ML20116B600

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Performance Indicators Sept 1992
ML20116B600
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 09/30/1992
From:
OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20116B598 List:
References
NUDOCS 9211020284
Download: ML20116B600 (109)


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t OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT l

Prepared By:

Production Engineerinc Division System Engineering Test and Performance Group l SEPTEMBER 1992 l

l s . _ . _ - - . , .- __ _ . _ _ _ _ - . .

o ABSTRACT PURPOSE ,

The

  • Performance indicators Program"is intended to provide selected Fort Calhoun plant perfor.

rr.ance information to OPPD's personnel responsible for optimizing unit pertormance. The information j is presented in a way that provides ready identification of trends and a means to track progress toward reaching corporate goals. The information can be used for assessing and monitoring Fort Calhoun's plant performance, with emphasis on safety and reliability Sume performance indicators show company goals or industry inf ormation. This information can be used f or comparison or as a means of promoting pride and motivation.

F

.S_C. OPE The conditions, goals, and projections reflected within this report are current as of the end of the month being repor1ed, unless otherwise stated.

In order for the Performance Indicator Program to be ellective, the following guidelines were followed while implementing the prograrn:

1) Data was selected which most effectively monitors Fort Calhoun's periormance in key areas.
2) Established corporate goals and industry information were included for comparison.
3) Formal definitions were developed for each periormance pararreter to ensure consistency in future reports and allow comparison with industry averages where appropriate.

Comments and input are encouraged to ensure that this program is tailored to address the areas which are most meaningful to the people using the report. Please refer comments to the System Engincenng Department's Test and Performance Group. To increase personnel awareness of Fort Calhoun Station's plant performance, it is suggested that this report be distributed throughout your respectivo departments, l

REFERENCES I INPO Good Practices OA 102,

  • Performance Monitoring Management Information" INPO Report Dated November 1984, *Nuc! car Power Plant Operational Data" NUMARC 67 00," Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Black out at Light Water Reactors", Revision 1, Appendix D, *EDG Refiability Program", dated April 6,1990.

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Table of Contents / Summary JNPO INDUSTRY KEY PARAMETERS PAGE emtTny .cLtc. ccca em n m rg;A;, TH e uynH utt ummi letsa UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7.000 HOURS CRITICAL., . ..06. .. o . 5 86. . 7 08. .NMA. .3 SAFETY SYSTEM PERFORfAANCE 9.ao.u.wm:

HIGH PRESSURE SAFETY INJECTION SYSTEM. . . . . . . .. . .00012. .0008 .00014. . O M 17 . . NA . .6 AUXILIARY FEEDWATER SYSTEM . . . . . . 0 0038 0 01. . 0 00c5. 0 0049. NA. 7 EMERGEtlCY AC POWER SYSTEM.. . .. . 0 0055. .0 074 . 0 0015 0 0017 .NA. .8 THERMAL PERFORMANCE . . . . . .... 998% . 99 3% . 99 4E. . 99 5% . D .. . 10 UNIT CAPABILITY FACTOR . . .096% . 69 2% 77.5 % .620%. . l .. . .12 UNPLANNED CAPABILITY LOSS FACTOR.. .1 ELE. .4SW . 22 5k. . 38 0% . .. l .. . 13 FUEL REllABILITY INDICATOR im,cas. nm).. . . . . NA. . 7 5:10-4. 7476:10 4._6 75 10-4. . NMA.. 15 COLLECTIVE RADIATION EXPOSURE (wwem) ..115 6/YR . 250TR . 245 3. . 239 9. N A ,.. = 16 - _

VOLUME OF LOW LEVEL SOLID RADIOACTIVE WASTE tcwe M . . 2.077 9/YR ._3.000'YR .1.300 4 . . BCS 1. . N A .. ..17 INDUSTRIAL SAFETY ACCIDENT RATE / DISABLING INJURY /lLLNESS FREQUENCY HATE., '

., . 012.. .. o 3 .. . 1.12 . 1.26 .. .A. 18 CHEMISTRY INDEX/ SECONDARY SYSTEM CHEMISTRY . .. . . . ...... . .. 0 20.. . 0 45.. ..,0 51. . 0 56 . NMA .. 44 OPERATIONS P. AGE P M STnY .OPf'D QEcQ gljm ggAj, TH'E l.ONf H t Ati UNITH M STATION NET GENERATION (10.000 Mwh)... .. . ..N A . . . N A .. . 27.2. . 21 9. , l .. . ._ . 1 FORCED OUTAGE RATE . , . . .. .. , . ..o 25E. .24E. .121E. .15 7% . .NMA. .2 UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7,000 CRITICAL HOURS. . .. .. . ..06. .. o . . 5 86 . . 7.08 . ..NMA ..3 UNPLANNED SAFETY SYSTEM ACTUATIONS . (INPO DEFINITION)... .. .. ....0~ . 0 .. . 0 .. .0. .. N M A . . . 4 UNPLANNED SAFETY SYSTEM ACTUATIONS - (NRC DEFINITION).. . .. . .0. ,.3. . 0 .. ..-.1. . NMA , ... 5 GROSS HEAT RATE . , . . . . . . . . . . . . . . . . . .. N A . .. N A . . 10.225 - 10,335.. . l . .. . . 9 EQUlVALENT AVAILABILITY FACTOR , . . . . . . . ....NA.... .. N A . . 81.0E. .643%. .. l .. . .. . 11 UNIT CAPABILITY FACTOR . .. .. . . . . , . . .. . 89 CE. .692E. 77SE. .620%. 1..... 12 UNPLANNED CAPABILITY LOSS FACTOR.. . . . ..1 BSE. 4.5W 22 LE. . 38 0% . . . l .. . 13 PLANNED CAPABILITY LOSS FACTOR. . . .. . . .. . . 8. 55 % . 26 3% . 0E. .Ok .. N A .. .14

