ML20059N509
| ML20059N509 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 09/30/1990 |
| From: | Cialkowski M, Diederich G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9010160124 | |
| Download: ML20059N509 (50) | |
Text
e. .;
4- .
.e; '%- Commonwealth Edison :
LaSalle County Nucl:ar Station
!4 Rural Route df, Box 220 Marseilles, Illinois 61341 Telephone 815/357-6761.
l October'10, 1990 ,
.i 1
Director of Nuclear Reactor Regulation ;
United' States Nuclear Regulatory Commission ;
Mail Station P1-137
- Washington, D.C. 20555 j
ATTN Document Control Desk Gentlemen '
Enclosed for your.information is the monthly performance report covering LaSalle County Nuclear Power. Station-for September, 1990. 'l Very truly yours,
'G. J. Diederich o f Station Manager
.LaSalle County Station GJD/MJC/jdp L Enclosure xc A. B.' Davis, NRC, Region III'
!. NRC Resident Inspector LaSalle Ill. T. )t. of Nuclear Safety R. Pu1 Lifer, NRR Project Manager D. P. Galle,. CECO
-D. L. Farrar, CECO INPO Records Center D. R. Eggett, NED J. E. Kuskey, GE' Resident
'r T. J. Kovach, l'unger of Nuclear Lic'ensing W. F. Haughton, Nuclear Fuel Services Manager C. F. Dillon,' Senior' Financial-Coordinator, LaSalle
,- T. R. Novotney, INPO Coordinator,..LaSalle Station
! T. A. Hammerich, Regulatory Assurance Supervisor J. W. Gieseker, Technical Staff' Supervisor Central File'
,4 Co 73 PDC
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LASALLE NUCLEAR POWER STATION UNIT-1 MONTHLY PERFORMANCE REPORT s
SEPTEMBER 1990 L
.1 COMMONWEALTH-EDISON COMPANY
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E o r L .ZCADTS/S
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k II, MONTHLY' REPORT.
, A . --
SUMMARY
.'Of OPERATINGLEKPERIENCE (Unit.1) .
DAY. Ilma RYant l' 0000- Reactor critical, generator on-line:at'1000 MWE. i 3- 0100 Reduced load to 850 MWE for. system load i
1200 Increased power to 1025 MWE-4 0100 Reduced load to 850 MWE for system load 1000 Increased power to 1025 MWE 5 2200 ' Reduced load to 950 MWE for system load power level' held due.to high generator hydrogen temperature. [
?
7 1200 Increased power to 1040 MWE 10 '2200 Reduced load to 960 MWE due to high generator-hydrogen temperature 13 2200 Increased power'to 1006 MWE 16 -0100 Reduced load to 920 MWE for system load-2100 Increased power to 100 MWE ,
17 2330 Reduced load to 900 MWE for CRD exercising 18 2300 Increased power to 1120 MWE 19 2300 Reduced load to 970 MWE for. system, load-20 1000 -Increased power to 1110 MWE-25 0100 Reduced power'to 750 MWE forLCRD exercising 1400 Increased power to'1115 MWE' i
26 0300 Reduced power to 900 MWE for system load 1200 Increased power to 1115 MWE
- l 27 0100 Reduced load to'750 MWE for heater. bay work 1300 Increased power to 1110 MWE i 30 '
2400 Reactor critical, generator on line at 1105 MWE ZCADTS/S I
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, f Bo- PLANT OR PROCEDURE l CHANGESo TESTS, OR EXPERIMENTS (50.59)-(Unit 1)"
' Amendments to the Facility. License or Technical Specification.
'l.
- a. Clarifications of requiremtats for automatic bypassing of-DG trips on an ECCS ar.Luation signal.-
- b. Correct the singleilarge load reject value for.Div-3 diesel generators.
- 2. Changes to procedures which'are described in the Safety .)
Analysis Report.
(None) .
- 3. Changes to facility.which are described in the Safety Analysis, Report.. !
(None).
4 Tests'and Experiments.not described in.the-Safety ~ Analysis -I Report.
(None)
C.- MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT '(including.
SOR differential. pressure switch failure reports). >
(See Table.1)
D.- l COMPLETED SAFETY-RELATED' MODIFICATIONS.
(None) i a'
E. LICENSEE EVENT REPORTS - (Unit 1)
LER Number Date Description (None)
.7
( F. DATA TABULATIONS (Unit 1)~
'i l '. . Operating Data Report (See Table 3)
^\
- 2. Average Daily Unit Power Level (See' Table 4) '
- 3. Unit Shutdowns and Significant~ Power Pe'itc* ions - (See Table 5) -;
1 !
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.ZCADTS/5.
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B.4 TABLE 1 (Unit 1). ..
MAJOR CORRECTIVE MAINTENANCE TO.
SAFETY-RELATED EQUIPMENT WORK REQUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION .ON SAFE. PLANT OPERATION CORRECTIVE ACTION LO1824 CRD Ultrasonic Breaker Line Side None' Replaced breaker Cleaner crimping tabs-missing i.02144 .APRM "C" Reset Switch Improper Indication. Replaced reset switch Upscale Alarm LO2592 LPCS Feed Cracked Contact on None Replaced contact Pump Breaker Feed Pump Breaker (No SOR failures'.this month)
'2CADTS/5.
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- OPERATING DATA R R ORT-
- DOCKET NO.' 050-373; d 1 1
, , 3 UNITLASALLE'ONE:
DALE.0CTOKR io,1990 - N 4
- COMPLEfD BY M1 CIALK0WSKI- , >
i .
- > ;TELEPHDNE-(815)-357-6761.
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10PERAllNGSidiUS' ,
113 :EREPORilNGPERIOD! . SEPTEMBER 1990 GROSS HOURS IN REPORilNG PERIOD:- 17209
, ; 2. ' CURRENTLY _AUTHORI2D POWER LEVELV(nWt): 3,323l .
- MAX
- DEPEND CAPACITY,(MWe-Net):[ _ J 1,034 :
P
- DESIGN ELECTRICAL RATING (MWe-Net)
- ; i,0787 -
.w
^
13/ POWER 1EVElt 10 WHICH RESTRICIED:(IF ANY);(MWe-Netit 0 i(NONEE E.OREASONSFCRRESTRICTION(IfANY)i 4 (N/A); y .. .. . [ .. . -1
^ '
m .
, REPORTING PERIOD DATA ( '.. _
.... f.-
THIS M0WiHt ; YEAR-TO-DATE W4 CUMULAT!YE7 w _
, e >
l6,266;3f,' . ?38,409.4 2 a j
, LL 'REAtl0R CR!ilCADTIMEI(H00RS)
? 72,0.0 . ,
.n a
,, , , . ;--s, Y 4
N 6.' REACTOR RESERVE SHUTDOWN TIME (HOURS) 1 3- (0.0P . 0.0.. 7,641'.'2i
.1 , o
' " r
- 7. CENERATOR ON LikE TIME (HOURS)- t?20.0J ' l6,12t;52
, m;- . ., , , , 337,~539.8, L . ;
i' . +
. wm m
8.i DNii. RESERVE SHVTDOWN TlhE.(HOURS); -
' O. 0 ' ' "7" 31.0%
1 0.0 ~ f +~ ' ,
1M S . -
9 THERMALENERGYGENERATED(MWHt)- 2'262'2t, , h ot.9,195,329.4.. -
4{07,926,897, g
LN
, u, - 4 .: .
m gP6.488, - 2261
- s. ELECTRICAL'ENERGYGENERATED(MWHe-Gross)1 .
- M754,0091, 35,556,747 <
i
.P.. u ..
ikELECTRICALENERGYGENERATED(MWHe-Net): ! .1726,45816 T6,270;515I l-34,003. ,.217
,, , ,1 - -
,;. ' ,,,t- - x-l , ,_ ..? :
J, 12.REACTORSERVICEFACTORs(%) '
s 6100.0 ,' ' 95.7:
7 1 s 264;91;
^
L: ' 13[REACf0R"AVAILAP!LITY FACTOR (%); ,
100!01 s Y95.7.' OL67.7) '
s a - -
3; 1 . -m
.m .
