ML20042G931
| ML20042G931 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/30/1990 |
| From: | Diederich G, Thunstedt J COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9005160303 | |
| Download: ML20042G931 (38) | |
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Commonwoolth Edison -
. LaSalle County Nuclear Station RuralRoute af, Box 220 Marseillos, Illinois 61341 Telephone 815/357-6761 May 10, 1990 Director'of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail Station F1-137 Washington, D.C. 20555 ATIN: Document Control Desk Gentloen Enclosed.for your information is the monthly performance report covering LaSalle County Nuclear Power Station for April, 1990.
Very truly yours, ;
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G . Diederich ['
dtation Manager.
LaSalle County Station ;
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GD T/crh 1 l Enclosure !
xc A. B. Davis, NRC, Region III i NRC Resident Inspector LaSalle i Ill . Dept.. of Nuclear Safety i
( R. Pulsifer, NRR Project Manager ,
D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center '
D. R. Eggett, NED !
J. E. Kuskey, GE Resident I T. J. Kovach, Manager of Nuclear Licensing W. F. Naughton, Nuclear Tuel Services Manager :
C. P. Dillon, Senior Financial Coordinator, LaSalle Terry Novotney.,INPO Coordinator, LaSalle Station T. A. Hammerich, Regulatory Assurance Supervisor J. N. Gieseker, Technical Staff Supervisor l g Central File l l
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LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT APRIL 1990-COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPP-11 ZCADTS/5 i
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a n e TABLE OF CONTENTS (UNIT 1)
- 1. INTRODUCTION II. REPORT '
A.
SUMMARY
OF OPERATING EXPERIENCE B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE
- 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. Corrective Maintenance of Safety-Relhted 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. Main Steam 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 1.
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- 1. -INTRODUCTION (Unit'1) j t The LaSalle County Nuclear Power Station is a two-unit f acility owned by !
Commonwealth Edison Company and located near Marsellies, Illinois. Each_ l unit is a Boiling Water Reactor with a designed net electrical output of. i 1078 Negawatts. Waste heat is rejected to a man-made. cooling pond using. ,
the Illinois River for make-up and blowdown. The architect-engineer was "l Sargent and Lundy and the primary construction contractor was j Commonwealth Edison Company. !
'i Unit One was issued operating-license number NPF-11 on' April 17, 1982.-
j 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.-
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!!. MONTHLY REPORT ,
A.
SUMMARY
OT OPERATING EXPERIENCE (Unit 1) ,
DAJ Ilms Event 1 0000 Reactor critical, generator on-line at 2216 MWT.
1300 Increased power to 3095 MWT.
2300 Reduced load to 1946 MWT for TDRTP repairs and rod-set.
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2 0600 Increased power to 3010 MWT.
3 1200 Reduced load to 2765 MWT to return TDRTP to service.
4 0100 Returned to full power.
10 0130 Reduced load to 3063 MWT for CRD exercising.
1000 Returned to full power.
11 0300 Reduced load to 1765 MWT for Main-Turbine Stop Valve work. ,
1600 Returned to full power. -
17 0130 Reduced load to 3144 MWT for CRD exercising. l 1000 Returned to full power.
24 0030 Reduced load to 2927 MWT for CRD exercising. 1 1000 Returned to. full power. '
30 2350 Reduced load to 3113 MWT for CRD exercising. ,
2400 Reactor critical, generator on-line at 3113 MWT.
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s <'e B.' PLANT OR PROCEDURE CHAN!ES, TESTS, EXPERIMENTS AND SAFETY RELATED ,
MAINTENANCE.(Unit 1)
- 1. Amendments to the racility License or Technical Specification.
(None) ,;
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- 2. Changes to procedures which are described in the Safety. j Analysls Report. .
- a. LaSalle Special Procedure LLP-90-032/ " Manipulation of the -
Reactor Recirc A/B Loor 's Flow Control Valve without LVDT
[
reedback". This procedure outlines the steps'necessary to control Unit 1 Loop B RR TCV without LVDT Teodback due to the position feedback signal becoming unstable and the ;
drywell inaccessible for troubleshooting.
- 3. Tests and Experiments not described in the Safety Analysis j Report.
(None)
- 4. Major corrective maintenance to Safety-Related Equipment, including any SOR switch failure reports. .i (None, See attached page for SOR-switch report)~
- 5. Complotto Safety-Related Modifications. J (See Table 2) k e
C. LICENSEE EVENT REPORTS (Unit 1) i LEILNumb.etr DAtt Description i
(None) r D. DATA TABULATICHS (Unit 1)
- 1. Operating Data Report (attached) .
- 2. Average Dally Unit Power Level (attached)
- 3. Unit Shutdowns and power Reductions (attached) .)
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A SOR do Switch Failure Data Sheet Equipment Piece Numbert,1E31-N012AA' Model Numbers.103AS-B203-NX-JJTTX6
,. - Serial Number: 88-6-123
- Applications- RHR Shutdown Coolina Hiah Suetion Flow Isolation Switch Date and~ Time of Discovery
- ; 03/30/90 EL2Q hours
. Reactor Modes Defueled Power' Levels- _QL_
Calibration Tolerance: 167. 4 ' - Litci 'WC < -
- Nominal Setpoints 168.4 'WC Action Limits
- <lilcQ or;>173.8WC Reject Limits:' (156. 8 or- >120,_Q M WC .
Technical Specification Limit IB6.0WC
'As Found Setpoints LE? Q *WC Date and Time of Return to Services .03/31/90 Q1QQ hours Model Number of Replacement Switch ; LQ1&S-B203-NX-JJTTX6' Serial Number of Replacement;Svitcht '87-12-605R' Cause Instrument setooint drift.
Corrective Actiont Replaced switch. ' Inspected failed switch with nothina abnormal'found.