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o OPER ATIONS (cont'd) PACE 2C41M .CtCD. CitD tmn e . C2ta lift f.etan Lt:1 f.etnH Intno FUEL REllABILITY INDICATOR (m;ctocuriet,! gram) . ..NA . 7 5 :D-4. 7.76 10-4. . 6 75:10-4 . . NMA . 15 DAILY THERMAL OUTPUT (mmh) . .. .. N A . .1495 .NA NA N A .. .19 EQUIPMENT FORCED OUT AGES PER 1,000 CRITICAL HOURS... .. N A . 02, .14, 1 co . NMA . . 20 OPERATIONS AND MAINTENANCE BUDGET, .. N A . .NA. .. N A . .NA. N A .. . 21 DOCUMENT REVIEW . . . . . . . . . . .NA. .NA. . NA. N A .. ~ N A .. . 22 MA!NTENANCE PAGE innutiny errn ccto g!'M - ggfa TH:t f.OfMH LAtt MONTH 111 LIQ EMERGENCY DIESEL GENERATOR UNIi REllABILITY . . .. . ....NA- .. N A . .. N A . mN A .. NA...23 DIESEL GENERATOR REllABILITY (25 DEMANDS).. . . . .. ,, , ,. .. N A . ..<4. NA. .. N A .. .. HA ., . 24 DIESEL GENERATOR UNAVAILADILITY kwmme hrs ) NA.. . et210 0T)0 . . N A . .-NA; .. N A ,. .. 25 AGE OF OUTSTANDING MAINTEN ANCE WOHK ORDERS (CORRECTIVE NON OUTAGE) ... . ..NA , .NA.. .NA. ..NA- .. N A .. . 26 MAINTENANCE WORK ORDER BREAKDOWN (CORRECTIVE NON OUTAGE) . . ... N A . . NA. .NA- .. N A .. ,. l . .. .. 2 7 CORRECTIVE MAINTENANCE BACKLOG GREATER THAN 3 MONTHS OLD (NON OUTAGE).. . . . . . . . . . . . . . . . . . . . . . ...NA. ..NA. . 63 9% .. 70 2% , _. l . . . 28 RATIO OF PREVENTIVE TO TOTAL MAINT E N AN C E , , .. .... . . .. . . . ..... . .. .. . . .. .. N A . . . 65% . . 50 6% . . 551% . . NMA . . 29 PREVENTIVE MAINTENANCE ITEMS OVERDUE... . . . . . ... . . ., . - -..NA ; . 0 5% :. . 0 38% ... ,.0.19% . . D .. . . 30 NUMBER OF OUT OF SERVICE CONTROL ROOM INSTRUMENTS .. .. . . ,, . . . . . N A . ..NA.

. 12. . 11 .. D . . 31 MAINTENANCE OVERTIME . . .. . . .. N A .. .10% .- .86%- . 22 7% . l . . . 32 PP.OCEDURAL. NONCOMPLIANCE INCIDENTS (MAINTENANC6) . . . . . . .. NA .. ., N A . .._....o. . .0. . l . , .. 33 -

PERCENT OF COMPLETED SCHEDULED ,

MAINTENANCE ACTIVITIES (ELECTRICAL MAINTENANCE) . . .. .NA. - .,80% .. . NA .. ...NA.. .. N A .. .. 34 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (PRESSURE EQUIPMENT).. . . . . . . . . . N A .. , . 80% .. mNA, .. N A .. . . N A .. .. 35 li

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PERCENT OF COMPLETED 2CHEDULED j MAINTENANCE ACTIVITIES i (GENERAL MAINTENANCE) . . . .. N A .. 80% .NA. NA. . N A .. . 3G  !

PERCENT OF COMPLETED SCHEDULED j MAINTENANCE ACTIVITIES ,

(MECHANICAL MA!NTENANCE) . . . . .. N A .- 80% ..NA. . NA- N A.. . 37  !

i PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVlilES  :

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) (INSTRUMENTATION & CONTROL) . . . .. N A .. 60% . NA. . N A .. NA.. . 38 i NUMBER OF MISSED SURVEILLANCE ,

TESTS RESULTING IN LICENSEE .

EVENT REPORTS . . . . . .. . . . . . . . . ... N A . . 0 .. . 0 .. .0. _ l .. . . 3 9 1

J COMPONENT FAILURE ANALYSIS ,

L .. .. N A . .NA. L l .. . . 4')

REPORT (CFAR)

SUMMARY

.. . . . .... . . .. NA . .. N A . ,

3 3 NUMBER OF NPRDS MULTIPLE FAILURES . . . .. ..NA . NA . .. N A . . N A .. NA. . 41 4 MAINTENANCE EFFECTIVENESS . . .

.,NA. NA .. NA. . NA .. .NA. .42 1

j CHECK VALVE FAILURE RATE . .NA. 2 00E4. . 617E 7. _6 10 E.7 . .NA. J43 a- 1 CHEMISTRY AND RADIOLOGICAL PROTECTION PAGE i mus1nt .CEED., C222 l unnt n m. ggAL in r uynn urT uynn intno i- COLLECTIVE RADIATION l EXPOSURE (person tem). ... , .115 &YR . . 250!YR . _245 3. , 239 9... . N A .. .16 j

VOLUME OF LOW LEVEL SOLID >

- RADIOACTIVE WASTE . . . .. . . . . . . . . . 2.077 9"(R , 3,03TYR ..1.306 4 . . 666 1, ~ N A .. .17 1

4 SECONDARY SYSTEM CHEMISTRY.. . . . . .. 0.20 .. . 0 45. .0 515% ,'. . 0 561 % . .. NMA . .. 44 i PRIMARY SYSTEM CHEMISTRY PERCENT OF HOURS OUT OF LIMIT . . . . .. N A .. .2%. ..1.18% .. . 2.13% . ..l... . 45 i AUXILIARY SYSTEM (CCW; CKEMISTRY PERCF.NT i

OF HOURS OUTSIDE STATION LIMITS , 4 . . .. N A . .. N A .. 0% .. 0%. . . l .. , . . 4 6 '

l i IN LINE CHEM!STRYINSTRUMENTS

OUT-OF-SERVICE . . . . . .. N A . 6 .. .-20 . 23 . .NMA...47 i

j HAZARDOUS WASTE PRODUCED .. . ... N A . .. N A . 10. .0. .. NA . ..48

. MAXIMUM LNDIVIDUAL _ . _ _ _ _ _

RADIATION EXPOSURE (mrem). . .. N A . .1.SoWYR ..1,752.. 1.740., .. NMA . . 49_ _

1 TOTAL SKIN AND CLOTHING CONTAMINATIONS .. . . - . . ..N A . .144. .257. 253. NMA . , . 50 -

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CljWJSI,By.ffJD RADIOLOGIC AL PROTECTION (cont'd) PAGE .

