH EVENT REPORTS ,

A ,

The following is a tabular sununary of'all licensee event reports for i LaSalle Nuclear Power Station,. Unit One, logged during the reporting

, . A i perloi, February O_1, through Ft.7/ts.tary 28, 1987. - This information is provided purm. ant to the reporthble occurrence reporting requirements as set forth in 10CFR 50.73.

g Licensee Event Rebort Numbei Date 'tutpf_.phs2trrencg

87-008-00 02/03/87 3t), day - Missed Hydrogen Analyzar Sample.

009-00 02/17/87 ?O day r Utwp IV Isolt, tion during Lurt. Testihy. ,

. . e 87-010-00 02/22/07 30 day - Failure'of 'O' Diesel Generator Cooling Vater Breaker.

Y ,

+

N f

f

~

l 4

\

+ /

4 1

)

I I

l l

Docunsc47 ID 0043r/0005r

r , ,

f.

4

.c

.I s ,

?

[

! 6 D. DATA TABULATIONS t The following data tabulations are presented in this report:

1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions I

J

  • i t

i

(

t' DOCUMENT ID 0043r/0005r

2- g 1.. OPEEATING DATA REPORT DOCKET NO. 050-373

) UNIT LaSalle One DATE March 10. 1987 CON LETED BY Gregory Kirchner TELEPHONE (815)357-6761 OPERATING STATUS

1.  ; REPORTING PERIOD: February. 1987 GROSS HOURS IN REPORTING PERIOD: 672
2. CURRENTLY AUTHORIEED POWER LEVEL (MWt):2222 MAX DEPEND CAPACITY s' (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078
3. POWER LEVEL 10 WHIQi RESTRICTED (IF ANY) (MWe-Net): 1050
4. REASONS FOR RESTRICTION (IF ANY): Administrative THIS MONTH YR TO DATE CUMULATIVE l' 5 NUMBER OF HOURS REACTOR WAS CRITICAL 554.25 1257.15 15692.75
6. REACTOR RESEHVE SHUTDOWN HOURS 0.0 0.0 1642.0 C 7. HOURS GENERATOR ON LINE 541.43 1175.40 15149.43
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ~ ENERGY GENERATED (MWH) 972984 2802264 43387186
10. GROSS ELEC. IDfBRGY GENERATED (MWH) 306064 920142 13610819
11. NET EL8C. EWERGY GENERATED (MWH) 292528 885911 12908485
12. REACTOR SEWICE FACTOR 82.5% 88.8% 56.6%
13. REACTOft AVAILABILITY FAC1VR _82.5% 88.8% 62.5%
14. UNIT SERVICE FACTOR 80.6% 83.0% 55.6%
15. UNIT AVAILABILITY FACTOR _80.6% 83.0% 54.6%
16. UNIT CAPACITY FACTOR (USING MDC) 42.0% 60.4% 44.9%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 40.4% 58.0% 43.2%
18. UNIT FORCED OUTAGE RATE ~ 19.4% 5.5% 15.2%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)

On June 13, 1987, Unit I will be shutdown to repair the IB Reactor Recirc Pump. The shutdown is scheduled to last fifty (50) days.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

N/A i

4 l

1

/ DOCUMENT ID 0043r/0005r s

- - . . . - . - . . . - . . ~ .~. . . - . . - , - . - . . . - . _ _ . _ . . , , _ . , _,_ ,,- ____ - , . , , , . , ,

j 2., AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: March 10. 1987 COMPLETED BY: Gregory Kirchner TELEPHONE: (815) 357-6761 MONTH: February, 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l (MWe-Net) (MWe-Wet) l l

1. -13 17. 557 h
2. 65 18. 544 3 662 19, 547
4. 849 20. 556
5. 226 21. 549
6. -13 22. 545
7. -14 23. 545
8. -14 24. 560
9. 60 25. 568
10. 367 26, 566 11, 540 27. 566
12. 551 28. 564
13. 563 14, 561 15, 561
16. 561 I

DOCUMENT ID 0043r/0005r

3. UNIT SHUTDOWNS AND PCMER RED'JCTIONS DOCKET NO. 050-373 UNIT NAME LaSalle One DATE March 10, 1987 REPORT MONTH FEBRUARY, 1987 COMPLETED BY Gregory Kirchner TELEPHONE Q15)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS / COMMENTS 3 02/01/87 F 40.08 A 3 Alterex Problems 4 02/05/87 F 77.67 A 1 'B' Rx Recirc Problems.

