ML20059G377

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Monthly Operating Repts for Dec 1993 for Dresden Nuclear Power Station
ML20059G377
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 12/31/1993
From: Spedl G, Sykes K
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
GFSLTR-94-0016, GFSLTR-94-16, NUDOCS 9401240128
Download: ML20059G377 (42)
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Text

{{#Wiki_filter:,. t O Commonwealth Edison Dresden Nuclear Power Station 6500 North Dresden Road

j Morris, Illinois 60450 t

Telephone 815/942-2920 January 11, 1994 i GFSLTR 94-0016 Director, Nuclear Reactor Regulation United States Nuclear Regulatory Commission i Washington, DC 20555 Attention: Document Control Desk i Gentlemen:

Subject:

Monthly Operating Data Report Dresden Nuclear Power Station Commonwealth Edison Company i Docket Nos. 50-010, 50-237, and 50-249 l t Enclosed is the Dresden Nuclear Power Station Monthly Operatina Summary i Report for December 1993. No 10 CFR 50.59 evaluations are included in this report. As indicated in prior reports, changes implemented between July 1993 and December 1993 will be reported along with_the FSAR updates. This change in reporting frequency remains within the guidance provided in 10 CFR 50.59 (b) (2), which states that the report'on changes, tests and experiments, with the accompanying safety evaluation summaries, may be } submitted annually or along with the FSAR updates as required by 50.71(e), or at shorter intervals as may be specified by the licensee-i l This information is supplied to your office in accordance with the i instructions set forth in Regulatory Guide 1.16>. Si er l l /n /-y-yf i / ary, Spe t Stay n Mandger y:ff 5'SI [ gpJ' 1 T00091 s ( t.:wKynoctrixtuamorsum 6.w J j( 9401240128 931231 I PDR ADDCK 05000010 N L R PDR k

Enclosure cc: NRC Region III Office Illinois Dept. of Nuclear Safety, State of Illinois U.S. NRC, Document Management Brc.nch Nuclear Licensing Administrator Site Vice President Regulatory Assurance NRC Senior Resident Inspector Site Quality Verification - Dresden Site Engineering and Construction Manager { Nuclear Oversight Manager / R. Janecek General Electric Comptroller's Office INPO Records Center UDI,Inc.- Wash.,D.C. File / Numerical ) i i L:\\WK, PROC \\PLNTMGR\\0PS94\\0016.94

b MONTIILY NRC

SUMMARY

OF OPERATING EXPERIENCE, CERNGES, TESTS, AND EXPERIMENTS l PER REGULATORY GUIDE 1.16 AND 10 CFR 59.59 FOR DRESDEN NUCLEAR POWER STATION COMMONWEALTil EDISON COMPANY -t FOR December,1993 i UNIT DOCKET LICENSE l 1 050-010 DPR-2 2 050-237 DPR-19 3 050-249 DPR-25 i I 1;\\WK_ PROC \\PIETMGR\\ GPS 9441016.94 i

j TABLE OF CONTFRTS i Deconher,1993 NRC REPORT 1.8 Introduction P 2.0 L=nmary of Operating Experiasm 2.1 Unit 2 Monthly Operating Experience Summary. 2.2 Unit 3 Monthly Operating Experience Summary. 3.s Operating Data statistics 3.1 Monthly Operating Data Report - Unit 2 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 Unit 2 Maximum Daily Electrical Load Data 3.8 Unit 3 Maximum Daily Electrical Load Data 4.0 Unique Reporting R-g= '.- -.:. l 4.1 Main Steam Relief and/or Safety Valve Operations - Unit 2 and Unit 3 4.2 Off-Site Dose Calculation Manual Changes 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 Plant or Ihd.we Changes, Tests, Exr ~.a.:s, and Safety-Related Maintenana 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 Analysis Report (FSAR) (Units 2 and 3) 5.3 Significant Tests and Experiments Not Described in the FSAR (Urus 2 and 3) 5.4 Safety-Related Maintenance (Unit 4 2 and 3) 5.5 Completed Safety-Related Modifications 5.6 Temporary System Alterations Installed 5.7 Other Required 10 CFR 50.59 Evaluations (Units 2 and 3) l l IdWK, PROC \\PIETMOR\\ GPS 94\\0016.94

1.0 Introduction Dresden Nuclear Power Station is a three reactor generating facility owned and operated by the Commonwealth Edison Company of Chicago, Illinois. Dresden 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 design net electrical output ratire of 200 megawatts electrical (MWe). The unit is retired in place with all nuclear fuel renoved 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 is rejected to a man-made cooling take using the Kankakee River for make-up and the Illinois River for blowdown. The Architect-Engineer for Dresden Units 2 and 3 was Sargent and Lundy of Chicago,'lilinois. This report for December,1993, was compiled by Kevin W. Sykes of the Dresden Regulatory Assurance Staff,' telephone number (815) 942-2920, extension 2704. L\\%% PROC \\PLNTMGR\\ GPS 94\\0016.94 -

t .t r i i l 2.0

SUMMARY

OF OPERATING EXPERIENCE FOR hw,- 1993 l .) 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE

SUMMARY

12/01/93 Unit 2 entered the month critical and on line. i 12/07/93 At 0320 hours, during the perfonnance of DOS 0250-01, Partial Closure '. Operability Test of Main Steam isolation Valves (MSIV), MSIV 2-203-2B remained. j at dual indication. At 0412 hours, Unit load was reduced to less than 50% power. to perform additional testing and troubleshooting. 12/11/93 At 0000 hours, Unit load was reduced to approximately 440 MWe to ' allow entry f into the heater hay to repair a steam leak. 12/28/93 At approximately 2240 hours, Unit load was reduced to approximately 300 MWe to. i allow for X-Area (i.e., steam tunnel) cooler repairs. i 12/31/93 Unit 2 remained critical and on line through the end of the month.- l ? f I i 1 i i i l l L\\WKJROC\\PINFMGR\\0PS94iUOl6.94 1 .i

2.0

SUMMARY

OF OPERATING EXPERIENCE IOR Decrunber,1993 2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE

SUMMARY

12!01/93 Unit 3 entered the month critical and on line. 12/04/93 At 0010 hours, Unit load was reduced to approximately 551 MWe to allow for the perfonnance of Dresden Technical Surveillance (DTS) 0300-02, Control Rod Drive. Scram Testing and Scram Valve Timing Test. 12/31/93 Unit 3 remained critical and on line through the end of the month. 1 L:\\WK PROC \\PINTMOR\\GFS94\\0016.94

3.0 OPERATING DATA REPORT 3.1 OPERATING DATA REPORT - DRESDEN UNIT TWO DOCKET No. 050-237 DATE January 1,1994 COMPLETED BY K. W. Sykes TELEPIIONE (815) 942-2920 OPERATING STATUS

1. REPORTING PERIOD: December,1993
2. CURRENTLY AUTilORIZED POWER LEVEL (MWth): 2,527 MAXIMUM DEPENDABLE CAPACITY (MWe NET): 772 DESIGN ELECTRICAL RATING (MWe Net): 794
3. POWER LEVEL TO WilICil RESTRICTED (IF ANY) (MWe Net): N/A
4. REASONS FOR RESTRICTIONS (IF ANY): N/A REPORTING PERIOD DATA PARAMETER Tills MON 111 YEAR *IO DATE CUMULATIVE 5.

