Text

Monthly Operating Repts for Oct 1988 for LaSalle Nuclear Power Station Units 1 & 2
	ML20206G761
Person / Time
Site:	LaSalle
Issue date:	10/31/1988
From:	Diederich G, Thunstedt J; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
References
	0043R-0031R, 43R-31R, NUDOCS 8811220416
	Download: ML20206G761 (32)
	v • d • e

. e s

c ,

f LASALLE NUCLEAR POWER STATION UNIT 1 HCHTHLY PERTORMANCE REPORT OCTOBER 1988 CCW.ONMEALTH EDISCri COMPANY i

NRC DOCKET NO. 050-373 l LICDISE NO. NPT-11 i

0811220416 881031 FOR ADOCK 05000373 p PDC DOCUMENT ID 0043r/0031r [. ) p. ,

l

j s

TABLE OF COITENTS o .

1. INTRODUCTI0tl II. HONTHLY REPORT FOR UNIT ONE A. Summary of Operating Experience B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED HAINTEN ANCE t

1. Amendments to racility License or Technical Specifications

2. Changes to procedures which are described in the Safety Analysis Report '

3. Tests and Experiments not covered in the Safety Analysis Report '

4. Correctise Haintenance of Safety Related Equipment

5. Completed Safety Related Hodifications. ;

C. LICENSEE EVENT REPORTS D. DATA TABULATIONS r i

1. Operating Data Report

2. Average Da!!y Unit Power Level ,

3. Unit Shutdowns and Power Reductions l l

A E. UNIQUE REPCRTING REQUIREMENTS 1

1. Main Steam Relief Valve Operations

2. SCCS System Outages

3. Off-Site Dose Calculation Manual Changes ,

4. Major Changes to Radioactive Waste Treatment System

5. Indications of railed fuel Elements I

I E

I l

i 6

l DOCtHENT ID 004 3 r / 00 31 r

s

. I, TNTRODUCTION The LaSalle County Nuclear Power Station is a two-unit f acility 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 Hegawatts. 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 number NPT-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 compiled by John W. Thunstedt, telephone number (815)357-6761, extension 2463.

DO'NMENT ID 004 3r/0031r

g II. MONTHLY REPORT TOR UNIT CHE e A.

SUMMARY

Ol' OPERATING EXPERIENCE TOR UNIT ONE October 1 0000 hours0 days 0 hours 0 weeks 0 months Unit Oae On-line, reactor critical, genetator at 1125 MWe (Various) Ramp down and up per Load Dispatcher October 24 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months Reduce load to 800 !Me to repair the 14C feedwater heater October 25 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months Begin increasing power to 1130 MWe following heater repairs.

October 31 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months Unit One on-line, reactor critical, generator at 1130 MWe.

DOCUMENT ID 0043r/0 )31r

j;3 .M ';1

, f '

'i; Bo PLANT OR PROCEDURE CHANGES, TESTS,' EXPERIMENTS AND SAFETY RELATED q [, y . s MAINTENANCE.

h-6Y; ' 7" 1. Amendments to Fac .11ty License or Technical S;,ecification.

(Nor.O

(.i i , ,

2. Changes to procedures which are described in the Safety Analysis

' Report.

r% ' a. Temporary System Changes to allr.w waste sludge, URC sludge, spent resine cancentrator wastes, and separato sludges to be transferred to vendor's waste treatment system.

b. Of f-gas pretreatment monitor changed from e logarithmic readout to a digital readout scale.

c. Minimum position interlock of Reactor Recirc flow centrol changed from 12% to 15%.open of flow conrol valve.

3. Tests and Erperiments not described in the Safety Analysis Report.

There were no tests ner experiments not described in the Safety Analysis Report.

4. Cerrective Maintent'ne of Safety Related Fquipment.

J 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 includet Work Request number, Component Name, Cause of Malfunction, Res'alts and Ef fects 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 1. ave a short synopsis explaining details involved with each modification.

9 J

e DOCUMENT ID 0043r/0031r I

O e

TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT UNIT ll WCRK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L84414 OPS-DG043 Instrt ment drif t Diesel starting air Verified setpoints not maintained via calibration check, no additional action required L84769 OD18-N515 Instrument noise Impropsr indication Cleaned power supply on WRGM connectors L84867 IE32-R651N Instrument failue due Inoperable instrument Replaced instrument to ruptured diaphram DOCUMENT ID 0043r/0031r a

s TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS HQDlflfATlRN N_ UMBER 1 A brief synopsis of incorporated modification objectives with final design resolution. Also, state reviewed or unreviewed safety questions.

