ML20006G013
| ML20006G013 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 01/31/1990 |
| From: | Stice D OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20006E501 | List: |
| References | |
| NUDOCS 9003010475 | |
| Download: ML20006G013 (17) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL-
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DOCKET NO.-
50-285 UNIT Fort Calhoun Station (I
DATE February 12, 1990
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COMPLETED BY D. L. Stice TELEPHONE (402)636-2474 "p
MONTH
January 1990 D AY. -
AVERAGE DAILY. POWER LEVEL DAY AVERAGE DAILY POWER LEVEL-i:
(MWe-Net)
(MWe-Net) 1 466' 17 467 2'
466 18 467 3.
466-19 467 4'
'467 20 467 5
458 21 467 6
443 22 467 7
443 23 466
'8 451 24 465 9
466' 25 466 10 467 26 466-11=
467 27 466 12 467 28 467 13 4f.7 29 467 14 467 30 A67
~ 15 -
467 31 467 16 467 l
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I INSTRUCTIONS I '
On this form, list the average daily unit power level in MWe-Net for each day
-i in'the reporting month. Compute to the nearest whole megawatt.
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OPERATING DATA REPORT l
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s DOCKET NO.
50-285-UNIT Fort Calhoun Station DATE February 12, 1990 COPFLETED BY D. L. Stice TELEPHONE-IT6fT6"36-2474 OPERATING STATUS 1
- 1. -Unit Name: Fort Calhoun Station-Notes
-1
'2..
Reporting Period:
January 1990 3.
Licensed Thermal Power (MWt):
1500 J
4.
Nameplate Rating-(Gross MWe):~
502
.i
.5.
Design Electrical Rating (Net MWe): 478 j
6.,iMaximum Dependable Capacity (Gross MWe): 502 N
. 7.
Maximum Dependable Capacity (Net MWe):
478 1
L8.
If changes occur in Capacity Ratings (Item Numbers 3 through 7) Since Last Report,.
p Give Reasons:
l N/A 9.-PowerLeveltoWhichRestricted,IfAny'(NetMWe):
N/A i
10
. Reasons for Restrictions, If Any:
N/A This Month Yr-to-Date Cumulative I
- 11. Hours in Reporting Period 744.0 744.0 143,354.0 12.:, Number of Hours Reactor was Critical 744.0 744.0 111,910.3
- 13.: Reactor' Reserve Shutuown Hours 0.0 0.0 1,309.5
- 14. Hours Generator On-Line 74C5~
744.0 110,749.4 15.' Unit Reserve Shutdown Hours 0.0 0.0-0.0
- 16. GrossThermalEnergy^ Generated (
1,107,379.1 1,107,379.1 144,722,490.3 e + 17. = Gross Electrical Energy Generated H) 362,196.0 362,196.0 47.572,304.2
- 18. Net Electrical Energy Generated (
-345,492.6 345,492.6 45,413,045.4
- 19. Unit Service Factor 100.0-100.0 77.3
- 20. Unit Availability Factor 100.0 100.0 77.3
- 21. UnitCapacityFactor.(UsingMDCNet) 97.1 97.1 68.8 l
i
- 22. Unit Capacity Factor (Using DER Net) 97.1 97.1 67.2
~~~~
23." Unit Forced 0utage Rate 0.0 0.0 2.9-l
. 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
t
- Refueling Outage estimated to begin February 17, 1990, with a planned duration of 86 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 1NITIAL CRITICALITY INITIAL ELECTRICITY N/A COPHERCIAL OPERATION l
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ly:
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y R,fu3 ling Infctmation Fort Calhoun - Unit No. 1 Report for the month ending January 1990
]
C 1.
Scheduled date for next refueling shutdown.
February 17, 1990
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2.
Scheduled date for restart following refueling.
May 13. 1990 3.
Will refueling or resumption of operation thereafter-require a technical specification change or other
- license amendment?
Yes a.
If answer is yes, what, in general, will
-these be7
- 1) Decrease the total unrodded integrated radial peaking factor,from 1.40 to 1.70.
- 2) Decrease the total unrodded planar radial peaking factor from 1.80 to 1.75.
- 3) Decrease the PLHGR from 15.22 to 14.4 Kw/ft
- 4) Change the TM/LP P equation to reflect a i
var change in the gamma term from -11350 to -11240.
b.
If answer is.no, has the reload fuel design i
and core configuration been reviewed by yout-Plant Safety Review Committee to deter-mine whether any unreviewed safety questions are associated with the core reload.
