ML20027B481
| ML20027B481 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 09/08/1982 |
| From: | Holyoak R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| Shared Package | |
| ML20027B482 | List: |
| References | |
| NUDOCS 8209210099 | |
| Download: ML20027B481 (16) | |
Text
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'N Comm:nw :lth Edison
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) LaSalle County Nuclear Station
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- - ', Rural Route *1, Box 220 1
- - -' / Marseilles, Illinois 61341
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Telephone 815/357-6761 j
September 8, 1982 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, Unit One, for the period covering August I through August 31, 1982.
Very truly yours, A
R H. Holyoak L
Superintendent LaSalle County Station Commonwealth Edison Co.
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RHH/JRU/psl Enclosure h
cc:
J. G. Keppler - NRC, Region 111 NRC Resident Inspector - LaSalle L. O. DelGeorge - CECO Gary Wright - 111. Dept. of Nuclear Safety 82092100$Qk
LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE RFPORT AUGUST, 1982 COMMONWEALTH EDISON COMPANY NRC DOLKET NO. 050-373 LICENSE NO. NPF-11
TABLE OF CONTENTS 1.
INTRODUCTION 11.
SUMMARY
OF OPERATING EXPERIENCE FOR UNIT ONE Ill. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.
Amendments to Facility License or Technical Specifications 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 Steam Relief Valve Operations B.
ECCS System Outages C.
Off-Site Dose Calculation Manual Changes D.
Major Changes to Radioactive Waste Treatment System E.
Changes to the Process Control Program
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1.
INTRODUCTION
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The LaSalle Nuclear Power Station Unit One is a Boiling Water Reactor with a designed electrical output of 1078 kWe net, i
located in Marseilles, Illinois. The Station is owned by
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Commonwealth Edison Company.
The Architect / Engineer was,
Sargent & Lundy, and the primary construction centrattor was '
Commonwealth Edison Company.
The condenser cooling method is a closed cycle cooling pond.
The plant is subject to License Number NPF-II, issued on April 17, 1982.
The date of initial criticality was June 21,-
1982.
The unit has not commenced commercial generation of power.
s This report was compiled by John Ullrich, telephone nuiaber.
(815)357-6761, extension 481.
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I 11.
SUMMARY
OF OPERATING EXPERIENCE FOR UNIT ONE s
August 1 Unit was in cold shutdown.
August 2-3 Reactor startup commenced at 18:20 hours on August 2, 1982'i achieved criticality at 20:00 hours.
This criticality was terminated alter 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> and 55 minutes.
August 4 - 12 The reactor went critical at 7:25 hours on August 4, 1982, for 203 hours0.00235 days <br />0.0564 hours <br />3.356481e-4 weeks <br />7.72415e-5 months <br /> and 25 minutes when it was shutdown due to loss of CRD pumps and two accumulator trouble alarms.
August 13 - 17 The reactor went critical on August 13, 1982, at 22:26 hours, for 83 hours9.606481e-4 days <br />0.0231 hours <br />1.372354e-4 weeks <br />3.15815e-5 months <br /> and 37 minutes when it was shutdown due to a high differential temperature in the main steam tunnel.
August 18 - 21 The reactor went critical on August 18, 1982, at 15:40
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hours, for 62 hours7.175926e-4 days <br />0.0172 hours <br />1.025132e-4 weeks <br />2.3591e-5 months <br />.
August 28 - 31 The reactor went critical at 3:00 on August 28, 1982, for 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> and 44 minutes.
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Ill. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTEN ANCE A.
The following is a list of Amendments to the facility license and technical speci fications.
AMMENDMENT 3 In Mr. A. Schwencer's letter to Mr. Louis 0. DelGeorge of July 15,1982 paragraph 2.C. (31) of the Facility Operating License No. NPF-11 was amended to read as follows:
(31) Bolting of Valves Prior to January 15, 1983, the licensee shall check the torque on all non pressure boundary bolts (bolts whose failure will effect the operability of the valve) on each safety-related valve located outside the containment.
AMMENDMENT 4.
In Mr. D. Eisenhut's letter to Mr. Louis DelGeorge of Aug. 13, 1982 pa rag raphs 2. C. (1), 2. C. (11), 2. C. (32),
2.C. (33), 2.D, 2. F and 2.H of the Faci li ty Ope rating License No. NPF-11 were amended to read as follows:
(1) Maximum Powe r Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3323 megawatts the rmal).
i lil. PLANT OR PROCEDURE CHANGES, TESTS,. EXPERIMENTS AND SAFETY RELATED MAINTENANCE (CONTINUED)
(11) Envi ronmental Quali fications (Section 3.11, SER, SSER #1, SSER #2)
(a)
No later than March 31, 1985, the licensee shall be In compliance with the provisions of NUREG-0588,
" Interim Staff Position on Environmental quali fications of Safety-Related Elect rical Equipment", for safety-related electrical equipment exposed to a harsh environment.
l (b)
Complete and auditable records must be available and maintained at a central location which describe the envi ronmental quali fication methods used for safety-related electrical equipment in sufficient detail to document the degree of compliance with NUREG-0588.