, m1 - , . ;.. ,
,14 UNIT SERVICE FACTOR (%) *
, ; 93.4 ? 1 63.4 i 4100.01
. . . i 13. UNIT AVAILl6ILITT FACTCR 1%) >jl00.0 L - 93.41 L 63.41 1 9, ,
, ,1 -
a W
f $ UNIil CAPACITY FACIDR (USING MDC)f(%) '
' / 97.4): , ' .
92.4.c .
, L 55.5 i L... ,
4 s .m , ,
L ' EIL UNIT CAPACliY FACIDR (USlH'; DESIGN MWe) f%);
1 93.6', . 88.8 ) 53.3:
$* l i,.+>t. - ,.
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'ig 18." UNIT FORCED OUTAGE FACTOR (%) -
fo, * '
' : 0.01; . .
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TABLE 5 1. D.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20% (Unit 1) METHOD OF . CORRECTIVE YEARLY -TYPE . SHUTTING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F: . FORCED DURATION THE REACTOR OR' (LER/DVR I if NUMBER (YYMMDD) S:-SCHEDULED ~ (HOURS) REASON REDUCING POWER. applicable) (None)
SUMMARY
'OF OPERATION:
~
The Unit remained on line.at high power throughout.the month. .Several minor power reductions:were required due to low. grid demand, routine surveillances, and elevated generator' hydrogen temperature.
'ZCADTS/5-~ ..
s_ .
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_ , _ _ - . _ _ . .__a.---. . _ . . _ _ _ _ _ . .
. - , . . . . _ _ _ . - _ _ _ . , . _ _ . . . . ~ _ __ , _ . _ _ _ _ _ . = . . . . .
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~
G. UNIQUE REPORTING REQUIREMENTS'(Unit 1).
- s. ;
- 1. Safety / Relief valve operations VALVES. NO-& TYPE. PLANT DESCRIPTION-DAIE- ACTUATED ACTUATION CONDITION OF EVENT ;
(None)
- 2. ECCS System Outages (See Table 6).
- 3. Changes.to-the OffiSite Dose Calculation' Manual-
-(None) . ,
- 4. Major changes to(Radioactive Waste Treabment Systems.
(See attached Enclosures A'& B)
- 5. Indications.of Failed Fuel Elements. q (None)'
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.1 ZCADTS/5-
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(Unit 1)-
, ,;; T;blo 6-ECCS System Outages Note _The year and unit ~ data has been removed-from the outage number. l 1
QQIAGE NO. EQUIPMENT PURPOSE (U-0) 297 ODGOBCB ' Check hold-down' screws 298- 0 D/G Install locktite handle I Perform surveillance LES-GM-109-
~
299 ODG Cooling Perform surveillance LES-GM-105- -l Water Pump 300 '0DG08CA Check hold-down screws (U-1)
\
435 'lE22-C302A -Repair HPCS:DG air compressor; 437 1E22-C003' Lubricate coupling 438 -1E22-C001 Megger motor h 440 IB D/G. Calibrate Var meter ' $ 451 1E12-F049B - EQ inspection , 452 1E12-F049B Remove and' inspect Limitorque 454 1E22-C302B . Replace; air _ compressor piping;and h
. Install. guards- !!
if
.I 465 1E12-F040A EQ inspection i 466 1E12-F040A ' Remove-~and; rebuild ~Limitorque I
478 1E12-C300A Perform surveillance.LES-GM-105 482 1E51-F022 Perform surve'111ance LES-EQ-112 488 1B21-NO37BB Replaced valve bonnet assembly 501 1E12-F040A- Inspect valve motor l l 1 1 ZCADTS/5 1
~
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.. 0 .
f ATT6cMO4T --A ,
'i Use of Chem-Nuclear to perform-Radwaste processing -i Sept ernber 24, 1990- .
i The.following information is being submitted-in' accordance-with- I Technical Spectfications 6.9 and.6.7.
.6.9.1.a.l'/6.9.1.a.2 '.La Salle Station uses.a' vendor to process and ship the majority of its radioactive waste., .This is~ partly. ;
due to-limitations _in the existing Stock System, and partly due- ! to econornics. After1the Radwaste processing Contract.was- ~ '
' reviewed:by purchasingi the station changed.radwaste processing =
vendors,.from SEG (Westinghouse)-to Chem-Nuclear Syntems.. . Thel changeover shall occur af ter sorne final solidi ficat 3 on work .by'., ; SEG.. During SEG's equipment teardown, the. station will: continue- i to ship barrels, which were. solidified with-the; Stock, System,'. I using l Chem-Nuclear's transpor,t at ion services., Concurrently,- the ,
. Station will be mobilizing Chem-Nuclear's equiprnent, and; ;
performing = the On-Site Review .~of Chem-Nuclear's procecures.- ! Chem-Nuclear will-be mobilized in the same area where SEG was' j locat ed. ' A 10CFR50.59 is, also included to address the safety! ' adequacy of their systems. 6.9.1.a.3 _ . A descript ion of' Chem-Nuclear's solidification equipment, Mobile
~
j Solidification' Service. Description, and 'its interface with7 plant- r systems, is attached., A descript ion of. Chem-Nuclear's : dewatering eq u i ptnent , RDS-1000 (Rapid Dewatering-System) Service, 'and :its ' 3 interface with plant systems,-is attached.. 6.9.1.a.4 > This change will-modify.the waste processing vendor, not the 'jl waste or its final form. Therefore, the releases of radioactive ,
-materials-in.1iquid, gaseous, and solid form should' rernain' the l same as those'previously predicted. ';
I 6.9.1.a 5 This change wi1~1 not modify the waste or 'its: final form.. g Therefore, the expected. maximum exposure toiindividuals irdthe l unrestricted area, and to the general population, should.not differ from those previously estimated. i
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6.9.1.a.6 This change will not modify,the rate of waste-production. . A Therefore, the releases of radioactive materials, in liquid, l gaseous, and solid form, should.not change. 1 l 6.9.1.a.7 ' Due to improved ALARA rneasures employed by Chem-Nuclear, the-estimated exposure to plant personnel should decrease due to ' their presence.
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6.9.1.a.8 . . _. The'usezof Chem-Nuclear to. process radioactive waste was reviewed #
. and found:: accept able by J the . Onsite = Review c and Invest igat ive; Function under OSR 90-034'.
- 6. 7. 2. a.1/6. 74. 2.'a.' 2 ,
Since the RadwastelProcessing vendor willLchange, as described, above, so will;the specific method'and; processes 1used.to ensure j
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that the wast e meet s ex ist ing.' burial' and 'NRC. -requirement s.- .Per J Chem-Nuclear's . Mobile Solidi ficat ion ' Service 1 Descript ion,- N attached, theie Topical? Report CNSI-2 M4313-01354-01P-A) has.been accepted by the USNRC. .Another Topical =Reporti CNSI-WF-C-01-NP,- has also been submitted to the=USNRC for. review.= Chem-Nuclear 11s' presently processing radwaste for other-Commonwealth.. Edison 'i Nuclear Faci.lities, with no waste' form concerns. 4 4 6.7.2.a.3 The use of Chem-Nuclear to process radioactive' waste was reviewed and:-found acceptable'by the Onsite Review =and.Investi'gative-j Function under OSR-90-034..