N/A c.
If no such review has taken place, when is it scheduled?
N/A
-4.
Scheduled date(s) for submitt'.ng proposed licensing action and. support information.
Subm(tted Jan. 1990 5.
Important licensing considerations associated with refueling, e.g.
new or different fuel design or j;
supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new.
I operating procedures.
None i:
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) planned spent fuel pool May be increased g
storage capacity
-via fuel nin L
consolidation or dry cask storage 7.
The projected date of the last refueling tha d be discharged to the spent fuel pool assuming the present licensed capacity.
1994*
- Capability of full core offload of 133 assemblies lost.
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Prepared by Date February 9, 1990 w
_q.
DOCKET NO. 50-285 UNIT NAfE Fort Calhoun Station DATE February 12. 1999~
UNIT SHUTDOWNS AND POWER REDUCTIONS COPFLETED BY D. L. ' Stice -
TELEPHONE (402) 636-2474-REPORT MONTH January, 1990 4
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Report #
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There were no unit shutdowns or significant reductions in power during the month of January,1990.
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1 2
3 4
F-Forced Reasort heethod-ExNtdt G - Instructions S-Schedr'ad A-Equipment FaRure (Explain) 14denuel for Properetton of Data B-Maintenance or Test 2-Manuel Scram Entry Shoots for Ucensee C-RefueIng 3-Autcwtic Scram Event Report (LER; FRe IPUEG-01811 D-Regulatory Restriction 4-Other (Expleb6 l
E-Operator Training & License Examinetton _
5 l
F-Administative ExNtdt 1 - Same Source G-Operational Error H-Other (Expimin)
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- e OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 January 1990 i
Monthly Operating Report 1
1.
OPERATIONS
SUMMARY
j Fort Calhoun Station operated at a nominal 100% power throughout the month
)
of January,1990, except for a period from January 5 through January 8.
During this period power was reduced to 95% to perform required moderator temperature coefficient surveillance testing.
The diesel fire pump discharge piping replacement was completed and the fire pump was returned to service. All four raw water pump discharge check
. valves were replaced.
j A design problem was identified where the containment spray pump suction piping is rated for a lower pressure than the shutdown cooling system.
Previous analysis for a worst case fire took credit for a containment spray pump used in an alternate shutdown cooling alignment to achieve and maintain cold shutdown. The design problem invalidates this analysis.
Additional compensatory measures have been implemented until procedures and repair parts are in place to restore a low pressure safety injection pump i
to operable status following a worst case fire.
The control room toxic gas monitors have been inoperable due to modification work on the ventilation system. As a result the control room has been in the recirculation mode for an extended time period.
Limited l
sampling capability by the toxic gas monitors was restored, and, with additional administrative controls in place, intermittent fresh air make up l
to the control room is now permitted.
L Modification work continues on the instrument air dryer and security system.
A modification was started to install air dryers on the emergency diesel generator starting air system. Work continues for the third Auxiliary Feedwater Pump modification.
Construction continues on the Chemistry and Radiation Protection and Rad Waste Buildings.
The following NRC inspections took place in January,1990:
IR-89-50 Resident Inspectors' Monthly Inspection (continued thru January 15, 1990)
IR 90-01 Regulatory Guide 1.97 Inspection IR 90-02 Resident Inspectors' Monthly Inspection (from January 16,1990)
IR 90-03 Surveillance Program Inspection IR 90-05 Inservice Testing Program The following LER's were submitted:
Date Submitted 89-023 Failure to Comply with High Radiation Area January 10, 1990 Access Requirements 89-S10 Discovery of Shotgun Shell in Protected Area January 03, 1990
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,c Monthly Operating Report Page Two o
A..
SAFETY VALVES OR PORV CHALLENGL F. FAILURES WHICH OCCURRED None B.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description None System Acceptance Committee Packages-for January 1990:
Packaae Description / Analysis MR-FC-86-59 American Technology Corporation (ATCOR) System Removal
==
Description:==
This modification provided for removal of the ATCOR waste processing system which was nonfunctional.
Sa_fety Analysis:
The removal of the unused ATCOR waste processing system did not increase the probability or consequences of an accident, nor did it reduce the margin of safety-as defined in the basis for any Technical Specification.
The removal of the ATCOR system did not damage any Critical Quality Element (CQE).
Therefore, this modification does not have an adverse effect on the safety analysis.
