ML20082B979
| ML20082B979 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/30/1991 |
| From: | Cialkowski M, Diederich G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9107170227 | |
| Download: ML20082B979 (27) | |
Text
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- N C:mm:nw:alth Edison
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LaSalle County Nuclear Station
- ! Rura1 Route 81. Box 220
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Marseilles. lilinois 61341 Telephone 815/357 6761 July 10, 1991 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Comission Mail Station PI-137 Mashington, D.C. 20555 ATTN: Document Control Desk Gentlemen:
Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for June, 1991.
Very truly yours, Mm G. J.'Diederich (StationHanager LaSalle County Station GJD/HJC/bkw Enclosure xc: A. B. Davis, NRC, Region III T. M. Tongue, NRC Resident Inspector LaSalle J. L. Roman, IL Dept. of Nuclear Safety J. B. Hickman, NRR Project Manager D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center D. R. Eggett, NED J. E. Kuskey, GE Resident T. J. Kovach, Manager of Nuclear Licensing H. F. Naughton, Nuclear Fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor J. M. Gleseker, Technical Staff Supervisor M. M. Servoss, QA/NS Off Site Review Station File 1
c107170227 910690 _J (
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ZCADTS/S '/
LASALLE NUCLEAR POWER STATION l UNIT 1 HONTHLY PERFORMANCE REPORT JUNE 1991 00HMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 l
l ZCADTS/5
TABLE OF CONTENTS (UNIT 1)
-I. INTRODUCTION II. REPORT A. SUMARY OF OPERATING EXPERIENCE B, AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D. -LICENSEE EVENT REPORTS E. DATA TABULATIONS L 1. Operating Data Report ,
- 2. Average Daily Unit Power Level
- 3. Unit Shutdowns and Power Reductions F. *IQUE REPORTING REQUIREMENTS
.. Main Steam Reller Valve Operations
- 2. ECCS System Outages
- 3. Off-Site Dose Calculation Manual Changes 1
- 4. Major Changes to Radioactive Maste Treatment System
- 5. Indications of Failed Fuel Elements L
l ZCADTS/5
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. e .,
I. INTRODUCTION (Unit 1)-
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 Nater Reactor with a designed net electrical output of
-1078 Megawatts. Haste 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 Cosmonwealth Edison Company.
Unit One was issued operating license number NPF-11 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 complied by Michael J. Cialkowski, telephone number (815)357-6761, extension 2427.
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II, MONfHLY REPORT A.- SU WARY OF OPERATING EXPERIENCE (Unit '> l day lige Event 1 0000 Reactor critical, generator on line at 1100 HNE.
2 0330 Reduced power to 850 W E for system load.
1100 Increased power to 1100 W E.
3 0100 Reduced power to 900 W E for system load.
0630 Increased power to 1090 W E.
4 0200 Reduced power to 850 W E for system load and monthly surveillances.
0900 Increased power to 1085 MNE.
1930 Reduced power to 850 W E for system load and heater drain work.
5 1300 Increased power to 1105 MHE.
6 0200 Reduced power to 850 W E for system load.
1000 Increased power to 1105 W E.
8- 0200. Reduced power to 750 WE for reactor recirculation performance test.
1100 Incteased' power to 1102 WE.
9 0200 Reduced power to 850 W E for system load.
1300 Increased power to 1103 W E.
12 0300 Reduced power to 850 W E for system load.
1000 Increased power to 1100 W E.
j 13- 0400 Reduced power to 850 WE for system load.
0900 Increased power to 1096 W E.
16 0230 Reduced power to 850 W E for system load.
1100 Increased power to 1100 WE.
17 0100 Reduced power to 850 W E for system load.
0900 Increased power to 1093 MHE.
18 0100 Reduced power to 850 WE for system load.
0700 Increased power to 1094 W E.
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I' II. MONTHLY REPORT A. SUMARY OF OPERATING EXPERIENCE (Unit 1) (Continued)
Day Ijag Event __
19 OMO Reduced power to 840 W E for system load.
1100 Increased power to 1069 W E (holding at 1069 W E due !
to condenser derating). 4 20 0400 Reduced power to 950 W E for system load. ;
1000 Increased power to 1080 W E. ;
I i
22 0100 Reduced power to 850 W E for system load.