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e. l MW 89 0804-P01 . CMEM NUCttam systtus s%C MOBILE BOLIDEMCATION lI5EVICE DMCRIPFIO14 a BACEGROUND On site solidiScotion ~ of low lent radioactive -wastec has- beeni conducted by Chem Nuclear personnel at over 35 ' nuclear facilities durir4 theLpast 14 years. Chem-Nuclear has denloped a Mobile Solidi 8 cation Unit (MSU) speciScally designed ; to facilitate in container solidi 5 cation of various radioactive waste ' including - : evaporator bottoms, resin beads,iPOWDEK O , alter sludges, 81terL precoat backwash, resin regeneration chemical wastes'(sodium sulfate),;deoon solutionsf oil. ,
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sludges and oil. N system is designed and operated in' keeping with all applicable ; industrial and nuclear- regulatory requirements, as_.well as Cham-Nuclear's own1 , stringent design eriteria. ( ci Immobilisation of the waste is accomplished using readily available comentitious types ; of dry chemical in coWunction with proprietary process additius.? All conditioning and . j solidi 8eation of the waste occurs in a disposable liner. Depending - on wasta characteristics, some of the required ' conditioning chessicals may be pro loaded inte ! the disposable liner prior to waste loading. EPreinstalled mixer blades permit j continuous ~ agitation until a thick cement paste basifbreed that will set to a hard, homogenous, water fkoe matriz, h end product is a true ca= ant structure formed in - 'i ' t accordance with established principles of concrete technology.. i Chem Nuclear has denloped'and' tested a Process Control Program (PCP) to ensure a
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that optimum solidineation is achieved ibt , each type _ ofcwaste. b : tests and calculations to determine the required amounts of additives needed ars' within this . l program. J Chem-Nuclear Mobile Cement Solidi 6 cation- System and' Process Control Program . described by Topical Report CNSI 2 (4313 01354 01P-A) has been accepted by.the U.S.' [ Nuclear. Regulatory Commission for incorporation by reference .in utility? licensing ! u applications. In Newmber 1988,~ Chem Nuclear also submitted Topical Report h I CNSI WF-C 01 NP,10CFR61 Waste Form CertiScation Coment to the U.S.-' Nuclear l Regulatory ('a==lamian for review and acceptance for meeting 10CFR81 requirements in utility licensing actions. A-1 (6291P) Jf S' _ _ . . . i
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~ EQUIPMElff DESCRIPTION '
N MSU has been designed for maximum Sexibility and connects easily to most waste collection systems. Portions of the MSU may be mounted in a control trailer to . facilitate-its use outdoors. - Another unit was developed for use .inside a utility ! radwaste building. Th's unit has its componente mounted on easily moved skids and : is called a Portable SordiSeation-Unit (PSU)., N solidiSeation knetion and basie = operational design of both the trailer and skid units is identical. The equipment furnished by Chem Nuclear is required to be ihnetionally testad prior s to processing wastes. b following major components are included in our' typical solidi 8 cation system. Figure 1 provides a- basie one line Process and Indication Drawing. 1 Disposeblo IJnar - A steel _ container with a disposable shaft / blade mixing aseeably.- , All waste conditioning. and solidiScation chemicals are added and mixed in b i
. disposable liner. Liner selection is based on weste characteristics such as radiation -
level, chemistry, amount and estimated curie content as reported to Chem Nuclear by the utility. J Fillhead Asesembly A Fillhead and Extension Skirt Assembly provides the means to j l control the spread' of contamination and cement dust during the solidi 6ention 3 l: operation. h 811 head seals onto the opening of the disposable liner through b use
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of turnbuckles b R11 head assembly contains a hydraulic mixing motor which mates - q l- to the mixer assembly in the disposable liner. Separate piping ibr dewatering, waste ]" addition, coment addition and chemical treatment are contained in the 811 head. -h 511 head also includes instrumentation for l monitoring the liner water . levels and
- l. temperature, as well as a camera fbr remote, closed eircuit television viewing. ][
o Plant Osamastism Stand TheJPlant Connection Stand (PCS) is a portable ' skid . containing an automatie waste shutoK valve (WS 1), dowatering pump, sample / flush connections, service water and service air connections. N waste valve (WS-1) may be L removed from the PCS and mounted directly to the plant waste connection. l Venturi Serubber % . disposable liner is vented through ~ the Althand vent connection to a. venturi scrubber skid. The venturi . scrubber includes - an ' air conditioning unit to cool the ver.ted air, ensuring removal of all dust. % outlet of the j ' venturi scrubber is then connected to the plant of-gas systems. i A-2 (6292P) J>
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;i 6 W 89 0804.M1 - -3 CMEW NUCLEAA SYSTGM8 INC FIGURE 1- ,
TYPICAL MOBILE SOLIDIFICATION UNIT p. l l
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HydranBe Unit - N hydraulie unit powere the miser motor located on the 611 head. In the trailer mounted units it is located within b trailer. With skid mounted units it is mounted on its own separate skid. Centrol Panel N Control Panel provides b Chem Nuclear operator with all l controls, indications and alnrms necessary for safe, remote operation of the entire j l
- unit. In trailer-mounted' vaits,. it is located within ~ the trailer. : b TV' monitor,:
temperature recording device and load cell readout are placed in close proximity with b control panel. Balk Trauer h dry themicals (eement and line) required for weste eeudiScation are stored in the bulk trailer. h bulk trauer has been designed to facilitate' delivery i of bulk material by a w,ndor directly to the trailer, h ' system has also been designed' to =H=ia=** dusting by utilising a bW- or cyclone separator. ~An optional ello may
. be used in place of the bulk trailer in long-term applications. Electronic load-oells' measure the amount of material transferred. , j 2
Conveying Systems a h dry chemicals for solidiSeation are transferred to the disposaWe liner vaing: a cycloneaire unit. ' b system has' also' been designed to: educator other proprietary dry chemicals into the. disposable liner, h dry chemicals .
.are transferred to' b liner through a cyclone separator and rotary airleek on the 611 head.' This system minimimaa the amount of dust and air'which entere the liner. 3 h return air' hem the cyclone separatsr is' vented back to the bulk trailer to eliminate dusti.ng.
1 E Equinnaant Set Up ! b equipment arrangement is highly :Bezible in the PSU skid-mounted unit. p Placement of the Control Trailer for the MSU is limited by the availabuity of services,. length of hose, and' length of cable run to the disposable liner.c Chem-Nuclear has- , designed its systems to separate non contaminated componente bom'the normally contaminated components such as the 811 head, disposable liner, and waste handling l' pumps and valves.L All components 'are controlled remotely toen the Control Panel, which is located in a clean area, and are interlocked and alarmed to preclude unsafe operation or operator error. Normally contaminated components have been designed and placed in the system in a manner that.allowe flushing and draining of that , component prior to' maintenance. This design helps to maintain personnel esposures ' l As-Low As Reasonably Achievable (ALARA) andL allowe ease of maintenance and I operation. l A-4
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MW 89 0804 P01 ' CMEM NUCLEan sv5tEMS INC PROCESS DESCRIPTION . Chem Nuclear solidi 8 cation process begins with the Process Control Program (PCP). L h PCP was developed to ensure that each batch of radioactive waste moeived by b i L process unit is capable of being solidi 8ed into the desired end product: 'a monolithic h solid containing no fW water.
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Chem Nuclear utilises specinc additives in the Process Control Program. These l chemical compounds control pH,' matrix strength, leachability,L waste-to.end-product - L ratios, heat generated, prevent " bleed" liquid, and are instrumental in controlling and _ q adjusting cement setting times.: h:Prooses . Control Program is run on actual + radweste, not on cold simulated waste. Chem Nuclear's hal==aad chemistry uses the waste components baselves to enhance solidiscation.- This procedure allows a I _ predictable end product and results in a strong concrete blust meeting all acceptance criteria for burial. .: h disposable liner is prepared by installing temperature detector leads and a level m.asurement tube which connects to b Slamed. m disposable liner is then placed ' in the process area'in a shipping cask orLehield (if required).: The 611 head / skirt l aseembly is then installed on the liner. h hydraulic motor shaft engages with the : disposable miser blade assembly to provide the agitation required. N dewatering leg; q is then' connected if roquired for dowatering waste slurry. After pre operational testing of the system, redweste is transferred by the plant pump : di-harge kom the plant waste connection through an automatic shutoff valve (WS 1) . i and a 11/2 inch waste hose to the Silhead. N Albad directs the' Sow of waste into the liner, b Ellhead is.yeates a built in television camera and lights so that the operator can monitor the entire operation runotely. - q Control of the addition of waste, water, additives, cement and mixing is performed by
'ns of the remotely located operator control panel. Should dewatering of the waste 3 L dred at this point, it is' accomplished by maakaale=1 futration through a
>ble Elter in the liner. Waste solids' are removed hem the sluice water and. J
- l. A wateris returned to the plant... -
! 1 l L . . l ba b waste transfer is complete, the hydraulic- system is started and waste l L agitation begins. At this point, should pre-treatment of the waste be necessary, such L additives are remotely added to the liner and thoroughly mined with b waste. I A-5 e, (6292P) "' \ _
t - gw.ag.ogog. pot . b CHEM NvCLtaa sv8fEWS INC (Order of addition of pre treatment chemicals and cement is dependent on the speci8e radwaste stream). Solidi 8eation dry chemical addition'is then started using the pneumatic conveying system. b dry chemical is' continuously weighed with an instantaneous road out on the control panel allowing for the predetermined quantity to be proeisely added to the - liDer. The formation.of cement is a complea,' heat. generating-procedure in which several different stages occur in the course of solidisestion. N Brot, a gol state, is a' rapid reaction and is normally completed in the Srst 24 hours of cure time. During the next several days, continuing hydration reactions occur which'further increase the prodnet . hardness. b formulas which produce structurauy sound and L &='N eement binets vary according to the type of waste being solidi 8ed.-._ Process variables include: waste temperature, pH, chemical composition, waste-to oementMadar ratice and waste z volume. These are careadly analysed and controBed by Chem Nuclear Seld engineers with extensive experience in waste soBdi8eation. A8er the required cure time has elapsed, the 811 head is removed,' the liner contents are scrutinised for the product quality and the liner is sealed for shipment.- Strong, stable concrete bulets are properly cured 86 to 72 heure aAer solidi 8eation. . Under normal solidlSeation conditions, the binet is transportable within 2 to 3 days. Interface 1%squiremnants o Electrical 480V,3 phase,'60 Hs at 100 ampe o k&e Water 26 gym at 80
- 20 paig.
