ML20058H291

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Monthly Operating Repts for Dresden Nuclear Power Station for Oct 1990
ML20058H291
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 10/31/1990
From: Eenigenburg E, Maxwell D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
90-724, NUDOCS 9011150136
Download: ML20058H291 (40)
v • d • e


Text

{{#Wiki_filter:._ J. [_N Comm:nwealth Edison. >j e (*- O

/ Dresd
n Nuclear Pow:r Statlinf i

O< RR' #1 : L\\ Morris, Illinois 60450 k

Telephone 815/942-2920

,j ' November 7, 1990? EDE LTR: #90-724-Director, Nuclear Reactor Regulation - United States Nuclear Regulatory Commission-Washington, DC .20555 Attention:- Document Control Desk.

Subject:

Monthly Operating Data Report .Dresden Nuclear Power Station Commonwealth Edison Company: Docket Nos. 50-010. 50-237; and 50-249 Gentlemen: Enclosed is the Dnaden Nuclear _four Station _ Month 1v Opsratina Summary. RepAI.t for October, 1990. This information is supplied to your office;in accordance with the instructions set forthlin' Regulatory _ Guide-1.16.' Please note that the report contains information which had been: . previously submitted to your attention on.an annut.1' basis 'in accordance'_- with 100FR50.59. Sincerely, c6y-E.D.Eerkebu" Station Nan ger Dresden Nuclear Power Station EDC:DM:ala Enclosure ec: U.S. NRC Region III Office Illinois Dept. of Nuclear Safety,: State of" Illinois U.S. NRC, Document Management Branchl Nuclear Licensing' Administrator Vice Pres. - BWR Operations-1- General. Manager - Nuclear' Services T. S. ENGR.-(2) NRC Senior Re'sident Inspector. Nuclear Quality' Programs-- Dresden= Nuclear Engineering Manager Comptro11er's Office-D.'Eggett - Reliability Programs INP0' Records Center Fi'le/NRC Op. Data File / Numerical ZEDE/445 9011150136 901031 fj ADOCKOS00g0 .PDR R { .c<

~ t - C i l l j 1 MGmILY NRC .1 SW9tARY OF OPERATING EEPERIENCE, CHANGES, TESTS. AND. EXPERIMENTS 1 PER REGUIA'IDRY CUIDE l.16 AND 10 CFR 50.59 m-j ERESDEELEELEAR POWER STAT 1Gi' CG993RfEALTH EDIBGt CGIPANY BHL,Qataber.1920 i . s. lit {ll

DOCKET

' LICEaiSE y 1 050-010 DPR-2 S d 2 050-237 'DPR-19 i o 3 050-249 -DPR-25 i i f i ? I 1 i ) ZR18/643/1 l 1 l .. J. .V

'? l 4 - .i 7 .4 't IABLE OF CONTENTS 'l s 1.0 Introductinn; t 2.0 Eummarv of operatina Experience l l 2.1 Unit'2 Monthly' Operating Experience Summary ~for October, 1990 i L 2.2 Unit 3 Monthly Operating Experience Summary.for October, 1990- 'I 3.0 Operating Data Statistics i 3.1 Monthly Operating Data Report - Unit ~2-l k l '3.2 Monthly Operating Data Report - Unit;3: 3.3 Average Daily-Power Level Data - Unit'2-3.4 Average Daily Power Level Data - Unit 3. ]; 3.5 Unit Shutdown and. Power Reduction Data - Unit 2 3.6. Unit Shutdown and Power Reduction. Data - Unit 3 ' 3.7 Station Maximum Daily' Load Data 4.0 Uniaue Reporting Reauirements 4.1 Main Steam Relief and/or Safety Valve Operations l Unit:2.and-Unit 3 4.2 Off-Site Dose Calculation ManualLChanges l 4.3 Major changes to the. Radioactive. Waste Treatment 4.4 Failed Fuel Element Indications. 4.4.1 Unit-2 4.4.2 Unit 3' 5.0 Elant_or_ Procedure Changes. Tests. Experiments. and Safety Related Maintenance .i L l 5.1 Amendments to Facility License oriTechnical Specifications' 5.1.1 Unit 2 i 5.1.2LUnit 3 5.2 Changes to Procedures Which are Described intthe Final Safety Analysis Report (FSAR) (Units 2 and 3) i 5.3 Significant Tests'and Experiments Not Described'in~the.FSAR-(Units-2-and 3) 5.4 Safety Related Maintenance (Units 2'and 3)' _3 5.5 Completed Safety Related Modifications: 5.6 Temporary System Alterations 5.6.1 Unit 2 5.6.2 Unit 3 ZR18/643/2 j L! ?

.a 1.0 Introduction o 4 Dresden Nuclear Power Station'is a three reactor generating facility-- [ owned and operated by the Commonwealth Edison Company of Chicago,t, Illinois. Creeden Station is located at the confluence of the Kankakee-and Des Plaines Rivers, in Grundy County, near Morris,' Illinois.- ] Dresden Unit 1 is a General Electric Boiling Water Reactor with'a designi I net electrical output rating of:200_ megawatts-electrical (MWe).- The unit.- zi is retired in place ~with all nuclear fuel removed from the reactor vessel. Therefore, no Unit 1 operating data is provided in this report. Dresden Units 2 and 3 are General Electric Boiling Water Reactors with~ design net electrical output ratings of 794_MWe each.- } Waste heat in_ rejected to a man-made cooling lake using the Kankakee-~ River for make-up and the Illinois River for blowdown.. l l .The Architect-Engineer for Dresden Units 2 and=3 was Sargent and Lundy.of. J Chicago, Illinois. This report was complied by Donald C. Maxwell of the Dresden Technical l Staf f, telephon'e number (815)942--2920' extension 2489 3 l 1 1 l l l .f l 1 t ZR18/643/3 1 1 4 .~ s b s c S+ f i

i; 2.0 SilttMRY OF OlglMTING EXPERI]2 ICE FOR OCTOBER; 1990 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE

SUMMARY

, t 10-01-90-to 10-31-90. Unit 2 remained off-line during the month of .0ctober for'its 12tb Refueling-Outage. Major. work during the.monthLincludedt. 1 .c ' Defueling = of: the Reactor. j PrimaryfContainment Local Leak Rate Testing - (LLRT). ; 'i In-Service Inspection (ISI) of various } Primary System Piping.. Replacement of;33 control Rod Drives. 3 Replacement,of.: Control Room Recorders (will1 j continue through mid-November).. l Diesel-Generator-Modifications and Testing.. t Normal Refueling ~ Outage ~related work.- 6 l l~ j A i o i I .i Fo k >i t i ZR18/643/4 .i s

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SilttMELDE _0PERATING TEXPERIENCE FOR' OCTOBER ~.1990 q

-2.2 UNIT'3 MONTHLY OPERATING EXPERIENCE

SUMMARY

't .t 10-01-90 to 10-31-90 Unit 3 entered the month.on-lin'e'!and operating' [ .at'768.MWe.; The Unit operated the entire month 1; in Economic Generation' Control or at41oads requested by th'e System Load Dispatcher, with an availability of.100% and a capacity l factor; of 93.6%.- . ) t i t -l t I [ 1 i I Y 4 i i Li e ZR18/643/5 e f

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.3.01 OPERATING' DATA REPORT; a 3.1 OPERATING DATA MPORT - UNIT 'IMO a DOCKET NO. 0501237-DATE November 1. 1990 ' COMPLETED BY D. C. Ms;gtf,J t .. TELEPHONE 815/942-2920 OPERATING STATUS 1. REPORTING PERIOD: OCTOBER. 1990 GROSS HOURS IN REPORTING PERIOD 1745

{

2. CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2.527 -MAX DEPEND CAPACITY (MWe-Net)1 772 DESIGN ELECTRICAL RATING (MWe-Net) 794; 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWei et): N/A N 4. REASONS FOR RESTRICTIONS-(IF-ANY):. N/A =i REPORTING PERIOD DATA-g This Month. Yr-to-Date Cumulative-5. TIME REAC't iR CRITICAL (HOURS) 0.0. 5;958.8 136,739.0 1' 6. TIME REACTOR RESERVE SHUTDOWN (HOURS)- 0.0' l0.0 0.0' 7. TIME GENERATOR ON-LINE (HOURS) .~ 0.0- -5,921.3 130,972.8' 8. TIME GENERATOR RESERVE SHUTDOWN (110URS)-