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!?.'1's 14Y M OfC2 j ener n 1ng cca TH!s 9mmi usi to*mi inOm i DECONTAMINATED RADIATION CONTROLLED AREA. . . .. N A . . 68% . 88 2R 872%. .l. . Si

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RADIOLOGICAL WORK PRACTICES PROGRAM , . . . . . . ...NA, .NA. .6. .1 .D. . 452 NUMBER OF HOT SPOTS . , . , NA . ..romon ilmo . 67 . . 72 . ,..l.. .. $3 GASEOUS RADIOACTIVE WISTE DEING DISCHARGED TO THE ENVIRONMENT (cuties). . ...NA. . 340)t. . .140 7 140 7- . N A . . . 54 .

LIQUID RADIOACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT (curies) . .. N A 225'yt. . 39 5- . 39 $ ,. . N A .. .. 5$

SECURITY PAGE tcuting ceto cLtp enntn e. ccg THis to*ata utt tofmi inum LOGGABLE/ REPORTABLE . .

INCIDENTS (SECURITY) . . . . ..NA.

. NA. 23 .18 . .D. . 56 SECUnlTY NON. SYSTEM FAILURES . . . N A .. .. N A _ .NA. . N A .. NA . . 57 SECURITY SYSTEM FAILURES . . . .. . .. .. .. . N A . . N A ., .. N A . N A .. .. N A , . 58

MATERtALS AND OUTSIDE SERVICES PAGE

] eeutiny cnca ccco j onern m. con 1His tornu vst to Jiu Inga l AMOUNT OF WORK ON HOLD

! AWAITING PARTS (NON OUT AGE).. ... ... .. N A . .35W. . 2 34% .. ..3 0% . . 1. . 59 ,

SPARE PARTS INVENTORY VALUE ($ milhon)... ..NA. .NA. ..12 7.. .. 12 6. .. N A . 60

{ SPARE PARTS ISSUED ($ thousands)... . . ... .. . .. . . N A . ,. N A .. . 123.9 . . 154.1. .. N A . . 60 INVENTORY ACCURACY. . . . . . . .. N A .. .98%. ..95 3% . , 100% .. . NMA .. . 61 l ...

i STOCKOUT RATE. . , . . . . ., . . . . ... N A . .20W ..0 38 % . . ..0 32% . . N A . . . 61 i

EXPEDITED PURCHr.SES.. .. . . . . ... N A . .. o SW. ..o45%. . 0% - D . . . 62 INVOICE BREAKDOWN , . . . , , . . .NA. . N A ., NA. .. NA . .. N A . .03 s

MATERIAL REQUEST PLANNING.. . . ... N A = , .. NA . . 45 7E. .59 3W N A . .. . 63

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DESIGN ENGINEERING . -f1GE l routiny CEED REED pnnt n ~, C2 n TH'S!.Otay LAsi L*N mi ISOQ

! OUTSTANDING MODIFICATIONS.. ..NA. _ _ . .NA. 148. 100 . l .. . 64 i-t b4 l

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TEMPORARY MODIFICATIONS (EXCLUDING SCAFFOLDING) . . . . . .. N A . .O_ . 21. 18. .NA. . 05 ENGINEERING ASSISTANCE REQUEST (EAR) BREAKDOWN . .. .. N A . .. N A . . 133 .. .133. . A . . . 06 ENGINEERING CHANGE NOTICE STATUS . . .. NA ,NA. . 1 $2 , . . 161 . . N A .. . 07  !

ENGINEERING CHANGE NOTICE BREAKDOWN . .....NA- .. N A .. .. N A . .NA. NA. . 08 ,

INDUSTRIAL SAFETY PACE j e:cutinY CECD CEE2 .

uPPEn 9% G2fg TH't MPHH LAti UNMH In[QQ DISABLING INJURY /lLLNESS FREQUENCY RATE . . 012. 03, .1 12 .. 1 26. . NMA . 18 RECORDABLE INJURY /lLLNESS CASES FREQUENCY RATE ... . . . . . . . . . .. N A .. 2 0.. .,3 58. . 3 28. .. A . . . 09 HUMAN RESOURCES PgE i fA m CEED CEED uPPt n m . ggAL is't uonta uti t.ons inEua NUMBER OF PERSONNEL ERRORS REPORTED IN LERs.... . . . . . . . . . . ... . . . . . . . N A .. . .NA. _0_ 1. .. l . . ... 70 LER ROOT CAUSE BREAKDOWN. . . , , ,.. .. .. N A . .. N A .. .. N A . _ N A .. .. N A . . 71 STAFFING LEVEL . , . . . . . . . . . . . . .. , , ., . .. N A . . NA .. .. NA .. .. N A .. .. N A . . 72 PERSONNEL TURNOVER RATE . .. .. . .. N A . .. N A .. .. N A . , N A .. .. N A . .. . 72 TRAINING AND QUAllFICATION PfASE rioustny CEED CEED UPPER * $ Q2AL TH$ MNJTH M M IEQQ LICENSED OPERATOR REQUALIFICATION TRAINING.. . . .. .. . , . .. N A .. .. N A .. N A '. . N A.. .-. N A . . . 73 LICENSE CANDIDATE EXAMS... .. .. . - , . . N A .. .. ... N A ,hA-. ;NA.. ... N A . . . 74 TOTAL INSTRUCTION HOURS . ... .. ,, . . . .. N A .. .. N A .. . 2.024. 1 1,*J 9 5 .. N A . .. .,75 TOTAL HOURS OF STUDENT TRAINING.. .. N A ,. t.A L 8.641 . . 4.768.. .. N A . . . 76 V

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_ ___. _ _ .. - - . - _ _ ... ~ --

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i OUAllTY ASSUR ANC.E PAGE i

1 4 a EQU11P.Y CEEJ CEEQ errm e . Cat;.;, twtte m y u siin m H 1 cum VIOLATIONS PER 1.000 ifJSPECTIOf 4 HOURS . . .. NA- 1.5 - . 2 71. . : to - NMA, .77 i COMPARISON OF VIOLATIONS l; AMONG REGION IV PLANTS . . . ...NA. NA~ _NA. .NA.. .. N A .. . 78 I CUMULATIVE VIOLATIONS AND NCVs j (TWELVE MONTH RUNNING TOTAL) . . . . . ..NA. .. N A ., 14 2 , .1td .l. . 79 ,

1 l i OUTST ANDING CORRECtlVE l ACTION REPORTS . ..NA. NA ..91. . 76 . D . . . 80 )

OVERDUE Af1D EXTENDED

CORRECTIVE ACTION REPORTS. . ..NA. . N A .. ..0'9 . . 0/9. . N A .-... . 81

! CARS ISSUED vs. SIGNIF. CARS vs.

iJRC VIOLAllONS ISSUED vs.

i LERs REPORTED.. . . . . . . .. . .. .. ... NA . NA , _NA. . NA . ~NA. . 02 9

I

REFUELING QUTAGE t

] JNDUttRY QEED -QEED UPPtn e*-. g2A], TH't voNTH LAst poN1H 1 REND j t/MO PLANf JING STATUS . . . . . .. N A . . ... ... N A .r. .. NA: NA 4. ..NA-... ..83

'i OVERALL PROJECT STATUS . a r.,N A ..... ... N A ... .. _ N A .. . .. .... td A .. 84 l ... . .. . ....NA...