IlOURS IN PERIOD 744 8760 206,448 6. TIME REACTOR CRITICAL Oloun) 744 4887 153,714 7 f 7. TIME REACTOR RESERVE SIIUTDOWN (lloun) 0 0 0 8. TIME GENERATOR ON-LINE Oloun) 744 4788 147,277 l 9. TIME GENERATOR RESERVE SIIUTDOWN Gloun) 0 0 0 10. TIIERMAL ENERGY GENERATED (MWilt Gron) 1,692,699 10,283,050 304,317,870 II. ELECTRICAL ENTRGY GENERATED (MWile Grou) 534,855 3.237,074 97,106,537 13. ELECTRICAL ENERGY GENERATED (MWIIe Net) 508,824 3,043,891 92,811,191 13. REACTOR SERVICE FACTOR (%) 100 55.8 74J 14. REACTOR AVAILABILITY FACTOR (%) 100 55.8 74.5 15. GENERATOR SERVICE FACTOR (%) 100 54.7 71.3 16. GENERATOR AVAILAllILITY FACTOR (%) 100 54.7 71J 17. CAPACITY FACTOR (USING MDC Net) (%) 88.6 45.0 58.2 18. CAPACITY FACTOR (USING DER Net) (%) 86.1 43.8 56.6 19. IX)RCED OUTAGE FACTOR (%) 0 15.8 12.3 20. SIIUTDOWNS SCIIEDULED OVER TIIE NEXT 6 MONTIIS (Type, Date and Duration of Each) 21. IF SIIUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP. N/A L:\\WK, PROC \\PINTMGR\\ GPS 94\\0016.94

l 3.0 OPERATING DATA REPORT 3.2 OPERATING DATA REPORT - DRESDEN UNIT TilREE DOCKET No. 050-249 DATE January 1,1994 COhlPLETED BY K. W. Sy kes TELEPilONE (815) 942-2920 OPERATING STATUS

1. REPORTING PERIOD: December,1993
2. CURRENTLY AUTilORIZED POWER LEVEL (htWth): 2,527 AIAXIh1Uh! DEPENDABLE CAPACITY (h!We Net): 773 DESIGN ELECTRICAL RATING (htWe Nel): 794
3. POWER LEVEL TO WIIICII RESTRICTED (IF ANY) (AIWe Net): N/A
4. REASONS FOR RESTRICTIONS (IF ANY): N/A REPORTING PERIOD DATA 5.

IlOL'RS IN PERIOD 744 8760 196,777 6. TIN 1E REACTOR CRITICAL (llours) 744 7117 142,706 7. TINiE REACTOR RESERVE SilU11)OWN Olours) 0 0 0 8. TL\\tE GENERATOR ON-LINE Olours) 744 7051 137,315 9. TINTE GENERATOR RESERVE SIfU11)OWN Olours) 0 0 0 10. TilERNIAL ENERGY GENERATED (N1 Wilt Gross) 1,553,606 16,205.362 283,734,817 11. ELECTRICAL ENERGY GENERATED (%fWile Cross) 500, % I SJ11,562 91.176,511 12. ELECTRICAL ENERGY GENERATED (%1WIIe Nat) 476,805 4,963.498 86,584,710 13. REACTOR SERVICE FACTOR (%) 100 81.2 72.5 14. REACTOR AVAILABILITY FACTOR (%) 100 81.2 72.5 15. GENERATOR SERVICE FACTOR (%) 100 80.5 69.8 16. GENERATOR AVAILABILITY FACTOR (%) 100 80.5 69.8 17. CAPACITY FACTOR (USING N1DC Net) (%) 82.9 73.3 56.9 18. CAPACITY FACTOR (USING DER Net) (%) 80.7 71.4 55.4 19. FORCED OUTAGE FACTOR (%) 0 19.5 11.7 20. SHUTDOWNS SCHEDUI.ED OVER THE NEXT 6 MONTHS (Type, Date and Duration of Each) Refuel Outage 13, D3R13, is scheduled for March 1994. The scheduled duration for this refuel outage is 13 weeks. 21. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A l.:\\WK_ PROC \\PINTMGR\\GFS94\\0016.94

g ,i f, 1 ? i-4 t 3.3 AVERAGE DAILY UNIT 2 POWER LEVEL i l 4 DOCKET No. 050-237 l UNIT Dresden 2 DATE January 1,1994 COMPLETED BY K. W. Sykes TELEPliONE (815) 942-2920 i i { 1 ) MONTH: December,1993 -i ') i DAY AVERAGE DAILY NET . DAY AVERAGE DAILY NET. POWER LEVEL (MWe) P0WER LEVEL (MWe) I i 1 .553 18 717 -] 2 735 19 714 j .l 3 748 20 735 4 750 21 737 5 709 22 739 l 6 746 23 739 7 522 24 723 [ 8 700 25 735 .j 9 758 26 715 le 738 27 741 11 323 28

712 12 355 29 552 13 654 30 740 14 717 31 684 i

15 720 I 16 723 17 719 uwx_enoctrunwonasmooi6.w

v l 3.4 AVERAGE DAILY UNIT 3 POWER LEVEL l DOCKET No. 050-249 i UNIT Dresden 3 i DATE January 1,1994 COMPLETED BY K. W. Sykes TELEPilONE (815) 942-2920 MONTil: Decesaber,1993 l i i l DAY AVERAGE DAILY NET DAY AVERAGE DAILY NET POWER LEVEL (MWe) POWER LEVEL (MWe) 1 694 18 631 j 2 684 19 632 3 681 28 627 4 522 21 629 l 5 658 22 627 6 673 23 623 7 674 24 622 i 8 675 25 621 9 670 26 619 i le 661 27 615 11 667 28 612 12 663 29 609 U M M M 14 658 31 604 15 652 l 16 645 J 17 642 IAt% PROC \\PLNTMGRWP594\\0016.94

...,_~. , +. I' 4 4 1 i 1 1- ) -l 1 i i 3.5 UNfr 2 SHUTDOWNS AND POWER REDUCTIONS - 4 REPORT MONTH OF December,1993 i 4 I NO. DATE TYPE (1) DURATION REASON (2) METHOD. l.JCENSEE SYSTEM' COMPO-CORREC-j (HOURS)*. OF EVENT CODE (4) NENT. TIVE SHUTTING REPORT # CODE (5) ACTIONS /. I DOWN COM-I REACTOR MENTS ' ~ i (3) i 12 931207 F 0 B 5 NA NA NA SEE NOTE -l I 1 BELOW 13 931211 F 0 B 5 NA' NA NA' SEE NOTE 2 BELOW 14 931228 F 0 B 5 NA NA NA $EE NOTE 3 BELOW ] f N 'l e i i a a I Year-toete forced outage hours = 896; Cumulative forced outage hours = 20,620 NOTE 1: Adjusted limit switch on Main Steam laolation Valve (MSIV) 2-203-2B. NOTE 2: Heater Bay entry made to repair steam leak. NOTE 3: X-area cooler repairs performed. Jj i TABLE KEY: l (1) (3) } F: Forced Method: S: Scheduled