0. 0.-

0.0 . 0.0' 9. TilERMAL ENERGY GENERATED (MWHt-GROSS) 0.0-13,486,952 271,604,143 10. ELECTRICAL ENERGY GENERATED (MWHe GROSS) 0.0-4,311,428! 86,805,777 11. ELECTRICAL. ENERGY GENERATED (MWHe-NET) -5,991 4,092,137 82,080,301 12. REACTOR SERVICE FACTOR (%) 0.0 81'. 7. 76.2-13. REACTOR AVAILABILITY FACTOR-(%) 0.0 L81'7. ! 76. 2: 14. SERVICE FACTOR (%) 0;0 81.2 73.0-i

15. AVAILABILITY FACTOR

'O.0 -81.2: 73.0 l 16. CAPACITY FACTOR (USING MDC) (%) 0.0 '72.6 59.3 l l

17. CAPACITY FACTOR (USING DESIGN MWe) (%)

0.0-70.6' 57.6 l-18. FORCED OUTAGE FACTOR (%) 0.0 6.9-

10.7

'i 19. SilUTDOWNS SCHEDI.T 2 OVER THE NEXT 6 MONTHS (TYPE DATF AND 1/uRATION OF EACH)' f REFUELING OUTAGE CURRENTLY SCHEDULED through 12-04-90 j 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF,STARTUP l ) 12-04-90 T ZR18/643/1 l .a +f 0 n

3.0 OPERATING DATA REPORT 3.3 OPERATING DATA REPORT - UNIT TilREE DOCKET NO.__010-149 DATE __Novamher LEQ. COMPLETED BY. D.C. Maxwell TELEPHONE 815/942-2920 Ol'ERATING STATUS 1. REPORTING PERIOD: QCIQLER. 1990 GROSS HOURS IN REPORTING PERIOD 745 2. CURRENTLY AUTil0RIZED POWER LEVEL (MWth): 2.527 MAX DEPEND CAPACITY (MWe-Net) 773 DESIGN ELECTRICAL RATING (MWe-Net) 794 l 3. POWER LEVEL TO WilICH RESTRICTED (IF ANY) (MWe-Net): N/A 4. REASONS FOR RESTRICTIONS (IF ANY): N/A i REPORTING PERIOD DATA This Month Yr-to-Date Cumulative 5. TIME REACTOR CRITICAL (ll0URS) 745.0' 6,026.8 126,261.1 6. TIME REACTOR RESERVE SilVTDOWN (110URS) 0.0 0.0 0.0 7. TIME GENERATOR ON-LINE (IlOURS) 745.0 5,871.3 118,233.5 P. TIME GENERATOR RESERVE SilVTDOWN (Il00P.b) 0.0-0.0 0.0 9. TilERMAL ENERGY GENERATED (MWilt-GROSS) 1,799.435 13,771,618 245,399.038 10. ELECTRICAL ENERGY GENERATED (MWHe GROSS) 581,480 4,447,724 79,159,969 11. ELECTRICAL ENERGY GENERATED (MWile-NET) 559,963 4,235,702 75,091,072-12. REACTOR SERVICE FACTOR (%) 100.0 82.6 -74.7 13. REACTOR AVAILABILITY FACTOR (%) 100.0 82.6 74.7 14. SERVICE FACTOR (%) 100.0 80.5 70.0 i

15. AVAILABILITY FACTOR 100.0 80.5 70.0 16.

CAPACITY FACTOR (USING MDC) (%) 97.2 75.1 57.5 17. CAPACITY FACTOR (USING DESIGN MWe) (%) -94.7 73.1 56.0 18. FORCED OUTAGE FACTOR (%) 0.0 4.9 11.8 { i e 29. SIIUTDOWNS SCIIEDULED OVER TilF NEXT 6 MONTilS i (TYPE DATE AND DURATION OF EACll) Refuel Outage (D3R12) scheduled to begin March 31, 19914 scheduled for 10-weeks duration, j 30. IF SilUTDOWN AT END OF REPORT PERIOD, ESTIMATED DA1E OF STARTUP - N/A t ZR18/643/7 t

4 0 3.3 AVERAGE DAILY UNIT POWER'IEVIL-DOCKET NO.,_Q50-237 UNIT _L1 DATE Nov==her 1.1990 COMPLETED BY_D.C. Maxwell C LEP!!ONE 815/94L-2920 MONTil QCIQBIL._L930 DAY AVERAGE DAILY POWER LEVEL DAY ' AVERAGE DAILY POWER LEVEL' (MWe-Net) (MWe-Net) 1 0 17 .0 2 0 18 0 3 0 19 0 4 _0 20 0 d 5 0 21 0 6 0 22 0 7 0 23 0 f 8 0 24 0 u 9 0 25 0 10 0 26-0 11 0 27 0 12 0 28 0 l 13 0 29 0 14 0 30 0 15 0 31 0 16 0 I 1 l l ZR18/643/1 'l w

i 3.4 AEEAGE DAILY UNIT POWER LEVEL DOCf,ET NO.._QiD-249 UNIT III DATE.Novamher_1 1990 COMPLETED BY D.C. Marwall TELEPHONE _;_815/942-2920 MONTH __QQIQER.1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 784 17 776 2 782 18 786 3 781 19 759 4 722 20 749 75R._ 21 406 1 6 747 22 673 7 746 23 782 ) 8 765 24 765 9 781 25 780 10 785 26 758 i 11 769 '27 759 l 12 762 28 754 1 13 727 29 768 i 14 _774 30 761 15 772-31 752 16 771 I .} ZR18/643/2 l

DOCKET NO. 050-237 UNIT NAME DRESDEN UNIT II~ 3.5 UNIT dauuiGiiNS AND POWER _EEDUCTIONS DATE November 1. 1900 COMFLETED BY D. C. Maxwell TELEPHONE _{SJ5)942-2920 REPORT MONTH OCTOBER. 1900 METHOD OF LICENSEE SYSTEg COMF0 p CAUSE & CORRECTIVE 1 2 NO. DATE TYPE DURATION REASON SHUTTING EVENT CODE CODE ACTION TO (HOURS) DOWN REACTOR REPORT # PREVENT RECURRENCE 4 09-23-90 S 745.0 C 1 N/A N/A N/A Off-line through 12-4-90 for Unit 2's 12th Refueling outage. 1 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions for S: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data B-Maintenance or Test 2-Manual. Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Other (Explain) (NUREG-0161) E-Operator Training & Licensee Fr==ination 5-Load Reduction F-Administrative G-Operational Error 5 Exhibit I - Same Source ZR10/10/10 H-Other (Explain)

.~ DOCKET NO. 050-249 UNIT NAME _DIESDEN UNIT III 3.6 UNIT SHUTDOWNS AND POWER REDUCTIONS DATE Novesaber 1.1990 COMPLETED BY D. C. Maxwell ~ TELEPHONE (815)942-2920 REPORT MONTH OCTOBER. 1990 s METHOD OF LICENSEE SYSTEtt COMPONENT CAUSE & CORRECTIVE NO. DATE TYPE DURATION REASON SHUTTING EVENT CODE" CODE ACTION TO (HOURS) DOWN REACTOR REPORT # PREVENT RECURRENCE NONE 2 3 4 F: Forced-Reason: Method: Exhibit G-Instructions for S: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Other (Explain) (NUREG-0161) E-Operator Training & Licensee Framination 5-Load Reduction F-Administrative G-Operational Error 5 Exhibit I - Same Source ZR18/643/11' H-Other (Explain)

3.7 00ft10NWEALTH EDISON COMi%NY - DRESDEN NUCLFAR POWER STATION - MAXIMUM DAILY ELECTRICAL LOAD FORM FOR THE MONTH OF. OCTOBER,1990 OUR W IM W DAILY LOAD DAY ENDING KW 1 1100 810.400 2 2300 808.100 3 0100 807.600 4 1200 806.500 5 1100 790.609 6 1100 791.000 7 0100 790.100 8 . _ _220D___ 801,sQQ 9 __D800 808.800 .___11 170D 813.300 11 0100 8 R,700 12 1200 796.400 13 2300 811.100 I 14 0100 811,200 15 1400 810 800 i 16 1400_,,, 811',100 17 1Z00 8102100 18 2300 812.100 19 0900 8Q2.500 20 2000 791.200 l 21 2400 582.100 ( 22 1300 777.400 1-23 010Q_._ 812.700 24_ 2400 804.000 25 1ZQ0 812.000 26 1900 796.700 _ 27 ._ _D109 _ 795 100 l 28 0700 795.5.QQ 29 1200 B R.3.00 _ 30____ 01QQ_ _ 795.900 31 1500 795.300 ZR18/643/12 <j

\\~ 4.0 UNIQUE REPORTING REQUIREMENTS I 4.1 MAIN STEAM RELIEF VAI.VE OPERATIONS Relief valve operations during the reporting period, October, 1990, are summarized 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. J 2 No Unit 2 Main Steam Relief and/or Safety Valve actuations occurred during this reporting period. 3 No Unit 3 Main Steam Relief and/or Safety Valve actuations occurred during this reporting period. l 4.2 0FF-SITE DOSE CALCULATION MANUAL (ODCM) CilANGES No ODCM changes were reported for the month of October, 1990.

