Text

Monthly Operating Rept for Feb 1983
	ML20073F254
Person / Time
Site:	Cook
Issue date:	03/14/1983
From:	Might A; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML20073F223	List: ML20073F219; ML20073F254;
References
	NUDOCS 8304150455
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DCCr.r No. 5 -316 DATz 3-2-83 CO.\\L*! ETIO sy A. Mioht Tzt,z,3HCNz (616)465-5901 OPI?.A-'NG S ATUS DONALD C. C00K 2 Nous

1. Uni: b.a==:

FEBRUARY 1981

2. Reporting ?t:fod:

3411

3. LI=nsed Th--*f ?ower(atW:):

1133

4. Namepiate R::in;(Cso:s atW:):

1100 S. Desi;n Be==i=! Rn:in;(Nec 51We):

1118

6. 5tW tu::r Depend:b!: Capsci:7 (Gross 51We):

1082 s

7. Siaxi==m Dep:nd:b! Cng:ci:/ (Net >!We):

N S. If C.:ntes Ce=zr in Cap:ci:y Rn:in;s (1::=s Nc:nhe: 3 Th:ou;h 7) Sine: L:st Report. Cive Re: sons:

9. Power Level To Which R::::f=ed.If Any (N :.\\1We):

10. Resons For ?--=i= ions.If Any:

I 1

This Stonth

' Y ao.Daen Cu=u!n:ive t

672 1416 45,240

11. Hour:!= Repot in P :fod 672 938.5 31,751.9

12. Numb:r Cf Hou:s R==or Was C:i:i=I 0

0 0

13. Rene:or Reserve Shu:down Hou::

i

14. Hou:s Ce:.:= tor ca.Lin, 672 858.8 30.820.5 0

0 0

15. Ur.it R: serve Shutdown Ho==

16. Cross Thc=:1 En:::y Cen==::d (31W1!)

2,242.228 2.583.762 98.847.993 744.530 848.050

31,805,800

17. Cross Ee=:ic=1Iscr;y Cent =: d G.IWH) 719.448 816.611 30.656.403

13. Net E::=i=1In::;y Genen: d C. WE)

19. Unit Serri= Esetor 100 60.6 72.6 100 60.6 72.6 i

20. Ucit As.azhi!!:7 F:sor 98.9 53.3 68.1

21. Unit C::scity 7::: r (Usin; >1DC Net) 97.3 52.4 67.3

. Unit Capscity.::::or(Usin; DER.9eti 0

2.9 13.7

23. Unic For::d Cu::ge Rate

24. Sh : downs Scheduled Over Nec 5.iton:hs (Type. 0:te.:nd Du=: ion of I: ht:

1

)

5. If She: Down At End Of Report P::iod. Estim::ed D:te oiSt:rmo:

i

. 25' Units in Tes: S=:us (Prior ta Ce==r::is! Ope-:: font:

Fore =st Achieved INIT:AL CRIT:CALITY INITIA L I:.ICTR:C;~Y l

Co..:.:E?.C:A:. 0? ira r:0N t

Includes +180 MW to correct error on November 1982 Report g3 8304150455 830314 PDR ADOCK 05000316 R

PDR

c, AVERAGE DALLY UNIT POWER LEVEL i

~ DOCKET NO.

50-316 UNIT 2

DATE 3-2-83 COMPLETED BY A. Might TELEPHONE (616)465-5901 i

MONTH February,1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL j

(MWE-Net)

(MWe-Net) 1 904 17 784 2

1029 18 1095 3

1091 19 1098 4

1088 20 1102 1074 5

21 1100 i

6 1096 22 1096 l

7 1100 23 1056 8

1075 24 1095 9

1066 25 1091 10 1099 25 1088 11 1097 27 1094 12 1091 28 1093 I

13 1101 29 14 1091 30 15 1101 31 16 1085 INSTRUCTIONS On this fonnat list the average daily unit power level in MWe-Net for each day in the reporting month. Ccmoute to the nearest whole megawatt.

50-316 DOCKET NO.

