ML19327B055
| ML19327B055 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 09/30/1989 |
| From: | Morris K, Stice D OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-89-915, NUDOCS 8910250040 | |
| Download: ML19327B055 (23) | |
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l Omaha Public Power District 1
1623 Harney Omaha, Nebraska 68102 2247 402/536 4000 October 33, 1989
'LIC-89-915 U. S. Nuclear Regulatory Commission l
Attn: Documeet Control Desk-Mail Station PI-137-
+
Washington,.DC 20555
Reference:
' Docket No. 50-285 L
Gentlemen:
l l'
SUBJECT:
September Monthly Operating Report l
Pursuant to Technical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1),
please find enclosed one copy of the September 1989 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.
If you should have any questions, please contact us, p3 Sincerely,
/
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Division Manager l
Nuclear Operations KJM/pje c:
R. D. Martin, NRC Regional Administrator l.
K P. H. Harrell, NRC Senior Resident Inspector L4 Office'of Management & Program Analysis (2)
R. M. Caruso - Combustion Engineering R. J. Simon - Westinghouse Nuclear Safety Analysis Center INP0 Records Center American Nuclear Insurers l
891025004o 890930 PDR ADOCK 05000285 i
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PNU I
'85 5124 Empiourtie'til with Eutsal ')pporturisty Male / Female
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-285~
UNIT Fort Calhoun Station i
DATE October 13. 1989 4
COMPLETED BY D. L. Stice TELEPHONE (402)636-2474
'i 4
MONTH September 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net)
+
1 452 17 304
~ '
2 453
~18 304-3 455 19 303 l
4 456 20 302 5
456 21 303 6
455 22 303 7
455 23 305 8
456 24 180 9
456 25 0
10 460 26 0
11 461 27 0
12 461 28 0
13 421 29 65 14' 305 30 111 15 305 I'
16 304 l-
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INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day l
in the reporting month. Compute to the nearest whole megawatt.
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OPERATING DATA REPORT
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DOCKET NO.
50-285 UNIT Fort Calhoun Station OATE October 13, 1989
. COMPLETED BY D. L. Stice TELEPHONE (402)636-2474 OPERATING STATUS 1'
1.
Unit Name:
Fort Calhoun Station Notes i
2.
Reporting Period:
September 1989 3.
Licensed Thermal Power (MWt):
1500 1
4.
NameplateRating(GrossMWe):
502 j
5.
Design Electrical Rating (Net MWe): 478 6.
Maximum Dependable Capacity (Gross MWe):
502 7.
MaximumDependableCapacity(NetMWe):
478
'I 8.
IfchangesoccurinCapacityRatings(ItemNumbers3through7)SinceLastRepor Give Reasons:
N/A i
I 9.
PowerLeveltoWhichRestricted,IfAny(NetMWe):
N/A
- 10. Reasons for Restrictions, If Any:
N/A This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 720.0 5,807.0 139,65'
- 12. Number of Hours Reactor was Critical 618.7 4,863.5 108,21
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 1,30
~
- 14. Hours Generator On-Line 609.8 4, 63 7._1_.
107,05
- 15. Unit Reserve Shutdown Hours 0.0 0.0 L
- 16. GrossThermalEnergyGenerated(MWH) 748,608.2 6,376,662.0 139,265,65
- 17. GrossElectricalEnergyGenerated(MWH) 236,692.0 2,056,336.0 45,800,46
- 18. NetElectricalEnergyGenerated(MWH) 222,992.0 1,953,461.9' 43,724,96
- 19. Unit Service Factor 84.7 79.9 76.7 l
- 20. Unit Availability Factor 84.7 79.9 76.7 4
1 21.
UnitCapacityFactor(UsingMDCNet) 64.8 70.4 67.7 l
- 22. Unit Capacity Factor (Using DER Net) 64.8 70.4 66.0 23.
Unit Forced Outage Rate 15.3 5.8 3.0 t
l 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
l Refuelino Outage estimated to beain on February 17, 1990, with a planned I
duration of 86 - 116 days.
25.
If Shut Down at End of Report Period, Estimated Date of Startup:
N/A 26.
Units In Test Status (Prior to Commercial Operation):
Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION
L'
_a Refueling Informati:n Fort Calhoun - Unit No. 1 q
Report for the month ending September 1989 i
1.
Scheduled date for next refueling shutdown.
February 1990 2.
Scheduled date for restart following refueling.
