ML20059J144

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Monthly Operating Repts for Aug 1990 for Dresden Nuclear Power Station Units 1,2 & 3
ML20059J144
Person / Time
Site: Dresden  
Issue date: 08/31/1990
From: Eenigenburg E, Maxwell D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-611, NUDOCS 9009190190
Download: ML20059J144 (27)
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Text

{{#Wiki_filter:.... _.... _ _ _ _ ~~ OOfn M MISOR s o o.3 uni. p w stat n f RA #1 ~ ~ ' Morris, Illinois 00480 Telephone B15/942-2920 September 1, 1990 EDE LTR: #90-611 Director, Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk Siioject: Monthly Operating Data Report Dresden Nuclear Power Station Comunonwealth Edison Company Docket Nos. 50-010. 50-237. and 50-249 Gentlemen: Enclosed is the Dresden Nuclear Power Station Monthlv Oneratine Si-a ry = Ragu:1 for August,1990. This information is supplied to your office in accordance with the instructions set forth in Regulatory Guide 1.16. Please note that the report contains information which had been previously submitted to your attention on an annual basis in accordance with 10CFR50.59. Sincerely. E. D. Eenigenburg Station Manager Dresden Nuclear Power Station EDEtGP jws Enclosure ec: U.S. NRC Region III Office Illinois Dept. of Nuclear Safety, State of Illinois U.S. NRC, Document Management Branch Nuclear Licensing Administrator Vice Pres. - BWR Operations General Manager - Nuclear Services T. S. ENGR. (2) MRC Senior Resident Inspector l Nuclear Quality Programs - Dresden Nucleer Engineering Manager Comptroller's Office D. Eggett - Reliability Programs INPO Records Center File /NRC Op. Data C y ' J File / Numerical Z16/10/1 0009190190 poos3; PDR ADOCK 0500001o R PDC r62+

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e 4-- m gy e e -1.0 introdnetian 2.0 Ba=ma*, of onerate.. awneriene. 2.1 Unit 2 Monthly Operating Experience Susanary for August,- 1990 1 2.2 Unit'3 Monthly. Operating Experience Susanary for August, 1990 3.0 ooerattaa nata'statiatles 3.1 Monthly Operating. Data Report - Unit 2: 3.2 Monthly operating Data Report.. Unit 3 3.3 AverageLDaily Power Level Data - Unit 2 3.4 Average Daily Power *14 vel. Data -. Unit 3. ~3.5 Unit Shutdown and Power. Reduction Data - Unit--2 'l 3.6 Unit Shutdown and Power.. Reduction Data'- Unit 3 3.7 Station Maximum Daily. lead Data j[ 4.0 tinione namort4== Ranui. tm .j 4.1 Main' Steam Relief and/or Safety Valve Operations Unit 2 and. Unit'3'. i 4.2 Off-Site Dose Calculation' Manual' Changes j 4.3 Major l changes to the Radioactive Waste Treatment. 4.4-. Failed Fuel Element: Indications'- 4.4.1 Unit 2 4'.4.2 Unit 3 5.0 Plant er Procedure t'haneas. Testa. Exner 4mmnta. and Enf atv Related Maintenance ll 5.1 Amendments to Facility License or Technical Specifications: 5.1.1 ' Unit' 2, 5.1.2 Unit ~3 5.2 Changes to Procedures Which'are Described in the Final-Safety-j Analysis Report (F8AR)L(Unitsi2 and 3) 5.3 Significant Tests and Experimente Not Described in the FSAR-j (Units 2'and 3) j 5.4 Safety Related Maintenancei(Units 2 and 3)- i 5.5 Completed Safety Related Modifications-5.6 Temporary System' Alterations 5.6.1 Unit 2 5.6.2 Unit 3 - I 1.3 'I - t 4 5 216/10/3. F l 3

g i{. n'- .n y 1,0 latrdluation j". Dresden Nuclear Power Station is a;three! reactor. generating facility' = owned' and operated. by th, Commonwealth Edison Ocepany of Chicago',. -1111acia. -Dresden Station is located'at.the' confluence of the Kankakee p., and Des Plaines Rivers, in Grundy County -near Morris, Illinois. Dresden Unit l'is a General Electric. Boiling Water Reactor with a design; not electrical output rating of 200 megawatts electrical:(We). The unit is retired in place with all nuclear fuel' removed from the reactor; ~ vessel. Therefore, no Unit 1 operating dat'a is provided in this report. e Dresden Units-2 and 3 are General Electric Boiling Water Reactors with ' design not electrical' output ratings of 794' W e each. Waste heat is rejected to'a een-eade cooling lake using the Kankakee q River for make-up andithe' Illinois River for blowdown. The Architect-Engineer for' Dresden.Unita 2 and 3 was Sargent and Lundy of, Chicago, Illinois.- q 1 ll This rt,wrt was compiled by Donald C. Maxwell of the Dresden Technical - Staff, telephone number _(815)942-2920 extension 2489.< t I -i .l i J t 4 i i 'i Z16/10/4 i