o Service Air 40 SCFM at 80 + 20 10 peig (may be supplied with one or two hoses, clean dry air)
- o. Waste 1 1/2",150 lb. ANSI /ASME Sange connection rated at 160 psi .
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% I o Vent 2" Camlock vent hoes discharge connocha to plant off-gas j system (manimum of 80 SCFM) space Reparamanta l
i space required for b solidi 8eation unit will be de*armined by the physical layout . 1 of the plant's radweste area. As a general rule, the akid mounted unit (PSU) requires d about 300 square feet, emeluding :the bulk trailer. ' A standard bulk trailer is l approximately 42 feet long by 8 feet wide.: Crane and building clearance over the; dispo.able liner must allow for installabo and removal of the 811 head /ekirt assembly.
- N 811 head / skirt assembly adds approximasely 7 feet to the top of the liner. - l 9
Servian Respdramanta ' 1 o Communication between the_ plant radweste operator and the Chem-Nuclear l mobile unit operator, o In plant, local and long distance telephone service at the Solidi 8eation Unit for . required business calls by Chem-Nuclear's personnel.o l 1 o An operator and the erane capability for the movement of items which include, y ' but are not limited to, cask covers, liners and 811 head / skirt amammbly. q o Special' equipment, such as calibrated torque we-h=, -necessary for . cask ) operations in accordance:with the Certi8cate of Compliance _and; operating 1 procedure for each particular eask used. H o A forklift capable of lifting 4,000 pounds with a 6-foot vertical lift to nalaad the reamvable akids and plade them in posibn for full ecale solidibation. i 1 o A Radiation Work Permit (RWP) issued to the Chem Nuclear operator before operations begin. o Protective clothing, respiratory equipment (if. required), and adequate radiation monitoring equipment necessary for radiation protecha.
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. WM1 Cngu souCLE Am svattwe seeC e A sentround area establiebed around the pensassing area.
o An area designated for PCP test notidi6estions. o Health Physics coverage and support required to conduet solidisestion-operations in a safe and proper mammae. o The name and departament of the Company employos desigasted: to be responsible for coordination of the solidi 8eation servies between Chesa Nuclear and the Company. Wanta Idandannatlan o To ensure proper liner and abipping container selection and establishment of adequate ahamleal inventeries, Company abau advies Chem-Nuclear d waste type, amount, appr==trante radiation level, ebeadstry parameters, and estimated curie sentent. i o A sample of actual waste shall be provided to Chem Nuclear operator with pH, speelse gravity and any other known ebeadstry param.etere for PCP test soliduisation. i I. A.8 (639BP) '.
g g Cat 48 n#UCLt am Svstitot iNC RDS4000 GIAPID DEWATERINGRESTERO RERVICE BACEGROUND a N Rapid Dewatering System (RDS 1000), developed by Chem Nucisar, is a selfgentained mobGe system for the accelerated dewatering of particulate waste. he system 2-1"My decreases dewatering thee trom current conventional methods used in the nuclear power industry, hree years of . estensive testing by Chem Nuclear, including lab acale, Adl seale and over-the road earti8eation, has produced a rapid dowatering system far emeseding the requirements of 10 CFR Part 41.88. N systema is cosapest, simple, and easy to operate. N RDS1000 provides measurable end points and is compatible with Chama Nuclear's present dispeamble liners, ineluding the CNS 31800 steel and CNS 14 316 10 0. Measured noise levels are well within the eurcent ua r .r:i OSHA stay thee of eight hours at 90 DbA. Chem Nuclear submitted Topleal Report RDS 36806 01.P Revision 1 in Marsh of 1988. In November of 1988, that Topical Report was nesepted and approved by the USNRC. BEtUIPMENT DESCRIPTION N Chean Nuclear RD81000 system is certi6ed to dowater most types of ar'da ua d in PWR and BWR auelear power plaats. Use of a vacuum pump to remove water through Chem Nuclear's proprietary liner Altering system provides shaple, error-free _ operation. N systema is comprised of: o Containar Fulbead (Chesa Nuclear's standard RD8 Dewatering Fulbead); o Plant Connection Stand; o ControlConsole(System); o Rapid Dewatering skid;and o Container, fr^:::: - " ; Homes, and Cable. j h RDS 1000 makes it possible to dowater containers to a media speciac certiSable ond point which can be visually sonarmai B1 (8308P) i
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- CMtM NUCLEam systtMS lesC l
l Danrataring MBhand Ammamal# l l ) j h $11 bend and extension skirt assembly connects to b liner's opening and prevents 4 l the spread of contandmation. N 811 bend also provides an interconnection between l b liner and dewatering unit. Instrumentation for monitoring the liner's waste level
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i and temperatum and a camera for remote elooed circuit television viewing an also ! included in the AlthanA ' i . I Optional attings an available for connecting the 611 bend to the liner. Noe [ j oonneetore are pull off compression attings which allow the S11 bead to be removed j remotely, thus reducing radiation espesure. l c : s Another optional feature includes b use of electro-posumatie dowatering valves l mounted atop the A11 bend instead of manual valves at the plant connection stand. This allowe remote ;:5'; of the dewatering valves tem b eentret panel avoiding ==- y radiation exposure during the dowatering operation and also i reduces the number of dewatering hoses between the Slamed plant eennection stand l Dom 6 to 1. Es setup mahan not only a more tidy home run, but alae eliminates i several potentially contaminated hoses. ' l ( q i Maat Commastina Stand ' l Mis component consists of. o A moetely operated waste valw to control in8uent to the processing liner, his valw is interlocked to close on High Waste Lowl, Hl.Hi Level (mechanical Seat t in 811 bend), and decreasing air pressure or loss of electrical power; o A diaphragm pump with connections to b 811 bead for initial groes dowatering; , and o Manifbids for air and water supplies to control elements and Bush components.- His unit is b interface for all connections between b plant's systems and the I portable system. 1 1 6 B.2 (6298P)
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e, ,. , MW.40 0804 p01 ! cameral Syndamn ! 1 !
- A Control Panel sentaining electrical and pneumatie controls allows remote operation of all componente and monitoring of individual parametere. A video monitor permits
- remote visual inspection of liner internals during processing. Temperature and pressure indication of the prianary coanyonente is provided on the Centrol Panel with I
audio and visual alarms to indicate any abnormal senditions asesting everall systema i operation. A FAVA level system monitore the media level in ths' liner, and provides J ! automatie closure of the waste valvo. A second system, with separate probes mounted { l in the moisture separater, eentrols moisture separater water level by pump activation. ! i f l Rapid Dawatastag Ehdd
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I h Rapid Dewatering 8 kid sensists of b veeuusa punap, meisture separater, air <
- conditioning unit, and piping interbe to the plant eennection stand. Pressures and j temperatures are monitored at various points en this compement to antiguard l
- maahanlaal operations.' A HEPA Siter is lastalled downstream of the saasty relist {
j valve and manual bypass valve to ensure against =aaldantal discharge of air to the i 1 environment. l Dispanni Comininase l l Clam Nuclear provides a wide range of stainless steel, carbon steel, and HIC, all ! designed and fabricated for transport by Chem Nuclear's Type A/B 'ensk Sest. Fabricated in accordance with the Chem Nuclear QA Program, the containere are inspected and accepted by Chem Nuclear.QA personnel prior to their departure trema
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the Earnwell Waste Managemaent Facility. High Integrity Containere amet the R.i. rte of 10CFR41 for stabilising wastes and are approved $sr disposal by the : State of South Carolina. i Elantrient and Power Distribution EspalP 'hant b RD81000 contains all auxiliary electrical equipment required for operation, such , as the motor controls, interlocks, alarms, and electrical wiring. b electrical system, with name resistant wire jacketing and insulating material, is , fabricated to accepted industrial standards, h systems motore are UL approved, ! and all electrical equipment and devices are rated for continuous servies, b B-8 (6293P) r
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c sw wcum mums =c ; l RDS 1000 Rapid Dewatering skid aestains automatie interlocks wldeh terednete ! i blewer operation upon high temperature indication, j
- PROCESS DESCRIFFION !
l i N RDS.1000 is a elooedleep systesa used to reeneve the bulk of water been a l container, as in a eenventional system. -N systeen then roeireulates air et high ! ! voleesty to rapidly dewater the container to the aneured este burial criteria. !
