ML20065C970

Monthly Operating Rept for Jul 1982

ML20065C970
Person / Time
Site:	LaSalle
Issue date:	08/09/1982
From:	Ullrich J COMMONWEALTH EDISON CO.
To:
Shared Package
ML20065C929	List: ML20065C926 ML20065C970
References
NUDOCS 8209240353
Download: ML20065C970 (18)

Text

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LASALLE NUCLEAR POWER STATl0tl UNIT I MONTHLY PERFORMANCE REPORT JULY, 1982 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 O hhh PDR

TABLE OF CONTENTS

1. INTRODUCTION

11.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE lil. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RE'.,".IED MAINTENANCE A. Anendments 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 i

l IV. LICENSEE EVENT REPORTS V. DATA TABULATIONS A. Operating Data Report l

B. Average Daily Unit Power Level l 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 i D. 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 Boiling Water Reactor with a designed electrical output of 1078 MWe net, located in Marseilles, Illinois. The Station is owned by Commonwealth Edison Company. The Architect / Engineer was Sargent & 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.

This report was compiled by John Ullrich, telephone number (815)357-6761, extension 481.

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11.

SUMMARY

OF OPERATING EXPERIENCE r0R UNIT ONE l July 1 - 20 Unit was in cold shutdown.

July 20 - 21 Reactor startup, sequence B commenced at 23:00 hours on July 20, 1982. Criticality was achieved at 3:04 hours on July 21, 1982. This criticality was terminated after 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> 50 minutes.

July 22 - 24 Reactor startup commenced at 3:37 hours on July 22, 1982, achieving criticality at 5: 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />. This criticality was terminated after 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br /> 57 minutes due to a high vessel pressure of 1043#. The NRC notification was made after 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

July 25 - 26 The reactor went critical at 9:40 hours on July 25, 1982, for 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> 10 minutes when it was scrammed for cooldown, i

July 26 - 31 Unit was in cold shutdown.

Startup testing and maintenance on the unit continued throughout the month.

Ill. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE A. The following is a list of amendments to the facility license and technical specifications:

AMENDMENT 1. In Mr. A. Schwencer's letter to Mr. Louis 0. DelGeorge of June 21, 1982:

a. Modify Tech Spec 4.6.6.l(b)(2) from 1200 + 9 F to 1200 + 25 F.

b. Change the main steam isolation valve scram set-point from a nominal value of 94% open to a nominal value of 92% open.

c. Modify Tech Spec 3/4.10.7 so as to permit perforn-ance of the confirmatory flow induced vibration test with one low pressure core injection loop isolated.

AMENDMENT 2. In Mr. A. Schwencer's letter to Mr. L. O DelGeorge of July 9, 1982:

a. To reduce the count rate of the source range monitors from 3 cps to .7 cps for modes other than shutdown with a minimum allowable value of .5 cps

instead of 2 cps.

b. To revise Tech Spec 4.4.3 2.2.B alarm setpoint for the reactor core isolation cooling system from 60 in2 to 90 in 2.

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 table 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.

VORK REQUEST LER C0llP011EllT CAUSE OF HALFUtiCTI0li RESULTS AND EFFECTS CORRECTIVE ACTI0il Oli SAFE OPERATI0ll SRV 1821-F013G, L Connectors broken No effects - were in Ccanector replaced L14680 ---

cable & connector shutdown RHR & LPCS Pump Dis- Reset span too large to No effect - plant was Replaced and calibra-L15067 ---

charge Pressure operate between Tech shutdown ted pressure switch switches 1E12-N022A, Spec limit and normal B, C & 1E12-N005 operating pressure 1E12-F087A ir?ut Burned 74 relay No effect - plant Replaced 74 relay L15192 ---

to ESF status panel was shutdown L15375 s Neutron monitoring Overheated resistors tio effect - plant was f #'*f fo f' ' a redesigned resistor in

he power supplies to i

he neutron monitors L16540 .

