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| {{#Wiki_filter:~~~5~AVERAGE DAILY UYflT PO)lt-"R L:"VEL DOCK:-7.lO.UNIT 5-3-79 COVIPL""T"D BY H.T.G.)11 ett~616-5-5991 MONTH a<xi 1979 DAY AVERAGE DAILY POWER LEVEL (MNe.;)et)I 1039 1036 1036 1024 1027 371 0 DAY AVERAGE DAILY POKER LEVEL (MÃe Net)0 17 0~0 0 0 10 lo 0 0 0 0 0 0 0 0 o5 ZS't9 30 0 0 0 0 0 0 Iih'S I tC,UtCTIONS O"'",ls Ot..et.::s: | | {{#Wiki_filter:}} |
| l;,'v t32" II)"t:!6 tt<4'ee te't.l:.1~i~Yel lot 33." c v I.1;.1 3":"1-:.igt I.Cia t.'e att I:le 1~3I i"ilole..1e33~<'3tl.
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| V 90517 0 4+4 OPERATING DATA REPORT ooczaT~o.oATE~5--COiIPt ETED IIY JMC~1 1 ett-TELEPHONE 9~~-'5 901;OPERATING STATUS Dona]d C.Cppk 1 3.Licensed Thermal Power POItt): 4..Nameplate Rating (Gross IIDVe): 5.Design Electrical Rating (Net MY/e): 6.hiaximum Dependable Capacity (Gross MKe)t 7.~iaximum Dependable Capacity (Net MNe): 3,250$089 1,054'080 1 044 Notes 8.If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report.Give Reasons: 9.Power I.evel To which Restrict&, If Any (Net ADVe)t ID.Reasons For Restrictions, If Any: 11.Hours 1n Reporting Period 13.i umber Of Hours Reactor Was Critical 13.Re ctor Reserve Shutdown Houz 14.Hours Generator On-Line 15.Unit Reserve Shutdown Hours 16.Gross Thermal Energy Generated (biWH)I'7.Gross Electrical Energy Generated (MNH)18.Net Electrical Energy Generated (.'rI'Iv'H)
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| )9.Unit, Service Factor 20.Urit Avaihbility Factor 31.Un!t Capacity Factor (Using MDC Net)32.Urit Capacity Factor (Using DER Net)33.Unit Forced Outage Rate 24.Shutdowns Scheduled Over Next 6 blonths This Month 719 128.8 128.8 Yr:to-Date 2 879 2,211.9 2 205.1 0 17.9 17.9 17.6 0{Type.Date.and Du:ation of Each): 76.6 76.6 74.0 73.3 411 763 6 942 086'37,490 2,306,110~95~2.8 Cumulative
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| '7 963.0 29,423.6 463~8,~3 78 279"877 25,595,770
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| ,562, 59 78.1 78.1 69.0 63.2 6~0 S.If Shut Down At End Of Report Period.Estimated Date of Startup!~6.Units In Test Status I Prior to Commercial Operation):
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| Forecast Achieved INITIA L CRITICA LITY IN IT I A L ELECTR.IC IT Y ColiDIERCIA L OPERATION UNIT SIIUTD01VNS AND POIVER REDUCTIONS REPORT hlONTII April, 1979 DOCKET NO.'sss cohlPLETED IIY B-A 5ve sson TELEPI ION r, 61 6 465-5901 N().Dale Q-((<<(<<IQ~(I)Cl L Ice I)sc c Event Rcport 4 (")o ((I Q O Q O Cr Cause&, Coffccllvc Aclion lo Prevent Rccurrcncc 149 790406 S 590.2 B,C 3 N.A.ZZ ZZZZZZ The Unit was scheduled to be re-moved from service for refueling and maintenance after peak on 790406.The Unit tripped the same day due to loss of both main feed pump turbines caused by low F.P.T.condenser vac-uum.The low vacuum condition was created by lake debris plugging up the condenser tube sheets.The Unit remained out of service at the end of the month.I: Forced S: Scl)cdulcd
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| ((I/77)Reason: A-E(luipn>cnt Failure (Explain)ll.hlaintcnance or Test C.Refueling D Regulatory Rcslriclion E.Operator Trainiog&License I:xan>inalion r-Adnllnlsllallvc G.Operational Lrrl)r (I'.xplain)
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| II.Oll)cr (Explai>>)3 hlethod: I Ma ll I I a I 2 Manual Scran).3.Auto)nalic Sera)n.4.0>l>cr (Explain)Exl>ibil G-Instructions for Preparation oi Data Lntry Sllccts for L)ccnscc Event Rcport (I.ER)File (NURI:G-016 I)'Exl>ibit I-Sa>nc Source UNIT SHUTDOWNS AND POWER RE cTIONS INSTRUCTIONS This report should describe all plant shutdowns during the report period.In addition.it should be the source of explan-ation of significant dips in average power levels.Each signi-ficant reduction in power level (greater than 20fo reduction in average daily power level for the preceding'24 hours)should be noted, even though the unit may not have been shut down completelyi.