0700 Increased power to 1070 W E.
2000 Reduced power to 850 WE to remove 2nd stage reheat from service.
23 0900 Increased power to 1090 W E.
24 0100 Reduced. power to 850 W E for system load.
0700- Increased power to 1070 W E.
1000 Reduced power to 970 W E to increase condensate booster suction pressure due to ISA heater level control problems.
2300 Reduced power to 850 WE for 15A heater drain valve work.
25 0800 Increased power to 1098 W E. ;
27 0100 Reduced power to-850 W E for heater bay work.
1600 Increased power to 1107 W E.
.28 0030~ Reduced power to 925 W E for system load.
1000 Increased power to 1070 W E.
30 - 2400 Reactor critical, generator on-line at 950 MHE.
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B. AMENDMENTS TO THE FACILITY LICENSE OR TECHNICAL SPECIFICATION None C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED E()UIPMEN1 (including ,
SOR differential pressure switch failure reports).
(See Table 1) 1 D. LICENSEE EVENT-REPORTS (Unit 1)
LER Number Daig Description 91-008-00 06/13/91 "A" Control Room HVAC/ Aux Electric Equipment Room Ventilation Emergency Make-up fan auto start due to spurious trip signal fan from Control Room Intake Rad Monitor.
l E. DATA TABULATIONS (Unit 1) l l.
- 1. ' Operating Data Report (See Table 2) ]
- 2. Average Daily Unit Power Level (See Table 3)
- 3. Unit Shutdowns and Significant Power Reductions (See Table 4) l L.
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TABLE 4 '
, E.3 UNIT SHUTDGetS AND POMER REDUCTIONS > 201
- j. .(Unit 1)~
l METHOD OF CORRECTIVE YEARLY TYPE SHUTTIIIG DGet ACTI(NIS/CD90lTS
- SECUENTIAL DATE F: FORCED DURATIDst THE REACTOR OR (LERIDWR # if NUISER (YY1900) S: SCHEDULED -(HOURS) REASON REDUCING PONER applicable)
(llone) 4 E
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I SUP94ARY OF OPERATION:
The Unit remained on-line at high power throughout the month. Several minor power reductions were required due to system loading, testing and maintenance activities.
i ZCADTS/5 I1
- l. .
F. UNIQUE REPORTING REQUIREMENTS (Unit 1)
- 1. Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIPTION 0611 8CIMILD 8CTUATION C0HEU10N OF EVEU .
(None) i
- 2. ECCS Systes Outages (See Table 5)
- 3. Changes to the Off-Site Dose Calculation Manual (See Attachment A) i 4. Major-changes to Radioactive Haste Treatment Systems.
(None)
- 5. Indications of failed fuel Elements.
l (None)
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(Unit 1)
'. Table S f.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.
OJIAGE_EQi E001LYLEI INREQSL i 1360 IE22-5001 Remove petter diesel ek; aust line.
1374 1DG01K Inspector governor wiring.
l 1378 IE22-S001 Replace soak back oil filters.
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LASALLE NUCLEAR FO4ER STATION UNIT 2 HONTHLY PERFORMANCE REPORT JUNE 1991 COHHONHEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 ZCADTS/7
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TABLE OF CONTENTS (Unit 2)
I. IN1RODUCTION II. REFORT A. SUHKARY Of OPERATING EXPERIENCE D. AMENDHENTS 10 FACILITY LICENSE OR TECilNICAL SPECIFICATIONS C. MAJOR CORRECTIVE HAINTENANCE TO SAFETY-RELATED EQUIPMENT D. LICENSEE EVENT REf0RTS E. DATA TABULATIONS
- 1. Operating Data Report
- 2. Average Daily Unit Power Level
- 3. Unit Shutdowns and Power Reductions
- f. UNIQUE REPORTING REQUIREMENTS
- 1. Safety / Relief Valve Operations
- 2. ECCS System Outages
- 3. Off-Site Dose Calculation Manual Changes
- 4. Major Changes to Radioactive Haste Treatment Systera
- 5. Indications of failed fuel Elements ZCADTS/7
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- 1. INTRODUCTION (Unit 2)
The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Warsellies Illinois. Each unit is a Bolling Water Reactor with a designed net electrical output of 1078 Negawatts. Haste 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 Ilcense 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 Michael J. Cialkowski, telephone number (815)357-6761 extension 2427.