DVR Number: 1-1-90-035 E
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B;5- TABLE 2;(Unit 1)-
COMPLETED SAFETY-RELATED NODIFICATIONS'
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NUMBER DESCRIPTION M01-1-82-120 Human' rectors to relocate control switches, Indicating lights,-
'Andicators'and recorders on IPM03J per Detailed Control Room-Design-Review (DCRDR).,
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< Wii LAGALLE ONE
~ MTE tur 10, 1990 -
COMPLETD 1:Y J.W,' TWJNSIDI TELEPHONE (015) 357-6T61 u . OFIF.AllilG S1 Aiut,
- 8 ' P& ORT.1NG FER100: AFRIL1990> GROSS HOURS IN REPORTING PERIODi 719
, < 2.' CWREN1LY AUTHOR!ID POWik LEVEL (Mt):
- 3,323, MAX LEFtND CAPAClif (MWt-Net)1- ., i ,h36'
' K SIGN ELECTRICAL RATING ( R -Nyt) _t.070
- 3. POWEk LOTL TO WICH REBlRICID (IF ANY)' (flue. Net)i (Nord) ,
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? 4. REASDRS FOR RESTRIC110N IIF ANY)b L(N/A) ,
REPORilK FERIOD NTA .
, . THIS HONTH YEAR 10-DATE ,-CUMULATIVE'
- 5.EilnE REACTOR CR!i! CAL (HOUR $) 1 719.0 2,708 5 ; 34,042.1?
- 6. ilnE REACTOR RESERVE SHU100W (HOURS) ' O.0 : , 0.0 L 1,641.2
- 7. TIME GENERATDR DN-LINE (HOURS) -719.0- -2,581.1 33,999.4
, r 8,11hl CLNERA10R FEGERVE SHU1DOW (HOURS) ' O.0 - 0.0 i /1.0
- 9. THCANN. ENDGY GENERATO (MWi-Gross) 2,333,0" l8,059,305.4 95,892,873.4 10.ELEC1RICALENERGYGENERATED(NWHe-Gross); B64,696= -2,756,0T6 -31,824,617 li.ELECTRICALENENGYGENERATED(NHe-Net) '782,037. 2,666,459. 30,399,161-
-12.'FEACTOR SERVICE FACTOR (%) Lt00.0 94.1 . - 62.8 ;
- 13. REACTOR AVAILABILITY FACTOR (1) ~ 160.0' 94d 65.7 ' -
- 14. $ERVICE FACTOR (1) 100.0 89.7 61.2 "
- 15.AVAILlBIllifFACT0lt(1) 100.0= 89.7 '61.2
!16. CAI ACITY FACIDR (USING MDC) (%) 105.0 { O 89.4 ' : 52.9 :
,(7. CI#ActiY FACTOR (USING ESIGN m ) (1) 100.9 , 85.9 50.8 t 10. F0GCD OUTAGE FACTOR (1) 9.ti 4.8 . 9.8
- 19. SHultGNS SCHEDULD DVER THE NEXT 6 MONTHS (TYFE, DATE, AND DURATION OF EACH):
(None)
- 20. IF 5HU1DOW A1 END OF REPORT FERIOD, ESilhAfD MIE OF S1ARTUF1 (N/A).
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!.. ? AVELA0t l'AILY UN!1 f'0WER LEVEL (hWe-l.et) !> ATE kn te, 1996 E0KPLETED FY J.W. THUN$TELT 1ELEFiONE (015) 357-6761 REftR1 ffRIOD: AFRll 1996 IAY F0WER LAY l'0WER i 903 17 1,102 2 952 10 1,112 3 1,024 19 1,105 4 i,115 26 1,104 5 1,115 ' 26 1,104 6 1,109 22 1,101 7 1,109 23 1,690 B 1,ilt 24 1,078 9 1.110 25 1,109 10 1,086 26 1,108 11 948 27 t ,166 12 1,111 28 1,108 13 1.111 29 1,100 14 1,113 30 1,105 15 1,112 31 16 1,113
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D.3 UNIT SHUTDOMIS AND POWER REDUCTIGTS > 20%
(Unit 1)
NOTE: This page identifies corrections to previously issued 1990 reports, revised information is indicated by an *.
METHOD OF YEARLY TYPE Se:uAAING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE SEQUENTIAL NUMBER DATE S: SCHEDULED (EOURS) REASON REDUCING PCWER ACTIONS /ColmEh"r5 2 12 S 6* B 1 Turbine Trip Testing l
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'E. UNIQUE REPORTING REQUIREMENTS (Unit 1)
'1. ' Safety / Relief valve operations i
VALVES NO & TYPE PLANT DESCRIPTION q j DAIK AC.TLIATED ACILIATIM COHu1112 OLEY.ENT !
i (None)
- 2. ECCS System Outages QUTAGLHQ2 EQUIPMENT PURPOSE (Notes the year and unit numbers have been ommitted from the Outage Number) ;
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102 ODGOBCs Repair 235 X/Y ;
103 ODG01P Lift leads 107 ODG01P Roland leads (clear TSC 2-381-90) 109 ODG01K Add alarms I i
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189 1E31-N012AA(RH) (Administrative) per Tech Spec 3.3.2 191 1DG01P Lubricate coupling. .[
212 IB D/G Repair. Duplex Strainer Gauge
- 3. Changes to the Off-Site Dose Calculation Manual-(None).
- 4. Major changes to Radioactive Waste Treatment Systems.
- i. (See attached report) .
- 5. Indications of railed fuel Elements. l (None) f s
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- 19CFR56-59 Safety R: view for LAP-266-6, R;v.0' 4
Tech Spac 6.9 MAJOR CHANGES TO RAD 10 ACTIVE' WASTE IREATMENT SYSTEMS lap-200-6 Revision 5, La Salle County Station process Control program will be reviewed and accepted by LaSalle Station's Onsite Review and Investigative Function prior to implementation..
6.9.1.a.1 A copy of this review will be included in the Monthly Operating report to the Commission. This document-provides sufficient information to verify that the change was made in accordance with 10CFR50.59.
6.9.1.a.2 A copy of this review, and the is'eR50.59 review from LAP-200-6 rev 5 (LBCS process Control program) will be included in the_ Monthly Operating Report to the Commission. . These documents provide sufficient information1to verify the rational for the change.
6.9.1.a.3 LAP-200-6 provides a description of the LSCS Solid.
Radweste System and the waste streams. It provides administrative control over'the processing of the waste at LaSalle Station.
. 6.9.1.a.4 There are no anticipated. new gaseous releases due to this administrative changes. There.are no anticipated new liquid releases due to this changes. The license application and amendments did not predict any LOMI 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.
6.9.1.a.6 There are no anticipated radioactive liquid effluents. There are so anticipated _ radioactive i gaseous effluents.
6.9.1.a.7 The exposure to to plant personnel . will not change.
6.9.1.a.8 The procedure change will be onsite' reviewed and-approved by the Onsite Review and Investigative Function prior to_ implementation.