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| For such reductions in power level, the duration should be listed as zero, the method of reduction should be listed as 4 (Other), and the Cause and Corrective Action to Prevent Recurrence column should explain.The Cause and Corrective Action to Prevent Recurrence column should be used to provide any needed explanation to f'ully describe the.circumstances of the outage or power reduction.
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| NUMBER.This column should indicate the sequential num-ber assigned to each shutdown or significant reduction in power for that calendar year.When a shutdown or significant power reduction begins in one report period and ends in another.an entry should be made for both report periods to be sure all shutdowns or significant power reductions are reported.Until a unit has achieved its first power generation, no num-ber should be assigned to each entry.DATE.This column should indicate the date of the start of each shutdown or signiiicant power reduction.
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| Report as year.month, and day.August i4.1977 would be reported as 770814.When a shutdown or significant power reduction begins in one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or significant power reductions are reported.TYPE.Use""F oF'S" to"indicate either"Forced" or"Sche-'uled," respectively, for each shutdown or significant power reduction.
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| Forced shutdowns include those required to be initiated by no later than the weekend following discovery of an off.normal condition.
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| It is recognized that some judg-ment is required in categorizing shutdowns in this way.In general.a forced shutdown is one that would not have been completed in the absence of the condition for which corrective action was taken.DURATION.Seifwxplanatory.
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| When a shutdown extends beyond the end oi a report period, count only the time to the end of the report period and pick up the ensuing down time in the following report periods.Report duratibn of outages rounded to the nearest tenth ot an hour to facilitate summation.
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| The sum of the total outage hours plus the hours the genera-tor was on line should equal the gross hours in the reporting period.REASON.Categorize by letter designation in accordance with the table appearing on the report 1'orm.If category H must he used.supply briei'comments.
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| METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.Categorize by number designation INoie thai this differs i'rom the Edison Ele tric Institute FEEI)definitions of-Forced Partial Outage-and-Sche.duied Partial Outage." For these turin~.I.EI uses~change oi.0 41W as the break point.For larger power reactors.~0 41W is ts~i small a chanae to warrant explanatii>>i.
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| in accordance with the table appearing on the report form.If category 4 must be used, supply brief comments.LICENSEE, EVENT REPORT-.Reference the applicable reportable occurrence pertaining to the outage or power reduction.
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| Enter the first four parts (event year.sequential report number, occurrence code and report type)of the five part designation as described in Item 17 of Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)File (NUREG4161).'his information may not be immediately evident for all such shutdowns, of course, since further investigation may be required to ascertain whether or not a reportable occurrence was involved.)
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| If the outage or power reduction will not result in a reportable occurrence.
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| the positive indication of this lack of correlation should be noted as not applicable (N/A).SYSTEM CODE.The system in which the outage or power reduction originated should be noted by the two digit code of Exhibit G-Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)File (NUREG4161).
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| Systems that do not fit any existing code should be designa-ted XX.The code ZZ should be used for those events where a system is not applicable.
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| COMPONENT CODE.Select the most appropriate component from Exhibit I-Instructions for Preparation of Data Entr)Sheets for Licensee Event Report (LER)File (NUREG4161).
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| using the following critieria:
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| A.If a component failed, use the component.
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| directly involved..B.If not a component failure, use the related component:
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| e.g., wrong valve operated through error: list valve as component.
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| C.If a chain of failures occurs, the first component to mal-function should be listed.The sequence of events.includ-ing the other components which fail, should be described under the Cause and Corrective Action to Prevent Recur-rence column.Components that do not fit any existing code should be de.signated XXXXXX.The code'ZZZZZZ should be used for events where a component designation is not applicable.
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| CAUSE L, CORRECTIVE ACTION TO PREVENT RECUR-RENCE.Use the column in a narrative fashion to ampiify or explain the circumstances of the shutdown or power reduction.
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| The column should include the specific cause for each shut~down or significant power reduction and the immediate and contemplated long term corrective action taken.if appropri-ate.This column should aiso be used for a description of the major safety-rehted corrective maintenance performed during the outage or power reduction including an identification of the critical path activity and a report of any single release ot radioactivity vr single radiation exposure specitically associ-ated with the outage which accounts for more than 10 percent or the allowable annual values.For long textual reports continue narrative on separate paper and ret'erence the shutdown or power reduction ior tlu>iiaff alive~
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| Docket No.: Unit Name: Completed By: Telephone:
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| Date: Page: 50-315 D.C.Cook Unit 81 R.S.Lease (616)465-5901 May 9, 1979 (1)MONTHLY OPERATING EXPERIENCES
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| --APRIL,'1979 Hi hli hts The Unit entered this reporting period operating at 100/power.Total electrical generation for the month was 137,490 Mwh.~Summa@4/03/79--It was decided to allow power level to drop slightly because the F(z)as indicated by the APDMS was approach-ing the Tech.Spec.limit.On 04/04/79 power was at 98$and F(z)margin was adequate so no further reduction was made.4/04/79--The Unit 1 Diesel Fire Pump was made inoperable for its 18-month Maintenance Inspection.