"A" Outboard MSIV Bad valve seating No effect - plant was Valve seats were shutdown lapped / ground and reassembled L17067 ---

RCIC drain trap Float rod stuck No effe.i pl:nt was Rewired,' replaced, level switch shutdown recalibrated new switch L17146 ---

ID RHR service H O Bad motor No effect - plant was Replaced with new 2

pump shutdown motor L17264 ---

1A RHR SWP Trip settings No effect Tested trip settings L17353 ---

Drywell Personnel "0" rings leaked during No effect plant was Installed new "0" airlock local leak rate test shutdown rings L17400 ---

"B" RHR Transmitter for pressure No effect Recalibrated trans-gauges were out of spec. mitter L17418 -

r' Div ll Post LOCA Malfunctioning flow- No effect plant was Cleaned the

% 0xygen monitor raters shutdown flowraters L17423 ---

1B RHR SP spray Torque switch bad Resulted in having only Changed & set torque valve one S.P. spray loop. switch Two required by Tech Spec'

WORK REQUEST LER C0flP0fiEllT CAUSE OF MALFUllCTI0il RESULTS AND EFFECTS CORRECTIVE ACT10ll Oil SAFE OPERATl0ll Ll7443 LER82-061/03L-C IB/lC RHR injection RHR B/C injection lines No effect Recalibrated monitor -

line integrity monitor out of calibra- bled air from monitor tion limits sensing lines Ll7467 HPCS D/G petter Starter not engaging Motor driven compressor Replaced woodruff air compressor was still available key & set screw on starter bendix shaft L17469 LER82-064/03L{ U SRV Improper interactior, Valve still operated Wiring changed to between the magnet & the correctly spare reed switches wired set of reed switches L17491 L E R82-066/03 L-C RCIC Turbine Oil leaking The HPCS system was Tightened fittings operable replaced oil filter gaskets Ll7493 LER82-068/0360 H safety relief improper interaction Valve still operated Cleaned magnet &

valve between the* magnet & the properly changed wiring to the wired set of reed i spare set of reed switches switches L17515 ---

RCIC Vacuum pump Pump not pulling The HPCS system was

., Chained lubricator negative vacuum operable & installed plug in sight glass Ll7526 ---

Vacuum pump Dirty disc & valve The HPCS system was Disassembled &

Discharge check operable cleaned va',ve valve Ll7545 ---

lE51-D006 RCIC pump does not The HPCS system was Modification to achieve rated flow operable increase orifice size Ll7593 LER82-0/7/03L{ RCIC valves Valves opened but The HPCS system was Adjusted limits IE51-F354 failed to reclose operable switch Ll7595 LER82-078/03L-0 Snubber 1 RH-04-15 205 Improper weld No effect Repaired weld RCIC Inboard Limit switch out of The HPCS system was Adjusted limit Ll7596 ---

Testable Check adj us tmen t operable switch

WORK REQUEST LER C0llP0flEllT CAUSE OF HALFUllCTI0ff RESULTS AflD EFFECTS CORRECTIVE ACT10ft Off SAFE OPERATIO!!

L17710 ---

SBGT Rad. Mon. Control ~not adjusted No effect - Unit was in Reset RM-23 OPLO58JB correctly cold shutdown G

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l 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, July I to July 31, 1982. This information is provided pursuant to the reportable occurrence reporting require-

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ments as set forth in section 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

Licensee Event Report Number Date Title of Occurrence 82-056,03L-0 July 7 Missed surveillance on Reactor Water pH and Chloride Sampling Analysis 82-057/03L-0 July 8 "A" RHR Service Water Process Radiation Monitor 82-059/03L-0 July 12 "A" RHR Service Water Process Radiation Monitor 82-060/03L-0 July 17 Chlorine and Ammonia Detection System failure 82-061/03L-0 July 20 RHR B/C Integrity Monitor 82-062/03L-0 July 20 Reactor Coolant System Leakage Detection Systems 82-063/03L-0 July 20 APRM D Neutron Flux High 82-064/03L-0 July 21 ADS Valve 1B21-F013 U position Indication 82-065/01T-0 July 22 Vacuum Breaker Analysis to Meet Code Allowables 82-066/03L-0 July 22 Failure of RCIC Govenor 82-067/03L-0 July 22 0A VE System 82-068/03L-0 July 22 Safety Relief Valve Position indicator 82-069/03L-0 July 22 Low Drywell Pressure