However, On-Site Review No. 90-21 was conducted, which will revise the ODCM to contain the Radiological Effluent Technical Specifications (RETS) in accordance with NRC Generic Letter 89-01.

The On-Site Review approved this change, along with the associated Technical Specification changes to delete RETS. Further, other minor changes to the ODCM were j approved. None of the changes will reduce the accuracy or reliability l of dose calculations or setpoint determinations. l .3 MAJOR CllANGES TO Tile RADIOACTIVE WASTE TREAINENT SYSTEMS during October 1990 The Radioactive Waste (RW) System Upgrade continues. During October, 1990, the Unit 2 Fuel Pool Filter (FPF) Outlet pipe and the Unit 3 FPF inlet pipe have been replaced. Currently, work is being done on the Unit 3 FPF Outlet piping replacement. _ The Unit 2 FPF Inlet piping is scheduled to be replaced during December, 1990. Transfer air piping for the RW Demineralizer Sparging Air to the RW I Sludge Tanks, and piping for the Service Air to the RW Headers have been replaced in the Tank Room over the last two months. 11.42 Man-Rem was expended for this work. For the remainder of 1990, work will begin on the two new Maximum Recyle Sample Sinks along with the FPF piping.. Also, there are some high-dose abandoned pipes in the South pipe tunnel that will be cut back about ten feet for ALARA considerations. In 1991, work will begin on installation of Equipment Drain and Floor l Drain Tank Room Inlet lleaders. This will be accomplished to facilitate the remaining pipe replacements in the RW Tank Room. !j i ZR18/643/13 I o

1 4.4 FAILED FUEL ELEMENT INDICATIONS 4.4.1 Unit 2 Dresden Unit 2 fuel performance during October,1990 continued to show no indications of leaking fuel. This is based on the sum of the activities of the six noble gases as measured at the recombiner. Based on the reported date, Unit 2 had excellent fuel performance. 4.4.2 Unit 3 Dresden Unit 3 fuel performance during October, 1990 continued to show no indications of leaking iuel.. This is based on the sum of the activities of the six noble gases as measured at the recombiner. Based 1 on the reported data, Unit 3 had excellent fuel performance. B 4 i l J s ZR18/643/14 l t

t a. t 5.0 ELANT OR_ PROCEDURE CllANGES. TESIS EYPERIMENTL AND SAFETY RELATED tRlHIENANCE 5.1 Amendments to Facility License or Technical Specifications. ? No new amendments to facility license or Technical l Specifications were approved for use during October, 1990. 5.2 Changes to Procedures Which are Described in the FSAR (Units 2 and 3). Table 5.2.1, attached, summarizes the revisions to procedures described t' in the FSAR which were approved during the October, 1990 reporting t period. l f f P i ZR18/643/15 i

TABLE 5.2.1 .i CHANGES TO PROCEDURES WHICH ARE DESCRIBED IN THE FSAR (UNITS 2 AND 3) FOR OCTOBER, 1990 PROCEDURE TYPE PROCEDURE NO. PROCEDURE TITLE / DESCRIPTION SUfflARY OF ("4ANGES Dresden Radiation DRP 1260-08 Calibration and Operation of Eberline Teletectors 3, 4 Protection Procedure NOTES: 1. Administrative _ change; intent of procedure unchanged.

2.. Changed for clarification, intent of procedure unchanged.

~ 3. Changed to incorporate requirements for new equipment; intent of procedure unchanged 4.. Changed to implement improved testing /calibrction methodology; intent of procedure unchanged. I 2R16/10/16

4 \\ 5.3 Significant tests and experiments not described in the'FSAR (Units 2 & 3) Significant special procedures involving tests not described in the FSAR which were approved during the month of 0;tober, 1990 are listed belows i SP-90-09-116 Modification Test for M12-2-88-063 The purpose of.this Special Procedure is to provide instruct',ons for testing the Motor Operated Valves WOV) modified in accordance with Mod #M12-2-88-063, 2 to 4 Rotor MOV Limit Switch Replacement. This procedure tests MOV's 1301-10, 1501-5A, 1501-11A, 1501-13A, 1501-20A, 1501-27A, 1501-28A, 1501-32A, 2301-6 and 2301-15. SP-90-10-117 Unit 1 Diesel Fire Pump Capacity Test The purpose of this Special Procedure is to outline steps to be taken to ved fy Unit 1 Diesel Fire Pump capacity following extensive pump l maintenance. This procedure was successfully completed prior to returning the fire pump to service. SP-90-10-118 Functional Operability Test'of 125VD0 Alternste Battery Room HVAC System. l The purpose of this Special Procedure is to detail the steps necessary to_ test the-125VDC Alternate Battery Room HVAC. System for proper operation and to ensure Smoke Detector operability. SP-90-10-119 125 Volt DC Stationary Battery Performance Test. h The purpose of this Special Procedure is to verify and trend total battery capacity. Total .i capacity is determined by discharging at a-l constant rate, equal to the manufacturer's rating of the battery for the test length, to the minimum terminal voltage of 1.81 volts per cell. SP-90-10-120 Work Request D92921 Test For Plant Paging System Upgrade to Add Page Override from the Control Room. The purpose of this is to verify the' operation of the plant paging system override from the Main Control Room. ZR18/643/17

l SP-90-10-121 24/48 Volt St: tion Batt ry P:rictmanca T;st. j The purpose of this test is to determine and l trend total-battery capacity. -The battery capacity is determined by discharging the battery 4 at a constant rate, equal to the manufacturer's rating of the battery for the selected test a length, to the minimum terminal voltage. j 1 SP-90-10-122 Annunciator Modification'M12-2-88-22B' Stage 3' Testing Verification. The' purpose of this procedure is to perform an j independent overview of the Operational Analysis Department (OAD) or Electrical Maintenance Department (EM) during Stage,3 construction testing of Modification M12-2-88-22B. This overview will verify operation of each annunciator window that has chassis input wires y and any associated KC relay wires moved from { terminal TB-21 to TB-21T. The isolation diode and Sequence of Events Recorder (SER) input wires-will also be landed at this time. l t SP-90-10-124 Modification Test for M12-2-88-063 The purpose of this procedure provides instructions to test the Motor Operated Valves .(MOVs) modified in Modification Number M12-2-88-063, 2 to 4 Rotor MOV Limit Switch Replacement. This procedure will test MOV's' 2-1001-2A, 1301-1, 1501-5c, 1501-18A, 1501-19A, 1501-21A, 1501-22A, 1501-38A, and 2301-4. SP-90-12-125 Dienel Generator Cooling Water Flow Meter j Modification Test The purpose of this p'ocedure is-to verify the y r proper function and system interf ace of the new -Diesel Generator cooling water flow meter that-r was installed per modification M12-2-87-54. SP-90-10-127 ~ Control of Work Associated with Maintenance of the.2-1001-1A Valve with the Reactor Cavity Full. The purpose of this procedure is to control the work associated with valve MO 2-1001-1A, and to address the consequences of a drain down of the-reactor cavity through the open bonnet of the subject valve in the event of a failure of the. r N1B nozzle plug. ZR18/643/18 i \\ r n