- 6. 9.1. b This change becomes' effective after approval of lap-200-6 Revision 5-(LSCS process Control program), and is complimentary to OSR 89-038, (Tech Specs Revision onsite review).-
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LAP-1200-13
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- Dee:taber 10, 1789 10 ATTACHMENT B Safety Evaluation Form +
Station: LaSalle Unit: 2 System: Wr OSR No: -
It:m To Be Evaluated ( )UFSAR ( ) Technical Specifications ( ) Modification (X) Procedure ( ) Test or Experirnent ( )Ternporary System Change ( )0ther It:m identification Nurnber LAP-200-6 Rev 5
Title:
LA SALLE CQUNTY Station PROCESS CONTROL PROGRAM
- 1. The Change ..
- a. Description of the Change: ffe attached
- b. purpose of the Change Jft_ttjfched
- 2. Answer each of the following questions. If the answer to question 2.a. is "No", then ,)ustify the "No" answer below (thereby, completing this form)
- a. Is this a change to the facility or its operation as described in the Safety Analysis Report (UFSAR), or a test or experiment? Yes ( ) No (X)
- b. Is this a change to the Technical Specifications incorporated in the Operating License? Yes ( ) No (X)
Uf54R is been ehenned to revise the description of the evaporator wastes.
An addition that the solid redweste system is controlled by the PCP is i ncl uded. AIR Number:373-300-89-RW107
- 3. If the answer to question 2.a. above is "Yes", initiate an AIR and answer each of the following cuestions "Yes" or "No" and ,)ustify each answers
- a. Is the probability of an occurrence or the consequence of an accident, or malfunction of equipment important to safety, as previously evaluated in the Safety Analysis Report (UFSAR), increased? Yes ( ) No (X)
Radweste system is not a concern for a safe snutdv of the clart. The channes concerned with LOSR-89-038. the definition of Process Control Procram in the Tech Goees will chance, the operabilJ ty and surveillance
_reggiremgnts for the Solid Radweste System have been cooled from the Tech
_SpeE.s_tt_Lh.R..PCP, P_Qp angjESAR ere be6Mevised to ensure no waste li.Pt9Re.1Etalhf.tuAh t,the_ Stock System as st able waste. only unstable waste ..
Untjl NRC review of_S12qk'g_Roical Repet is re-imolemented. PCP revisions
..p re conjservativpn end y civina more ouidelines for review, they do not
. affect _pperatJ9ns.
- b. Is the possibility for an accident or malfunction of a dif ferent type than any previously evaluated in the Safety Analysis Report (UFSAR) created? Yes ( ) No (X) i The oossibilities for accidents / malfunctions causec ov vendor eautoment are the same as W M he ones addressed for the C4dwaste systems.
These chances to.the LAP (administrative chances) will not affect acttLgl _
operations. but af feet the station's administrative control on waste processina.
- c. Is the margin of safety, as defined in the basis for any Technical Specification, reduced? Yes ( ) No (X'
_On section 3.11.3 of the Technical Specifications vendor orocessino for solidification is addressed and allowed. No chances to the safe operatio n of the plant are created by these procedure chance.
- 4. I f the answer to question 2. b. is "Yes", then proceed by complying with procedure LAP 1200-12q0peratingLicense/TechnicalSpecificationChanges.
Prepared By: . A&M fM Date: 03-26-90 l Approved By: Date: V -Y -90 o Reference - LAP-120L 3 I
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,r#50-59 Saf;ty R3 view for LAP-EBe-6, Rev 5 4
LAP-1260-13 Att B, Question 2.at is this a change to the facility or its operation as described in the Safety Analysis Report (UFSAR), or a test or experiment? No This procedure change does not af fect the f acility or its operation as describe in UFSAR Section 11.4, Solid Weste Management System. This section does not specifically state whether waste is processed to be stable or unstable, nor which waste by vendor streams are processed by the Stock system and which are processed equipment.
The AIR to change the PCP and UFSAR was originated due to the corporate assessment. The UFSAR description of a couple of the waste streams is been revised to reflect actual operations.. A sentence has been added to the FSAR stating that solid redweste processing is controlled by the PCP.
In addition a statement has been added in accordance with Branch Technical Position Paper ETSB 11-3 stating " Regulatory Guide 1.143, Seismic criteria for Structures housing Solid Waste Systems are not applicable to Portable Solid Waste Systems. "
LAP-1200-13 Att B, Question 2.bl is this a change License? No to the Technical Specifications incorporated in the Operating The definition for PCP has been changed as discussed before. Sections 3/4 11.3, 3/4 11.3.1 and 3/4 11.3.2 have been copied in Attachment B of this LAP.
Tech Spec Administrative Controls are discussed below.
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18CFR56-59 Safoty Review fer LAP-206-6, Rev 5 LAP-820-2 Att F, Question 1 & lap-1200-13 Att B, Question 1.a; Describe the Changes The Process Control program Definition for LSCS will be changed in accordance with NRC Generic Letter 89-01, and Revision in progress to the Tech Specs, On-site Review 89-038. This new definition is more complete and conservative, therefore it does not change the present Tech Spee definition, it enhances it.
New referenced documents, letters, burial site licenses, procedures which implement and affect the program, or that were utilized to changed this procedure have been added to the References Section.
The limitations and actions have been changed due to format changes in the body of the procedure. The definition of pCp changes has been added, the limitations to PCP changes and the actions to be taken when PCp changes occur are listed. New limitations identified the documentation and records to be kept necessary to change the PCp. Limitations are given on vendor procedures control. Limitations to deviation on vendor procedures which implement the PCP are also listed. A limitation has been added to ensure the PCp complies with 10CFR20 and 10CFR61. It establishes a limitation to ensure lap-190-16 Att. S is performed in concurrence with waste processing by vendors. Limitations on the operability of the Bolid Radwaste System and Surveillance Requirements are transferred from the Tech Specs to this procedure. Limitations on the location and minimum requirements for use of portable Systems as established per reference B.11 are given.
Cosmetic changes to the procedure section of this procedure have been implemented. Definitions to the most important terms used throughout the program are defined. The revised scope of the program, and the revised description of the Solid Radwaste Handling System are given.
The LSCS Solid Radwaste System feecs include all the minor feeds and their description. The description of the major feeds have been changed in f accordance to operating changes that have occurred (i.e. new resins used, etc).