May 1990 1
3.
Hill refueling or resumption of operation thereafter require a' technical specification change or other i
license amendment?
Yes e
a.
If answer is yes, what, in general, will these be?
- Incorporate specific requirements resulting from reload safety analysis b.
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to deter-mine whether any unreviewed safety questions are associated with the core reload.
c.
If no such review has taken place, when is it scheduled?
4.
Scheduleddate(s)forsubmittingproposedlicensing action and support information.
January 1990 5.
Important licensing considerations associated with refueling, e.g., new or different fuel design or sup)1ier, unreviewed design or performance analysis met 1ods, significant changes in fuel design, new operating procedures.
None Planned 6.
The number of fuel assemblies: a in the core 133 assemblies b in the spent fuel pool 437 c spent fuel pool storage capacity 729 d)plannedspentfuelpool May be increased l
storage capacity via fuel pin consolidation l
or dry cask storage 7.
The 3rojected date of the last refueling that can be disclarged to the spent fuel pool assuming the present l'
licensed capacity.
1994*
- Full core offload of 133 assemblies lost.
l Prepared by A We*+----
Date October 10. 1989 l
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DOCKET NO.- 50-285 UNIT NAPE Fort Calhoun Station '
DATE - October-13, 1989 UNIT SHUTDOWMS AND POWER REDUCTIONS COPFLETED BY D. L. Stice -
TELEPHONE (402) 636-2474 REPORT MONTH September 1989 i
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890913 0
4 Reduced power due to delta-T power anomaly.
4 890924 F
110 A
1 Shutdown due to suspected problem with RC-3A upper thrust bearing.
Problem found to be failed RTD wiring. RTD and wiring replaced.
I i
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1 2
3 4
F-Forced Reasort Method:
Extet G - hetnsctione S-Scheduled A-Equipment Fabre Explain) 1-4denuel for Properation of Deta j
B-Maintenance or Test 2-Manuel Scram Entry Shoots for Licensee C-Refuegno 3-Automatic Scram Event Report E.E74 FBo SUEG-0189 I
D-Regidatory Restriction 4-Other Explain l 1
E-Operator Tralrdng & License Examinetton 5
j F-Admhistative Eidet 1 - Some Sasce G-Operationat Error H-Other GExplain)
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I OMAHA PUBLIC POWER DISTRICT V
Fort Calhoun Station Unit No. 1 j
4 r
September 1989
'Manthly Operations Report i
I.
OPERATIONS
SUMMARY
Fort Calhoun Station operated at a nominal 100% power until September 13, 1989, when an anomaly involving the Reactor Protective Systa (RPS) occurred.
The delta-temperature (delta-T) power indication on two RPS 1
channels deviated low by approximately 4% and two channels deviated high by approximately 2%. Other abnormal indications were a 2'F drop in the s
delta-T recorder feeding the reactor regulating system and an approximate 2% drop in power input to Reactor Coolant Pump (RCP) RC-38.
Nuclear power and delta-T power are auctioneered for the highest power input to the RPS.
The two RPS channels that c'eviated low were declared inoperable since the deviation was in the non-conservative direction.
A power reduction to 70%
was initiated per Technical Specifications. The anomaly corrected to normal indications when reactor power reached 76%.
Power is to remain under 70% until sufficient justification for the cause of the anomaly is i
formulated and there is reasonable certainty that there are no safety concerns restricting a return to 100% power.
Dolta-T )ower is not used in the safety analysis.
At all times during this event t1e nuclear power and all other )lant indications remained normal and constant.
The most likely cause of tie event is thermal stratification of the flow in the hotleg of the reactor coolant system. This anomaly has occurred at several other Combustion Engineering plants after having gone to a low neutron leakage core design. This core design produces a higher temperature gradient across the core.
On September 24, 1989, the upper thrust bearing temperature indication for RCP motor RC-3A was observed trending up and above the specified operating limit. A rapid shutdcwn of the plant was initiated from 69% power. At about 8% power the temperature indication on the bearing spiked up.
The reactor was manually tripped and RC-3A was secured. A plant cooldown was initiated to facilitate repair of the thrust bearing. Investigations during the plant shutdown indicated the thrust bearing was not damaged but the wiring from the Resistance Temperature Detector (RTD) was found to have cuts in the insulation. The RTD and wiring were replaced.
Fort Calhoun Station returned critical September 28 and held at 10% power for vibration monitoring of the reactor vessel thermal shield.
