ML20027E425
| ML20027E425 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 11/05/1982 |
| From: | Ullrich J COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20027E424 | List: |
| References | |
| NUDOCS 8211150222 | |
| Download: ML20027E425 (17) | |
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LASALLE NUCLEAR POWER STATION UNIT l' MONTHLY PERFORMANCE REPORT OCTOBER, 1982 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 i
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8211150222 821105 PDR ADOCK 05000373 R PDR
TABLE OF CONTENTS
- 1. INTRODUCTION
- 11.
SUMMARY
OF OPERATING EXPERIENCE FOR UNIT ONE Ill . PLANT OR PROCEDURE CHANGES, TESTS, EXPERlHENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facili ty License or Technical Speci fications B. Facility or' Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approval D. Corrective Maintenance of Safety Related Equipment 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 Stean Relief Valve Operations B. ECCS System Outages C. Off-Site Dose Calculation Manual Changes l 0. Major Changes to Radioactive Waste Treatment System E. Changes to the Process Control Program l
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- 1. INTRODUCTION The 'LaSalle Nuclear Power Station Unit One is a Bolling Water Reactor with a designed electrical output of 1078 MWe net, ,
located in Marseilles, Illinois. The Station is owned oy Commonwealth Edison Company. The Architect / Engineer was Sargent s Lundy, and the primary construction contractor was Commonwealth Edison Company.
The condenser cooling method is a closed cycle cooling pond.
The plant is. subject to License Number NPF-11, issued on April 17,1982. The date of initial criticality was June 21, 1982. The unit has not commenced commercial generation of power.
J This report was compiled by John Ullrich, telephone number (815)357-6761,- extension 481.
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SUMMARY
OF UNIT OPERATING EXPERIENCE FOR UNIT ONE October 1-2 The unit started the reporting period at a load of 1501MWe. At 0129 on October 2 the load was reduced to O MWe and the main turbine was secured so that STP-71 "RHR Steam Condensing" could be performed. At 1405 on October 2 the main generator was synchronized to the grid and load increased to 150 MWe.
October 2-6 Load was maintained at approximately 150 MWe until 1150 on October 6 when the Unit was manually scrammed due to low reactor water level. The cause of the low water level was the loss of all the feedwater pumps due to inadvertently shorting out the low suction pressure interlock while troubleshooting. Reactor vessel water level was restored by RCIC and the motor driven feed water pump.
October 9-19 heactor was brought critical at 2215 on October 9 At 2115 on October 10 the main generator was synchronized to the grid and load increased to 140 MWe. At 1345 on October 17, load was increased slowly until 300 MWe was reached at 2100 on October
- 18. At 1111 on October 19 load was reduced to O MWe and the main turbine was secured to repair a steam leak on the First Stage Pressure sencing line.
October 20-31 At 0345 on October 20 the main generator was synchronized to the grid and loaded to 135 MWe. By 1500 load was increased to 365 MWe. At 1600 on October 22 load was increased slowly until at 0845 on October 24 load was at 490 MWe. At 0346 on October 29 load was decreased to 450 MWe due to Condensate Polisher problems.
Due to these CP problems by the end of the reporting period, load was reduced to 400 MWe.
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. lit. PLANT OR PROCEDURE CHANGES-, TESTS, EXPERIMENTS AND SAFETY RELATED ' C 0 *
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MAINTENANCE -
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A. Amendments to Facility License or Technical SpdcifIcations, s
} 4 AMENDMENT 5 Thisl Amendment consists of changes to the
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Technical Spec] fications. The changes to the Technical Specifications were as folloh~J[ (1) demonstrate the RCIC system is operable" at least every 18 months, by verifying, using the test flow. , y path, that the system is capable of delivering a flow greater 3
than or equal to 500 gpm to the reactor vessel whdh steam is i 3'
supplied to the turbine at a pressure of 150M15 psig, and -
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(2) allow the use of initial startup test data for determinin~g i equivalent flows in the RCIC test line aaE v$ssel injection 3 ,
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I AMENDMENT 6 This Amendment consists of;Fa change to the Technical Specifications to include the Uni't 2 Service Water System Effluent Line Radiation Monitor (2D18-K608) in Tables
{ 3.3.7.10-1 and 4.3.7.10-1 of Specification 3 3. 10.