DOCUMENT ID 0043r/0005r

.s E. UNIQUE REPORTING R8QUIREMENTS
1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED 8CTUATION 90NDITION OF EVENT There were no Safety Relief Valves Operated for Unit One during this reporting period.

i l

l l

l l

l l

DOCUMENT ID 0043r/0005r

2. ECCS Systems Outcge3
.s The fallowing outige3 were tckan on ECCS Sy
stems during the reporting period.

- QUTAGE N!;b. BQUIPMENT PURPOSB OF OUTAGB 01-50-87 RR HPU Repair RR FCU Leak 01-53-87 MS System Flx Leaks 01-59-87 MSIV-LCS Repack 1E32-F302J and N j

DOCUMENT ID 0043r/0005r

j .:

3. Off-Site Dose Calculation Manual There were no changes to the ODCM during this reporting period.
4. Radioactive Weste Treatment Systems.

Reference the attached letter dated March 2, 1987, concerning a change to the LSCS Process Control Program.

5. Indications of Failed Fuel Elements There were no indications of Failed Fuel Elements during this reporting period.

DOCUMENT ID 0043r/0005r

.s E

March 2, 1987

SUBJECT:

Memorandum describing a change to the LSCS Process Control Program BACKGROUND During the past two years there have been many operational difficulties associated with Stock squipment System used to solidify radwaste. Now that most of the difficulties have been resolved radweste solidification is.

proceeding in a timely manner. However during the interim a significant backlog of radwaste has accumulated hindering efficient operation of the system as a whole. Additionally, vendors can offer a more cost effective means for solidifying and dewatering various wastes.

For the above reasons it has been decided to employ Westinghouse Hittman Nuclear Inc. to dewater and solidify the contents of IA/IB/2A/28 Phase Separator Tanks, the URC Sludge Tank, the Spent Resin Tank and the Waste Sludge Tank. The dewatering, solidification, and subsequent transportation of waste off-site is expected to begin Nov. 7, 1986, and March 2, 1987, respectively. The contract with Westinghouse Hittman (Vendor) will run through March 31, 1987.

Our Stock system has been modified to allow interfacing with the vendor's equipment.- The changes, installed under Temporary System Changes 1-1921-86 4 and 1-156-87, constitute major changes to the radwaste system and Licensee -

initiated substitutions to the PCP needing review under T.S. 6.9.1. and 6.7.2.

respectively.-

The contractor will be using his own equipment, personnel and procedures l

to perform the dewatering / solidification. Thedewatering[solidificationwill be performed in accordance with a NRC approved Topical Report (STD-R-05-011) l and Process Control Program (STD-PCP-03-003) which meets the requirements of 10CFR20/50/61/71 and 100. The vendor's procedures have been approved by the on Site review and Investigative Function for implementation at LaSalle Station..

MODIFICATION DETAILS All vendor equipment is to be maintained within the Radwaste Truck Bay.

The dewatering / solidification will take place under both operating and health physics supervision. Entry level status of the Truck bay will be upgraded at

! the discretion of the Health Physics department.

An interface with the existing loop transfer lines is needed to transfer waste to the vendor's equipment. Flanges existing on several lines and off several new " tees" all installed under Temporary System Changes 1-1921-86 and 3

1-156-87 will be opened and manual isolation valves will be flanged in-line.

The various sludge lines all have a second manual isolation valve before the

} vendor system connection.

DOCUMENT ID 2593r/

.s i

An air supply, uncontaminated water supply and electrical hook-up are presently available in the truck bay.

No radioactive liquid or gaseous releases are expected. During the dewatering / solidification process air samples are taken at the outlet of the vacuum pump to determine if any net release of radioactive material occurs.