Such records shall be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified to document complete compliance no later than March 31, 1985.
(32) Vacuum Breaker Valves Prior to November 1,1982, the licensee shall complete a test and shall submit its evaluation of the results which confi rm the capability of the vacuum breaker valves to withstand the opening and closing forces associated with.
pool swell.
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lli. PLANT OR PROCEDURE CHANGESo TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE (CONTINUED)
(33) Heating-Ventilation and Air Condition Systems (a)
Prior to exceeding 5% power operation, the licensee must provide formal documentation of information regarding HVAC design fabrication and installation, discussed in meetings with the NRC on August 2 and 4, 1982.
(b)
Prior to exceeding 50% power operation, the licensee shall submit the results of an independent review acceptable to the NRC staff of the HVAC system, including design changes, fabrication, and installatioa.
The review shall encompass all safety-related HVAC systems and the ef fect of non-safely related HVAC system failures on safety systems.
i D.
Exemptions from certain requi rements of Appendices G, H and J and 10 CFR Part 73 are described in the Safety Evaluation Report and Supplenent No.
1, No. 2 and No. 3 to the Safety Evaluation Report.
In addi tion, an exemption was requested until the completion of the first re fuel ing i
from the requirements of 10CFR 70.24 and an exemption from 10 CFR Part 50, Appendix E from performing a full 1
scale exercise within one year before issuance of an operating license, both exemptions are described in Supplenent No. 2 of the Safety Evaluation Report. These exemptions are authorized by law and will not endanger li fe or property or the common defense and security and
Il1. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE (CONTINUED) are otherwise in the public interest.
The re fo re, these exemptions are hereby granted.
The faci li ty wi l l ope rate,
to the extent authorized herein, in conformi ty wi th the application, as ame.nded, and the rules and regulations of the Commission (except as hereinafter exempted therefrom),
and the provisions of the Act.
F.
Reporting to the Commission:
(a) The licensee shall report any violations of the requi rements contained in Section 2, i tems C(1),
C(3) through (33), and E of this license within twenty-four (24) hours by telephone and confirmed by telegram, mailgram, or facsimile transmission to the NRC Regional Administrator, Region li l, or designee,
not later than the first working day following the violation, wi th a written followup report wi thin fourteen (14) working days.
(b) The licensee shall noti fy the Commission, as soon as possible but not later than one hour, of any accident at this facility which could result in an unplanned release of quantities of fission products in excess of allowable limits for normal operation established by the Commission.
H.
This license is effective as of the date of issuance and shal l expi re April 17, 2022.
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7 l'll. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY-RELATED MAINTENANCE (CONTINUED)
B.
Facility or Procedure Changes Requiring NRC Approval.
There were no facility or procedure changes requiring NRC approval during the reporting period.
C.
Tests and Experiments Requiring NRC Approval.
There were no tests or experiments requiring NRC approval during the reporting period.
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 Ef fects on Safe Operation, and Corrective Action.
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\\!ORK REQUEST LER C0l!P0!lEllT.
CAdSETOF 'liALFUllCT10!1 RESULTS All0 EFFECTS CORRECTIVE ACT10fl Off SAFE OPERATI0il Ll7265 RIIR 1C Service.
LTD settings Affects motor protection Adjusted LTD water pump out of adjustment settings L17488 Unit.1 Division 1 liigh voltage sensing and Charger kept tripping Replaced high voltage Battery Charger AC and alarm board bad sensing and alarm Breaker board L17550 lE31-N008C Transmitter shifting Larger than allowed Replaced transmitter
'q when subjected to static tolerance limits pressure.
Ll7552 1C Outboard MSlV Limit switch for full Threw limit switch setting Cycled valve limits closed' indication out of spec 0.K.
hanging up LI7554 Governor Valve Incorrect wiring Lightindicationisbach-Wiring conforms to wards drawing Ll7665 RIIR A testable check Cables have severely No effect i'
Replaced sealtite cables deteriorated ATWS test switches
'+' bacic-feed to K101 Recirc pump trips while in Lifted T3 lead to L17738 A&B relays test position prevent breaking from tripping Ll7893 OVC05A IIVAC Pressure switch out of Compressor kept tripping Recalibrated pressure compressor adj ustment on, low suction pressure switch 1
L17894 OVE04CB IIVAC.
Unit needed to be Compressor kept tripping Charged unit with 100 compressor charged on low suction pressure lbs of freon 0
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VORK itEQUEST' LER C0llP0ilEllT CAUSE OF MALFUllCTl0ll RESULTS AllD EFFECTS CORREC'flVE ACTI0ll Ort SAFE OPERAT10ll
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l L17924
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RCIC Barometric Cond.
Dirty commutator Pump does not auto start Cleaned commutator pump on Hi level L17943 82-085/03L-0 DG-2A Excessive pre-lubing Oil on cylinders Cleaned off tops to all 20 pistons L17999 B IRM Loose pin on H.V.P.S.