MR-FC-87-018 Relocation of Underground Fire Loop
==
Description:==
This modification provided for the relocation and expansion of the underground fire loop for building expansion at Fort Calhoun Station.
Safety Analysis:
Modification of the Underground Fire Loop was carried out beyond the confines of the main plant and there's no safety related equipment located in or directly adjacent i
'to the construction area. Modification of this Fire Protection System maintained compliance with the National Fire Protection Association (NFPA) codes.
No change or impact on the existing power plant systems were afforded by this modification.
The relocation of the Underground Fire Loop did not increase the probability or consequences of an accident, and the margin of safety was maintained since no changes to the existing power plant systems were performed. This modification, therefore, does not have an adverse effect on the safety analysis.
l
' Monthly Operating Report n
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Page:Three MR-FC-87-026. Replacement of the P250 Computer
.m
==
Description:==
1.
This modification provided for the transfer of computer points from the P250 computer to the Emergency Response Facility (ERF) computer.
Safetv Analysis:
- Transfer of computer points from the P250 computer to the ERF computer doesn't increase the consequences of an accident. This modification doesn't reduce.the margin of safety as defined in the basis for any Technical Specification since the CQE portion of the modification
-is a functionally equivaient equipment replacement with no design basis change.- No increase in the probability of occurrence of an accident exists.
This modification, therefore, does not have an adverse effect on the safety J
analysis.
1 MR-FC-88-063 Control Room Heating, Ventilating, and Air Conditioning (HVAC) Prep Work Descriotion:
This modification provided for the beginning of pre-outage work on the control room HVAC modification MR-FC-81-51. This removed non-seismic, non-boundary walls, rest room, kitchenette, the ceiling of the control R
room and removed VA-171 air conditioning to the computer d
room.
' Safety Analysis:
This modification consisted of architectural changes I
being made to the Control Room and removal of auxiliary
. steam piping. The safety function of any CQE equipment was not impacted.. Control room habitability was not compromised and no other new accident possibilities were l
created. Control room envelope integrity wasn't breached L
so habitability will be maintained through radiological or toxic gas release. Toxic Gas Monitor and Control Room-Ventilation operability Technical Specification l
requirements were observed.
Installation didn't impact the operability of either. so the-margin of safety as defined in the basis for any Technical Specification was not reduced. This modification did not increase the probability of occurrence or consequences of an accident. This modification, therefore, does not have an i
adverse effect on the safety analysis.
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Monthly Operating Report s
Page Four N
MR-FC-89-047 Electrical Service for Station Engineering Trailers Descriotigr:
a This modification provided for installing a new power panel MPP-037 and utilized existing power panel MPP-039 to provide electrical power service to the station engineering trailers. This modification also provided gai-tronics and communications to the station engineers' trailers.
Safety Analysis:
The installation of this modification had no affect on plant equipment and did not create the possibility of degrading CQE equipment.
Nuclear safety was not affected since no CQE components were located within the construction area.
The provision of electrical power, gai-tronics and communications to the station engineers trailers did not increase the probability or consequences of an accident.
This modification, therefore, does not have an adverse effect on the safety analysis.
C.
RESULTS OF LEAK RATE TESTS The reactor coolant system leak rate test, ST-RLT-3 F.1, indicates for the month of January a continuation of the elevated leak rates seen throughout Cycle 12. The actual leak rate tests gave varying results due to changes in the condition of the operating and standby charging pumps.
The maximum leak rate for the month was recorded on January 27, 1090.
This test registered a total leak rate of 0.691 gpm and an unknown leak rate of 0.229 gpm.
The minimum leak rate for the month was recorded on January 9, 1990. At this time, the total leak rate was 0.473 gpm and the unknown leak rate was -0.002 gpm. There was no evidence of primary to secondary leaks into the steam generators.
Plans have been formulated by the System Engineering Department to attempt to correct the leaks from the Reactor Coolant System.
D.
CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT T0 10CFR50.59 Amendment Ng.
Description Amendment No. 123 This amendment modifies Fort Calhoun Technical Specification Section 3.1, Table 3-3 in order to correct an administrative error that was made when Amendment No. 32 to the Technical Specifications was issued.
The changes requasted pertain to surveillance testing of the Interlocks-Isolation Valves on Shutdown Cooling Line.
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-Page Five bs M ;7e
' Amendment No.
Description-Amendment No. 124 Ihis amendment adds'an operating mode number
- for. each operating mode in Table 3-4 of the Technical Specifications.