PROGRESS OF CYCLE 15 OUTAGE y MODIFICATION PLANNIfJG. .. . . . ,, . ... . . . . N A ...... .. N A . . . N A .. ..... N A ... . N A , 8 $

i  !

'i PERFORMANCE INDICATOR DEFINITIONS..... . . . . . .. . . . . . . ... . . . . . .. . . . . ... . . 86 SAFETY ENHANCEMENT PROGRAM INDEX. .. .... . . . . . . . . . ... . . . . . ... . ... . 94 1

i REPORT DISTRIBUTION LIST . , . . . . . . . . . . . ., . . . . . . . , . . . . . . ... . ... ,. . 96 4

! SUMM ARY SECTION I

s .

! POSITIVE TREND REPORT .. . . .. . .. . . .. . . . . . . .. . . . . . . . .. 97 1

l ADVERSE TREND REPORT.. . .. . .. . . . . . . .. . . . . . . . . . . . . . . . . . . ... .. . . . . . . . . .. 97-

)

5: INDICATORS NEEDING INCREASED MANAGEMENT ATTENTION REPORT ... . . .. . . ,. ..... .... , . .. 97. -;

I PERFORMANCE INDICATOR REPORT IMPROVEMENTS / CHANGES - .. . .....-. .......................98 1

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4 TABLE OF CONTENTS'SUMM ARY TREND SYfdPQl,$

A- ADVERSE TREND

! I IMPROVED PERFORMANCE i D - DECLINING PERIORMANCE NMA NEEDS MANAGEMENT ATTENTION NA - NOT APPLICABLE /AVAILABLE-Vi

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t i Oct91 Nov Dec Jan rob Mar Apr May Jun Jul Aug Sop 02 l STATION NET GENER ATION i 4

During the month of September 1992 a net total of 272,032 MWH was generated by the >

Fort Calhoun Station Unplanned energy losses for the month of September were

attributable to the forced outage which began on 8/22/92 when an AC/DC converter l

failed in the Turbine Electro Hydraulic Control system. Pressurizer safety valve RC 142 then opened prior to reaching design pressure and the plant tripped on TM/LP. The  ;

generator was brought on line at 2101 hours0.0243 days <br />0.584 hours <br />0.00347 weeks <br />7.994305e-4 months <br /> on 9/5/92.

i l Unplanned energy losses during August were the result of the forced outage on 8/2P/92

(described above) and the forced outage on 8/5/92 when a feeder breaker to the 125V ,

de panel Al 41 A failed resulting in a controlled shutdown to Mode 2. The turbine gen-orator was synchronized to the grid on 8/6/92.

Unplanned energy losses for the month of July were a result of the forced outage that l

i occurred on 7/3/92 due to the loss of an inverter and the subsequent reactor trip. The

generator was brought on line at 0610 hours0.00706 days <br />0.169 hours <br />0.00101 weeks <br />2.32105e-4 months <br /> on 7/23.

During the month of June 1992 unplanned energy losses were a result of a forced outage that occurred on 6/1/92 due to a dropped control rod. The plant was returned to t

100% power on 6/4/92.

The station was returned to service after the Cycle 14 Refueling Outage when the

]

reactor was taken critical on 5/1/92 at 1035 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.938175e-4 months <br /> and the generator was put on line on l 5/3/92.' A forced outage occurred on 5/14/92 when the turbine generator tripped on a

! false high level moisture separator trip signal which caused a simultaneous reactor trip.

The reactor was retumed to critical and the generator was put on line on 5/15/92.

'I Unplanned energy losses for May were: 1) the Cycle 14 Refueling Outage extension; 2) the reduction to 58% power for repair of an inoperable condenser valve: 3) the reactor trip; 4) the hold at 48% power for _ repair on a feedwater pump suction valve; and 5) the 5/31 dropped control rod caused by a faulty clutch coil.

Data Source: Station Generation Report Accountability: Patterson Adverse Trend: None 1

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4 Forced Outage Rate lG000]

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'fj9 '90 '91 Oc191 Nov Doc Jan Feb Mar Apr May Jun Jul Aug Sop 92 FORCED OUTAGE RATE The forced outage rate was reported as 12.06% for the twelve months from 10/1/91 to 9/30/92.

l Forced outage hours for September 1992 were due to the forced outage that began on 8/22/92 when an AC/DC converter f ailed in the Turbine Electro Hydraulic Control system. Pressurizer 1

safety valve RC 142 then opened prior to reaching design pressure and the plant tripped on TM/

LP. The generator was brought on line at 2101 hours0.0243 days <br />0.584 hours <br />0.00347 weeks <br />7.994305e-4 months <br /> on 9/5/92.

During the month of August forced outage hours were due to the forced outage on 8/22/92 (described above) and the forced outage on 8/5/92 when the turbine was taken off line to rep! ace a feeder breaker to the 125V de panel Al 41 A. The turbine generator was synchronized to the grid on 8/6/92.

A forced outage caused by the loss of an inverter and the subsequent reactor trip occurred on 7/

3/92. Ad&tionally, RC-142 opened and failed to reclose The generator was brought on line at 0010 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> on 7/23/92.

A forced outage occurred on 6/1/92 when the unit was shutdown due to a dropped control rod.

The generator was brought on line at 0852 on 6/2/92.

A forced outage occurred on 5/1412 at 1557 hours0.018 days <br />0.433 hours <br />0.00257 weeks <br />5.924385e-4 months <br /> when the turbine gencrator tripped on a f also high level moisture separator trip signal which caused a simultaneous reactor trip. The generator was brought on line at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br /> at 5/15/92 following repairs.