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- AMENDMENT 7 This Amendment consists of a change to paragraph -
i 2.C(30)(o) of th6 Facility Operating License No.(NPF-11. The.
i i change is as follows: ,'
Upgrade Emergency Support Facilitics'(ill.A.1.2, SER, SSER#1)
The licensee shall complete its Emergency Response Facilities as follows: N, g
(i) Safety Parameter Display System T Decembe r 31, 1982 i <
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(ii) Emergency Operations Facility Decembe r 31, 1982 '
(iii) Technical Support Center October 1,1982 l
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s Ill. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE (CONTINUED) i W
AMENDMENT 8 This Amendment consists of a change to Technical Specification 6.1; Organization, Review, investigat!on and
, Audit. This change specifies the requirements for the Operating Assistant Superintendent.
B. Facility or Procedure Changes Requiring NRC Approval.
There were no facility or procedure changes requiring NRC approval during the reporting period.
1 C. Tests and Experiments Requiring NRC Approval.
There were no tests or experiments requiring NRC approval during the reporting period.
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D. Corrective Maintenance of Safety Related Equipment.
The following tables present a summary of safety-related maintenance completed on Unit One during the reported period.
! The headings indicated in this summary include: Work Request Numbers, LER Numbers, Component Name, Cause of Malfunctions, Results and Effects on Safe Operation, and Corrective Action.
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LER C0llP0flEllT CAUSE OF HAl.FullCTIO!! RESULTS APID EFFECTS CORRECTIVE ACT10ll WORK REQUEST Oil SAFE OPERATl0ll -
L11690 ---
GPS-VE145 Pressure Switch out-of- Did not operate within Recalibrated switch adj ustmen t acceptable limits L18616 ---
APRM Channels Channels out-of- Showing greater than the Recalibrated adj us tment 4% tolerance limit APRM recorders L18930 ---
'0' D/G Fuel Gauge o0't-of-adj us tmen t Pressure reading low Recalibrated gauge Pressure L19083 ---
Div 1 Suppression Blown fuse Thermocouple ? 5 F differ- ' Replaced fuse and
f Pool Temperature ence from others in same meter movement 4 well L19096 1 ---
Rx Vessel' Low Level Bad R.H. and L.H. switch Switch setpoint is non- Replaced R.H. and Scram Switch re pet i t i ve L.H. switches L19267
'C' Rx Bldg Vent Bad G.M. tube Detector reading about 10 Replaced G.M. tube Exhaus t Rad Moni tor times what other channels
, are ' reading
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'D' Fuel Pool Bad G.M. tube Indicates a factor of 5* Replaced G.M. tube
. Exhaust Rad Element over other 3 units .