(None) 4 DOCUMENT ID 0043r/0031r l . - - . __ .-- ___ . __ __

s C. LICENSEE EVENT REPORTS s

The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, logged during the reporting period, October 1, 1988 through Octo~uer 31, 1988. This information is provided pursuant to the reportable occurrence reporting requirements as ont forth in 10CFR 50.73.

Liggnsee Event Report Number Data Iltle of Occur m 88-022-00 10/13/88 "B" VC Train A Ammonia Detector Trip 88-023-00 10/17/88 30 Day, Closure of IVR04YB 88-024-00 10/17/88 30 Day, DW Lighting Found Energized DOCUMENT ID 0043r/0031r

o .

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

1. Operating Data Report

2. Average Dally Unit. Power Level

3. Unit Shutdowns and Power Reductions DOCUMENT ID 0043r/0031r

1.'0FERATING CATA REPORT ECCKET k0. 650-373 UNIT LASALLE ONE IATE Navenber 10,19f,8 CONtETED Bf J.W. THUNSTEDT TELEFHONE (8151 357-6761 0FERA?!NG STATUS

1. REPORTI4 FERIOD: October 1968 GROSS 11URS IN REPORTING FER100: 745 3,323 MAX IEPEND CAPACITY (MWe-Net): 1,036

2. CURRENTLY AUTHORIIED PCWER LEVEL (MWt)

IESIGN ELECTRICAL RATING (MWe-Net) 1,078

3. PWER LEVEL TO WHICH RESTRICIED (If ANY) (MVe-Net): (None)

4. FEASONS FOR RESTRICTION (IF ANY): (N/A)

FE70RTING KRIOD IATA THIS MONTH YEAR-TO-DATE CUMULATIVE 745.0 4,467.1 24,555.3

5. TIME REACTOR CRITICAL (FOURS)

6. IIhE REACIOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 t,641.2

7. T!6E GENERAIGR ON-LINE (HOURS) 745.0 4,355.3 23,850.5

8. TIME GENERATOR RESERYE SHUTCCwN (HL%S) 0.0 0.0 1.0

9. THERMAL ENERGY GEhERAID (MLHt-Gross) 2,393,376 12,950,496 64,734,7(4 811,006 4,321 c 494 21,288,754

10. CLECTRICAL ENERGY GEhERATED (hkHe-Gross)

11. ELECTRICAL E6TRGY GENIRATED (MWHe-Net) 755,E65 4,133,166 29,270,036

12. DEACTOR SERVICE FACTCR (I) 100.0 61.0 57.9

13. REACTOR AVAILABILITY FACTOR (!) 100.0 41.0 61.6

14. SERVICE FACTOR (!) 10).0 59.5 56.3 l

15. AVAILIBILITY FACTM (!) 160.0 59.5 56.3 l

! 101.8 54.6 46.2

16. CAPACI11 FACTOR (USt% nDC) (!)

97.9 52.4 44.4

, 17. CAFACITY FACTOR (U51% EESIGN NVe) (!)

0.0 3.2 12.5 l 18. F0FCED OUTAGE FACTOR (t) 4 "Ya., & - DN ..J ~en \La" i

19. SHUTIGNS SchtDULED OVER THE heli 6 M0kiHS (IYFT, DATE, AND tt#ATION C# EACH): v h n N m be m c.s o n, & N t W re)

28. rr SHUitewur ENo cr ur0Rr rmoD, ESrrmEe em er Simur.

< re<~Cy<>g/M ^ J -

(N/A) 1 1

1 1

2. AVEP4'E DAILY LUIT F0kER LEVEL O'We-Net) DOCKET NO. 650-373

UNIT LA!ALLE ONE DATE Novesber 10,1988 C0hftETED BY J.W. THUNSTEDT TELEPHONE (815)-357-6761 P.EPORT FEA!06: October 1988 MY FCER DAT F%n I 1,059 17 1,035 2 1,002 18 i,065 3 993 19 i,077 4 1,064 20 t,049 5 1,C53 21 1,081 6 1,064 22 1,080 7 1,068 23 1,071 8 1,069 24 1,002 9 1,060 25 848 le 992 24 1,063 11 976 27 1,687 12 923 ^8 1,087 13 1,070 21 1,096 14 1,070 33 1,139 15 1,062 31 1,092 16 1,016

{

e-

3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. Q10-373 UNIT NAME T=C=lle one DATE Novemher 10. 1988 REPORT MONTH OCTOBER. 1988 COMPLETED BY J. Thunatedt TELEPHOttE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR. CORRECTIVE CO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS /COISENTS (None)

'l DOCUMENT ID 0043r/0031r

,E. UNIQUE REPORTING REQUIREMENTS

.- 1."Safety / Relief valve. operations for~ Unit Onw.