The description of the Stock system and formulas has been changed to reflect actual approved use, ,
Administrative controls to vendor procedures, formula developments, and waste processing have been formalized. The batch definitions for the different streams have been expanded. The control of process parameters that affect solidification has been expanded to include the control of vendor parameters.
Shipment control has been expanded to include LAP-100-16 as a reference, step reflection encapsulation of cartridge filters prior to shipping has been deleted. The Stock system can only be used to process the major waste streams as Unstable Waste.
Limiting conditions for operations, and surveillance requirements for the solid )
Radwaste System are included. The number of procedure which implement the PCp i has been expanded. The new Attachment E is an outline of the LSCS controls on vendor procedures. A typo on the minimum run mixing times has been changed.
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l'0CFR50-59 SafGty R; view fcr LCP-200-6, R;v 5 LAP-820-2 Att F, Guestion 2 & LAP-1200-13 Att B, Question 1.bl i Purpose of the Changes
- 1. To implement a new format to the Process Control Program, which will be easier to follow, understand, and maintain. Due to the large number of regulations which control Radweste Processing and shipment, it is necessary (and required) to have a more user friendly Process Control Program which ensures that these regulation are implemented.
- 2. To revise the definition and the scope of the Process Control Program at the Station due to NRC Generic Letter 89-01, and On-Site review of ,
Technical Specification Changes LOSR-89-038. These new definition and }
scope are more conservative, specific, and increase control of Radioactive .
Waste Management at the Station. The program under revision includes {
f i requirements for vendor control on formula development, procedures, and processing. The new definition includes compliance with regulations for F
shipment.
- 3. The general purpose of the procedure did not change. New references that were utilited for doing the revision are included, references that
, implement, regulate, limit, supplement or give guidelines for the program ;
are included. The addition of these references will help ensure that revisions to these references are reviewed and compared with the existing program. These comparison will help maintain the PCP current with the
- State, Federal and any other relevant regulation, t
4 Limitations and actions have been added to describe changes to the PCP, !
the requirements, specifications, documentation, and reporting actions .
that have to be met in accordance with Corporate Guidelines and LaSalle t Station's PCP for implementation of the changes.
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- 5. Limitations and actions have been added to ensure vendor procedures for .
waste processing are on-site reviewed prior to implementation. These will I ensure that any changes to any vendor processing parameters which affect the final waste product! therefore, affect the PCP are reviewed, and proper steps to implement the changes are taken. :
- 6. A limitation and action to perform Attachment S of LAP-100-16, " Process and Container Checklist" in concurrence with all vendor Solidification and dewatering procedures has been added. This will increase the- station's '
control on vendor's processing.
j' 7. Definitions of several relevant terms which are pertinent to the program l are included. These terms are defined by Tech Specs, UFSAR, and State, Federal or Controlling Regulations.
This will ensure that a conflict of definitions does not occur.
- 8. The description of the Waste Feeds has been expanded to not only include the station's major streams but to include the minor streams which are produced at LSCS. These are either processed or waiting to be processed at LSCS. The addition of these streams allows for a guideline to be given on how to classify these streams, and which options are available for processing.
. l 10CFR50-59 Saf ty Review far lap-200-6, R;v 5 l l
- 9. A definition for Dry Active Waste (DAW) is included due to the new scope I of the program. processing of Radioactive Waste is controlled by lap-900-25, which supplements this procedure.
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- 10. A definition for waste oil is included, due to the new scope. Currently waste oil is being deconned by vendors with approved Special procedures. .
The option is being lef t open for the processing of waste oil by the i station or vendor, as long as procedures are on-site reviewed, due to the -
l rapidly evolving waste oil processing industry.
- 11. A Definition of chelated waste is included. The Station has performed ;
three Chemical Decontaminations during L1R02, L2R02, and L1R03. Chelated waste will be process by vendors and will meet necessary burial site criteria.
- 12. Due to the discontinuance of the NRC review of the Stock equipment Company Topical report (stable waste) as of the last quarter of 1988, LaSalle ,
waste streams are not processed as stable waste by The Stock Equipment.
Further testing, documentation and a new Topical report submittal to the
- l NRC by Stock is required prior to ever using the Stock Equipment for Stable waste.
- 13. The definition of a batch for the ma,}or waste streams has been expanded.
Currently the waste is transferred to the vendor's liner / HIC, when the amount of waste to be processed has been transferred, a sample is taken and this becomes the batch. This definition has been included for the !
dif ferent waste streams. The conditions are different than for the Tank '
being the batch.
- 14. References to the Decant Tanks for transferring and processing of the waste by vendors have been delet9d due to the valve manifold added to the Dpus with M-1-0-87-006, which allows bypassing of the tanks.
- 15. Due to the Tech Spec Changes, under review under LOSR-89-038, Attachment B and C have been created. Attachment B copies the conditions for Operations of the Solid Radwaste System from the Tech Specs to the PCp.
Attachment C copies the Solid Radwaste System Surveillance requirements to meet the controlling conditions that shall. be taken from the Tech specs to the pCp.
- 15. Several procedures have been added to the LSCS list of procedures which implement the program. These procedures help to comply with the expanded pCp scope. Any changes to this procedures need to be reviewed and ecmpared to the pCp in compliance with limitations and actions of this procedure. If the program is changed then the steps necessary to document this program changes should be performed.
- 16. A new Attachment E is implemented to establish administrative control guidelines on vendor procedures which implement the program. Limitations and actions shall be followed when reviewing these procedures.
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- LABALLE' NUCLEAR POWER STATION il .,
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UNIT 2 MONTHLY PERFORMANCE REPORTL.
i APRIL, 1990-
. COMMONWEALTH: EDISON COMPANY
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-s NRC DOCNET NO. : 050'-374I 4 4~^ LICENSE NO.:NPF-18 4.: ,
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TABLE OF CONTENTS
'(Unit 2)
- 1. INTRODUCTION II. REPORT A.
SUMMARY
OF OPERATING EXPERIENCE -
B. PLANT' OR PROCEDURE' CHANGES, TESTS, ' EXPERIMENTS,' AND SATETY RELATED MAINTENANCE
- 1. -Amendments to racility License or Technical Specifications
- 2. . Changes;to procedures which are described.in the Safety; Analysis Report.