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Systesa operation is estremely simple, requiring enh one operater. AAer setting the j mador compemente in plan and leveling 6 liner, the esanestions ano snapped inte !
; place between unit componesta. When eleetdeal power, service . water and air are j
) connected, the system is ready to receive the waste transfer. N system een be i j r.seeabled and ready for dowatedag in less than 4 hours. { i ; t , A Process Flow Diagram (PFD) is abowa in Pigure 1. AAer waste tranader thr4 the l [ waste inlet valve (WS 1), eseems water is pumped been the liner through ; 1 Cheen Nuclear's pa,.d2.y, media specise, Altering systeen and then rotermed to the ; i plant, leaving the solids in the liner. N remotely controlled SD operation is viewed on the Control Panel using the videe camera mounted in the Subead ama===Wy. I N level control system detects and monitoso the liner level to adaimise operater [ exposure. Over611 proteeties is provided through this systeen and an 1% t Hi Hi level control in the SHbead, either of which will automaticalh elese WS 1 when I over611 conditions exist in the liner. WS 1 will alas eloos automatieauy in the event of
- loss of system air or electrical power. N operater can also manuaDy activate WS 1 if '
the video monitor indientes that it is necessary. ' During waste transfer, a dowatering pump is activated to renwee the eseems water , used for transfer and to and in compaction of the media. AAer the completion of waste
- transfer, a grees dewatering operaties is conducted with the same positive displaceanent airoperated diaphragm pump. With the removal of most of the water kom b oontainer, the pump is shut off and valved out of the systeen.
b Rapid Dewatering Skid is valved in and turned on. N heart of the systeen is a quiet (less than 76 DbA), high quality vacuum pump, capable of sustained operation at 29.5 inches of mercury vacuum. When the pump is started, air is reenoved been the , closed loop with the off.ges valve to the self contained HEPA system. At the proper 9 b B4 i (6298P)
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l MWNP01 i CHEW NUCLtan systsus aNC l ! systema pressure the off gas valve is elooed. Systesa performanse is monitored to i 2 completion. 1 i l i Water is moved by air velocity through the waste media and the container Eltration j
- system to a meisture separater in the dewatering skid. Chem. Nuclear's proprietary 1 i water remeval system includes a refrigeration coil that reduees the dew pdat of the L air, b air then enters the vacuum pump for indeetion beek into the liner. A pressure relief valve provides liner everpressure protection. .
i i [ Chem Nuclear - has elected to use - a positive, visual motbed for end point _ 1 l deter =l=h To sesomplieb this,- a eight glass, enlibrated in inebes, has been i installed on the bottom of the moisture esparator. When the water collection Ibr a spectae media is reduesd to an aseeptable level, as verised by the eight sinas, the ) ! media is considered dewatered. ! 1
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i TEWFING AND EVALUATION Over two years ago Chem Nuclear embarked on an ambitious laboratory resenreb and , development program to redueo dewatering times. his program involved running i estensive laboratory, Sold, and fall seale testing of the more difBoult to' dewater . l granular and preenet media. Tests were witnessed and sonarmed by Chem Nuclear's ! l QA group. Media samples were obtained during the testing process. Testing ! included: (1) after standing, and (2) befbre and after a 900-mile road test over .
==aandav roads.
N samples were analysed for moisture content using ANSI /ASME standard tests. i N test data results were compared with the manufacturer's publiebed meisture retention espeetties. Eg'- criteria were met only if the percent water in the sample was below the manufacturer's published Moisture Retention Capacity after completion of dowatering. His approach ensures that any aaad==aaMa moisture in ! i the container would be reabsorbed into the media. Drainable water was collected after read tests and evaluated to ensure protection when received at the disposal site. All disposal site minimum water criteria in the containers were aableved as predicted. , Chem Nuclear's end point determination was carefully ebooen after extensive testing ; and' data correlation to far enosed the fkee 9 "-g water criteria of 10 CFR part 61.56 (a) 3 and (b) 2. Water collection rates were monitored during the drying phase of the test. A sample of these data is presented in Figure 2. N degree of testing ' performed provides an added insurance of Chem Nuclear's commitment to quality. B-6 (6293P) ,
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6 y e MW m P01 i Coqu wuCLt&A Svetenes 64 j L FIGURE $ i RDS 1000 WATER COLIACTION RATES : I- l
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, to-a y y 3 i i y o 2 4 6 s 10 12 TIME-HOURS (A' FTER INI'TIAL GROSS DEW ATERING) I .. B-7 (6293P) W_ . .. -. J
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'-. ..,,-,n, , . , . . . . - . - ~ . - - - - - ___ __
- j I
l : e1 g g CaelW wuCLtd systlet tNC Reviews were esadmeted durias the design, fabriention, and testing of the RDS.1000 l erstem to assure operster espesure was maintained As Low As Reasonably Aehievable l (ALARA). N test data showed that the liner operates undw a slight negatin pressure to proelude espelling potentially oostaminated gas or media to the stamphere. OPTIONAL BQUIPSENT 1 i ! LSA bosso how base designed for transportation of the RDS1000 system between plaats. l DISPOSAL CONTADER COMPATIBIIJTY ' N RDS 1000 has been designed to be compatible with the present sentainer product l line of earben steel and HIC, including the Steel 31800. Several diSerent sets of i proprietary tainn intenals, tailored and enginemed ser sp=ine media, are instaued. All of the containere are of the Sat bottosa design. l l l . VOLUME REDUCTION l ! When rapid dewatering of a sentainer occurs, the medority of water removed trem the container is neoomplished by Suid dynamies, b forees erested in the sentainer i prednee eenu compacties of the media. Advantage in packaging edSeiency een be ! realised if the spaes made available is oceupied by transferring additional weste. N ) trade off requires additional drying time, and the volume is small compared to the i estra time -v to dowater the container. Chem Nuelear does not m=aad eseessive drying, particularly when dowatering resia beads. Enpossive drying without some forma of Esation can eaune the beads to return to their original volume and produes estremely high loads upon the containw walls as ruin ; oesure when. meistue is reabsorbed. CODES AND STANDARDS h applicable portions of the fouowing. emes.anTotandards were used during the design, fabrication and testing of the RDS 1000 system: o NRC Regulatory Guido No.1.148 Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed la Light Water Cooled Nuclear Power Plants; 4 B.8 (g298P) j
~
a ;,.w;n::,cw;: ;;.w..;a,. :w - - - - - - - - - -
. 1 4 . .
