Similar Documents at Cook |
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Category:MONTHLY OPERATING ANALYSIS REPORT
MONTHYEARML17335A5621999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With 991012 Ltr ML17335A5631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With 991012 Ltr ML17326A1201999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With 990915 Ltr ML17326A1211999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With 990915 Ltr ML17326A0861999-07-31031 July 1999 Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With 990812 Ltr ML17326A0871999-07-31031 July 1999 Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Unit 1.With 990812 Ltr ML17326A0511999-06-30030 June 1999 Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With 990709 Ltr ML17326A0501999-06-30030 June 1999 Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With 990709 Ltr ML17326A0071999-05-31031 May 1999 Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr ML17326A0061999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr ML17335A5301999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With 990508 Ltr ML17335A5291999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With 990508 Ltr ML17325B5441999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr ML17325B5491999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr ML17325B4631999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Power Station,Unit 2.With 990308 Ltr ML17325B4621999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Plant,Unit 1.With 990308 Ltr ML17335A5201999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Dccnp Unit 1.With 990208 Ltr ML17335A5191999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Dccnp,Unit 2.With 990208 Ltr ML17335A4831998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for DC Cook Nuclear Plant,Unit 2.With 990108 Ltr ML17335A4841998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for DC Cook Nuclear Plant,Unit 1.With 990108 Ltr ML17335A3951998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for DC Cook Nuclear Plant,Unit 2.With 981207 Ltr ML17335A3941998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for DC Cook Nuclear Plant,Unit 1.With 981207 Ltr ML17335A3331998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for DC Cook Nuclear Plant,Unit 1.With 981105 Ltr ML17335A3381998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for DC Cook Nuclear Power,Unit 2.With 981105 Ltr ML17335A2931998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for DC Cook Nuclear Plant,Unit 2.With 981005 Ltr ML17335A2941998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for DC Cook Nuclear Plant,Unit 1.With 981005 Ltr ML17335A2131998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for DC Cook Nuclear Plant,Unit 2.W/980903 Ltr ML17335A2151998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for DC Cook Nuclear Plant,Unit 1.W/980903 Ltr ML17335A1741998-07-31031 July 1998 Monthly Operating Rept for July 1998 for DC Cook Nuclear Plant Unit 2.W/980806 Ltr ML17335A1731998-07-31031 July 1998 Monthly Operating Rept for July 1998 for DC Cook Nuclear Plant Unit 1.W/980806 Ltr ML17334B8171998-06-30030 June 1998 Monthly Operating Rept for June 1998 for DC Cook Nuclear Plant Unit 2.W/980706 Ltr ML17334B8131998-06-30030 June 1998 Monthly Operating Rept for June 1998 for DC Cook Nuclear Station,Unit 1.W/980706 Ltr ML17334A7511998-05-31031 May 1998 Monthly Operating Rept for May 1998 for DC Cook Nuclear Plant,Unit 2.W/980609 ML17334A7521998-05-31031 May 1998 Monthly Operating Rept for May 1998 for DC Cook Nuclear Plant,Unit 1.W/980609 Ltr ML17334B7921998-04-30030 April 1998 Addendum to Monthly Operating Rept for Apr 1998 for DC Cook Nuclear Station,Unit 2 ML17334B7721998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for DC Cook Nuclear Plant,Unit 1.W/980506 Ltr ML17334B7911998-03-31031 March 1998 Addendum to Monthly Operating Rept for Mar 1998 for DC Cook Nuclear Plant,Unit 2 ML17334B7171998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Donald C Cook Nuclear Plant,Unit 1.W/980407 Ltr ML17334B7181998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Donald C Cook Nuclear Plant,Unit 2.W/980407 Ltr ML17334A6831998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Donald C Cook Nuclear Plant,Unit 2.W/980309 Ltr ML17334A6811998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Donald C Cook Nuclear Plant,Unit 1.W/980309 Ltr ML17334B7901998-02-28028 February 1998 Addendum to Monthly Operating Rept for Feb 1998 for DC Cook Nuclear Plant,Unit 2 ML17334A6481998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for DC Cook Nuclear Plant,Unit 2.W/980209 Ltr ML17334B7891998-01-31031 January 1998 Addendum to Monthly Operating Rept for Jan 1998 for DC Cook Nuclear Plant,Unit 2 ML17334A6051997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Donald C Cook Nuclear Plant,Unit 2 ML17334A6021997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Donald C Cook Nuclear Plant,Unit 1.W/980108 Ltr ML17334B6711997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for DC Cook Nuclear Plant,Unit 2.W/971208 Ltr ML17334A6061997-11-30030 November 1997 Revised Monthly Operating Rept for Nov 1997 for DC Cook Nuclear Station,Unit 2 