Did not trip in "inop" Tightened pin on connector when mode switch removed H.V.P.S. connector
+5 from operate t.
a L18028 I
Flow control for Primary containment flow Does not control in AUTO Readjusted switc h f
panel IPL75J control valve switch out operation of adjdstmdnt L18136
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RCIC condensate pump Limit switch,not making Has double indication when Adjusted open limit discharge Inboard closed from panel switch Isolation Valve L18160
'C' IRM Power Supply Bad preregulator No effect
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Replace preregulator L18163 82-089/03L-0 RCIC Governor Valve Dowel [pinsoutofplace Valve sticks at about 50%
Replaced dowel pins, with a full closed indic-cleaned control link-ation. This causes turbino age, reset governor to trip on overspeed level clearance L18175 82-090/03L-0 RCIC Inboard' Equal-Limit. switch out of V'a'1ve indicates full open Reset limit switch izing valve adj us tment-and will not close when for proper light
,e cycled indication 1
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a
VORK REQUEST-LER
' C0llP0l_lEllT
- .CAUSE OF'MALFU!!CTI0li RESULTS AND EFFECTS C DRRECTTV I: AlliUH O!! SAFE OPERATIO!!
LPRM.16-57' Incorrect Wiring LPRM 16-57 detectors B & C Corrected wiring L18267 readings appear to be swapped s
L18269 LPRM 24-17 Incorrect wiring LFRM 24-17 detector C gave Corrected wiring a "0" reading while neighboring detectors had positive readings IRM Channel B Faulty Hi voltage power Channel reads high compar-Replaced power supply L18271 supply cd to other scales l
1 L18301 82-091/03L-0 RCIC Steam supply Hi Switch 'out 'of adj us tment No effect Adjusted switch flow switcha L18316 82-091/03L-0 RCIC Steam supply Hi Broken locki g device No effect Repaired locking flow detector device L18352 82-090/03L-0 Main Steam Mechani-Defective snubber No effect
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Replaced snubber cal. Snubber L18362 82-093/03L-0 RCIC Turbine Sight glass leaks oil No effect Replace gaskets from gasket 1A Battery Charger Defective pot on sens-Output voltage oscillates Replaced pot L18377 ing board i
L18380
-4 DW-1' CAM Loose' fitting connector Particulate Monitor Readjusted fitting to 1R1T-CM023 inoperable ccanectot
il0RK REQUE5 f LER C0llP0tlEllT CAUSE OF'MALFUttCTIO!I RESULTS AND EFFECTS c0anEcicVL ACll0N Oil SAFE OPERAT10?!
L18385
'B' RHR Injection Limits out of adjustment Valve did not cycle from Reset limits Line Testable Check Control Room Valve LPCI 'C' Injection Cylinder needed Maint-Valve did not cycle com-Replaced software and L18387 Line Testable Check enance pletely from Control Room seals in cylinder Valve.
L18524
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IRM 'H' Preregulator voltage IRM did not work Replaced preregulator low t
e.
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IV.
LICENSEE E'/ENT RE?CRTS The folicwing is a tabular summary cf all licensee event reports for LaSalle Nuclear ?oner Station, Uni: One, occurring during :ne recorting period, August 1 to Augus 31, 1982.
This in forma t ion is provided pursuant to the reportable occurrence reporting require-ments as set for:n in secticn 6.6.3.1 and 6.6.3.2 of the Technical Specifications.
Licensee Event Recer: Number Date Title of Cccurrence 32-031/03L-0 3/2/32 acic Equipment Area High Temperature Isolation 32-033/01T-0 S/4/32 Unit 2 Division 2 Switchgear Heat Removal System Welds 32-084/03L-0 3/6/32 Steam Leak en 1921.c30 32-085/03L-0 3/6/32 G-2A Gil in the cylincers 32-036/03L-0 3/9/32 Excess of 135 in Drywell Recuiring Reactor Snu:down 32-037/03L-0 S/3/32 Lis-NR-02 Functicnal Test 32-039/03L-0 3/15/32 acic Oversceed 32-090/03L-0 3/20/32 Defec:ive Mechanical Snubber 32-091/03L-0 3/13/32 RCIC Steam Line Hi.!cw l
isolation 82-093/03L-0 8/21/82 Broken Oil Sightglass on RCIC Turbine i
32-09L/03L-0 3/21/32 1A RR Pumo Sea:s.ailure 32-095/03L-0 3/22/32 03 Diesel Fire ?cmo 32-096/03L-0 3/30/32 Rcic Testable check valve t
l c2-097/03L-0 3/16/32 IE31-F355, lE51 :366, 1E51-F35L, 1E51 0065 (Failure :: Close) 32-093/03L-0 3/26/32 Mechanical Snubber No: Installec I
V.
DATA TABULATIONS The following data tabulations are presented in this report:
A.
Operating Data Report l
B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions 1
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