If there is any. release of radioactive materals, the outlet vent will be filtered and/or re-routed directly to the Radweste Ventilation System, under the direction of the Tech Staff Engineer, resulting in no release.

Increased exposures to individuals in the unrestricted area and to the general population are not expected.

Exposure to plant personnel is expected to decrease 80% (35 man-rem) as a

result of using a vendor's system. Actual exposure to plant personnel is
monitored by the Health Physics Department as standard procedure.

L Any comments or questions involving the above program should be addressed to John Arand, x-5*10.

I

?

F I

l:

l lI I

lf  ?

ll l[ i l..

F L

L b

i fy k

I i

DOCUMENT In 2593r/

L , . . , ~ . . _ _ _ ___ . . - - . . . . _ . . _ _ . . . . . _ . _ _ _ _ _ _ _ _ , _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ .

LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT FEBRUARY, 1987 COPMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 l

DOCUMENT ID 0036r/0005r

TABLE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT TWO 4

A. Susunary of Operating Experience B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

1. Amendments to Facility License or Technical Specifications
2. Facility or Procedure Changes Requiring NRC Approval
3. Tests and Experiments Requiring NRC Approval
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 B. UNIQUE REPORTING REQUIREMENTS
1. Safety / 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 Failed Fuel Elements DOCUMENT ID 0036r/0005r

g .i I. INTRODUCTION The LaSalle County Nuclear power Station is a two-unit facility owned by Comunonwealth 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 two was issued operating license number NPF-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and comunercial power operation was commenced on June 19, 1984.

This report was compiled by Gregory J. Kirchner, telephone number (815)357-6761 extension 245.

DOCUMENT ID 0036r/0005r

i II, MONTHLY REPORT FOR UNIT TWO I g

  • 3

( A. SUfMARY OF OPERATING EXPERIENCE FOR UNIT TWO 1

Pebruary 1-28. 1987 February 1, 0000 Hours. Rx Subcritical, Refuel Outage in progress.

February 28, 2400 Hours. Rx Subcritical.

(

DOCUMENT ID 0036r/0005r ,

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l

g ,0.5 PLANT.OR PROCEDUR3 CHANGES, TESTS, EXPERDEDfTS AND SAFETY RELATED MAINTENANCE.

1. Amendments to Facility license or Technical Specification.

There were no Amendments to the Facility License or Technical Specifications during this reporting period.

2. Facility or Procedure changes requiring NRC approval.

There were no Facility or Procedure changes requiring NRC approval during the reporting period.

3. Tests and Experiments, requiring NRC approval.

There were no Tests or Experiments requiring NRC approval during the reporting period.

4. Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a summary of Safety-Related Maintenance completed on Unit Two during the reporting period. The headings indicated in this summary include: Work Request number, Component Name, cause of malfunction, results and effects on safe operation, and

' corrective action,

5. Completed Safety Related Modifications.

I The following table (Table 2) presents a list of completed Modifications during this reporting period. Each entry will have l a short synopsis explaining details involved with each i

modification.

I l

I l

l I

i l

l DOCUMENT ID 0036r/0005r

. - . . _ _. __ _. . . _ . . _ _ , . m TABLE l-CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION

! L49687 HPCS Swg Room Seal on Door Cracked Replace gasket. Replaced gasket.

1 Water Tight Door L58512 Div. 3 Battery Battery hold down clamps Exposing Bare Metal. Replaced straps and 2E22-5001 worn out verified battery integrity. ,

L58552 HPCS DG Cooling Water Valve Leaks Repack valve. Repacked valve and Valve 2B22-F319 checked for leaks.

L62366 Interlock Switch Component Replacement Install new.S.O.R. Instrument Installed new S.O.R.

for SRV 2B21-F013A Switch. Switch.. DCR 387-27 written to reflect changes.

L62367 Intlk Switch for Component Replacement Install new switch per Installed new switch.

, SRV 2B21-F013B DCR 87-27.

