Text

Monthly Operating Rept for Apr 1979
	ML17317B203
Person / Time
Site:	Cook
Issue date:	05/03/1979
From:	Gillett W; INDIANA MICHIGAN POWER CO.
To:	;
Shared Package
ML17317B202	List: ML17317B201; ML17317B203;
References
	MOR-790430-1, NUDOCS 7905170262
	Download: ML17317B203 (16)
	v • d • e

AVERAGE DAILYUNITPOR:R L:-VEL DOCI ~O 50-316 UNIT 5-3-7 9 COMPLETED BY W.T. Gl,llete MONTH A ril 1979 DAY AVERAGEDAILYPOVr'ER LEVEL

(,'vfWhet)

316 925 1032 DAY AVERAGE DAlLYPOWER LEVEL (MWe Net) 1074 1081 19 10 l3 I5 894 1079 520 0

374 1069 1079 1062 1057 1

8 1074 1035

'lP 24

')5 26 3S 30 31 167 0 1079 1079 1080 1073 1064 1053 1053 1058 1070 1072 INSTRUCTIONS O." t..lt tQra..8t.:!5: iPae '-'~'"-'te

-"ll~ "t:l'. -:~~eet -" l:."'e': e'ct e~e:1 c2<'.. t:te teed:t" i" '~fPLEYEoBY ii ~il1 lett TELEPHONE ~~-.5 9 0 1 9