1. Manual _

t

2. Manual Scram 1

(2)

3. Automatic Scram i

Reason:

4. Other (Explain)

-) A Equipment Failure (Explain)

5. Load Reduction l

B Maintenance or Test C Refueling (4) - D Regulatory Restriction Exhibit G Instructions for Preparation of Data Entry Sheets for Licensee Event Reports (LER) File (NUREG-Ol6I) E Operator Training & Licensing Exam F Administrative (5) G Operational Error Exhibit I Same Source as above. l H Other (Explain) { t t I L:\\WIC,PROCPLNTMGRiGFS9410016.94 i I h

l [ 3.6 UNTT 3 SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH December,1993 NO. DATE TYPE (1) DURATION REASON (2) METHOD LICENSEE SYSTEM COMPO-CORREC-(HOURS)* OF EVENT CODE (4) NENT TIVE SHUTTING REPORT # CODE (5) ACTIONS / DOWN COM-REACTOR MENTS (3) 8 931204 F 0 B 5 NA NA NA SEE NOTE I BELOW i Year to-date forced outage hours = 1707: Cumulativs forced outage hours = 18,239 Note 1 - Half core scram testing performed in accordance with Dreaden Technical Surveillance (DTS) 030(M)2, Control Rod Drive Scram Testing and Scram Valve Timing Test. TABLE KEY: (1) (3) F: Forced Method: S: Scheduled 1 Manual

2. Manual Scram (2)
3. Automatic Scram Reason:
4. Other (Explain)

A Equipment Failure (Explain)

5. Imad Reduction B Maintenance or Test C Refueling (4)

D Regulatory Restridion Exhibit G Instructions for Preparation of Data Entry Sheets for Licensee Event Reports (LER) File (NUREG-0161) E Operator Training & Licensing Exam F Administrative (5) Exhibit I Same Source as above. l H Other (Explain) i I i l 1 L\\WK PROC \\PIRTMGR\\ GPS 94\\0016.94 I

i' p l 3,7 UNIT 2 MAXIMUM DAILY ELECTRICAL LOAD FOR THE MONTH OF December,1993. Day Hour Ending UNIT 2 MAXIMUM DAILY ELECTRICAL LOAD (KWe) 1 2400 712,000 2 1500 804,000 3 1200 803,000 4 1600 792.000 5 0100 780,000 6 1000 790,000 7 0200 803.000 8 2400 799,000 l 9 0100 802.000 10 1300 801,000 1I O100 726,000 12 1900 503,000 13 1900 779,000 14 0800 793,000 15 1200 763,000 I 16 1000 765,000 17 0600 763,000 18 1800 782,000 19 0900 782,000 20 1800 783,000 ) i 21 0400 784,000 22 2l00 787,000 l 23 0600 786,000 24 2300 788,000 j 25 0100 788,000 i 26 2100 789,000 27 0100 789,000 28 0800 789,000 1 29 2400 776,000 30 1500 788,000 1 31 1000 790,000 ifWK,PROCPLNTMGR\\GFSW10016.M

3.8 UNIT 3 MAXIMUM DAILY ELECTRICAL LOAD FOR December,1993 Day Hour Ending UNIT 3 MAXIMUM DAILY ELECTRICAL LOAD (KWe) 1 I800 728,000 2 1200 728,000 3 1000 725,000 6 4 0100 694,000 5 1500 757,000 6 0100 733,000 7 1100 713,000 8 0100 710,000 9 0100 703,000 10 1000 704.000 11 0400 702,000 12 0100 697,000 13 0100 694,000 - 14 0100 692,000 15 0100 689,000 16 0100 680,000 17 0100 677,000 18 1400 671,000 19 0100 669,000 20 0700 667,000 21 0100 664,000 22 0100 661,000 23 0100 659,000 24 0100 656.000 25 1000 656,000 26 0100 654,000 27 0100 650,000 28 0100 647,000 1 29 0100 644,000 I 30 0100 639,000 31 0100 637,000 IdWK_PROCPINrMGRCI'S9441016.94

r-3 t .F i' 4.9 UNIQUE REPORTING REQUIREMENTS 4.1 MAIN STEAM RELIEF VALVE OPERATIONS None 'l 4.2 OFT-SITE DOSE CALCULATION MANUAL (ODCM) CHANGES ' None t f i l i ^I I l l i 1 'i 1 l i 1 l i i 1 l j i l \\ l l 12\\WKJROC',PINTMOR\\GI'S94 \\0016.94 I

I - i t i 4.3 MAJOR CHANGES TO THE RADIOACTIVE WASTE TREATMENT SETEMS DURING j December,1993 None. 4.4 FAurn FUEL FJRMENT INDICATIONS l i 4.4.1 Unit 2 Unit 2 fuel perfonnance during December,1993, continued to show no indications of leaking fuel. 'This'is based'on the ; i sum of the activities of the six (6) Noble Gases as measured at the Recombiner. Therefore, Unit 2 had excellent fuel performance. 4.4.2 Unit 3 j Unit 3 fuel perfonnance during December,1993, continued to show no indications of leaking fuel. This is based on the' { sum of the activities of the six (6) Noble Gases as measured at the Recombiner. Therefore, Unit 3 had excellent fuel perfonnance. t - I t i e f LdWK, PROC \\PLNTMGREFSM\\0016.M j i [ -e., --y = .w y -e-

k j 4 j. i 1 l 1 + i j i I l 5.0 PLANT OR PROCEDURE CitANGES, TFSTS, EXPERIMENTS, AND SANTY RELATED MAINTENANCE - l 5.1 Amendments to Facility License or Technical Specifications during December,1993. I None. i 9 i i i I t k i 2 i t I .Io [ 1 i f I I i L:\\WK PROC \\PLNTMGRiGPSW\\0016 94 i I

i 4 i i I 5.2 Additional Changes to Procedures Which are Described in the FSAR (Units 2 and 3) during the months prior to July 1993. Only those procedures that required a new or an additional 10 CFR 50.59 review of changes are. r included. Changes implemented between July,1993 and December,1993 will be reported along with the FSAR updates in accordance with 10 CFR 50.71(e). i a PROCEDURE TYPE PROCEDURE NUMBER PROCEDURE TITLE /

SUMMARY

OF i DESCRilrrION CIIANGES None I i 'l j i LSWK,PROCPLNFMGR\\GFSH\\0016.M

i 5.3 Significant tests and experiments not described in the FSAR (Unks 2 & 3) i i No Special promdures involving tests not descrital in the FSAR, which were approved during the months prior to July,1993, were reported to Regulatory Assurance. Special procedum impWM between July,1993 and j Decantur,1993 will be reported along with the FSAR updates in accords-with 18CFR$8.71(c). I l J i i i L:\\WK,PROCvtNTMORiOPS94\\0016.94

i i 5.4 Safdy Rdated MaiWe==are (Unit 2 and 3) l Safety related maintenance activities for December,1993/ January,1994 (i.e., approximately Decanber 15 through January 15), are summarized in the attached tables. i f i

