ML19325F382
| ML19325F382 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 10/31/1989 |
| From: | Morris K, Stice D OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-89-1079, NUDOCS 8911200280 | |
| Download: ML19325F382 (22) | |
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l' ,Y ,- 1 l l e I i ! Omaha Public Power District i ! 1623 Horney Omaha, Nebraska 68102 2247 j 402/536 4000 November 14, 1989 LIC 89-1079 i U. S. Nuclear Regulat-ory Commission Attn: Document Control Desk Mail Station PI-137 , Washington, DC 20555 i
Reference:
Docket No. 50 285
- Gentlemen: l October Monthly Operating Report SUB.1ECT: ,
I Pursuant to Technical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1), l please find enclosed one copy of the October 1989 Monthly Operating Repart for ; the fort Calhou.1 Station Unit No.1. i If you should haie any quhtions, please contact us. l Sincerely, , ^ r
' J. orris '
Division Manager i Nuclear Operations j 4 r KJM/pje ; i c: LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator ; P. H. Harrell, NRC Senior Resident Inspector R. M. Caruso - Combustion Engineering ' R. J. Simon - Westinghouse : Office of Management & Program Analysis (2) Nucleaa Safety Analysis Center INPO Records Center ! American Nuclear Insurers ;
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+- u-AVERAGE DAILY UNIT POWER LEVEL- 1 t.
o L DOCKET NO. 50-285 UNIT Fort Calhoun Station : DATE November 13, 1989 ' COMPLETED BY D. L. Stice TELEPHONE (402)636-2474 _ MONTH October ikd DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (HWe-Net) 1 282 17 461 2 306 18 462 3 307 19 461 4 308 20 461 5 314 ,,_ 21 462 6 432 . . _ _ 22 461 7 458 23 461 ~ 8 463 24 460 9 460 25 460 30 457 26 458 , 11 457 _ 27 459 12 457 28 _ 461 13 __ 459 29 462 14 460 30 463 15 459 31 464 26 458 INSTRUCTIONS , On this form, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. l
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,, OPERATING DATA REPORT 00CKET NO. 50-285 UNIT fort Calhoun Station-DATE Evember 13, 1989 COMPLETED BY 0. L. Stice TELEPHONE (402)636-2474 OPERATING STATUS
- 1. Unit Names Fort Calhoun Station ~ Notes
- 2. Reporting Period October 1989 !
- 3. Licensed Thermal Power (MWt): 1500 l
-4. Nameplate Rating (Gross MWe): 502
- 5. Design Electrical Rating (het MWe): 478
- 6. MaximumDependableCapacity]GrossMWe): 502 1
- 7. Maximum Dependable Capacity tNet MWe): 478 !
- 8. If changes occur in Capacity Ratings (Item Numbers 3 through 7) Since Last Report, j Give Reasons: i N/A !
- 9. Power Level to Which Restricted, If Any (Net MWe): N/A !
- 10. Reasons for Restrictions, If Any: N/A l This Month Yr-to-Date Cumulative !
i
- 11. Hours in Reporting Period 745.0 6.552.0 140.402.0 '
- 12. Number of Hours Reactor was Critical 745.0 5.608.5 10E.958.3 !
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 . 309.5 !
- 14. Hours Generator On-Line '
745.0 r ,g 107,797,4 i
- 15. Unit Reserve Stutdown Hours O.0 0.0 0.0 f.
l 16. Gross Thermal Energy Generated (HWH) 1,051,493.3 7,428,155.3 140,317,149.2 :
- 17. Gross Electrical Energy Generated (MWH) 340,160.0 2,396,496.0 46,140,624.2
- 18. Net Electrical Energy Generated (MWH) 323,325.3 2,276,787.2 44,048,292.0 :
l
- 19. Unit Service factor 10Q 82.1 76.8 L 20. Unit Availability Facto' 100.0 82.1 76.8 r
- 21. UnitCapacityFactor(UsingMDCNet) 90 T 72.7 [' 67.8 l
- 22. Unit Capacity Factor (Using DER Net) 90.8 72.7 66.2 :
- 23. Unit Forced Outage Rate 0.0 5.0 3.0 h
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refuelino Outage estimated to begin on February 17, 1990, with a planned - duration of 86 - 118 days.
