ML20097A537
| ML20097A537 | |
| Person / Time | |
|---|---|
| Site: | Cook |
| Issue date: | 07/31/1984 |
| From: | Gillett W, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8409130300 | |
| Download: ML20097A537 (7) | |
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AVED. AGE DAILY. UNIT POWER LEVEL
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n 00CXET NO.
50-315 UNIT 1
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DATE 8-2-84 COMPLETED BY W.T. Gillett TELEPHON'E 616-465-5901 MONTH July
~1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net),
(MWe-Net) 1 1,026 17 996 2
1,022 18 996 3
1,019 19 998 4
1,017 20 1006 5
1,017 21 1006 6
1,017 1005 22 7
1,017 23 1000 8
1,018 24 1007 4
~
9 1,015 25 1020 10 1,009 25 1021 11 1,010 27 896 12 1,010 23 13 1,008 29 14 983 30 15 991 31 l
.16 1,002 j
INSTRUCTICNS On this format list the averace daily unit pcwer level irl MWe-Net for each day in the recortina month.
Ccmaute tn *%
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e 50-315 DOCKET NO.
UNITSilUTDOWNS AND POWER REDUCTIONS D.C. Cook-Unit 1 UNIT NAME 8-13-84 DATE COMPLETED BY.
B.A. Svensson JULY, 1984 REPORT MONTil TELEPilONE B6/465-5901 -
PAGE
-1 of 1 "t.
)(Ebch Evens Cause & Connective E;
'E Licensee E
(i N
Action to No.
llate k
3$
k j'
Prevens Reciuvence jE cE j gy3 g Repos Je so O H
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1 225 840727 S
97.0 B
1 N.A.
ZZ
'ZZZZZZ The Unit was removed from service to l
perform required ice condenser sur-veillance and to repair leaking pres-surizer safety valves. The Unit re-mained out of service at the end of the month.
l l
l 1
2 3
4 l
Method:
Exhibis G-Insan ctions F: Foiced Reason:
l S: Scheduleil A Equipmens Failme(Explain)
- 1. Manual for Prei.aration of Data ll-Maintenance of Test
- 2. Manual Scram.
linisy Slicens for Licenste C. Refueling 3 Automatic Scram.
Eveni Repini ll.ER) File INURI:G.
D Regulaiosy Resisiction
-l-Other (Explain) 0161)
E-Opesalos reaining & Ucenw Examination F Administrative 5
lishibit I - Same Somce G-Opesaiional Eisos lExplain) 19/77) ll Other (Explain)
a; UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should desenbe a!! plant shutdowns dunng the m sceordance with the table appearing on the report form.
report penod. In addition it should be the source of explan-If category 4 must be used. supply brief comments.
atton of signi6 cant dips m average power levels. Each sieni-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 pertaimng to the outage or power should be noted, even though the unit may not have been reduction. Enter the Erst four parts (event year, sequent:s!
l shut down completely. For such reductions in power level.
report number. occurrence code and report type) of the 6ve the duration should be listed as zero, the method of reduction part designation as desenbed in Item 17 of Instrucuons for should be listed as 4 (Other). and the Cause and Correctve 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 Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns, of course, smce should be used to provide any needed explanation to fully further investigation may be required to ascertam whether or desenbe the circumstances of the outage or power reduction.
not a reportable occurrence was involved.) If the outsge or power reduction will not result in a reportable occurrence.
NUMBER. This column should indicate the sequential num.
the postuve indication of this lack of correlation should be ber assigned to each shutdown orsigmncant reductionin power noted as not applicable (N/A).
for that calendar year. When a shutdown or significant power SYSTEM CODE. The system in which the outage or power reduction begins m one report period and ends m another.
reduction originated sh' uld be noted by the two digit code at o
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an entry should be made for both report periods to be sure
- 11 shutdcwns or sigmdcant power reductions are reported.
mit G. Instruenons foy heparadon of Data Entry hens Until a unit has achieved its first power generation, no num-f r Licensee Esent Report (LER) File (NUREG.0161).
ber should be assigned to each e stry.
Systems that do not fit any existing code should be designs.
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 appropriate component as 770314 When a shutdown or significant power reducuan from Exhibit I - Instructions for Preparation of Data Entry begins in one report penod and ends m another, an entry should Sheets for Licensee Event Report (LER) File (NUREG.0161).
be made for both report periods to be sure all shutdowns using the followmg entieria:
or sigmficant 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:
reducuan. Forced shutdowns include those required to be e.g., wrong valve operated through error: list valve as attiated by no later than the weekend following discovery component.
of an off. normal condition. It is recognized that some judg.
ment is required in categonzmg 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 descnbed action was taken.
under the Cause and Corrective Action to Prevent Recur.
rence column.
DURATION. Self. explanatory. When a shutdown extends beyond the end or s report penod, count only the time to the Components that do not fit any existmg code shou ld be de.
signated XXXXXX. The code 777777 should be used for end or the report penod and pick up the ensuing down time in the followmg report penods. Report duration of outages events where a component designation is not applicable.
rounded to the nearest tenth of an hour to facilitate summation.
The sum of the total outage hours plus the hours the genera.
CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-tor was on line should equal the gross hours in the reportmg RENCE. Use the column in a narrative fashion to amplify or penod.
explain the circumstances of the shutdown or power reduction.
The column should include the specific cause for each shut.