- 3. Tests and Emperiments 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 'Jnit Power Level
- 3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS
- 1. Safety /Rellef Valve Operations
- 2. ECCS System Outuges
- 3. Off-Site Dose Calculation Manual Changes-
- 4. Major Changes to Radioactive Waste Treatment System
- 5. Indications of ralled Fuel Elements-I a
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il I. INTRODUCTION (Unit 2) ;
.The LaSalle County Nuclear Power Station is a two-unit. facility owned'by' Commonwealth Edison Company and located near Marsellies,LIllinois. Each f 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. < ,
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' Unit Two was issued operating license number NPF-18 on December 16, - l 1983. . Initial criticality.was achieved-on. March 10, 1984 and commercial j power operation was commenced on June. 19, 1984. j
'i This report was compiled by John W. Thunstedt, telephone number' Il (815)357-6761~ extension 2463. j i
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'11. MONTHLY REPORT A.-
SUMMARY
.0F OPERATING EXPERIENCE (Unit'2)
Day Time Event 1 0000 Reactor suberitical, generator off-line,-L2R03 in-progress.
30 2400 Reactor suberitical, generator off-line, L2R03 in; progress.
B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE. (Unit 2)
- 1. Amendments to the Facility License or Technical Specification.
(None)
- 2. Changes to procedures which'are described in the Safety Analysis Report.
(None)-
- 3. Tests and Experiments not described in the Safety Analysis Report.
(None) l 4. Major corrective maintenance to Safety-Related Equipment, including any SOR switch failures.
'(See Table 1)
- 5. - Completed Safety-Related Modifications.
(See Table 2)
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B.4 . TABLE'1-(UQit 2) [
MAJOR'. CORRECTIVE MAINTENANCE.TO' *
- SAFETT-RELATED EQUIPMENT
-NORK REQUEST RESULTS AND EFFECTS-NUMBER COMPONENT CAUSE OF MALFUNCTION Ott SAFE PLANT. OPERATION CORRECTIVE ACTION..
L98075 2E22-P301-CB14 Internal ground on ~ Ground on DIV III,DC Bus Replaced Priming Pusep ,
Priming Pump (No SOR Switch Failures) w-r 5
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B.5 TABLE 2 (Unit.2)
COMPLETED SAFETY-RELATED MODITICATIONS MUMDIR , DISERIPTION M01-2-84-027 Human Factors to relocate the the alarms associated with Cycled Condensate (CY) Storage Tank located on 2PM10J per Detailed Control Room Design Review-(DCRDR),
M01-2-87-007 Install a new " Local-Remote" Transfer switch and a new set of control circuit fuses DG 2A Cooling Water Pump 2DG01P reed Breaker.
M01-2-87-008 Install a new " Local-Remote" Transfer switch and e-new set of control circuit fuses for the ESS Division 1 Teed Breakers.
M01-2-87-009 Install a new " Local-Remote" Transfer switch and a new set of-control circuit fuses for the=ESS Division 2 Feed Breakers.
M01-2-87-010 Install a.new " Local-Remote" Transfer switch and a new set of control circuit fuses for the DG "21." Feed Breakers.
M01-2-87-011 Install a new'" Local-Remote" Transfer switch and a new set of control circuit fuses for the DG "0" Unit 2 Feed Breakers.
M01-2-87-012 Install a new " Local-Remote" Transfer switch and a new set of control circuit fuses for the DG "0" Cooling Water-Pump ODG01P Unit 2 feed Breakers.
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, C. LICENSEE EVENT REPORTS (Unit 2)
- LfdLMW11hn DAtti EuCLiPtion-90-005-00 04/11/90 Inadvertant DIV 1 Isolation due to loss of DC Power to-Isolation Logic..
90-006-00 04/12/90 Inadvertant DIV 1 Group 2 Isolation while transferring 2B RPS Bus to normal.
90-007-00 04/21/90 Partial Group 2 Isolation during RPS.
~
Transfer.
lr D. De TA TABULATIONS (Unit 2)
- 1. Operating Data Report (Attached)
- 2. Average Dai'.y Unit Power Level (Attached) i
- 1. Unit Shutdowns and Power Reductions (Attached)
E. ' UNIQUE REPORTING REQUIREMENTS i i
- 1. Safety / Relief Valve Operations VALVES NO &. TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATIDtiS CONDITION. OF EVENT
-]
(None)
- 2. ECCS System Outages QU.TAGE_HD_t EOUIPMENT PURPOSE 909 2E51-F359(RI) Replace Valve.-
912 ~2B D/G Repair Fuel-Priming Pump.
913 2B D/G Reterminate Priming. Pump Motor.
946 2B D/G (Administrative).. j i
958 LPCS (Administrative). ]
961 RCIC Turbine Repair oil-leak on governor. I l
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D.fl.~~ OPERATING DATA REPORT'
- DOCfET NO. 650-374 ..
J > . UW11.LASALLE TW0i
- DATE May 10,1996b
-COMPLETEDBYJ.W.THUNSTED1
' TELEPHONE (815)*357-6761
.0FERA11NGSTATUSL
' , lp; REPORTING PERIODi april.1990 , 'GROSSHOURSINREPORilNT, PERIOD:- t719-a -- .