0 Donald C.

C

2. Reporting Period:
A
)
1 1
3. Licensed Thermal Power (MWt):
4.. Nameplate Rating (Gross MWe):
5. Design Electrical Rating (Net MWe):
6. Maximum Dependable Capacity (Gross MWe)t
7. ~bfaximum Dep ndable Capacity (Net MWe):
1 133 1,100 '
118 1
082 Notes S. IfChanges Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:
9. Power Level To Which Restricted, IfAny (Net ibDVe):
10. Reasons For Restrictions. IfAny:
Yr:to-Date 2,879 This Month 719 697.1 2 823.6 0
0 2.769.6 0
0 2.164 269
~9409 0
708,420 2
965 250 684 209 2 862,301
92. 2
96. 2
92. 2
96. 2 9.9
90. 4 86.4 7.8 3.8 s (Type. Date. and Du:ation of Each):
11. Hours ln Reporting Period
12. Number Of Hours Reactor Was Critical
13. Reactor Reserve Shutdown Houa
14. Hours Generator On-Line
15. Unit Reserve Shutdown Hoes
16. Gross Thermal Ener y Generated (MWH) l7. Gross Eiectricai Energy Generated (MWH)
18. Net Electrical Energy Generated (MNH)
19. Unit.Service Factor
20. Urit AvailabilityFactor
21. Un!t Capacity Factor (Using MDC Net) 2". Urit Capacity Factor (Using DER Net)
"3 Unit Forced Outage Rate
24. Shutdowns Scheduled Over Next 6 Month Cumulative 1 1 639 8,054. 3 0
7 497.
0 22,214,107 80 6,676 ~300 75.8 74.
25. IfShut Down At End Of Report Period, Estimated Date of Startup'..
6. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved IYITIALCRITICALITY IYITIALELECTRICITY COl I.'iIERCIAL OPLRATION (t)I~7)
UNITSIIUTI)01VNS AND P01VER REI)UCTIONS pORTI)IONTII April, 1979 l)OCKETNO.
, ;~2 l)ATE 5-11-79 COMPLETE() Dy B.A. Svensson TELEPIIONE 616 465-5901
~l Nii.
l)atc PI IA 3J Q
u i
x gn.'CA g
C)
. Ln.cl)st,l Event Rcpi)rt )f 4l Q
O Eu O
Cause &Coffel:t)vc Act)on til Prevent Rc<<uffcncc 53 54 55 790401 S
790401 F
790403 S
0 9.9 0
B 4
H 3
B 4
N.A.
N.A.
N.A.
zz zzzzzz Zz Zzzzzz zz zzzzzz Reactor power reduced to 55% to per-mit removal of test flow nozzles from the main feed pump turbine condensate drain lines.
While placing the east main feed pump back in service, the Unit tripped due to high level in the No.
1 steam gen-erator.
The Unit was returned to service the same day and loaded to 100K 790402.
Reactor power reduced to 705 to per-form N. I.S. Incore/Excore cross cal-ibration.
Reactor power returned to 100K 790404.
I I:: rofceu S: Schellulcil
(')/77)
Reason:
A-Eilulpn)cnl I'alhlre (Explain)
II hlah)tcn;n)cc nr Test C-Rcfucli>>g D.Regulatory Restriction E-Oi erat )r Training & Lice>>sc I.'xaininatiinl I -A)in)inistrativc G Operational EI tof (Explahl)
I I.Othcf (Explahl)
Method:
I -Manlial 2.Manual Scrain.
3-Autolnatic Scrain.
4 Other (Explain)
Exhibit G - Inst ru<<tions fi)r Preparatii)n ol l)ata Entry Sheets for Li<<ensec Event Rcport (LLR) Elle (NURI.'G-Ol 6I )
5
'I!xhibit I - Salne Source
UNITSHUTDOWNS AND POWER RE TIONS 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 207o reduction in average daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) should be noted, even though the unit may not have been shut down completely 1.
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 shutdown 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
~JI 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.
DATE.
This column should indicate the date of the start of each shutdown or significant power reduction.
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 all shutdowns or significant power reductions are reported.
TYPE.
Use "F" or "S" to indicate either "Forced" or "Sche-duled," respectively, 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 oif-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.
Selfwxplanatory.
When a shutdown extends beyond the end of a report period, count only the time to the end ot the report period and pick up the ensuing down time in the following report periods.
Report duration of outages rounded to the nearest tenth ofan hour to faciTitate 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 the report t'orm. Ifcategory H must he used. supply brief comments.
METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.
Categorize by number designation INote that this differs irom the Edison Electric Institute
{EEI) detmitions of -Forced Partial Outage" and
-Sche.
duled Pariial Outage."
F>>r these tern>i. EFI uses a change oi'0
~IW as the break pi>ini. F>>r larger power reactors. SOMW is t>><> small a change n> warrant explanation.
in accordance with the table appearing on the report form.
Ifcategory 4 must be used, supply bri fcomments.
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.) Ifthe 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
(> l/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.
CO>>IPONENT CODE.
Select the most appropriate component from Exhibit I
~ Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) FiIe!NUREG4161).
using the followingcritieria:
A. Ifa component failed, use the component directly involved.
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 ftt any existing code should be de.
signated XXXXXX. The code ZZZZZZ should be used for events where a
component designation is not applicable.