VALVES NO & TYPE PLANT DESCRIPTION DATE AC'IUATED ACIMAT10ti C0ttDITIOt{ OF EVENT There were no Safety Relief Valves actuations during the reporting period October 1, 1988 through October 31, 1988.

f 1

I i

r 1

t i

l 1

l l

r

, [

l l

, i i t

[

L L

DOCUMENT ID 0043r/0031r i l

[

l t

2 ECCS. Systems Outtgzo Th3 following outtg:s waro takan on ECCS Systems during

~

3 . . the reporting period.

OUTAGE NC. EOUIPMENT PURPOSE OF OUTAGE 0-270-88 "O" D/G A Air Compressor Investigate breaker trips 0-273-88 "O" D/G A Air Compressor Repair compressor 0-277-88 ODG08CA Investigate 0-291-88 "0" D/G (Administrate Control) t 0-292-88 "O" D/G Air Compressor Repair Co.apressor 1-1748-38 1A D/G Air Dryer Replace water trap 4

DOCUMENT ID 0043r/0031r

3. Off-Site Doss Calculation Manual.

No changes to Off-site Dose Calculation Manual during the reporting period.

4. Major. changes to Radioactive Waste Treatment Systems.

r No changes to Radioactive Waste Treatment systems during the reporting period.

5. Indications of Failed Fuel Elements No indications of Failed Fuel Elements on Unit One during this reporting period.

i t

4 t

4 I

i l

P l

i i DOCUMENT ID 0043r/0031r !

7 ,

I LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT OCTOBER, 1988 COMMONWEALTH EDISON COMPANY 1

NRC DOCKET 110. 050-374 LICENSE NO. NPF-18 DOCUMENT ID 0036r/0031r

t TABLE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT TWO 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. Changes to procedures which are described in the Safety Analysis Report.

3. Tests and Experiments not covered in the Safety Analysis Report.

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

DOCUMENT ID 0036r/0031r

, I. . INTRODUCTION 4

The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marsellies, Illinois.

Each unit is a Boiling Water 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 Commonwealth Edison Company.

Unit two was issued operating license 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 complied by John W. Thunstedt, telephone nunb9r

, (815)357-6761 extension 2463.

1 4

i l

i i

i DOCUMENT ID 0036r/0031r

- 4 i

II.- MONTHLY REPORT FOR l' NIT 'Df0 e

A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT TWO ,

October 1 0000 hours0 days 0 hours 0 weeks 0 months Unit Two on-line, reactor critical,' generator et' 665 MWe 1 October 14 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months Ramping to 430 MWe for RR testing-October 14 1126 hours0.013 days 0.313 hours 0.00186 weeks 4.28443e-4 months Mannal scram due to' loss of RR pumps ,

9-October 15 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months Began L2R02 (refuel outage)

October.31 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months Unit Two off-line, reactor'defueled i l

1 t

i l

t f

i r

DOCUMENT ID 0036r/0031r

,c B. PLANT OR PROCEDifRE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED 6; MAINTEN ANCE.

iss .

1. Amendments to Fecility license or Technical Specification.

4 (None)

2. Changes to procedures which are described in the Safety Analysis Report.

a. Temporary System Changes to allow waste sludge, URC sludge, spent resins, concentrator wastes, and separator sludges to be transferred to vendor's waste treatment system.

b. Off-gas pretreatment monitor changed from a logarithmic readout to a digital readout scale.

c. Minimum position interlock of Reactor Recirc flow control changed from 12% to 15% open of flow control valve,

d. Main Steamline flooding to maintain Secondary Containment during flooding.

3. Tests and Experiments not described in the Safety Analysis Report.

There were no tedts nor experiments not described in the Safety Analysis Report.

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 includet Work Request number, Component Name, cause of malfunction, rerults and effects on safe operation, and corrective action.

5. Completed Safety Related Modifications.

The following table (Table 2) presents a list of completed Mcdifications during this reporting period. Each entry will have a short synopsis explaining details involved with each modification.

DOCUMENT ID 0036r/0031r

TABLE 1 COR9ECTIVE MAINTENANCE OF .

