ML20202G284

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Monthly Operating Repts for June 1986
ML20202G284
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 06/30/1986
From: Diederich G, Peters J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8607150357
Download: ML20202G284 (61)
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LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT JUNE, 1986 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll 8607150357 860630 PDR ADOCK 05000373 R PDR __

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o TABLE OF CONTENTS i I. INTRODUCTION II. MONTHLY REPORT FOR UNIT ONE 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. Facility or Procedure Changes Requiring NRC Approval
3. Tests and Experiments Requiring NRC Approval
4. Corrective Maintenance of Safety Related Equipment C. LICENSEE EVENT REPORTS D. DATA TABULATIONS
l. Operating Data Report i 2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions l

E. UNIQUE REPORTING REQUIREMENTS.

1. Main Steam Relief Valve Operations
2. ECCS System Outages
3. Off-Site Dose Calculation Manual Changes
4. Major Changes to Radioactive Waste Treatment System J

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a g I. INTRODUCTION 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 Water Reactor with a designed net electrical output of 1078 Megawatts. 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 NPF-ll 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 James P. Peters, telephone number (815)357-6761 extension 325.

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o 3 II. MONTHLY REPORT FOR UNIT ONE

.A. SUI 9tARY OF OPERATING EXPERIENCE FOR UNIT ONE t

June 1-30 June 1, 0001 Hours. The Unit entered June with the Reactor subcritical and off-line in cold shutdown for first refueling outage.

June 30, 2400 Hours. Reactor in Cold Shutdown for First Refueling Outage.

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B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

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1. Amendments to facility license or Technical Specification.

AMENDMENT 43 - Revise NPDES Reporting Requirements and delete fog and ice monitoring program from Appendix B Technical Specifications (EPP).

AMENDMENT 44 - Add Additional zones to the fire detector table.

2. Facility or procedure changes requiring NRC approval.

There were no Facility or Procedure Changes Requiring NRC approval during this reporting period.

3. Tests and Experiments requiring NRC approval.

There were no tests or experiments requiring NRC approval during this reporting period.

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4. Corrective maintenance of safety related equipment.

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 include: Work Request number, Component Name, Cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.

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TABLE 1 CORRECTIVE MAINTENANCE OF

  • SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L20832 250VDC Control Room M-1-1-83-018 Additional Control Room Installed per M-1-1 Instrumentation Instrumentation. 018.
L51592 FW INBD Check Valve Poor Valve Performance Increase efficiency and Machine seats and Disc and IB21-F010A operating life of valve. line bore new stellite l bushings.

l L53273 RHR Hx Stm Supply Packing Leak. No Potential Effect Repack Valve and Tested from RCIC Valve electrically.

lE51-F064 L53344 "IN" Purge Valve Excessive Leakage Failure of LTS-100-33 Rebuilt valve internals, lIN074 L53660 Div-I Ground Detector Trip coil Terminal No Potential Effect Replaced coil assembly, lH13-P621 grounded on metal cover

( of solenoid Assembly, i

L53722 RCIC Turb. Trip and Bad 74 Device Failure of LES-RI-01 Replaced O/L relay on 74 throttle valve device.

MCC-121Y,lDC06E l

L53796 RCIC Suction From Faulty Aux. Contact Failure of LES-RI-01, valve Replaced with new S/P IE51-F031 would not open with C/S. component.

L53861 RCIC Stm. INBD Excessive Leakage Failure of LTS-100-24 Repaired seat and replaced Isolation valve steam nut.

IE51-F076.

L55104 Mechanical Snubber Failed Snubber. Failure of LTS-500-14 Replaced Snubber.

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TABLE 1 CORRECTIVE MAINTENANCE OF

  • SAFETY RELATED SQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L55989 Mechanical Snubbers Failed Snubbers. Failure of LTS-500-14 Replaced Snubbers.

IFWil-1003S and IRI24-ll20s.

L56294 S/P N2 Make-up Bad Torque switch contacts Valve will not operate correctly. Replaced torque switch.

Isolation valve IVg050 L56412 RCIC Vacuum Bkr. Internal Binding. Excessive current in excess of Repacked valve.

IE51-F080 130% of full load current.

L57802 "D" Vacuum Bkr. Excessive Leakage. Failure of LTS-500-1. Adjusted Seat Magnet.

IPC001D L57836 H2 Recomb. Vlv. Excessive Leakage. Failure of LTS-100-23. Rebuilt Valve, lHG005B.

L58134 Mechanical Snubber Failed Snubber Failure of LTS-500-14 Replaced Snubbers IMSO4-11585.

58138 Mechanical Snubber Failed Snubber Failure of LTS-500-14 Replaced Snubber.

IMS00-1012S ,

L58139 Mechanical Snubber Failed Snubber Failure of LTS-500-14 Replaced Snubber.

IMS00-1026S L58140 Mechanical Snubber Failed Snubber Failure of LTS-500-14 Replaced Snubber.

IMS00-1039S L58141 Mechanical Snubber Failled Snubber Failure of LTS-500-14 Replaced Snubber.

IMS00 1010s L58142 Mechanical Snubber Fallied Snubber- Failure of LTS-500-14 Replaced Snubber.

IMS50-402S Document 0043r/0005r __ _ _ _ _. _ _ _ _

TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT l

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L58143 Mechanical Snubber Failed Snubber Failure of LTS-500-14 Replaced Snubber.

IMS00-1016S LS8456 Mechanical Snubber Failed Snubber Failure LTS-500-14 Replaced Snubber.

IFWO2-Il47S L58457 Mechanical Snubber Failed Snubber Failure of LTS-500-14 Replaced Snubber.

M-1302-24-111 L58596 RCIC STM. Supply Bad Packing Water Leakage from stem. Replaced Packing.

Valve IE51-F063 LS8624 D/W Supply to H2 Excessive Leakage Failed LTS-100-23 Rebuilt Valve.

Recomb. lHG006B L58850 H2 Make-up Valve Nicked insulation on Control Power Fuses Blow. Replaced with new jumper.

IVQ050 Internal Jumper L58861 RHR Temp. Recorder Bad print head return Recorder does not with new Replaced print head return IE12-R601 spring. ink pad. spring.

L58890 S/P N2 Make-Up Misadjusted Limits Valve will not go full closed. Readjusted limits and Isolation valve cleaned contacts.

IvgC51 L59260 Div-II 125 VDC Bad Firing Module. Failure LES-DC-103 Replaced all failed Battery Charger amplifier module and components.