CAUSE & 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 and the immediate and contemplated long term corrective action taken. ifappropri-ate.
This column should aiso be used for a description of the major safety.rehted 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 ur single radiation exposure specitically 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 anJ ret'erence ilie shutdown or power reduction for iliis na rrJ tive.
UNITSIIUTDO)VNS AND POPOVER REDUCTIONS REPORT MONTII Apr'il, 1979 DOCKET NO.
UNITNAME D. C. Cook-Unit 2 22 2
No.
Date Vl FS 2
ri 222 3
<r,L
()
~
~- n 4J
~ C/l Llccnscc Event Rcport 0 4I~
OC Q2 ~
O Cause k, ( i)fir.i.tlvc Aclio>> lo Prcvcnl Rccurrcnce 56 57 790406 F
790407 F
0 46.1 A
N.A.
N.A.
ZZ CB ZZZZZZ INSTRU Reactor power reduced to 55K to per-mit removal from service of one main feed pump turbine condenser at a time for cleaning of'condenser water boxes.
Reactor power returned to 100'X the same day.
Unit removed from service to inves-tigate "High" oil level alarm on the No.
1 reactor coolant pump upper oil reservoir.
Cause was found to be failure of level alarm device.
Alarm device was repaired.
Unit re-turned to service 790409 and reached
'004 the same day.
I I': Forced S: Scllc(l<<lcil Rcasi)n:
A-I:(Iuiptnent Failure (Exl)lairr)
I).hIairitcnancc or Test C. Ref<<el i<<I, D.lkcl,<<latory Restriction I -Operator Traini<<I, A Uccnsc Exanlinaliiln F-Adnlinistrat ive G.Opcraliollal Ltror (I'.xplaitt)
II.Other (Explanl)
Mctliod:
I-Maniial 2 hianual Scrain.
3-Auloinalic Sera<<i.
4-Otiicr (Explain)
- Exliibit G - Instr<<ctions I'or Preparatiil>> ol')ata Lorry Sliccts for Lice<<sec Event Reporl (I.I'.R) File (NUltllG-016I )
'Exliibit I - Salnc Soiirce
UNITSHUTDOWNS AND POWER RE TIONS INSTRUCTIONS This report should describe all plant shutdowns during the report period.
In addition. it should be the source ofexplan-ation of significant dips in average power levels.
Each signi-ficant reduction in power level (greater than 2'eduction in average daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) should be noted, even though the unit may not have been shut down completeiyl.
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 signiiicant 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 JI 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.
DATE.
This column should indicate the date of the start of each shutdown or signiricant power reduction.
Report as year. month. and day.
Auaust 14. 1977 would be reported as 770814.
When a shutdown or significant power reduction begins in one report period and <<nds in another, an entry should be made for both report periods to be sure all shutdowns or significant power reductions are reported.
TYPE.
Use "F" or "S" to indicate either "Forced" or "Sche-duled," respectively, 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.
Self~xpianatory.
When a shutdown extends beyond the end of a report period, count only the time to the end oi the report period and pic'p the ensuing down time in the following report periods.
Report duration 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 appearinv. un the report torm. Ifcategory H must be used. supply briei'comments.
METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.
Categorize by number designation INoie that this dift'ers i'rom the Edison Electric Institute (EEI) definitions of -Forced Partial Outage" and
-Sche-duled Partial Outage."
Fi>r these tern>>. EEI uses a change oi
.0 MW as the breai'oint.
Fi>r larger power reactors. ~0 MW l>>ii st>lail a cllallge t(> Waffalii explanatloll.
in accordance with the table appearing on the report form.
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 ot 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 followingcritieria:
A. Ifa component failed, use the component directly involved.
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 mai-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.
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 and 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 reiease of radioactivity or single radiation exposure specittcally associ-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 and reierence the shutdown or power reduction ior tins lia r ra tive.
(qly7"
Docket No.:
Unit Name:
Completed By:
Telephone:
Date:
Page:
50-316 D.
C.
Cook Unit 0'2 R.
S.
Lease (616) 465-5901 May 9, 1979 (1)
MONTHLY OPERATING EXPERIENCES -- APRIL, 1979
'i hli hts This Unit operated at full power the en'tire period except as noted in the summary.
Total electrical generation for the month was 708,420 Mwh';
~Summar 4/01/79 -- The Unit started the month operating at 55/ power.
The East Main Feed Pump was o'ut of service tor removal of a Condensate Drain Flow Nozzle that had been used for Initial Performance Testing.
The Unit tripped at 1140 hours0.0132 days 0.317 hours 0.00188 weeks 4.3377e-4 months as the East Main Feed Pump was being returned to service.
The intention was to remove the Nest Main Feed Pump for drain nozzle removal.
