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| {{#Wiki_filter:AVERAGE DAILY L;(17 POWER Led%.DOC~Y~O.'0-315 D~3-1-79 DAM~M..::666 Februar 1979 I DAY A~AGE DAILY POWER LEYEL (MWe Net)1041 1045 DAY AVERAGE DAILY POWWOW.LEYEL (MWe.%et)1039 1033 3 10 13 IS 878 101 4'1039 312 679 1041 1035 1035 1046 1047 1044 1045 1044 1044 19 31 Og 30 31 1044 1043 1042 1040 1041 1041 1041 1046 IiMSTR U~~OH S Qn.!;is;orr-at. | | {{#Wiki_filter:}} |
| !is: " averav='a!iy"n:t tttv r!t:e!;n!le se!d'or each"'av in t'nc r nvr.:na:nttntn.
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| C.nnot;lc le'ne nea6 S'6 tt'nOIC.66.an't'art.
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| V9032 i oofy I
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| I~OPERATING DATA REPORT DOCKET NO.50 315*DATE~29 COMPLETED BY~~1 ett.TELEPHONE~~901'PERATING STATUS Qnif Nam Donal d C.Cook 1 2.Reporting Period: Februar 3.Licensed Thetmal Power (MWt)t 4..Nameplate Rating, (Gross MNe)t S.Design EIectti&Ratmg (Net MNe): 6.Maximum Dependable Capacity (Gross MSe): 7.Maximum De mdabie Ca acity (Net 5OVe)t Notes 1 089 1,054 1 080 1 044 p p S.If Changes Occur in Capacity Ratings (Items Number S Through 7)Since Last R port.Give Reasons: 9 9.Power Level To Mich Restr~ed, If"Any Piit hWe)t IO.Reasons For Resuictions, If Any:-This Month Yr.ao-Date Cumuiative 1399.2 0 1396.8 0 669 231 98.6 95.1 94.2 1.4 I I.Hours In Reporting Period 672 12.Number Of Hours Reactor Was Critical 655.2 IS.Re ctor Reserve Shutdown Bout 0 14.Hours Genemtor On~652.8 15.Unit Reserve Shutdown Houts 0 9, 1.9.91 551 I7.Gross Electrics Enemy Generated{M>YH)9'~4459 19.Unit Serac Factor 1..ZO.Uric Availability Factor 91.1"1.Unit C pacig.actor(Using MDCNet)22.Unit.Capacity Factor (Using DER Net)~~".L'nit Forced Outage Rate 24.Shutdowns Scheduled Over Next 6 Months (Type.Date, and Duration of Each): 36,480.0 463 27 810.1 75 728 764 23 743 404 79.2 79.2 63.7 5.9'5.If Shut Down*t End Of Report Period.Estimated Date of Startup: 5.Units In Test Status I Prior to Commercial Operation):
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| Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY CONDIERCIAL OPERATION (i)l77)
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| IT IIV DO VNS N POI ER ONTIIFeb ua hl (ED y, 19 ON DOCKET NO.UNIT NAME D'TE Y E COMPLETED a TELEPI IO 50-315 I a verls son B.6!I6 469-590 D.C.Coo-~l)alc rI an rj fPa a Q Q~c Q1 U~c~Vs CL Llcco sec Eveot Report¹Cns 0 El~Q an oI'6 nl c~p 0 p p E~p CJ Cause k, Corrcctlvc AcliIot lo Prevent Rccurrcocc 144 145 790203 790206 19.2 H 4 N/A 1 79-006/03L-0 ZZ ZZ ZZZZZZ ZZZZZZ: Reactor power reduced to 705 to per-form N.I.S.incore/excore cross cal-ibration.Power returned to 1005 780204.During a"feed and bleed" operation on the pressurizer relief tank a failure occurred of the pressurizer r'elief tank rupture disc.The pres-sure surge caused all ice condenser inlet doors to indicate open.The Unit was removed from service to permit closing the ice condenser inlet doors and replace the rupture discs.The Unit was returned to sei'.vice 790207 and loaded to 100%the same day.I I': Fore 0 S: SCIICIIoleII Reason: A.EIiuipment Failure (Explai>>)II-hlalnlcnancc or Test C.Rcfuellog D Regulator)'(cslriclloo E-Operator Training 8I Lice>>sc Examination F-Administrative G Operational Error (Explainl I I.OIIIcr (Explain)hlctltod: I Manual 2 h(annal Scratn.3-Aulootatic Scrato.4.01IIcr (Explain)Exhibit C-Instntctions RIr Preparation ol Data Lolry Sheets for Licensee Event Rcport (LI!RI File (NIIRI G.0l 6l)5'Exhibit I-Sante Source 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 20%reduction in average daily power level for the preceding 24 hours)should be noted, even though the unit may not have been shut down completelyl.
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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 Correcuve 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 fully 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 shutdovm or significant reductionin 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 3~1 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.DATF This column should indicate the date of the start of each shutdown or significant power reducuon.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 ail shutdowns or significant power reducuons are reported.TYPE.Use"F" or"S" to indicate either"Forced" or"Sche-duled," 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 oifwormal 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 acuon was taken.DURATION.Self~xplanatory.
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| When a shutdown extends beyond the end ot 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 duration of outages rounded to the nearest tenth of anhour 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>Iesi>gnatiun in accordance with the table appearing on the report form.If category H must he used.supply briei'comments.