The generator was online September 29 and back to 69% power October 1, 1989.
l The Raw Water / Component Cooling water heat exchangers have been experiencing flow restrictions due to deposits of sand settling in heat L
exchanger end bells. More passive methods of removing the sand have not proved satisfactory so heat exchanger AC-1B was opened up and cleaned out.
L During ISI testing, data showed that Raw Water Pump AC-10C was in the required range for corrective action. The pump shaft lift was adjusted but the pump still did not meet design requirements. AC-10C was removed and I
rebuilt.
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Mcnthly Operations Report Page Two iy r
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The post maintenance testing showed pump AC-10C was operable and by calculation is capable of design flow rates. However, since the margin
)
J above minimum acceptable performance is not large, an administrative control has been applied to enter a more restrictive Technical Specification Limited tenottion for Operation (LCO).
If Raw Water. Pump AC-10A becomes inoperable, AC-100 will also be declared inoperable.
Both AC-10A and AC-10C are fed by the same Emergency Diesel Generator.
Modification work continues on the Control Room HVAC, Instrument Air Dryer, and Security System.
Construction continues on the Chemistry / Radiation Protection and Radiation l
Waste Buildings. ' Site preparation has begun for the Administration 3
Building.
' The following NRC inspections took place in September:
IR 89-33 Resident Inspectors' Monthly Inspection IR 89-34 Follow Up to Generic Letter 88-17 Loss of Decay Heat Removal
'IR 89-36 Operating Procedures IR 89-39 Follow Up to Raw Water System Operability Concerns The following LERs were submitted.
Date Submitted 89-S07 Failure to Maintain Compensatory Measures -
Inattentive Security Officer September 21, 1989 89-S08 Failure to Maintain Compensatory Actions September 20, 1989 89-14R1 Auxiliary Feedwater Panel Outside Design Basis September 29, 1989 A.
PERFORMANCE CHARACTERISTICS None.
B.
CHANGES IN OPERATING METHODS None.
C.
RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS l
None.
i-1 l'
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i Monthly Operations Report
'Page Three 3
e E
D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL System Acceptance Committee Packages for September 1989:
Packaae Descriotion/ Analysis r
None E.
RESULTS OF LEAK RATE TESTS The Reactor Coolant System Leak Rate Test, ST-RLT-3 F.1, indicates t
for the month of September a continuation of the elevated total leak E
rate seen throughout Cycle 12.
On September 24, the plant was placed in hot shutdown to repair a
' problem with RC-3A-M's upper thrust bearing temperature indication.
' Within a couple of hours of achieving hot shutdown, the RCS System Engineer we.s in containment measuring all of the valve leak-off temperatures, RCP vapor seal leak-off temperatures, RC loop drain line temperatures, and the temperature of the equipment drain header just upstream of the Reactor Coolant Drain Tank (RCDT) loop seal. No appreciable leakage was found visually or through leak-off temperature measurements. There was, however, evidence of RC leakage into the RCDT. The temperature measured at the bottom of the Equipment Drain Header (EDH) just before the loop seal was 155'F.
The source of this possible leakage was not found.
The plant was placed back in service on September 29. The heat-ups, cooldowns, and other plant maneuvering during this mini-outage, skewed the leak rate test results. Overall, no RCS leakage tests performed during the month of September appeared unusual for the Cycle of operation or for the particular plant conditions.
l F.
CHANGES IN PLANT OPERATING STAFF Two Operators were hired during the month of September 1989.
G.
TRAINING During the month of September, three licensed operator applications were submitted to the NRC for an October examination.
Plans for a second Reactor Operator program beginning in October were developed.
As a result of discussions held, six individuals were identified to enter the program beginning October 2, 1989.
Reactor Operator i
students from the first class continued training and will begin on-the-job training (CJT) October 2, 1989 and continue through i.
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Monthly Operations Report Page Four January 15, 1990.
Senior Reactor Operator (SRO) candidates completed preparations and practice walk through examinations for the October 2,.1989 NRC examination.
A meeting between OPPD, Westinghouse and Interfacts was held to establish criteria on the formal factory acceptance test, simulator shipment from Pittsburgh to Omaha, and the estimated shipment date of l
Fort Calhoun's new sit.iulator.
The current estimate is that the i
formal factory acceptance test will begin the week of October 23, 1989. Normal operations testing of the simulator continued and it 1
has been determined this testing will not be " official" testing due to the number of deficiencies identified.