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DRESD H I!N1f. SAFETY DELAIi D MAith ElMNCE NAfuRE OF I.ER OR OUfnGE MALFur1Ci10H E00It' MENT MAINTENANCE NtlMBER CAtlGE RE E.UI. T CDHRECTIVE ACTION 2 DOS 2122:30:Hi PRFeFNTTUF H/A VAL 9E A0 SPLIT 00DYs SCRAM 007249 RFPt AiTD D1 APHR60lt.__101tGUf Ti Th_ 2011_/LES OUTIET VALVE CUMPLElED MANIENANCE SIEPS TO J-1-H AS PER DHS 0300-01 PEV 0. STROKED AND ADJUSYED VALVE TO SPECG. 2I305-127-34-b1 i PEULill I VE tl ' A I:t FER 10 liH3 0 300-01. UAlUE AD SPLIT BODY, SCRAM h07250 UUTIEl VALVE z -305-11. ',-3 4-5 ~ PREVENTIVE N/A REFER TO DMS 0300-01. "ALVE A0 SPLIT BODY, SCRAM 007317 ldLCI_VALVF 2 905-126-38-51 PREVENTIVE N/A INSTAt.LEn NEN DIAPHRAGH. 10R0llED TO 30 VALVE AQ SPLIL_Ennv. crpAu nn7ain INLET VALVE I r n im _ nTr:nvrn ANN AD.fllM TEh UAl VF TI) .UPECS 2-305.J "' A-4 ?-r;! rnrurHTTUF n/A -- --- i---- - TNsTAt t Fn NFW n r AP11RAGM. ' r!_rANcn/LllnEn UALVE A0 SPLIT 00DY, SCRAM D0731Y INLET VALVE DULIING MAIERI AL. STROKED AND ADJUGIEtt VIV TO SPECS. TOROUED STFM NUf/30 FT/LBS COUPLING NilT ID 10 FT/LBS. 2-355-126-30-47 PREVENTIVE N/A . REPLACED DIAPHRAGM. TOROUED BULTS 10 32- + --------- VALVE A0 SPLIT BODY, SCRAM.- D07320 'FT/LES. BAGGED. DUST COVER AND COUPLING.i INLET VALVE-

STROKED AND ADJUSTED.VLV PER SPECS.._

2-305-126-38-43 PREVENTIVE N/A hEPLACED DIAPHRAGM. CLEANED /LUPED ALL - -----~ VALUE A0 SPLIT BOGY, SCRAM 00'7321 INLET __ pat ur DOLTING MAlERIAL. TOROUED STEM NUT TO 30 FT/t_DG_R COUPfTHM Nt1T 10 10 FT/LD91 fBTROKED. AND ;ADJUSTEDJ+ALVE TO 5Fu.'u ' - hn ; e~n M,, x ' m w g g g, m. e g u. -- M s .,: n m yx e ~$ 9----- ? 4 2-t A~ 2 305-126-4'6-43 1..; PREVENTIVE M" -or n ,...,r w a .x ',1N/A

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, i J :i 'Al'E AD SPLII DODY. GLRAM 1:07 L ' 1:, Pt ni f D D t f.I'llRAGH. gel l'l:EG EUI:E. Idii T VALVL .-305-126-33-27 PREVENTIVE N/A REPLACED DIAPHRAGM. SET PREG 5thsE. "ALVE AD SPLIf RODY, SCRAM 00735! hJLET UALUE 10 0 PREVENilVE N/A - - ~ finUGEb bHPI'0F: ( STEEL Willi C INnTALLING. M[uC SYSTEM Ludi'ROL.RUD DRLUE bu2359 llVDRAllLICS Hn ADJURfMiirfH df F F4 fie uuHIEf1 Cit HP 1.005E JAM NUTS. 1022n 47n pproFNTTUF H/A tlNPACXrn utU rn iAlu m _p m _ RFPArJFR "AluE MANUAL FN INBDAPf t liO 7 161 1001ATION M R DMU 040-07. Fall.LU phi. th W Huf:K REO D1701U. ~ 2 0220-43 PREVENTIVE N/A REMOVED PACKING / REPACKED. VALVE MANUAL RX HEAD VENT - D07364 OUTDOARD .,,._ 9 Q 9 m, N. M ..w 2-0220-45 PREVENTIVE N/A TOROUED PACKING GLAND ON 2-220 - - - - - - - - - --- ----- 9ALVE A0 RECIRC LOOP OUTBOARD 007367 SAMF1E.Inni (3 FT/LBS) PER DMP 0040-0/. LUDED STEM. ~ x

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DPESDEN llNIT." SAFETY RELAli'D MAsN1ENANCE NAluRE OF l.Ek OR OtilnGE MALFUNCtidN EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 2:1601:21._ - PREMERL11!E N/A HI PlaED A)P HOSEL _EHLrg[D 1H V's, OPERATOR A0 VALVE DRYWELL VENT 007783 J NSPE(.lLD OF FRA10R. REPCACEO Li ASTOMERS liURINb REASSEMBLY. TOROUED TO PROCE DURE. [1T01-24 PhEVENTIVE IUn ht PL Attu ACUAIUR HOSES, Us.V, HISASFNBlED GPERATOR A0 UALVE DRYNELL UENT 007/06 )HuPEfYiD AND REPA1RfD A1R OPIhA10k PER bhp 1/01 0?. 2-1601-318 PREVENTIVE N/A LOWERED COUNTER WEIGHTS 04 ARMS. REMOVED "ALVE VACUtlM DREAKER TORUS TO 007707 RLOUlf DING I Ti n BONNET FOR INSPECTION. REPLACED BONNET 'llGING NEM O-RINGS COATED HITH fl0W 1: URN [l-G bb, 2-1601-32F PREVENTIVE N/A INSPFCiED PER DMS 1600-3 AND DAP 1400-3. "ALVE VACUUtL13RE6KEh DF3HI LL TO 007791 10RilS 32F Pl RF0f: MFD 'f 0Rollr TES T fHFH REPLACED 0-RIIES nNO A55EMDLED. 2-1601-33A PREVENTIVE N/A PFRFOPMFD TOROUF' TEST PER DMS 1600-03 V4fSL VACUllM UREAKER DRYWELL TO 007 /'m TURti5 33A kl.V Oi> bu ) t-2 AND VAh5LD. 2 2 1501-33C PREVENTIVE N/A r-VALVE VACUUM DREAKER DRYWELL TO D07797 PERFDPt1ED lOROUE TESI PER DMS 1600-03 TORUS 33C REV 01, SECT _I-2 AND PASSED.- L _,. y "X Cg,, T .e4,* M' e e 2-1601-17B PREVENTIVE N/A REMOVED /REINSTALLEDRELIEFVALVEPER.'w[5 7 VALVE RELIEF B HEAT EXCH OUTLET 007812 HEADER DMS O(0-01. TOROUED TO,70-78 FT/LBS W M 1 ~" '? I ; - ): i @y@/4EN$ta-OM---~M $;dUlbk% N h?h@hh Ih T 4 s; 2h1501-17A 1PREVENTIVET' '------- " W: TESTED 5VALVEdTaii&OUNOWIFTTAND ~ 1:'N ~ i*~h ~ ' VALUE priTFF R HFAT FYrH DUTLET' n07 91'1 ~ s -' PASSED 2 " TURNED DUER ~ TO - M.M.E.G1 i M E - HEADER y% n 7- %