In. addition, in the Refueling Shutdown mode, when fuel is in -
the core, a water sam) ling and analysis is required. However, w1en the total core has!
been off-loaded, this amendment. incorporates:
h
,that t is water testing and analysis is not..
required since there is no fuel in the core; II. MAINTENANCE (Significant Safety Related)
N
.See Attachment I
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,is Gary R. Peterson i
Manager-Fort Calhoun Station j
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-PAGEs.
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.OPPD FORT CALHOUN PLOWT :
(WFFRMMH1),
. TIME:~16:5g
-COMPLETED CQE MWO'S JANUARV LE A D'..:PRINTE.
- :j CHAMPS REPORT NO7 MWO #
SYSTEM ~
-DISC STATUS-
~-
EQUIP ID
' WORK DESCRIPTION
. P E.
.C 883739 ~
AC-SFP
. VALVE HAS A. PACKING LEAK WHEN SHUT.
AC-186 PERFORMED WORK VALVE AC-186 AND REPLACED THE O-RING AS PER PE-RR-VX-04285 TORQUE COE: Y CLASS: 3
-REPACK TO PE-RR-VX-04285 REPLACE COVER-AS QC CAGE TESTING AREA KEG
't-25-90 COMPLETE: 01/25/90 WORK DESCRIPTION MM ~
C PERFORM PRESSURE BREAMDOWN TEST ON THE SEAL REMOVED FROM RC-3C PER 888081 RC MP-RC-3-3-C.
-1990 OUTAGE PREREQUISITE RC-3C WORK PERFORMED COE: Y CLASS: 1
' PERFORMED BREAKDOWN TEST PER ATTACHED PROCEDURE MM-RR-RC-OOO7. THI S -
PROCEDURE SUPERCEDES MP-RC-3-3-C. WORK WAS PERFORMED WITH NO PROBLEMS ALL BREAKDOWN'S FLOWS WERE ACCEPTABLE.
COMPLETE: 01/19/90 WORK DESCRIPTION FM -
C.
888092 RC PERFORM PRESSURE BREAKDOWN TEST ON THE SEAL REMOVED FROM RC-3D PER MP-RC-3-3-C.
1990 OUTAGE PREREOUISITE RC-3D WORK PERFORMED COE: V CLASS: 1 PERFORMED BREAKDOWN TEST PER ATTACHED PROCEDURE MM-RR-RC-OOO7. THIS PROCEDURE SUPERCEDES MP-AC-3-3-C. THE FLOW ON THE MIDDLE PRESSURE TABLE 1 RC-25088 DID NOT MEET THE ACCEPTABLE CRITERIA ON BREAKDOWN COMPLETE: 01/19/90 THE UPPER BREAKDOWN RC-24734 AND THE LOWER BREAKDOWN RC-24724 WERE ACCEPTABLE PER TABLE 1.
WORK DESCRIPTION NUTS WHICH DO NOT MEET MINUMIM THREA PE C-FLANGES HAVE'EIGHT 889180 SI-CS INLET AND OUTLET TIGHTEN BOLTS TO ENSURE ALL NUTS MEET MINIMUM THREAD ENGAG D ENGAGEMENT.
EMENT.
SI-3A WORK PERFORMED COE: Y CLASS: 2 PERFORM AS REQUIRED BV WORK INSTRUCTIONS. ON DISCHARGE FLANGE 10 OF TE 1 2 STUDS WERE CHANGED. TWO STUDS HAD ON:BOTH END 1 /2 THREAD ENGAGEMENT COMPLETE: 01/15/90
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' OPPD FORT CALHOUit - PLANT r COMPLETED COE MWO'S'
~ JANUARY-. $ (ttFFRMMH1 ).
' TILE :.16:55 '
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- CHAMPS REPORTiEOTs MWO #
SYSTEM
.LEADJ:
PRINTER I'
s DISC $.STATU$ -
EQUIP ID ~
WOR K' DESCRI PTION PE. -
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894055 AC-SFP ISOLATION VALVE NEEDS REBUILT.IT LEAKS,8V THE SEAT.