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| The Pump was returned operable 4/07/79'/05/79--4/06/79--One phase of the 69KV off-site power source failed open during a windstorm at 2130 hours.Repairs were made and the source was again available at 0957 hours 4/6/79.The Hest Main Feed Pump tripped followed by trip of the East Main Feed Pump and the Unit.The cause of the Feed Pump trips was low condenser vacuum due to debris on the condenser tube sheets.During the night there had been a windstorm with velocities up to 78 m.p.h.which caused extremely rough lake conditions, stirring up leaves from the bottom.The Unit had been scheduled out later the same day for its annual refueling outage, so no attempt was made to return it to service.4/07/79--The Unit entered Mode 5 operation and degassing of the system was initiated.
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| Also, H202 was injected for clean-up of the system.At 2330 hours both Emergency Diesel Generators started and accepted their designed load.Cause of start was a degraded system voltage actuation.
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| At this time both Units were off the line and they were receiving auxiliary power from the normal outside source.7 of the 8 Reactor Coolant Pumps were in operation.
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| As the 8th pump was started, the degraded voltage actuation was initiated.
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| ''t L"1 l 4 Docket No.: Unit Name: Completed By: Telephone:
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| Date: Page: 50-315 D.C.Cook Unit kl R.S.Lease (616)465-5901 Hay 9, 1979 (2)4/12/79--Cleanup of the RCS was completed and the system drained to 1/2 loop.4/15/79--Initial lift of the Reactor head was made.Due to leakage problems in the refueling cavity, the removal of the head was not accomplished until 4/18/79.4/20/79--Fuel shuffle was started this day and completed 4/26/79.4/28/79--The Reactor head was again set in place.
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| l)~7 I f I<
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| DOCKET NO.UNIT NAME DATE COMPLETED BY TELEPHONE MAJOR SAFETY-RELATED MAINTENANCE 50-315 D.C.Cook-Unit No.1 5-11-79 B.A.Svensson 616 465-5901 APRIL, 1979 M-1 M-2 The north waste gas compressor would not operate properly.Replaced diaphragm in suction valve, RRV-378.Operational retest satisfactorily.
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| WCR-906, NESW containment isolation valve did not pass STP.203 leak test.Cleaned internals, lapped plug to cage.Reassembled with new gaskets.WCR-907, NESW containment isolation valve did not pass STP.203 leak test.Cleaned internals, lapped cage seat and machined disc seat.Reassembled with new gaskets.WCR-911, NESW containment isolation valve did not pass STP.203 leak test.Cleaned internals, and lapped seat.Reassembled with new gas-kets.M-5 WCR-910, NESW containment isolation valve did not pass STP.203 leak test.Cleaned internals and lapped seat.Reassembled with new gas-kets.M-7 WCR-946, NESW containment isolation valve did not pass STP.203 leak test.Cleaned internals, lapped plug and cage.Reassembled with new gaskets.WCR-926, NESW containment isolation valve did not pass STP.203 leak test.Cleaned internals and lapped seat.Reassembled with new gas-kets.WCR-930, NESW containment isolation valve did not pass STP.203 leak test.Cleaned internals and lapped plug.Reassembled with new gas-kets.M-9 WCR-909, NESW containment isolation valve did not pass STP.203 leak test.Cleaned internals and lapped seat.Reassembled with new gas-kets.M-10 Hydraulic snubbers k'65 and 866 were of a style that required an un-wieldy reservoir piping installation.
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| Replaced the snubbers with a newer model which improved the reservoir piping configuration.
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| The new snubbers were tested prior to installation.
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| DOCKET NO.50-315 UNIT NAME D.C.Cook-Unit No.1 DATE 5-11-79 COMPLETED BY B.A.Svensson TELEPHONE'16 465-5901 PAGE-2-MAJOR SAFETY-RELATED MAINTENANCE APRIL, 1979 Twelve carbon steelvalves were discovered to have been installed as steam generator level instrument root valves in lieu of stainless steel valves as specified.
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| Stainless steel valves were installed as replacements per specifications:
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| All required NDE was performed.
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| ICM-260, safety injection pump discharge containment isolation motor-operated valve to cold legs 1 and 4 had a body to bonnet leak.Re-placed bonnet gasket and had valve retested.The rod position indication system for rod F-6 indicated a deviation greater than 12 steps from the demand position.The output signal level of the signal conditioning module was measured and recorded at 2.635 vdc'.The signal conditioning module's calibration was performed after the secondary coil voltage of the LVDT was determined to be within specifications.
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| One hour after the calibration the output of the signal conditioning module again changed.Resistance measurements of the cables to the LVDT were measured and indicated a higher than normal secondary coil resistance of 290.The high resistance of the cable was traced to the connector on the reactor vessel head and will be tested during the outage.The 50 foot wind speed and direction recorder failed.The detectors on the tower were frozen due to weather conditions.
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| As the ambient temperature increased, the detectors returned to operation.
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| h The 150 foot wind speed and direction recorder failed.The wind speed cups on the primary and secondary transmitters required re-placement.
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| The wind directional vane on the primary also was replaced.f f 4}}
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