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[,.,2BOTT0H. HYORDSTATIC TESTE . NEW-TUDES, PLUGGED.1 AT IUBE-SHTS lur 1 ~~ a u N, ~(DHP 1000-12. REINSTALLED HEADS PER; PROC. i a. 2--1503A iREVENTIVE N/A kl.f10Vt.0/CLLANED/INSPEC1ED HEADS. REMOVED liEAT EXCHANGER D LPCI 007010 110 TUDES PLUGGED 6 AT TUBE SHTS TOP & DOTT0tl. IlYDROSTATIC TESTED EXCllANGER PER DMP 1 GOO-1'). RFINSTAfLFD HEADS PFR PROC. J u. q - 4-, j, ' r;. c z -m - - Q f ',. W $p U 4 qf.17 - ; (2p q g :p wygg s n* .,5ka..y A.. D 9 d. . _..~,. _. - -. ~

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ORESDEN UNfI d SAFETY MELATi.0 MAltilENANCl NATURE OF IER OR OUlAGE MAIJUNCTION EQUIPMENT MAINTENANCE NUME:ER CnUSE NEbOL T C0hkECTIVE ACTION 2-1699-13C PREW444. VALVE RELIEF C LPCI PUMP 007017 <-:! M 0"! Ti PE'. I r r natyg _ ggur _ ppp 7eg ringu GilCTION f:EINSTALLED 2~1699-13A PREVENTIVE H/A REMOVED REIIll VALVIG SEHi 0FF TESTING, VALVE RELIEF A LPCI PUMP N07G19 SUCfION RL IN5 f Al.l.EH 2-2301-53 PREVENTIVE- 'N/A. ~ VALVE RELIEF flPCI OLAND SEAL D07325 . REMOVED R.V.' CAPPED ENDS. REINSTALLED) CONDEh!SEP int rr VLV AFTER COMPLETION OF SURVE(LLANCE Ac no i n en 2-2302 PREVENTIVE N/A PUMP HCCLMMp nnynm> blSASGEMBLED COUPLINGS, CLEANED, rm innrn. prrtArrn urTu arw neracr Awn REASSEMBLED COUPLINGS. .2 2au _m 'enorterror u/A Arunctrn ernoo eno cwTvrure A n rJ:n n'n SHI5H RECIRC LOOP RISER DIFF 007a44 ~ ~ PRESSURE BMITCllCS OK. CALIBRAIION OF INDIVIOUAL GHITCHES PERFORMED AFTER llI/LO STOPS ~ Nt:RE CllECKED/ ADJUSTED. 2-261-34B CORRECTIVE N/A , ADJUSTED STOPS FOR SNITCHES A & C.,B E D. SHITCH RECIRC LOOP RISER DIFF 007G44 'SWITCilES=0K.' CALIBRATION OF INDIVIDUAL h PRESSURE ~ J SWITCHES: PERFORMED AFTER HI/LO, STOPS. ~3 urcr currrrn/An.tuctrn _ ^ 2 -261-34C CORRECTIVE H/A SWITCH RECIRC LOOP RISER DIFF 007344 ADJUSTED STOPS FOR SWITCHES A B'Cf B.8 0 1 PRESSupr SWITCilES OK. CALIBRATION OF INDIVIDUAL: " tutTrurn prcrnr,mrn ArTrrs uf/tn cTnpa JM n&& gn 3: - Q u Q &rM jpMERE CHECKED /.4DJUSTED.g g g e WN/n 3/4 AA M * ---p: w M_& gg 4 ug gs uA 2 2 261-34D -? CORRECTIVE,~ f4 s _ a :. - m AM < --- b 1 ADJUSlED:STOPSTOR)SWITCHE90 At --S sg.Tru cerfor i nne orcro nTrr nn?nu r' PRESSURE nuftrurn nY_ ralThDATinM nr1TNnfU u UNITCHES PERFORMED AFTER HI/LO STOPS' WERE CHECKED / ADJUSTED. 2-17n t. gn r>rtrOFNT T UF H/A finFD MMP 040-OA. nMP 040-07. EllANnrn DLIT OPERATOR AIR ISOL CDSR STEAM 008493. DIAPHRAOM AND REPACKED: VALVE. VERIFIED M VENT TO MN STEAM "O

1" STROKE ANDiLIFT PRESSURE 32 PSIG., @

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DRESD!U UNii SAFETY RELAii0 HnIN)LMANCE NAIURE OF lEN DR 00fnGE MAU lHF l uid EQUIPMENT MAINTENANCE ?HMBER En%E RLSUI I LOUREPTIVE ACTION 2 2 do2:1_ LtFeriaT Tur v /A etiMP tilnAPmt Fn M W RitTAlllm A9nFMf:LY PUMP HPCI BOOSTER D10167 1NSIAllED HIllt UEW OLARINGS AND SEAL 4 PORTS. PUMP 1NTLRNALS AL16NED !:URING THE ~ AUSEMBLY PilASL. 1601-20A PREVEN 11VE fl / A Ol'EMATOR A0 VALVE DRYNELL VENi D1017t. INSTALU D AND REr10VED fESI TAf*S FOR T.S. If 5 TING OF 1600 VALVi:, Al l HORK 00HE PER STATION IRAVELER. ADhRESSED Al L OC WELD Pil1 HT C /ihn PMO'q_ 2-1600 PREVENTIVE N/A WORK FFRFORMEn PER NWR D10177 AND. MISC SYSTEM PRESSURE 010177 SUPI'EESSinu PACKAGE D10177-01. 2-4899-77 PREVENTIVE N/A VALVE _RELIFF f: 1 O f' T ffT FX TilRF fi10179 REMOVi.fi 801 TS, OASKETS. INSTAlIED NEW SIDE G AOK rt AHn Pal 1Cg E. REPLALFh htit_TS AND luROUEli PER REGUIREMENIS. 74 01/LDS. 2-110Mo PRFUFMTTUF H/A ---= - - - --:------ RFMnUFO ntn RU_ P! FANFD F: Agnpd Ayn VALVE RELIEF A STANDDY LIQUID D10132 CON 1ROL ACCUM 1HSI Af.i ED HEW RV HIlli GAGXETS, TOROUED JHLET 001.TG 10 320 FT/LBS, OUILET 1:0LTS TO 74 F1/LDS. 1 2 300 PREVENTIVE . N/A ". . - - - - = - - - -.-------- > . REMOVED FLANGES, INSTALLED PIPINGiTO SYSTEM CRD PIPING / WELDS CLASS., -D10194 ~ ~ ' ^ " ' . ~ -. HYDRO'AZE~ LINES PER SATION TRAVELERtV, s T REINSTALLED FLANGES., j g! II 2-1500 PREVENTIVE N/A MISC SYSTEM PRIMARY CONTAINMENT D10227 REPLACED EXISTING FLANGE W/ TEST. FLANGE -AFTER ORYNELL PRESSURIZED TO TEST CQGtTNG F'RFARHRF kr'MnUEn TERT FLANOF/Rf f hteTAt i tre -.- 3 eW -ORIGINAL.;,SATFIO ; ALL.DC HOLD /WITNESSi ria p-l--y % T. L. M ---- @, W"m: A 4:L, 1 f .,. ; ;.v . r s wp ?2 c.,. f -+ ., _3m.,, _ 2 0220-32C'. ---v i c 0ISCONNECTEDMECONNECTED) AIR E LPREVENTIVEi ~ ACCUMut ATOR ATR - MsIU ~~1r1 'nio225' ~ % ~*JN/A W~ ' Mk 'GUPPORT :ILRT;: ADDRESSED ALL PMu' 9 ~ ~ WC HOLD PIS.., x., l &} f&g..,, th a l 2-160?-c rnRRFPTTUE~ M/A - WORK COMPLFTFD PER' THI9 NWR AND1FCIIM'#^ ---=- - - - MOTOR C.LPCI. PUMP. D10246 -NORK PACKAGE D10246-01 4,