AC-191
' WORK PERFORMED"
~"
ISOLATED AND DRAINED SYSTEM. REMOVED VALVE FROM SYSTEM AND INSTALLED NEW SEAL RING NEW 0-RING AND NEW PACKING. PACKING FOLLOWER WAS CRACKED DURI COE: Y CLASS: 3 NG REPACKING WHEN THE FOLLUWER WAS TORQUED. FABRICATED AND INSTALLED A 1 COMPLETES- 01/24/90 (4" PLATE BETWEEN THE PACKING FOLLOWER AND THE' VALVE. BODY SEE ATTACHED TEMPORARY MODIFICATION NUMBER 90-M-OZ. DRILLED NEW HOLE IN TO THE VALVES -
TEM. TO ADAPT THF VALVE HANDLE TO THE 1/4" SPACER. PLATE. INSTALLED VALVE-WORK DESCRIPTION
- PE C.
ISOLATION VALVE NEEDS REBUILT.iT LEAKS SY THE SEAT.
894056 AC-SFP AC-192
~;
WORK PERFORMED COE: Y CLASS: 3 ISOLATED AND DRAINED' SYSTEM. RiMOVEDVALVE FROM SYSTEM AND INSTALLED NEW SEAL RING.NEW 0-RING AND NEW' PACKING. PACKING FOLLCWER WAS CRACKED DURIN G REPACKING WHEN THE FOLLOWER WAS TORQUED. FABRICATED AND INSTALLED A 1/
TEMPORAR COMPLETE: 01/24/90 4" SPACER PLATE BETWEEN THE PACKING FDLLOWER'AIJD THE VALVE BODY Y MODIFICATION s 90-M-02. DRILLED NEW HOLE NTO THE VALVE STEM. TO ADAPT THE VALVE HANDLE TO THE'1/4" SPACER PLATE. INSTALLED VALVE BACK IN-SYSTE WORK' DESCRIPTION PE' C;
DISCHARGE ISOLATION VALVE NEEDS REBUILT.IT LEAKS BY THE SEAT.
094057 AC-SFP AC-199 s
WORK PERFORMED' COE: Y CLASS: 3 REMOVED SOME ROUND BAR FROM THE VERYHIGH ROD CAGE TO ENABLE FOR THE REM' OVAL OF THE VALVE 2 ISOLATED SYSTCM AND REMOVED. VALVE FOR REPAIRS.
I NST '-
ALLED NEW SEAL RING. NEW'O RING AND NEW PACKING.IINSTALLED VALVE BACK IN TORQUED PER PR SYSTEM USING NEW 8" FLEX GASKET AND NEW STUDS AND NUTS.
ALL WORK WAS PERFORMED USING ATTACHED PE-RR-VX-04285 PROCED COMPLETE: 01/24/90 C PROCEDURE.
RETURNED SYSTEM BACK TO NORMAL.*PER TONY'CHRISTENSEN (RADIOLOGY OPE URE.
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WORK DESCRIPTION C?
894059 AC-SFP GAUGE LINE OFF OF AC-58 DISCHARGE FLANGE NEEDS-REMOVED. CLEANED AND.
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AC-58
< ;p WORK PERFORMED COEE Y CLASS:~3 REMOVED G4UGE'LINE CLEANED THREADS AND REDOPED'WITH COE' LOCTITE P.S.T.
~'
. RETURNED FITTINGS.TO ORIGINAL.. CONFIGURATION -.AND RETURNED TO SERVICE.
ki-COMPLETE: 01/24/90 u
WORK DESCRIPTION..
894060 AC-SFP ISOLATION VALVE NEEDS REBUILT.IT LEAKS BY THE SEAT.
'C-AC-193
~
WORK PERFORMED-CQE: Y CLASS: 3 ISOLATED AND. DRAINED DOWN SYSTEM. REMOVED VALVE FROM SYSTEM AND IN-STALLED NEW SEAL RING. NEW 0-RING. NEW PACKING. INSTALLED VALVE BACK IN SYSTEM USING NEW 8 FLEX GASKET AND TORQUED PER PRC PROCEDURE. ALL WO COMPLETE: 01/22/90 RK WAS PERFORMED USING ATTACHED PE-RR-VX-04285 MAINTENANCE PROCEDURE.
RETURNED SYSTEM BACK TO NORMAL, WORK DESCRIPTION.
894061 AC-SFP ISOLATION VALVE NEEDS REBUILT.IT' LEAKS BY THE SEAT.
-C AC-188
' WORK PERFORMED-
~
'L CQE: Y CLASS: 3 REButLT AC-188 AS PER-PE-RR-VX-04285 MAINTENANCE PROCEDURE.