. MW 890006 F01 s e TRle 10, Code of Federal Regulations, Put 30, Standards for Protection Against :
i Radiatism; l l l o American National Standard ANSI /ANS . 66.6 1979 IJguid Fadia-tive Waste f Processing System for Lidnt Water Reactor Mante; i l o Amerleen National Standard ANSI /ASME B81.1 Code for Preneure Mping;
- o ASME Bouer and Preneure Vessel Code Section IK Welding and Brasing I QualiSeations;
- a j o ASME Bouer and Prosauro Vessel Code Section VIII Pressure Vessele; .
l l o Nuclear Pgitf ca==l=lan OfBee of Inspection and Enbreement Buustin .{ i No. 7919; , 1 1 o- CN AD 019, Chem Nuclear Systems, Inc., A1 ARA Polley. j ( o QA AD 001, Chem Nuclear Systems, Inc., QA Program; and o EN AD 002, Chem Nuclear Systems, Inc.', Design Control Procedure. 1 SIEPPING AND FIELD INSTALLATION l Shipping and Ammanable Raquirenamatn ; i l N RDS 1000 is designed to be abipped on a Sathed trailer. Loading or unloading is I nooosaptiebed by a minimum two ton especity fork truck or erano using en approved sprender bar. h Ahand is shipped on a protectin stand to ensure the integrity of l the gasketed liner sonnection surface. o , Por over the road abipment between plants, LSA bosse are prwided for et.ch of the , four mador components, interconnecting hoses, and embles. All equipinent will be ; l_ tested at Chem Nuclear prior to abipment to the oceapany. Asseeably of the equipment has been kept staple.: Interconnecting hoses between mador components ans 50 feet in length and have been provided with standard proven - a==6h quick disconneet couplings or ANSI /ABME Sanges. Elsetrical cables use B.9 : g (6298P) j
.....m....,-..---
(., - j 1 , ; MW494806 701 canui msaa systeus ac l l l M eh fBr power cables and amM connecter 5 IDF signal embles. M I cables are norusally 80 feet la length, but may be manufactured for special applications in lengths up to 100 feet. L ., 1 SPACE REttUIREMEN15 N three ador components of equipment have been designed to operate in a truck bay and require a minimum Soor spaes of 90' long a 8'4" wide. N di=h of these items (dewatering skid, plant connection stand, and control panel) are given la
- Figure 8. Maximum overhead clearamos for the rapid dowatering skid is 83 inehen. 1 j- ;
N entire system may be operated either indoors or outdoors. 'If outdoors, everhead j l rais protection must be provided for the control panel. : 5 I
- INTE3tFACE REMtUIREMENIS Interface requirements for operation of the RDS 1000 system _are speci8ed as fouews: :
\ o Electrical 480 VAC/8 phamet00 Ha at 50 amps ISO VAC/1 phaea40 Ha at g 90 amps o Service Air Approximately 40 SCFM at 80 + 20 10 pois, clean dry air o Service Water Approximately 26 gym at 80 t 20 peig (intermittent) PROCESSEFFLUENTS o Process waste media slurry water return to plant: 11/2" hoes (as required to transfer waste). y i o Moisture 5eparator Cousetion Water Retura: 3/4" hoes (maximum 8 gallons per minute). l 4 o Recirculated Air to Off Gas System: 11/S". hose; required only if dowatering skid IMPA system is not used (typically 60 SCFM during startup and shutdown). 1 I PROCESS INFLUENT o Weste from plant (1 1/2",150. pound ANSI /ASME flat-faced Sange). . B - 10 l 0 ! (6298P) ( . . . . _ . . J
i . F d
,. gggg FIGURE 8 RDS.1000 RASIC DDEENSIONS ii -
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'Information-for thesMonthly; Report '
Major.Changesjto the:Radwaste System ! 6.9.1.a.1/6.9.1.a;2/6.9.1.a;3
~
Modification ~ 1-0-88-014-1 was~on-site reviewed andiapproved...'This, modification wil.1. provide thel .;
. addition of' concrete.. shield' walls:tofform-cubicles.for: processing' t
'of solid _.radwaste Liners andLHigh:Integt_ity_ Containers.,;These: '
wallsLare; being sinstalled11n; the 'areafpresently designated asc the. i:
- . North / Intermediate Level Storage' Area.1 nTof facilitate thefabove.
processing,_penetrationsithrough the?outside wallLfor3 cement. _ delivery.will-be adde'd,.portionsiofaexisting-_masonaryLwalls'will; a
, be removed,;andl core holes will-be;added11n a' block. wall.toi '
4 y facilitate hose. connections'to radwaste-vendorcprocessingi,. ', equipment. A copy of' the 10CFR50.59idone' for' the modificatioriiis - V attached. ,
, e
'6.9.1.a.4 This change.will; relocate the; processing;from the- -
truckbays toithe . area? over the shielded: walls;- Thisiwill'freelup0 " c; the truckbays for; shipping activitles,.:andihopefullyfmake the- j station more ef ficient in . shipping.: TheLquantities of waste- -e generated, in liquid, gaseous, and.. solid' forms, should not change? J , from those previously predicted,,on1_ytthefefficiencyLin which; they are shipped should" increase.r _
. r 6.9.1.a.5 Exposures to;individualslin'the restricted t area,Jand 0 to.the general populationJdueLto this: change should decrease., _
i The-processing will be relocated fromcinLthe..truckbay,rto'behind- O shielded concrete walls. J j 6.9.1.a.6 The predicted . releases-Tof1 sio11d'iliquid,-. and. gaseous, , l effluents should remain constant. The; waste will continue to;be} generated at existing rates,>.andfthisfchange would(helpEincrease: the!. efficiency at'which it;is' shipped, but~there! should notlbe a_ l change in the.. amount _ produced.- ' l
-6.9.1.a.7 Exposure.to plantLoperating.personnelishould2 decrease j as a result of thisichange. (The. processing of sludgestwillibe: .. .:
relocated from the truckbay, : a busy operating- area,0 tolbehind the - N
.concente shield walls. !
~
6.9.1.a.8 R copy of the On-Site Review appro0 alt signaturesiis. attached.. <
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f i . LAP-1300-2 i
/y'/ Revision 25
,/ \ February 26, 1990
/ !
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! i d.
j,i > MTADRENT N
,e MODIFICATION NO _N-1-e-aa-e14-1
- EM61MERDElEIEESIS i
- 1. PURPOSE ABS E28 pes
)
l ! A. TO PROVIDE TM ADDITION OF CONCRETE SHIELD WALLS FOR CUBIC l i' FOR PROCESSIN8 0F SOLID RADWASTE SYSTEM LIERS AND HIGH e INTESRITY CONTAINERS (HIC). THESE WALLS ARE BEINS INSTALLED THE AREA PRESENTLY DES!9NATED AS THE NDRTH INTEfDEDIATE L 4 STORAGE AREA. TO FACILITATE TM ABOVE PROCESSINS PENETRAT SLEEVES WITH CAPS WILL DE ADDED THROUGH TM OUTSIDE WAL USED FOR CEMENT DELIVERY, PORTIONS OF EXISTINO MA00 NARY WALLS l ' WILL BE REMOVED, AND CORE HOLES WILL DE ADDED IN A BLOCK WALL
- l. TO FACILITATE EQUIPMENT. i HOSE CONNECTIONS TO RADWASTE PROCESSINS B. SHIELDING LIDS FOR CUBICLES WILL BE FABRICATED BY OTM RS, AND- i IS OUT FOR BID UNDER SPEC. ECC-St-Sett o
- 2. Qgt!GN BASIS FOR EXISTING CGdBITIONBa l i
DE818N BASIS FOR EXIIITIN8 CONDITION IS SECTION 11.4 (80L1'D
, WASTE (11.4.5.9)MANAGEMENT SYSTEM) 0F THE LSCS-UFSAR. A SECTION -I IS SHIPPING CONTA!E RS. DE!N8 ADDED TO ADDRESS TE PROCESSING OF RADWAST I
- 3. !
TYPES OF 0""INBB/D0tDCMTB kminus l
! STRUCTURAL DWOS., ARCHITECTURAL DW88., MECHANICAL DW88.
(PENETRATION SCMDUAL), AND UFSAR. i' I
; 4. INDACT OF om*DS C#^ =
(OU M M l' t' MOD M-1-4-88-814-41 MAY REQUIRE THE ADDITION OF AUTOMRTIC 1; DETECTION IN THE RAD WRSTE AREA THIS WORK WILL DE DONE l R} H t! 4: DUTSTANDINS PARTIAL MOD M-1-9-88-814-88. THERE IS NO IMPACT ON ANY I. SPCR'S OR CR'S. [ l, , i 4 i el l J
,' ; S.I
.-U IMDACT OF'RQRT!aL INBTotiATIONa e tv.o :
f; ni
}, mil' t
c; ) 1 iFi ; PARTIAL i REQUIRE < INSTALLATION OF MODIFICATION M-1-9-88-914-1 WOULD iI, f BWR APPROVAL. w~ h j gjj j ' n '; -3
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LAP-1306-2 t' ,4 Revision 25 j i
; February 26, 1998 l
I't l l ; 6. I IWTM.LAT!tBd lElft( SIEMDIMels j\ji' A. CORE DRILL HDLES. i
'l B. LOWER WALL.
