ML17317B011

Monthly Operating Rept for Feb 1979

ML17317B011
Person / Time
Site:	Cook
Issue date:	03/01/1979
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17317B010	List: ML17317B009 ML17317B011
References
NUDOCS 7903210044
Download: ML17317B011 (8)

Text

AVERAGE DAILYL; (17 POWER Led%.

DOC~Y~O. '0-315 DAM D ~ 3-1-79

~M..::666 Februar 1979 I

DAY A~AGE DAILYPOWER LEYEL DAY AVERAGE DAILYPOWWOW. LEYEL (MWe Net) (MWe.%et) 1041 1039 1045 1033 3

878 19 101 4 1044

'1039 31 1043 312 1042 679 1040 1041 1041 1035 1041 10 1035 1041 1046 1046 1047 13 1044 Og 1045 30 IS 1044 31 1044 IiMSTRU~~OH S Qn .!;is;orr-at. !is: " averav ='a!iy "n:t tttv r! t:e!;n! le se! d'or each "'av in t'nc r nvr.:na:nttntn. C.nnot;lc le'ne nea6 S'6 tt'nOIC .66 .an't'art.

V9032 i oofy

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OPERATING DATA REPORT 50 315 DOCKET NO.

DATE ~29

~~1 ett COMPLETED BY TELEPHONE ~~901 .

STATUS 'PERATING Donal d C. Cook 1 Notes Qnif Nam

2. Reporting Period: Februar

3. Licensed Thetmal Power (MWt)t 4.. Nameplate Rating, (Gross MNe)t 1 089 S. Design EIectti& Ratmg (Net MNe): 1,054 1 080

6. Maximum Dependable Capacity (Gross MSe):

7. Maximum De p mdabie Ca p acity (Net 5OVe) t 1 044 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, IfAny:-

This Month Yr.ao-Date Cumuiative I I. Hours In Reporting Period 672 36,480.0

12. Number Of Hours Reactor Was Critical 655.2 1399. 2 IS. Re ctor Reserve Shutdown Bout 0 0 463

14. Hours Genemtor On~ 652. 8 1396.8 27 810.1

15. Unit Reserve Shutdown Houts 0 0 9, 1

. 9. 91 551 75 728 764 I7. Gross Electrics Enemy Generated {M>YH) 9

~4459 669 231 23 743 404

19. Unit Serac Factor 1.. 79. 2 ZO. Uric Availability Factor 91. 1 98.6 79. 2 "1. Unit C pacig .actor(Using MDCNet) 95. 1

22. Unit. Capacity Factor (Using DER Net) 94. 2 63. 7

~~". L'nit Forced Outage Rate 1.4 5.9

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):

'5. If Shut Down *t End Of Report Period. Estimated Date of Startup:

5. Units In Test Status I Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY CONDIERCIAL OPERATION (i)l77 )

I a IT IIV DO VNS N POI ER (ED ON DOCKET NO.

UNIT NAME D 'TE 50-315 D.C.Coo - ~

COMPLETED Y B. verls son hl ONTIIFeb ua y, 19 a TELEPI IO E 6!I6 469-590 fPa a

rI Q c Q ~

Llcco sec nl c~ Cause k, Corrcctlvc 0CnsEl p 0 p p Q1 l)alc an rj Eveot

~

an Q AcliIot lo U~ c Report ¹ oI'6 E~

p Prevent Rccurrcocc

~ Vs CJ CL 144 790203 4 N/A ZZ ZZZZZZ Reactor power reduced to 705 to per-form N. I.S. incore/excore cross cal-ibration. Power returned to 1005 780204.

145 790206 19.2 H 1 79-006/03L-0 ZZ ZZZZZZ: 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 Reason: hlctltod: Exhibit C - Instntctions S: SCIICIIoleII A.EIiuipment Failure (Explai>>) I Manual RIr Preparation ol Data II-hlalnlcnancc or Test 2 h(annal Scratn. Lolry Sheets for Licensee C.Rcfuellog 3-Aulootatic Scrato. Event Rcport (LI!RIFile (NIIRI G.

D Regulator)'(cslriclloo 4.01IIcr (Explain) 0l 6l )

E-Operator Training 8I Lice>>sc Examination F-Administrative 5 G Operational Error (Explainl 'Exhibit I - Sante Source I I.OIIIcr (Explain)

INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appearing on the report form.

report period. In addition. it should be the source of explan- Ifcategory 4 must be used, supply brief comments.

ation of significant dips in average power levels. Each signi-ficant reduction in power level (greater than 20% reduction LICENSEE EVENT REPORT . Reference the applicable in average daily power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) reportable occurrence pertaining to the outage or power should be noted, even though the unit may not have been reduction. Enter the first four paris (event year. sequential shut down completelyl. For such reductions in power level, report number, occurrence code and rapport type) of the five the duration should be listed as zero, the method of reduction part designation as described in Item 17 of Instructions for should be listed as 4 (Other), and the Cause and Correcuve Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG4161). This information may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns, of course, since should be used to provide any needed explanation to fully further investigation may be required to ascertain whether or describe the circumstances of the outage or power reduction. not a reportable occurrence was involved.) If the outage or power reduction will not result in a reportable occurrence.