- 25. TT 5 Tut Down at End of Report Period, Estimated Date of Startup: N/A ,_
- 26. Units In Test Status (Prior to Commercial Operation): Forcast Achieved ,
INITIAL CalTICALITY INITIAL ELECTRICITY N/A ' COMMERCIAL OPERt. TION l 1
- p. i P,efueling Infcreation !
,, fort Calhoun - Unit No. 1 ] ,,s !
Report for the mMth ending October 1989 i
- 1. Scheduled date for next refueling shutdown. February 17. 1990 l
- 2. Scheduled date for restart following refueling. May 14,1990 __
- 3. Will refueling or resumption of operation thereafter i require a tec1nical specification change or othar !
license amendment? Yes I t
- a. If answer is yes, what, in general, will these be?
- Incorporate specific requirements resulting from reload safety analysis i
- b. If answer is no, has the reload fuel design and core configuration been reviewed by l your 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 i
- 4. Scheduleddate(s)forsubmittingproposedlicensing action and support information. January 11, 1990 i
- b. 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 l
- 6. The number of fuel assemblies: a in the core 133 assemblies b in the spent fuel pool 437 t c spent fuel pool "
storage capacity 729 i d)plannedspentfuelpool May be increased , storage capacity via fuel o'n i consolidat'on i
- 7. The )rojected date of the last refueling that can be disclarged to the spent fuel pool assuming the present r licensed capacity. 1994* l
- Capability of full core offload of 133 assemblies lost.
Prepared by lhldMR e Date November 10, 1989
p DOCKET 100. 50-275 o INIIT IIME Fort Calhoun Station DATE November 13, 1989 UNIT SHUTDOWIIS AlIO POWER REDUCTI0lIS COPFLETED BY D. L. Stice + TELEPHOIIE (402) 635-2474 REPORT M0 LITH October, 1989 5 E 52 gj Ucenwe 5I
~
E **"****"*** No. Date g 3 5 j
- Event ; g Action to e 2- 3 j; Repwt
- Ao ,3 PrW Recunence o
There were no unit shutdowns or power reductions during the month of October, 1989. 1 2 3 4 F-Forced Reasonc Method Extedt G - Inservctions S-Scheduled A-Egwornant FaEure (Explaint Heenwel
~
for Properation of Data B-Maintenance or Test 2h Scram Entry Sheets for Ucensee C-Refuelne 3-Automatic Screm Event Report 5.ERI FBo 94AEG-0184 D-Regehtory Restriction d-Other Explaint E-Operator Training & Ucense Examination 5 F-Admhistative TMdtdt 1 - Some Source G-Operational Error N (Explain)
T OMAHA PUBLIC POWER OfSTRICT Fort Calhoun Station Unit No. 1 . October 1989 Monthly Operations Report ! I. OPERATIONS
SUMMARY
f Fort Calhoun Station attained 69% power on October 1,1989, after start up l from an unscheduled outage caused by faulty reactor coolant pump thrust bearing temperature indication. Power was maintained under 70% until the cause of a delta temperature power indication anomaly was determined to be thermal stratification of flow in the Reactor Coolant System (RCS) hot ! leg. On October 6 and 7, power was raised to 99% and held there due to fluctuating delta temperature power indication on two of the Reactor l Protection System (RPS) channels. Based on lessons learned from the ' September 13 anomoly, delta T power indications wtre not allowed to exceed 101%. It was determined that the fluctuation for the two RPS channels is caused by faster responding Conax Resistance Temperature Detectors (RTDs) measuring normal hot leg temperature variations. The average power reading is now used. Power was raised to a nominal 100% on October 27, 1989. - A possible non conservative error in the method used for generating the ' Cycle 12 Thermal Margin / Low Pressure (TM/LP) setpoints was discovered. This prompted administrative 1y limiting the total integrated radial peaking factor (FnT) to 1.75, rather than the Technical Specification limit of 1.80. SuTficient margin was gained to compensate for the error, i The Raw Water / Component Cooling Water heat exchanger flow restriction problem was reduced by cleaning the sand out of one heat exchanger. i Attempts to clean other heat exchangers has been unsuccessful due to the , inability to isolate them.- The progress made was sufficient to remove the ! administrative limitations placed on the service condition of the heat , exchangers. , Modification work continues on the control room Heating, Ventilating and Air Conditioning (HVAC) system, instrument air dryer, and Security system. L Construction continues on the Chemistry and Radiation Protection and Rad L Waste Buildings. Site preparation has begun for the Administration Building. The following NRC inspections took place in October: IR 89-38 Resident Inspectors' Monthly inspection IR 89-41 Radiation Protection Program l The following LER's were submitted: Date Submitted 89 012-01 feedwater Valve HCV 1386 Inoperability October 13, 1989 89 019 Manual Trip due to High Temperature of RCP October 24, 1989 No safety valve or PORV challenges or failures occurred.