i t A i SP-90-10-128 Control of Work Associated with Maintenance of the 2-1001-1B. Valve with the Reactor Cavity Full. j 1 The purpose'of this procedurefis to control the work associated with valve MO 2-1001-18, and to address the consequences of a drain down of the reactor cavity through the open bonnet of the subject valve in the event of a failure of the NIA nozzle' plug. i SP-90-10-129 Modification Test for M12-2-88-063 The purpose of this Special Procedure is to 3 provide instructions for testing the Motor Operated Valves (MOV) modified in accordance witn ~ MOD #12-2-88-063, 2 to 4 Rotor MOV Limit Switch Replacement. This procedure test MOV's 202-4A, 202-9A, 1201-1, 1201-3, 1402-3A, 1402-4A, 1402-24A, 1402-25A, and 1402-38A. SP-90-10-130 250 Volt DO Station Battery Performance Test' The purpose of this test is to verify and trend total. battery capacity. The battery capacity is determined by discharging the battery at a constant rate, equal to the manufacturer's rating. of the battery for the selected test length, to i the minimum terminal voltage. ~ SP-90-10-145 Control Rod Drive (CRD) Electrical Checklist. The purpose of this procedure is to provide a r listing of necessary CRD System parameters for system startup after refueling is complete. i SP-90-10-149 -2(3) Reactor Protection System Electrical Checklist. i The purpose of this procedure is to provide a listing of necessary Reactor Protection System patameters fur system startup after refuel. SP-90-153 Reactor Manual Control Electrical Checklist. The purposes of this' procedure is to provide.a listing if necessary Reactor Manual Control parameters for system start up after refuel. SP-90-156 48/24 VDC Modification' Test M12-2-87-58 The purpose of this Special Procedure is to detail the steps necessary to. verify the operability of the 48/24 V battery feed breakers, i microprocessor. ammeter relays,;and associated equipment. ZR18/643/19 y -( l ~

4 T SP-90-157 Remov:d from c:rvico and R:stcr; tion Cf. Transformer 22 during Refuel Outage D2R12. The purpore of this procedure is to provide instructions for supplying Unit 2 electrical y loads using the Unit 2 Diesel Generator and de-energizing Transformer 22. 'Upon restoration j of TR 22, this procedure also provides a means to return to a normal electrical line up. ~! k -{ i ? i .~ l l ( ZR18/643/20 l l

o i 1 5.4 Safety Related Maintenance (Unit 2 and 3) - t Safety related maintenance activities f or October,1990 are [ summarized in the attached tables. 5.5 Completed Safety Related Modifications (Units 2 and'3) I Only modifications which have been completely closed during October, 1990 are listeilt modifications which are authorized for use but not completely closed will be reported based on the date of their final ~ j closure. For ease of reference,_the changes have been identified by their design change control modification number. l No Safety '.< elated Modifications were completed during the reporting period. ( + r { e b t ZR18/643/21 i

g W LI, i: E T.e4i[P 1,. p " k ' t ru NATURE OF LER OR DUTAGE MLFUNC T ION w e EQUIPMENT MAI:TENANCE NUMPER CnOSE RESULT CORRECiIVE A TIUN L 2-1501-13A PREVENTIVE N/A MOV 2-1501-13A WR D79016 INSTALLED VOTES SENSUR DN VALVE '.0KE AND TESTED VALVE WITH VOTES SYSTEM L '902-17 FUSE BLOCK "A" CORRECTIVE N/A WR D31915 REPLACED DAMAGED FUSE CLUCKS b 3 2-1500-MISC PREVENTIVE N/A REPLA 'O TWO UNISIGUi CLAMPS, y UNISTRUT SUPPORT WR D32254 TIGHT _. ED ONE OTHl:R CLAMP, UN GANf7 StPPORT g. y MAINLEeS.Se UPS FD CB. PREVENTIVE N/A (_EANED AtU INSPECTED CUBICLE AND Gb._ 'MR 984062-dREAKER _. ;-. e - L'. 28-1503 CORRECTIVE N/A REPAIRED 'C' LPCI ffX TUDE LEAt's - U-2?B' LPCI HX ~ ~ ' WR D86659 pg, - 'fx .;n- ; G E;: - ~, yj .2--2301-14 ^ PREVENTIVE N/A MOV 2-2301-14 WR D37257 PERFORMED DIAGNOSTIC TEST DN MOV 2-2301-14 USING VOTES TEST - (, SYSTEM ~ 2-203-38 PREVENTIVE N/A REMOVED LEAKING PILOI VALVE, 78 EMRV WR D88203 CLEANED VALVE AND REINSTALLED, CORRECTED LEAK 6723-21 CURRECTIVE H/A '~' ALARM FOR 'C' SHUTDOWN MR DS9704 PERFURMED CUBICLE MAtNTEtlANCE, ' COOLING PUMP TRIP:. INSIALLED PGSIT*0N SMITCH Ar-ID AUXILIARY SWITCll REACTOR BUILDING / TURBINE PREVENTIVE N/A BUILDING INTERiOCK 000R WR D70077 INSTALLED NEM DOOR OPERATUR, RET AIRED SEAL-Rett ACED ARM 2-1501-20A PREVENTIVE N/A D-2 NO-1501-20 WR D70773 It!SPECTED OFEASE.10!!Nir URE6S! AND GREASE LEVEL TU DE ACCEPTA!LE A hgg... _, - m. <r w + f me.-. w- .,,.,--c ,.w..,.-,.y-.

W Liv iEl4:iEP rN !i, u g r NA'dRE OF LER OR DUTAGE !!ALFU?tC T IO!8 ^ -M EQUIPMENT MAINTENANCE NUMBER CAUSE FESULT CORRECTIVE ACTION 'l 2-1501-19A PP'_VENTIVE N/A D-2 MD-1501-19A kR D70774 INSPECTED GREASE. FOUND GREASE-. AND GREASE LEVEL 10 DE ACCEPTM LE .X. 2-1501-18A PREVENTIVE N/A INSPECTED GREASE, FOUND GREASE D-2 MD-1501-18A WR D90775 .( t-AND GREASE LEVEL 10 DE ACCEPTAL1E 2-1001-2A PREVENTIVE N/A . y D2 MD-1001-2A WR D90819 INSPECTED GREASE, FOUND GREASE AND GREASE LEVEL TO DE ACCEPT A!:LE 3mmm= y 2-1501--114 PREVENTIVE N/A INSPECTED GREASE, FOUND GREASE D2,GID-1501-11 A WR D90876 AND GREASE LEVEL TO BE ACCEPTAPLE sw., 2-1402-25A PREVENTIVE N/A INSPECTED GFEASE. FOUND fikEASE D2;MD-1402-25A ~ ~ .MR D90878 Mj g 3 - - AND GREASE LEVEL 10 BE ACCEPTAbtE . 7; e+' r :;. V ' {p ~ h -,jg 2-1501-274 PREVENTIVE N/A USING LIBERTV TES1 EQUIPMEH1, MOV 2-101-27A WR D91369 DIAGNOSTICALLY lESTED MOV 2-101-27A \\./ 2-1402-248 PREVENTIVE N/A INSTALLED VOTES SENSOR ON MOV'2-1402-24B WR D91398 MOV 2 -1402-24B PER DEP 0040-03 2-1402-25B PREVENTIVE HiA ~'MOV 2-1402-258 WR D91400 li! STALLED VoiES SLHSDR ON HOV 2-1402-25B PER DTP 0040 0:: 2-1501-5C PREVENTIVE N/A INSTALLED VOTES SENSDR ON MOV 2-1501-5C WR D91406 MOV 2-1501-SC 2-1501-118 PREVENTIVE N/A INSTALLED VOTES SEN3UR ON MOV 2-1501-11B WR D91408 MOV 2-1501-11D - _ _ _ _ _ _ _ _ _ _ _ ~ _ _ _

4^ 39: F IV Fit.AUf dd M E NiEE NATURE OF LER OR DUTAGE MaLFut2CT ION

~-.'