The Abnormal Operating Procedures (A0Ps) are 52% complete and on schedule toward meeting the November commitment.
Shift Technical Advisor candidates took part in 1"
simulator training, OJT, and completad their comprehensive examination and Oral Boards, General Employee training, as well as System Engineer, Technical Staff and Quality Assurance training, continued as scheduled. Maintenance training was' conducted as scheduled for September. _ A semiannual maintenance training and plant maintenance conference was held on September 21,.1989.
Chemistry / Radiation Protection initial training also continued as scheduled during the month of September.
The NRRPT exam preparatory class started on September 25, 1989.
H.
CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY l
COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 l
l-Amendment No.
Descriotion None II. MAINTENANCE (Significant Safety Related) l 1.
See attached printout.
L l
G. R. Peterson Manager-Fort Calhoun Station l
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COMPLETE 09/22/89 i
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p C75812 AC-RW VALVE ~IS EXTREteELY HARD TO OPERATE.& VALVE LEAKS PAST THE SEAT. GRIND OUT
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3 STUFFING SOA DEPTH WAS 1 1/8*.
3 COMPLETE: 09/29/89 t
WORK DESCRIPTION CG1880 AC-RW HCV-2861 LIMIT Sw!TCH. GREEN LIGHT NOT INDICATED w1TH VALVE CLOSED.
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_2 COMPLETE: 09/09/89 5 & G READ 2.14 VOLTS OM 4-20-69 c.r8 CELL' TEMP OF 5 & 6 wERE BOTH 7BF GFB SEE ATTACHED DATA SHEET.
WORM DESCRIPTIOt8 886648 EE VI$UAL INSPECTION AND CLEANUP OF DRvCHEM. DISCHARGED DUE TO FIRE IN DG-1~
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~~C' SEE-DAN JOHNSON FOR INSP. CRITERIA AND WGRA INSTRUCTIONS.
EE wCRK PERFORMED COE. Y CLASS:
- INSPECTION OF ROOM BETnEEN OG ROOMS AND SWITCHGEAR ROOM SHowED NO SIGNS OF CRv CHENICAL. ROOM 63 NEEDS TO INSPECTED CS 12-14-88. ROOM 63 1MJECTE s
D & CLEANED HAD OC INSPECT'ALL AREAS.
COMPLETE: 09/12/89 l
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l' COMPLETE: 09/12/89
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- C90777-RC C/112C TEaspERATURE=INO1 CATION-
~; DROPPING OUT AT~RPS CHANNEL "C*
-c C/TE,112C DEF TAG s881267 - TECH SPEC.2.15'
~
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.AND WETER ON (8-3.
s.
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AT POT MEAD. TEMP. READS 540.6 erTF-192C:/ TE122C READS-540.8. NO CAL 8IR-u Q --
WORK PERFORMED-j.-
CQE:.V CLASS: SR TIGHTENED CONNECTIONS AT POTHEAD VERIFIED THAT CABI.ES DID NOT Groused 'OUT r',
COntPLET E : 09/18/89 007
' LOOP HAS 980T DROPPED -
~
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ATION OF LOOP REQUIRED.- RPS READS TC540.9. ' 9-17-89..
. s. s
..g c.
WORK DESCRIPTION' y
CO2285 CH
' PRESSURE SWITCH FOR LUBE OIL APPEARS TO BE wfRED WRONG. SEE RIGH CONNERS EN'
'C-FOR DETAILS a
PCS-224 WORK PERFORMED' M
COE: V CLASS: SR INVESTIGATED WIRIteG AMD FOUND TO BE WIDED IN ACCORDANCE WITH DRAwlteG_
~
- 4.^ ~
161F561 SHEET 4 g
g COMPLETE: 09/06/89 J
WORK DESCRIPTION C92315 EE CONTROL INDICATING PANEL AT MCC 15 NO teOUNTED COR9ECTLY AND WIRING !$ -
EM - -
C^
q EXPOSED.
T.S.2.2-'
MCC-3C2-DO2 WORK PERFORWED COE: V CLASS: SR
-INSPECTED CUBICLE AND CUBICLE DOOR AND BOuteD TO BE CM r BREAKER WAS IN -
_d.
CUBICLE FRIMLv AND COULD NOT BE REP OSITIONED.
j-L COMPLETE: 09/01/89 7.