y l - C 200 atsel&RY OF OPERATING ERIENCE FqS AUGUST, 1990 g =2.1 WIT 2 Holr!ELY OPERATING EKPERIENCE StR9tARY l j -l l. 08-01-90 to 08-06-90 -' The Unit en'tersd'.the mor.th on-line and operating- ~ L[ l at 650 W e'andlin normal operation.' on_Auguet 2;_ <1 L 1990 0 0105 ' ~--' the Main steam Target. Rock. H Safety.- Reli=&.41ve.2-203-3A 2;;- Sic' monitor: 'i alarmed indicating-that the valve had~ spuriously. l opened.. After attempts:to close the Target Rock valve failed the Reactor was manually scrammed at_ q 0116 hours perJ8tation procedures. After thorough:. investigations and replacement of the. j l Target Rock valve was completed; the. unit ~was- -) l' ready for startup. 08-07-90 to 08-31-90 The Reactor.was made critical 8-7-90 at 1025 hours ' and; the Turbine was brought on-line _at 2341. hours of the_same day. _The unit' steadily. increased loads through 8-9-90 and operated the-remainder of the month in Economic Operation-Control'or'at. loads; requested by the System Load , Dispatcher with an availability of.80.9% and at

capacity factor of 63.3%.
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fHRfMRIM_DERBATIIHl.5EP.ER2D10E_BldULUGuttbl990 n . g. . 1.2 UNIT 3 9000lTELY OPERATDIG EXPERIDICE SUB8EiltY. +- 08-01-90 to~08-31-90 Unitl3. entered,thesonth'on-lineandoperating ' at 615 99fe. : The unit operated'the entire month - in Economic' Generation control ^or at loads- ^ requested by the System lead Dispatcherf with:

an. availability-of.100% and a capoeity factor.

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m._ 3.0_ OPERATING MTA REPORT- ~ 3.1.0PERATING. DATA REPORT - UNIT TWO DOCKET N0. 050-237 I [; DATE-Empt==har 1. 1990 l' COMPLETED BY D. c. Maxwell TELEPHWE R15/942-2920 OPERATING STATUS 1. REPORTING PERIOD: AUGUST. 1990 GROSS HCURS IN REPORTING PERIOD-748' i 3 CURRENTLY AUTHORIZED POWER' LEVEL (MWe): 2,527. MAX DEPEND CAPACITY (MWe-Net) 772 DESIGN ELECTRICAL RATING:(MWe-Net) 794 -{ i 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A l 4. REASONS FOR RESTRICTIONS (IF ANY): ~ N/A L{ REPORTING PERIOD DATA This Month Yr-to-Date-Cumulative 5. TIME REACTOR CRITICAL (HOURS) 614.9 5,429.5' 136,209.7 6. TIME REACTOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0-7. TIME GENERATOR ON-LINE (HOURS) 601.6 5,392.3 130,443.8 8. TIME GENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0: 0.0-9. THERMAL ENERGY GENERATED (MWHt-GROSS) 1,229,425-12,492,210-270,609,401 10. ELECTRICAL ENERGY GENERATED (MWHe GROSS) 392,436 3.995,748 86,496,097 11. ELECTRICAL ENERGY GENERATED (MWHe-NET) 369,987_ 3,802,003-- _81,790.167 12. REACTOR-SERVICE FACTOR (1) 82.6 93.11 76.5 13. REACTOR AVAILABILITY FACTOR (1) 82.6 93.1 76.5 14. SERVICE FACTOR (%) 80.9 92.5-73.3 15. AVAILABILITY FACTOR 80.9 92.5-173.3-1" 16. CAPACITY FACTOR (USING MDC) (1) -64.4 84.5' 59.5-17. CAPACITY FACTOR (USING DESIGN MWe) (1) 62.6 82.1 57.9 j l 18. FORCED OUTAGE FACTOR (%) ~ 19.1 7.5 10.71 1 19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE DATE AND DURATION OF EACH) p REFUELING OUTAGE CURRENTLY SCHEDULED for 9-23-90 thru 12-04-90 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED.DATE OF;STARTUP-N/A .l l 216/10/6 [

