ML20206F589

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Mar 1987
ML20206F589
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 03/31/1987
From: Diederich G, Kirchner G
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8704140299
Download: ML20206F589 (38)
v • d • e


Text

. - _--_____-_-

(f"3b sff I

1 I

l 1

1 LASALLE NUCLEAR POWER STATION l

UNIT 1 MONTHLY PERFORMANCE REPORT MARCH 1987 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 l

l LICENSE NO. NPF-ll l

l 1

l l

{

l I

8704140299 870331 PDR ADOCK 05000373 R PDR

- - - - e

=

TABLE OF CONTENTS I. INTRODUCTION II. MONTHLY' REPORT POR 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 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 Failed Fuel Elements DOCUMENT ID 0043r/0005r

1 1

1 I. INTRODUCTION 1

The LaSalle County Nuclear Power Station is a two-unit facility owned by Cosamonwealth 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 niunber 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 704.

l 1

l i

l l

i l DOCUMENT ID 0043r/0005r

e II. MONTHLY REPORT FOR UNIT ONE l l

A. SUfelARY OF OPERATING EXPERIENCE FOR UNIT ONE March 1, 1987 0000 Hours. Rx critical, Generator on-line at 585 MWe.

1220 Hours. Drop 60 MWe to 520 MWe to gather 'A' Recirc data and immediately go up to 585 MWe.

March 12, 1987 2145 Hours Start Shutdown at 50 MWe/hr. Due to High Drywell temperature due to 'B' VP Fan Trip.

March 13, 1987 0950 Hours Generator Off-line.

1020 Hours Rx Subcritical March 18, 1987 0245 Hours Rx Critical March 19, 1987 0206 Hours. Generator synched to grid, ramping at 95 MWe/hr to 380 MWe.

0640 Hours. Upshift 'A' RR pump and ramp to 570 MWe at 35 MWe/hr.

1400 Hours. Unit Scram on load reject, loss of 6.9/4.1 KV from UAT-T141.

March 24, 1987 1750 Hours. Rx Critical March 25, 1987 1450 Hours. Generator synched to grid at 50 MWe and rampling at 35 MWe/hr to 590 MWe.

March 28, 1987 1435 Hours Drop 100 MWe to 500 MWe in order to gather data on 'A' RRR.

1600 Hours Increase to 590 MWe.

March 31, 1987 2400 Hours Generator on line at 605 MWe.

DOCUMENT ID 0043r/0005r

, D. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY REMTED MAINTENANCE.

1. Amendments to Facility License or Technical Specification.

There were no ammendments to the Facility License or Technical Specifications during March, 1987. '

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.

4 DOCUMENT ID 0043r/0005r

, -yr, --.-- -- ,,.- -,9,,,, - - , ,n-- ,cg-<..,, y- ,,,,g ,. g , , ,,-- - ,. - - ,,- _

TABLE 1 .

CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT .

UNIT #1 WORF REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION 39220 Water Tight Door Torn Water Tight Seal Replace Door Gasket Replaced Gasket and

  1. 6 Inspected.

39771 Water Tight Door

  1. 8 39772 Water Tight Door
  1. 15 53449 U-l Refuel Bridge Broken Power Cable Replace Cable Replaced Power Cable IF21-E003 SIN 505E89 56681 VC Damper OVC16YB Actuator Seals Leaking Rebuild Damper Removed / Repaired Oil Actuator Damper Actuator.

58090 Damper OVCl3YB Damper does not cycle Rebuild actuator Rebuilt actuator, verified proper Ops.

58941 'B/C' RHR Conductivity Indicates half scale only Replace cell Installed new cell.

cell IE12-N001B/C probe bent 59039 'A' RHR conductiavity Failed cell cell IE12-N001A 61506 IRM "F" Detector IRM failed downscale. Repair / Replace Replaced Detector IC51-K601F 64848 Main Steam Hi-Flow Switch Erratic Replace switch Replaced switch, differential press assured proper ops.

switch IE31-N008D DOCUMENT ID 0043r/0005r

TABLE 1 .

CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT .

UNIT #1 WORK. REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION 65829 Inlet Damper Does not cycle / binding Repair Repaired, assured IVYO6C proper ops.

65914 High Vent Diff. Trip Circuit Chatters Bad Relay Replaced Relay, Like Temp. Tsol. for Like.

TDS-lE31-N613B 64323 LPCS Water Leg Can not maintain system Bad oriface plate Replaced oriface plate.

pump min flow line pressure.

oriface IE12-D003.

5939 SGTS EFF Low Range Computer Point A834 Reads . Repair Recalibrated and gas signal converter high verified normal ops.

OD18-K501 65955 HCU 30-43 Valve Leaks Replace 111 Valve on Replaced valve ICll-D001 111 30-43 5001 Div II S/P water Chart paper does not Bad drive gear Replaced pinion gear, temp recorder advance lubricated, and verified ITR-CM038 proper ops.

66545 RCIC Test, Check Valve stuck in mid Troubleshoot / repair bad Tightened set screw, viv. lE51-F065 position solenoid set limits assured proper ops.

66566 Div. II Ground Detector Reading High. Repair / Replace Recalibrated, Reads Detector IER-DCO21 normally.

DOCUMENT ID 0043r/0005r

R TABLE 1 .

CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT . i UNIT #1 idORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION 66577 RCIC Isol. Switch Lower Right mounting Replace Replaced bolt, washer, IE31-N007BA bolt missing. nut. Proper torque applied.

66605 1C RHR Full Flow Torque Switch Bad Repair / Replace Repaired and cycled test viv. lE12-F021 valved, sat.

66771 Div. II Supp Pool Paper does not advance Bad clutch Tighten clutch, for proper water temp. Recorder ops.

ITR-CM038 66007 MSIV Leakage Control vent tap stripped Repair Replaced fittings outbd, steam line verified no leakage.

pressure vent IE32-N056.

66008 RHR S/D Cooling Vent connection Repair Replaced fittings, pressure interface stripped verified no leaks.

alarm lE12-N018 66058 1*B' Diesel Gen. Low Oil Level Add Oil Added 1 Pint of oil.

Governor IE22-5001 66075 HCV 26-47 Bad 111 valve Replace Valve Replaced 111 Cartridge valve.

5173 Fuel Zone Level Indicating off scale. Bad transmitter Replaced transmitter and Rec. IB21-R615 calibrated.

66226 HCU 58-23 Bad 111 valve Bad cartridge Replaced Cartridge.

ICl1-D001-111 l

i DOCUMENT ID 0043r/0005r

TABLE 1- .

.I CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT ..

UNIT #1 1dORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION-ON SAFE PLANT OPERATION 6623'l RBM 'A' gain change Gain change. card will Bad OP-AMP Replaced OP-AMP OA2.

card IC51-K605 66238 MSIV. LCV. Bleed Instrument off'-scale Troubleshoot / Repair Recalibrated, verified flow ind. lE32-R653J -proper ops.

DOCUMENT ID 0043r/0005r

TABLE 2 COMPLETED SAFETY REIJ.TED MODIFICATIONS MODIFICATION NUMBER; A brief synopsis of incorporated modification objectives with final design resolution. Also, state reviewed or unreviewed safety questions.

UNIT ONE M-1-1-84-003 This Mcdification allowed the removal of the BCCS injection line testable check bypass valves. There were no unreviewed safety questions.

M-1-1-84-108 This modification increased the size of the north south strut on support ws26-18050 from a PSA-3 assembly to a size PSA-35 assembly in the service water drain line from the RB CCW heat exchangers. There were no unreviewed safety questions.

l f

i i

! DOCUMENT ID 0043r/0005r l __

C. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for

'LaSalle Nuclear Power Station, Unit One, logged during the reporting period, March 1, 1987 through March 31, 1987. This information is provided pursuant to the reportable occurrence reporting requirements as J

set forth in 10CPR 50.73.

Licensee Event Report Nemabed Qal.e. e Title of Occurrence 87-010-00 3/2/87 Reactor Water Level Confirmed ADS switch OOT/ Reject Limit Exceeded /setpoint drift replaced' switch /sent switch to SOR for inspection.