f-2. CURREN1LT AUTHDRillD POWER LEVEL (Mt)i 3,323 -
NAX DEFEND CAPACITY UlWe Net): '1,036 Le; W KSIGN ELECTRICAL RATING -(Me-NetI ~1,078 tA l3.1 POWER.L L110 WHICH RESTRICTED (if ANY) (Me-NetN 0' N '
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4.'-REASONS FOR RESTRICTION (IF ANY) d lRefuelingTL2R03)( '
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- REPORTINGPERIODDATAe -
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THIS NONTH. JYEAR-10-DATE? : CUMULATIVE 4
-3. TIME REACTOR CRII! call(HOURBh ' O.0 ' !!764d1 31,911.2 L >
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- 6. 'llhi REACTOR RESERVE SHUlDOWN<(HOURS)' .0.0: 'O.0; li jf t6.9 C. '
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g ' 7. :- TIME GENERATOR ON-LINE (HOURS)-
, t0;0; i,748.7.7 - [3t,431.8} , . '
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-8. TIME GENERATOR RESERVE SilVTDOWN (HOURS)- ' 0.0 ' E0.0: 30;0 "
9, ' THERMAL ENERGY GENERATED (MHi-Gross) 10- '5,586,967.2: ~91,907,015.2 ~
- 10. ELECTRICAL ENERGY GENERATED ( MHe-Gross). 0- '1,99?;842V l30,350,768:
-11. ELECTRICAL ENERGY GENERATED (MWHe-Net)' 4 ,0811 1,829,917h 29,065,222d E, ~
12.REACTORSERVICEFACTOR(%L " 0.0: . , 31.3) 65.B i <
- 13. REACTOR AVAILABIllif FACTOR-(2) O.0 ' k 61.3 . 69.3
- 14. SERVICE FACTOR (%) 0.0 60.7 ~64.6
- 15. AVAILIBILITY FACTOR (2) 0.0 ~ !64.7 k4.BI I
- 16. CAPACITY FACTOR-(USING hi,C)-(%)
-i.lf 61.~4 ' :57.8 17.CAPACITfFACIOR(USINGDESIGNMWe)(1) -1.0 $?M -- 55dI [
Ei8.' FORCED OUTAGE FACTOR (I)- 0.0 2.9 . ' ' L15.7 l
7' _
' l 19.'SHUIDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYFE, DATE, AND DURA 110N OF EACH):
I Continue L2R03 120.'!F. SHUTDOWN AT END OF REPORT FERIOD, ESTIMATED DATE OF STARTUP:
June 09,1990 l
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- 2 D.3 UNIT SHUTDOWNS AND PCHER REDUCTIONS'>20%-- .
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- p NOTE:- This page' identifies corrections..to previously issued 1990 reports 7 revised.information.is indicated hy an *.; cg .
~ ' METHOD OF:
iEARLY TYPE- ' SHUTTING-DOWN
- SEQUENTIAL F: FORCED- DURATION THE. REACTOR OR- CORRECTIVE-
+
- NITMBER ' DATE - S:' SCHEDULED (HOURS) REASON CODE 1 REDUCING POWER ACTIONS /CQetENTS 1 3-3-90 .S 0.0 . B/ F -- '5* - -CRD' Exercising and-
- system load.
2 3-19-90 S 0.0 F- 5* " System Load., V
.3 24-90 S 0 . 0 -. 'F '5*' System; Load.
-6 3-17-90 S: 359.5*. C. '1* -L2R03.
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l0.'- eL ;QUIAGE_liOi - EQUlI2iENT PJIRPOSE
, c967: 2DG011 - Porfora EQ insp;ctitn. i 985; 2E12-F072D(RH) - Repair'.-
987 LPCS Perform LES-LP-201. i 1006. 2E12-F020(RH) (Administrative).
1007 2E12-F041C(RH) Repair Solenoids.
1012 2E51-F022(RI) Perform LES-GM-130.
1013 2E51-F019(RI)- Perform LES-GM-130.
1014 2E51-F031(RI) Perform LES-GM-130.
1015 2E51-f069(RI)' Perform LES-GM-130.- f 1016 2E51-F068(RI) Perform LES-GM-130.
1017 2E12-F097(RH) Remove Wire from Spare Fuso.
1020 DIV-I'ECCS SOR's Replace SOR's.
1021 DIV I ECCS Logic Insta11'DIV I SOR Modification.
1022 DIV I Logic Install,DIV I SOR Modificatloa.
1030 2VYO4C Clean Cooling Coll.
1031 2DG036 Inspect.
1032 LPCS Pump Perform LES-GM-229.
1035 2A D/G Perform post-maintenance hot-adjustments.-
1039 2DG01P Trouble-shoot. Control Circuit.
1040 2A D/G ' Repair Air-Start Solenoids.-
1042 2A D/G Cooler Repair. leak.
1043 2DG035 Repair Position-indicator. ,
1047 2A RHR Pump (Various).
1048 2E12-F084A(RH) Inspect Valve.
1049 2E12-F084A(RH) Inspect Valve.
1050 2E12-F041A(RE) Repair Binding.
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$ M QQTAGE_HQt EOUIPM]2{I: PURPOSE
. 1000 1E12-F040 Logic (RH) ~Inrp;ct HFA R;1cy 2B21H-K60.
1081 2E12-F006A- -(Administrative).
l 1082 2B RHR Fill / Vent Seal Cooler.
1089 2B RHR HK Clean Vent Line..
Service Water 1095 ODG01P Repair U-2 Feeder Breaker.
1097 2B D/G Repair Air-Leak.
1100 OD/G Install Human-Factors Modification. i 1167 RCIC Repair:2E51-F008, 2E51-F091.
1176 2E12-F090A(RH) Repack Valve.
1177 2DG08CB Repair Gasket.
s 1180 2DG035 Repack Valve.
- 1182 2E12-F068A(RH) Repack Valve. 3 1190 2E21-F051(LP) Adjust Packing.
1191 2E12-C002B(RH) Repair Seal-Cooler Leak.
1192 2E12-C300B Repair Seal-Cooler Leak.
1193 0 D/G -(Administrative),
1197 0 D/G ( A&ninistrative ) . '
I 1208 2B33-F067A(RH) Perform Hydrostatic Test. ,
I 1209 2B33-F067A(RH) Perform Hydrostatic Test.
1210 '2E12-F092B & C (Administrative).
1216 2B D/G Replace Run-Solenoid.
1219 2A D/G Inspect Turbo Charger.
- 3. Changes to the Off-Site Dose Calculation Manual. '.
(None).
- 4. Major changes to Radioactive Waste Treatment Syg*, ems'. l (See attached report) c t
- 5. Indications of Failed Fuel Elements. '
(None) l-I ZCADTS/7
I s' 4' 4 10CFR50-59 Safcty Rsvicw for lap-200-6, R3v S l -
'i Tech Spec 6.9 MAJOR CHANGCS TO RADIDACTIVE WASTE TREATMENT SYSTEMS lap-200-6 Revision 5, La Salle County Station process Control program will be roviewed and accepted by LaSalle Station',s Onsite Review and Investigative Function prior to implementation.'
6.9.1.a.1 A copy of this review will be included in the Monthly Operating report to the Commission. This document provides sufficient information to verify that the change was made in accordance with 10CFRSO.59. ,
'I 6.9.1.a.2 A copy ef tnis review, and the 10CFR50.59 review from LAP-200-6 rev 5 (LSCS process Control program) 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 lap-200-6 provides a description of the LSCS Solid Radwaste System and the waste streams. It provides .
. administrative control over the processing of the waste at LaSalle Station.