4 C. POUR CONCRETE & CURE. D. INSTALL 8ALLERY. f E. INSTALL PENETRATION IN CORE DRILLED HDLE.
?
i F. PAINT AREA. l ll 7. ' STATICBMBillEE Mtpt(e.a. MCURITY,FIM PMITICTl!BI) A. EXTERIOR WALL PENETRATION MAY REQUIRE FIRE WATCH UNTIL RESTORED TO ORIGINAL RAIT!NS. B. IF OPENING IN EXTERIOR WALL IS LARGER THAN 64 90. IN. OPENING
.' MAY REQUIRE SECURITY WATCH.
- i S. 6dDRHIM DEPARTMNT MBptBEIBILITIE$a i ALL WORK IS TO BE COMPLETED BY ENC.
i'
- 9. TEST MIMENTS & fECEPTfMI CRITERIAs .,
TESTIN8 PER MOD. TEST CONSISTS OF TE FOLLOWINS. DIE NSIONAL VERIFICATION, CONCRETE SLUMP,. COMPRESSIVE TEST, REINFORCENENT i LAP, RE!W ORCEMl!NT PLACEMENT, BOLT TOROUE!NG, WELDINS l INSPECTION, VERIFICATION OF STEEL INSTALLATION, & VERIFICATION OF COATINS.
- 18. TRAINIM MIMENTR1 RADWASTE OPERATORS SHALL BE TRAINED IN TE OPERATION OF DVERitEAD i CRANE FOR LOCAT10N AND MOVEMENT OF HIGH INTE8RITY CONTAINERS, LIERS, OR SHIE.D LIDS. TRAINING IS TO BE PERFORMED BY THE TRAINING DEPARTHENT..
I1. l TECH SPEC & LFSRR M1fEDENTS:
- 4 TERE ~ ARE NO TECH SPEC REQUIREENTS, LFSAR REQUIRES A REVISION AS A RESULT OF THIS MODIFICATION.
NOTE: UFSAR REVISION MAY REQUIRE ADDITION OF AUTOMATIC FIRE DETECTION SYSTEM. j 4 j l i p page 2 of 3 1
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I LAP-1346-G
./ Revision E!5
> # February 26, 1990 11
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- 12. CODES.RTMSARDS & SAFETY CLJ$$ MllEfeiTS3 t!. ? AISC-LATEST REVIS!DN, AWS D1.1 LATilli REVISION, ACI 318-83,
[ 'h J 7 UNIFORM DUILDING CODE ~1988, )ON-$AFETY- RELATED. L jj i 4 J i [
. ] 13. SPECIAL MIMIEffSa 9 ,
4 NONE
; t 14. EMIfEER!fe & IISTALLAT!Wd SOEMA.ES l i; !
id FALL OF 1990 ["- ,
. )
- i. 6 , ,
- 15. SPECIE E IISPECT!WI MEJIMIEdTS l.
INSTALLAT10N SHALL DE PERFORMED IN ACCORDANCE W!TH THE REQUIREMENTS FOR NON-SAFETY-RELATED WORK IN THE CECO GA M441AL . OR CONTRACTOR'S QA MANUAL APPROVED BY CECO. !
. .l t
a Prepared by: Ext. X ~22 # 7 1 Dates 9 - W- OD l l l 1
' i i ! [-
i F page-3 of 3 4
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LASALLE NUCLEAR POWER STATION ; i UNIT 2 [ MONTHLY PERFORMANCE REPORT i SEPTEMBER 1990 ; i COMMONWEALTH EDISCN COMPANY i ( NRC DOCKET NO. 050-374 LICENSE NO. NPT-18
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- e'
- i TABLE OF CONTENTS (Unit-2)
I. INTRODUCTION l II. REPORT A.
SUMMARY
OF OPERATING EXPERIENCE B. PLANT OR PROCEDURE CHANGES, TESTS,.EXPERINENTS, AND SATETY'RELATED MAINTENANCE (50.59)
- 1. Amendments to facility License or Technical Specifications
- 2. Changes to procedures which are described-in the' Safety Analysis Report. . i
- 3. . Changes to facility which are described in the Safety Analysis t Report.
- 4. Tests and Experiments not covered in the. Safety Analysis Report.
C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D. COMPLETED SAFETY-RELATED MODITICATIONS , E. LICENSEE EVENT REPORTS : F. DATA TABULATIONS ,
- 1. Operating Data Report
- 2. Average Daily Unit Power Level- '
- 3. Unit Shutdowns and Power Reductions '
G. UNIQUE REPORTING REQUIREMENTS
- 1. Safety / Relief Valve Operations
- 2. ECCS System Outages ;
- 3. Off-Site Dose Calculation Manual Changes '
- 4. Major Changes to Radioactive Waste Treatment System
- 5. Indications of ralled ruel Elements l
1 J l 1 l I ZCADTS/7
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- 1. INTRODUCTION (Unit 2) i The LaSalle County Nuclear Power Station is a two-unit friellity owned by Commonwealth Edison Company and located near Marsellies,~ Illinois. Each l unit is a Boiling Water Reactor with a designed not 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.
t Unit Two was issued. operating license number NPF-18-on December.1- 6, i 1983. Initial criticallty was achieved on March 10, 1984 and commercial
~I power operation was commenced on June 19, 1984.
i This report was complied by Michael J. Clalkowski, telephone number (815)357-6761 extension 2427. e l-l l l l l l 1 i l l l l ZCADTS/7 s
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.fs. ] . , , , . 'II. ' MONTHLY REPORT !
4 A. SUM 4ARY OF OPERATING EXPERIENCE (Unit 2) Pay Ilma Event
}
1 0000 Reactor critical, generator on-line at 1100 MWE. , 3 0500 Reduced load to 900 MWE for System Load. i 1130 Increased power to 1100 MWE. 5 0400 Reduced load to 960 MWE to Cycle Turbine Control Valves. ;
)
1000 Increased power to 1100 MWE. , 12 0305 Reactor Shutdown'(Scram)'due to problems encountered-during Weekly Surveillances.. l l 20 0803 Reactor Critical. 21 0430 Generator on line. =3 22 0200 Increased' power to 925 MWE. 25 0300 Reduced load to 620 MWE for Rod Set. ! i 1400 Increased power to 1120 MWE. { 26 0300 Reduced load to 850 MWE for CRD Exercising. [ l i 1200 Increased power to 1123 MWE. I i 30 2400 Reactor Critical, Generator on line at 1123 MWE. ' I ( i f i I l ZCADTS/7 i
,_ m. . ., - -4. , ,.
. . *. ,' 1 B. PLANT OR PROCEDURE CHANGES, TESTS OR EXPERIMENTS (50.59) (Unit 2) l
- 1. Amendments to the racility License or Technical Specification. ]
J
- a. Clarifications of requirements for automatic bypassing of l DG trips on an ECCS actuation signt.1. j
- b. Correct the single large load reject value for Div 3 diesel generators. ;
'1 I
- 2. Changes to_ procedures which are described in the Safety 1 Analysis Report. '
(None)
- 3. Changes to faellity which are described in the Safety Analysis ;
Report. ;
- a. Modification M01-2-87-006 - See Table 2 for description.
- b. Modification M01-2-88-001 ~ See Table 2 for description.