L19439 82-133/03L-0 IC RHR SW Pump Bad motor Motor tripped and set of/ Replaced motor smoke detector L19507 82-114/01T-0 B RHR SW PRM Sump Blown Gasket Pump leaks Replaced gasket Pump L19540 82-115/03L-0 HPCS Testable Check Actuator spring loose Valve stuck open Wound spring Bypass Valve L19541 82-115/03L-0 HPCS Testable Check Reciprocat ing parts Valve stuck open Cleaned and lubri-Valve dirty , cating all recipro-
- I cating parts
' Replaced outboard L19546 ---. '1 A' RHR Service Bad Outboard bearing Caused high vibration Water Pump bearing L19580 ---
"1B' Nain Steam Instrument out of- Monitor reading about Reca li brated Line Rad Monitor tole rance 50-60% as high as other Instrument 3 monitors
VORK REQUEST LER C0llP0i1EllT CAUSE OF HALFullCTIO!! RESULTS AllD EFFECTS CORRECTIVE ACTI0ff O!! SAFE OPERATl0ll -
L19600 ---
SBGT Flow Recorder Instrument out of Reads 200 cfm when there Recalibrated calibration is no flow instrument
.L19617 82-117/03L-0 U-1 Div i 125 VDC Blown fuse and bad Charger not putting any Replaced fuse and Charger ampli fier board amps out ampli fier board L19637 ---
ADS 'E' Accumulator Loose sM tch Control room alarm is up Tightened switch Low Pressure L19642 ---
1B RHR Service Existing oiler too large Oiler cannot be set to Replaced oiler d Water Pump maintain proper oil level O in bearing housing L19643 J ---
IA RHR Service Existing oiler too large Oiler cannot be set to Replaced oiler f Water Pump maintain proper oii level in bearing housing L19687 ---
LPRM'3B-48-41 Bad LPRM card LPRM indicating high Replaced LPRM L19708 ---
'A' VE Air Conden- Back pressu e regulator Operating at 1/2 capacitjy Adj usted back ser Compressor out -o f-a dj us t men t -
pressure regulator L19714 ---
Intermediate Range T ran s i ent times too When switching IRM's from GE is investigating Monitor short range 6 to 7, get a momeri- problem tary half scram L19770 82-125/03 L-0 Div 11 Fuel Pool Bad K2 relay Back panel drawers showed Replaced K2 relay Radiation Hi-Hi no trip lights or upscale Alarm indication L19778 ---
LPRM 08-49C Bad LPRM card LPRM channel failed Replaced LPRM card downscale I
L19865 82-135/03L-0 'B' Rx Bldg Vent Bad GM tube Mbnitor dri fting upward Replace GM tube Exhaust PRM L19866 ---
'O' D/G Ventilation Blown fuse Con t ro l le r wi l l not ope r- Replace fuse ate outside ai r damper L19874 82-134/03L-0 U-1 Rx Bldg Closed damper ' Vent i lation wi ll not mr.i n- Opened damper Ventilaton D/P tain Rx Bldg at less than
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VORK REQUEST LER C0llPO!1EllT CAUSE OF MALFullCTI0li RESULTS AND EFFECTS CORRECTIVE ACTI0ff 011 SAFE OPERATION .
L19876 ---
Steam Tunnel Hi AT Selec' tor switch dirty H _i AT a l a rm up. Indica- Cleaned s.slector Alarm tion also shows hi switch
.L19974 ---
Div I Post LOCA Broken pen drive motor Excessive noise and Repaired pen drive Mon i to r scribbles all ove. paper motor 46 O,
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IV. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, occurring during the reporting period, October I to October 31, 1982. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in section 6.6.B.1 and 6.6.B.2 of the Technical Speci fications.
Licensee Event Report Number Date Title of Occurrence 82-111/03L-0 9/27/82 Main Steam Leak to Radwaste Reboller 82-112/03L-0 9/29/82 Rx. Vessel Low Water Level Scram, Primary Containnent Isolation 82-113/03L-0 8/16/82 D Fuel Pool Vent Rad Monitor 82-114/01T-0 10/5/82 Potential Safety Concern Identi fied by Independent HVAC Review 82-115/03L-0 10/5/82 Failure to Close of the HPCS Testable Check and Testable Check Bypass valves 82-116/03L-0 10/5/82 Failure of U-1 Containment Cam IPL75J 4