L62368 Intlk Switch for Component Replacement Install new switch per New switch installed.

4 SRV 2B21-F013C DCR 87-27.

L62369 Intlk Switch for Component Replacement Install new switch per New switch installed.

SRV 2B21-F013D DCR 87-27. ,

L62370 Intlk Switch for Component Replacement Install new switch per New switch installed.

2B21-F013E DCR 87-27.

]

j L62371 Intlk Switch for component Replacement Install new switch per. New switch installed.

2B21-F013F DCR 87-27.

L62372 Intlk Switch for component Replacement Install new switch per' New switch installed.

2B21-F013G DCR 87-27.

.1 L62373 Intlk Switch for Component Replacement Install new switch per New switch installed.

j 2B21-F013H DCR 87-27.

i DOCUMENT ID 0036r/0005r i

1

. TABLE 1 CORRECTIVE MAINTENANCE OF-SAFETY RELATED EQUIPMENT Unit #2

[ WORK REQUEST COMPONENT CAUSE.OF MALFUNCTION. RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION i L62374 Intlk Switch for Component Replacement Install new switch per Installed new switch.

2B21-F013J DCR 87-27.

. L62375 Intik Switch for component Replacement Install new switch per Installed new switch.

2B21-F013K DCR 87-27.

t L62376 Intlk Switch for Component Replacement Install new switch per Installed new switch.

2B21-F013L DCR 87-27.

L62377 Intlk Switch for component Replacement Install new switch per Installed new switch.

2B21-F013M DCR 87-27.

L62378 Intlk Switch for Component Replacement Install new switch per Installed new switch.

2B21-F013N DCR 87-27.

L62379 Intlk Switch for Component Replacement New switch installed per Installed new switch.

2B21-F013P DCR 87-27.  !

j L62380 Intlk Switch for component Replacement New switch installed per Installed new switch, j 2B21-F013R DCR 87-27.

i l L62381 Intlk Switch for Component Replacement New switch installed per Installed new switch.

1 2B21-F013S DCR 87-27.

L62382 Intlk Switch for Component Replacement New switch installed per Installed new switch.

l 2B21-F013U DCR 87-27.

i 4

j L62383 Intlk Switch for Component Replacement New switch installed per Installed new switch.

3 2B21-F013V DCR 87-27.

J

] L64268 Supp. Pool Wtr. 2TE-CM057N Element Operability not affected as Rewired to relfect

! Temp. Monitor #1 not wired per drawing. wired. drawing IE-2-40182C, ZD.

1 2

i L64625 D-APRM APRM spiked and caused Four values found out of Recalibrated and verified half-scram, tolerance. proper Ops.

]

I DOCUMENT ID 0036r/0005r

~

i

':'ABLE 1 CORRECTIVE MAINTENANCE OF [*

SAFETY RELATED EQUIPMENT Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L64744 HPCS DG Vtr Cooling Switch cracked, calib. Obtain new calibrated Replaced with new calib.

Temp. Htr. Control unknown. switch, switch.

(S35)

L64829 '2A' DG Cooler Suspect Tube side Clean / Hydrolyze Tubes. Hydrolyzed DG Cooler fouling. Tubes.

L64849 ITT Damper Actuator Flex and Lugs are damaged. Replace damaged parts. Replaced flex and lugs.

L64923 OVC 214B Damper sticks while Troubleshoot. Adjusted spring tension opening. on limit.

L64960 Solenoid valve Bolts holding down Torque bolts to 70-75 in-lbs. Bolts torqued to meet 2CM026B solenoid cover. EQ requirements.

L64970 2A Vr. Exc. Prm Rad monitor downscale Bug source needs adjusting. Adjusted bug source.

2D18-K609A is up.

L65009 Div. 3 Battery Battery charger output Test current limiter. Current limiter was reset Charger low. to get proper output.

L65186 CRD 2Cll-D001 Rust found in drive. Rebuild CRD. CRD rebuilt with all new seals and bushings.