UNIT SiluTDOWNS AND POWER REDUCTIONS UNIT NAME D.C. Cook - Unit 2 DATE 3-14-83 February,1983 COMPLETED itY B.A. Svensson bib-4bb-b901 REPORT MONTil TELEPflONE PAGE 1 of 1 n.

$E 3

E Licensee

,E v, h.

Cause & Connective No.

Date k

3g

)g5 Event g'g p

Actiini lo g'

yE j ;f, Repent #

un U Prevent Recmsence 6-6 100% reactor power was reached for the first time in Cycle IV at 1820 hours0.0211 days 0.506 hours 0.00301 weeks 6.9251e-4 months on 830202.

122 830208 S

0 H

4 N.A.

HB HTEXCH Reactor power was reduced to 80% to place the moisture separator-reheater coils in service. Reactor power was returned to 100% on 820209.

123 830216 F

0 A

4 N.A.

CH ZZZZZZ Reactor power was initially reduced to 80% to remove the "A"-string of H.P. heaters from service to check for leaks.

Reactor power was further re-duced to 57% to remove the west main feed pump turbine from service to re-pair tube leaks in the F.P.T. con-denser. One tube was plugged.

Re-actor power was returned to 100% on 820217.

l l

2 3

4 F: Fmeed Reasim:

Mc Inid:

Exhible G Instrucilims S: Scheduled A.Eiguipmens Failme(Explain) l-Manual for Preparation of Data ll-Maintenan..: of Test

2. Manual Scram.

Enity Sheels Im 1.icensee C Refueling 3 Automatic Scram.

Eveni Repois (1.l!R) File INUREG-D Regulatiny Resisiction 4-Other (Explain) 0161)

E-Openalos Isaining & License lixamination F-Administrative 5

G Operational Essor (Explain) lishibii 1 - Same Somce I'l/77)

Il Olher (Explain)

.4 UNIT SHUTDOWNS AND POWER REDUCTIONS 3

INSTRUCTIONS This report should desenbe 211 plant shutdowns dunng the in accordance with the table appearing on the report form.

report penod. In addition. tt should be the source of explan.

If category 4 must be used. supply bnef comments.

anon of sigmficant dips m average power levels. Eacn signi-LICENSEE EVENT REPORT =. Refer:nce the applicaole ficant reduenon in power level (greater than 20% reduction m average daily power level for the preceding :4 hours) mp rtable occurrence pertainmg to the outage or power reduction. Enter the first four parts (event year, sequent:al should be noted, even though the unit may not have been shut down completely. For'such reducuens in power levet rep n number, occunence code and report type) of the nye l

the duration should be !!sted as zero, the method of reducuan part designation as described m item 17 of Instructions for should be listed as 4 (Other), and the Cause and Correcuve Preparanon of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG.0161). This information may not be Cause and Correenve Action to Prevent Recurrence column tmmediately evident for all such shutdowns, of course, since should be used to provide any needed explanation to fully further investigation may be required to asc rtam whether or descnbe the circumstances of the outage or power reduction.

not a reportable occurrence was involvec.) If the outage or power reduct:en 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 shutdowti or significant reductionin power noted as not applicable (N/A).

for that calendar year. When a shutdown or sigmncant power SYSTEM CODE. The system in which the outsee or power reduction begms m one report period and ends m another.

reduction onginated sh' uld be noted by the two digit code of

~

o an entry should be made for both report penods to be sure Exhibit G. Instructions for Preparation of Data Entry Sheets all shutdowns or sigmncant power reductions are reported, Until a unit has achieved its first power generation, no num, for Licensee Event Repon (LER) File (NUREG.0161).

ber should be assigned to each entry.

Systems that do not fit any existing code should be designa.

ted XX. The code ZZ should be used for those events where DATE. This column should mdicate the date of the start a system is not applicable.

of each shutdown or significant power reduction. Report as year. month, and day. August 14.1977 would be reported COMPONENT CODE. Select the most appropnate component as 770514 When a shutdown or significant power reductior' from Exhibit i. Instructions for Preparation of Data Entry begms m one repon penod and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG.01611.

be made for both report periods to be sure all shutdowns using the following critieria:

or s:gmficant power reductions are reported.