82-117/03L-0 10/8/82 Loss of Unit 1 Division 1 125V Battery Charger 82-118/03L-0 10/8/82 Station Ventilation Stack Process Radiation Moni tor 82-119/03L-0 10/10/82 "0B" VC Control Room Air Condition System 82-120/03L-0 10/10/82 "1A" OG Hydrogen Analyzer 82-121/01T-0 10/12/82 Potential Safety Concern Identified by Independent HVAC Review 82-122/03L-0 10/6/82 Failure of Lake Blowdown Flow Recorder 82-123/03L-0 10/6/82 Inoperable Mechanical Snubber 82-124/03L-0 10/16/82 Flow Recorder 0FT-WL001 Inop 82-125/03L-0 10/16/82 Failure of Monitor 1018-K615D 82-126/03L-0 10/17/82 T Factor Too Low (.92)
IV. LICENSEE EVENT REPORTS (CONTINUE 0)
Licensee Event Report Number Date Title of Occurrence 82-127/03L-0 9/20/82 Degradation of Spent Resin Tank Influent Header 82-128/03L-0 10/18/82 Failure of U-2 SBGT System Heaters to Energize 82-129/03L-0 10/18/82 Weld Leaking on Line ICB30AC 3/4" 82-130/03L-0 10/19/82 Vald Leak on "1 A" CD/CB Pump Vent 82-131/03L-0 10/19/82 "16A" Feedwater Heater Plug Leak 82-132/03L-0 10/4/82 "1B" RHR SW Process Rad Monitor 82-133/03L-0 9/30/82 "C" RHR SW Pump Hotor Failure 82-134/03L-0 10/21/82 Rx Building Vent 26P Inadequate 82-135/03L-0 10/21/82 Drifting of Rx Bldg Vent Rad Monitor IB
- 82-136/03L-0 10/22/82 Loss of Primary Containment 82-137/03L-0 10/26/82 Trip of Recirc Pumps from Fast Speed 82-138/03L-0 10/26/82 Reactor Vessel Low Low Water Level MSIV isolation 82-139/03L-0 10/30/82 Div ll Post LOCA 82-140/03L-0 10/30/82 P ret reatment Sample Line Purging
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4 V. DATA TABULATIONS q The following data tabulations are presented in this report:
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{ A. Operating ~ Data Report l
B. Average Daily Unit Power Level
! C. Unit Shutdowns and Power Reductions i
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- ATTACIDElff D RaviSloh 2 f.. November 13,.1979
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- OPERATING DATA REPORT
- DOCKET NO. 050-3.73
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UNIT LaSalle 1 DATE 11-5-82 J ohn U l l r'i ch COMPLETE 0 8Y TELEPHONE (815)357-6761X481l 5
OPERATING STATUS ..
October 1982 'G rioss Houns IN REPORTING PERICO: 7k6
- 1. REPORTING PERICO. '
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- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 502'* max. DEPEND. CAPACITY (MWo. Net):
- OESIGN ELECTRICAL M ATING (MWo. Net): 1078 I s 3. POWER LEVEL TO WHICH RESTRICTED llF ANY) (MWo.Neth En9
- 4. REA$oNS FCR RESTRICT 80N ilF ANY1: License Condition on HVAC Review THIS MONTH YR 70 DATE ',CUMULATiv E
.............. 662.6 1786.0 1786.O
- 5. NUMBER OF HOURS REACTOR WAS CRITICAL.
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O O S. R E ACTOR R ES ERVE SHUTDOWN HOURS . . . . . . . . . . . . . . . . . . .
' 991.k 991.0
- 7. Hour $ G ENER ATOR ON LIN E . . . . . . . . . . . . . . . . . . . . . . . . . . b l l 0
' 0 0 O
- S. UNIT RESERVE SHUT WN HOURS ...................... ,
~ 9. GROSS THERMAL ENERGY GENER ATED (MWH1 ..............b7bb7I *U#I9.d514 **1008s16 173042 225419 225h19
- 10. GROSS ELECTRICAL ENERGY GENERATED (MWH) . . . . . . . . . . . . .
195't 96 19q146 5
- 11. NET ELECTRICAL ENERGY GENERATED (MWH) ............. 166996 NA NA NA ^
- 12. R EACTOR SE RVICE FACTOR . . . . . . . . . .. . . . . . . . . . . . . . . . . .
- NA NA NA
- 13. REACTOR AVAILASILITY F ACTOR . . . . . . . . . . . . . . .'. . . . . . . .