During the Feed Pump interchange, the Unit tripped due to high water level in 81 Steam Generator.
The, Reactor was returned to criti-cality at 1850 hours0.0214 days 0.514 hours 0.00306 weeks 7.03925e-4 months and the Unit paralleled to the sys-tem at 2133 hours0.0247 days 0.593 hours 0.00353 weeks 8.116065e-4 months .
The Unit was loaded to 100% power by 1142 hours0.0132 days 0.317 hours 0.00189 weeks 4.34531e-4 months 4/2/79.
4/03/79 Power was reduced to 70! for Incore/Excore Nuclear Instrument Cross Calibration.
Power was returned to 1005 by 1425 hours0.0165 days 0.396 hours 0.00236 weeks 5.422125e-4 months 4/4/79.
Total time below 100'A was 18.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .
4/05/79
. One phase of the 69KV off-site power source failed open during a windstorm at 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months .
Repairs were made and
'.th'esource was again available at 0957 hours0.0111 days 0.266 hours 0.00158 weeks 3.641385e-4 months 4/6/79.
4/06/79 -- Loading was reduced to 55K for hand cleaning of the liest Main Feed Pump Condenser.:.
'After this condenser was cleaned the two Main Feed Pumps were interchanged and the East Main Feed Pump Condenser was hand cleaned.
Power was returned to 100/ by 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months the same day.
Total time below 100/ was 9.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .
Docket No.:
Unit Name:
Completed By:
Telephone:
Date:
Page:
50-316 D.
C.
Cook Unit 82 R.
S.
Lease (616) 465-5901 May 9, 1979 (2) 4/07/79 -- Load reduction was started at 1120 hours0.013 days 0.311 hours 0.00185 weeks 4.2616e-4 months and the Unit was removed from service at 1205 hours0.0139 days 0.335 hours 0.00199 weeks 4.585025e-4 months .
Reason was that the upper lubricating oil reservoir for the 81 Reactor Coolant Pump was indicating high.
Inspection found the reason to be level alarm failure rather. than actual high level.
At 2330 hours0.027 days 0.647 hours 0.00385 weeks 8.86565e-4 months both Emergency Diesel Generators started and accepted their designed load.
Cause of start was a
degraded system voltage actuation.
At this time both Units were off the line and they were receiving auxiliary power from the normal outside source.
7 of the 8 Reactor Coolant Pumps were in operation.
As the 8th pump was
started, the degraded voltage actuation was initiated.
4/08/79 -- The Reactor was returned to criticality at 0313 hours0.00362 days 0.0869 hours 5.175265e-4 weeks 1.190965e-4 months .
At 0831 hours0.00962 days 0.231 hours 0.00137 weeks 3.161955e-4 months we experienced fire in the area of Steam Generator Stop Valves b2, 3 and 4.
The cause of the fire was oil on the hot steam lines.
Unknown at that time, the stop valves had developed.hydraulic leaks upon the tr ip of the previous day.
The normal hydraulic fluid for these valves is the fire retardant fluid and the, wrong oil had been added to the system.
When the hydraulic pumps were started to open the valves,,it pumped the normal oil out on the hot steam lines causing the flash fires.
All fires were out by 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months .
The hydraulic system to the four Steam Generator Stop Valves were drained, cleaned and refilled and the valves were trip-tested prior to being;~declared operable at 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months 4/9/79.
1 4/09/79 -- Turbines rolled at 0827 hours0.00957 days 0.23 hours 0.00137 weeks 3.146735e-4 months .
Unit paralleled to the system at 1010 hours0.0117 days 0.281 hours 0.00167 weeks 3.84305e-4 months .
The Unit was loaded to 100/ power by 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months .
Auxiliary Feedwater; to the=82 Steam Generator through FMO-232 was inoperable for a 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period starting at 1004 hours0.0116 days 0.279 hours 0.00166 weeks 3.82022e-4 months .
A cracked weld had been discovered between the FMO valve and its upstream hand isolation valve.
Repairs were made.
The Unit k'2 Motor Driven Auxiliary Feedwater Pump was'inoperable for a 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months period starting at 0108 hours0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months .4/10/79.
This was required for hydrostatic testing of the weld repair.
4 J
2'I
Docket No.:
Unit Name:
Completed By:
Telephone:
Date:
Page:
50-316 D.
C.
Cook Unit 0'2 R. S.
Lease (616) 465-5901 May 9, 1979 (3) 4/13/79 Loading was reduced to 96! power for testing of Turbine valves.
Total time below 1005 was 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .
4/24/79 -- 821 Circulating Water Pump was removed from service at 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months due to unusual noises.
Inspection identified failed pump bearing.
The pump remains under repair.
With this pump out of service, the allowable temperature rise across the Condensers was marginal and the power'.has been reduced to 99/.