87-011-00 3/7/87 HPCS Water Leg Pump Discharge Check Failure / Surface Irregularities on valve seat / disassembled, inspected, cleaned, and lapped

. valve / tested.

87-012-00 3/11/87 'B' Ammonia Detector Trip.

87-013-00 3/13/87 Drywell ave. temp greater than 135 degrees for greater than eight(8) hours.

87-014-00 3/19/87 Reactor Scram caused by Fault i on 6.9/4.1 KV Feed to Unit Aux transformer TR-141.

87-015-00 3/28/87 Failure of RCIC Water Leg Pump.

l l

l i

DOCUMENT ID 0043r/0005r I

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

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 1

1 i

DOCUMENT ID 0043r/0005r

1. OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE April 10. 1987 COMPLETED BY Qragory Kirchner TELEPHONE (815)357-6761 OPERATING STATUS
1. REPORTING PERIOD: March. 1987 GROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3.}23. MAX DEPEND CAPACITY (PRie-Net ) : 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): 1050
4. REASONS FOR RESTRICTION (IP ANY): Administrative THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 495.45 1752.60 17445.35 s
6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1642.0 (
7. HOURS GENERATOR ON LINE 462.54 1637.94 16787.37
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 827328 3629592 44214514
10. GROSS ELEC. ENERGY GENERATED (MWH) 262538 1182680 13873357
11. NET BLEC. ENERGY GENERATED (MWH) 248654 1134565 13157139
12. REACTOR SERVICE FACTOR 67% 81.0% 61%
13. REACTOR AVAILABILITY FACTOR 67% __81.0% 67%
14. UNIT SERVICE FACTOR 62% 76% 59%
15. UNIT AVAILABILITY FACTOR 62% 76% 59%
16. UNIT CAPACITY FACTOR (USING MDC) 32% 51% 45%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 31% 49% 43%
18. UNIT FORCED OUTAGE RATE 38% 21% 15.2%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF BACH) 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 DOCUMENT ID 0043r/0005r

2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 I UNIT: LASALLE ONE DATE: April 10, 1987 COMPLETED BY: Gregory Kirchner TELEPHONE: (815) 357-6761 MONTH: March, 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)
1. 562 17. -14
2. 564 18. -14 3 566 19. 153
4. 565 20. -13
5. 569 21. -13
6. 572 22. -13
7. 570 23. -13
8. 568 24. -13
9. 569 25. 77
10. 570 26. 533
11. 570 27. 560
12. 559 28. 572
13. 71 29. 567
14. -14 30. 574
15. -14 31. 581
16. -14 DOCUMENT ID 0043r/0005r
3. UNIT SHUTDOWNS AND POWER REDUCTIONS .

DOCKET NO. 050-374 UNIT NAME LaSalle One DATE April 10, 1987 REPORT MONTH March, 1987 COMPLETED BY G.J. Kirchner TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS / COMMENTS 4 3/13/87 F 112:25 A 3 Hi Drywell Temperature 5 3/19/87 F 123:50 A 3 Load Reject due to Electrical fault on 6.9/4.1 KV Bus.

DOCUMENT ID 0036r/0005r

E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations for Unit One.

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

.i i

}

l i

i l

1 i DOCUMENT ID 0043r/0005r

_ _ . ~ . __ _ _

2. ECCS Systems Outr.ges l The following outages were tak:n on ECCS Syatens during the reporting period.

OUTAGE NO. BOUIPMENT PURPOSE OF OUTAGE 01-88-87 HPCS Water Leg Pump Repair Valve Discharge check Valve 1822-F007 01-106-87 1E12-F009 Inspect Wash Gasket l 01-111-87 1E12-F063A Fill "A" RHR 01-114-87 IE12-F042C Repair Torque Switch 01-122-87 Div. I Water Leg Pump Repair Orifice 01-146-87 IE12-F074A Repair Leak 01-148-87 1812-F073A Repair - Set Limits DOCUMENT ID 0043r/0005r

-3. .Cff-Sito Dos) C01culction Manual There were no changes to the ODCM during this reporting period.