. - ~
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WORK DESCRIPTION B92319 FE NEED TO INSTALL COVER ON VACATED CUBICLE C04 IN NCC*3A2 TO. PREVENT
~
'Em-C' DEBRIS froes ENTERING MCC.
~
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CLASS: SR INSTALLED 2 SETS OF 450 BLANAS OVER EXISTING HOLES IN CUBILE COVER. ANO FA5TENED WITH 2-3/4-x'1/4 BOLTS AND NUTS COMPLETE: 09/01/89 r----
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" PE -
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.M LACED w!TH NEw STEM & DISC REPACMED= INSTALLED SONMET & MEW GASMET MEEDS PACMING GLANOS.
_4 COMPLETE: 09/26/89
~ ~
' ' 3 wCRK DESCRIPTION CO2957 DG LUBE OIL EXPANSION TANK HAS LEAKING UNIONS ON TOP OF TAMK
- y
- PE
- C.
~
WORK-PERFORMED COE: v CLASS: SH DG-2 BRAZED COUPLING QN DRUM AFTER REMOv!NG PLASTIC INSERT THREADS SECA USE THEY MERE BROMEN. DISCONNECTED VENT PIPING.HAD NO OBSTRUCTION HAD QC CLOSE OUT. D-G-1 TIGHTEN LOOSE FITTINOS ON VENT LINE AND HAD OC CLOSE O COMPLETE; 09/26/89 UT.
worm DESCRIPTION 893448 CH REPAIR OR REPLA'E VALVE AS NEEDED.THIS Mwo w!LL VOID PE
~ C M.O.874005. VALVE IS IN ROOM 7 AND-IS A mELDFD END VALVE.
CH-371 mORK PERFORMED
~
COE: v CLASS: 1 DISASSEMBLED WALVES. CLEANED & LAPPED SEAT WITH 220 GRIT CLOVER-COMPOUND' THEN FINSISHED w!TH 600 GRIT CLOYER COMPOUNT REPACMED & REASSEMBLED WITH NEVER SEIZE ON THREADS. CLEANLINESS LEVEL C FOUND INSIDE VALyt AROUND T COMPLETF: 09/01/89 HE SEATING SURFACE. LEVEL 8 RESTORED.
+~
WORM DESCRIPTION C93648 CH CH-400 IS AN EQUALIZATION VALVE.IT CPERATES HARD.NEEDS TO BE DISASSEMBLE.
PE C
AND CLEANED. LUBRICATE AS NEEDED.
CH-400 WORK PERFORMED CCE: Y CLASS: 1 LUBRICATED VALVED STEM..AND MANUALLY OPERATED THE VALVE FPOM FULLY OPEME D TO FULLY CLOSED SEVERAL TIMES TO PROVE GOOD OPERASILITV BONMET REMOVAL AND VALVE REPACK WAS NOT REOutet0 TO REPAIR VALVE TO OPERABLE. STATUS.
COMPLETE: 09/01/89 2"
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CO3684 CH
'CH-183 HAS WATER LEAMING FROM TOP CAP / REPAIR--VALVE DELLOws LEAS'. AGE.
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. }k BELLOWS PUT VALVE BACM TOGETHER AND TESTED THE VALVE PASSED ALL TESTS.
5 7_
- r -
WORM DESCRIPTIO's L,k C;37F6 CH EXCESSIVE PACMING LEAM.REPACM PLUNGER PACKING.
MM - - C CH-1A WORM PERFORMED COE: Y CLASS: 1 REPACMED POMP AND REPLACED PLUNGERS.
PER INSTRUCTIONS. PER HP-CH-I:
,,j COMPLETE: 09/12/89 wCAM DESCRIPTION' 893882 CH ADO OIL AS NEEDED TO CHARGING PUMPS. CRAMM CASE. AND GEAR SOM ON CH-14, Wes C-u B.
AND C DURING THE MONTH OF AUGUST.
CH-1A WORK PERFORMED COE: V CLASS: N
.NO WORK OONE USING THIS MO DURING AUG4JST.
COMPLETE: 09/05/09
~ ~
~
wCRM OESCRIPTION C93894 SI-HP I&C TO RESET AND REPAIR HCW-2987 BOOSTER IF NEEDED FOR THE esONTH OF
-IC C.