( u p, w , L 3 [ j I Monthly Operations Report- ; Page Two l A. PERFORMANCE CHARACTERISTICS , L, , L None ; e , b L B. CHANGES IN OPERATING METHODS None ; i i C. RESULTS OF SVRVEILLANCE TESTS AND INSPECTIONS i L None
?
D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL , System Acceptance Committee Packages for October 1989: ! Procedure Description SP FP-5 Fire Pritection System Valve Cycling and Flushing This test did not involve an unreviewed safety question as defined by 10 CFR 50.59 because this ' test is in conformance with the testing o requirements specified by the plant Technical !'
- l. Specifications related to fire protection. The probability of an accident or malfunction of a different type than any previously evaluated in ,
I the Updated Safety Analysis Report (USAR) has not , been created. , i The results of the test were satisfactory. i E. RESVLTS OF LEAK RATE TESTS - 5 l The reactor coolant system leak rate test, ST RLT-3 F.1, indicates i for the month of October a continuation of the elevated leak rates seen throughout Cycle 12. The actual leak rate tests showed varying I results due to plant power changes throughout the month and due to I constant change in the condition of the operating and standby ! I charging pumps. l' i L l
l l l \
- s. '
i Monthly Operations Report ! j Page Three l l i l s :
> On October 1, 1989, a minimum leak rate was recorded at 59% power and l t increasing. This test registered a total leak rate of 0.225 gpm and ! - a calculated value of -0.187 gpm for unknown leakage. It is )
suspected that the power increase in progress during this test ' resulted in inaccuracies that underestimated the total leak rate. ! This, in turn, resulted in a negative unknown leak rate. ! j The maximum leak rate for the month was found on October 14, 1989. ) At this time, the total leak rate was 0.725 gam and the unknown leak rate was 0.335 gpm. Whenever the unknown lea ( rate exceeds 0.3 gpm, j Chemistry performs a primary-to-secondary leak rate test. Results of j this test showed no primary to secondary leakage. , j The elevated total and unknown leak rates found during the middle of 3 October are indicative of higher than normal charging pump leakages. Subsequent maintenance on the charging pumps has reduced the RCS leak : rate to values consistent with Cycle 12. F. CHANGES IN PLANT OPERATING STAFF j None l G. TMINING ; During the month of October, NRC exams were completed for the three
- Senior Reactor Operator (SRO) candidates. The NRC notified OPPD that all three examinees passed. Simulator testing continues and formal acceptance testing should begin in November. A tentative date for the INPO reaccreditation team visit for the four (4) operator :
programs and the Shift Technical Advisor (STA) program has been set for August of 1990. The Significant Event Report (SER) for these programs will be submitted in May 1990. Two Shift Technical *dvisor candidates successfully completed all requirements and are fully ' l qualified to perform STA duties. Technical Staff, System Engineers, i and selected Quality Assurance training continued throughout the . j month. Additiorally, Maintenance Planners training was conducted. Maintenance Training continued during the month with the first class , I of Kepner Tregoe Advanced Trouble Shooting methodology being taught to I&C technicians. GET training continued during October to meet the goal of training personnel before the upcoming outage.