ML17334B6651997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for DC Cook Nuclear Plant,Unit 1.W/971208 Ltr ML17333B1421997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Donald C Cook Nuclear Plant,Unit 1.W/971110 Ltr 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17335A5641999-10-18018 October 1999 LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr ML17335A5531999-10-0707 October 1999 LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented ML17335A5631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With 991012 Ltr ML17335A5621999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With 991012 Ltr ML17335A5481999-09-30030 September 1999 Non-proprietary DC Cook Nuclear Plant Units 1 & 2 Mods to Containment Sys W SE (Secl 99-076,Rev 3). ML17335A5451999-09-28028 September 1999 Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios. ML17326A1291999-09-17017 September 1999 LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary ML17326A1481999-09-17017 September 1999 Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2. ML17326A1211999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With 990915 Ltr ML17326A1201999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With 990915 Ltr ML17326A1121999-08-27027 August 1999 LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed ML17326A1011999-08-26026 August 1999 LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs ML17326A0911999-08-16016 August 1999 LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4 ML17326A0771999-08-0404 August 1999 LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830 ML17335A5461999-08-0202 August 1999 Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates. ML17326A0871999-07-31031 July 1999 Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Unit 1.With 990812 Ltr ML17326A0861999-07-31031 July 1999 Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With 990812 Ltr ML17326A0741999-07-29029 July 1999 LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves ML17326A0661999-07-26026 July 1999 LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr ML17326A0651999-07-22022 July 1999 LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis ML17326A0491999-07-13013 July 1999 LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr ML17326A0331999-07-0101 July 1999 LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written ML17326A0511999-06-30030 June 1999 Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With 990709 Ltr ML17326A0501999-06-30030 June 1999 Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With 990709 Ltr ML17326A0151999-06-18018 June 1999 LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified ML17325B6421999-06-0101 June 1999 LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed ML17325B6311999-06-0101 June 1999 LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions ML17326A0061999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr ML17326A0071999-05-31031 May 1999 Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr ML17325B6351999-05-28028 May 1999 LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions ML17265A8231999-05-24024 May 1999 LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made ML17325B6001999-05-20020 May 1999 LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed ML17325B5861999-05-10010 May 1999 LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised ML17325B5811999-05-0404 May 1999 LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared ML17325B5771999-05-0303 May 1999 LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design ML17335A5301999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With 990508 Ltr ML17335A5291999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With 990508 Ltr ML17325B5581999-04-16016 April 1999 LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold ML17325B5471999-04-12012 April 1999 LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation ML17325B5321999-04-0707 April 1999 LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate ML17325B5161999-04-0101 April 1999 LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures ML17325B5491999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr ML17325B5441999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr ML17325B5221999-03-29029 March 1999 LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing ML17325B4801999-03-18018 March 1999 LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling ML17325B4741999-03-18018 March 1999 LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed ML17325B5671999-03-0202 March 1999 Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218. ML17325B4631999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Power Station,Unit 2.With 990308 Ltr ML17325B4621999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Plant,Unit 1.With 990308 Ltr ML17325B4571999-02-24024 February 1999 LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors 1999-09-30
[Table view] |
Text
e N.R.C. OPERATING DATA REPORT DOCKET NO. 50-316 DATE 10/1/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 OPERATING STATUS
- 1. Unit Name D. C. Cook Unit 2 -----------------------
- 2. Reporting Period SEP 85 : notes :
- 3. Licensed Thermal Power (MWt) 3411
- 4. Name Plate Ratir4 (Gross MWe) 1133 !