~
ISOLATED AND DRAINED.DOWN. SYSTEM. REMOVED' VALVE-FROM SYSTEM AND INSTALL ED NEW SEAL.' RING. NEW 0-RING.' NEW PACKING. INSTALLED VALVE BACK IN'SYSTE:
COMPLETE: 01/22/90 M USING NEW 8" FLEX GASKET AND TOROUED PER PRC PROCEDURE. ALL WORK-WAS P ERFORMEG USING ATTACHED PE-RR-VX-04285 PROCEDURE.CG.1-22-90 RETURNED-SYSTEM BACK TO NORMAL; WORK DESCRIPTIO:1 '
894453 AC-RW THE INTERNALS OF RW-125 ARE BADLY ERODED. REPLACE RW-125 WITH A NEW VALV
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RW-125 l
l WORK PERFORMED COE: Y CLASS: 3 ACQUIRED NECESSARV TOOLS &1 RIGGING. REMOVED BOLTING & EXISTING VALVE' BOD Y CLEANED & INSPECTED ALL GASKET SURFACESr MADE'2:NEW GASKETS. CLEANED S TUDS'& NUTS AND HAD Q.C.~ INSPECT THEM AS PER THE PROCEDURE. LUBRICATED.
4 COMPLETE: 01/25/90 BOLTING WITH APPROVED LUBRICANT.. INSTALLED'NEW VALVE'AND GRAFOIL GASKETS
. INSTALLED BOLTING & TORQUED AS PER THE PROCEDURE: PERFORMED VISUAL-..
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LEAK' CHECK AND FOUND NO LEAKAGE.
CLEANED UP WORK AREA AND RETURNED.TOO.
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DATE.02/07/90:
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. CHAMPS REPORT M07 l-COMPLETED CQE MWO'S'- E NUA1,Y ';(WFFRMMH1)'
,TIMEi : 11. :5 6 -
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'LEADi -PRiNTI
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DISC' SSTATUS:
' EQUIP ID-
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~ WORK DESCRIPTION.
4 804523 AC-RW RW-115 HAS BEEN REPORTED LEAKING BY.. REPLACE RW-715'WITH A'NEW VALVE.
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R':t-115 WORK PERFORMED CQE: Y CLASS: 3 LOAD TEST PERFORMED ON't-23-90 D GASKILL QCs90-390. REMOVED CHECK VALV E FROM SYSTEM AND FOUND ONE FLAPPER ON CHECK VALVE MISSING AND PULLED RO-.
W WATER PUMP (ON-A DIFFERENT Mwo) FOUND MISSING FLAPPER INSIDE PUf?P. REP-COMPLETE: 01/25/90 ALCED OLD CHECM VALVE WITH NEW ONE INSTALL A WITH NEW GASKETS.
WORK DESCRIPTION NEW VALVE.-
894524 AC-RW RW-117 HAS BEEN REPORTED LEAKING BY. REPLACE RW-117 WITH A..
PE' 3.
fr.!- 1 17 WORK PERFCRMED COE:
Y-CLASS: 3 TAGGED AMD REMOVED CHECK VALVE. CLEANED FLANGE SURFACE.
INSTALLED.PER MWO SIGN OJ TORQUED AND CHECKED FOR LEAKS TEMPORARY REINSULATED RW-117-WILL REINSULATED WHEN NEW EWO IS ISSUED COMPLETE: 01/29/90 LATER. T.S 01-26-90 T-1.220 TO 450 LBS. 11-9-90 CALIDATE 1-25-90 T-3 730 LBS, 2-6-90 CALIDATE WORK DESCRIPTION 894525 AC-RW RW-121 HAS BEEN REPORTED LEAKING BY. REPLACE RW-121 WITH A NEW VALVE.
PE 3
RW-121 WORK PERFORMED COE: Y CLASS: 3 RW 121 REMOVED CLEANED AND INSTALLED NEW CHECK VALVE CLEANED TAGS INSPEC TED FOR LEAKS. TEMPORAPY INSULATED RW-121-WILL REINSULATE WHEN NEW MWO I' S ISSUED LATER. T.'S.~1-26-90 COMPLETE: 01/29/90 1-25-90'T1 220 TO 450LBS' 11-9a90 CAL DATE 7 TORQUE 1-25-90 T-3 73OLB 2 90 CAL DATE 5 WRENCH'S WD-"9_'h_Thh"he*-h-'""
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' COMPLETED CQE MWO!S M J?NUJiRV;... {( WFFRMMH 1 ).-
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. CHAMPS' REPORT MO7.'-
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_N' WORK DESCRIPTION-Y I
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835146:
AC-SFP AC-319-APPEARS TO BE PLUGGED.NEED-iTO' UNPLUG.POSSIBLV REPLACE DIAPHRAM.