EQUIPMENT MAINTENANCE NUMBER 0AUSE RESULT CORRECiIVE ACT10N L '2-1501-188 PREVENTIVE N/A INSTALLED VOTES SENSUR ON MOV 2-1501-188 WR D91410 MOU 2-1501-188 PER DEP 0040- 0:1 2-1501-198 PREVENTIVE N/A INSTALLED VUTES SENSUR MOV.2-1501-198 WR D91412 PER DEP 0040-03 L M te - 2-1501-20B PREVENTIVE N/A INSTAILED VOTES SENSOR PER U MOV 2-1501-208 WR D91414 DEP 0040-03 REVISION 3 p.yryw p-Q 2-1601-2191 PREVENTIVE N/e INSTALLED VOTES SENSUR rlN IW JU 2-1501-21B-MR D91416 MOV 1501-21B PER DEP 0040-03 4,,a a, V 2-1501-27B PREVENTIVE N/A INSTALLED VOTES SENSUR UN MOV;2-1501-278 ~ WR D91418 MOV 2-1501-27B PER DEP 0040-03 g(' ^ ' _ Mj. - L_-QD C; .s

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~, 2 i501-28A' ^ d PREVENTIVE N/A CLEANED AREA DN VALVE YOKE MOV 2-1501-28A. WR D91419 AND MOUNTED SENSCR sJ 2-1501-288 PREVENTIVE N/A v MOV 2-1501-288-WR D91420 INSTALLED VOTES SENSUR ON MOV 2-1501-288 PER DEP 0040-03 2-1501-328 PREVENTIVE N/A MOV 2-1501-328 HR D71422 INSTAlt.EU VOTES SENSUR ON MOV 2-1501-32B 2-1501-33B PREVENTIVE N/A-INSTALLED VOTES SENSUR Off MOV 2-1501-388 WR D91424 MOV 2-1501-308 PER DEP 0040-03 2A-1501-44 PREVENTIVE-N/A ADJUSIED PACRING 2A CCSM PUMP HR 092384 y.,. r 3 r. ~,% ,r,_

. hr 3M ET'i EEL 41F_D ma NR.MFA NATURE OF LER OR OUTAGE MALFUHrTION ' EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTIUff L 28-1501-44 PREVENTIVE N/A REMOVED LEAKING TOP COVER BULI, 28 CCSW PUMP WR D72385 CLEANLD COLT. APPLIED LIGili FILM OF N-5000, AND REINSTALLED VERIFIED #9 L LEAKAGE AROUND BOLT 2-1402-34A PREVENTIVE N/A INSPECTED AffD CLEANED VALVE IN1ERNot" CORE SPRAY KEEP-FILL CHECK WR D92548 L VALVE-2/3-6723 PREVENTIVE N/A CLEANED, REGREASED, DILED M4D DIU .U 4KV CIRCUIT BREAKER WR D92642 ALL PREVENTIVE MAINTENAtJUE ON I;RLAt:1.1 SER NO. 0204A 2316-006 REPLACED AUX SNITCH nr me. y 2/396723-15005-PREVENTIVE N/A PERFORMED INSPECTION ON THE 4KV 4KVFCIRCUIT BREAKER WR D92651 BREAKER AND REPLACED THE 152 SERTN,O '.0204A 2315-005' AUX SWITCH cu L 2-202 PREVENTIVE N/A CLEANED AND INSPECTED BREAKLR 29 RECIRCULATION PUMP r WR D92878 AND CUBICLE, REPLACED LUG MG;*SETiFIELD: BREAKER, G .y ~ 7, 2-0202 PREVENTIVE N/A CLEANED AND INSPECTED CUBICLE 23 RECIRCULATION PUMP WR D92881 MJD BREAKER t MG SET FIELD BREAKER 2-252-2930 PREVENTIVE N/A CLEANED 3 INSPECTLD CUBICLE ,'. BUS 29 480V BREAKER WR D92894 AND BREAKER. CHANGED ALL 1HRTE FEED TO MCC 29-2 TRIPPING DEVICES (DASH POTS) ,-2-263-61 PREVENTIVE N/A-WIDE RANGE GE MAC WR D73031 VAL.VED DUT LT 2-26:1-61 IN ACCURDANCE WITH DIP 760-3 AND DIP 260-1 2-6715-2409 PREVENTIVE-N/A CLEANED CUBICLE,iUCRICA1ED A!L BUS 24 FEED TO SWITCHGEAR WR 093202 27 4KV' CUBICLE NECESSARY POINTS 2-6715-2240 PREVENTIVE N/A PERFORMED BREAKER CUBICLE INSP. I Ek BUS-24 FD TO SWGR 26 - WR D93203. SP 89-9-84 REV. 1, REPLACLD Tl!E 152 4KV CUBICLE STA AtiX SW., THE SPM POSITION SR. n THE LUG ON WIRE 84 GH THE BKR POS SF -1 ,+%-' ..,.9 m g = g -sw p ww y .+ -y+- es a +' s as.. m... -- -m. m m .--a--

" h "" Sof~ETY RELATEfr AidirfiEt NCE v-NATURE OF LER OR DUTAGE tiALFUNC T ION - V_ EQUIP. MENT-MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 2-6724-32 PREVENTIVE N/A PERFORMED INSP. & MAINT. OF CUSd'4-- BUS 24-1 BUS TIE TO 34-1 WR D93206 BUS TIE TO 34-1 4KV CUDICLE CLEAin !* 4KV CUBICLE CUBICIE, LUBED LINKAGE & SHUDOCRS, .L 2-700-40-09C CORRECTIVE N/A PERFORMED DIP 700-15 REV. 3 ANit LPRM 40-09C WR D93446 DIP 700-14 REV. 2, CLEANED OFF L WHISKERS 2-833 PREVENTIVE N/A REMOVED GIMBAL PING 10 Ur V REFUEL GRAPPLE WR D93S75 AND PT THEM, THEN REINSTALLID THEM F=TMi^ - Q 2-700-32 414 CORRECTIVE N/A PERFORMED DIP 700-13 AND LPp :32-41A-.(APRM 4) WR'D94155-DIP 700-15, CLEANED OFF WHISKERS L 2-900 CORRECTIVE N/A CHANGED OUT BROKEN FUSE CLOCK 902-5 PNLiTERM FF: WR D94173-w- FUSE 31130-7044 v i n " C fy j'

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~ 2-900 ~ CORRECTIVE N/A CHANGED OUT BROKEN FUSE DL0tK 902-15 PNL TERM 'E' FUSE WR D94180 Q 595-703C 2-700-56-41B CORRECTIVE N/A PERFORMED DIP 700-13 REV. 2 Alfri ~. LPRM 56-418 (GROUP-1) WR D94295 DIP 700-15 REV. 3, CLEANED OFF ^ WHISEERS 2-700-48-33A CORRECTIVE N/A PERFORMED DIP 700-13 RLV.-2 Al?lt ~ LPRM 48-33A (GROUP.I) -WR D94296 DIP 700-15 REV. 3, CLEANED UFl~ WHISKERS '~LPRMf1A-08-49'(G2) PREVENTIVE N/A-PERFORMED DIP 700-13 REV. 2 ~ WR D94297 AND DIP 700-1'~ REV 3 2-700-40-33C CORRECTIVE N/A DUE 10 LPRM 40-33C DRIFTING Iffl0 H)**' LPRM 40-33C (GROUP II) WR D94454 PERFORriED DAP15-7, DIP 700-13, ItIP705-DURING PERFORMANCE OF DIP 700-19. T!!!;