IDC16E. current sensing module.

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C. LICENSEE EVENT REPORTS \

i The following is a tabular summary of all licensee event reports for i LaSalle Nuclear Power Station, Unit One, logged during the reporting

period, June 1 through June 30, 1986. This information is provided I

pursuant to the reportable occurrence reporting requirements as set forth 4

in 10CFR 50.73.

Licensee Event Report Number Date Title of Occurrence 86-019-00 05/21/86 RHR pipe plug leaks due to entrapped slag or defect in plug seal weld.

86-020-00 05/30/86 Inadvertent ESF actuation due to loss of continuity in pCIS logic while installing a jumper due to personnel error.

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

1. Operating Data Report
2. Average Daily Unit Power Level r

. 3. Unit Shutdowns and Power Reductions 1

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,1. OPERATING DATA REPORT DOCKET NO. 050-373

  • UNIT LaSalle One DATE 7/10/86 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS
1. REPORTING PERIOD: Jur.e 1986 GROSS HOURS IN REPORTING PERIOD: ~120
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A
4. REASONS FOR RESTRICTION (IF ANY): N 'A THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0.0 12039.00
6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1642.00
7. HOURS GENERATOR ON LINE 0.0 _.'0.0 11642.00
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 0.0 0.0 32213650
10. GROSS ELEC. ENERGY GENERATED (MWH) 0.0 0.0 10499394
11. NET ELEC. ENERGY GENERATED (MWH) _.-10874 -58792 9945665
12. REACTOR SERVICE FACTOR 0.0% 0.0% 54.9%
13. REACTOR AVAI! ABILITY FACTOR 0.0% _ 020% 62.4%
14. UNIT SERVICE FACTOR 0.0% U.0% 53.3%
15. UNIT AVAILABILITY FACTOR 0.0% 0.0% 53.3%
16. UNIT CAPACITY FACTOR (USING MDC) -1.5% -1.3% 43.8%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) -1.4% -1.3% 42.1%
18. UNIT FORCED OUTAGE RATE 0.0% 0.0% 17.4%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, P 9 DURATION OF EACH)

The first refueling, maintenance, surveillance and modification outage began October 18, 1985 and will last till August, 1986.

20. IF SHUT DOWN AT END OF PEPORT PERIOD, ESTIMATED DATE OF STARTUP:

Start-up in August, 1986 is determined by administrative postulation upon completion of static-O-ring problem pending NRC approval.

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2. AVERAGE DAILY UNIT POWER LEVEL

, DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: 7/10/86 COMPLETED BY: James P. Peters TELEPHONE: J.8_15) 357-6761 MONTH: JUNE 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l (MWe-Net) (MWe-Net)

1. -15 17. -14
2. -15 18. -15 3 -15 19. -15
4. -16 20. _13
5. -16 21. -15
6. -16 22. -15
7. -16 23. -14
8. -15 24. -14
9. -16 25. -14
10. -16 26. -14

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-16 27. -15

12. -18 28. -14
13. -17 29. -14
14. -17 30. -14
15. -16 31. N/A
16. -14 I

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ATTACHMENT E

3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAME LaSalIe One -

. DATE 7/10/86 REPORT MONTH JUNE 1986 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 METfiCD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS /COPMENTS Thers were no Unit shutdowns or power reductions during this reporting period due to the first refueling outage, l

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. E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPR PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVRNT There were no Safety Relief Valves Operated for Unit one during this reporting period.

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, 2. ECCS Systems Outtg2s i

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

I j OUTAGE NO. BOUIPMENT PURPOSE OF OUTAGE 0-129-86 "O" DG "A" Air Troubleshoot motors.

Compressor.

, 0-131-86 "O" DG Diesel Oil Repair OD6004 Transfer 0-132-86 "O" DG OD6004 De-reterminate OD6004.

0-134-86 "O" DG Diesel Oil Repair OD6004.

Transfer 0-143-86 "O" DG Fuel Oil Adjust Pump Impeller 4 Transfer i 1-981-86 "A" RHR VLV's/Isol.Vlvs. Removal of ILRT Spool piece.

1-982-86 IFC27A Remove and Blank Flange.

1-987-86 1851-F031 Repair Aux. Contact 1-998-86 1E12-F008/b3B LIS-RH-312 1 1-999-86 "A" RHR Instal 1 Vents l-1001-86 IE12-F009/99B LIS-RH-312 1-1005-86 lE12-F047A Change Motor 1-1006-86 "A" RHR WS System Repair lE12-F068A 1-1009-86 "A" RHR Hydro. Net Vent Valves 1-1010-86 "B" And "C" RHR/LPCI LTS-500-10 1-1036-86 lE51-F022 Inspect Heat Shrink 1-1043-86 "B" RHR Install New Vents 1-1051-86 lE51-F063 LES-AP-101 l-1052-86 lE51-F076 LES-AP-101 1-1053-86 lE12-F009 LES-AP-101 1-1054-86 lE12-F009 LES-AP-101 1-1055-86 lE12-F099A LES-AP-101 1-1056-86 lE12-F099B LES-AP-101 j 1-1065-86 RCIC Barometric Cend. Troubleshoot Condensate Pp.

1-1074-86 IE12-F063B Fill "B" RHR System  ;

l-1075-86 IE12-F073A/74A LES-GM-109 l-1083-86 "B" RHR LES-GM-120 i

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3. Off-Site Dos 3 Csiculation Manual ,

Reference the attached copy of Revision 12 stating the changes made to the ODCM. ,

, 4. Radioactive Waste Treatment Systems.

There were no changes to the radioactive waste treatment

. system during this reporting period.

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June 30, 1986 )

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To: G. J. Diederich Station Manager LaSalle County Station

Subject:

Inclusion of the LaSalle County Station Offsite Dose calculation Manual, Site Specific Section 8.4, Revision 12, in the June Operating Report Per Technical Specifications, revisions to the Offsite Dose calculation Manual (ODCM) are to be included in the Station's Monthly Operating Report for submittal to the NRC.

The enclosed LaSalle ODCM, Site 9pecific Section 8.4, Revision 12, has completed the necessary onsite and offsite reviews, and appropriate comments incorporated. Please include this ODCM in the June Operating Report.

If you have any questions regarding this request, please feel free to call D. M. Kenealy of my staff at G.O. Extension 3271.