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2CADTS/7
II. MONTHLY REPORT A. SUMARY Of OPERATING EXPERIENCE (Unit 2)
Day line Event 1 0000 Reactor critical, generator on Ilne at 1107 MNE. ,
0430 Reduced power to 905 MNE due to reactor coolant high conductivity, i 2000 Increased power to 1107 MNE.
6 0300 Reduced power to 900 WE for system load, i 1000 Increased power to 1113 INE.
15 0200 Reduced power to 730 MWE for rod set. !
1800 Increased power to 1107
- E.
l l 16 0430 Reduced power to 850 MHE for system load.
l 1400 Increased power to 1110 MNE. .l 17 0300 Reduced power to 850 WE for system load, j 1000 Increased power to 1102 WE.
19 0100 Reducert power to 1040 WE for system load and weekly surveillances.
20 0500 Increased power to 1102 W E.
22 2300 L.duced power to 830 WE for turbine driven reactor feed pump work.
23 1600 Increased power to 1115 MNE.
l 24 0300 Reduced power to 850 MHE for system load.
1000 Increased power to 1110 W E.
26 0000 Reduced power to 1060 MNE for turbine generator and l
reactor survelliances.
0700 ,
Increased power to 1109 W E. '
c ,
30 2400 Reacttr critical, generator on-line at 1100 MHE.
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ZCADTS/7
- 8. AMENDNENTS TO THE FACILITY LICENSE OR TECHNICAL SPECIFICATION (None).
C. MAJOR CORRECTIVE MINTENANCE TO SAFETY RELATED EQUIPMENT (including
-SOR differential pressure switch failure reports).
(See lable 1)
D. LICENSEE EVENT REPORTS (Unit 2)
LER. Number Q111 Q.ticIjAtion 91-004-00 06/17/91 Inboard Reactor Building ventilation isolation.
91-005-00 06/21/91 RCIC inoperable due to a failed SOR H1 flow Isolation switch due to diaphragm failure.
91-006-00 06/26/91 An Instrument Maintenance Technician i inadvertently grounded an electrical i circuit causing an ESF actuation. ;
E. DATA TABULATIONS-(Unit 2)
- 1. Operating Data Report.
(See Table 2)
- 2. Average Daily Unit Power Level.
'(See Table 3) ,
- 3. Unit Shutdowns and Significant Power Reductions.
(See Table 4)..
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C. TABLE 1 (Unit 2)- '
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l MJOR CORRECTIVE MINTENANCE TO -
. SAFETY-RELATED EWIPMENT i
- r
. MORK REQUEST RESULTS AND EFFECTS
! NUBSER COWONENT CAUSE OF M LFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION :j i t i-LO5899 Division II Oxygen bottle regulator Mone. Replaced regulator.
Post loca panel 2PL77J t I i LO6171 High pressure core Damper actuator' Degraded damper operation. Replaced actuator.
spray diesel generator HVAC t i damper LO8660 Reactor core SOR differential Switch inoperable. Replaced switch.
isolation cooling pressure switch
- steam flow line 2E31-N0138A i i
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SCR dp Syltch Failure Data Sheet Equipment Ploce Number: 2 E 31 -11013 B4 Model fiumber 10 3 AS-132 03 -UX-JJTTX 6 Serial Number: 86-1-3270 Application: RC LCJ11 pLS t e allLLine_ r10W_1g ol at. ion _.Swi t c h Date and Time of Discovery 06/21/91 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> ]
l Reactor Modei ... 1_fRuni Power Level 10.01 I t Calibration Tolerance: 165.4 - 152J "WC h
Nominal Setpoints 166.4 "WC Action Limits: <l61&Q or >12LJ "WC Reject Limits: <151J or >211J "WC l
Technica) Specification Limit: 115LQ "WC 1
As Found Sotpoints ---
"WC j DateLand Time of-Return to Service: 06/22/91 D115 hours Model Number of Replacement Switch 103AS-BZ.Ql-11X-JJITX6 Serial Number of Replacement Switch:. 10-0 .6232 DVR Number 1-2-91-022 ,
Cause:. Switch would not hold pigggurn during_ functional testino.