L65296 Instrument power Power supply output low. Repair / Replace as needed. Power supply observed for supply 2EY-CM082 proper ops for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

L65367 Fuel Pool Exh. No continuity at detector Found open Ckt 3" from end Cutaway bad cable and Rad Monitor end of cable. of cable. reterminated.

L65634 CRD 2Cll-D001 Drive failed leak test. Rebuild Drive. Drive rebuilt with S/N A1008 new seals.

L65636 CRD 2Cll-D001 Drive failed leak test. Rebuild Drive. Drive rebuilt with S/N 7766 new seals.

DOCUMENT ID 0036r/0005r

TABLE 1 '

CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT .

Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION .RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L65668 CRD 2Cll-D001 Drive failed leak rate Rebuild. Rebuilt, installed new S/N A1008 test on vessel ports. ball and ball gauge.

L65710 Hydrogen Recombiner Arm Tripper Fingers Repair / Replace. Installed new tripper Viv. 2HG009 found broke, fingers.

L65711 2B HPCS DG Oil Temp Erroneous Readings. Replace. New switch installed and SW Element 2E22-N511 calibrated.

DOCUMENT ID 0036r/0005r

TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS MODIFICATION NUMBER: A brief Synopsis of Incorporated Modification Objectives with final design resolution. Also, state reviewed or unreviewed safety questions.

Below is a list of Safety-Related Modifications which were completed from February 1, 1987 to February 28, 1987.

M-1-2-83-012 - This Modification was to install the EMD Maintenance Instruction 9644 Lube oil Modification on Diesel Generators lA, IB, 0, 2A & 2B. There were no unreviewed safety questions.

M-1-2-84-090 - This Modification was done to meet license condition 2.c(12)(A), that requires all control and monitoring instruments to be removed from the engine skid, except those instruments that are qualified for this location.

There were no unreviewed safety questions.

M-1-2-84-174 - This modification was to alter the battery rack design to facilitate air gap adjustment between the battery cells and stringers, to within the limits specified by the manufacturer and seismic loading. There were no unreviewed safety questions.

M-1-2-85-020 - This modification deleted the off-cas instruments IN62-N016 and N017, 2N62-N016 and N017. There were no unreviewed safety questions.

f DOCUMENT ID 0036r/0005r

C. LICENSEE EVENT REPORTS The following is a tabular sumanary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, February 1 through February 28, 1987. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Licensee Event Report Number Date Title of Occurrence There were no Unit Two LER's to report during this period.

l l

l I

l l

[

l i

I t

l

[

[

l l

l DOCUMENT ID 0036r/0005r i - - - - - - _ . . _ _ _ _ _ _ . , _ - _ - , _ _ _ _ - - . . . _ _ __

. , . s%

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

1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit shutdowns and Power Reductions 4

i l

l i

I l

i I

1 l

DOCUMENT ID 0036r/0005r

s... .s \

1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE March 10. 1987 00MPLETED BY Gregory Kirchner TELEPHONE (815)357-6761 OPERATING STATUS
1. REPORTING PERIOD: February. 1987 GROSS HOURS IN REPORTING PERIOD: 672
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): 1050
4. REASONS FOR RESTRICTION (IF ANY): Administrative THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 66.05 12069.5
6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 29.83
7. HOURS GENERATOR ON LINE 0.0 59.92 11830.84
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

! 9. GROGS THERMAL ENERGY GENERATED (MWH) 0.0 120864 33635128

10. GROSS EL8C. ENERGY GENERATED (MWH) 0.0 39232 11100804
11. NET ELEC. ENERGY GENERATED (MWH) -7071 20155 10560384
12. REACTOR SERVICE FACTOR 0% 4.7% 58.2%
13. REACTOR AVAILABILITY FACTOR 0% 4.7% 58.3%
14. UNIT SERVICE FACTOR 0% 4.2% 57%
15. UNIT AVAILABILITY FACTOR 0% 4.2% 57%
16. UNIT CAPACITY FACTOR (USING MDC) -1.0% 1.4% 49.1%
17. UNIT CAPACITY FACTOR (USING DESIGN