- NA NA NA
- 14. UNIT SE RVIC E F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
NA NA NA
- 15. U NIT AVAILABILITY F ACTOR , . . . . . . . . . . . . . . . . . . . . . . . . .
NA NA NA !
~ 18. UNIT CAPACITY FACTOR (Using MDC) .....................
NA NA NA
- 17. UNIT CAPACITY FACTOR (Using Design MWel . . . . . . . . . . . . . . . . .
NA NA NA
- 18. UNIT FORCED OUTAGE RATE ......................... ,
- 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND OURATION OF EACHl:
NA
. 20. IF SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP:
- 21. UNITS IN TEST $TATUS (PRIOR TO COMMERCIAL OPER ATION): FORECAST ACHIEVED INITI AL CRITICALITY 6/21/82 INITIAL ELECTRICITY 9/4/82 COMMERCI AL OPERATION 11/15/82 !
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- The Year To Date and Comulative Gross Thermal Energy Generated (MWH) were incorrectly' reported for the month of September 1982 due to a mathematical
[ error. Thesa columns should have read 332645 L
- License restriction
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. LTP-300-7
- Revision 2 '
t - ' November 13, 1979 r
- 5 ATTACHMENT A AVERAGE DAILY UNIT POWER LEVEL 00CKET NO. 050-373 dNIT LaSalle 1 DATE 11-5-8'2
- COMPLETED BY John Ull rich TELEPHONE (815 hq7-6761 1481 MONTH October 1982
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DAY AVERAGE DAILY POWER LEVEL . DAY AVERAGE DAILY POWER LEVEL (MWe-Ne t) (MWe-Net)
- . l. 133 -
17 169
- 2. 50 18. 208
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3 122 19 109' -
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- 4. 127 216 5 137 21. 332
- 6. 60 22. 373 7 -18 23 408
- 8. -18 24. 443 9 -18 25 447
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- 10. -3 26. ' 421
- 11. 123 27 422
- 12. 143 28. 417
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13 in 29 4 10
- 14. iji 30. 397
- 15. 130 31. 397
- 16. 134.
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y -- LTP-300-7
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Revision 2 November 13, 1979 6 .
ATTACllMENT B '*
UNIT SHUTDOWNS AND POWER REDUCTIONS .
DOCKET NO. 050-373
- UNIT NAME LaSalle 1 CTOBER 1982 DATE 11/5/82 REPORT MONTH COMPLETED BY John Ullrich .
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TELEPHONE (815) 357-6761 x48i ,
HETH00 0F SHUTTING DOWN TYPE DURATION THE REACTOR OR F: FORCED CORRECTIVE ACTIONS / COMMENTS (ll0URS) REASON (1) REDUCING POWER (2) .
NO. DATE S: SCHEDULED A 2 Manual scram due to low j..
3 10-6-82 F 105.3 Reactor water leveI caused [~
by the loss of the running '
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VI. UNIQUE REPORTING REQUIREMENTS A. Main Steam Relief Valve Operations for Unit 1 There were no main steam relief valve operations for the reporting period.
4 B. ECCS Systems Outages The following outages were taken on ECCS Systems during the reporting period:
4 Outage No. Equipment Purpose of Outage 1-1624-82 "1A" RHR Service To replace the outboard Water Pump thrust bearing 1-1651-82 "B" RHR Service To repair pump casing leak Water PRM Sample Pump 1-1658-82 "1A" RHR Service To replace the oiler assembly Water Pump 1-1663-82 "1B" RHR S'ervice To replace the oiler Water Pump 1 -1671-82 "BC" RHR Water To lubricate bearings Leg Pump l C. Off-Site Dose Calculation Manual There were no changes to the Off-Site Oose Calculations Manual during this reporting period.
D. Radioactive Waste Treatment System There were no changes to the Radioactive Waste Treatment System during this reporting period.
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VI. UNIQUE REPORTING REQUIREMENTS (CONTINUED)
E. Process Control Program There were no changes to the Process Control Program during this reporting period.
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