3.0 OPERATING MTA REPORT 3.2 OPERATING DATA REPORT - UNIT TERRE DOCERT NO.- 050-149 .DATE Banta=her 1. 1990 COMPLETED BY D.c. b uwell TFLEPHONE '815/962-2920 OPERATING STATUS 1. REPORTING PERIOD -AUGUST. 1990 GROSS BOURS-IN REPORTING PERIOD 7 2. CURRENT 1X AUTHORIEED PCWER LEVEL (We):- 2,527 MAK DEPEND CAPACITY (We-Net) ? DESIGN ELECTRICAL RATING (MWe-Net) 7 l 3. POWER LEVEL TO WHICE RESTRICTED (IF ANY) (MWe-Net): N/A )!. 4. REASONS FOR RESTRICTIONS (IF ANY): N/A REPORTING PERIOD DATA bisMonth Yr-to-Date- ' Cumulative-5. TIME REACTOR CRITICAL (HOURS) 744'.0 4,561.8 -124,796.2' 6. TIME REACTOR RESERVE SHUTDOWN (BOURS) 0.0 0.0 0.0 7. TIME GENERATOR ON-LINE (HOURS) 744.0 4,406.3 116,768.5-8. TIME GENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0 9. THERMAL ENERGY GENERATED (MWHt-GROSS) 1,786,432 10,288,851 241,916,271 10. ELECTRICAL ENERGY GENERATED (MWHe GROSS) 574,480 3,323,829 78,036,074 11. ELECTRICAL ENERGY GENERATED (MWHe-NET) 546,183 3,160.095 74,015,465 4 12. REACTOR SERVICE FACTOR (%) 100.0 78.2-74.5 13. REACTOR AVAILABILITY FACTOR (%) 100.0 78.2 74.5 14. SERVICE FACTOR (1) 100.0 75.6 .69.7 15. AVAILABILITY FACTOR 100.0 75.6 69.7 16. CAPACITY FACTOR (UEING MDC) (1) 95.0 70.1 57.1 17. CAPACITY FACTOR (USING DESIGN MWe) (%) 92.5 68.3 55.6 18. FORCED OUTAGE FACTOP (1) 0.0 6.4 11.9 l 19. SHUTDOWNS SCHEDULED OVER THE NEKT 6 MONTHS (TYPE DATE AND DURATION OF EACH) NONE i 20. IF SHUTDOWN AT END OF. REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A Zi6/10/8

)! /t 4 303 AVERAGE MILY IMIT POWER IMEL ~ 1 DOCKET No, 050-237 UNIT II MTE sent 'ar 1. 1920 ' C(DIPLETED BY D.c. Mawail-TELEPHONE B15/942-1920 l MONTil AUGUST. 1990 DAY AVERAGE DAILY POWER LEVEL. DAY-AVERAGE DAILY POWER IJNEL (MWe-Net)- (We-Net) i 1 623-

17 614

- 2.' 27 18; '593 .3 0 19 614-4 0 20 630-5 0-21 638 6. 0 22 '624 7 0 23-604 8 599 24 591 9 64B 25 - 554' 1 I 10 674 26 579-( 11 660 27 619 12, _. 629 28 620' t 13 640 29~ 611" 14 659 30 :- 573 L 15 ^ _. 656 31 569 16 643 l l l 216/10/9 = ,o _L,, _,, _ _ _. _.,.

,i t c... - 3.4 = AVERAGE MILY lEf1T POWER LEVEL j s.. j DOC U T NO."050-249 4 1911T - III ' ' ~ ' MTE sentaar 1.'1990 COMPLETED BY D'.c. hwell l - TELEPB(NIE 8151942-1920~ j I l MONTVI i._ AUGUST. 1990 ,l MY ' LAVERACE MILY POWER LEVEL MY - AVERAGE MILY POWER LEVEL 9 i. -(MWe-Net)

(MWe-Met)