AUGUST. BOOSTER IS NON-CQE T S.2.3 SI-HP WORK PERFORMED COE Y
CLASS: 1 RESET INTENSIFIER. L'POWELL 8-8-89-1607/ RESET INTENSIFIER 8-25-89 FOUNO AT320 LEFT 350 A-GREEN / WALT NENEMANl' RESET INTEN$1FIER 8-029-89 FOUND -
=
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AT 315 LEFT AT.350 P DOWNINA/ DALE PIME.:
COMPLETE: 09/01/89
- FOUND AT 320 LEFT AT 350 L PONELL 9-8-89.
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'r 003897 St ALL S.1. TANK REFERENCE LEGS NEED TG SE-FILLED FOR THE MONTH OF1 AUGUST IC-~
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CQE: Y CLASS: 1 8-31-89 1015-FILLED $1-60. BEFORE W-73. N-71.4 AFTER W-70.5 NO 70.2.Ju
~
COMPLE7E: 09/01/89
^
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- WORK DESCRIPTION 803997 AI REPAIR PRINTHEAD ON TAR THREE (3) RECORDER, PRESENTLY ORAWING A_ STRAIGHT ~
'1C;
'.C-
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LINE.
tab 3
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work PERFORMED COE V
CLAS$t N INSPECTED TAR-3.NO STRAIGHT LINE BEING DRAwM 8-17-89. COULD MOT Ot.1PLICAT E ORGINAL PROBLEM. NO REPAIRS REQUIRED.MO CP PERFORMED.
COMPLETE: C9/09/R9 l
L',
a WORK DESCRIPTION 094083 RC OPERATIONS 15 EMPERFENCING TO muCH RIPPLE ON TEMPERATURE-INDICATION ~
IC 5
OF THE RCS w1DE RA%E LOOP.. POSSIBLv POWER SuPPLv PROBLEM.
TT-113 h0RM PERFORMEO -
CCE: v CLASS: S ON hot.D AWAITING Dw! FROm ENGINEER DID WORM PER DETAILED WORM INSTRUCT 10'-
N AND CP-113/115 (ATTACHED) REPALCED 20 mFDAT 100 VDC CAPACITOR IN LOOP.
POWER SUPPLv. BENCH TESTED AT RATED C.URRENT AND REINSTALLED.DURING POST <
COMPL E T E : 09/25/89 MAINT TESTING IT WAS REQUIRED *O DECAL OR-113/115 SECAUSE LOOP TEST. FALL ED. RETEST OK.
^
worm DESCRIPTION C94355 EE-BA AT AMMETER A1 w!RE s 80 'I5 LIFTED FPOW #81' TO AmerETER FOR NO APPARENT A Em
-C-EASON. SUGGEST ATTACNMENT OF WIRING AS PER SOLIDSTATE-ORw
- 2C6288. LPM' EE-8F (6681) FOR G. WOOD (6877) e 1313-08/24/891 i
WORM PERFORMED COE: v CLASS: N RELANDEO w!RE PER WORK INSTRUCTIONS AN3 DRAW!NGS.
(
i COWPLETE: 09/21/H9 l
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'894357 EE-GA-
_ AT AssR8ETER A1 WIRE #80 IS LIFTED FROtt P81 TO AmuETER FOR NO APPARENT-RE.
- n. j WORK DESCRIPTION _
^
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C' C
_n P
-ASON.'SUGGEST THAT WIRING SE RETERWINATED AS PER SOILOSTATE ORd a.2C6289 lE~
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L G. ' WOOD (667 7). e ',1337 08/ 24/89 must aOOO2566
~
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EE-6G LPM (6681) FOR 7
f'
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WORK PER FOResED -
- p.
i COE: Y CLASS: N LANDED WIRE PER WORK INSTRUCTIONS CO#PLETE: 09/21/89 j
wCRK DESCRIPTION-C04387 AC-Rw PUwP PERFORMANCE DOES NOT.wEET AN ADEOUATE MsRGIN ASOvE REQUIRED LEAR RA '
- um -,
.C.
3 TES.(PER SURVAILANCE TEST). REMOVE.AND REPLACE AC-10C PuesP.
~
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~
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- CLASS: 3 REMOVED PUNP ON 9-15-89 AND PEPLACEC w!TH PEBUILT SPARE PER MP-AC-10(9-1 Er
~
S/9-16) PUNP FAILED ST-Re-2 AND #wO 897565 WAS 'INITI ATED TO RESUILD Pump 1.
