ML17317B274
| ML17317B274 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/04/1979 |
| From: | Gillett W, Lease R, Svensson B INDIANA MICHIGAN POWER CO. |
| To: | |
| Shared Package | |
| ML17317B271 | List: |
| References | |
| NUDOCS 7906190296 | |
| Download: ML17317B274 (7) | |
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I AV:-RAGEDAILYUNITPOVr R L:-VEL I
DOCI--7 NO.
6-4-79 GPMPLETED I)Y W.T. Gillett
~g ~HONE 616-465-5901 MONTH DAY A~AGEDAILYPOWER LEVEL (MWC-Net) 0 0
DAY AVERAGE DAII.YPO)!'ER LEVEL (MNC-Net) 0 17 0
3 10 0
0 0
0 0
0 0
19 21 2T 55 i5 0
~ 0 0
0 0
0 l3 IS 0
0 0
0 0
2S
%9 30 31 0
0 0
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OPERATL JG DATAREPORT DOCKET NO.
DATE COMPLETED BY TELEPHONE 50-315 ett 16-t~901 OPERATING STATUS Donald C. Cook 1
L Reporting PeriorL 3
Licensed Thettnaf Power (MWt)t
- 4. Narnephte Rating (Gross ilfWe):
- 5. Design Electricai Rating (Net hfWe)t
- 6. l(faxfmurn Dependable Capacity (Gross MWe)t
- 7. Maximum Dependable Capacity (Net MWe)r 3250 1089 1054 1080 1044 Notes S. ffChanges Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:
- 9. Power Level To Which Restrict<, IfAny (Net hfWe):
- 10. Reasons For Restrictions, lfAny:
II. Hours In Reporting Period
- 12. Numoer Of Hours Reactor Was Critical
- 13. Re"ctor Reserve Shutdown Hours
- 14. Hours Generator On-Line
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (BfWH)
- 17. Gross ElecaicJ Fner y Generated (ii)WH)
IS. ilet Electrica Energy Gene!at d ( if'iVH)
- 19. Unit Servic Factor
- 20. Unit Availability Factor "I. Un!t Capacity Factor (Using i~1DC Net) 2". Unit Capacity Factor (Using DER i let)
~. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months This Month 744 0
0 0
0 0
0 0
0 0
0 0
0 Yr:to-Date 3,623 2
2 0
2,205.1 0
6,942,086 2 306 110 2,224 982
- 60. 9
- 60. 9
- 58. 8 58.2 3.7 IType. Date. and Duction of Each):
Cumuhtive 38 707 29 423.6 463 28,618.4 321 78,279,877 25 5
5 770 24 562 159
- 76. 3 67.4 61.8 6 ~ 0
- 5. IfShut Down At End Of Report Period. Estimated Date of Startupr
~
'5. Units In Test Status IPrior ro Cornrnercial Opemtionl:
Forec" st Achieved INITIAL CRITICALITY INITIALELECTRICiTY CO,,DIERCIAL OPERATION
UN(TSllUTDO)UNS ANl)POlVER REDUCTIONS REPORT hlONTlI DOCKET NO.
DATF 6-13-79 COMPLETED nY B.A. Sv sso
~H No.
Dale C
an L
C) r)
anjJ ra a
N>>
~ fly Lice>>scc Event Rcpi)fl +
0 Cl an il) G Cause &. Ci)rrccllvc Action to Prcvcnl Rccurrcncc 149 790406 744.0 B,C N.A.
ZZ ZZZZZZ The Unit was removed for Cycle III-IV refueling outage on April 6, 1979.
The scheduled refueling outage has been extended to perform testing of concrete expansion anchor bolts per I.E. Bulletin No. 79-02 and to re-pair cracks identified in the main feedwater piping.
The Unit remained out of service at the end of the month.
F: Fi)reed S: Schcd>>lc(l
(')/77)
Rcasi)>>:
A.E lulpnlcnl FJllurc (Explaill)
I)-hlai>>tenancc or Test C-Ref>>clio(;
D-Rct,nial ory Rest riel ion l:-Operator Training & Lice>>sc l:xanli>>ation I"Ail>>)I>>lslliltlvc G.Opcratii>>lal Error (lixplJin)
I l.OII)cf(Ext)1JI>>)
hlcthod:
l -Maniial 2.hlanual Scraln.
3-Auli)nla lie ScrJ>>).
0 Olllcf(ExplJI>>)
ExllibilG - instructions fi)rPrcparJIII>>l l)fDala E>>lry Sl)ects I'or Lice>>sce Evc>>l Report ((.LR) File (NUREG-016I)
Lxhibil I - Sa)ne So>>rcc
UNITSHUTDOWNS AND POWER RE IONS 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 leveis.
Each signi ~
ficant reduction in power level (greater than 207'eduction in average daily power level for the preceding-24 hours) should be noted, even though the unit may not have been shut down completelyi.
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 fully describe the circumstances of the outage or power reduction.
NUMBER.
This column should indicate the sequential num-ber assigned to each shutdov'n 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 shouid be assigned to each entry.
DATE.
This column should indicate the date of the start of each shutdown or significant power reduction.
Report as year. month. and day.
Auaust 14. 1977 would be reported as 770814.
When a shutdown or significant power reducrion begins in one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or signiricant power reductions are reported.
TYPE.
Use "F" or -S" to indicate either "Forced" or "Sche-duled." respectivelv, for each shutdown or significant power reduction.