Durina inspection tho ~ switch was _ found to havc__a. t ear _ in tite t;iinphrAgth The cause of the tear could not be determined.
Corrective Actions railedJWitch inspected _under_LaSalle__. Instrument Surveillance L I S -Gl{- 9 4 2 . f[ git _fLw1.tch was installed, tested and returned -
to service.
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TABLE 4
- f E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS 220%
(UNIT 2) l METHOD OF CORRECTIVE SHUTTING DOWN ACTIONS / CODE (ENTS YEARLT TYPE THE REACTOR OR (LER/DVR I if F: FORCED OURATION coplij:able)
SEQUENTIAL DATE REASON R_ EDUCING POWER NUMBER (YYMMDD) S: SCHEDULED { HOURS)__
(Non.e)
SUMMARY
OF OPERATION:
Several minor power reductions were required due to system The unit remained on line at high power throughout the month.
loading, ratine surveillances and maintenance.
j ZCADTS/7
I F. UNIQUE REPORTING REQUIREMENTS (Unit 2) 1
- 1. Safety /Reller Valve Operations ,
VALVES NO & TYPE PLANT DESCRIPTION <
t DAIE - AC10ATED ACRIATIONS CONDITION OF EVENT (None)
- 2. ECCS System Outages (None)
- 3. Changes to the 0ff-Site Dose Calculation Manual.
(See Attachment A)
- 4. Major changes-to Radioactive Haste Treatment Systems. ,
(None)
- 5. Indications of Failed fuel Elements.
(None) 4 I-1 g
ZCADTS/7-
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. CHANGES TO THE OFFS!!E 00SE CALCULATION MANUAL 'l Changes to the Offsite Dose Calculation Manual (00CH) are reportable to the Nuclear Regulatory Commission (NRC) in accordance with station Technical
- Specifications. This document contains the models for the public dose assessment from gaseous effluents, 11guld discharges, and direct radiation.
The NRC, per Generic Letter 89-01, requested that the information found in the station Radiological Effluent Technical Specifications to be transferred to the ODCM and Process Control Program-(PCP), as applicable. The major changes to the OOCH complied with this request. The remaining minor changes were editorial, outstanding from the previous distribution, Revision 0, dated March, 1989.
This revision does not reduce the accuracy and reliability of dose calculations or set point determination methodology.
Any changes to the OOCH computer program required by this document are in the process of being implemented now and should be fully available by July 8, 1991.
MAJOR CHANGES The generic manual both introduces and references the Radiological Effluent Technical Specifications contained in the site annexes, in Chapter 12, now titled the " Radiological Effluent Technical Standards (RETS)".
" Operability Requirements" in the RETS are equivalent to Limiting Conditions for Operations in the station Technical Specifications.
Jhe generic manual is common for six sites, therefore the reporting requirement for " Changes to the 00CM" deviates slightly from the recommendation given in the Generic Letter. An effective date for generic manual implementation is to specified in the station Onsite Review. As ,in the past, the official transmittal to the NRC is mad.e through the stations' Honthly Operating Report within 90 days of the effective date.
MINOR CHANGES The remaining minor changes are editorial. Below is the abbreviated version of an itemized list of changes available in Emergency Preparedness in at the Corporate Office:
- Revised titles for the Corporate Office Department and Positions
- Prepared a stand alone section for the EPA's Clean Air Act (if and L when enacted) l L
e Deleted references to Commonwealth Edison (or CECO) e Added text regarding the Wilmington Public Water Supply nearby Braidwood Station
- Corrected parameter syshols, values and units.