~
q REBUILT Pump USING NEw PARTS AS LISTED ON towO 8975651 REw0VED Pump AND R i
COMPLETE: 09/21/09 EINSTALLED AFTER REPAIR USING MP-AC-10(9-18-89)
I l
w.
.~
wCPK DESCRIPTION
~
u-F C-s SEAL LEAWAGE ALARM CAME IN AT O$QWPSN06/27/09'. VALVE WAS CLOSED AND-
-?
893409 RC OPERATIONS REPORTS PRESSURIZER SPRAY VALVE ALA&M PCV-183-2 (A-4 E2)
N PE
- C-T'
' ~
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PCV-103-2 ALARM CLEADED AT 1832 08/27/89. ItevESTIGATE FOR ^ POSSIBLE PROBLEMS.
f q '-
t ALSO Cr*ECK PCV-103-1 FOR PROPEa PACKING ADJUSTMENT,
~
wGDK PERFORNED CCE: < CLASS: 1 TIGHTENED PCV-103-2 PACKING NUTS TO-45FT LBS WHICM REQUIRED APROK. 1/8
' 1
-~
~
TURN EACM. PACKING NOT SEIZING. IS'7/8 64Ex NOT. NON-PATCMET TVPE 3/8"-
TCRQUE wmENCH wOULD WORK BEST w!TH A 3/8 DRIVE DEEP mELL SOCKETZ.PCV-103' COMPLETE: 09701/89
-1 WAS CHECKED AND FOunD TO BE FAIRLY ShuG 35 TO 45FT LBS
,~
i WORK DESCRIPTION 69a581 AC-RW AC-10C FAILED ISI TEST. ADJUST PUMP IsePE LLER LIFT.
MRI C-AC-10C wOen PERFOPMED COE: w CLASS: 3 TAGGED OUT Pump AND ADJUSTED LIFT PER MP-AC-10-AND PLANNERS. INSTRUCTION, S.
PUwp AS FOUND HAD.125 LIFT. CHECAED TOTAL LIFT AND FOUND TO BE.650 l
RESET LIFT TO.012 l
COMPLETE: 09/14/89 L
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" COMPLETED COE MwC*S SEPTEMSER..
,.fET ~ D,~~
, S[d W l.d U OATEp19/06/99)
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WORE DESCRIPTION:
u'c e 894634 Al THE GROUND IMO1CATING LIGHT ON A1-418 NEGATIVE SUS INDICATES A GROUND.NE cf EM -
,? h.
ED.TO TROUSLE$NOOT TO DETERMINE WHERE.THE GROUND IS.
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AI-418 D.
ROVAR/JEV
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+ TO GROUND 95vDC. NEG TO GROUND-3SvDC4 FOUND DC-GROUNO IN 82 SATTERV
'N Q _c -. T CHARGER. MwO WRITTEN.
s.
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J f
COMPLETC 09/29/89
~
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1 WORK DESCRIPr!ON
'i 094682 87W IMvESTIGATE PRCOLEWS ASSOCIATED w1TH CALIBRATION DOCUMENTATION CU RM.
ICK 3-RM-060 060.
9 I
-d WORK PERFORMED
- M COE Y
CLASS: S JUMPED OUT ANALIZER BOARD. MOVED DETECTOR GEOMETRY AwAv FROM SERVICE UNT
~, ~
It wE GOT GROSS COUNTS 1E6 wtTH BA 133 a345. THE TOOK A SOURCE SET READI.
NG SEE,ATTCHED. THIS PROVED THAT 8v BACRING OF ON THE DETECTOR WE WERE A~
COMPLETE: 09/21/89 SLE TO REDUCE OR ELIMINATE THE SATURATIONOF~THE PM TUGE PERFO##ED CP-060
~
APPLICABLE SECTION ON SECONDARY CAL. ALL INTO WAS GOOD 9-21-89.
work DESCRIPTION 094686 AC-Rw REMOVE VALVE FROM SYSTEM BV GRINDINGOUT THE SOCMET MELDS. DISASSE4GLE.
PE' 3-INSPECT. RE-AS5Em8LE AND TEST RELIEFVALVE PER WP-RV-1 RE-INSTALL VALVE D5-222 IN THE SYSTEM BV WELDING THE SOCKET WELDS FOR THE INLET AND OUTLET.
wOnn PERFORwCD e
COE: V CLASS: 3 REtappED VALVE SEAT & DISC. HAD THE NOZZLE WACHINED REPALCED THE GASMETS
-4
. VALVE wAS FULL OF SANO. WELDED RELIEF VALVE Rw-222 BACM IN PLACE R.