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DOCHT 100. 050-237 UNIT NAME DRESDEN~tntIT II 3.5 UNIT SHUTDOWNS AND POWER A mUCTIONS DATE 3ent 1. 1990 COMPLETED BY D. C. h 11 TELEPHONE M15)962-2920 REPORT MONTH _ AUGUST-1990 CAUSE & CORRECTIVE METHOD OF LICENSEE SYSTEg 3 2 NO. DATE TYPE' DURATION REASON SHUTTING EVENT CODE ACTION TO (HOURS). DOWN REACTOR REPORT # PRETENT RECUEF.EIOCE 142.4 3 08 42-'90 F (142:25) A 2 90-006-0 SB RB Spurious opening of-the 2-203-3A target rock valve. After'the valve was replaced.. Unit 2 returned to service. iV 1 .1 2 3 4 F: Forced Reason:. Method: Exhibit G-Instrections for S: Scheduledi A-Equipment Failure-(Explain) .1-Manual Preparation of Data -B-Maintenance'or Test-' 2-Manual Scram Entry Sheets for Licensee C-Refueling-3-Automatic'Scrac. Event Report (LER) File D-Regulatory Restriction 4-Other (Explain) (NUREC-0161) E-Operator Training & Licensee Ermeination 5-Imad Reduction -F-Administrative 5 Exhibit I - Same Source G-Operational Error ZR16/10 H-Other (Explain) =.. ,,............ _ = -., _..... - _. - -...... _... i _. ... c_

DOCKET NO. 050-249. UNIT MAME DRESDEN tlRIT III 3.6 UNIT SHUTDOWNS AND POWER REDUCTIONS DATE Ser,t 1. 1990*- COMPLETED BY D. C. h 11~ TELEPRONE fR15)M2-1928 ~ REPORT MONTE ADCUST 1. 1990 METHOD OF LICENSEE- -SYSTg CAUSE & CORRBCTIVE i - NO. DATE TYPE DURATION REASON SHUTTING EVENT CODE ACTION 10 I (HOURS) DOWN REACTOR REPORT # FREVENT RECURRENCE 1 NONE ~ 1 f r . N 2.1, s; i 2 3' - 4 F: Forced. ReasonE Method: ~ Exhibit G-Instructions for- ~ . Si Scheduled - A-EquipmentiFailure-(Explain) ~ 1-4tennal;- Preparation'of Datai B-Maintenance or. Test- ~

2-41anual Screat f

- Entry Sheets for Licensee C-Refueling.. '~~ l _

4-OtherL. (Esplain).

^ ~ 3-Automatic Scram' Event Report (IAR); File D-Regulatory Restriction (NUREG-0161) + 'E-Operator Training'& Licensee Examination 5-Imed Reduction. 1 2 l i.' - - 1F-Administrative H ~ G-OperationaliError~ 5 EmMbit I - Same Source ~., ~ , ; r, n - ,, m. : in.., a; g ,p.., +*' we , _ + h g -+ g e .ryi e m s =-___.y__, .,a 'J' mc+w --y, -*hq' (g mt ,d-3 y' -yg .*%*-[-N5." M- ,*w. N*..r%ne g a.n+' g-4gg*g:_--s..-W 3,ng Ag*%- 4" %

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MAXDRM MILY EIACTRICAL 14AD PORM
FOR TRE MOBITE OF' AUGUST 19901 BOUR MAKINUM MILY LOAD gy ENDING

.EN 1-1200 ~1458.400 2- -0100 13RR.600 ' 3 OA00 808.900 1500' 804.100-5- '0700 902.500 6 1200 806.100 1 _ 2400' '832.800' i 8 M D-1.557.300 9 2200 1.510i200 ~ 10 0600 1.511.900' 11-1800 1.500.300-12 0300 '1.469m600 13 2200 1.514.800: 14-0900 -1'510.300 125032400' 15' 0300-L q 16 0100 1.486.500 17 0800 1'.431.9b0 = i 18 2200 1.489.800 d 19 1700' 1.6h3.600'- 20 2100 -1.489I900' 21-0100 1.486.400 "1 22 2100 1.459.500 l 23 0100 l'.453.700 i 24 1100 1.431'.900 .{ 25 0100-1.393;300

l 26 1200 1.390.800 27 1400 1.475.200 28 0200 i.457.900' 29-0900 1.454.000' 30 1600 1.401.600