During the months of September and October 1991 a forced outage occurred when the station batteries were declared inoperabte. The generator was taken off-line on 9/12/91 and remained off line until 10/6/91.

The generator was taken off line on October 18 & 19,1991 due to a steam leak on a turbine control valve before seat drain line. The generator was again taken off line on October 25 & 26 due to a steam leak from an instrument tap on the high pressure turbine.

The 1992 and 1991 Fort Calhoun goals for Forced Outage Rate are 2.4%

Data Source: Monthly Operations Report & NERC GAD Forms Accountability: Patterson Adverse Trend: None 2

_ _ _ _ _ _ . _ _ . _ .--. . -- _ - -. . . -~ _ _ _ - . . . _ _ _ _ . - - . . _ . _ _ _ _ _ . _ _ - _ _ __ __

- FCS Heattc,t Lerams Per 7.000 Hours Critica! (Year to cate)

-+- FCS neactor Scrams Per 7,000 Hours Critical (for tne last 30 months)

--O. 1991 h 199? Fort camNn Gen

-tr- 1005 INPO Industry Goal gn_ O' inantry Urper t D% (0 6 per 7,000 hou 6 entscal over a 30 rnonth timo penod) i 4- ,

C-4-

2- m m m m m m m m m m m m o U 2 '

'j , U -U U ,

, - 8 9= 6 3 . W r " d r**M OctDi Nov Doc Jan Feb Mar Apr May Jun Jul Aug Sep92 5-C Number of FCs neactor 5 rams 2- -

t $ i i

0 0 0 0

> > i

'88 T9'90'91 i

1-0-

o i

o i

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Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug SepD2 Uf1PLAlllJED AUTOMATIC REACTOR SCRAMS PER 7,000 HOURS CRITICAL The upper graph shows the number of unplanned automatic reactor scrams per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical (as defined in INPO's 11/91 publication *DLailed Descriptions of International Nuclear Power Plant Performance Indicators and Other IndicatorV) for Fort Calhoun Station. This value is calculated by multiplying the total number of scrams in a specified time period by 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, toen dividing that number by the total number of critical hours in the samo time period. The year to date station value is 5.86 and the value for the last 36 months is 1.08 for the month of September 1992. The lower graph shows the number of unplanned automatic reactor scrams that occurred during each month for the last twelve months.

There were no unplanned automatic reactor scrams during September 1992.

There was one unplanned automatic reactor scram in August 1992. This scram occurred on l August 22 as a result of the failure of an AC/D0 converter in the Turbine Electro Hydraulic Control system. Pressurizer safety valve RC 142 then opened prior to reaching design pres-sure and the plant tripped on TM/LP.

There was one unplanned automatic reactor scram in July 1992. This scram occurred on July 3 at 2336 as a result of the loss of inverter No. 2.

There was one unplanned automatic reactor scram in May 1992. This scram occurred on May 14 at 1557 when the turbine generator tripped on a falso high level moisture separator trip signal which caused a simultaneous reactor trip. The last unplanned automatic reactor scram

, prior to this occurred on July 2,1986.

l The 1992 goal for unplanned automatic reactor scrams per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical has been set at i zero. The 1995 INPO industry goalis one unplanned automatic reactor scram per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> i

critical, The industry upper ten percentile value is approximately 0.6 scrams per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical for the 36 month time period from 7/89 through 6/92.

Data Source: Monthly Operations Report & Plant Licensee Event Reports (LERs)

Accountability: Patterson Adverse Trend: None 1 3 l

l l

l .- - , - - - - - - - - ,, . - _ . -. . -.. . -- - - - - -

3 1 O satoiy system ^ctuations

-G-- 1992 Fort Calhoun Goal

-G- Industry Upper 10 Percentile 2-

)

i I

1 1

1- -

3 0 0 i i 4

,0 0 i G , G- 7 -O , O , O ,G , 3 r--G , G 7-G , h

'89 '90 '91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov DoD92 UNPLANNED SAFETY SYSTEM ACTUATIONS-(INPO DEFINITION)

I There were no unplanned safety system actuations during the month of September 1992.

There were no unplanned safety system actuations during the month of August 1992.

There was one unplanned safety system actuation during the month of July 1992 due to the loss of an inverter and the subsequent reactor trip on 7/3/92.

The 1992 goal for the number of unplanned safety system actuations is zero.

The industry upper ten percentile value for the number of unplanned safety system actuations per year is zero.

Data Source: Monthly Operations Report & Plant Licensee Event Reports (LERs)

Accountability: Jaworski/Foley/Ronning Adverse Trend: None 4

= . . . . - - . . . . - . _- _ _-. __. _ .- -_. __ __._ . . - __ .- - - . ..- -..- _- __

12 Month Running Total SSAs

+ Cnt.cul Houre '

C Stht,- Cys tem Actautior;s (USAs.)

10- 1000 Doo 0- Boo  !

~'*

7oo j 0- -

Coo S

{4- 3 ldi vi 400 4 v x

},} y 2

$a- - - 200 0 Al ~$, 0 n p g

, , , _ 0

'09 *00 '91 S O tJ D J FMAMJ J A S O fJ D J F M A fA J J A S UNPLANtJED SAFETY SYSTEM ACTUATIONS-(l1RC DEFINITION)

This indicator shows the number of unplanned safety system actuations (SSAs), which inclJdes the High and Low Pressure Safety injection Systems, the Safety injection Tanks, and the Emergency Diesel Generators. The NRC classification of SSAs in-cludes actuations when major equipment is operated and when the logic systems for these safety systems are challenged.

There were no unplanned safety system actuations during the month of September 1992.

An unplanned safety system actuation occurred on August 22,1992 due to the failure of an AC/DC converter in the Turbine Electro Hydraulic Control system. Pressurizer safety valve RC 142 then opened prior to reaching design pressure during a plant transient and trip.

Two unplanned safety system actuations occurred in July 1992: 1) On July 3 there was an invener failure and the subsequent reactor trip; 2) On July 23 there was an unplanned diesel generator start when an operator performing a surv6illance test inad-vertently pushed the normal stad button instead of the alarm acknowledge button.

An unplanned safety system actuation occurred on May 14,1992 when the turbine generator tripped on a false high level moisture separator trip signal which caused a simultaneous reactor trip and subsequent anticipatory start signal to both diesel genera-tors.

The 1992 Fort Calhoun goal for this indicator is a maximum of three.