SAFETY RELATED EQUIPMENT Unit 82 RESULTS AND EFFECTS WORK REQUEST CCMPCNENT CAUSE OF *IALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L79596 CVC5248 Faulty actuator Failed test Replaced actuator L80235 Recire Flow- Unit Faulty mode meter Failed test Replaced mode meter "C"

f_83000 2E12-F075A&B Faulty coils Failed Test Replaced coils L83943 PRM 32-17-B Dirty connector Drifting indicator Cleaned connectors L84274 APRM "E" Faulty instrument Failed test Replaced instrument (PC card)

L84355 IRM "A" Faulty connector Failed test Replaced connector L84468 2B21-N044B Faulty transmitter Failed test Replaced instrument L84557 IRM "B" Faulty switch Failed test Replaced switch L84565 2E21-N004 Faulty switch Minimum flow bypass Replaced switch flow limit exceeded (LPCS)

T,84706 2C71-5003C Faulty breaker Failed test Replaced breaker DOCUMENT ID 0036r/0031r

TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS MQDIFICATION NUMBER 1 A brief Synopsis of Incorporated Modification Objectives with final design resolution. Also, state reviewed or unreviewed safety questions.

UNIT 1WO (None)

IXXT. HENT ID 0036r/0031r

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

I LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, October 1, through October 31, 1988. This information is

. i provided pursuant to the reportable occurrence reporting requirements as t

set forth in 10CTR 50.73.

r llc 1Dsee Event Report Numhgr Rata Title of Occurrenct 88-012-00 10/14/88 30 Day, Mannual Scram due to loss of RR flow j 88-013-00 10/15/88 30 Day, LPCS Minimum flow Bypass Switch Greater than Reject Limit SOR 88-014-00 10/21/88 30 Day, Containment Leakage !

Exceeding 0.6LA i i

88-015-00 10/26/88 30 Day, 2A RHR Minimum Flow SOR l failure r

r DOCUMENT ID 0036r/0031r

r D. DATA TADULATIONS ,

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

l L

L l

r l

l DOCUMENT ID 0036r/0031r

l t.1)PERAi!G DATA FUtRT DOCXET NO. 650-374 UNIT LASALLE TWO DATE Novester to, 1988 CCMFtETED BY J.W. THUNSTEDT TELEftt0NE (815)-357-6761 0FLRai!C STATUS

1. RrftliTIK FERIOD: Odober 1968 GPOSS HOURS IN SEPORTI% FERICD: 745

2. CUPJENTLY AUTh0RIZED PCWER LEVEL (MWt): 3,323 MAX DEFEND CAPACITY ( N e-Net): 1,036 CESIGN ELICTRICAL RAi!NG (Ne-Net) 1,078

3. POWER LEVEL TO WICH FESTRICIES (If ANY) (PWe-Net): 0

4. REASCNS FDR RESTRICTION (!F ANY): Refsel Ostage .K.

REFORTIE FERIOD DATA THIS PCNTH YEAR-TO-DATE CU C Af!vE

5. TIME REACTOR CRITICAL (HCt13) 323.4 6,648.2 23,479.0

6. TIME REACICR RESERVE SHUID0VN (HOURS) 0.0 0.0 1,716.9

7. TIME GEhERATOR CN-LINE (HOLAS) 323.4 6,595.9 23.091.0

8. TIr.E GENEPATOR REEERiE SHUIDOW (HOL'RS) 0.0 0.0 0.0

9. THERML ENERGY GENERATED (NHt-Gross) 6S3,064 I3,144,552 65,939,608

10. ELECTRICAL ENERGY GENERATED (M W -Gross) 212,634 5,815,132 21,703,338

11. ELECTRICAL ENERGY GENEFATED (PWe-Net) 197,231 5,662,760 29,745,173

12. REACTOR SERVICE F ACTOR (I) 43.4 90.8 66.4

13. FIACICR AVAILABIllif FACTOR (1) 43,4 90.8 71.2

14. SERV!CE FACICR (!) 43.4 99.1 65.3

15. AVAILI)ILITY FACTCA (1) 43.4 99.1 65.3

16. C/IAClii iACTOR (l;31% MC) (1) 25.6 74.7 56.4

17. Ctf AClif FACTOR (US!kG DESIGN Ne) (1) 24.6 71.8 54.4

18. FCtCED CUTAGE FACTOR (!) 0.0 4.0 16.9 e'% .b.0S ,J %J.L;

19. SHUIDOW3 SCHEDULED 0i9 Tbt AEII 6 W1HS (TIFE, DATE, AND L(AAI!GN OF EACH):

(kre ) hvgjfwt be'^ (orret ' Cg 20 ir Sme.ui m a mm amp. Esimta nu u Smiur: 4, t r, c J7 c3,.f W >#

r,n. 1, i . im

r.