Sincerely, 8

J. C. Golden Supervisor of anergency Planning Enclosure cc: L. R. Aldrich J. P. Peters i

EPG-01-RE-ODCM12 l

DMK/1mk/6306E/48

, LA SALLE REVISZON 12 MAY 1986 ODCM LIST OF TABLES FOR LA SALLE SECTION 8.0 NUMBER TITLE PAGE 8.4-1 Environmental Radiological Monitoring Program 8.4-2 Reporting Levels for RadioGctivity 8.4-2 Concentrations in Environmental Samples 8.4-8 l 8.4-3 Maximum Values for the Lower Limits of Detection (LLD) 8.4-9 l 8-ii

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LA SALLE REVISION 12

. MAY 1986 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING 1

The environmental radiological monitoring program to be performed in the environs around La Salle County Station is given in Table  ;

8.4-1.

Figure 8.4-1 shows the 14 fixed air sampling sites and TLD locations; also shown are the " outer ring" (approximately 5 miles distant)

TLD locations. Figure 8.4-2.shows the " inner ring" TLD locations.

Figure 8.4-3 shows all other sampling locations. Most of the TLD's l are code numbered as follows: XYY-N, where:

X= 1 means inner ring, X= 2 means outer ring, and YY-N is an' identification code.

The reporting levels for radioactivity concentrations in environmental samples are given in Table 8.4-2.

The lower limits of detection for this program are given in l Table 8.4-3.

8.4-1

TABLE 9.4-1 -

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM TYPE AND EXPOSURE PATIIWAY SAMPLING OR FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCAT. ION COLLECTION FREQUENCY OF ANALYSIS a

1. Airborne a. Onsite and Near Field Continuous sampler Radioiodine operation with Canisters:

Radioiodine L-01, Near-site Station 1, 0.5 mi NW sample collection and L-02, Onsite Station 2, 0.6 mi N weekly I-131 analysis Particulates L-03, Onsite Station 3, 0.2 mi NE L-04, Near-site Station 4, 1.5 mi E L-05, Onsite Station 5, 0.3 mi SE Particulate L-06, Near-site Station 6, 0.4 mi W Sampler:

Gross beta E m

analysis m

  • following >

a

' filter E change b M Gamma isotopic on quarterly composite (by location)

Sampling Train:

Test and maintenance weekly jy

<<H HM O

mz H

M L _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

TABLE 8.4-1 (Cont'd) .

TYPE AND EXPOSURE PATilWAY SAMPLING OR FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATION COLLECTION FREQUENCY OF ANALYSIS

b. Far Field" Continuous sampler Radioiodine operation with Canisters:

L-07, Seneca, 5.2 mi NNE particulate filter L-08, Marseilles, 7.0 mi NW exchange weekly I-131 when L-09, Grand Ridge, 10.4 mi W and radioiodine analyses c L-10, Streator, 13.5 mi SW canister exchange are made L-ll, Ransom, 6.0 mi S bi-weekly L-12, Kernan, 5.0 mi SSW Particulate L-13, Route 6 at Gonnom, 4.3 mi E Sampler:

L-14, Ottawa, 12.0 mi NW Gross beta whenanagges ,

are made >

. m m

Sampling y

', Train: g

" Test and maintenance weekly 3 :o

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WU WH co O 04 2:

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TABLE 8.4-1 (Cont'd) .

TYPE AND EXPOSURE PATHWAY SAMPLING OR FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATION COLLECTION FREQUENCY OF ANALYSIS

2. Direct a. At Air Sampler Sites" Quarterly Gamma dose Radiation quarterly Same locations as fixed air sampling locations in Item 1.
b. Inner Ring Quarterly Gamma dose l quarterly 101-1, 0.5 mi N 101-2, 0.5 mi N 102-1, 0.6 mi NNE 102-2, 0.6 mi NNE o 103-1, 0.7 mi NE 103-2, 0.7 mi NE m 105-1, 0.7 mi E $

- - 105-2, 0.7 mi E y

  • 106-1, ESE 1.4 mi
  • 106-2, 1.4 mi ESE 107-1, 0.8 mi SE 107-2, 0.8 mi SE 109-1, 0.6 mi S 109-2, 0.6 mi S 110-1, 0.6 mi SSW 110-2, 0.6 mi SSW llla-1, 0.7 mi SW llla-2, 0.7 mi SW lllb-1, 0.8 mi SW 111b-2, 0.8 mi SW xx 112-1, 0.9 mi WSW $Q 112-2, 0.9 mi WSW H i

ll3a-1, 0.8 mi W $0 113a-2, 0.8 mi W "@

ll3b-1, 0.8 mi W 113b-2, 0.8 mi W C 114-1, 0.9 mi WNW

114-2, 0.9 mi WNW

TABLE 8.4-1 (Cont'd) .

TYPE AND SAMPLING OR FREQUENCY EXPOSURE PATilWAY OF ANALYSIS SAMPLING OR MONITORING LOCATION COLLECTION FREQUENCY AND/OR SAMPLE

2. Direct c. Outer Ring a Quarterly Gamma dose quarterly Radiation (Cont'd) 201-1, 2.0 mi N 201-2, 2.0 mi N 202-1, 2.3 mi NNE 202-2, 2.3 mi NNE 203-1, 4.0 mi NE

' '~ 203-2, 4.0 mi NE

~~ 204-1, 3.5 mi ENE 204-2, 3.5 mi ENE &

205-1, 3.5 mi E p 205-2, 3.5 mi E m 206-1, 4.3 mi ESE $

M 206-2, 4.3 mi ESE 207-1, 4.5 mi SE

& 207-2, 4.5 mi SE i 208-1, 4.5 mi SSE 208-2, 4.5 mi SSE 209-1, 4.0 mi S i 209-2, 4.0 mi S 210-1, 3.3 mi SSW 210-2, 3.3 mi SSW 211-1, 4.5 mi SW j 211-2, 4.5 mi SW

212-1, 4.0 mi WSW 212-2, 4.0 mi WSW

' 213-1, 3.8 mi W xx 213-2, 3.8 mi W $$

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214-1, 2.0 mi WNW $$

214-2, 2.0 mi WNW 215-1, 2.0 mi NW "@

215-2, 2.0 mi NW g u

' 216-1, 1.5 mi NNW 216-2, 1.5 mi NNW .