Data Source: Monthly Operations Report & Plant Licensee Event Reports (LERs)

Accountability: Jaworski/Foley/Ronning Adverse Trend: None 5

d Q 1902 Monthly H:gh Pressure Safety injection System Unavailab.hty Vaivo

-N- 1992 High Pressure Safety inject or, System Unavailabihty Vatue Year to Date

-O- 1991& 1992 For ca'houn coa!s

+ 1991 H;gh Pressure Safety inject <on System Unava:labihty V.nive Year.to Date

-A- 1995 INPO Ind astry Gotal(0.02)

-{"}- Int stry Uppe' 10 % (0 0012) 0.02s -

l 0.02 - b - +b- 6- A h- h- -b- ~ 6 -=h

< 0.015 -

Cycle 14 Refuehng i 0.01 - O O Os O.:tage

O O O O O O 0.005 - -et.-

E Km

! 0 Oct91

[Nov 7 Doc ,

Jan Feb Mar Apr May Jun Jul Aug SepD2 HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the High Pressure Safety injection System unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for the report-ing month.

The High Pressure Safety injection System unavailability value for September 1992 was 0.0. There were no (zero) hours of planned or unplanned unavailability in September.

The 1992 year to-date HPSI unavailability value was 0.0014 at the end of September.

There were 1.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of planned unavailability for surveillance tests in August, in July there were no (zero) hours of planned or unplanned unavailability; in June there

, were 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of planned unavailability for surveillance tests and in May there were 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of planned unavailability for surveillance tests.

The 1992 For1 Calhoun goal for this indicator is 0.008. The 1995 INPO lndustry goalis 0.02 and the industry upper ten percentile value (for the three year period from 7/89 through 6/92) is approximately 0.001E.

Data Source: Jaworski/Schaffer Accountability: Jaworski/Schaffer Adverse Trend: None 6

I


- - ~ . - - -_ . _ . - . .

O 1992 Monthly Auxihnry Feedwater System unavailabihty value l

-M- 1992 Auxil,ary Foodwater system unavailabihty Valse Year to date

-O- 1991 & 1992 For1 Cathavn Goals

-@- 1991 Avail.ary Foodwater system unavailab.hty Value Year to date

-A- 1995 If4PO Industry Goal

-O- Industry upper 10% (0 0038) 0.025 - A-- A - A- -A A- -A- - A -- A -- A Cycle 14 0.02- O O Os Refachng 0.01s - Outage 0.01 - O. 2 O O O H u 4t 0.005 -

D O O

O $CC ^

NO 0--@ , , ,

+ , , , , , , ,

Oct91 Nov Doc Jan Feb Mar Apr May Jun Jul Aug Sep92 AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Auxiliary Feedwater System Unavailability s alue, as defined by INPO in the Safety System Performance Indicator Definitions, for the reportir.g month.

The Auxiliary Feedwater System Unavailability Value for September 1902 was 0.0138.

The 1992 year-to date AFW unavailability value was 0.0065 at the end of September.

There were 0.67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> of planned unavailability for surveillance tests in Sefember. In addition, there were 16.43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> of unplanned unavailability for repair of YCV 1045.

There were 1.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of planned unavailability for surveillance tests in August.

There were 1.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of planned unavailability for surveillance tests in July.

in June 1992 there were 2.82 hours9.490741e-4 days <br />0.0228 hours <br />1.35582e-4 weeks <br />3.1201e-5 months <br /> of planned unavailability for a M and 7.33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> of unplanned unavailability for corrective maintenance on a flow instrument.

In May 1992 preventive maintenance activities resulted in 2.67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> of planned un-l availability and there were 10.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> of unplanned unavailability due to corrective maintenance following the initial attempt to perform a PM.

l The 1992 Fort Calhoun goal for this indicator is 0.01. The 1995 INPO industry goalls 0.025 and the industry upper ten percentile value (for the three year period from 7/89 through 6/92) is approximately 0.0038.

Data Source: Jaworski/Nay Accountability: Jaworski/Nay Adverse Trend: None 7

_ , - - ,~_ . - _

_ __ . _ _ . .__..___.__._..__m _ . _ _ . _ _ _ _ _ . _ _ _ _ _ _ . _ . _ . _ _ - . . ____,. - ____-, _.___. ____

l O 1992 'Aoniniv Emerooner Ac Power unava iab,iity vaivo

-M- 1992 Emorgoney AC Power Unavailabshty Valvo Year-tn Dato i 4- 1991 a1992 Fort Cdha<n ceas (c ON; I GCpDJ

--+-- 1991 Emergoney Ac Power Unavailabihty Valvo Year to Dato 0 00 - -- A .. 1995 If4PO Industry Goal (0 025) 0.05- -Q- Industry Upper 10% (0055) 0 04 -

~

003-1 6 t6a m6..m : 6a _ 6.. t ..aa 6 ;am . 6 aa 6. a.m. 6 a .aua.f aa.. aa.6 a.a .a.6 j O 02 -

l 0 01 -

1 0- , , , , j , - ]~ , , ,

Oct91 f40v Doc Jan Feb PAar Apr tAny Jun Jul Aug Sep92 EMERCENCY AC POWER SYSTEM SAFETY SYSTEM PERFORMANCE 4

This indicator shows the Emergency AC Power System unavailability value, as defined by lisPO in the Safety System Performance Indicator Definitions, for the reporting month.

The Emergency AC Power System unavailability value for September 1992 is 0.0. The Emergency AC Power System unavailabil: y value year to date is 0.0015.

There were no (zero) hours of planned or unplanned unavailability for DG-1 or DG 2 in September.

There were 2.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> of planned unavailability for DG 1 in August to inspect relays for contact degradation.

I in July there were no (zero) hours of planned or unplanned unavailability.

In June 1992 there were 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> of planned unavailability for DG-2 for retorqueing radiator fan retaining bolts.

In May 1992 there were 7.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> of planned unavailability for DG 1 to tighten the fan blades and repair a starting air solenoid valve.

The 1992 Fort Calhoun goal for this indicator is 0.024. The 1995 INPO industry goalis 0.025 and the industry upper ten percentile value (for the three year period from 7/89 through 6/92) is approximately 0.0055.

Data Source: Jaworski/Ronning Accountability: Jaworski/ Running Adverse Trend: None 8

13 -.

s O Monthly Gross Heat Rate

] -A- Year to Date Gross Heat Rate 5

x 12 i

e i

i 8

o i

l 11-10520 10304 10023

- Cycle 14 - ._

m$

El [ Mil '@,i Refuehng A- -e + ~

$'pf 10-NY*/)lll$? $

Outage Vl O{$ f l ' $) s Pf'k&

{' h ,  ?