2. AVEPEE DAILY t:IT ftWER LEVEL (P.We-Nat) IEET NO. 656-374 UNIT Lt.SALLE TWO

DATE November is, 1933 CMftETED B7 J.W. THUNSTEDT TELEFHCAE(0151-357-6761 f.EPORT FERIOD: Ostober 1933 IAY fnER DAT f%Q t 642 17 -4 2 637 18 -3 3 646 19 -1 4 647 26 -3 5 647 21 -2 6 645 22 -2 7 637 23 -1 8 636 24 -3 7 641 25 -6 10 635 25 -1 11 632 27 0 12 627 29 6 13 632 29 -0 14 232 30 -1 15 -4 31 -1 16 -5

.?

1. UNIT SHLMS AND POWER REDUCTIOt:S Y "

DOCKET NO. 050-374 UNIT NAME F=C=lle Two ~*

DATE October 20. 1988 REPORT MONTH SEPTEMBER- 1988 COMPLETED BY J. h e tedt TELEPHONE (8151357-6761 METHOD OF f4 TYPE SHUTIING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE-NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWLt ACTIONS /COleG2rIS 14 F 13.6 G 2 Procedural error during instrument calibration tripped R2 Pumps, operator 3nitiated Manual Scram in accordance with procedures AS S 405 C 9 Continued previous '

shutdown period for Unit refuel e

.x ECCUMENT ID 0036r/0031r

. . ir

.s. E. . UNIQUE REPORTING REQUIREMENTS a ;

1. Safety / Relief Valve Operations for Unit Two.

DATI VALVES. NO & TYPE PLANT DESCRIPTION g) * - ACTUATED ACTIfATJ2S CCtiDITIM OF EVENT There were no Satety Rollef Valve actuations during the reporting period October 1, 196d through October 31, 1988.

i 1

l 1

i i

l 5

i i

l l

I

! DOCUMENT ID 0036r/0031r 1

L.

, 2. ECCS Sy; tem] Outag:s s

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

GLIAGE NO. EOUIPMENT EllRPOSE OF OUTAGE 2-593-88 HPCS CY flush Spool-piece Install spool piece 2-594-88 LPCS CY flush Spool-piece Install spool piece 2-666-88 2B D/G Rebuild t ir-start solenold, ,

Mod Work 2-667-88 2B D/G Refuel overhaul 2-668-88 25 D/G Relay calibration 2-669-88 2B D/G BOP calibrations 2-692-88 HPCS D/G Injection Stop Conduct relay logic test 2-731-88 HPCS (Various work requests) 2-733-88 HPCS (Various work requests) 2-736-88 HPCS (Various work requests) 2-746-88 2B D/G Drain and clean storage tank 2-761-88 2B D/G (Administrate Control) 2-762-88 RCIC Replace K15/KR15 Relays 2-842-88 LPCS Perform LES-LP-201/202 2-918-88 2A D/G Lubricate / Inspect 2-945-88 HPCS flush Spool-piece Remove Spool Piece DOCUNENT ID 0036r/0031r

3. Off-Sito Doss Calculation Manual

~

9 I

No changes to the Off-Site Dose Calculation Manual during this

}

reporting period.

4. Major changes to Radioactive Waste Treatment Systems.

To support the chemical decontamination (LOMI) process of the Unit 2 Reactor Recirculation piping in November of 1988, various bead resin wastes will be generated requiring solidification and disposal. Our present radwaste vendor will be unable to solidify these LOMI wastes in a timely manner. LaSalle Station has therefore opted to contract the services of LN Technologies to solid.fy the LOMI wastes.

LN Technologies

PCP uses an NRC aJcepted system for the solidification of the LOMI wastes. Concurrence to perform the PCP at reduced waste loadings has been obtained from the NRC and from South Carolina Department of Health and Environmental Control (Barnwell burial site). (See Oct. 26, 1988 letter from Paul Denault to Michael Tokar, Nov. 1, 1988 letter from Michael Tokar to Paul Denault, and Oct. 26, 1988 letter from Virgil Autry to William House.) LN's system has been designed to comply with all of the applicable codes, regulations, and industry standards including:

' 10CTR20, Standards for Protection Against Radiation 10CTR50, Licensing of Production and Utilisation racilities 10CF261, Licensing Requirements for Land Disposal of Radioactive Wastes 10CTR71, Packaging of Radioactive Materials Therefore, there is no reduction in the conformance of the solidified waste product compared to the current solidified waste critoria.