  • WHISKERS
  • ON DETECTOR WERE bur #ED Uf

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M 3st i ii Wt fik p,6 j,1j Eu..ptr NATURE OF LER OR OLITAGE emLFUNr iION EQUIPMECT MAINTENANCE NUME:ER CAUSE RESULY CORRECVIVE ACTION L 2-700-16-33A FREVENTIVE N/A LPRM 16-33A WAS FEADING LUH, CEEf 0F9: LPRM 16-33A (GROUP I) HR D94490 DIP 700-13, 3 DIP 700-15 LORH 19 NOW FUNCTIONING CORRLCiLY L 2-1402-28A-RV PREVENTIVE N/A INSTALLED GnG RLLIEF VALVE CS PUMP (2A) OUTLET RELIEF WR D94514 RV-2-1402-2SA PRIOR TO I1YDRO TESI L VALVE THEN REMOVED GAG WITII QC l'RLSENT RV-2-1501-178 PREVENTIVE N/A INSTAI LED GAG RELIEF VAL'1C y LPCI HE EXCHANGE OUTLET WR D94515 RV-2-1501-178 PRIOR 10 HYIrRit TESI RELIEF VALVE THEN REMOVED GAG WITl! OC PRESLNI n y RV-2-1501-17A PREVENTIVE N/A INSTALLED GAG RELIEF VALVE LPCI IEATH EXCHANGE DUTLET WR D94516 RV-2-1501-17A PRIOR 10 HYDRO TEST RELIEF VALVE ~ THEN REMOVED GAG WITil QC PRESENT - ww., RV-2-1599-13D PREVEN TIVE N/A INSTALLED GAG RELIEF VALVE 2C LPCP PUNP SUCTION RELIEF WR D94517 RV-2-1599-130 PRIOR TO HYDRO IESI VALVEk f % >- THEN REMOVED GAG WITil QC PRESENT G LS{ -2 4 RV-2-1599-138 PREVENTIVE N/A INSTALLED GAG RELIEF VALVE 2B LPCI PUMP SUCTION RELIEF WR 094513 RV-2-tS99-138 PRIOR TO HYORO TESI L VALVE OF LPCI A PUMP AND DISCHARGE PIPINH. THEN REMOVED GAG W/DC PRESENT RV-2-1599-13C PREVENTIVE N/A INSTALLED GAG ;<ELIEF VALUE 2C LPCI PUMP. SUCTION RELIEF MR D94519 RV-2-1599-13C PRIOR TO HYDRO !! S1 .~ MALVE THEN REMOVED GAG HIT!! OC l' RESENT I RV-2-1599-13A PREVENTIVE N/A INST AL LED SAG RELIEF UALVT: 20 LPCI PUMP SUCTION RELIEF WR D94520 PV-2-1599-13A PRIOR 10 HY!rRtt II2C l 'VALUE RV-2-1599-13A Of LPCI A FUMP ANit DISEHARGE PIPINii THEN REMOVED GAG N/DC PRESENT 2-2352 CORRECTIVE N/A INSTALLED NEW TRANSMTTTER AND DPT 2352 HPCI STEAM LINE WR D94624

  • ROSEHONT 353C' CONDUIT SEAL 2-700-24-25A PREVENTIVE N/A PEhfORMED DIP 700-15 l

KWU LPRM DETECTDRS WR D94633 ___....~~n---- ~' ' ' " " -- - - ' " ~ ^ ' -

(pi % -E t i y FEli,I Ei. ric.!:1 T U v 9 ^ N4iURL OF LER OR 00TAGE fMLTtlNC ! ION v EQUIPMENT MAINTENANCE NUMDER CAUSE REGULT CORRECTIt'E ACTION b 2-201 PREVENTIVE N/A REMOVED ALL REACTOR SHIEll! I:LetL% D-2 REACTOR (DISASSEMBLY) WR D94959 AHD DRWELL COVER, liAD LlitT FEhrem + AND ADDRESSED ALL I MT 'S AND PM'/'S. L REACTOR (DISASSEMBLY) PREVENTIVE N/A PEkFURMED ALL CAVITV WORK PLR WR D94960 DAP 3-14, ADDRESStin ALL PMT'S \\,,, ,~ AND PMV'S 2-201-1 PREVENTIVE N/A INST AI. LED REFUELING SHIElit 10 AID L REACTOR (DISASSEMBLY) WR D94962 IN UNLOADING OF REACIOR, ADi'RLSSED ALL PMT'S r,7 INSPECTED GREASE, FOUND GREASE y 2-2301-14 PREVENTIVE N/A MOV-2301-14 DPERATOR WR D95048 AND GREASE LEVEL TO BE ACCEPTAULE 2-2301-3 PREVENTIVE N/A INSPECTED GREASF,fOUND GREASE MOV-2301~-3=0PERATOR WR D95049 AND GREASE LEVEL 10 BE ACCEPTAI:LE 4, + ~ "' ~ }~ 2-2301-9 PREVENTIVE' N/A INSPECTED GREASE,!~0tIND GREASE MOV 2301-9 OPERATOR WR D95053 AND GREASE LEVEL 10 UE ACCEPT AT:LI y 2A-1341L PREVENTIVE N/A DISCONNECTED 1/4" TUDING ANir PIPL~ ~ ISOLATION CONDENSER WR D95076 REDUCERS, PLUGGED THE 1" LINE HI1H A SAFETY RELATED PLUG 2-261-34C CORRECTIVE N/A FErLACED MICR0 SWITCil IN DPIS 261-34C WR D95164 DPIS 2-261-34C AND F1RFORMEI DIS 1500-6 FEVISION 1 2-5201 PREVENTIVE N/A CLEANED FLANGES SURFACES Arm DULTS DIESEL GENERATOR FUEL WR D95374 0F TANK DIL TANK l s._- 2-702-SRM-24 CORRECTIVE N/A IrlPUTS TO SEM 22 AND 24 Mt RL Mmi f i t' SRM 24 WR D95333 WHEN NORMALIZED, IHE PRODI EH 01 SRH READING JUMPING HAD l'ISAPPEARElf, CONNECTION WAS DIRTY Al CONNEC10R l ._.i.,,_.a.s- .,.ip ...,-. - - i,,,,, --+..iar.-.um...

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k 'AElV'hEt31Nt ;idim E %isCII NATURE OF LER OR 00TAGE MALFUtJEII0:1 -EOUIPNECT HAINTENANCE NUMDER CnOSE RESULT CORRECTIVE ACTION ^ ( 2/3-03-CR1062 REBUILT CONTROL ROU DRIVE #1042 PREVENTIVE N/A CONTROL ROD DRIVE WR D36513 L SPARE CRD-A5115 PREVENTJVE N/A LEAK TESTED CRD inG115 PER WR DS9294 DMP-0300-11 REVISION 2 L SPARE CRDS 983 PREVENTIVE N/A LEAK TESTED CRD 8903 FER L HR D39298 DMP-0300-11 REVISION 2 Q[ G 6441D.- CORRECTIVE N/A INSTALLED NEW CRANK CASE 2/3 DIESELfGENERATOR' NR D89348 PRESSURE SWITCH CRANK.. CASE' PRESSURE SWITCH - c. v., 2/3-03-1267 PREVENTIVE N/A LEAK TES1ED CRD 11267 PER CONTROL' ROD DRIVE WR D90506 DnP-0300-11 REVISION 2 g ;b-Q si' ^.rs; x3_ zg. 2/3-03-CR285 PREVENTIVE N/A LEAK TESTED CRD 5205 FER CONTROL RCD DRIVE WR 090507 DNP-0300-11 REVISION 2 O 2/3-03-CR8960 PREVENTIVE N/A LEAK fESTED CRD 43760 PER _ CONTROL ROD DRIVE WR D90508 DMP-0300-11 REVISION 2 .._ 2/3-03-CRS33C PREVENTIVE N/A LEAK IESTED CRD 4533C PER CONTROL RDD DRIVE WR D90511 DMF-0300-11 REVISION 2 2/3-03-CR6701 PREVENTIVE N/A LEAK IESTED CRD #6701 PER CONTROL ROD DRIVE WR 090515 DMP-0300 REVISION 2 2/3-6699-114 PREVENTIVE N/A REPLACED CADLY LEAKIN(e FILTER. 2/3 DIESEL GENERATOR 'WR-D91277 GASKET TURBO CHARGER OIL FILTER

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b afElyr:EL IED n51HidMHCE NATURE OF LER OR OUTAGE HnLFUNC110N ~ F--- E9UIPMENT MAINTENANCE f!UME'ER CAUSE RLSULT CORRECTIVE ACTION C 2/3'F3-CR113 PREVENTIVE N/A LEAM TESTED CRD #113 FER CONTROL ROD DRIVE WR 092275 PMP-0300-11 REVISION 2 L 2/3-03-CR962 PREVENTIVE N/A CONTROL-ROD DRIVE WR D92501 LEnk IESTED CRD 1533C PER DHP-0300-11 REVISION 2 L .y~ .l', QUAD CITIES SAFETY VALVE PREVENTIVE N/A KEPAIRED QUAD CITIES SAFE 1Y VotNE y WR D93289 PER DNP 200-30 AND DHP 040-30 gg.7s G QUAD' CITIES. SAFETY VALVE. PREVENTIVE N/A REPAIRED VALVE PER DNP 200-30 ggit? 'WR D93291' AND DNP 040-30 L QUAD CITIES SAFETY VALVE PREVENTIVE N/A REPLACED WORN DISC AND SPINDLE s w - WR D93292 WITH NEW, PERFORMED ALL PMT'S AND !q!C-..g