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DREGih N flNai. ' SA! E IY RELA (! 'l Mn J rn EN,itirE NATURE OF l.FN OR DUIAGE MALFUNCl[0N EQUIPMENT M AINT E MANIT NUeli:El: CAUSE kt:UUL f f:0RRECTIVE ACT[HN ! -46 0- 1-- - ! WOE 4ITVE h ' JPERATOR h0V MAIN STEAM DRAIN D10350 3 HOT;a_! E D - Sf'k1MG PALK: e:EA51 Eriitr "dLVE KIT. RLMOVLD ANI) INGTALLED OPlRA10R PER DNP 0010-15. 10R0llED ALL REQUlkED DOLTIUG. Nb':02 4A ef:EUEni 1 VE n.' A la it AMD WnPli Bf ARINu, SE1 SCI:CHG, ni:Pt:AlOR MOV nt0J51 TRINis PACK, IIGHTENFD AlL 001.T1HG ANO I UU I N F,. -1201-3 PREVENTIVE N/A NdTOR MOV D10354 INSTAlLFO NEW SPRING PACM, NEW GREASE RtLIEF KIT, TIGHTENED All. BOLIING. IWPi t.Er n Tf1RfJ11F nb8 f TCH _ 2 -1bO1-1] A PREVENTIVE N/A LAC'O '. IN3TAl l.ED NEM fire ASE kF LIEF dPERAIGR MOU in o m 1 !!RF _ VHnIniiin HFU n!?L6L1__REL 1 FF k iI. RLPLACED Si' RING PACK. !L21501:2?A rorurHTTur M/4 THRTalIrn UFw RPRTHn Porv. TNnTAIrrn NFw sit'ERATOR MOV ti l0 R e tHEASF hlL1EF KLT. ~ 2-1501-278 PREVENTIVE N/A INSTALLED NEW SPRING PACK, GRLAGE RELIEF OPERATOR MOV D10367 KIT, NEW TORQUE SHITCH. t 2-1bO1-28A PREVENTIVE N/A OPERATOR MOV D10360 REPLACE 0 SPRING PACK, GREASE RFLIEF KIT. 2-1501-28B PREVENTIVE N/A INSTALLED NEW SPR1NG PACK, GREASE: RELIEF OP.ERAInR Mnu n10 L49 KIT AND NEW TOROUE GNITCll. albO1-un rRrOFNTTUF N/A TNRTAl I Fn NFW RPRTNG PArl(i GRIARF RELIFF OPERATOR MOV D10370 K1T. q$ U 301-8 PREVENTIVE N/A INSI AI I EH n f:ALANCED Ni H 10R00L SWITCH, OPERATOR MOV HPCI PUhP DISCH D10371 1G01 OllTDD REPLACED SPRING PACK, OACKE15 4 0-RINGS, TIGHTENED ALL BOLTING R SATISFIED ALL llOLD POINT 9. >.p wo w:w.am m 6f- .+

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tit?E50 d ifriIT.. SAIETY HELAit'D MAINfEdaNCL-NATURE OF i ER OR DUroGE mal filNC TION EQUIPMENT MnINTENANCE HUMDER CAIJGL REdill r CORRECTIVE ACTION 2-300=L4 PoEoENTIUE " ' ^ t.r sno!p rr:n gi. i i CONTROL RDD DRIVE POSITION 4LO4 D10403 _nr 1-a. rugtorirn enn 9220 WilICil HAG BEEN LEAK TESTF.D AND PASSED. 2300-P00 PREVENTIVE N/A RI MOVITt CRP 901 FROM LOC P-0. INSTALLED r0NTROL ROD DRIVE POSITI0t1 BP03 U10404 CRD A274/ (1972) TRANSFERRED G/N TO CRD REBUILD R00r4 1-300-L 11 PREVENTIVE N/A REMOVED CRD 963 FROM POSTITION L11 AND-CONTRGe ROD DRIVE POSITION #L11~.D10405 INSTALLED V440. 4 2-300-009 CON TROL-ROD-DMUC EDCLTIDH ' 00 - PREVENTIVE N/A REMOVED CRD 109Cs LOC 0-9. INSTALLED CRD 010417 ^ m unrrn nan nrrn irav Trc: rrn own PASSED. g.._30 & t" rnEururror-n/a-poiien enn tna renM inn nt? tve t9Aru 1 CONTROL ROD DRIVE POSITION BP12 010119 PUT IN CRD A1051 IN l.00 P12 WR 1772) PFR STATION TRAVELER. TRANSPORTED CRD 153 TO CRD REBUILD ROOM. b-300-P11 PREVENTIVE N/A PULLED CRD 772C-1967, PUT-IN CRD,1020 p

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==- REMOVED CRD 275-1967, FROM LOC P10s 3 INSTALLED CRD A9344-1992 PER f;TATION' Tt2AUrl : R _ Yt2aMilonDTrn 97M 70 t'Dh DrLi f fl_ h - w ~; - q pg.g;f, g jg.y;gROUN r,,,...,4., 3gg @Q qfgyq ~n --~%. sw m .~ ~u C(IMD0' DOM DDIt.rr encirigu at42- ' PREVENTIVE? KN/A # 'r '~ ' --- R n. 24300-L13- ~ -.. -- K FREMOVE0JCRD 6910,3AND?, INSTALLED;cROlit s... nio m 12 20^-vsn peroruTror n/a nrwnurn con At rnnw rnstTrnu ren aun CONT ROL ROD DRIVE POSITION? 4K151 : 010423 INSTALLED'2018., - +- V 2~300-F15 PREVENTIVE H/A -- - - - - -- - - - - - - - ~ ~ ~ PULLED CRD 957 FROM LOC r 15-1W.Y. l'UT Ih iCONTROL ROD DRIVE POSITION 4F15 010425 CRD 1YO42 LOC F15-1992 PER STA110N TRAVEikR. h hh -r 4 I .s...- se app w ww% _ .u-epe n i . ~ - - - - _. -.. _.. - - _. _. _ _ -. _ _. _ _ _ ~. _, -, - _ -. _ _ s a. ...w ne-,-., .-m, ,-----wa, .w-,