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| METHOD OF SHUTTINC DOWN THE REACTOR OR REDUCING POWER.Cateaorize by numher designation 1 Nioie that this diff'ers t'rom the Edison Ele tric Institute<EEI)definitions oi'Forced Partial Outage" and-Sche.duled Partial Outage." F>>r these tern>>.EEl uses a<<hange or'0 MW as the break i>>>int.For larger power reactors.~0 MW is I>><>small a<<hange ti>warrant<<xplanati>>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 paris (event year.sequential report number, occurrence code and rapport 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).
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| This 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
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| (>>I/A).SYSTEM CODE.The system in which the outage or power reduction originated should be noted by the two digit code of Exhibit C-instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)File (NUREG4161).
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| Sysiems 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 Entry Sheets for Licensee Event Report (LER)File (NUREC4161).
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| using the following critieriai A.If a component failed, use the component directly involved.B.If not a component failure, use the related component:
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| eg., wrong valve operated through error: list valve as component.
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| C.If a chain of failures occurs, the fiat 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&, CORRECTIVE ACTION TO PREVE>VE RECUR-RENCE.Use the column in a narrative fashion to amplify 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 coluinn should also be used for a description of the major safety-related corrective maintenance performed during the outage or power reduction including an identification of the critical path activity and a report of any single release oi radioactivity or single radiation exposure speciti<<ally asso<<i-ated with the outage which accounts for more than 10 percent oi the allowable annual values.For long textual reports continue narrative on separate paper an>I rer'eren<<e the shutdown or=power redu<<tiun for th>>naf fa tive.
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| Docket No.: Unit Name: Completed By: Telephone:
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| Date: 50-315 D,.C.Cook Unct 81 R.S.Lease (616)465-5901 Harch 5, 1979 OPERATING EXPERIENCES
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| -FEBRUARY, 1979 Hi hli hts This Unit has operated at full power the entire reporting period except for one outage and other load reductions as required for maintenance.
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| Summar 02/03/79-Loading was reduced to 70K (780 tQe)starting down at 1130 hours.This was for Cross Calibration of Incore/Excore Nuclear Instrumentation.
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| Power was returned to 1005 (~1080 NMe)by 0350 hour s 2/04/79.02/06/79-One of two Pressurizer Relief Tank ruptured diaphragms ruptured at 0455 hours.This caused all Ice Condenser doors to indicate open.The Unit was started down at 0730 hours and removed from service at 0816.All Ice Condenser doors were reclosed by 0920 hours.The ruptured disc failed during a feed and bleed maneuver to reduce the temperature of the water in the tank.Both ruptured discs were replaced on the tank.02/07/79-The Reactor was returned to criticality at 0108 hours and the Generator paralleled to the system at 0329 hours.The Unit was loaded to 100K (1080-MWe)by 1545 hours.2/8//I-I d/I d d 858 (888 81/I'11 CWP from service for repair of a lube oil leak.Power was returned to lOOX (1080 NWe)by 0255 hours, 2/10/79.02/18/79-Loading was reduced to 905 (980 NWe)for testing of Turbine valves.Total time below 100Ãpower was 2.25 hours.
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| DOCKET NO.50-315 UNIT NAME~brook-Unit No.1 DATE 3-14-79 COMPLETED BY B.A.Svensson TELEPHONE 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE FEBRUARY, 1979 M-1: M-2 Unit 1 East centrifugal charging pump mechanical seal leaked.A new mechanical seal was installed and operational retest of the pump was satisfactory.
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| During inspection of aux.feedwater motor operated valves, FMO-231 was found to have a broken jumper wire at terminal¹46.Repaired broken wire.Had valve tested and returned to service.M-3 C&I-1 C&I-2 C&I-3 Cooling water safety valve on TDAFP oil cooler, SV-140 was leaking by.Relapped seat and disc.Performed set point check.Heat tracing circuit train 112, the emergency boration line, would not maintain temperature.
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| The train B control thermostat set point was adjusted to increase the temperature of the line to 175 F.DRV-150, the emergency drain valve from the reactor coolant drain tank to the pipe tunnel sump, failed to the closed position.The coil of the solenoid supplying air to the valve failed.The coil was replaced and proper operation verified.The APDMS system actuated at 715 and 695 power levels.The required power level actuation is 84%.The isolation amplifiers of NIS chan-nels N41 and N42 sending the power level signal to the APDMS were-recalibrated.
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| C&I-4 C&I-5 C&I-6 C&I-7 The control room cable vault fire detection system alarmed.A check of the fire detectors was performed.
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| One detector was found alarming.The detector was removed, cleaned and adjusted for the correct sen--sitivity.
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| The system reset was actuated and the alarm cleared.Radiation monitoring system channel R-2, containment area monitor, failed low.The connector was'found loose at the containment pene-.tration and an open connection.
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| The connector and wire were repaired and the channel returned to normal operation.
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| Radiation monitoring channels R-ll and R-12, filters supply pump would fail.The air flow of the pump required adjustment to 10 SCFM.The excessive air flow resulted in the filter pump trips.ILS-950, refueling water storage tank level recorder, indicated 96.5%when the tank overflow was reached.The calibration calculations were in error.Measurements were performed and the revised calcula-tions of 124" to 487" H20 were used in calibrating the level trans-mitter.}}
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