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Monthly Operations Report s Ptge four r
' H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY !'
COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 p Amendment No. Descriotion NONE l
- 11. MAINTENANCE (Significant Safety Related) !
See attached printout. l G. R. Peterson Manager Fort Calhoun Station l I e I f r i e I h i h l t
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CHAMPS REPORT'1808~ =2.~'-.-. v CLOSED CQE muO* 5 COMPLTD D' MIN (e OCT. f- (uFFRem41) ' , TIME: 10:20 - -
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CCE: Y CLASS: 3 10-17-89 REMOVED HAND JACM AND BONNETT AS PER mP-OP-FL-1-10-19-89. REmAC. _ _ HINED HAND JACK SHAFT AS PER ATTACHED DRAW 1NG 10-19-89 19-19-89 RE-INSTA ^ - COMPLETE 10/19/89 LLED HAND JACM AND BONNET A"> R WP-OP-F1-1 WORK DESCRIPTION 890561 RC PIA-3195 IN UPPER ELECTRICAL PENETRATION ROOM IS IN ALARM AND w1LL teOT C LEAR. RC-3C DEF. TAG #881961 - WORK PERFORMED - COE: Y CLASS: 1 NO PROOLENS FOUkD ON PIA-3195.NO ALARMS FOUND ON PIA-3195 LOOP. NO CP RE. SJIRED AS PER PLANhER INSTRUCTION IF LOOP APPEARED TO BE OPERATING NORMA COMPLETE 10/09/c? L READING 12. WORK DESCRIPTION . _ ' 8918G9 EE INCREASE THE AesOUNT OF NO-OX-ID GREASE ON BATTERY #1 AND a2 INTERCELL CO NMECTORS TO REDUCE CORROSION RATf, EE-8A ., WORK PERFORNED . CQE: Y CLASS: SR CLEANED CORROSION FROtt INhER CELL CONNECTORS ON BATTERIES at AND 2 AND RECOATED WITH NO-OX-ID GREASE. COMPLETE 10/04/89
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DATE:'11/01/09' iPAGE. 1 '
-CHAMPS PEPORT mO8 CLOSE-) COE uwO'S COmPLTD DURING OCT, (WFFRMMH1 ) '. i TIMEt-11:20f -
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C93857 AC-CCW ISOLATE. DRAIN. DISASSEMBLE. CLEAN & INSPECT THE RAW WATER SIDE OF CCW: . i HEAT EXCHANGER. SUPPORT ECT EXAMINATIONS. IF ACCOWPLI$HED.' & RE-ASSENSLE. EC-1A THE HEAT EXCHANGER ON COMPLETION OF INSPECTIONS. WCRK PERFORWED ~ COE: V CLASS: 3 REMOVED BLIND FLANGE ON VALVE sRWO213 FOR DRAINING OF AC-1A 10-3-89. REP LACED BLIND FLANGE ON VALVE RW 213 JC 1-=12r89. HEAT EXCHANGER COULD NOT COwPLETE 10/19/89 BE SUCESSFULLY ISOLATED FROM THE RW SYSTEM THIS PROCEDURE WAS NOT COppt. - ETED AND THE HEAT EXCNANGER WAS NEVER OPENED UP USING THE mwO RON JOHANS EN. WORK OESCRIPTION C94410 AC-RW SECURE SWAGELOK FITTINGS / TUBING LEAKAGE TO PRESSURE INDICATOR PI-2857. V PI-2857 WORK PERFORMED ' CQE: V CLASS: S NO WORM PERFORwED. NO LEAMS NOTED ATTHIS TIME NO EVIDENCE OF LEARS NOTED y EVER PI-2857 CAL DUE 7-24-90. PI-2857 CURRENTLY INDICATOR 53 PSI. COMPLETE 10/18/89 WORK OESCRIPTION. . _ . 894415 AC-RW SECURE LEAKAGE ON SWAGELOK FITTINGS / TUBING FOR PRESSURE INDICATOR PI-285
-4 AC-RW WORK PERFORMED COE: Y CLASS: S REPLACED S'CTION OF TUBING FROM TEE FITTING TO PI-2854 REPALCED TEE FITT ING.