HMESDI.il 1)NI T.: HAF ETY met A fi O M6IfifENANG NATURE OF ! ER UR O!!1 AGE Mol f IINC110N EQUIPMENT MAINTENANCE NUMDER CAUGL RESULT CORRECTIVE ACTION . 300--EL3 l'RFUFrlT T UF M /A CONTROL ROD DRIVE POSITION BK13 D10420 Rt'HOVEf t CRn N47C AND IN51AltEn CRD 18313 PI-R MMP/fRAVELER. ' ^ 3 0-K14 PREVEt!TIVE N/A RtPLAttD CRD b910, POSITION K14 H/1028. FONTROL ROD DRIVE POSIIION bKt4 01012'/ -300-K2 PREVENTIVE N/A REMOVED CRD 959 FR0 1.0 CATION H2, i.ONIROL ROD DRIVE POSITION 4K02 010430 INSTAtlED CRO 270 CllECKED 0-RINGS.AND llMCOUP1ING ROD, TOROt!ED CCD. .F300-K6 PREVENTIVE N/A REMOVFD OLD CRD AND INSTALLED NEW DRIVE i00NIRuiJ 00 DRI.VE POSITION PK06 D10431 PFR SinT(OH TlOWELER. 4 ..n300-LO3 PREVENTIVE 'N/A 2-REMOVED CRD 728C FROM L3.-INSTALLED CRD _ CONfROL ROD DRIVE POSII10tl &LO3 010432 i vo9 Ft:n 8f AiiuH TRAVLLt R. TRAN6PORIED 1 CRD 720C TO DRIVE REDUILD ROOM.

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x-__ ORESDif! tih I T./ gal ETY RELA 11 D MA)NiENnHi:E NAFURE OF LER UR OUTAGE r4ALF Udt:i r()N EQUIPMENT MAINTENANCF NUelF.ER cal!SE REGULf CORRECTIVE ACT(ON 2 -200=M3 Pf.rurnirur m'A CONTiiOL ROD DRIVE POSITION (M03 D10439 prmnVin enn 79 rnnh i nrArTDy in Aun REPLACED WITH REOUILT CRD 717C. DID SfEPS PER STATION TRAVELER. INSTALLED 0-RINOS. TORQUED CRD. c 200-M7 PREVENTIVE N 'A CONIR0! ROD DRIVE POSIIION BM07 f r104-10 Rf MOVED CRu Y/3 FROH LOCAIION n7 AND REPLACED WtTH CRD 8297 '_-300-P4 PREVENTIVE N/A CONTROL ROD DRIVE POSITION iPO4 010441 REMOVED CRD 259 FOR P-4. INSTALLED CRD~ 1022 l'UR P4 PCR STATION TRAVELER. 2-7020-7C2 PREVENTIVE N/A SH6R Bng_ny rerrrpr rsr nincu ut u n t nmo 01.EANLD CONTACT CARRTERS S P0t.C PII:CES. 2-202-5A nrPt AfTh Aux CDNT ACTn _ lie 11ACEn OVERl OAD_ RELAYS. TESTED CAPABILITIES OF OVERLOADS OK. VERIFIED _0PERATION. 2_7n?n -i. f 4 pnrurHTiuF N/A -- 2 r m SHGR ORK ISOL COND RX OUT ISOL D105G:1 PrRFnPMFD THFRMOVfRTON_ ~ RRR W!!If F OPFRTri VLV 2-1301-1 AUD 003 lENP CLEARED BRK. OPERATED OK HITH HO fl01 SPOIS. 2-2301-7 PREVENTIVE. -N/A

TACK IcELDED PER MMP STATION TRAVELER REV VAVLE CHECK A0 HPCI INLET TO.

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IstmSDi d (JNI f S AFETY gel. A ll'D MA IN I EtinN!:1-NA(URE OF IER OR OlnAriE mal f flNC f ION EQUIPMENT MAIN T ENM'CE NilNDFR Coln,I REbilt i

.ORRECTIVE ACTION

_:-6/23 2 irruruTiur H/A UllS CUBICLE Fl!ED LP COOLANT PP N10770 rirquin Ann T Hwrn Trt) fItnintr. prptArrrt ~R-1502 UlATIONARY AUX SWITCll AND POSITION SWITCll. '/23 31 IT:EVENTIVE ?! ' A Dlib CUCICLE FCED LP CDOL ANT PP (110?95 Cl E At!i.D ANO l.llBl:D CUDICI E. REPL ACED Tile 2n 1502 i'OSI T i uti AND AUX SWIICitEs LIKI. FOR LIKE. b6/24-25 PREVENTIVE N/A PERFORMED DEG 6700-4 REV 2. BUS CUDICLE FEED LP COOLANT INJ D107?6 i R ?C=1T.02 2 -20 3-3 A PREVENTIVE fl/A 1IFTEh SOLI:N01D USING l.IFTED/t.ANDED LEAD St)L ENUID_I ARGLT_ ROC!L.W.LVI ^ D11n o *' nurrT. ni Nr:tt frnTrn (N r,u n s ar $rc A r rts PROPERLY. PUT BACK Otl ALI. HARiiWARE SNUG TIGHT. perornitor o/a r:rpt Af rn reri av rnis K!1AY URYNELL FLOOR IIRAIN SilNP D110]? PilMP .[-595-138 PREVENTIVE N/A CHANGED RELAY AND COIL. RELAY PROTECTIVE DW FLR DRN D11040 SUMP PUMP INTLK 'f m 2-5Y5-13Y PREVENTIVE N/A REPLACED RELAY. TESTED: MET SPECS. RELAY PROTECTIVE DW FLR DRN D11041 SUnR-RUMR--IN W 'r .p ygg p 2-1501-238 PREVENTIVE LN/A -M--- --k [ REPACNDfVNLhEP$ 2 ;,' d ^hM%MM v4tyg wn na7g n tect m woav ru ir>7 INCD 2-itiG1 - Un rcrurMTTUr N/A f't FAN 1/n = TH ATAf I rn NFW PArtt TNil WTTH I TUr __ VALVE MO GATE LPCI DISCHARGE D11224 HEADER CROSSTIE LOAD SPRINGS AND SWING BOLTS. TOROUED.iTO j 21 FT/LBS. 'c

  1. J N1601-388 PREVENTIVE N/A REPACl-CD VALVE. INSTALL 1.IVE I.0AD UAi_VE t10 Gl.0Bli B LPCI HDR FULL D1122G SPRINCG AND SWING col.TS. f0R0lJED TO i

FLON BYPASS DI: 67 FT/LBS. ^ 4 e..- !A., <k}lhb$h q "/ P ' .#1 ^;te ~ 4,%

fli ESD: ; UN1 T. SAFETY REl AT1 D HA1NlENANCE NAllJRE OF l.ER OR OUrAGE MALrHNLio)H EGulPMENT M A l tn E N AHEE HUMBEls chuSE RL::UI.T CORRFCTIVE ACTION 2-E.;01.:4_ _.. LunnreTIUr

u. A u pArjt n U a VI WIIML_LOAll_]D 21 FT /LI.!S 2 YAl.VE GATE MO HPCI PP SUCT FFM 011020 CND Si TK ISOL i:YCL Eli VALVE ANie REinh00ED.