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TYPE AND EXPOSURE PATHWAY SAMPLING OR FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATION COLLECTION FREQUENCY OF ANALYSIS

3. Waterborne" l
a. Surface L-21, Illinois River at Seneca, Weekly collection Gamma isotopic 4.0 mi NNE composited monthly on monthly L-23, Illinois Nitrogen Co., composite; 5.3 mi NNW composite '

L-24, LSCS Cooling Lake near quarterly for recreation area tritium analysis.

b. Ground L-28, Marseilles Well, 7.0 mi NW Quarterly Gamma isotopic L-29, Seneca Well, 5.1 mi NNE and tritium L-30, Ransom Well, 6.0 mi S analysis E m L-31, Ottawa Well, 12.8 mi NW quarterly u,

. L-32, Illinois State >

d Park 6.5 mi NW E M

c. Sediment L-34, Downstream of Cooling Lake Semiannually Gamma isotopicl from discharge structure at station analysis Shoreline semiannually 38 M M<

m WH mO mZ W

tQ a

TABLE 8.4-1 (Cont'd) .

TYPE AND EXPOSURE PATHWAY SAMPLING OR FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATION COLLECTION FREQUENCY OF ANALYSIS

4. Ingestion
  • l
a. Milk L-15, Granby Farm, 7.0 mi E Weekly: May to Gamma isotopic L-16, Lowery Dairy, 7.2 mi ESE October and I-131 L-17, Norsen Dairy, 9.0 mi NNW Monthly: November analysis on L-18, Sunny Isle Farm, 12.8 mi NNE to April each sample
b. Fish L-24, LSCS Cooling Lake near Semiannually Gamma isotopic recreation area analysis on L-35, Marseilles Pool of edible portions Illinois River, 6.5 mi NW of each sample n.

2 m $

. . n a r e M 4

a. See Figure 8.4-1.
b. Perform gamma isotopic analysis on each sample when gross beta activity is greater than (>) 10 times the yearly mean of control samples.
c. Far field samples are analyzed when near field results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents released from the station, or at the discretion of the Emergency Planning Supervisor. s$
d. See Figure 8.4-2. ,

gh mo

  • Z
e. See Figure 8.4-3.

M M

d TABLE 8.4-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBORNE PARTICULATE WATER FISH MILK ANALYSIS (pCi/ g) ORGASEg)

(pCi/m (pCi/kg, wet) (pCi/ g)

H-3 20,000*

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 g

, . Co-60 300 10,000 g e

i Zn-65 300 20,000 y m

Zr-Nb-95 400 I-131 2 0.9 3 Cs-134 30 10 1,000 60 Cs-137 50 20 2,000 70 B a-La-14 0 200 300 gy d

  • For drinking water samples. This is 40 CFR Part 141 value.
  • g mz C

TABLE 8.4-3 MAXIMUM VALUES FOR Tile LOWER LIMITS OF DETECTION (LLD)a,b ,

AIRBORNE PARTICULATE WATER OR GASgS FISil MILK SEDIMENT ANALYSIS (pCi/t) (pCi/m ) (pCi/kg, wet) (pCi/t) (pCi/kg, dry)

Gross Beta 5 0.01 1,000 NA 2,000 H-3 200 NA NA NA NA

  • NA ** * **

Mn-54

  • NA ** * **

Fe-59

  • NA ** * **

Co-58,60

  • NA ** * ** g Zn-65 ,

n

, Zr-95

  • NA
  • r4 i
  • ** * ** E Nb-95 NA NA 0.1 ** 0.5 **

I-131 100 **

Cs-134 10 0.01 10 Cs-137 10 0.01 100 10 Ba-140

  • NA ** * **

La-140

  • NA  %$

d

  • Gamma isotopic analysis provides LLD of - 20 pCi/g per nuclide. h8 j ** Gamma isotopic analysis provides LLD of - 20 pCi/kg per nuclide.

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~

-- ._= . _ -. - _.

LA SALLE REVISION 12 MAY 1986 TABLE 8.4-3 (Cont'd)

TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation -

represents a "real" signal.

For a particular measurement system (which may include radiochemical separation) :

4.66 s b LLD = E. V. 2.22. Y. exp (-Aa t) I where:

LLD is the "a priori" lower limit of detection as defined above (as picocurie per unit mass or volume), j s s is the standard deviation of the background counting rXte or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per transformation) ,

V is the sample size (in units of mass or volume),

2.22 is the number of transformations per minute per picocurie, Y is the f ractional radiochemical yield (when applicable),

A is the radioactive decay const7nt for the particular l radionuclide, and l At is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluents). j l

The value of s b used in the calculation of the LLD for a  !

detection system shall be based on the actual observed variance  ;

of the background counting rate or of the counting rate of j the blank samples (as appropriate) rather than on an unverified '

theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g.,

potassium-40 in milk samples). Typical values of E, V, Y, and at shall be used in the calculations,

b. Other peaks which are measurable and identifiable, together with the radionuclides in Table 8.4-3 shall be identified and reported.

8.4-10

REVZSIOM 12 '

MAY 1986 Ottawa {mEg i

o14 35 ff,'.

I Marseilles South %s B#'

Ottawa 8e Seneca i V e 203-1 215-1 216-1 201-1 202 1 215-2 216-2 201-2 202 2 e 203-2 es ,se se se 1 214-2 e 1 2* a 204-1 l

213-2 e 214-1 e 213-1 e 3e Plant

  • e 204-2

, g 212-2 e a 205-1 212-1 e I e 205' 2 Site Property e13 l

e 20s-1 a 206-2 Verona 9' Grand Ridge == $li.! ,,,

se ,,10 2 2 sein:1 sin:1 ,

"" 208-1 20s 2 Kinsman 11eRansom e

12 i

Kernan Streator 10' Grundy La Salle County _

County _

Livingston County l

I t

i

? 0 1 2 3 4 5 Miles LA SALLE COUNTY ST ATION i

0 2 4 6 8 10 Kilometers FIGURE 8.4-1 l FIXED AIR SAMPLING SITES AND OUTER RING TLD LOCATIONS 0

REVZSION 12 MAY 1986

- q'p\

, g\

p' . ,02.,

e 102-2

\ N. 22 "d St. , jot 2

\ -- 103$ 031 Waste Stabilization Pond e 114-2 a 1141 s

,X .

E: .,u Me% M'"'l ex\

IN'.'

  1. 105-t m )

N e 112 2 E 112-1 1

11A 1 107 gg g

, j11B 1 , [10-1 , ,109-1 111 A-2 110-2 109-2 107 1 "1118 2 o o.2 o.4 o.s o.s 1.o mine.