REASON. Categorize by letter deugnanon in accordance Icant erte u and de immdate and with the nble appearmy on the report form. If category H contempiated long term corrective action taken, if appropn-l must be used, supply bnet comments' ste. This column should also be used for a desenption of the i
maior safety.related corrective maintenance performed dunn.a I
METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identifiestion ot; REDUCING POWER. Categonze by number designation the ennest path aeuvity and a report of any smgle release et radioactmty or single radiation exposure specifiesily assoet.
INote that this differs trom the Edisoa Electric Institute sted with the outage which accounts for more t!un 10 percent tEEll definitions of " Forced Parnal Outage" and " Sche, of the silowacle annual vslues.
auled Partial Outage." For these terna. eel uses a shange or For long textual reports continue narrative on separate paper 30 MW as the break pomt. For targer puwer reserors.30 MW and reference the shutdown or power redustion im tha
- s im small a.hange to wanant explanation.
narranve.
W77
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Dockst No.:
50-315 Unit Nam 3s D. C. Cook Unit I Completed By:
G. J. Peak Telephone:
(616) 465-5901 Date:
08/07/84 O
Page:
1 of _1 l
, MONTHLY OPERATING ACTIVITIES - JULY 1984 Highlights:
The unit entered the reporting period in Mode 1 at 100% of rated thermal power. -The unit operated at 100% power up until 7-27-84 when the unit.was removed from service to complete surveillance requirements on the ice condenser and to repair leaking pressurizer safety valves.
This planned-outage was stili in progress when the reporting period came to an end as the unit was.in mode 5 with the Reactor Coolant System at the half loop elevtion.
No=other major power re-ductions occurred during the reporting period.
Total electrical generation for the month was 675,190 MWH.
Summary:
7-12-84 The low demand fire pump was inoperable from 0435 hours0.00503 days <br />0.121 hours <br />7.19246e-4 weeks <br />1.655175e-4 months <br /> on 7-12-84 to 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br /> on 7-14-84 for maintenance on the system.
The high demand fire pump-was inoperable from 0435 hours0.00503 days <br />0.121 hours <br />7.19246e-4 weeks <br />1.655175e-4 months <br /> on 7-12-84 to 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> on 7-15-84 for maintenance reasons also.
7-13-84 Engineering safety features ventilation unit HV-AES-1 was inoperable from 1250 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.75625e-4 months <br /> on 7-13-84 to 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br /> on 7-14-84 to repair the damper linkage.
7-18-84 The turbine driven auxiliary feedwater pump was inoperable for about 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to repair a leak in the system.
7-27-84 A power reduction to remove the unit from service for a planned surveillance outage started at 2101 hours0.0243 days <br />0.584 hours <br />0.00347 weeks <br />7.994305e-4 months <br />.
The unit was divorced from the grid at 2257 hours0.0261 days <br />0.627 hours <br />0.00373 weeks <br />8.587885e-4 months <br />.
Mode 2 was entered at 2305 hours0.0267 days <br />0.64 hours <br />0.00381 weeks <br />8.770525e-4 months <br /> and mode 3 was entered at 2324 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.84282e-4 months <br />.
4 7-28-84 Mode 4 was entered at 0707 hours0.00818 days <br />0.196 hours <br />0.00117 weeks <br />2.690135e-4 months <br /> and mode 5 was entered at 1809 hours0.0209 days <br />0.503 hours <br />0.00299 weeks <br />6.883245e-4 months <br />.
7-29-84 A Train B blackout occurred at 2030 bours due to the failure of reserve feed transformer 101 AB.
The Control Room Cable Vault Halon System remains inoperable as of 14Co hours on 4/5/83.
The backup CO system for the Control Room 2
Cable Vault remains operable.
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' DOCKET NO.
50 - 315-UNIT NAME-
'D. C. Cook - Unit No. 1~
DATE 8-13-84 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 11 MAJOR SAFETY-RELATED MAINTENANCE JULY. 1984 M 600V Bus ground (Ann:19. Drop' 68) was. received when cycling ICM-321 (W RHR Discharge to Legs 2 & 3).
Found faulted power cable to valve motor. Pulled in new-cable. Valve-retested satisfactorily.
C&I-l-
.The CD battery had_a ground from FRV-251.~ - Water was coming out of the valve from _ a packing leak and had filled the
' lower limit switch with water. A new length of cable was instal. led between the limit switch and the junction box.
' Silicone RTV was used to seal the limit switch case. The ground cleared.
C&I-2
. Loop 4 Tavg and overtemperature AT both failed. 1TY-411B and A, and 1TY-441A and C were all recalibrated. The loops were then declared operable.
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- Ls/RM INDMNA 6.MICHMAN_BECTRIC CCMPAN1
.r,,,,,.
Donald C. Cook Nuclear Plant -
P.O. Box 458, Bridgman, Mchigan 49106 -
' August 13, 1984
-Director, Office.0f Management'Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
Pursuant.to the requirements of Donald C. Cook Nuclear Plant Unit 1 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of July, 1984 is submitted.
Sincerely, W.
. Smith, Jr.
Plant Manager UGS:ab Attachment.s cc:
J. E. Dolan M. P. Alexich R. W. Jurgensen NRC Region III E. R. Swanson R. O. Bruggee (NSAC)
R. C. Callen S. J. Micrzwa R. F. Kroeger B. H. Bennett J. D. Huebner J. H. Hennigan A. F. Kozlowski R. F. Hering J. F. Stietzel PNSRC File INPO Records Center ANI Nuclear Engineering Department
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