-EPEf Cj
~.1 THIS IS ' A 2. INCH DI APHRAM VALVE.WE-' MIGHT BE ABLE TO FREE BLOCKAGE BY r.
i AC-319 PRESSURIZINGELINE.WITH AIR. CONNECTING AT.DW-207.THIS..IS.A.3/4 INCH VALVE ~~
O SEE-JIM ALLEN.
WORK PERFORMED
~
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CQE: V CLASS: 3 TEMP AIR'AND WATER' LINES. ASSEMBLED AND' INSTALLED DOWN' STREAM OFI DW-204 5
- m-ca S'PER DRAWING 11-10-89 RC OPSETO PE'RFORM FLUSHING OF;LINE-PER
- PROCEDURE.
-'E JNSTALLED RELIEF-VALVE-SETJTO--150a AS'PER DRAWING.12-8-89 RC REMOVE' AIR COMPLETE: 01/12/90 PRESSURE REGULATOR. INSTALLED'SWAGLOCK FILLING UP' STREAM OF' BALL VALVE O N.TEMPOARY SLUICE PIPING.(AIR SIDE) FOR ATTACHMENT'TO NITROGEN BOTTLE RC
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1-2-90 SLUICE COEPLETED BY'OPERATIO NS.cTEMPOARY< SLUICE PIPING *PROCEDO:
.,5 7 '
.: n WORK DESCRIPTION 895851 EE-5 THE RED INDICATING LIGHT'FOR'FW-348 ON' UNIT.801 DOES NOT WORKhNEED TO TRf'
- EM-
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OUBLESHOOT TO DETERMINE PROBLEM. CHECK THE BULB ANDl SOCKET.MAKE REPAIRS.A C'
ECC-4A2 S REQUIRED.
J.BRAUN/JCV
'a WORKTPERFORMEDi CQE V CLASS: N FOUND RED INDICATION LIGHT BULB BURNT OUT. REPLACED BULB. VERIFIED PROPE
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R' OPERATION.
m COMPLETE: 01/18/90 a
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' [DAT.n.S2/07/90.:pPAGEM 7 1
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-COOO33 AC-SFPl
~ VENDOR-TO CREATE' FREEZE SEAL ON'8S S.S., PIPE. SUCTION LINE'TO AC-5A&5B L
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- THIS WILL' ALLOW REBUILDING OF.ISOLATIONsVALVES.
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CQE: Y CLASS: 3
'HAD-OPERATIONS'CLOSE FLOOD ~ DOORS TO THE SI ROOMS.;HAD G.M' INSTALL FLOOD
' BARRIER.FOR. ROOM 5.' HAD VENDOR !NSTALL FREEZE SEAL EQUIPMENT AND ESTABLI SH A FREEZE. SEAL ON THE'8"ESTAINLESS: STEEL: PIPE TO ENABLE IN THE-REMOVAL:
7f CCMPLETE: 01/25/90
- OF THE ISOLATION VALVES - TO AC-5A AC-58.-ALL-WORK ~WAS. PERFORMED AS'PER_A
'..w TTACHED MD-RR-MX-1002 PROCEDURE. REMOVED. FLOOD BARRIER AND SCAFFOLD OUT-~
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- WORK - DESCRIPTION -.
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-900092 AI-RPS REPAIR' TRIP INDICATING LIGHT.ON RPS CHANNEL.A ' TRIP' UNIT NO.-8.' PRESS-S
~ ICE 33"
"~;P URIZEa PRESSURE-CHANNEL.
'~
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. WORK PERFORMED s
CQE: Y CLASS: S REPAIRED, SPRING MECHANISM FOR RESET. BV RE-SEATING SPRING IN ITS RETAINER
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. SPRING HAD' SLIPPED OFF., PERFORMED CP-RPS-2 FOR--.THIS. CHANNEL'.
COMPLETE: 01/11/90~
WORK' DESCRIPTION 900235 DG
' PERFORM TROUBLESHOOTING ON REGULATOR TO FURTHER INVESTIGATE THE OVERVOLT
- EM-
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AGE PROBLEM.: SYSTEM ENGINEER TO PROVIDE DWI. LPH (6681) FOR R.
RONNING(6.
A!-1338-28 887) e 1527 01/16/90 WORK PERFORMED.
CQE:
Y-CLASS: N SEE D.W.I.