N- o o.4 o.s 1.2 1.s 2.0 Kilometers j

LA SALLE COUNTY STATION FIGURE 8.4-2 INNER RING TLD LOCATIONS TA# as l

REVISION 12 MAlf 1986 L-t a e e l-80 Ottawa Marseilles U.S.6

  • [

filinoig L-2s Seneca L-35 L.23 e L-29 L-32 L-21 Rt.23 f

e t-is L 34

e Ransom L-30 e

-n-o 1 2 3 4 s Miles LA SALLE COUNTY STATION O 2 4 6 8 to Kilometers l

p FIGURE 8.4-3 If'iESTION AND WATERBORNE EXPOSURE PATHWAY SAMPLE LOCATIONS 3fA'369

1 i

LASALLE NUCLEAR POWER STATION

UNIT 2 i MONTHLY PERFORMANCE REPORT JUNE 1986 COIMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 DOCUMENT ID 0036r/0005r

l

. TABLE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT TWO A. Sununary of Operating Experience B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

1. Amendments to Facility License or Technical Specifications
2. Facility or Procedure Changes Requiring NRC Approval
3. Tests and Experiments Requiring NRC Approval
4. Corrective Maintenance of Safety Related Equipment 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 i

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_ - - - . _ . _ _ ~ . . _ . _ -. _ _ . . , . _ _ .,

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\

I. INTRODUCTION 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 Water Reactor with a designed net electrical output of 1078 Megawatts. 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 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 compiled by James P. Peters, telephone number (815)357-6761 extension 325.

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I DOCUMENT ID 0036r/0005r

II. MONTHLY REPORT FOR UNIT TWO

k. SUf9fAltY OF OPERATING EXPERIENCE FOR UNIT TWO

]

June 1-30 l June 1, 0001 Hours The Unit entered June with the Reactor critical at 99% Power and generator on line at 1048 MWe.

j June 1, 0445 Hours. Reactor Power Decreased 45% (530 MWe) Due to feedwater pumps lock up ("A" Pump in manual and "B" in 3-element control).

June 1, 1430 Hours. Commenced unit shutdown per LGP-2-1 at approximately 100 MWe/Hr.

June 1, 1815 Hours. Inserted Channel "A" RPS scram with a do not reset order per

Shift Engineer. Declared RPS Channel "A" Inoperable, due to level problem.

June 1, 1830 Hours. Declared GSEP Alert.

June 2, 0015 Hours. Turbine taken off-line. 1 June 2, 1135 Hours. Terminated GSEP Alert.

June 3, 0925 Hours. Per LGP-2-1 All Rods Full in Reactor and mode switch taken to shutdown position and scram reset.

June 4, 1830 Hours "A" RHR Shutdown cooling loop declared inoperable, utilizing steam line drains for decay heat r i removal.

June 4, 1755 Hours. Unit Entered condition #4, cold shutdown.

l June 30, 2400 Hours. Reactor in Cold Shutdown while investigation in progress for

solution to static-o-ring

! problems. ,

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- - - _. _ . _ _ _ _ . ,__. _- ,- ..=_. _ -. - - . = - , _ . . _ _ _ . , ~ . _ - , _ . - - . . _ _ _ , _ . . _ _ . . - _ . _ _ _ . - . --

DJ PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

1. Amendments to facility license or Technical Specification.

AMENDMENT 24 - Revise NPDES Reporting Requirements and delete fog and ice monitoring program from Appendix B Technical Specifications (EPP).

2. Facility or procedure changes requiring NRC approval.

There were no facility or procedure change requiring NRC approval during the reporting period.

3. Tests and experiments requiring NRC approval.

There were no tests or experiments requiring NRC approval during the reporting period.

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 stannary include: Work Request number, component Name, cause of malfunction, results and effects on safe operation, and corrective action.

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DOCUMENT ID 0036r/0005r l l

_. . _ ~ - - . - _ _ - _ _ _ - _ . . . -

TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMEhr

~

i WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L45134 VQ Control Panel M-1-2-85-014 Relocate Local Control Panel. Relocated 2PL71J.

2PL71J LS8210 Control Room Process Alarm Point out of Spec. Reading HI and High Alarm light Readjusted setpoint Rad. Monitor Low. keeps tripping. Per LIS-AR-05.

2D18-K751D 1

L59171 S/P Water Temp. Computer Point Reads to 2TI-CM037 shows A Differential Adjusted computer i recorder 2TI-CM037 high. Pressure of 10 degrees between point.

control room and remote shutdown panel.

4

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s

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i DOCUMENT ID 0036r/0005r l

C. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, May 1 through May 31, 1986. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Licensee Event Report Number Date Title of Occurrence 86-008-00 05/09/86 Scram on low level due to stationman bumping MCC for both feedwater level control panel.

86-009-00 05/11/86 MSL HI Flow Group-I isolation Reactor scram due to unknown factors.

86-010-00 05/25/86 Failure to perform surveillance on RWM and RSCS during power reduction due to insufficient procedure.

f DOCUMENT ID 0036r/0005r I

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

i 1. Operating Data Report

2. Average Daily Unit Power Level ,
3. Unit Shutdowns and Power Reductions i

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f DOCUIUDIT ID 0036r/0005r .

I

1. OPERATING DATA REPORT

+ DOCKET NO. 050-374 UNIT LaSalle Two DATE 7/10/86 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: June, 1986 GROSS HOURS IN REPORTING PERIOD: 720
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net):1078
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A
4. REASONS FOR RESTRICTION (IF ANY): N/A THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 33.4 3213.39 8602.79
6. REACTOR RESERVE SHUTDOWN HOURS 0.0 29.83 29.83
7. HOURS GENERATOR ON LINE 24.25 3152.29 8388.59
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 48936 9148872 24657424
10. GROSS ELEC. ENERGY GENERATED (MWH) 15012 3050559 8160628
11. NET ELEC. ENERGY GENERATED (MWH) 4295 2943132 7766347
12. REACTOR SERVICE FACTOR 4.6% 73.9% _57.7%
13. REACTCR AVAILABILITY FACTOR 4.6% 74.7% 57.9%
14. UNIT SERVICE FACTOR 3.4% 72.6% 56.3%
15. UNIT AVAILABILITY FACTOR 3.4% 72.6% 56.3%
16. UNIT CAPACITY FACTOR (USING MDC) 0.6% 65.4% 50.3%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 0.55% 62.9% 48.3%
18. UNIT FORCED OUTAGE RATE 96.6% 27.4% 27.4%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

None.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP Start-up is determined by administrative postulation upon completion of static-o-ring problem pending NRC approval.