4. Radioactive Waste Treatment Systems.

There were no changes to the Radioactive Waste treatment systems during March, 1987.

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

I i

I a

I l

DOCUMENT ID 0043r/0005r i

I i

)

i 4

1 LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT MARCH, 1987 COfMONWEALTH EDISON COMPAN'1 4

NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 i

4 l

i i

i i

i DOCUMENT ID 0036r/0005r

TABLE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT TWO A. Sununary 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 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 Waste Treatment System
5. Indications of Failed Fuel Elements I

P i

DOCUMENT ID 0036r/0005r

-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 4

contractor was Commonwealth Edison company.

Unit two was issued operating license number NPP-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 Gregory J. Kirchner, telephone number (815)357-6761 extension 704.

'1 b

i i

1 ,

i DOCUMENT ID 0036r/0005r

1

. 11. MONTHLY REPORT FOR UNIT TWO A. SUpWUutY OF OPERATING EXPERIENCE FOR UNIT TWO March 1. 1987

  • 0000 Hours - Rx Subcritical, Refuel in Progress.

March 31. 1987 i

/ l 2400 Hours Rx subcritical, Unit still in refuel anode.

l l

DOCUMENT ID 0036r/0005r

, - .. . = -- - ._ , _ . .

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

1. Amendments to Facility license or Technical Specification.

There were no amendments to the facility license of Technical Specification during March, 1987.

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.

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.

i DOCUMENT ID 0036r/0005r l

TABLE 1 ,

CORRECTIVE MAINTENANCE OF.

SAFETY RELATED BQUIPMENT ,

Unit #2

. WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION-36017 LPRM 40-25-B Failed Downscale Repair Replaced Cable connector.

2C51-K605BM 39070 LPRM 48-09C-6C Failed Downscale Repair Replaced Detector.

2B13-D193GH 50143 MS High Flow Root Vlv. Valve Leaks Dissassemble and repair Lapped seat and rewelded 2B21-F3220 bonnett to valve.

5'1312 RHR Conductivity Broken Probe Replace Installed new probe and probe CE-2E12-N001A tested.

54550 2B D/G Immersion Dual indication on Bad Aux. Contact on Installed new contact

(

heater heater on contactor assured proper ops.

55241 LPRM OB25A LPRM Drifts Re-Adjust and Calibrate Replaced LPRM string.

58318 LPRM 2425A LPRM Failed 61912 Valve 2E12-F068A Water Leaking from Repack Valve Repacked Valve and packing. cycled properly.

62645 Div II S/P temp Not mounted securely Repair Mounted securely per Recorder 2TR-CM038 design.

1 E378 LPRM 4817B Reads Downscale. Troubleshoot and repair. LPRM string replaced. l l

5380 LPRM 08-33D LPRM has drifted upscale. Installed new test i resistor and verified

]

proper ops. 1 1

64491 MS1V LCS outbd. Valve Valve operator drawing Repair / Lube valve stem Repacked valve stem and f 2E32-F006 high running current, verified proper ops.

i l

l 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 64539 Bus 242Y U.V. Relay U.V. Relay tripped below Replace Relay Installed new relay.

2427-AP040A setpoint.

64613 MSIV outboard LC Declutch mechanism broken Replace mechanism Mechanism replaced.

j VLV. 2E32-F003A f 64616 MSIV-LCS OTBD VLV. Handwheel declutch tripper Repair / replace Repaired valve and 2 2832-F003J fingers missing. Verified cycled operation.

64637 O.L. B/P Relay Relay (HMA) Did not. drop Bad relay Replaced the relay 2E12-KX60A out. '

assured proper ops.

64648 MSIV outboard L.C. Declutch lever will not Troubleshoot and repair. Valve repaired and valve 2E32-F0038. engage. observed proper cycle.

64649 MSIV outboard L.C.

! valve 2E32-F003N 64732 RPS MG set av Unable to calibrate meter Verify proper isolation. Replaced meter like for voltmeter 2C71-R902B like.