- 5. Design Electrical Rating (Net MWe) 1100 l l
- 6. Maximum Dependable Capacity (GROSS MWe) 1100 i
- 7. Maximum Dependable Capacity (Net MWe) 1060 ---------- ------------
- 8. If Changes Occur in Capacity Ratings (Items no. 3 through 7) Since Last Report Give Reasons __________________________________________
- 9. Power Level To Which Restricted. If Any (Net MWe) _________________
- 10. Reasons For Restrictions. If Any:________________________________
This Mo. Yr. to Date Cumm.,
- 11. Hours in Reporting Period 720.0 6551.0 67919.0
- 12. No. of Hrs. Reactor Was Critical O.0 4507.6 47587.6
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator on Line 0.0 4447.3 46445.9
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Therm. Energy Gen. (MWH) 0 14637312 147715373
- 17. Gross Elect. Energy Gen. (MWH) O 4771520 4855A950
- 18. Net Elect. Energy Gen. (MWH) O 4604162 4Sd21896
- 19. Unit Service Factor 0.0 67.9 71.0
- 20. Unit Availability Factor 0.0 67.9 71.0
- 21. Unit Capacity Factor (MDC Net) 0.0 66.3 67.6
- 22. Unit Capacity Factor (DER Net) 0.0 63.9 66.1
- 23. Unit Forced Outage Rate 100.0 31.5 15.0
- 24. Shutdowns Scheduled over Next Sin Months (Type,Date,and Duration):
- 25. If Shut Down At End of Report Period, Estimated Date of Startup:
SHUT DOWN FOR S/G TUBE REPAIR. ESTIMATE GTARTUP 9/15/05
- 26. Units in Test Status (Prior to Commercial Operation):
Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION l
l g i ,
0512120464 850930 l PDR ADOCK 05000316 '
R PDR
\
l
=
AVERAGE DAILY POWER LEVEL (MWe-Net)
DOCKET NO. 50-316 UNIT TWO DATE 10/1/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 MONTH SEP 85 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 .
9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0
. _ _ . _ . _ _ _ . _ . _ _ _ _ _ _ _ . ~ . . - _ . _ _ ._ _ _
e IMM.KET NO.
50-316 .
llNil'SilllllM)WNS ANilPOWLM NiiltllCllONS UNIT NAME D.C. Cook Unit 2 IBA l'E 10-10-85 COMPLETEin my B. A. Svensson September, 1985 NI FON'l MON H3 TEl.ErlH)NE 616/465-5901
- t. .
c r. 's .."3 ti Causc a rusicaive
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M*- 1848e ?, ~E ;; 2 s oc livent r. 'l sq Aui.us sia ik fggygpl McOHfCucC hE sE j5g McPeNI 4 6
164 850824 F 720 A 1 N.A. CC HTEXCH rhe Unit was removed from service on 850824 for steam generator tube leak repairs. Eddy current testing and required tube plugging has been com-pleted. The outage has been extended to complete required design changes.
The estimated return to service date is October 20, 1985.
l
.I 4 I 2 1: l'ostcJ Neasius: McshnJ: lininhis G Imssantiivis A l'ipnemcs.: 1:aalius (l nplasul 1 -Manual los Psepasasiani of Data S: SihcJuical u Maiuscuasme ns Test 2 Manual Saam. linisy Sheets fus I.kensee C Rclucling LAulomasse & sam. !! vent Hepini 18 l'HI l'ile INIIHI G-In Hegulasiuy kesisusinia l Ollies Ilimplamil 01611
' l' Opesatos Isaining & i s.cssse i mandnaisoss itAilupussisassve i G Opesassanial 1.s n.: II:splaml lainbei ! - Same Somce l'8/11) 11 Othes llisplanal
. . . . . . .w .. . .: , . -. ,- m UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should deserte 211 ;lant shutdowns dunng me in se:ordanes with the taols apecumg on the report form.
report penod. In addition tt should be the source of explan. If category 4 must be used. sapoly snef comments.
anon of ugmacant dios m average power levels. Each signi.
ricant reducuan m power level (greater than 204r reduction LICENSEE EVENT REPORT z. Reference the applicable m average daily power level for the preceding 24 hnurs) reportaole occurrence pertammg to se outage or power should se noted even though da un:t may not have been reduction. Enter the !!rn fcur parts (event year, sequenuai shut down completeiyl . For such reductions in power level. report number. occurrence code and report type) of the tive the duration should be listed as zero, the method of reducuan part designauon as desenbed in item 17 of Instruccons for should be '.isted as .1 (Other). and the Cause and Correcuve Preparauon of Data Entry Sheets for I.acensee Ennt R port Acuen to Prennt Recurrence olumn should explain. The (LER) File (NUREG.0161). This mformation may not be Cause and Correcuve Acuan to Frennt Recurrence column nediately evident for all suJt shutdowns. of course, smee should be used to provide any needed explanation to fully further investgauon may be required to ascertam whether or desenbe the :ircumstances of tne outage or power reducuan. not a reportable occurrence was involved.) If the outage ur power reduccon wtli not result in a reportable occurrence.