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+ 4.0 WIOUR kap 0RfD8G RIQlti MNTS 4.1 MAIN STRAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period August, 1990, are summarised in the following table.. The table includes information as to which relief valve was actuated, how it was actuated, and.the circumstances resulting in its actuation. No, and Type Valvaa of 'Plent 8mmeriptien limit Data Actuated Agtuatiena canditigma af Evunte 2 08-02-90 203-3A 1 Rua N de Unit 2 safety / relief valve 2-203-3A lifted E-i sput ously. :See L.E.R. 90-006-0,. 3 No Unit 3 Main Steam Relief and/or safety valve actuations occurred during this reporting period. E. 4.2 0FF-81TE DOSE CALCU!ATION MANUAL (ODC34) CEANGES ' No 0DW changes were reported for the month of August, 1990. 4.3 MAJOR CHANGES TV THE RADIDACTIVE PA5TE TREA7 MENT ST8TEMS The Radweste upgrade continues and tiring August,1990 the unit 2 Fuel Fool Filter Outlet Line 2-1909-6" was replaced:in eleven working day 0. This included approximately forty feet of schedule 40 stainless steel 6" piping and five field welds in the 1/3'Radweste Tank Room. T,ie two and one-half week time frame originally scheduled was critical because the Unit 2 Fuel Pool Filter and Domineraliser were out-eI-servict during the pipe replacement. Total man-rem expended by the worksrs was approximately 4.5. The Unit 3 Fuel Pool Filter inlet and Outlet piping will-be replaced in October 1990 and the Unit 2 Fuel tool Filter piping will be replaced, after the upcoming Refuei Outage. M ER16/10/14 Mr ~~

4.4 -FA11N PUBL BlaEDff 2ND10AT!cNg 4.4.1 Unit 8 Dresden Unit 2 fuel' performance'euring August,1990 continu*d to show no indications of: leaking fuel. This is based on the_se os the-activities of the sia noble gases as measured at the recombiner. Based on the reported data Unit 2 had acceptable fuel performance. 4.4.2 Unit 3 Dresden Unit 3 fuel performance during August, 1990 conEinued to show no indications of leaking fuel. This is based on the s e of the activities of the sin noble gases as measured at the recombiner. Based on the reported 6ata. Unit 3 had acceptable fuel performance. 5.0 PIANT OR PqtocRf1HLK CRANGER. TRSTR. ERP5ptpaarfs, AMD RAFRTY RRIATED numramanca 5.1 Amendments to Facility License or Technical Specificatic,ns 5.1.1. Unit 2 Amendment #112, Dated July 31, 1990 he NRC has approved Technical Specification Amendment #112 for Unit 2. his amendment excludes the Reactor Building Closed Cooling Water inlet pathway to the primary containment from Appendia J. Type C: leak ra.. testing requirements until the next refueling outage. A temporary waiver by compliance was approved orally on July 20, 1990 and in: writing on July 24, 1990. The waiver allowed the NRC 8tatf sufficient time to process the emergency technical specification amendment submittal by July 31, 1990. 1 1 5.1.1. Unit 3 Amendment #108 DetM July 31.,1990 The NRC has approved Technical Specification Amendment #108 for Unit 3. This amor.dment excludes the Reactor Building Closed Cooling Water inlet pathway to the primary containment from Appendia'J Type C leak i rate testing requirements until the next refueling outage. _A temporary waiver by compliance was approved orally on July 20, 1990 and in-writing on July 24, 1990. The waiver allowed the NRC 8taff sufficient time to process the emergency technical specification amendment submittal of July 31, 1990. 5.2 Changes to Procedures Which are Described in the FSAR (Units 2. and 3) Table 5.2.1, attached, sunenarises the revisions to proccAures described in the FSAR which were approved during the August,1990 reporting period. i b 2,R16/10/15 l

I id lii l e T = = 5.2.1 CHANGES TO PROCEDURES WICE ARE DESCRIBED IN TBE F5AR (UNITS 2 AIW 3) FUR MpCus?,1990 FROCEDURE TYFE FROCEDURE NO. PROCEDURE TITIA/ DESCRIPTION SENWOARY OF c -== Dresden Administrative DAF 07-45 Operating Imss And Records Procedure Dresden Administrative D4F 12 44 Control of High and Eigh-Eigh. 3 Radiation Areas Procedure NOTES: 1. Administrative change; intent of procedure unchanged. 2. Changed for clarifi:4 tion, latest of procedure unchanged. Changed to incorporate requirements for now equipment; inteet of procedure m ehenged 3. Changed to implement improved testing / calibration asethodology; inteet of y.+: _ __, unchanged. 4. 2R16/10/16'