I j 64847 ACB 2433 Trip fuse Holder is cracked Replace. New fuse holder.

holder. Installed.

U938 28 D/G inspection Valve inspection cover- Replace gasket as required Installed new head cover deck cover flange leaking. seal.

2E22-S001.

65000 Mechanical Snubber Snubber Damaged Replace New Snubber Replaced.

M504-2769S 65001 Mechanical Snubber Snubber Damaged Replace New Snubber Replaced.

M500-2014S 65002 Mechanical snubber snubber. Dam.sged Replace New Snubber Replaced.

RH42-2969S DOCUMENT ID 0036r/0005r

TATLE 1 ,

CORRECTIVE MAINTENANCE OF SAFETY RELATED BQUIPMENT ,

Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION 65003 Mechanical Snubber Snubber Damaged Replace New Snubber Replaced.

RI41-2803S

65004 Mechanical Snubber Snubber Damaged Replace New Snubber Replaced.

] FWll-2803S l 65005 Mechanical Snubber Snubber Damaged Replace New Snubber Replaced.

MSO4-2846S 65145 Mechanical Snubber Snubber Damaged Replace New Snubber Replaced.

RH03- 2867S 65146 Mechanical Snubber Snubber Damaged Replace New Snubber Replaced.

RH03-2855S 65547 Mechanical Snubber Snubber Damaged Replace New Snubber Replaced.

RH42- 2971S 65148 Mechanical Snubber Snubber Damaged Replace New Snubber Replaced.

RI41-2834S 65149 Mechanical Snubber Snubber Damaged Replace New Snubber Replaced.

RH03-2863S 65150 Mechanical Snubber Snubber Damaged Replace New Snubber Replaced.

RH40-28953 65152 Mechanical Snubber Snubber Damaged Replace New Snubber Replaced.

l RH40-2897S 65153 Mechanical Snubber Snubber Damaged Replace New Snubber Replaced.

RH40-290lS 65154 Mechanical Snubber snubber Damaged Replace New Snubber Replaced.

RH40--2904S 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 65155 Mechanical Snubber Snubber Damaged Replace New Snubber Replaced.

RH40- 2918S 65157 Mechanical Snubber Snubber Damaged Replace New Snubber Replaced.

RH04- 2821-S 65292 Mechanical Snubber Snubber Damaged Replace New Snubber Installed.

RHB5 -2499 -S 65293 Mechanical Snubber " " "

1 RH23-2825-S f

1 65294 Mechanical Snubber " "

RH40-2866-S 65295 Mechanical Snubber "

RH21-2997-S 65301 Mechanical Snubber " " "

RHA3-2976-S 65302 Mechanical Snubber " " "

RH12-2806-S 65362 Mechanical Snubber " " "

RH53-2851--S 65363 Mechanical Snubber RH14-2833 S 65364 Mechanical Snubber " " "

RH14-2860-S DOCUMENT ID 0036r/0005r

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 65365 Mechanical Snubber "

RH53-2848-S 65424 Mechanical Snubber HP09 2812-S 65425 Mechanical Snubber 2HP20-2800S 65499 LPRM 32-57B Failed Upscale Troubleshoot / Repair Cable / connector found bad. replaced with new.

65500 Pressure retalning Six(6) Loose nuts Tighten Torqued six(6) bolts to bolting on 2812-F050n found 230 Ft. Ibs.

! 65557 MCC 235X-1(Al) Reversing contactor Bad Mechanical Repaired and verified valve 2VQO26 sticks Interlock proper Ops.

65640 Mechanical Snubber Snubber Damaged Replace New Snubber Installed i RR28-2817-S 65641 Mechanical Snubber NBAl-2001-S 65642 Mechanical Snubber RRC7-2013-S 65643 Mechanical Snubber NB13-2807-S 65676 Steam Line Isol. 74 Relay will not Found O.L. Relay Replaced overload relay.

Viv. 2E12-F087A reset, sticking.

74-Relay.

DOCUMENT ID 0036r/0005r

, w TABLE 1-r CORRECTIVE MAINTENANCE OF ,

SAFETY RELATED EQUIPMENT Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION 65730 Mechanical Snubber Snubber Damaged Replace New Snubber installed.