NUMBER. T*us :olumn should mdicate the sequennal num, the pouuve mdicauon of this lack of correlation should be ber asagned to essa shutdown or ugruncant reductionin power noW as not apphok dM for that calendar year. When a shutdown or ugntricant power SYSTEM CODE. The system in wtuch the outage or power reduction beg ns in one recort penod and ends m acother, an entry should be made tor botn report penods to be sure reduction ong:natea should ce noted sy the two d: sit code of all snutdowns or signalcant power reducaons are reported. Ex:ubit G . Instrucuans for Preparauen or. Data Entry Sheets Unt:1 a uru: has 2:h:eved its first power generuton, no num. for Licensee Event Re: ort (LER) Fde (NUREC4161).
ber should be us:gned to each entry. Systems that do not fit any ex:st:ng code should be dengna.
ted XX. The code ZZ should be used for tnosa events where DATE. This solumn should .ndicate the date of the start a system ts not appticaole.
of esca shutdown or ugru:1: ant ;cwer reduenon. Report as year month. and day. Aupst 14.1977 would be reported COMPOSENT CODE. Select the most accropnate .omponent as 7?C314. When a sutdown or ugrufIc:nt power reduccon from Exh2tt I . Instrucuens for Preparauon of Osta Entt3 bepts m one report pened and enes :n moder, an entry should Sheets for Licensee Ennt Report (LER) Ft!e (NUREG4161).
be made for both report peneds to se sure all shutdowns usms the following entiena:
or up;i! cant power reduccons are reported.
TYPE. Lse "F" or "S" to encic2te either " Forced" or " Sche.
dulac." respectively, for each shutcown or ugruilcant power B. If not a omponent fu!ure, use the related component:
reducaon. Forud shutdowns include those requued to be e.g.. wrong vain operated through errort list valve as atuated by no later than de weekend followmg discovery component.
of an off-normal :endit2on. It is recognized that some judg.
=ent is required n categonzmg shutdowns in this way. In C. If a cham of fatlures occurs, the first component to mai.
general, a forced snutdown is one that would not have hun funcuon should be listed. The sequence of events, me!ad.
- cmpleted :rt the absence of the condtuon for which corteedve ing the other components whica fall, should be desenbed action was tanen.
under the Case and Correcuve Acuan to ?tevent Recur.
. rence column.
DURATION. Self explanatory. When a thutdown extends beyond the end or a tepcrt penod. count only the time to the Components that do not r1t any mstmg : ode should be de.
signated XXXXXX. The code n2222 should be used for end of the report penod and piclc up the ensuing down time m tne foCcwtng recort penods. Report dursuon of cutages events where a component daugnatton is not applicaele.
yunded tu the nr arest tenth ui :n hout to fac:litate summation.
ahe sum of the total oatage hours stus the hours the genera
- CAUSE & CORRECTTVE ACTION TO PREVENT RECUR.
tot was on line snould equal the pass hours in the reportmg RENCE. Use the column :n a narrattn fastuon to ampitfy or explam the arcumstances of the shutdown orpower reducuon.
P'UO4' lb :olumn should .nclude the toecule cause for each snut.
REA50N. CateIortae sy letter Jeugnanon in accordana wn r wincant rwn reducuan and tne immediate and
- tth the tacle appeartag on the report form. If ;stegory H eentemotated long term correcuse action tamen. if appropn.
must be used.lucciy bnet summents.
ste. This column should also be used for 4 descnption ot'tne maic' safety related corrective mamtenance performed furtna METHOD OF SHUTTING DowN THE REACTOR OR 'h'""'84'E*"8"#UC"'"'I"di"I3"'d'""#I""0"M tne ertti.al path aettvity and a report of any s.ngie release et REDUCING POWER. Catefonte ey numner despauun radioastmty or smgle radiation execture seeeul. ally assose
% c that this differs trom the Edison E:e:trte Insuture ated with the outage wtuch 16 aunts far more tnan 10 :er.ent 4
- EEll defmiticns as " Farced Parnal Outage'* and "Sene. ulthe allowsole annual values Juled Parnal Ouun." For these tentti. FEl uses 4.hange or For long textual recorts contmue astratrve in se: arue ; son
.t0 'lW as the breax pmni. For urger power reseturs. 30 MW .nJ reteren.e the shutdo*n or power red 2.uon rio in:.