COMPLETE 10/09/89 s L - L_A
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E94448 SI-HO. I&C TO~ RESET / REPAIR HCV-2937'BOOSTERIF NEEDED FOR THE-MONTH SEPTEMBER , +
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"t. .T COMPLETE 10/02/89 189 1610. RESET 2987'800 STER TO 350 PSIG.-090689. FF. RESET 2987 800"-
AS FOUND 321 AS LEFT- 351 PS '090989 1100 RESET 2987 BOOSTER TO 350 F#i ' _- - % -fff 91489 FF RESET 2997 BOOSTER TG 350 PSIG 092589 MN RESET- 2987 500STE. . y -
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C94817 AI CL'IAR GROT.,ED FOUND ON AI-208B QSPOS. CHASSIS NUMBER TWO.(2).PER INVESTIG + ATION OF MwOsB94782. .. - . . .
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AI-2008 CRIGINAL'pAOBLEM WAS THOUGHT TO BE-125 VOLT D.C. BATTERY CHAPGER CAUSING' - THE PROBLEM. SEPT.28.19889-R.PERRV- /JO.
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WORK PERFORMED ~ COE: Y CLASSt SR AS FOUND (LIA-381-187.) LIA-382-188)(L381-187) AS LEFT. CALIBRATED AS. PER CP. AS FOUND ALARM LOW SETPOINT 44.36MA=186 AND RESET: AT 44.6 MA= 187. VALVES WEFl WELL WITHIN TOLERANCE. - COMPLETE: 10/17/89 WORK DESCRIPTION . . . 892203 PC-ERF COMPUTER ALARMS COMING IN ON RODS 15 AND 16. COULD BE CAUSED BY BAD IC C. SIGNAL FROM AI-61. ERF _. WORK PERFORMED . . . . CQE: V CLASS: 1E ROD #16 REPAIRED ON MO 893006 ROD'15 REPLACED WORK ISOLATOR SLOT s4 - ORIGINAL FROM SLOT WAS SNaO3078E. TOOK AS FOUNDS AS LEFTS AND DOCUMENTED' ON MP-EE-44-1. SN OF REPLACEMENT WASO3082E DOCUMENTED SN'S ON-MP-EE-44-1 COMPLETE: 10/04/89 PERFORMED Call 6 RATION OF RODS CHANNELS AS- 13.14.15. AND'16 ON MP-EE-44-1 -
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WORK DESCRIPTION .. . . 893679 PC-OSP FIVE CET'S (CORE EXIT TEMPERATURE $) ARE READING LOW AND OUT.0F SPEC ON IC- C^.
"B" CHANNEL. CRAFTSMAN TO TROUBLESHOOT AND REPAIR AS REQUIRED.