- 4. Tests and Experiments'not described in the Safety Analysis )
Report. (None) C. MAJOR CORRECTIVE MAINTENANCE TO SATETY RELATED EQUIPMENT (including i SOR differential pressure switch failure reports). (See Table 1) i D. COMPLETED SAFETY RELATED MODITICATIONS. (See Table 2) s 4 7 p F ZCADTS/7 , i
D.4 TABLE 1 (Urdt 2) '. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT WORK REQUEST RESULTS AND ETTECTS CAUSE OF MALTUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION NUMBER COMPONENT LO2308 Suppression Pool Level Indicator Improper Level Indication Replaced Level Indicator Narrow Range Level LO2511 Outboard Feed Water Solenoid valve Solenoid Inoperable Replaced Solenoid Valve Check Valve LO2576 RCIC Condensate Ptump Relay Indicating Lights Shcw Replaced Relay Improper Indication (No SOR failures) ZCADTS/7 1 ._= ,_ _ _ ___ _ _ _ _ - _ _ _ - - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _
- D. TABLE 2 (U2it 2)
COMPLETED SAFETY-CELATED MODIFICATIONS , . . i NUMBER DESCRIPTION. . M01-2-87-006 This modification involved replacement of the 2PM13J panel in ' the control room. This corrected o.tstanding problems with the panel such as 1) mirror imagining b etween the two divisions which comprise the panel, 2) lack of functional grouping of controls and displays for the thre> major systems on the panel,- and 3) existing suppression pool unter temperature /drywell toeperature air temperature recorders were replaced with , separate instrumentation for each process monitored. The safety evaluation for this modification concluded that the i scope of the modification did not change the functional , requirements of the controls and displays mounted on the new l panel. Therefore, this modification has no impact upon the - margin of safety required by Technical Specifications. j M01-2-87-080 This modification removed leakoff lines associated with Reactor Recirculation Low Point Drain Valves due to the lines becoming hot spots and increase area dose and personnel esposure. The _l safety evaluation concluded that this modification did not Involve changes to the UFSAR or Technical Specifications and i the margin of safety'is not reduced. M01-2-88-001 This modification replaced the' existing 250 volt Division 1
- Battery (2DC01E) and rack. It also revised the current' monitoring instrumentation for the battery and_its associated i charger. The safety evaluation concluded that this modification will not affect or add to any accident analysis as i described in the UFSAR, but it increases the margin of safety
- due to the batteries greater capacity than before.
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, E. LICENSEE EVENT REPORTS (U2it 2) . , , LER MumbtI Date Description 90-010-00 09/12/90 .30 Day-Reactor Scram During Sury Testing !
F. DATA TABULATIONS (Unit 2)
- 1. Operating Data Report.
(See Table 3)
- 2. Average Daily Unit Power Level.
(See Table 4) ,
- 3. Unit Shutdowns and Significant Power Reductions. ,
(See Table 5) , t i f s
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E i?' < D.11 OPERATIC DATA REPORT.'. DOCKET C. 65F374:.
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'4 .
, UNIT LAGALLE TWO DATE DC10BER 10, 1990 ,
COMPLETED BY M.J.'CIAlt0WSKI l
-TELEPHONE (815) 357 6761_-.
OPEAAi!E 6'ATUS
~ .
i tl.. REPORT!NG PERIDDi BEP1EMbERI990 : GROSS HOURS IN REPDRilNG PERIOD: 729
~
2.. CURRENTLT AUTHORITED POWER LEVEL (tWth 3.323 .1,036
>i :heXKPENDCAPACITT(HWeht)fKSIG -1,070' t
,c -
a ._ . 3.l POWER LEVEL 10 WHICH RESTRICIED (IF ANY) (MWe W I): (NONE) < pa
- 4. REASONS FOR RESTRICT 10N (!F AND : (N/A) .
- REPORTIE PERIOD DATA - :. ;
THIS MONTH - YEAR-fD-DATE. zCtMULATIVE' e
~,
- 5. REACf0R Crit! CAL I!ME (H3URS)- , 523.01 4;230.1 '34,377.2
- 6. REACTOR RESERVE SHU1DOWN ilhE (HOURS) 0.0 ' O.0 > "1,71s.9 P
-t
- 7. GENERATOR ON-LINE TIME (HOURS) 502.4 . 4,091.6 : 33,774.7 ,
. 0
- 8. UNIT PESERVE SHU1DOWN TIME (HOURS)' l 0.0 : 0.0 .10.0: .'
V. THERNAL ENE K Y GENERATED (MWHil 1,543,824 12,544,535.2L 090,866,583.2' . r - . t
- 10. ELECTRICAL ENfRGY GENERATED (HWHe-Gross)'. .512,422i 4,195.944- 32,646,870- 4 c
11.ELECTRICALENERGiGENERATED(MWHeNet) >491,885: 4.020,495 3I.255,000
.j:
- 12. REACIDR SERVICE FAC10R I U 72.6.
64.6. ; 65.9 '! l
- 13. REACTOR AVAILABILITY Fact 0R (D 72.6i 64.6- . 69.2 : 3
- 14. UNii SERVICE FAC10R (!) 69.8 J -62.5 L 64.? ? _
i15. UNIT AVAILIBILITT FACTOR (%) : 69.9 ' '62.5 < l64.7.- ] l-; Ll6. (21T CAPACITY FACTOR (USING 2 C) (D : 65.9 59.2 - 57.8- j y
- 17. UNIT CAPACITT FACICR (USING DE$1GN L'e) (1) 63.4' 56.9 : ' 55.6 :
- 18. C11 FORCED OUTAGE FAC10R (%). ,
li i 29.9 7.? ' 15.4' i s
- 19. SHUTPOWNS SCHEDULED DVEA ilt Eli 6'MGNTHS (itFE, DATE; AC DURATION OF EACH)i .
j (NO.NE);
'~
j L 20. lf Diu1DOWM:AT.END OF REFORT PERIOD, ESilMATID DATE OF STARTUP:
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' WTE OCTOIER il,1996; '% '
{p.y :4 x g , iCOMFtETED M EL CMit0W9th 9-4 J - a f
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TABLE 5 . D.3 UNIT SEUTDOWNS AND POWER REDUCTIONS >20% (UNIT 2) N METHOD OF CORRECTIVE YEARLY TIPE SEUTTING.DOWN ACTIONS /COpetENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR S if NUMBER (YTie(DD) S: SCHEDULED (HOURS) REASON REDUCING POWER applicable) 12 900912 F 214.6 A 3 Failure of 2E Main Power Transformer Differential Current Relay (Unknown causes) 13 900921 S 1.8' B 4 Continuation of Previous Outage for OAD Testing.
SUMMARY
OF OPERATION: The Unit remained on linir at high power from 09/01/90 to 09/12/90.and from 09/21/90 to 09/30/90. Several minor power reductions were required due.to low grid demand and routine surveillances. The Unit experienced a forced outage on 9/12/90 and was returned to service on 09/21/90.. The unit scram was initiated by a trip of.the 2E main power transformer due to a differential current signal. Continuation of the outage was due to testing performed by OAD. ZCADTS/7
o l .e G.
.. .A UNIQUE REPORTIIG REQUIREMENTS'(Unit 2)
.* 1. Safety / Relief Valve Operations s
VALVES NO & TYPE PLANT DESCRIPTION DAIE AC211ATID ACTUATIONS CNDITIN OF EVENT 9/12/90 2B21-r013U~ MANUAL 1- SCRAM 9/12/90 2B21-r013S MANUAL 1 SCRAM 9/12/90 2B21-F013K MANUAL 1 SCRAM 9/12/90 2B21-T013E MANUAL 1 SCRAM 9/12/90 2B21-F013D MANUAL 1 SCRAM
- 2. ECCS System Outages (See Table 6)
- 3. Changes to the Off-Site Dose Calculation Manual.
(None).
- 4. Major changes to Radioactive Waste Treatment _ Systems.
(See Unit 1 report))
- 5. Indications of ralled ruel Elements.
(Hone) l 1 ZCADTS/7
I E,' .. ' o ** . 16 ' ' . , en '(Unit 2)..
.o, g T2blo 6'
.'=
ECCS System. Outages Note: The year ~and' unit data has been removed from the outage number. OUTAGE NO. EQUIPMENT PURPOSE
'1622 2E51-C005 Replace Motor Space Heater 1624 2E51-C004 Perform Surveillance LES-DC-104 1625 2DG08CA Check Hold-Down Screws 1626 RCIC Turbine Replace Oil and'F11ters.
1627 RCIC Turbine- Inspect Governor' Valve 1670 2E51-C004 Repair 74 Relay 1685 2E51-C003 Inspect riow Orifice 1687 2E31-N028A Tech., Spec. 3.2.2 Compliance i 1693 2A D/G Adjust Overspeed Trip Circuit 1694 2E12-C002C Lubricate Motor Bearing 1701' 2VYO2C Lubricate Motor Bearing 1702 2E22-C003 . Lubricate Motor Bearing ZCADTS/7}}