6.9.1.a.4 There are no anticipated new gaseous releases due to this administrative changes. There are no anticipated new liquid releases due to this changes. The license application and amendments did ,
not predict any LOMI wastes. l 6.9.1.a.5 The expected maximum exposure to an individual in the i unrestricted area, and to the general population, will not change, j l
6.9.1.a.6 There are no anticipated radioactive liquid effluents. .There are no anticipated radioactive !
gaseous effluents. 1 6.9.1.a.7 The exposure to to plant personnel will not change.
6.9.1.a.8 The procedure change will be onsite reviewed and i approved by the Onsite Review and Investigative Function prior to implementation.
6.9.1.b This. change becomes effective after approval of lap-200-6 Revision 5 (LSCS process Control program), and is complimentary to OSR 89-038, (Tech Specs Revision-onsite review).
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LAP-1200-13
""""~- R3violon 2
- D;esmb2r 1S, 1989 10 r
ATTACHMENT B Safety Evaluation Form +
Station LaSalle Unit 2 System: WY OSR No -
Itcm To Be Evaluated ( )UFSAR ( ) Technical-Specifications ( ) Modification (X) procedure ( ) Test or Experiment ( ) Temporary System Change ( )0ther itGm Identification Number LAP-200-6 Rev: 5
.Titlo! kP SQLLE COUNTV Station DROCESS CONTROL DROGRQM
- 1. The Change
- e. Description of the Change: See attached
- b. Purpose of the Change!._See__ attached
- 2. Answer each of the following Questions. If the answer to question 2.a. is "No", then Justify the "No" answer below (thereby, completing this form):-
- 4. Is this a change to the facility or its operation as described in the Safety Analysis Report (UFSAR), or a test or experiment' Yes ( ) No (X).
- b. Is this a change to the Technical Specifications incorporated in the 10perating License? Yes ( ) No (X)
UfSAR is been chanaed to revise th, description of the evaporator wastes.
An addition that the solid radwaf - System is controlled by the PCP is i ncluded. AIR Number:373-360-89-RW107
- 3. If the answer to question '2. a. above is "Yes". Initiate an AIR and answer each of the fn1' lowing questions "Yes" or "No" and justify each answers
- a. Is the probability of an occurrence or the consequence of an accident, or malfunction of equipment import ant to safety, as previously evaluated in the Safety Analysis Peport (UFSAR), increased? Yes ( ) No (X)
Redwaste system is not a concern for a safe shutd y of the olent. The '
channes concerned with LOSR-89-038, the definition of Process Control Prooram in the Tech Specs will chanae, the~operab:, tv and surveillance reautrements for the Solid Radwaste System have been cooled from the Tech Jpeci e ot the PCp. PCp and UFSAR are bed #evised to ensure no waste
.h E Ac_e_s_51d tbro_u,qh,_th_e. Stock System as stable waste. only unstable' waste until NRC revjeg,of Stock's T Dical Report is re-imdemented.
PCP revisions are consenyat.i_ve2 and are aivina more auidelines fr review, they do not-affect operations.
l, b. Is the possibility for an accident or malfunction cd a different type l
than any previously evaluated in the Safety Analysti Report (UFSAR) created? Yes ( ) No (X)
The oossibilities for accidents / malfunctions causer _Sv vendor eautoment are the same as ;uc' ^!"the ones addressed for the 23dwkste systems.
These chances to the LAP (administrative chances) #
- 11 not affect actual operations. but af fect the station's administrative _ control on waste processina,
- c. Is the margin of safety, as defined in the basis for any Technical Scecification, reduced? Yes ( ) No (X)
-On section 3.11.3 of the Technical Specifications vendor processina for solidification is addressed and allowed. No channes to the safe operation of the plant are created by these procedure chance.
- 4. If'the answer to question 2.b. is "Yes", then proceed by complying with procedure LAP 1200-12e Operating License / Technical Specification Changes.
Prepared By: _
[Ac u. WJ /In Date: 03-26-90 Approved By: ,
(> Date: V - V -90 o R3ference - LAP-1200 3
, * ~. r t *
',r#50-59 SafGty R2vicw for LAP-200-6, R3v 5 LAP-1200-13 Att B, Question 2.a; Is this a change to the facility or its operation as described in the Safety Analysis Report (UFSAR), or a test or experiment? No This procedure change does not affect the facility or its operation as describe in UFSAR Section 11.4, Solid Waste Management System. This section does not epecifically state whether waste is processed to be stable or unstable, nor which waste streams are processed by the Stock system and which are processed by vendor equipment. The AIR to change the PCP and UFSAR was oriBinated due to the corporate assessment. The UFSAR description of a couple of the waste streams is been revised to reflect actual operations.. A sentence has been cdded to the FSAR stating that solid radweste processing is controlled by the PCP. In addition a statement has been added in accordance with Branch '
Technical Position Paper ETSB 11-3 stating " Regulatory Guide 1.143, Seismic criteria for Structures housing Solid Waste Systems are not applicable to Portable Solid Waste Systems. "
i LAP-1200-13 Att B, Question 2.b; 1s this a change to the Technical Specifications incorporated in the Operating License? No 4
The definition for PCP has been changed as discussed before. Sections 3/4 11.3, 3/4 11.3.1 and 3/4 11.3.2 have been copied in Attachment B of this LAP.
Tech Spec Administrative Controls are discussed below.
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18CFR58-59 Safoty R;vicw for LAP-208-6, R3v 5 LAP-820-2 A> F, Guestion 1 & LAP-1200-13 Att B, Question 1.a; Descrios the J.hanges The Process Control Program Definition for LSCS will be changed in accordance with NRC Generic Letter 89-01, and Revision in progress to the Tech Specs, On-site Review 89-038. This new definition is more complete and conservative, therefore it does not change the present Tech Spec definition, it enhances it.