ZMOC/7/1
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CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (con't)
SITE SPECIFIC ANNEX OlANGES LaSalle Station (Chapters 10, 11, 12 and Appendix F)
Chapter 10 Minor editorial changes Chapter 11-Table 11-1 p 11-3 Revised distance and direction for the air sampling location, L-08.
Harseilles, from 7.0 mi NH (11.3 km 0) to 6.3 mi NNH (10.1 km R)
Table 11-1 p 11-7 Added milking monitoring locations L-19, Bettenhausen Dairy, 1.0 mi S (11.3 km J) and L-20, Gass Dairy, 4.6 mi HSH (7.4 km)
Deleted milking monitoring location, L-15 Granby Farm, 7.0 mi E (11.3 km E)
Table 11-3 p 11-12 Added the sentence to definition E, "V The sample size (in units of mass or volume)."
Figure 11-3 p 11-16 Updated table for L-15, L-16. L-19, and L-20.
Other minor editorial changes Chapter 12 - New RETS insert Appendix F - Developed Direct Radiation model parameters.
Hinor editorial changes v.
ZHDC/7/6
~.
SUMMARY
OF CHANGES PAGE ACTION DESCRIPTION SUBJECT Resised Ew.eigency Preparedness Supervsor to Drector.
N/A Revsson Signature Page Updated to include a new index desgnatons on pp i-xi.
i Revsson ODCM Reveson index Deleted page. Page number 4s used for a new inder desgnatons, i Deletion Special Notes Ttyy new index desgnations are iderthed on pp Fxii_
Revson Desgnation Deleton Refer to Section 1.4, p 16.
Deletion Organization of this Manual Refer to Secton 1.2.1, p 1-4.
Revision 10CFR20 Transferred paragraph to a note in Section 42.1.1, p 4-12.
Revisaan Notation for Powers of 10 Deleted page. Page number hs used for a new index desgnatons.
til Deletion Tableof Contents Page number is used for a new index desgnatons, iv Revsion refer to revued pages TOC for Table of Conterts.
Rettled tt e Tabie of Corserts to Summary of Topes.
Revned 9.0 caption fmm *PC.&= (to
- Reserved for the Clean As Act*.
- References *is a sugect-tiled chapter. Revned Part II, to include Chapter 12.
Deleted page. Consolidated a Esting of conterts, appendees, tables, and hgures in front v Deletion Notes on Table of Conts/ts of the genenc manual v Deletion . Deleted page.
Detailed Listing of Corterts Deleted page. The references are cortained h a subgect4 sled cMpter.
Listing of References v Debtion Adde. ion Page number is used for a new inder deegnations, refer to revsed p TOC-17 to 20.
List of Actoriyms vai loserted Nucieer Services Emergency Properedness and Operatety Requiremones on p TOC-19.
Revsed the *S* h RETS from Specfcamions to Standards on p TOC-19.
Revsion itsetted Unit Review Group on p TOC-20 tr Addition l
C. TABLE 1 (Unit 1) '
i MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT RESULTS AND EFFECTS HORK REQUEST CORRECTIVE ACTION COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION NUMBER -.
Switch failed to alarm on Replaced pressure LD5073 Control Room Make-up Pressure switch switch.
Fan OPDS-VC313 increasing differential OVCO3CA pressure.
Detector inoperable. Replaced tape drive LO8192 Ammonia Detector Tape drive mechanism mechanism.
OXY-VC125A Improper indication. Replaced differential LO8392 Aux. Electric Differential pressure pressure indicator.
Equipment Room indicator.
"A" filter train. OPDI-VE064A Damper act Jator Degraded damper operation. Replaced actuator.
L99459 Control Room damper 0FZ-VC007A OVC011YA Damper actuator Degraded damper cperation. Replaced actuator.
i L99761 Aux. Electric l Equipment Root 0FZ-VE007A filter train l inlet damper.
OVE07YA 9
(No SOR failures this month.)
ZCADTS/5+
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