=0:
^
h uSLE 9-29-89.
COMPLETE: 09/29/89 WORK DESCRIPTION 694T16 AC-RW REPLACE THE VALVE BV WELDING IN A REPLACEMENT SOCMET WELDED GATE VALVE.
~ PE C.
THE ORIGINAL VALVE WAS REMOVED ON MnO 8893850 OUE TO THE VALVE-8EING R3-169 CBSTRUCTED.
WORK PERFORMED 2
,~.
COE: W CLASS: 3 REPLACE VALVE Rw-169-p wOweLE 9-29-89 REPACRED NEW VALVE w!TH GRAFOIL PACMING PRIOR TO INSTALLATION.
COMPLETE: 09/29/89
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- 7 ' e COMPLETED COE MwO'S.--SE.3TENBERJ.
- TIMES 15
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- 894739 AI PLEASE REPAIR. TAR-3 RECORDER SLIDEw1RE/AND OR' servo MOTOR.
IC 4
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CCE:
- CLASS: S REPLACED SLIDE.wfRE. PERFORMED CALIBRATION 9-27-89. REPALCED SERUD MOTOR.
m PERFORMED CAL CP-T AR-3 9-28-89.
J- ~ dN COMPLETE: 09/28/89
~
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WORK DESCRIPTION C94742 RC TECHNICIAN REMOv!NG TQ-113 FROM PANEL. RECEIVED A: SPURIOUS-PRE-TRIP
'IC' C-ALARM ON TWLP ON C CHANNEL AND POSSteLv s/2 TRIP ON PPLS.
CHECK C/PO-102 FOR LOOSE FUSE HOLDER ON ~ ADJACENT POWER SUPPLV TO C/PQ-IO2 FOR POSSIBLE_
'n PROBLEMS AS REPORTED 8V DICK CAMP 8 ELL. I/C SHOP.
,1 WORM PERFORMED 7
i COE: Y CLASS: 5 CHECMED 8 LOCK CONTACTS IM 8LOCM CIRCUIT FIRST THEN FOUND FUSE HOLDER EAR -
S LOOSE. IN C/PQ-lOZ PULLED FUSE AND TIGHTENED EARS PEIN5ERTED. CHECMS O x
COwpLETE: 09/26/09
.j worn DESCRIPTION E94764 VA NEED TO INSTALL 90 DEGREE EL80w EXTENTIONS TO 4 INCH DRAINLINES.THESE PE'
_C DRAINLINES ARE TELLTALE LINES FROM FAN _ HOUSINGS 6A AND 66 1t4 VA-6A AND 68 CONTAINMENT.
worn PERFORMED COEe V CLA55: 1 TM-69-M-044 EL80w IS NOT.NOR IS IT NEOu1 RED TO BE CCE WORK AUTHORIZED P-ER Temp WOD. MJ DUNHA4 SvS-ENGNR 9-29-69.' F ABRICATED 'Tw'J 4 OF 4 PVC PIPE.
CUT LONGITUDINAL TO ' FORM THROUGH. INSTALLED WITH TWO HOSE CLAMPS AS PER-COMPT.E T E : 09/27/89 Temp WOO 889-M-044 s
wo#m DESCRIPTION 094782 EE-8A THE BATTERv CHARGER IS CAUSING A GROUND.ON DC BUS #2. NEED TO TROUBLESHO Em C
OT TO IDENTIFV PROBLEM. AND MAME REPAIRS AS REOUIRED TO RESTORE NORMAL OP EE-BD ERATION.
J.FOLEV/JEV WORK PERFORMED
-e CCE: Y CLAS5: N TROUBLE SHOOT AND SU5PECT D-7 DIODE BAP VZ50PA40C VARISTOR TROUBLE-SHOT FOUND CABLE GOINT AMP METER IN CONTROL RM THEN COMPUTER GROUNDED GFS 9-2
~
8-89 RN. TRACED GROUNO TO AI 208 8 SIGNAL CONDITIONER CARD 1701-2 AND CHA-COwetETE: 09/29/89 RGER s2 DN BUS WITH NO GROUNDS. RN/GF8 9-29-89
~~
I&C w=R 3720 WRITTEN TO CLEAN GROUNOS IN AI. 2C98-TP1 -
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