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y.. 'r? QUAD CITIES SAFETY'V'4LVES PREVENTIVE N/A REFAIRED VALVE PER DNP 200-30 WR 093293 AND DMP 040-30 v 2/3-03-CR1215 PREVENTIVE N/A . CONTROL ROD DRIVE. WR D93547 LEAK TESTED CRD #1215 PER DMP-0300-11 REVISION 2 2/3-30-CR966-PREVENTIVE ti/A LEAK TESTED CRO 1946 PER ~ CONTROL ROD DRIVE WR D93540 DNP-0300-11 REVISION 2 2/3-d3-CR1104 PREVENTIVE N/A LEAK 1ESTED CRD 51104 PER CONTROL ROD DRIVE WR D93549 DNP-0300-11 REVISION 2 2/3-03-CR3466 PREVENTIVE N/A CONTROL ROD DRIVE WR D93558-LEA 7 TESTED CRD 23464 PER DMP-G OO-f1 REVISION 2

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  • EQUIPMENT MAINTENANCE HUMBER CAUSE RESULT CURRECTIVE ACTION y 2-700-24-57D.

PREVENTIVE N/A REMOVE VARICUS LFRM CARDS TO, ~ LPRM CARD *' WR 093574 FACILITATE INSTALLTTION OF GE AMP MODULES ONIO KWU LPRM L DETECf0RS 2/3-4699-314B PREVENIIVE N/A FERFORMED AS-FOUND TLST AND DIESEL GENERATOR AIR WR D93537 RECORDED FINDINGS L RECEIVER TANK RELIEF VALVE-e n: 2/3 REACTOR LIFTING RIG PREVENTIVE N/A PERFORMEP >Ryt UN REACTOR I.II TIDG y D/S LIFTING RIG AND D/S WR-094024 RIG, D/S LIFTING RIG AND D/S Il00K HOOK BOX E:0X 373 2/3-6499-103 PREVENTIVE N/A REFLACED AIR START SULENDIDS ON L'2/3; DIESEL GENERATOR... WR D94397. '..' 1 2/3 DIESEL GENERATOR AFTER 'CIR* START'SOLENDID VALVE SUCCESSFUL E:ENCH TEST m.g.. r 4 L FCILED ROSEMOUNT HPCI PREVENTIVE N/A CALIETATED TRANSHI TIER FER HORK STEAM FLOW WR D94703 INSTRUCTIONS V ijky y w. p; TRANSMITTER -

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,pfp ~ # '2-28-3 ~

p PREVENTIVE N/A FERFORMED OFEAKER INSFECTION 2/3 DIESEL COOLING WATER WR D95041 C PUMP 480V BREAKER (NORMAL FEED) 2-28-1 PREVENTIVE N/A PERFORMED PREAKER INSPECIl0N v 2/3 DIESEL GENERATOR AIR WR D95042 START COMP'490V BREAKER-3-38-3 PREVENTIVE N/A PERFORMED E'FEAKER IN9PECTION

~ 2/3 DIESEL COOLING WR D95043 WATER PUNP 480V BREAKER (RESERVE FEED) 2-28-1 PEEVENTIVE N/A PERFORMED BFEAKER INSFECTION 2/3 DIESEL OIL TRANS PUMP WR D95044-480 V BREAKER 3-38-1 PREVENTIVE N/A CLEANED CREAKER EXIERNALS, CONT ACTi'- ~2/3 DIESEL VENT FAN NR D95045 ElIRRENT TES1ED MOLfED CASE ORLAKER, _ 480V BREAKER THEN REIMSTALLED BREAKER -,= . = - _ - _. - -

M Sr-F tTi EEI ATED ddt!iEF :NCE f NATURE OF LER OR 00 TACE rinLFUNCIION EQUIPMENT-MAINTENANCE NUMBER CAUSE RE!? ULT CORRECTIVE ACTION . ( 3-38-1 PREVENTIVE N/A PERFORMED 400V BREAKER INSPEC1104 2/3 DIESEL GENERATOR WR D75046 .. DIL TRANS PUMP 480V BREAKER AND PREVENTIVE MAINTFNANCE C (ALTERNATE FEED) bIESELVENTFAN h E N/A FERFORMED 480V CREAKER INSPECtIDH ('480V BREAKER 13-38-4 PREVENTIVE H/A y 2/3 'B' DIESEL GENERATOR WR D95061 FERFORMED BREAKER IN*iPECI(DN CIR START COMP 4SOV BREAKER y. s. L 2/3-6641-524' ' CORRECTIVE N/A ' TEMPE.R.ATURE ~ SMITCHES * '~' WR D'5123 REPLACED GASKETS AS REQUIRED ftR 2/3 DIESEL DEMERATOR. 2 DIS 6600-2 REVISION O m ca y. V 2/3-6601-LI PREVENTIVE N/A REMOVED SIGHT GLASS AND CLEANLD, 2/3 DIESEL GENERATORe : WR D95176 COOLANT ' SIGHT-BLASS.

  • REPLACED RUBBER WASHER AND FIBER 2

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,j,,. .3- ,. y, 2/3-4411A PREVENTIVE N/A r2/3 DIESEL GENERATOR WR D06196 PERFORMED DIS 6600-1 FOR-U CIR START COMPRESSOR

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SNITCH 4 .e m %,aa-aw.-m._--_z_w.%.s.ies--wam....--1._s-%_:.- -ah- -gs--- ww e 6 g g. _,w-g m ,w.., - - n.. m. .-.i

NATURE OF LER OR OUIACE 11ALFUttCT IUN ~ . EQUIPMENT-MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION ( 3 2301-6. PREVENTIVE N/A i USING LIBERTY TEST EDUIPMEN1/ MOV 2-2301-6 WR D84496 OIAGNOSTICALLY TESTED MOV 2-23S1-6 .Q. ?3-1402-24B PREVENTIVE N/A - MOV-3-1402-24B :- WR D84508 USING LIBERTY TEST EuUIPMEH1, DI AGNOSTICALLY TESTED M0'?-3-1402-20 .y 3-1501-58' PREVENTIVE N/A - - - - - - - - - - - - ~ ~ USING LIBERTY TEST EDUIPMEN1, L MOV 3-1501-5B WR D84512 DIAGNOSTICALLY TESTED MCV 3-1501-50 ~ y3 1-5C i.. ~ PREVENTIVE N/A USING LIBERTY TESi E.,UIPMENT,

M0y43-1501-5C._

WR D84513 DIAGNOSTICALLY TESTED MOV 3-1501-5C ,m, 3-1501-20B PREVENTIVE N/A USING LIBERTY TEST EQUIPMENI, MOV03-1501-208a ~.: ,WR D84522 DIAGNOSTICALLY 1ES1ED MOV 3-1501-20" I Ilf$ M I. " 32 M' v (f y jg 2301-14 PREVENTIVE' N/A USING LIBERTV TEST E9UIPHENT, MOV 3-2301-14 WR D84524 DI AGNOSTICALLY TESTED MOV -2301-1+ g 3'-2301-351 PREVENTIVE N/A USING' LIBERTY TEST EOL8IPMEN1, MOV 3-2301--35 WR'D84526 -DIAGNOSTICALLY 1ESTED MOV 3-2301-35 m '3-2301-36 -PREVENTIVE N/A ' 'MOV 3-2301-36 WR D84527 USING LIBERTV TES3 EOUIPMFN), DIAGNOSTICALLY IESTED MOV 3-2301-34 3-2301-48. -PREVENTIVE N/A ~ USING LIBERTY TEST EDUIPMENT, NOV 3-2301-48 WR D84528 DI AGNOSTICALLY TES1ED MOV 3--2301 3-2301 PREVENTIVE 'N/A USING LABERTV TEST Euu1PMENI.. -MOV 3-2301-49 WR D84529 DIAGNUSTICALLY TESTED MOV 3-2301-47

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2

m Sal ETY RELATED riAINTEDANCE rw - NATURE OF LER OR DUTAGE riALFUtJCT IOff W -EQUIPMENT.. MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION t 2/3IDIESEL. GENERATOR' PREVENTIVE N/A INSTALLED NEW BREAKER COOLING WATER PUMP WR D86978 s L .3-3316-20-L PREVENTIVE N/A INSTALLED NEW SUPPOR'l LINE 3-3316-20"-L WR DS9412 PER FCII TRAVELER 89412-01 G !;J2 ^ P