AI-208B WORK PERFORMED _ .. COE: Y CLASS: 1 CHECKED COLD REFERENCE JUNCTION CAMP ON 701-1 CARD BECAUSE READINGS ARE. APP 40 DEGREES LOW..HOWEVLR. TO-1 CARDIS OK. REMOVED CARD CONNECTOR AND FOUND WIRE TO PIN s4 ON J2* BROKEN OFF. REPAIRED-(WIRE TO PIN) CONNECTION COMPLETF: 10/02/89 RESTORED "B* OCPDS'.TO SERVICE ?ND NOTICED THE SUSPECT CET'S READING NDRM-AL. THIS CONNECTOR IS J2 OF-TH'. 1748-2 CARD. NO-OC SINCE CP WAS NOT PERFORMED ', ;... WORK DESCRIP/ ION . 893756 FO-DG RECENT CHEMICAL ANALYSIS INDICATES THAT THE DIESEL FUEL NEEDS TREATMENT, PE- cC FOR MICROBLIAL' CONTAMINATION. ADDRCFEMICALS PER DIRECTIONS FROM SYSTEM FO-1 ENGINEER. PERFORM CMEMICAL ADDITION ON FO-1 FO-2-1 FO-2-2 FO-2C AND FO-20. ' WORK PERFORMED . ACCOMPANIED SYSTEM ENGR AND CHEMIST TO FILL PART IN FO-1, REMOVED CAP Of* COE: Y CLASS: N FILL PORT REINSTALLED CAP AFTER ADDITION OF CHEMICALSJ REPEATED ABOVE AT ,
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- COMPLETED CQE MWO*S~.- OCTOBEJ . (WFFRtMM1) ' - TIME : ' 1,: 22 ' ./: c c F-r~-4 . ; -
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C64619 AI. 'DURING PERFORMANCE OF ST-RPS-1-F.3. METER READ >200% AT .THE CAL POSITION ~'
- AND SHOULD HAVE READ 200L CALIBRATE OR REPAIR THE METER AS REQUIREI' VERI-- , T AI-318 -IFV LINEARITV -
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WORT PERFORMED . CQE: Y CLASS: S PERFORMED CP-RPS/SUB CH.ANNEL AND FOUND MEIER TO BE OK. HOWEVER THE INPUT. ' TO METER WAS READING 10.'167DCV (DESIRED IS 10.000). PERFORMED APPLICABLE R. SECTION OF ST-RPS-13 F.1 TO ADJUST THIS INPUT.. ,. COMPLETE: 10/24/89 WORK DESCRIPTION. . , 894823 Al REPLACE TEC ISOLATOR FOR RR 31 WHICH INDICATING FALSELV. ; IC- 3' AI-61 ~ 7 ' ~ 7" WORK PERFORMED CQE: Y C'.A S S : S REPLACED TEC ISOLATOR SLOT 8 (CHS 29,30.31 AND 32). CHs 31-' OUTPUT 1/10 CF EXPECTED FOR INPUTJ ORIGINAs. 980-3E ISOLATOR'SNs WAS 03076E. NEW _ l' REPLACEMENT IS 03079E. PERFORMED MP-EE-44-1 DVM USED WAS OPPDs 14023 % COMPLETE: 10/26/89 DUE DATE 3-15-90. DID 5 POINT AS LEFT/AS FOUND CALIBRATION CHECK ON; SLOT. _.
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8 ISCLATOR (AI-61). - : WONK DESCRIPTION - ;
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894844 AC-RW PERFORM A HVDROSTATIO TEST OF ONE (1) VALVE RECIEVED ON PURCHASE ORDER PE C - sS 048470 TO SATISFY THE COMMEPCIAL Ge4ADE DEDICATION REQUIREMENT OF THE ^ MATERIAL EVALUATION REPORT (MER) FC-89-09. THIS VALVE WAS PREVIOUSLY TO HANCOCK 1- GLOBE dE TESTED ON MWO 894670 BUT TESTING WAS NOT ACCOMPLISHED. WORK PERFCRMED CQE: Y CLASS: N PERFORMED HVOROSTATIC TEST ON A HANCOCK MODEL 350W GATE VALVE TO 225PSIG FOR 20 SECONDS.TO MEET.THE REQUIREMENTS OF MER aFC-89-09 QC WITNESSED T. HE TEST AND FOUND NC LEAKS RETURNED VALVE TO WAREHOUSE. COMPLETE: 10/11/89 WORK DESCRIPTION . r 894853 RM RE-ADJUST FLOW TO PROPER VALUES PER CP AT 6 TO 11.5 SCFM. -IC C' RJ-061 . -- WORK PERFORMED COE: Y CLASS: S A3 JUSTED VALVE TO REDUCE FLOW WITHIN LIMITS SPECIFIED IN CP.-00'. , COMPLETE: 10/05/89
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TIME:-10:22 2 *5 IJ . CHAMPS BLEPORT MO7 _y c' COMPLETED CQE'MwO"S - OCTOBE2~ ((MFFRMMH1)~ _
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-N 894870 AC-CCW PUMP BEARINGS ARE GETTING NOISV,NEEDTO REPLACE INBOARD AND OUT 80ARD - MM ': C '
BEARINGS. - ~ AC-3C WORK PERFORMED . _ REPLACED OUT BOARD AND IN BOARD BEARINGS AND SEALS (OIL) COE: Y CLASS: 3 - -
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COMPLETE: 10/24/89 , t' W WORK DESCRIPTION 094874 AI COMPLETE QSPOS TESTING OF TERMINATION ASSIGNMENT PER ATTACHED COPIES . IC' C-OF TEST CHANNEL NUM8ERS. JJO AI-208A - J. -
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work PERFORMED . . CQE: Y CtASS: S PERFORMED SELF TEST Ot. QSPDS. RECORDED DATA AND FORWARDED TO DAN BYF.. ' THIS TEST DOES NOT EFFECT OPERABILITV STATUS OF COMPUTER _ _ COMPLETE: 10/10/89 , WORK DESCRIPTION .