1 DOCUMENT ID 0036r/0005r

___ , _ . . = _ _. _ ___ _ _ . _ _ _ , -.._ ,. _ _ _

2. AVERAGE DAILY UNIT POWER LEVEL

- DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: 7/10/86 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: June 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 600 17. -14
2. -14 18. -14 3 -14 19. -14
4. -15 20. -12
5. -15 21. -14
6. -16 22. -14
7. -15 23. -14
8. -14 24. -14
9. -15 25. -14
10. -15 26. -14
11. -16 27. -14
12. -17 28. -14
13. -17 29. -14
14. -16 30. -14
15. -16 31. N/A
16. -13 1

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DOCUMENT ID 0036r/0005r

I ATTACHMENT E l 3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT WAME LaSa11e Two-DATE 7/10/86 REPORT MONTH JUNE 1986 COMPLETED BY James P. Peter.g TELEPHONE (815)357-6761 I

METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS / COMMENTS l

l 22 06/01/86 F 9.85 A 5 Spurious signal causing

! a feedwater pump lockup

("A" pump in manual and

( "B" pump in 3-element).

j l 23 06/02/86 F 685.90 A 1 Static-O-Ring problem uncovered due to feedwater transient.

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DOCUMENT ID 0036r/0005r

E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION I ACTUATED ACTUATIONS CONDITION OF EVENT There were no safety relief valves operated for Unit #2 during this reporting period.

DOCUMENT ID 0036r/0005r '

, 2. ECCS Systems Outag s The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE 2-296-86 2E12-F003A Inspect / Repair 2-297-86 2E12-F003A Inspect / Repair 2-298-86 2E12-F003A LOP-RH-17 2-316-86 2E12-C002C Sample Oil 2-319-86 2E12-F009 Install Txque Switch limiter Plate 2-230-86 HPCS Pump Sample Oil 2 2-324-86 2E12-F009 Install Torque Switch limiter plate.

2-327-86 2E21-F003 Repair Check Valve 2-340-86 2E51-F008 Repack Valve 2-341-86 2E51-D003 Repair Drain Trap 4 2-345-86 2D6002P LIP-DG-03 2-349-86 "B" RHR WS PRM Decon. Detector 2-354-86 "A" DG "B" Air Comp. Repair / Replace Relief 1

2-357-86 RHR Div.-I S/D Cool. LIS-RH-412 2-358-86 RHR Div.-II S/D Cool. LIS-RH-412 2-359-86 2E12-F087 Cable Segregation Problem 2-361-86 "C" RHR LES-GM-120

2-362-86 "A" DG LIP-DG-03 2-363-86 "A" RHR LES-GM-120 f

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DOCUMENT ID 0036r/0005r j

)

3. Off-Sits Dosa Calculation Manual Reference the attached copy of Revision 12 stating the changes made to i the ODCM.
4. Radioactive Waste Treatment Systems.

There were no changes to the' radioactive waste treatment system during this reporting period.

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DOCUMENT ID 0036r/0005r

o s

June 30, 1986 To: G. J. Diederich Station Manager LaSalle County Station

Subject:

Inclusion of the LaSalle County Station offsite Dose Calculation Manual, Site Specific Section 8.4, Revisien 12, in the June Operating Report Per Technical Specifications, revisions to the Offsite Dose Calculation Manual (ODCM) are to be included in the Station's Monthly Operating Report for submittal to the NRC.

The enclosed LaSalle ODCM, Site Specific Section 8.4, Revision 12, has completed the necessary onsite end offsite reviews, and appropriate comments incorporated. Please include this ODCM in the June Operating Report.

If you have any questions regarding this request, please feel free to call D. M. Kenealy of my staff at G.O. Extension 3271.

Sincerely, i

J. C. Golden Supervisor of Emergency Planning l Enclosure cc: L. R. Aldrich J. P. Peters EPG-01-RE-ODCM12 DMK/1mk/6306E/48

O

  • LA SALLE REVISION 12

. MAY 1986 ODCM LIST OF TABLES FOR LA SALLE SECTION 8.0 NUMBER TITLE PAGE 4

8.4-1 Environmental Radiological Monitoring Program 8.4-2 8.4-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 8.4-8 l 8.4-3 Maximum values for the Lower Limits of Detection (LLD) 8.4-9 l 1

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l 8-11

. LA SALLE REVISION 12 MAY 1986 8.4 ENVIRONMENTAL RADIOLOGICAL MONITORING The environmental radiological monitoring program to be performed in the environs arou..d La Salle County Station is given in Table 8.4-1.

Figure 8.4-1 shows the 14 fixed air sampling sites and TLD locations; also shown are the " outer ring" (approximately 5 miles distant)

TLD locations. Figure 8.4-2.shows the " inner ring" TLD locations.

Figure 8.4-3 shows all other sampling locations. Most of the TLD's l are code numbered as follows: XYY-N, where:

X= 1 means inner ring, X= 2 means outer ring, and YY-N is an identification code.

The reporting levels for radioactivity concentrations in environmental samples are given in Table 8.4-2.

The lower limits of detection for this program are given in l Table 8.4-3.

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( 8.4-1 i

l TABLE 8.4-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM TYPE AND EXPOSURE PAT!!WAY SAMPLING OR FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCAT. ION COLLECTION FREQUENCY OF ANALYSIS

1. Airborne a. Onsite and Near Field,a Continuous sampler Radioiodine operation with Canisters:

Radioiodine L-01, Near-site Station 1, 0.5 mi NW sample collection and L-02, Onsite Station 2, 0.6 mi N weekly I-131 analysis Particulates L-03, Onsite Station 3, 0.2 mi NE L-04, Near-site Station 4, 1.5 mi E L-05, Onsite Station 5, 0.3 mi SE Particulate L-06, Near-site Station 6, 0.4 mi W Sampler:

Gross beta $

, analysis m o

following >

? filter change b d

u M

Gamma isotopic on quarterly composite (by location)

Sampling Train:

Test and maintenance weekly @@

i' H HM eH cn o Ch Z w

M

TABLE 8.4-1 (Cont'd) .