TR01-2851-S 65743 Mechanical Snubber RR00-2044-S G5746 U-2 Radiation Paper will not advance Bad drive motor Replaced drive motor l Recorder 2D18-R800 and verified proper ops.

! 65892 Mechanical Snubber Snubber Damaged Replace New Snubber installed.

RHGS-2999-S 65920 Spare Breaker A3 Center leg on breaker Replace Circuit Breaker New circuit breaker on MCC 235x-1, is damaged. Installed. Magnetics 2AP71E. set at 800 Amps.

65997 Mechanical Snubber Snubber Damaged Replace. New Snubber installed.

RIA4-2994-S 65998 Mechanical Snubber MS00-2031-S 66034 Gross Gamma Recorder Out of Tolerance Faulty AMP Card. Replaced Amp Card and 2RR--CM011 calibrated.

66204 2A D/G Fuel Oil Day Sticky Limit Switch Troubleshoot / Repair Calibrated and adjusted-tank level switch micro switch mechanism.

2LS-DOOO4. Verified proper' Ops.

5355 RHR Pump 2C Discharge Unable to calibrate during "

Replaced with a new Press. Hi switch surveillance. switch, calibrated and 2E12-N022C leak tested at 600 psi.

66679 Mechanical Snubber Snubber Damaged Replace New Snubber installed.

RH27--H058-S .

DOCUMENT ID 0036r/0005r

TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS tE2PlE19ATI9tLHU!EHgt2 A brief Synopsis of Incorporated Modification Objectives with final design resolution. Also, state reviewed or unreviewed safety questions.

UNIT TWO M-1-2-82-012 This modification allowed for the addition of downgraded voltage protection to busses 241Y and 242Y. There were no unreviewed safety questions.

M-1-2-84-085 This modification allowed for the removal of the woodruff keys that engages the worm shaft to the worm gear. This will prevent manual positioning of the air-operated control valves. There were no unreviewed safety questions.

M-1-2-84-175 This modification was to modify the battery racks to bring the gaps on the end of each row within acceptable limits.

There were no unreviewed safety questions.

M-1-2-86-040 This modification was done to add a high point vent to the existing piping of the RHR System line 2RH33A-16. These vents were added to improve pipe venting which will reduce the potential of water hammer and possible snubber damage.

There were no unreviewed safety questions.

M-1-2-86-057,M-1-2-86-052, M-1-2-86-056 These Three(3) Modifications were to re-analyze piping subsystems 2RRC1, 2RRA7, and 2RRC3 respectively, to eliminate as many mechanical snubbers as possible under the snubber reduction program. There were no unreviewed safety questions.

]

DOCUMENT ID 0036r/0005r

C. LICENSEE EVENT REPORTS The following is a tabular sununary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, March 01, through March 31, 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 87-003-00 3/7/87 Continuous conductivity Monitor INOP 87-004-00 3/25/87 SRV's S,P, and M failed to meet setpoint tolerance.

l

[.

i l

I I

DOCUMENT ID 0036r/0005r l

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 l

i DOCUMENT ID 0036r/0005r

1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE April 10. 1987 COMPLETED BY Gregory Kirchner TELEPHONE (815)357-6761 OPERATING STATUS
1. REPORTING PERIOD: March. 1987 GROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):1223 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. GROSS THERMAL ENERGY GENERATED (MWH) 0.0 120864 33635128
10. GROSS ELEC. ENERGY GENERATED (MWH) 0.0 39232 11100804
11. NET ELEC. ENERGY GENERATED (MWH) -8074 12081 10552310
12. REACTOR SERVICE FACTOR 0% 3% 56.2%
13. REACTOR AVAILABILITY FACTOR 0% 3% 56.3%
14. UNIT SERVICE FACTOR 0% 2.7% 55%
15. UNIT AVAILABILITY FACTOR 0% 2.7% 55%
16. UNIT CAPACITY FACTOR (USING MDC) -1.0% 0.5% 47.4%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) -1.0% 0.5% 45.5%
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 DOCUMENT ID 0036r/0005r