3-202-5B PREVENTIVE

-N/A INSTALLED VOTES' SENSOR AND-G MOV 3-202-5B WR D90072 DIAGNOSTICALLY TESTED MOV 3-202-SD fJXpCTC ?" - ;R~: 5 i U 3 2034E B,"C, D.e A CORRECTIVEN .N/A CUT GUT A SMALL SECTION OF PIPE FROH ' &QSg'C,gDiMSIV'SMh1x WR D90457-GLAND LEAK OFF LINES, THREADED EACil-- 2 '~ END OF 3/4" PIPING & INSTALLED PIPE. %b CAPS ON EACH END 3-MO-202-58 ~ Ct5SECTIVE N/A INSTALLED NEW MACilINED DRIVE NUT 3-B REACTOR CIRCULATING _- W4TER4 PUMP.DISCHARGEiVALVE-WR DYO948-g 7 m-g 3-1502-24" PREVENTIVE' N/A LINE-3-1502-24" WR D91361 INSTALLED NEW FABRICATED D00T WITH CTAINLESS STEEL CLAMPS ANil _ L. ADHESIVE 3-300-H-10 CORRECTIVE N/A ~ INSTALLED NEW DRIVE, NEW UNLAICllING H-10 CONTROL. ROD DRIVE WR D92084 PIN, ONE NEW LARGE 0-RING GASXE1 Aliti TWO SMALL GASKETS. 3-700-RBM3 CURRECTIVE TOA ~ 'RBM 3 LPRM DISPLAY WR D93560 - - ~ - - - REPLACED METER AND CALIBRATI-D PER DIP 700-18 REVISION 1 3-0305-111'- CORRECTIVE idA REFLACED 00tJNET,-SEAL.,-AND'U-RINO" HCU C-5 (10-19F WR 094026 STAR VALVE SEAT TO REPAIR STAR VALVE WITil- . PACKING LEAK 700-16-41C CORRECTIVE N/A - FERFORMED DIP 700-13.ANDl .LPRM 16-41C-WR 094084 ' DIP 700-15 ..~ .. -.. =. - = - ,.. = -

' ~ ^ ' Of liv YLL(dED rid 1isidN 5_ F. HAIURE OF LER OR OUTAGE HALFUtnTION M- - EQUIPMENT: . MAINTENANCE NUMBER CnUSE RESULT CURRECTIVE ACTION 4 2/3 DIESEL GENERATOR PREVENTIVE N/A CALIBRATED DIESEL GENERA 1(IR FREQUENCY METER WR D94255 FREQUENCY METER AT 903-3 PANEL,' .. Q' LPRM.3B 48-33 CORRECTIVE N/A PERFORMED DAP 1507, l'IP 700 13 AND .,u. WR D94446 DIP 700-15, CLEANED OFF H!!ISKERS - 3-2402A CORRECTIVE N/A REPLALED 02 CELL AND TERH1fML STRIP-y POST-LOCA CONTAINMENT WR 09,804 H202 NONITORA' D-3 TIGHTENED FITTINGS AND Cl!ECKED CALIBRATION PER DIS 2400-05 REV. O p%37; . y, TR i3-1641-9 & 200A PREVENTIVE N/A REPLACED DRUM DRIVE AND CAL RECORDER TORUSzTEMPERATURE3 RECORDERS' WR D94878: N:cA : 3-4699-135 PREVENTIVE N/A INSTALLED NEW VALVE U3;D/6:AUR: START-REGULATOR-WR. D95127.... gwze - min mmu r; t sow,. : =;.. - k'- [rfy 1'_ ~4;% -~ ^. < Ni1B T ~igi PREVENTIVE N/A 3B DIESEL GEN. AIR START-NR D95145 PERFORMED DIS 6600-1 REV 3 UN V COMPRESSOR SWITC!! 'B' --3B H2 102' MONITOR! PREVEllTIVE 'N/A 'WR D95147 PERFORMED DIS 2400-5 3-1705-16A'. CORRECTIVE N/A .3A REFUEL POOL ARM WR D95475 RECAL10 RATED ARH 3-1705-164: PER DIS 1700-15 ALSO PERTORMED-FUNCTIONAL CHECK PER DIS' 1700-15 ' DPI53-261-34D ~ PREVENTIVE N/A LPCI LOOP SELECT 'WR D95530 t.DJUSTED CAM FOLLOl4ER 10.TRJr SWITCH 3-261-34D ON Store OF DETENT f 1 F '1"-*

  1. '"Y

c .e c **.-8 o l -1 5.6. Temporary System Alterations (Unit l2 and Unit 3). installed during-j October, 1990 i 1 LA " Temporary System Alteration" refers to electrical jumpers, lifted: l leads,. removed fuses, fuses turned to non-conducting position.1 fuses: j moved from normal-to reserve holder,> temporary power supplies,< test! switches in alternate positions,1 temporary blank flanges, and. spool pieces. Alteraticus controlled:and documented as part of a routine! l out-of-service'or other procedure,. alterations;which are a normal feature of system' design, and. hoses, installed as part of'a venting'or' i l draining process are not included. 5.6.1 Unit 2 Temporary ' Removal System Installation ALLAIA11on No. Description Date~ Date - .1 II-30-90 Alteration provides temporary 10-5-90 6 l 4 Control Room indications during; =! recorder' replacement on the 902-2 i l and 902-54 Control' Room' Panels' during the Unit 2 refueling' outage.' 1 I1-31-90 Alteration provides temporary' control! ~10-7-90l room indication during replacement:.of i recorder 2-3340-06 during'the. Unit:2 Refueling Outage. 11-32-90 This alteration. involves installing. 10-16 10-19-90 temporary jumpers in on'the dryvell High Radiation Monitors 2419A & 2419B. This was accomplished to disable the monitors and prevent a Group;II: Isolation during cable. replacement. I II-35-90 Alteration provides temporary; feed.to-10-20-902 21-90 emergency. lights 234, 251, and 248' . while Bus 29-2 is out of : service.., Emergency lights are required for-~ safe-shutdown procedures for Unit 3. During installation of. Bus?.9-9,-the i feeds for the above-mentioned 111ghts (Bus 29-2) will be de-energized. ~ i II-36-90 Alteration provides for the removal 10-23-90 of the Alterex Housing to allow for. the disconnection =of the west quarter of the.Alterex System. \\ ii ZR18/643/22 i

l

' i,

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l != Temporary-Removal-r .o-System Installation-Alteratio1LHo2 De.scription. Date Date.- 11-37-90 Alteration-provides continuous 125V DC 10-27-90. 10-31-90 f -power to annunciator windows-C-24 (fuel pool skimmeritank level below l-normal), E-19-(Rx/Turb. 517 interlock. 1 door inop/ bypass),--.E-20 (Rx/Turb. 569 interlock' door inop/ bypass),.F-20 ..j -(Refuel floor internlock door' l inop/ bypass)', and E-21 (Diesel. Generator 'i 2/3 interlock door inop/ bypass)_on the' t 902-4 pane 1Lduring work on modification M12-2-88-228. Lj 'i II-38-90 Alteration provides continous 125 VDC. 10-28-90 '10-31-90 power to annunciator window A-17 (dryvell equipment sump. level liigh-liigh) on Panel.902-4 durin's work' i on' modification-M12-2-88-22B. 5.6.2 -Unit 3 i 111-21-90 The purpose of.this alterationdis the-. 10-16-90 provide continuousLdrywell' air sampling in the CAM System between:linesu; r ' j 3-9207-1"-H and 3-9208-1"-11 on the.' South wall of the.Drywell'Personne1' Interlock Room. III-22-98 The purpose of this temporary. 10-19-90 t l alteration is-to' isolate the bypass. } valve <of theLeondens' ate / booster: pump-i minimum. flow-line. The bypass valve.' l-(3-3407-500) is to be repairedLto~stop l 1eakage, which is causing'a pressure-l' loss and reduction of suction pressure 4 in the condensate--system;and reactor: feed pump suction. header. 1 l. o j i lf d ZR18/643/23-4 [ 7 ,}}

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