Forced shutdowns include those required to be initiated by no later than the weekend following discovery of an off.normal condition.
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.
Seif~xplanatory.
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 duratibn of outages rounded to the nearest tenth ofan hour to facilitate summation.
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 th>> report form. Ifcategory H must be used. supply briei comments.
METHOD OF SHUTTlNG DOWN THE REACTOR OR REDUCli>IG POWER.
Categorize by number designation INoie that this ditt'ers irom the Edison Electric Institute (EEI) definitions ot'Forced Partial Outage" and
-Sche.
duied Partial Outage."
Fi>r these term~. F.FI'uses a change ot'.0 MW as the break point.
Fi>r larger power reactors. 30 MW is t>><> su>all a change ti> warrant explanaiii>>i.
in accordance with the table appearing on the report torm.
Ifcategory 4 must be used, supply brief comments.
LICENSEE EVENT REPORT
=.'.
Reference the applicable reportable occurrence pertaining to the outage or power reduction.
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).
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.) If the outage or power,'reduction will not result in a reportable occurrence.
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).
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.
COMPONEiNT CODE.
Select the most appropriate component from Exhibit I - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161).
using the following critieria:
A. Ifa component failed, use the component directly invo!ved.
B. If not a component failure, use the related component:
e.g..
wrong valve operated through error: list valve as component.
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 wnere a
component designation is not applicable.
CAUSE Ec 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.
The column should include the specific cause for each shut-down or significant power reduction hand the immediate and contemplated long term corrective action taken. ifappropri-ate.
This column 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 of radioactivity or single radiation exposure speciiically associ
~
.ated with the outage which accounts for more than 10 percent of the allowable annual values.
For long textual reports continue narrative on separate paper and rei'erence the shutdown or power reduction i'or tiui liaffactive.
(L)I (7
Docket No.:
Unit Name:
Completed By:
Telephone:
Date:
Page:
50-315 D.
C.
Cook Unit Pl R.
S.
Lease (616) 465-5901 June ll, 1979 1 of 1
MONTHLY OPERATING EXPERIENCES -- MAY, 1979 Hi hli hts This Unit was in its third annual refueling outage the enti re reporting period.
Summar It became necessary to remove the Reactor Vessel Head the second time due to possible fuel damage in..locations G-8 arid N-8.
New secondary sources were installed in this area and after the head was reinstalled we were notified that the source assembly would not fit in these locations without possible fuel damage.
05/21/79 -- After cracks in feedwater lines of Unit 2 had been identified, radiographs were taken of the feedwater attachment to the Unit 1
Steam Generators and indi-cation was that 3 of the 4 had developed cracks.
The pipe elbow that attaches to the Steam Generator is being replaced on all 4 Steam Generators.
05/22/79 -- The Reactor Vessel Head was removed at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />.
The fuel assemblies in the C-8 and N-8 locations did indicate minor damage and they were replaced with fuel assemblies from a previous core.
Of the two new source assemblies, one was damaged to the point that it could not be extracted from the fuel assembly.
A third new source was used to replace the damaged one and the two sources were relocated in the core to positions B-7 and P-9.
05/27/79 -- The Reactor Vessel Head was again set down on the flange at 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br />.
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50 - 315 D.
C.
Cook - Unit No.
1 6-13-79 B. A. Svensson 6 6 465-590 MAJOR SAFETY-RELATED MAINTENANCE MAY, 1979 M-5 M-6 M-7 M-8 M-9 M-10 M-11 M-12 NESW containment isolation check valve, NSW-417-4, did not pass leak test.,
Cleaned valve internals.
DCR-,205 and DCR-206, containment, isolation valves, did not pass leak test.
The v'alves'iaphragms were replaced.
North waste gas compressor would not operate.
Replaced diaphragm on suction valve RRV-378.
Retested satisfactorily.
CCR-460 and 462, component cooling water containment isolation valves, did not pass leak test.
Valves were disassembled; cleaned and retested satisfactorily.
NSW-415-1, NESW containment isolation check valve did not pass leak test.
Seats were lapped.
Retest following repairs was satisfactory.
Pressurizer relief valve, NRV-151, leaked by.
Replaced seat ring and checked the -seat ring fit to the plug.
Retest was satisfactory.
Minor surface indications in reactor vessel hot leg to safe-end welds on loops 2 and 3 were ground out.
Necessary NDE was performed following grinding.
Excess letdown heat exchanger component cooling water containment isolation valves, CCR-460 and 462 failed to pass leak rate test.
Re-placed the valve cages, plugs and stems, pins and gaskets.
Valves retested satisfactorily.
Auxi1 iary feedwater isol ati on valve to 82 steam generator, FMO-222 leaked by due to internal wear.
Valve was removed from the line, returned to manufacturer and repaired.
Valve was then reinstalled and tested satisfactorily.
All required NDE including hydrostatic test was performed.
Discharge valve from the boric acid blender to the volume control
- tank, HARV-451 was leaking by.
Replaced the valve diaphragm.
Valve retested satisfactorily.
Letdown line from regenerative heat exchanger regulating valve, HARV-161, had a leaking diaphragm in the valve operator.
Replaced operator diaphragm.
Valve tested satisfactorily.
The RHR pump discharge valve to the RCS cold legs, IM0-234, motor operator came loose from the valve and damaged power cable.
Power cable was replaced and valve operation verified.