New referenced documents, letters, burial site licenses, procedures which >
implement and affect the program, or that were utilized to changed this ,
procedure have been added to the References Section.
i The limitations and actions have been changed due to format changes in the body of the procedure. The definition of PCP changes has been added, the limitations to PCP changes and the actions to be taken when PCP changes occur cre listed. New limitations identified.the documentation and records to be kept necessary to change the PCP. Limitations are given on vendor procedures control. Limitations to deviation on vendor procedures which implement the PCP are also listed. A limitation has been added to ensure the PCP complies with 10CFR20 and 10CFR61. It establishes a limitation to ensure LAP-100-16 Att. S 4 is performed in concurrence with waste processing by vendors. Limitations on the operability of the Solid Radwaste System and Surveillance Requirements are transferred' from the Tech Specs to this procedure. Limitations on the location i
i and minimum requirements for use of Portable Systems as established per reference B.11 are given.
i Cosmetic changes to the procedure section of this procedure have been imolemented. Definitions to the most important terms used throughout the I program are defined. The revised scope of the program, and the revised description of the-Solid Radwaste Handling System are given.
The LSCS Solid Radwaste System feeds include all the minor feeds and their description. The description of the major feeds have been changed -in accordance to operating-changes that have occurred (i.e. new resins used, etc).
The description of the Stock system and formulas has-been changed to reflect actual approved use.
Administrative controls to vendor procedures, formula developments, and waste processing have been formalized. The batch definitions for the different streams have been expandad. The control of process parameters that affect solidification has been expanded to include the control of vendor parameters.
Shipment control has been expanded to include LAP-100-16 as a reference, step reflection encapsulation of cartridge filters prior to shipping has been deleted. The Stock system can only be used to process the major waste streams j
as Unstable Waste.
l Limiting conditions for operations, and surveillance requirements for the solid-Radwaste System are included. The number of procedure which implement the PCP has been expanded. The new Attachment E is an outline of the LSCS controls on vendor procedures. A typo on the minimum run mixing times has been changed.
, - . , , ,. . , . . . , . .,-er
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l 10CFR50-59 Safoty Ravicw for LAP-200-6, R2v 5 7 . lap-820-2 Att F, Question 2 & lap-1200-13 Att B, Question 1.b; ,
purpose of the Changes To implement a new format to the process Control program,c which will be ,
f
- 1. Due to the large number of easier to follow, understand, and maintain. t regulations which control Radwaste processing and shipment, it is necessary (and required) to have a more user friendly process Control program which ensures that these regulation are implemented.
- 2. To revise the definition and the scope of the process Control program at
- the Station due to NRC Generic Letter 89-01, and On-Site review of Technical Specification Changes LOSR-89-038.. These new definition and '
,' scope are more conservative, specific, and increase control of Radioactive '
Waste Management at the Station. The program under revision includes requirements for vendor control on formula development, procedures, and processing. The new definition includes compliance with regulations for shipment.
- 3. The general purpose of the procedure did not change. New references that F
were utilized for doing the revision are included, references that.
implement, regulate, limit, . supplement or give guidelines for the program are included. The addition of these references will help ensure that revisions to these references are reviewed and compared with ths existing l program. These comparison wi'll help maintain the pCp current with the L State, Federal and any other relevant regulation.
4 Limitations and actions nave been added to describe changes to the pCp, the requirements, specifications, documentation,' and reporting actions that have to be met in accordance with Corporate Guidelines and LaSalle.
f Station's pCp for implementation of the changes, i
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- 5. Limitations and actions have been added to ensure vendor procedures for waste processing are on-site reviewed prior to implementation. These will ensure that any changes to any vendor processing parameters which affect the final waste product; therefore,-affect the pCp are reviewed, and proper steps to implement the changes are taken. ,
- 6. A limitation and action to perform Attachment S of LAP-100-16, " Process and Container Checklist" in concurrence with all vendor Solidification and dewatering procedures has been added. This will increase the station's -
control on vendor's processing.
- 7. Definitions of several relevant terms which are pertinent to the program-are included. These terms are defined by Tech Specs, UFSAR, and State, Federal or Controlling Regulations. This will ensure that a conflict of definitions does not occur.
- 8. The description of the Waste Feeds has been expanded to not only-include the station's major streams but to include the minor streams which are produced at LSCS. These are either processed or waiting to be processed at LSCS. The addition of these streams allows for a guideline to be given.
on how to classify these streams, and which options are available for processing.
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10CFR50-59 Safcty R; view for lap-200-6,-R;v 5 -l r
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- 9. A definition for Dry Active Waste-(DAW) is included due to the new scope of the program. processing of Radioactive Waste is controlled by lap-900-25, which supplements this procedure.
Currently.
, ' l e. A definition for waste oil is included, due to the new scope.
weste oil is being deconned by vendors with approved Special procedures.
)_ The option is 'being lef t open for _ the processing of waste oil by the l
I station or vendor, as long as procedures are on-site reviewed, due to the l rapidly evolving waste oil processing industry.
The Station has performed
- 11. A Definition of chelated waste is included.
three Chemical Decontaminations during L1R02, L2R02, and L1R03. Chelated -
waste will be-process'by vendors and will meet necessary burial site l
criteria.
- 12. Due to the discontinuance of the NRC review of the Stock equipment Company Topical report (stable waste) as of'the last quarter of 1988,- LaSalle r waste streams are not processed as stable waste by The Stock Equipment. i l
Further testing, documentation and a new Topical report -submiital to the l
NRC by Stock is required prior to ever using the Stock Equipasnt. for '
Stable waste.
- 13. The definition of a batch for the major waste streams has been expanded.
Currently the waste is transferred to the vendor's = liner / HIC, when the l amount of waste to be processed has been transferred, a sample _ is taken and this becomes the batch. This definition has.been included for the different waste streams. The conditions are different than for the-Tank being the batch.
+
- 14. References to the Decant Tanks for transferring and processing of the l
waste by vendors have been deleted due to the valve manifold added to the +
Dpus with M-1-0-87-006, which allows bypassing of the tanks.
Due to the Tech Spec Changes, under review- under LOSR-89-038, Attachment B 15.
and C have been created. _ Attachment B copist the conditions for Operations of the Solid Radwaste System from the Tech Specs to the pCp. ,
I Attachment C copies the Solid Radwaste System _ Surveillance requirements to meet the controlling conditions that shall be taken from the Tech specs to the pCp.
- 15. Several procedures ~have been added.to the LSCS list of procedures which implement the program. These procedures help to comply with the expanded PCp-scope. Any changes to this procedures need to be reviewed and compared to the PCp in compliance with limitations and actions of this procedure. If the program is changed then the steps necessary to' document 9 this program changes should be 7erformed.
- 16. A new Attachment E is implemented to establish administrative control guidelines on vendor procedures which implement the program. Limitations and actions shall be followed when reviewing these procedures.- ,
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