2-2301-9 IFEVENTIVE U/A UALVE 6 ATE NU HPCI PUhr DISCH i11229 Ul EAfd b STHFi it'G f:0X fi S11 M. )UG1AfLED ISUL f.)VE f uAli PAngIni, gjlh CANDON $ pat:f R R B RINH i /.CV ING. TilROUEli NilTS 10 79 FT/ lim _ 2-2301-36 PREVENTIVE N/A VALVE GATE MO HPCI PUMP SilCT U11231 CUTOUT LANTERN RING, CLEANED STUFFING IROM.TDRUS_Isnt DOX AND STEM. REPACKED VALVE N/ LIVE LDAD 1 ACMIllG-2-2301-10 PREVENTIVE N/A ClEANI11 STIIFFING BOX, STEM & G1AND VALVE. M0_ISOL6TlutLCONDERSEIe h11 m F[LL INLET iOLtOl&iL CLEANED GLAND DOLIS n ANTI SIEZE. REPACKED VALVE A5 l'ER OMP 0040 07 2:140 M A pnrurHTTUF H/A RFPACFFn UA! Ur W/R ' RTNA CrT. CARRON VALVE MD A C0f(E SPRAY PUMP h11231 10h0S SilCTION hl' ACEL;, l.IVE I.0AD SPRINGb AND LYEDULIS. 271402-38 PREVENTIVE N/A VALVE M0 A CORE SPRAY PUMP D11235 CLEANED AND INSPECTED. INSTALLED 5 RING: TORUS SUCTION PACKING AND LIVE LOAD SPRING STACKS ON.- NEW PACKING STUDS. . 4; 2-- 1501 -5 A PREVENTIVE N/A VALVE NO GATE A LPCI PUMP D11240 REMOVED OLD PACKING. CLEANED 3 INSPECTED SUCTIDN STUFFING BOX AND VALVE STEM. DROPPED. t ANTrr H niwn Tn nnTTnM nr nitfrrtwet renv. 2-1501-50 PREVENTIVE N/A1 INSTALLED ADDITIONAL. BUSHING. REPACKED.,L .w.

. A M @~ AO ValUF Mn GATF R IPf'T PifMP nii?41

~ 2 ~- REMOVED OLL PACKING.' INSTALLED: SllCTION RPRTNilR AND ~ NFl4 PACKTNG. 'LIVC10. u:' 2 d5n1-1 M parurwTTur u/A ritT AHn TNRTAl i Fn A PADPAM MPorfR _ VALVE MO GATE A LPCI HEAT D11244 EXCllANGER BYPASS REPACKED VALVE W/NEW PACKING & INSTALLED LIVE LOAD SET,P. TORQUED. bl601-110 CORRECTIVE N/A IINPAC!;ED. REPACKED VALVE. INSlALLED LIVE - - - - - - - ----- ~ ~- VALVE MO GATC 8 LPCI HEAT 011245 CXCIIANGER DYPASS LOAD UPRINGS. y;q , %y y s. ~- '.w /C_ ]$ i mg

^ - nRESDCN UNIT 7 SAFETY RELA WD MolNIEtlANCE NATURE OF IER OR OU1 AGE MALFUNCTION EQUIPMENT MAINTENANCE NUMDER CAUSE RESULT CORRECTIVE ACTION 2 ;1GOL 171A rfwnrrT1ur w/A VALUE MD GATE A LPCI MIN FLOW D11244 itNPArgC n_ r:FrArxrn VALUF. INSIM i rn i TVE-LOAD ASSENGLY. 2 NEH EYEBOLTS. TORQUED 10 5 FT/LBS. c1001-13B CORicECTIVE N/A "Al.VE M0 GATE A LPCI Mitt FLOW D1124/ DiSASSEMDL1 D/RECONDIIIONt O/l1Lt.lC CHCCKED. REPACKED VI.V AND MOV INSI'ALLEO. REASSEMBIEO. .. 1601-19A PREVENTIVE N/A UNPACKCD, REPACKED, LIVE LOAD INSTALLED UALUE M0 GATE A LPCI TORUS .D11240 IN VALVE.. GCRAY__IlDit_INnn 2-1601-198 PREVENTIVE N/A UNPACKCD, REPACKED H/ CARBON SPACER ] ALUE_ MG GAIE_PL_1_>r t Tnpun nf1?49 oPRAY HDR INDO CHERTt RTON PEM THn, NEW FYEDQLIR AifD NUTS, LIVE LOAD GPRINGS. 10RQUCD BOLTS.. TO 3 FT/LDS.. 2-1501-?nn 'PRFUFMTTUF N/A ~~-L-- IINPACKFD AND THEM RFPACKFn WI1H f_TUF' ~~---- VALUE MO GATE G LPCI HDR l'ULL D11250 FiOH DYPASG INDO LUAU ASSEMl:LY AND ISNTALt I D NLH EYE DOLTS. 61'501-22A PREVENTIVE

N/A

~~ . UNPACKED-AND 1 HEN REPACKED VALVE:5 RING VALVE M0 GATE A LPCI-INJECTION" -D11251

SET CARBON BUSHING. INSTAtt. LIVE LOAD A HEADER INBD 4",

' SPRING,:BOLTSTORQUED.TO-103FT/LBS.gg r 2-1501-22B PREVENTIVE N/A UNPACKED AND THEN REPACKED VALVE.AND. VALVE NO GATE B LPCI INJECTION D11252 HEADER.INHn INSTALLED LIVE LOAD, SPRING SET.,W '- *4 ikl ') I f ,. u .w cv,_ _4 -} i{ - H .f ( y .a c. 4.39 %p w,73,u,.-,y; a v a q-m{uym a;x;m y n,a,a g, i 4 ;. t 7, p 7 m g w .e i en I * ?- --j;g e*

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5.5 Campided Safdy Reintad Mod (=tiaa (Units 2 and 3) No additional modifications authorized for operation during the months prior to July,1993 were reported to. Regulatory Assurance. Modifications impitsnented between July,1993 and December,1993 will be reported with the ESAR updates in accordance with 10 CFR 50.71(e). 1 b f + I .- l l i i i h I i i 1.:\\WK, PROC \\PLNTMGR\\0F's94\\0016 94 i

r i i 5.6 Tunporary Systan Alterations Installed (Unit 2 and Unit 3) A " Temporary System Alteration" refers to electrical jumpers, lifted leads, ranoved fuses, fuses turned to non<onducting position, fuses moved from normal to reserve holder, tanporary power supplies, test switches in 1 attemate positions, temporary blank flanges, and spool pieces. Alterations controlled 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 pmcess are not included. l No additional temporary alterations approved for use during the monds prior to July,1993 were reported to Regulatory Assurance. Temporary alterations made between July,1993 and Decanber,1993 will be reported i with the FSAR updates in accordance with 10 CFR 50.71(e). ? i i e f .[ 4 1 i I 1AWKfROCTLNTMGR\\GPSNiOOl6.M

i i a 5 5.7 Other Units 2 and 3 Required 10 CFR 59.59 Evaluations Other required 10 CFR 50.59 evaluations include Set Point Changes (SPC), Rigging Evaluations and changes to. equipment not reported.3n Sections 5.2 through Section 5.6. No additional evaluations performed during the months prior to July,1993 were reported to Regulatory Assurance. Evaluations perfonned between July,1993 and December,1993 will be reported with the FSAR updates in accordance with 10 CFR 50.71(e). s h Y r L:\\WK,PROCPLNTMGR' OPS 94\\0016.94 5 ._}}

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