TYPE AND EXPOSURE PATilWAY SAMPLING OR FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATION COLLECTION FREQUENCY OF ANALYSIS

b. Far Field" Continuous sampler Radioiodine operation with Canisters:

L-07, Seneca, 5.2 mi NNE particulate filter L-08, Marseilles, 7.0 mi NW exchange weekly I-131 when L-09, Grand Ridge, 10.4 mi W and radioiodine analyses L-10, Streator, 13.5 mi SW canister exchange are made L-ll, Ransom, 6.0 mi S bi-weekly L-12, Kernan, 5.0 mi SSW Particulate L-13, Route 6 at Gonnom, 4.3 mi E Sampler:

L-34, Ottawa, 12.0 mi NW Gross beta whenanagges ,

are made >

en co Sampling y

, Train: &

i M Test and maintenance weekly x :o lrs M M<

s H (O WH mO

<h Z t*

tJ

TABLE 8.4-1 (Cont'd) ,

TYPE AND EXPOSURE PATHWAY SAMPLING OR FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATION COLLECTION FREQUENCY OF ANALYSIS

2. Direct a. At Air Sampler Sites a Quarterly Gamma dose Radiation quarterly Same locations as fixed air sampling locations in Item 1.
b. Inner Ring Quarterly Gamma dose l quarterly 101-1, 0.5 mi N 101-2, 0.5 mi N 102-1, 0.6 ni NNE 102-2, 0.6 mi NNE n 103-1, 0.7 mi NE >

103-2, 0.7 mi NE m

, 105-1, 0.7 mi E $

^

105-2, 106-1, 0.7 mi 1.4 mi E

ESE Ei

  • 106-2, 1.4 mi ESE 107-1, 0.8 mi SE 107-2, 0.8 mi SE 109-1, 0.6 mi S 109-2, 0.6 mi S 110-1, 0.6 mi SSW 110-2, 0.6 mi SSW llla-1, 0.7 mi SW 111a-2, 0.7,mi SW lllb-1, 0.8.mi SW 111b-2, 0.8 mi SW 33 112-1, 0.9 mi WSW >m 112-2, 0.9 mi WSW *$

113a-1, 0.8 mi W GS ll3a-2, 0.8 mi W mo ll3b-1, 0.8 mi W **

ll3b-2, 0.8 mi W [

114-1, 0.9 mi WNW 114-2, 0.9 mi WNW

. _ _ _ . - . . _ __ _. . _ _ = - - - _ - .- .- - .. _ - . - . _ . -

TABLE 8.4-1 (Cont'd) .

TYPE AND EXPO 3URE PATHWAY SAMPLING OR FREQUENCY SAMPLING OR MONITORING LOCATION COLLECTION FREQUENCY OF ANALYSIS

-AND/OR SAMPLE

2. Direct c. Outer ' Ring" Quarterly Gamma dose Radiation quarterly j (Cont'd) 201-1, 2.0 mi N ~

201-2, 2.0 mi N

< 202-1, 2.3 mi NNE 202-2, 2.3 mi NNE 203-1, 4.0 mi NE 203-2, 4.0 mi NE 204-1, 3.5 mi ENE

! 204-2, 3.5 mi ENE 3

205-1, 3.5 mi E y 205-2, 3.5 mi E m 206-1, 4.3 mi ESE $

^' M li 206-2, 4.3 mi ESE j, 207-1, 4.5 mi SE E 207-2, 4.5 mi SE 208-1, 4.5 mi SSE 208-2, 4.5 mi SSE 209-1, 4.0 mi S 4

209-2, 4.0 mi S j 210-1, 3.3 mi SSW i 210-2, 3.3 mi SSW i 211-1, 4.5 mi SW j 211-2, 4.5 mi SW

~

212-1, 4.0 mi WSW j 212-2, 4.0 mi WSW

213-1, 3.8 mi W zm 213-2, 3.8 mi W $Q H 214-1, 2.0 mi WNW g 214-2, 2.0 mi WNW ws j 215-1, 2.0 mi NW "@

215-2, 2.0 mi NW g 216-1, 1.5 mi NNW w

! 216-2, 1.5 mi NNW .

e i

E_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . . .

_ _ _ _ _ _ _ _ _ _ _ _ _ _ ~ . __ __ _ - _.___ - . _ _ _ . . _ . _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _. . -. __ . .

TABLE 8.4-1 (Cont'd)

  • TYPE AND EXPOSURE PATHWAY SAMPLING OR FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATION COLLECTION FREQUENCY OF ANALYSIS
3. Waterborne" , l
a. Surface L-21, Illinois River at Seneca, Weekly collection Gamma isotopic 4.0 mi NNE composited monthly on monthly L-23, Illinois Nitrogen Co., ' composite; 5.3 mi NNW composite
  • L-24, LSCS Cooling Lake near quarterly for recreation area tritium analysis.

l

b. Ground L-28, Marseilles Well, 7.0 mi NW Quarterly Gamma isotopic L-29, Seneca Well, 5.1 mi NNE and tritium L-30, Ransom Well, 6.0 mi S analysis E m L-31, Ottawa Well, 12.8 mi NW

, quarterly m a, L-32, Illinois State >

1 Park 6.5 mi NW E' M

c. Sediment L-34, Downstream of Cooling Lake Semiannually Gamma isotopicl from discharge structure at station analysis Shoreline semiannually

.s I

>M M<

! H

& TJ)

@H j

CD O 04 Z H

w

'f =

1

TABLE 8.4-1 (Cont'd)

TYPE AND EXPOSURE PATHWAY SAMPLING OR FREQUENCY AND/OR SAMPLE SAMPLING OR MONITORING LOCATION COLLECTION FREQUENCY OF ANALYSIS

4. Ingestion
  • l
a. Milk L-15, Granby Farm, 7.0 mi E Weekly: May to Gamma isotopic L-16, Lowery Dairy, 7.2 mi ESE October and I-131 L-17, Norsen Dairy, 9.0 mi NNW Monthly: November analysis on L-18, Sunny Isle Farm, 12.8 mi NNE to April each sample
b. Fish L-24, LSCS Cooling Lake near Semiannually Gamma isotopic recreation area analysis on L-35, Marseilles Pool of edible portions Illinois River, 6.5 mi NW of aach sample n

?