, MWe) -1.0% 1.4% 47.2%

18. UNIT FORCED OUTAGE RATE 0% 0% 26.2%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

N/A Unit is in shutdown during this period.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP 5/16/87 k

l l

l l

I i

i i DOCUMENT ID 0036r/0005r I

2 AVERAGE DAILY UNIT POWER LEVEL

, , < . .s DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: March 10. 1987 COMPLETED BY: Gregory Kirchner TELEPHONE: (815) 357-6761 MONTH: February, 1987__

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -13 17. -9
2. -13 18. -10 3 -12 19. -9
4. -14 20. -9
5. -11 21. -9
6. -12 22. -9
7. -13 23. -9
8. -13 24. -9
9. -13 25. -9
10. -10 26. -8
11. -10 27. -8
12. -10 28. -9
13. -9 29.
14. -9 30.
15. -9 31.
16. -9 DOCUMENT ID 0036r/0005r

1

3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.' 050-374 UNITNAMELaSalleTwo(*~

DATE March 10, 1987 REPORT MONTH February, 1987 OOMPLETED BY G.J. Kirchner TELEPHONE (815)357-676I METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS /COfGENTS 1 02/1/87 S 672.0 C 1 Ongoing Refuleing Outage DOCUMENT ID 0036r/0005r

g.. o$

E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT There were no safety relief valves operated for Unit #2 during this reporting period.

l l

l DOCUMENT ID 0036r/0005r

g.. .$ 2. scCS Systems outcges The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO. BOUIPMENT PURPOSB OF OUTAGE s

2-546-87 2812-F409B Replace Valve.

2-550-87 2812-C300D Inspect Motor Winding.

2-551-87 2C RHR Prevent Draining Reactor Vessel During Limitorque LES.

4 2-556-87 2812-F004C RHR Suct. Limitorque Surveillance.

2-557-87 2E12-F042C Inj. V1v. Limitorque Surveillance.

2-558-87 2812-F064C Min. Flow Limitorque Surveillance.

2-559-87 2812-F021 Full Flow Test Limitorque Surveillance.

2-562-87 2E21-F023 Limitorque surveil 1ance.

2-565-87 2E12-F042A Repack Valve.

2-566-87 2E12-F336B RHR SW Sys. Repack.

2-569-87 2B12-F027B Repair Position Indication.

2-572-87 2E12-F053A Repair Valve.

2-575-87 2E12-F046B Repair Check Valve.

2-581-87 2E12-F073A Limitorque Surveillance.

2-582-87 2812-F074A Limitorque Surveillance.

2-583-87 2E12-F312A Limitorque Surveillance.

2-584-87 2812-F3128 Limitorque Surveillance.

2-585-87 2A D/G Instrument Calibration.

2-587-87 2812-F041A Replace Air Cylinder.

2-588-87 2E12-F099A Disassemble and Repair.

2-590-87 2E12-F024B E. Q.

2-594-87 2812-F017A Isolate During F016A.

DOCUMENT ID 0036r/0005r

v.. o' OUTAGE NO. BOUIPMENT PURPOSE OF OUTAGE 2-595-8'l 2812-P016A Limitorque Surveillance.

2-596-87 2812-P073B Limitorque Surveillance.

2-597-87 2E12-P026A Limitorque Surveillancs.

2-600-87 2A D/G Peed HACR - Relay Inspection.

2-606-87 2E22-P001 Limitorque Surveillance.

2-623-87 2812-B001A/2A RHR Hydrolaze Heat Exchanger.

Heat Exchanger 2-624-87 2812-B001B/2B RHR Hydrolaze Heat Exchanger.

Heat Exchanger

2-625-87 2B12-PO46C/2C RHR Inspect Valve.

Min Flow Check Valve 2-652-87 2H13-P609 and 2H13-P611 Inspect and Repair RPS Logic Terminations and separation of scram contactor wiring.

2-653-87 B-RHR Lube.

2-654-87 C-RNR Lube.

2-657-87 2812-PO41C 2E12-PO41C Repair.

2-662-87 2E12-P0178 Limitorque Inspection.