IV. LICENSEE EVENT REPORTS (CONTINUED)

Licensee Event Report Number Date Title of Occurrence 82-070/03L-0 July 24 Hissed Station Vent Stack Surveillance 82-071/03L-0 July 25 tiissed Samples Following Reactor Shutdown 82-072/03L-0 July 24 Group 1 Isolation and Reactor Scram 82-073/03L-0 July 25 Heatup Rate Exceeded 82-074/03L-0 July 19 Post LOCA H 60 2 2 82-075/03L-0 July 26 Failure of ADS Accumulator IN Line 82-076/03L-0 July 27 RCIC Steam Supply Pressure Low Isolation 82-077/03L-0 July 26 Failure of RCIC Cont.

Isolation Valve IE51-F355 82-078/03L-0 July 26 Inoperable Snubber RH04-15205 l

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

A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions t

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.LTP-300-7 e .

- ATTACH?fEI.'T D Revis,lo'rt 2

. Novembar' 13,.1979

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' OPERATING DATA REPORT DOCKET NO. 050-373 UNIT I DATE 8/5/82 l John Ul1. rich COMPLETED BY

. TELEPHONE 815/357-6761. X-481 l OPER ATING STATUS July, 1982 gross HOURS tN REPORTimc PERIOo: 744.0

1. REPORTINC PERIOD:

5't M Ax. DEPE ND. CAPACITY (MWo. Net): 0

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):

DESIGN ELECTRICAL RATING (MWe. Net): 1078 5%

3. POWER LEVEL TO WHICH RESTRICTED (lF ANY) (MWe Net):

4. RE ASONS FOR RESTRICTION (IF ANY1:

THis nsONTH YR TO DATE CUMULATIV E 93.95 99.05 99.05

5. NUMBER OF HOURS REACTOR WAS CRITICAL ..............

0 .0 0

8. REACTOR RESERVE SHUTDOWN HOURS . . . ...............

0 0 0

7. HOUR $ GENER ATOR ON LINE . . . . . . . . . ................

0 0 0

8. UNIT RESERVE SHUTDOWN HOUR $ ................. ....

9. GROSS TkERMAL ENERGY GENER ATED (MWH1 ...... .......

10. GROS $ ELECTRICAL ENERGY GENERATED IMWH) . . . .

0 0 0

11. NET ELECTRICAL ENERGY GENER ATED (MWH) ..... ........

NA NA NA

12. REACTOR SERVICE FACTOR . . ........................

NA NA NA

13. R E ACTOR AVAILA BILITY F ACTOR . . . . . . . . . . . . . . . . . . . . . .

. NA NA NA

14. UNIT SERVICE F ACTOR ... .. .....................

NA NA NA

15. UNIT AVAILA881lTY F ACTOR ......... ..............

18. UNIT CAPACITY FACTOR (Useng MDC) ................... . NA NA NA l NA NA NA

17. UNIT CAP ACITY F ACTOR tus.ng Oeogn MWel . . .. .........

NA NA NA

18. UNIT FORCED OUTAGE R ATE .................. ..... e

19. SHUTDOWNS $CHEOULEC OVER NExT 6 MONTHS (TYPE. DATE. ANO DUPr.T.ON OF EACHl:

20. IF SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTur:_8/2/82

21. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPERATIONI.

FORECAST ACHIEVED 6/21/82 INITI AL CRITICALITY i

tNITIAL ELECTRICtTY 9/1/82 COMMERCI AL OPER ATION 10/1/82 i t::..- .~. .

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LTP-300-7 Revision 2 -

, November 13, 1979 5

ATTACHMENT A AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-373 UNIT I DATE 8/5/82 COMPLETED BY John Ullrich TELEPHONE 815/357-6761, X-481 MONTH July, 1982 DAY AVERAGE DAILY POWER LEVEL , DAY AVERAGE DAILY POWER LEVEL (MWe-Ne t) (MWe-Ne ?.)

. 1. 0 17 0

2. 0 18. 0 3

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4. 0 20. 0

5. 0 21. 0

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l VI. UNIQUE REPORTING REQUIREMENTS A. Main Steam Relief Valve Operations-for Unit 1 Relief valve operations during the reporting period are summarized in the following table. The table includes information as to which relief valve was actuated, how it was activated and the circumstances resulting in its actuation.