COMPLETE: 01/18/90
.g WORK DESCRIPTION 900334
'AC-RW NEED TO PULL AC-100'FROM. PIT TO
' LOCATE FLAPPER MISSING FCOM RW-115; MM.
C DISHARGE CHECK VALVE.
l AC-100 I
WORK. PERFORMED-l COE: Y CLASS: 3 PUMP WAS REMOVED FROM PUMP'WELL TO LOCATE CHECK VALVE FLAPPER.-FLAPPER
.WAS FOUND ON TOP OF SECOND' STAGE, REMOVEDM FLAPPER.' PUMP WAS'VISUALLv:IN i
i SPECTED. NO DAMAGE WAS FOUND;' PUMP SET BACK IN PIT. LEFT LIFT AT
.017".
COMPLETE: 01/26/90 FG ' BUCK '1-25 AS PER MM-RR-RW-OOO1
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'DATE:
- OPPD FORT CALHOUN, PLANT -
CO%PLETED COE'MWO'S - JANUARY ?(WFFRMMH1);
. TIME:: 16:53-w CHAMPS REPORT-MO71
' LEA D ":
PRINTi'?-
??S ^ b. i DISCc JSTATUS' _ '
HWO
- SYSTEM EQUIP ID
= - - _ - - -
WORK DESCRIPTION N2 BOTTLE
- PE C-
-THE LATERIALS IN AC-7 HAVE BECOME PLUGGED.WE NEED TO CONNECT TO THE SYSTEM AND FLUFF THE RESIN BED. INSTALL'N2 BOTTLE UPSTREAM OF 900357-AC-SFP NG-233.THIS VALVE IS LOCATED IN RM. 5.
MANWAY REMOVAL MAY BE NEEDED.
AC-7
~
WORK PERFORMED UP LINE TO NG.233 TO BOTTLE N.G.
AC 01-26-90 DISCONNECTED LINE FROM HOOK NG 233 TO BOTTLE REPLACED CAP ON NG.233 CLOSED DOOR TO ROOM 5. AC 01 '
COE:-Y CLASS: 3 TO NG233 TO SPARG LINE. WHEN SPARGI 90 CONNECTED NG LINE FROM NG BOTTLE WAS COMPLETE DISCONNECTED LINE FROM BOTTLE TO NG233.'FOLLOWED DETAIL COMPLETE: 01/29/90 NG ED WORK INSTRUCTIONS NO PROCEDURE WAS USED-JC 1-27 WORK DESCRIPTION IC C
SA-193 DIAPHRAM APPEARS TO BE RUPTURED.
907506 DG DG-2 WORK PERFORMED REMOVED PIPING AND REGULATOR FOR IEC REINSTALLED SAME PIPING AND NEW REGULATOR. LEAK CHECKED:ALL FITTING CONNECTIONS OK. TJS 1-19-90 INSTALLE COE: Y CLASS: N 180 PSI D CALIBRATED TEST GAUGE *00117 AND SPT AIR REGULATOR PRESSURE AT REMOVED TEST GAUGE AND INSTALLED PROCESS GAUGE. VERIFIED SYSTEM COMPLETE: 01/19/90 G.
TO BE LEAK FREE USING SNOOP.
WORK OESCRIPTION~
189-2 EM C
NEED LUG REPLACED ON WIRE FI-102-2-2 TO FI-102-2 (CB-1.2.3.
907507 RC LUG BROKEN F1-102-2 WORK PERFORMED.
REPLACED LUG-PERFORMED-ST-ACCOUSTIC-1 F.1-SPECTRUM ANALYZER SECTIONS.
PS 1-19-90 (MONTHLY ST) NOTE: LUG WAS BROKEN DURING THRESHOLD SECTIONS O COE V CLASS: S F ST-ACCOUSTIC-1 WHERE LUG HAD NO EFFECT ON T. COMPLETETION OF SPECTRUM ANALYSIS SECTIONS COMPLETED UPON REPAIR OF LUG.
COMPLETE: 01/1G/90 l}
AC-10B FAILED FLOW REQUIREMENTS OF ST-RW-2-NEED TO ADJUST PUMP LIFT.
MM CJ WORK DESCRIPTION 907511 AC-RW AC-108 WORK PERFORMED COE: Y CLASS: 3 LIFT AS FOUND 138" TOATL LIFT'.240" AS LEFT.018" COMPLETE: 01/26/90 ADJUSTED LIFT AS PER PROCEDURE MM RR RW 0001 m