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:

reducuon. Forced shutdowns include those required to be e.g.. wrong valve operated through errort list valve as initiated by no later than the weekend following discovery component, of an off. normal condition. It is recognized that some judg.

ment is required in categorizmg shutdowns in this way. In C.

If a chain of failures occurs, the first component to mai.

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 action was taken.

under the Cause and Corrective Action to Prevent Recur.

tence column.

DURATION. Seif. explanatory. When a shutdown extends Components that do not fit any existmg code should be de.

beyond the end or a report penod count only the time to the signated XXXXXX. The code 777777 should be used for end at the report penod and pick up the ensuing down time events where a component designation is not applirable.

{

m the following report periods. Report duration of outages rounded to the nearest tenth of an hout to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT 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 m the reportmg explain the circumstances of the shutdown or power reduction.

penod.

The column should include the specific cause for each shut-down or significant power reduction and the immediate and REASON. Categonze by letter de> gnation in accordance contemplated long term corrective action taken if appropri.

with the table appearmg on the report form. If category H ste. This column should also be used for a descnotion of the must be used.suppiy bnes. comments.

major safety.related corrective maintenance performed dunna the outage or power reduction including an identification of METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorue by number designation the entteal path acuvity and a report of any smale release et, radioactmty or single radiation exposure speettically assoet.

l%ie that this differs trom the Edison Electric Institute ated with the outane which accounts for more than 10 percent teel) dermitions of " Forced Partial Outage" and " Sche, of the allowable annual values.

duled Partial Ourage." For these tenn>. eel uses a change of For long textual reports continue narrative on separate paper

.to MW as the break pomt. For larger power reactors.30 MW and reference the shutdown or power reduction for this i

is im small a change to wanant aplanation.

narrative.

i

_M

Dockst No.:

50-316 Unit Name:

D. C. Cook Unit 2 Completed By:

R. S. Leass Telephone:

(616) 465-5901 Date:

3/11/83 i

Page:

1 of 2 MONTHLY OPERATING ACTIVITIES - FEBRUARY 1983 l

Highlights:

The Unit entered the reporting period operating at 80% power in the power escalation program following the third refueling of the Reactor Core. The Unit was further loaded to 100% power and power was reduced seven times, below the 100% value, during the reporting period.

Details of these power fluctuations follow in the Summary.

The Unit remained in service the entire reporting period. Total electrical generation was 744,530 MWH.

Summary:

2/1/83 Unit power was increased to 90% over a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ramp starting at 1219 hours0.0141 days 0.339 hours 0.00202 weeks 4.638295e-4 months .

I 2/2/83 Unit power was increased to 96% over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ramp starting at 1026 hours0.0119 days 0.285 hours 0.0017 weeks 3.90393e-4 months .

(

Unit power was increased to 100% over a 3h hour ramp starting at 1502 hours0.0174 days 0.417 hours 0.00248 weeks 5.71511e-4 months . This was the initial loading to this power level for the new Reactor Core.

The East Containment Spray System was inoperable for a 10-3/4 i

hour period while repairs were made to valve 2-CTS-128E.

2/4/83 The Reactor Coolant Subcooling Meter was declared inoperable at 0523 hours0.00605 days 0.145 hours 8.647487e-4 weeks 1.990015e-4 months when it started indicating falsely low.

Repairs were made and this meter returned to service at 1525 hours0.0177 days 0.424 hours 0.00252 weeks 5.802625e-4 months Feb. 17.

During this time period the subcooling margin was j

available from the unit computer.

i The East Residual Heat Removal System was inoperable for a 3k hour period while the system was vented.

i Unit power was reduced to 98% over a h hour ramp starting at 1224 due to a high indication of Delta temperature of Reactor Coolant loops 3 and 4.

2/5/83 Unit power was reduced to-95% over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ramp starting at 1

0407 hours0.00471 days 0.113 hours 6.729497e-4 weeks 1.548635e-4 months for calibration of Reactor Coolant loops 3 a'nd 4 Overpower and Overtemperature Delta Temperature Protection Instrumentation.