Valves No. & Type Plant' Description Date Actuated Actuations Conditions of Events 7/21/82 1821-F013C 1 Manual 150 psig LOS-MS-R2 7/21/82 IB21-F013D 1 Manual 150 psig LOS-MS-R2-7/21/82 1B21-F013E 1 Manual' 150 psig LOS-MS-R2 7/21/82 1821-F013R 1 Manual 150 psig LOS-MS-R2 7/21/82 IB21-F013S 1 Manual 150 psig. LOS-MS-R2 7/21/82 1821-F013U 2 Manual 150 psig LOS-MS-R2 7/22/82 1B21-F013P 2 Manual 230 psig PT-MS-101C 7/22/82 1821-F013A 1 Manual. 240 psig _PT-MS-101C 7/22/82 1B21-F013F 2 Manual 240 psig PT-MS-101C 7/22/82 IB21-F013H 3 Manual 240 psig PT-MS-101C 7/22/82 1821-F013B 1-Manual 240 psig PT-MS-101C L

240 psig 7/22/82 1821-F013G 1 Manual PT-MS-101C 7/22/82 IB21-F013J 1 Manual 240 psig PT-MS-101C 7/22/82 IB21-F013S 3 Manual 240 psig PT-MS-101C 7/22/82 1821-F013L 1 Manual 240 psig PT -MS-101 C

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91. UNIQUE REPORTING REQUIREMENTS (CONTINUED)

Valves No. & Type Plant Description Date Actuated Actuations Conditions of Events 7/22/82 1821-F013R 3 Manual 240 psig P T-MS- 101 C 7/22/82 IB21-F013V 3 Manual 240 psig F T-MS-101 C 7/22/82 IB21-F013C 3 Manual 240 psig P T-MS- 101 C 7/22/82 IB21-F013D 3 Manual 240 psig P T-MS- 101 C 7/22/82 IB2l-F013N 1 Manual 240 psig P T-MS- 101 C 7/22/82 IB21-F013M 1 Manual 240 psig P T-MS-101 C 7/22/82 1821-F013U 3 Manual 240 psig FT-MS-101C 7/22/82 1821-F013K 1 Manual 240 psig PT-MS-101C 7/22/82 1821-F013E 3 Manual 240 psig PT-MS-101C 7/23/82 1821-F013U 2 Manual 140 psig Post Maintenance 7/23/82 1B21-F013H 1 Manual 140 psig Post Maintenance 7/23/82 1821-F013K 2 Manual 230 psig Post Maintenance 7/23/82 1821-F013P 1 Manual 230 psig Post Maintenance 7/23/82 1821-F013H 2 Manual 220 psig Post Maintenance 7/23/82 1821-F013H 1 Manual 230 psig Post Maintenance 7/23/82 1821-F013C 5 Manual 230 psig PT-MS-101C 7/23/82 1821-F013E 5 Manual 230 psig PT-MS-101C 7/23/82 IB21-F013R 5 Manual 230 psig PT-MS-101C 7/23/82 IB21-F013U 5 Manual 230 psig PT-MS-101C 7/23/82 IB21-F013V 5 Manual 230 psig PT-MS-101C 7/23/82 1821-F013D 5 Manual 230 psig PT-MS-101C 7/23/82 1821-F013S 5 Manual 230 psig PT-MS-101C 7/26/82 1821-F013v 1 Manual 940 psig STP-26 l

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• l VI. UHlquE REPORTING REQUIREMENTS (CONTINUED)

B. ECCS Systems Outages The following outages were taken on ECCS Systems during the reporting period:

Outage No. Equipment Purpose of Outage 1-1321-82 SRV 1B21-F013U Repair 'U' SRV position indication 1-1324-82 SRV 1B21-F013H Repair 'H' SRV position indication C. Of f-Site Dose Calculation Manual There were no changes to the Of f-Site Dose Calculations Manual during this reporting period.

D. Radioactive Waste Treatment System 1

! There were no changes to the Radioactive Waste Treatment System during this reporting period.

E. Process Control Program c

l There were no changes to the Process Control Program during this reporting period.