E n

l

a. See Figure 8.4-1.

t

b. Perform gamma isotopic analysis on each sample when gross beta activity is greater than (>) 10 times the yearly mean of control samples.
c. Far field samples are analyzed when near field results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents 3, released from the station, or at the discretion of the Emergency Planning Supervisor. >M a

<<M ,

d. See Figure 8.4-2.  ;;m mo
e. See Figure 8.4-3. *Z

[

TABLE 8.4-2 ,

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBORNE PARTICULATE WATER FISH MILK A_NALYSIS (pCi/1) ORGASEg)

(pCi/m (pCi/kg, wet) (pCi/g)

H-3 20,000*

i Mn-54 1,000 30,000 Fe-59 400 10,000 l Co-58 1,000 30,000 g

,, m Co-60 300 10,000 g a &

m i Zn-65 300 20,000 y Zr-Nb-95 400 I-131 2 0.9 3 Cs-134 30 10 1,000 60

) Cs-137 50 20 2,000 70 Ba-La-140 200 300 gy

.i K <:

HN

  • For drinking water samples. This is 40 CFR Part 141 value. gg mz

TABLE 8.4-3 -

MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,b AIRBORNE PARTICULATE WATER OR GASgS FISH MILK SEDIMENT ANALYSIS (pCi/t) (pCi/m ) (pCi/kg, wet) (pCi/g) (pCi/kg, dry)

Gross Beta 5 0.01 1,000 NA 2,000 H-3 200 NA NA NA NA Mn-54

  • NA ** * **

Fe-59

  • NA ** * **

Co-58,60

  • NA ** * **

Zn-65 * ** * **

NA g es

, Zr-95

  • NA ** * ** y e t' Nb-95
  • NA ** * ** E I-131 NA 0.1 ** 0.5 **

Cs-134 10 0.01 100 10 **

Cs-137 10 0.01 100 10 **

Ba-140

  • NA ** * **

i La-140

  • NA ** * **

k<

HU

^

  • Gamma isotopic analysis provides LLD of - 20 pCi/g per nuclide. g5
    • Gamma isotopic analysis provides LLD of ~ 20 pCi/kg per nuclide. **

U

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LA SALLE REVISION 12 o MAY 1986

. 1 TABLE 8.4-3 (Cont'd)

TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. -

For a particular measurement system (which may include radiochemical separation):

4.66 s b LD=

E. V. 2.22. Y. exp (-Aa t) where:

LLD is the "a priori" lower limit of detection as defined above (as picocurie per unit mass or volume),

s h is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per transformation),

V is the sample size (in units of mass or volume),

2.22 is the number of transformations per minute per picocurie, Y is the f ractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between sample collection (or end of the sample collection period) and time of counting l (for environmental samples, not plant effluents). l The value of s u used in the calculation of the LLD for a detection systNm shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g.,

potassium-40 in milk samples). Typical values of E, V, Y, and at shall be r97d in the calculations,

b. Other peaks which are measurable and identifiable, together with the radionuclides in Table 8.4-3 shall be identified and reported.

8.4-10

REVISION 12

' MAY 1986 Ottawa jg WSI o14 j$

I~ Marseilles South ff,'%s Ottawa 8 @ *'

Seneca i M l 215-1 216-1 201-1 202-1 e 203-1 215-2 216-2 201 2 202 2 e 203-2 es se se so I 214-2 e 214-1 e 2' a 2041 l

213-2 e 213-1 e 3e Plant

  • e 204-2

, g O e 205-1 212-2 e I 2121 e e 205-2' Site Property e13 l

gg a 206-1

  • 282 Grand Ridge se 2jj t 2 Verona

" 2i0-i 210-2 es$,-j e 2gg,g

  • 38 1

" 20s-2 Kinsman 11eRansom e12 8 i Kernan Streator e

10 Grundy La Salle County County Livingston County i

@ 0 Miles LA SALLE COUNTY STATION N

d 0 0 Kilometers FIXED AIR SAMPLING SITES AND OUTER RING TLD LOCATIONS

REVXSION 12 MAY 1986

\ '" > \\ \,

x.

d'* ' x. \

h a 102-1

, y a 102-2

\

N.22"d St. ,j01-2 Ng lNa,*0s, a 114-2 Waste Stabilization Pond E 114-1 3

, . A k'..

\\ WYi\\\\3\

1 - hk' 7 \

M) 105-1 e s

N

=

"1110-2 118 1 111A 2 1A 1 110-2 11C 1 109-2 09-1

\ 107-ga 1071 N Grand Ridge Rd. ! 1! ~-

0 0.2 0.4 0.6 0.8 1.0 Miles If N* O 0.4 0.8 1.2 1.6 2.0 Kilometers L

LA SALLE COUNTY STATION FIGURE 8.4-2 INNER RING TLD LOCATIONS CEA# m

REVISION 12 MAY 1986 0

L-ta e i

L-17 e l 80 Ottawa e

I-31 Marseilles U.S.6 Illino ,,

L-2s Seneca L-35 L-23 f0 e -29 L-32

?.-21 Rt.23 7

e L-15 L 34 e L 24 I

. LSL Station Rt.170 2

e l L-1s Ransom L-30e b

0 5 Miles LA SALLE COUNTY STATION 0 2 4 6 8 10 Kilometers f FIGURE 8.4-3 INGESTION AND WATERBORNE EXPOSURE eu.3 PATHWAY SAMPLE LOCATIONS C4 85 M9

[

M N C:mmcnw2:lth Edissn 2

- ~.., ) RuralRoute #1, Box 220LaSalle County Nuclear Station

v' Marseilles, Illinois 61341
7- .\ Telephone 815/357-6761

/

July 10, 1986 l

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 for the period June 1, 1986 through June 30, 1986.

Very truly yours, 4.

G. J. Diederich Station Manager LaSalle County Station GJD/JPP/jdp Enclosure xc: J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center L. J. Anastasia, PIP Coordinator SNED J. E. Ellis, GE Resident H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle Document 0043r/0005r 1

Commonwe:lth Edison

_ LaSalle CoJnty Nuclear Station

/

f . _ - . .-

Rural Routs c1, Box 220 Marseiller, Illinois 61341 Telephone 815/357-6761 July 10, 1986 Director, Office of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Dccument Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for the period June 1, 1986 through June 30, 1986.

Very truly yours,

. N G. J. Diederich Station Manager LaSalle County Station GJD/JPP/jdp Enclosure xc: J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclasr Safety D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center L. J. Anastasia, PIP Coordinator SNED J. E. Ellis, GE Resident H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle

~

Document 0043r/0005r l .

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