LN's PCP and solidification operating procedures will be reviewed and accepted by LaSalle Station's Onsite Review and Investigative Function under Onsite Review 88-067.

Technical Specification 6.9 -Major Changes to Radioactive Waste Treatment System 6.9.1.a.1 A copy of this revier will be included in the Monthly Operating Report to the Coemission. This document provides sufficient information to verify that the change was made in accordance with 10CTR50.59.

6.9.1.a.2 A copy of this review, and the 10CTR$0.59 review from OSR 88-067 will be included in the Monthly Operating Report to the Commission. These documents provide sufficient information to verify the rational for the change.

6.9.1.a.3 The following procedures were included in OSR 88-067, and provide detailed descriptions of the equipment, components, and processes involved in the solidification, and describe interfaces with other plant systems:

SS-011, System Set-Up/ Removal Procedure for LN Radwaste Solidification System No. 8958 DOCUMENT ID 0036r/0031r

f 3457-003, Op3r; ting Proc;duro far LN R:dw sto S211dificctio2 System No. 9858 for Uso ct L: Salla f 3262-006, Contamin tion Bib In3t:116 tion / Rem:v21 for LH s . Radwaste System No. 8958 e,t LaSalle 3457-004, Procesa Control Program for Radwaste Solidification of LONI Resins for Use at LaSa.11e 3457-002, Radwaste Sampling in LN Techno4ogies CD Style Liners at LaSalle 6.9.1.a.4 There are no anticipated new gaseous releases due to this solidification. There are no anticipated new 11guld relecses due to this solidification. Two liners of solidified resins (120 cu. ft. prior to solidification) will result from the decontamination. The license application and snendments did not predict any LONI wastes.

6.9.1.a.5 The expected maximum exposure to an individual in the unrestricted area, and to the general population, will not change. The solidification is being performed inside the restricted area, just as any other selldification.

6.9.1.a.6 There are no anticipated radioactive liquid effluents. Thete are no anticipated radioactive gareous effleunts. There will be two liners, an estimated 145 curies total, as solid waste.

This waste will supplement the r.ormal solid waste produced during the period.

6.9.1.a.7 An estimated 10 man-rem of exposure to plant personnel will result due to the decontamination and solidification.

6.9.1.a.8 The solidification of the LONI wastes was reviewed and approved by the Onsite Review and Investigative Function under OSR 88-067.

6.9.1.b This change becomes effective after approval of OSR 88-067.

5. Indications of Failed Fuel Elements.

Off Gas levels indicate that there is one pinhole Fuel Element failure in the reactor vessel. This does not represent a change from the previous reporting period.

There were no further indications of failed fuel elementa during this reporting period.

DOCUMENT ID 0036r/0031r

Commonwealth Edison o / ) LaSalle County Nucir r St: tion Rural Houte #1, Box 220

/ . - Marseilles, Illinois 61341 Telephone 815/367-67C1 November 10, 1988 Director of Nuclear Reactor Regulation United States Nuclear Regulatory CommisMion Hall Station F1-137 Washington, D.C. 20555 ATTN: Document Control Desk Gentlemen Enclosed for your information is the monthly performcnce report cover!ng LaSalle County N'uclear Power Station for the period October 1, 1988 through October 31, 1988.

Very t.21y yours, j{ . u G J. Diederich S ation Manager LaSalle County Station

'6Ya/gg4 dJD/JWT/crh i Enclosure xc A. B. Davis, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety P. Shemanski, NRR Project Manager D. P. Galle, CECO D. L. Tarrar, CECO INFO Records Center L. J. Anastasia, AIP Coordinator, Nuclear 5.. vices H. A. Ortin, GE Resident II . E. Bliss, Manager of Nuclear Licensing W. F. Haughton, Nuclear Tuel Services Manager C. T. Dillon, Senior Financial Coordinator, LaSalle Dennis Carlson/ Tech Staff Terry Novotney/1NPO Coordinator, Tech Steff Central file DOCUM ENT ID 004 3 r / 0031 r p

<

ML20206G761

Text

SUMMARY

SUMMARY

Navigation menu

Search