- s em imail a .hange to wanant oplananon. carranve.
pe
_ _. ~. _ _ . _ . . . _. .. .
F
. Docket No.: 50-316
. Unit Name: D. C. Cook Unit 2 Completed By: D. A. Bruck Telephone: (616) 465-5901 l Date: October 3, 1985 l Page : 1 of 1 MONTifLY OPERATING ACTIVITIES - SEPTEMBER, 1985 IIIGIILIGHTS:
The reporting period began and ended with the reactor coolant system in Mode 5 for steam generator tube repairs.
l There was no electrical generation in the month of September.
SUMMARY
09-03-85 At 1740, auxiliary building ESF fan, 2-HV-AES-2, was discovered inoperable due to a split seam allowing charcoal to leak out.
l 09-06-85 At 0847, an inadvertant Engineering Safeguard Features actuation occurred due to surveillance testing.
l 09-07-85 At 1811, the West Fesidual ifeat Removal lleat Exchanger was removed from service to repair a leaking sample valve.
l 09-08-85 At 1022, the West Residual lleat Removal lleat Exchanger was l returned to service.
At 1022, the East Residual lleat Removal lleat Exchanger was removed from service to repair a leaking outlet cooldown isolation valve.
1 09-09-85 At 1700, the East Residual ifcat Removal ifeat Exchanger was returned to service.
l 09-10-85 At 1833, the East Residual ifcat Removal lleat Exchanger was l removed from service to repair a leaking outlet cooldown isolation valve.
l 09-14-85 At 1300, the East Residual lleat Removal system was returned
! to service. i l
l 09-15-85 At 1345, the Spray Additive Tank found inoperible due to '
containing more than the maximum of 4600 gallons.
, 09-18-85 At 2256, the Spray Additive Tank was returned to service.
l 09-20-85 At 1310 the liigh Demand Fire Pump was declared inoperable because it failed to develop discharge pressure.
09-22-85 At 0037, the liigh Demand Fire Pump was returned to service.
a_
- e DOCKET NO. 50 - 316 4 UNIT NAME D. C. Cook - Unit No. 2 DATE 10-11-85 COMPLETED BY B. A. Svensson MAJOR SAFETY-RELATED MAINTENANCE SEPTEMBER, 1985 M-1 The equalizing line around 2-RH-128E. (RHR heat exchanger outlet hand shutoff valve) broke away from the valve body. The old pipe and tubing were removed and new pipe and tubing were installed.
Required NDE was performed.
M-2 Revelded broken equalizing line on 2-RH-128E. Required NDE was performed.
C&I-1 Recalibrated indicator transmitter and square root extractor and verified that indicator read zero after being returned to service.
C&I-2 FFI-220 auxiliary feedwater flow to steam generator #2 read 10,000 lbs./hr. with no auxiliary foedpumps on. Recalibrated indicator transmitter and square root extractor and verified that indicator read zero after being returned to service.
/T~ .
U~';",,n'_ INDIANA & MlCHIGAN ELECTRlC COMPANY
- Donald C. Cook Nuclear Plant P O. Box 458. B x3gman, Mctugan 49106 October 12, 1985 Director, Office Of Management Information I and Prograr.1 Control U. S. Nuclear Regulatory Commission i Washington, D. C. 20555 Gentlemen:
j Pursuant to the requirements of Donald C. Cook Nuclear Plant Unit 2 i Technical Specification 6.9.1.6, the attached Monthly Operating Report
- for the Month of September, 1985 is submitted.
l Sincerely, i
i l gU ~
W. G. Smit k J .
Plant Manager i
j WGS:ab l I
' Attachments cc: J. E. Dolan l M. P. Alexich {
j n. W. J uf gellbell I i NRC Region III l B. L. Jorgensen !
R. O. Bruggee !
l I R. C. Callen I
S. J. Mierzwa F. S. VanPe lt , J r.
P. D. Rennix D. R. Ilahn '
Z. Cordero
{ J. J. Markowsky 1 J. F. Stietzel !
PNSRC File !
INP0 Records Center !
ANI Nuclear Engineering Department i
l 1