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50 - 316 D.
C.
Cook - Unit No.
2 5-11-79 B. A. Svensson 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE APRIL, 1979 M-2 M-4 M-6 M-9 CSI-1 No.
4 steam generator stop valve, MRV-240, hydraulic bypass valve would not release.
The bypass valve was repaired and MRV-240 retested satisfactorily.
A 3/8" OD hydraulic tubing was replaced on all four steam generator stop valve hydraulic actuators.
The hydraulic system fluid levels were restored and the valves retested satisfactorily.
MRV-231, 5'3 steam generator stop trip valve leaked by.
The seat ring was replaced and disc remachined.
Operational retest was satisfactory.
MRV-222, 0'2 steam generator trip valve leaked by.
The seat was replaced and the disc machined.
Retest was satisfactory.
650'ontainment airlocks interlock did not work properly.
Re-placed cable to outer door pawl and springs.
Retest was satisfactory.
Pinhole leak was discovered at inlet to auxiliary feedwater valve, FMO-232.
Ground out a small crack in valve body and repaired by welding.
Had repair examined by PT and RT..
Hydrostatic test was also performed.
No.
3 steam generator stop valve dump valve, MRV-232 was leaking by.
Installed new seat ring and gaskets.
Machined valve plug and re-assembled.
Retested satisfactorily.
Unit 1 west RHR pump vent valve, RH-107W, leaked excessively.
Valve wa,s replaced.
ESW-142, essential service water check valve for 2CD diesel was not preventing backflow.
Discs, seat and springs were replaced.
Retest was satisfactory.
The rod position indication system for rod F-10 indicated full scale.
The signal conditioning modules output voltage was measured and re-corded as 3.690 vdc.
The module was recalibrated and returned to service.
CS I-2 Control Bank D Low and Low-Low rod insertion alarms were received in the control room.
The Bank D pulse to analog coverter was man-ually pulsed in RPI-2 to the actual bank position.
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 - 316 ook - Unit No.
2 5-11-79 B. A. Svensson 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE APRIL, '1979 Axial power distribution monitoring system would not display the correct Fz or print properly.
The system was functionally tested with the test panel.
The problem could not be reproduced and was determined to be a circuit board connector problem.
The high demand fire pump logic would not reset.
A low temperature on the start-up transformer 201CD deluge house caused the deluge abnormal alarm which prevented the logic from resetting.
As the temperature increased, the alarm and logic cleared.
The rod position indication system for rods H-10, B-8, F-10 and K-6 indicated greater than 12 steps from demand.
The secondary coil voltages of the rods were measured and verified correct.
The asso-ciated signal conditioning modules were calibrated to provide the correct indication.
The panel meter, position indication for rod D-8, appeared to respond slower than normal.
The channel was removed from service and tested for response while applying a test input signal.
The panel meter responded as required to the test signal.
The channel was calibrated and returned to normal service.
HARV-251, the centrifugal charging pump flow control valve, position limits were incorrect and would not respond properly when operated in the automatic mode.
The high and low limits were adjusted and the automatic operation of the valve functionally tested.
CPS-610, stator cooling water low pressure generator trip switch, mercury switch was found blown.
The mercury bulb switch of CPS-610 was replaced and the instruments calibration was performed.
During surveillance testing on the Axial Power Distribution Monitor-ing System several problems were identified.
When switching to de-tector number 3, the indication lights required a longer than normal time to respond.
The high F(z) digital indication did not agree with the recorders printout.
The part length step counter failed.
The detector switching relays were not operating properly and were re-placed.
The F(z) digital indication was adjusted to indicate the correct value.
The connector for the part length step indicator was found disconnected and reinserted.
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE PAGE MAJOR SAFETY-RELATED MAINTENANCE APRIL, 1979 50 - 316 D.
C.
Cook Unit No.
2 5-1 -79 B. A. Svensson 616 465-5901 Surveillance test 2 THP 4030 STP.111, 112 and 113; pressurizer pressure protection sets I, II and III, were performed.
The low pressure safety injection bistables were calibrated to trip at 1900 psig decreasing.
The P-ll permissive, which allows manual blocking of the pressurizer low pressure safety injection signal, permits manual blocking below 1907 psig decreasing and automatically unblocks at 1915 psig increasing.
The previous calibration of the pressurizer low pressure safety injection bistables, required the bistables to actuate at 1908 psig decreasing.

ML17317B203

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