I. .a 5 3 Signitscant tests and emperimmate met described is the ptAR (Units 1 + g 3). Significant special procedures involving tests set deeeribed in the FSAR which were approved durier the scath of August, 1990 ese listed below. Procedura Me. Pencaduce Titia/ weristiam. V 0 4-07-92 Bydrogen Water Chemistry Verification Systea Bydrostatic Test / .he purpose of this. procedure 15 to identify the location of any blockage, and to clear this blockage, in the Bydrogen Water Chemistry Verification System (WWCV8) sample inlet and outlet lines. 8P-90-08-93 U-2/3 Clean Dominere11 sed Water Line Inspection e The purpose of this procedure is t provide a means to perfoss a boroscope inspection on the Unit 2/3 Clean Dominera11 sed Water Pump suction line. a SP-90-08-95 Modification M11-1/3-86-6Dt Test / Inspection of-Unit 2 Rattery Room 8yewash Drain Reroute and Battery Room Drain Line Removal. + The purpose of this procedure is to verify proper operation of the Unit 1 125/250V Battery Room j area eyewash drain'line. SP-90-08-96 Unit 3 Righ Pressure Coolant Injection (EPCI) 1 Flow Calibration. The purpose.of this procedure is to provide-instructions to calibrate the BPCI Pump Flow Transmitter FT-3-2358 and supporting instruments. Computer Point Insulator 943-112, Flow Indicating-Controller FIC-3-2340-1 and Flow switch FS-3-2354 (low and high flow switch). SF-90-08-97 Modification Test for Mit-2/3-87-05Al 8 teel Beam Below Unit 1 Control Room' The purpose of this procedure is to verify that the steel 'oeam has been installed to and conforms with the latest approved-for-construction-drev uss, installation specifications, and procedures. h is. procedure verifles proper i re-support of interferences that were temporarily supported or relocated, and_ verifies proper removal of cable tray. sections. 116/10/17 l

W .[~ '3 87-90-08-98 tighpressureCoolietIcjecties(BPCI) Area Ym.wroture Dwitah Calibraties and Malatenanco Inspecties.- The purpose of this pa. odure is to proviwe instructions to assure taquired environmental qualification (BQ) mautenance inspection and consistant performance in calibration of the MPCI Area Righ Temperature Switches. SP-90-08-100 Drywell Imak Detector System Temperature Recorders Calibration and Msti, Safety, Safety /Aelief Valve, and Drywell atmosphere Temperature Thermocouple Functional Test. The purpose of'this procedure is to provide instructions to_ calibrate Drywell Leak Detector ' Temperature Recorder (TR) 2(3)-160-20A and -20B; and to functionally test the M8IV Pilot, Safety, safety / Relief Valves, and Daywell Atmosphere . Temperature Thermocouples.: 8F-90-08-102 Drywell Radiation Monitor Modification Test M12-2-88-46 The purpose of this~procedt. is to test and verify that after implementasson of Modification-M12-2-88-46, when power is lost to either_the 2419A or 24198 Radiation Monitor, proper relay i de-energisation'has occurred will be performed. 5.4 Safety Related Maintenance (Unit 2 and 3) Safety related maintenance activities for August, 1990 are summarised in the attached tables. D.5 Completed Safety Related Modifications'(Units.2 and 3). There were no safet) related modification packages closed during the month of August,1990. 216/10/18 v )

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. _ _ _ __ _ _..._ _ _ _ _ ___ _.___ _ __.. _ _ _~. _ 5.6 Tempor:ry System Alter tions'(Unit 2 and Unit 3) inst:11ed during '/ August, 1990 A " Temporary System Alteration" refers to electrical jumpers, lifted leads, removed fuses, fuses turned to non-conducting position, fuses moved from normal to reserve holder, temporary power supplies, test switches in alternate posit As, temporary blank flanges _and spool pieces. Alterations contre 4ed and documented as part of a routine out-of-service or other procedure, alterations which are a normal feature of system design, and hoses installed as part of a venting or-draining process are not included. j 5.6.1 Unit 2 J J None. i 1 5.6.2 Unit 3 j ) Temporary System Insta11stion' Removal' Alteration No. Description Dain Date l III-17-90 This alteration relocates WR D93835 the particulate:and iodine - i j & filter cartridges from sample point 15 to semple-l point 25. This allows the sample to be taken from a i line which has a Group II j Isolation Valve upstream. ] 111-18-90 This alteration disconnects WR D94189. 11/16/90 the' existing sample header from a sample panel and 'n-stalls header near noir',ure separator sample station. i 'l -I 3 ? 6 216/10/19 l 3 + J.~. ., --,-.,.... _ ;..... ~.-..,r ..C.l -}}

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