NUMBER. This column should indicate the sequential num. the positive indication of this lack of correlation should be ber assigned to each shutdovm or significant reductionin power noted as not applicable (>>I/A).

for that calendar year. When a shutdown or significant power SYSTEM CODE. The system in which the outage or power reduction begins in one report period and ends in another.

an entry should be made for both report periods to be sure reduction originated should be noted by the two digit code of 3~1 shutdowns or significant power reductions are reported. Exhibit C - instructions for Preparation of Data Entry Sheets Until a unit has achieved its first power generation, no num- for Licensee Event Report (LER) File (NUREG4161).

ber should be assigned to each entry. Sysiems that do not fit any existing code should be designa-ted XX The code ZZ should be used for those events where DATF This column should indicate the date of the start a system is not applicable.

of each shutdown or significant power reducuon. Report as year. month, and day. August i4. 1977 would be reported COMPONENT CODE. Select the most appropriate component as 770814. When a shutdown or significant power reduction from Exhibit I - Instructions for Preparation of Data Entry begins in one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREC4161).

be made for both report periods to be sure ail shutdowns using the following critieriai or significant power reducuons are reported.

A. Ifa component failed, use the component directly involved.

TYPE. Use "F" or "S" to indicate either "Forced" or "Sche-duled," respectively, for each shutdown or significant power B. If not a component failure, use the related component:

reduction. Forced shutdowns include those required to be eg., wrong valve operated through error: list valve as initiated by no.,later than the weekend following discovery component.

of an oifwormal condition. It is recognized that some judg-ment is required in categorizing shutdowns in this way. In C. If a chain of failures occurs, the fiat component to mal-general. a forced shutdown is one that would not have been function should be listed. The sequence of events. includ-completed in the absence of the condition for which corrective ing the other components which fail, should be described acuon was taken. under the Cause and Corrective Action to Prevent Recur-rence column.

DURATION. Self~xplanatory. When a shutdown extends Components that do not fit any existing code should be de.

beyond the end ot a report period, count only the time to the signated XXXXXX. The code ZZZZZZ should be used for end of the report period and pick up the ensuing down time events where a component designation is not applicable.

in the following report periods. Report duration of outages rounded to the nearest tenth of anhour to facilitate summation.

CAUSE &, CORRECTIVE ACTION TO PREVE>VE RECUR-The sum of the total outage hours plus the hours the genera-RENCE. Use the column in a narrative fashion to amplify or tor was on line should equal the gross hours in the reporting explain the circumstances of the shutdown or power reduction.

period.

The column should include the specific cause for each shut ~

down or significant power reduction and the immediate and REASON. Categorize by letter >Iesi>gnatiun in accordance with the table appearing on the report form. If category H contemplated long term corrective action taken. if appropri ~

ate. This coluinn should also be used for a description of the must he used. supply briei'comments.

major safety-related corrective maintenance performed during METHOD OF SHUTTINC DOWN THE REACTOR OR the outage or power reduction including an identification of REDUCING POWER. Cateaorize by numher designation the critical path activity and a report of any single release oi radioactivity or single radiation exposure speciti<<ally asso<<i-1 Nioie that this diff'ers t'rom the Edison Ele tric Institute ated with the outage which accounts for more than 10 percent

<EEI) definitions oi'Forced Partial Outage" and -Sche. oi the allowable annual values.

duled Partial Outage." F>>r these tern>>. EEl uses a <<hange or'0 For long textual reports continue narrative on separate paper MW as the break i>>>int. For larger power reactors. ~0 MW an>I rer'eren<<e the shutdown or =power redu<<tiun for th>>

is I>><> small a <<hange ti> warrant <<xplanati>>i>. naf fa tive.

Docket No.: 50-315 Unit Name: D,.C. Cook Unct 81 Completed By: R. S. Lease Telephone: (616) 465-5901 Date: Harch 5, 1979 OPERATING EXPERIENCES 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.

Summar 02/03/79 Loading was reduced to 70K (780 tQe) starting down at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />. This was for Cross Calibration of Incore/Excore Nuclear Instrumentation. Power was returned to 1005 (~1080 NMe) by 0350 hour0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> s 2/04/79.

02/06/79 One of two Pressurizer Relief Tank ruptured diaphragms ruptured at 0455 hours0.00527 days <br />0.126 hours <br />7.523148e-4 weeks <br />1.731275e-4 months <br />. This caused all Ice Condenser doors to indicate open. The Unit was started down at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> and removed from service at 0816. All Ice Condenser doors were reclosed by 0920 hours0.0106 days <br />0.256 hours <br />0.00152 weeks <br />3.5006e-4 months <br />.

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 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> and the Generator paralleled to the system at 0329 hours0.00381 days <br />0.0914 hours <br />5.439815e-4 weeks <br />1.251845e-4 months <br />. The Unit was loaded to 100K (1080- MWe) by 1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br />.

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 hours0.00295 days <br />0.0708 hours <br />4.21627e-4 weeks <br />9.70275e-5 months <br />, 2/10/79.

02/18/79 Loading was reduced to 905 (980 NWe) for testing of Turbine valves. Total time below 100Ã power was 2.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.

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: Unit 1 East centrifugal charging pump mechanical seal leaked. A new mechanical seal was installed and operational retest of the pump was satisfactory.

M-2 During inspection of aux. feedwater motor operated valves, FMO-231 was found to have a broken jumper wire at terminal ¹46. Repaired broken wire. Had valve tested and returned to service.

M-3 Cooling water safety valve on TDAFP oil cooler, SV-140 was leaking by.

Relapped seat and disc. Performed set point check.

C&I-1 Heat tracing circuit train 112, the emergency boration line, would not maintain temperature. The train B control thermostat set point was adjusted to increase the temperature of the line to 175 F.

C&I-2 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.

C& I-3 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.

C&I-4 The control room cable vault fire detection system alarmed. A check of the fire detectors was performed. One detector was found alarming.

The detector was removed, cleaned and adjusted for the correct sen-

-sitivity. The system reset was actuated and the alarm cleared.

C&I-5 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. The connector and wire were repaired and the channel returned to normal operation.

C&I-6 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.

C&I-7 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.