$/?

nsl

, 9 , , , , , , , , , , , ,

'39 '90 '91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 GROSS HEAT R ATE Thic indicator shows the Gross Heat Rate (GHR) for the reporting month, the year to-date value, and the year end GHR for the previous 3 years.

The gross heat rate for the Fort Calhoun Station was reported as 10,225 BTU /KWH for the month of September 1992.

The year to date gross heat rate was reported as 10,253 BTU /KWH.

Data Source: Holthaus/ Gray (Manager / Source)

Accountabliity: Patterson/Jaworski Adverse Trends: None d

i l g.

l l

_ _ . . _ _ - _ . _,~. - -. . , _ . . . _ . _ . - _ - . , , _ - . _ - , _ _ . _ _ . _.. ._ , - . .

i e

t ow- 4 I

["J 1992 Monthly Theimal Pelformance

-H- 1992 Year to Date Average Thermal Performatice 4

-O- 1992 Fort Calhoun Goal (99 3%) l GOOD,)

-o- 1995 INPO Industry Goal (99 5%)

D- Industry Upper 10% (99 8%)

100%-

D -D - ~ D - D - D -- U --O- D - O- -O D- O a a E- c- T n a a a o-- A 6 A -

o' o D o 0 - -

o- -

o- -

u o o o 99% +

Cycle 14 Refueling 98% -.

Omga 97% - ,

90% , , , , , , , , , , , ,

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec?9 THERMAL PERFORMANCE This indicator shows the Thermal Performar 3 value for the reporting month, the year-to date average thermal performance vah he 1992 Fort Calhoun goal, the 1995 INPO industry goal and the industry met., . e.tue.

The thermal performance value for the reporting month was 99.4%. The year to-date average thermal performance value was 99.5%

The 1992 Fort Calhoun Goal for tiiis indicator is 99.3%. The 1995 INPO industry goalis 99.5% and the industry upper ten percentile value (for the one year period from 7/91 through 6/92) is approximately 99.8%.

Data Source: Jaworski/Popek Accountability: Jaworski/Popek Adverse Trend: None 10

_ .~ , _

t

, Year tw Date Average EAF 100001 666 77 00% - -

56.6 00% ~ C/ClO14 Refuehng Outage

/

40% - E

/ -

/

20%-

I i 7 1

0% , , , , , , , , , , , ,

'89 '90 '91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 EQUIVALENT AVAILADILITY FACTOh This indicator shows the plant monthly Fquivalent Availability Factor (EAF), the year to-date EAF br 1992, and the FAF for the previous 3 years.

The EAF for the month of September was reported as 81%. This figure is the result of a forced outage that began on 8/22/92 when an AC/DC converter falk.t in the Turbine Electro Hydraulic Control system. Pressurizer safety valve RC 142 then opened prior to -

reaching design pressure during a plant transient and trip. The generator was brought on line on 9/5/92.

The EAF for August 1992 was reported as 64.29%. This figure is a result of the 8/22/92 forced outage (described above) and a forced outage on 8/5/92 when a feeder breaker to the 125V de panel Al 41 A failed. The turbine generator was synchronized to the grid on 8/6/92.

The EAF for July 1992 was reported as 34.39%. This figure is a result of the forced outage caused by the loss of an inverter and the subsequent reactor trip on 7/3/92. The plant was brought to 90% power on 7/26/92.

The year to-date average EAF was reported as 47.8% at the end of September.

Data Source: Dietz/Parra (Manager / Source)

Accountability: Patterson Adverse Trend: None 11 l

4 C 1992 Monthly Unit Capabihty Factor

-M- 1992 Year to.Date Average Unit Capateility c ar 3r

-b 1991 Year to Dato Averago Unit C' -. .o . tar GOOD l

-.O- 1991 81992 Fort Calhoun Goals

-/x-- 1995 INPO Industry Goal (80%)  !

- -{~)- Industry Upper 10% (09 G% for a Three Year Average) 100 % - -M-

D C ^ ^

Q--C O E O 4- -M' 2 'N ja ,- -M 38R: Re l'n'gN' 10*/. - Outage

Oct91 Nov Dec Jan Feb Mar ' Apr May Jun Jul Aug Sep02 l UNIT CAPABILITY FACTL.i This indicator shows the plant monthly Unit Capability (UCF) Factor and the 1995 INPO industry goal. UCF is defi
.ed as the ratio d the available energy generation over a given period of time
to the reference energy generation (the energy that co' '4 be produced if the unit were operated

=

continuously at full power under reference ambient cc -) over the same time period, expressed as a percentage.

The UCF was reported as 77.5% for the month of September 1992. Unplanned energy losses for the month were a result of the forced outage that began on 8/22/92 when an AC/DC con.

verter failed in the Turbine Electro Hydraulic Control system. Pressurizer safm valve RC-142 then opened prior to reaching design pressure during a plant transient and trio. The generator was brought on line at 2101 houts on 9/5/92.

The UCF was reported as 62% for the month of AJgust 1992. Unplanned energy losses for the month were a result of the 8/22/92 forced cutage (cescribed above) and the forced outage on 8/

5/92 when a feeder breaker to the 125V de panel Al-41 A failed. The turbine generator was synchronized to the grid on 8/6/92.

The UCF ws reported as 34% for the month of July 1992. Energy losses for the month were due to the forced outage caused by the loss of an inverter and the subsequent reactor trip on 7/

3/92. The plant was brought to 90% power en 7/26/92.

TM year-to-date average unit capability facter was reported as 48.4%.

The 1905 INPO industry goalis 80% and the industry upper ten percentile value (for the three year won tr en 7/89 through 6/92) is approximately 89.6%.

l The 1992 Fort Calhoun goal for Unit Capability Factor is 69.2%. The basis for tus goal is 86 days for the Cyde 14 Refueling Outage,20 daye rampup (10 ful! power equivalent days),

unplanned loss of 11.5 full power equivalent days, and 10 day campup (5 full power equivalent days).

l Data Source: Generation Totals Report & Monthly Operating Report Accountability: Patterson Adverse Tnd: None 12

'~

~

O 1992 tdonthly Unplannoc Capabety Loss Factor

-st - 1992 Year-to Dato Avorago Unrtanned Capabety Loss Factor 80% - lGCODI

-- j.-- 1991 Year to-Dato Avorage L'nplanned Capacaty Loss Factor

-O- 1991 & 1992 Fort Calhoun Goals -

60%-

--6-- 1995 INPO Industry Goal (4.5%)

50% -

--O- Industry Upper 10% (1.85% for a Three Year Average) ,

30% - CyCIO 14 Refuel;ng 20% - ~

Outage y - N- M 10% - I."~*'*- a ~

/

o% !