Unit power was returned to-100% over a 2h hour ramp starting at 1345 hours0.0156 days 0.374 hours 0.00222 weeks 5.117725e-4 months .

I 2

- - - +

Docket No.: 50-316 Unit Nama: D. C. Cook Unit 2 Completed By: R. S. Lease Telephona: (616) 465-5901 Date: 3/11/83 Page: 2 of 2 2/8/83 Unit power was reduced to 80% over a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ramp starting at 2104 hours0.0244 days 0.584 hours 0.00348 weeks 8.00572e-4 months to place the heating coils of the reheaters in service.

2/9/83 Unit power was returned to 100% over a 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ramp starting at 0237 hours0.00274 days 0.0658 hours 3.918651e-4 weeks 9.01785e-5 months .

The South Safety Injection System was inoperable for a Sh hour period while repairs were made to valve 2-ICM-265.

2/11/83 Valve 2-MRV-231 (Emergency Closure For Steam Generator Stop Valve #3) was inoperable for a 3h hour period for repairs.

2/12/83 Unit power was reduced to 95% for testing of turbine valves.

Total time below 100% was 3h hours.

2/14/83 The Reheater Heating Coils were removed from service at 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months due to excessive steam consumption by the right Southwest coil.

2/16/83 Unit power was reduced to 80% over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ramp starting at 2128 hours0.0246 days 0.591 hours 0.00352 weeks 8.09704e-4 months to remove the "A" set of high pressure heaters from service to check for a leak in the No. 5 heater.

No leak was identified and the set of heaters were returned to service.

2/17/83 Unit power was further reduced to 57% over a lh hour ramp starting at 0525 hours0.00608 days 0.146 hours 8.680556e-4 weeks 1.997625e-4 months to remove the West Main Feedwater Pump from service so it's condenser could be checked for inleakage of circulating water. One leak was repaired and the pump was returned to service.

Unit power was returned to 100% over a 7h hour period starting at 1240 hours0.0144 days 0.344 hours 0.00205 weeks 4.7182e-4 months . During this time there was a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months hold at 90%

power while turbine valves were tested.

2/23/83 Unit power was reduced to 85% over a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ramp to place the Reheater Heating Coils in service. Six of the eight heating coils were placed in service. The coil that was indicating high steam consumption 2-14-83 and it's companion coil were left out of service.

Unit power was returned to 100% over a 4h hour ramp starting at 1635 hours0.0189 days 0.454 hours 0.0027 weeks 6.221175e-4 months .

2/25/83 Unit power was reduced to 95% for testing of turbine valves.

Total time below 100% was 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

Main condenser halfs were out of service, one half at a time, for a total of 295 hours0.00341 days 0.0819 hours 4.877645e-4 weeks 1.122475e-4 months during the reporting period for identification and repair of circulating water leaks.

i' I

UNIT NAME D. C. Cook - Unit No. 2 DATE 3-14-83 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE 4

FEBRUARY,1983

[L-JL No. 3 steam generator stop valve dump valve, MRV-231, was leaking by. Replaced the valve stem, cage, seat and plug.

Reassembled and had the valve tested.

i M-2 The miscellaneous CCW header isolation valve, CM0-416, would not close during a test. Adjusted torque switch and had l

valve retested.

C&I-l Pressurizer pressure indicators were in disagreement by greater than 20 psi. Pressure transmitter NPP-151 was recalibrated to bring the indication channels into coincidence.

C&I-2 Containment isolation valve, WCR-915, (non-essential service water) could not be closed from the control room. Actuating i

solenoid valve XS0-915 was replaced to restore operation to the WCR.

C&I-3 A spurious overpower AT automatic rod block C-4 was received from reactor coolant loop No. 3 instrumentation.

Cold leg RTD resistance-to-voltage converter module 2TY-413B was found to have drifted low in output, causing AT signal to be high and the T average signal to be low. The module was recalibrated and the alarm cleared.

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ML20073F254

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