'2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: ADril 10.-1987 COMPLETED BY: Gregory Kirchner TELEPHONE: (815) 357-6761 MONTH: March 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -8 17. -14
2. -8 18. -13 3 -9 19. -13
4. -9 20. -13
5. -8 21. -12
6. -7 22. -13
7. -8 23. -12
8. -9 24. -11
9. -10 25. -11
10. -10 26. -9
11. -10 27. -10
12. -9 28. -8
13. -12 29. -8
14. -13 30. -9
15. -14 31. -9
16. -14 DOCUMENT ID 0036r/0005r
3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAME LaSalle Two -

DATE April 10, 1987 REPORT MONTH MARCH, 1987 COMPLETED BY Gregory Kirchner TELEPliONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTGR OR CORRECTIVE NO. DATE S: SClfEDULED (IIOURS) REASON HEDUCING POWER ACTIOtJS/ COMMENTS 1 03/01/87 s 744.0 C 1 Refuel DOCUMENT ID 0043r/0005r

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.

4

)

I l

l l DOCUMENT ID 0036r/0005r l

l

2. ECCS Sy2tems OutEgsa The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO- BOUIPMENT PURPOSE OF OUTAGE 2-807-87 Check Valve 2B12-F050A Repair Viv.

2-808-87 2DG0lP Breaker Inspection 2-809-87 2B12-C300C " "

2-818-87 2A D/G ACB 2423 " "

2-819-87 2B RHR Pump " "

2-828-87 U-2 HPCS Prevent Draining the System 2-834-87 2E22-F005 Troubleshoot and repair.

2-841-87 2A D/G Change Filters 2-842-87 2B RHR Pump Calibrate Relays 2-844-87 2C RHR Pump 2-861-87 MCC 236x-2 F-6 Install overload relay.

2-873-87 2E51-F091 Repair reversing contactor.

2-887-87 2E12-F016A Isolate Drywell spray.

2-917-87 Aux Power Supply to Repair annunciator 2DG03J 2-935-87 2B D/G Lubrication 2-950-87 MSIV 2B21-F033A Replace solenoid.

2-954-87 2E12-F001 RHR Shutdown Hydro SDC Suction Cooling Pressure Tap Header.

2-957-87 Div II Battery Prevent Discharge while Sat Down.

2-971-87 Inboard MSIV 2B21-F022 MSIV Solenoid A/B/C/D Replacement.

2-983-87 HPCS Fuel Oil Day Tank Drill Anti-Syphon hole in pipe.

2-1022-87 2E51-F008 Repack Valve 2-1024-87 2A RHR Shutdown Cooling Repair Weld on Return Line. 2E12-F325A.

2-1027-87 2E12-F006A RHR SDC Repair Grounding Stop Short.

2-1028-87 2E51-F357 Put ned gasket on oriface flanger.

DOCUMENT ID 0036r/0005r

3. Off-Sito Dosa calculation Manum 1 There were no changes to the ODCM during this reporting period.
4. Radioactive Wasts Treatment Systems.

There were no changes to the Radioactive Waste Treatment Systems during March, 1987.

T'

5. Indications of Failed Fuel Elements.

There was one(l) indication of a failed fuel element discovered in March, 1987. This element was identified as LJC-175.

4 4

DOCUMENT ID 0036r/0005r

r .-

, D.

April 10, 1987 Director, Office of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C. .20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for the period March 1, 1987 through March 31, 1987.

Very truly yours, k -

G. J. Diederich Station Manager LaSalle County Station GJD/GJK/msh Enclosure xc: J. G. Keppler, NRC, Region III NRC Resident In9pector LaSalle

Gary Wright, Ill. Dept. of Nuclear Safety A. Bournia, NRR Project Manager D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center L. J. Anastasia, PIP Coordinator SNED M. A. Ortin, CE Resident H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle i J. C. Klika, Surveillance Group Leader Central File DOCUMENT ID 0043r/0005r l

,

Retrieved from "https://kanterella.com/w/index.php?title=ML20206F589&oldid=3014261"