2-680-87 2E12-PO41A Testable Cycle and Adjust Valve.

Check Valve 2-681-87 2E12-PO41B Testable Troubleshoot and Adjust Check Valve Valve.

2-690-87 RHR to R/W Relocate 2RE043, 2-705-87 2812-P006 RHR Limitorque Surveillance.

2-710-87 2A RHR S.W. Pump Breaker Inspection.

2-711-87 2B RHR S.W. Pump Breaker Inspection.

2-713-87 2851-PO46 Brush Inspection.

2-714-87 2851-P019 Brush Inspection.

DOCUMENT ID 0036r/0005r i

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

s .

zj , . i '-

)

OttfAGE NO. BOUIPfW I PURPOSE OF. OUTAGE ..

715 2851-F022 ~'" '-

Brush Inspection., i

^ 1.

710 .2851-F031 BrushInspection['

2-717-87 2851-F068 Brush Inspection.

u1 ,

2-718187 2851-F059 t' Brush Inspectiors.

2-719-87 3tE51-F610 ~1trush Inspection. ,

1

.g 2-733-87 2A D/G. ,

Move Switches 519A & 55A.

2-734-87 2A D/G Calibrate Instrument.

2-735-87 A'.HR SDC Leak Place Stret.ss' Relief Equip.

DH ection Lines od SDC Line.

}

2-746-87 D'iv. II.RHR Water Leg Pump, Lube Coupling. , ,

2-751-87 'O' D/G CocIi.g Water E.Q. Prot. ,

Pump Feed Movats Testing. ' '

2-755-87 2851-F010 N'

2-759-87 2E12-F015 ,

Novets; Testing. [

2-760-8') 1851-F063 Movats Testing..,

2-761-87 2E51-F076 Novets *'esting.

2-762-87 2E51-F008 Novats Testing.

2-763-87 2851-F064 Novats Testing.

2-771-87 2B D/G ,

Clean & Inspect Check Valve.

i 2 ~172 2A/2B RHR WS Pumps Clean & Inspect 2E12-F331A.

2-788-87 2B21-C001 LPCS Pump Calibrate Relays & Perform '

l Functionals on Breakers.

I s t g 2-794-87 2A D/G - -a Calibrate Relays & Perform Functionals on 1;reakers.

l

\

s

~

. . + +

l . ,

i I%

~

f TK/h ID 0036r/0005r c ,

3._ ;>

-V . . 3. Off-Sito Dose C*:lculatink Manual There were no changes to the ODCM during this reporting period. e

4. Radioactive Waste Treatment Systems.

There were no changes to the Radioactive Waste Treatment Systems.

during this reporting period.

5. Indications of Failed Fuel Elements.

There were no indications of failed fuel elements during this reporting period.

?

's g -

DOCUMENT ID 0036r/0005r

Commonwealth Edison

.M -O c LaSalla County Nucitar Station

-,; Ruril Routa #1, Box 220 V Marseilles. Illinois 61341 Telephone 815/357-6761

.(

f; March 10, 1987 ly

.r Director, Office of Management Information and Program control United States Nuclear Regulatory Cceamission Washington, D.C. 20555 ATTW: Document Control Desk Gentlemen:

Enclosed'for your information is the monthly performance report covering LaSalle County Nuclear Power Station for the period February 1, 1987 through February 28, 1987.

very truly yours, A9. &

G. J. Diederich Station Manager LaSalle County Station GJD/GJK/msh Enclosure 1

xc: J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nucl6ar Safety

- A. Bournia, letR Project Manager D. P. Galle, CBCo D. L. Farrar, CBCo IMPO Records Center

^

L.. J. Anastasia, PIP Coordinator SNBD M. A. Ortin, GE Resident H. E. Bliss, Nuclear Fuel Services Manager-C. F. Dillon, Senior Financial Coordinator,'LaSalle l: J. C. Klika, Surveillance Group Leader 9 Central File \

' I l i DOCUM NT ID 0043r/0005r

-________s___- .. . - - _

_ _ _ _ _ _ _ - - - _ _ _ _