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894875 Al COMPLETE QSPDS TESTING OF TERMINATION ASSIGNMENT PER ATTACHED COPIES- ~ -IC . -C: , OF TEST CHANNEL NUMBERS. JJO , AI-208A WORK PERFORMED _ . COE: Y CLASS: S PERFORMED SELF TEST ON QSPDS. RECORDED DATA AND FORWAROFO TO DAN BVE THIS TEST DOES NOT EFFECT OPERABILITY STATUS OF COMPUTER; _
~~~ 1 COMPLETE: 10/10/89 WORK DESCRIPTION , .
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894876 Al CORRECT PROBLEM ASSOCIATED WITH CET'S NOT SENDING CORRECT INFORMATION TO IC C: ERF COMPUTER. JJO - AI-208A
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COE: Y CLASS: S BROUGHT IN FACTORY REP TO LOOK AT PROBLEM FOUND COMMUNICATION MISMATCH B ' ' ETWEEN QSPDS & ERF. REP WAS ABLE TO TEMPORARILY. RECONFIGURE'UNULATE SOFT WARE TO CURE PROBLEM HOWEVER MODIFICATION MUST BE MADE TO MAKE PERMANENT [ f '" CO3PLETE: 10/20/89 FIX. CONTACT R. PERiiY OR D. BYE FOR FURTHER INFORMATION. RETURNED QSPDS< TO NORMAL CONFIGU~4ATION AFTER TROUBLE. SHOOTING. 2
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COMPLETE-- 10/23/89 . p WORK DESCRIPTION . 894901 EE ELECTRICAL PENTRATIOf4 F-11 NEEDS TO BE RECHARGED.WITH NITROGEN.. . 7 IC_ _C; _ F-11 - ; WORK PERFORMED .. COE: V CLASS: 2 CHARGED Up PENETRATION AS-PER ST-CONT-2 - COMPLETE: 10/2argg - 'T WORK DESCRIPTION. .
- T 894982 AC-CCW NEED TUBE PLUGS FOR AC-1E. MM C: .
AC-1B l WORK PERFORMED . . . CQti: Y CLASS: 3 FABRICATED 12-EA PLUCS FOR . TUBE Pl%5 REF: ATTACHED DRAWING USED 8 PLUGS 4 - ON AC-18. PUT 4 PLUGS IN WAREHOUSE WITH REQi>EST.THAT THEY BE MADE STOCK ITEu WITH WAREHOUSE NUM9ER. . . _ r!- COMPLETE: 10/10/89 -- , r 1 - , - -
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fd wor:K~ DESCRIPTION 094998 CH EXCESSIVE PACKING LEAK REPACK FJMP,
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895020 ..TM TERMINAt; RING ON WIRE s 1T-1 NEEDS'TO BE REPLACED.~SUGGEST'THAT RING TON ' -JM1
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WORK OESCRIPTION _._ 895069 AC-CCW IN ROCM B1 ON CCW INLET TO VA-468 VALVC HCV-2899A IS BLOWING AIR '
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.u BEING JACKED CLOSE BY. OPS..THIS WORK DOES NO REQUIRE POST-MAINT.> TESTING e - - 7 ::
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