]~~ -- - -- y T ,

Oct91 Nov Dec Jan Feb PAar Apr FAay Jun Jul Aug Sep92 UNPLANNED CAPABILITY LOSS FACTOR This indicator shows the plant monthly Unplanned Capability Loss Factor (UCLF) , the Fort Calhoun UCLF goal for 1992, and the 1995 INPO industry gcal. UCLF is defined as the ratio of the unplanned energy losses during a given period of time, to the reference energy generation (the energy that could be prodJCed if the unit were operated conti" ously at full power under mference ambient conditions), expressed as a percentage.

=

The UO' F was reported as 22.5% for the month of September 1992. Unplanned energy losses for the month were a result of the forced outage that began on 8/22/92 when an AC/DC con-verter failed in the Turbine Electro Hydraulic Control system. Pressurizer safety valve RC-142 then opened prior to reaching design pressure during a plant transient and trip. The generator was brought on line at 2101 hours0.0243 days <br />0.584 hours <br />0.00347 weeks <br />7.994305e-4 months <br /> on 9/5/92.

The UCLF was reported as 62% for the month of August 1992. Unplanned energy losses for the month were a result of the 8/22/92 forced outage (described above) and the forced outage ,

3 on 8/5/92 when a feeder breaker to the 125V de panel Al-41 A failed. The turbine generator was

$$J synchronized to the grid on 8/6/92.

N0 l, j The UCLF was reported as 66% for the month of July 1992. Unplanned energy losses foi ine month were due to the forced outage caused by the loss of an inverter and the subsequent reactor trip on 7/3/92 and operating at less than full power from 7/23 through 7/31 after bringing

~- the unit back on line.

The year to date average monthly UCLF for 1992 is 18.7%.

The 1995 INPO industry goal is 4.5% and the industry upper ten percentile value (for the three year period from 7/89 through 6/92) is approximately 1.85%.

The Fort Calhoun goal for Unplanned Capability Loss Factor is 4.5%. The basis for this goalis an unplanned loss of 11.5 full power equivalent days and 10 day rampup (5 full power equiva-lent days).

Data Source: Generation Totals Report & Monthly Operating Report Accountability: Patterson Adverse Trend: Non 13

- , m - . _ . _ . _ _ . - _ . . _ . _ _ _ _ ._

e C 1992 PAonthly Pinnned Capataihty Losa f actor

-M- 1992 Year to-Date Average PCLF I I

-t- 1901 Yonr to Data Averogo PCLF -

--C> - 1991 & 1992 Fun Calhoun Goals C}-- Industry Upper 10% (015% for a Threo Year AvoraDO)

I Cyclo 14

' Refuehng ago 100 % _

s W "

w y y eg - m ,

,&CRg , 2 ,

E,2 ,

E,R, Oct91 N ov Doc Jan reta fAar Apr PAny Jun Jul Aug SepO2

PLANNED CAPABILITY LOSS FACTOR This indicator shows the plant monthly Planned Capability Loss Factor (PCLF), the PCLF year-to-date monthly average, and the Fort Calhoun yearly average goals for

- 1991 and 1992. PCLF is defined as the ratio of the planned energy losses during a

, given period of time, to the reference energy generation (the energy that could be pro-duced if the unit were operated continuously at full power under reference ambient conditions), expressed as a percentage.

The PCLF was reported as 0% for the month of September 1992. Energy losses for the -

- month were due to the forced outage that began on 8/22/92 when an AC/DC converter failed in the Turbine Electro Hydreulic Control system. Pressurizer safety valve RC-142

then opened prior to reaching design pressure during a plant transient and trip. The i

generator was brought on line on 9/5/92. These energy losses were classified as unplanned.

The PCLF was reported as 0% for the month of August 1992. Energy losses for tne i month were due to the forced outage on 8/22/92 (described above) and the forced outage on 8/5/92 when a feeder breaker to the 125V de panel Al-41 A failed. The tur-bine generator was synchrc w.ed to the grid on 8/6/92. ,

The PCLF was repurted as 0% for the monia of July 1992. Energy losses for July were

due to the forced outage caused by the loss of an inverter and the subsequent reactor
trip on 7/3/92. These energy losses were classified as unplanned.

The year to-date-average monthly PCLF for 1992 is 32.9%.

Tne 1992 Fort Calhoun yearly average Planned Capability Loss Factor goalis 26.3%.

The basis for this goalis 86 days for the Cycle 14 Refueling Outage and 20 days rampup (10 full power equivalent days). The 1991 goal was 7%

The PCLF industry upper .t n percentile value (for the three year period from 7/89 through 6/92) is 8.55%.

Data Source: Generation Totals Report & Monthly Operating Report Accountability: Patterson Adverse Trend: None 14

O Fue! SohabWty indicator IGOODj

- 1995 INPO Industry Goal (0.5 X 10-3 MicrocuneuGram)

@' -O- 1992 Cort Ca:ho.:n Goai y 4-g 3~ ~~~~

FRI Not Cycle 14 Ava!!able 2- Refuehng for July

- Outage '92 0 6"-% A- -9 [9T""Ohi~~ "9""" ~[9] -[9]

Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 FUEL RELIABILITY INDICATOR ,

The Fuel Reliability Indicator (FRI) was reported as 7.76 X 10-4 microcuries/ gram for the month of September 1992. This value being slightly higher than August's FRI of 6.75 X 10-4 microcuries/ gram can be attributed to:

Reactor coolant not obtaining equilitHum with respect to lodine 131.

The current FRI calculation method does not take into account the contribution of Tramp Activity (fissioning of uranium and plutonium from past fuel f ailures that has plated on internal reactor surfaces) which increases with core life.

7.76 X 10-4 microcuries/ gram is still a favorable FRI value and with no iodine activity spiking present indicates a defect free core.

l The September FRI was calculated using the data from September 12 through 30. In accordance with the INPO definition of steady state operation, the plant was at power levels above 85% during this time and the power levels did not vary more than + or - 5%

for at least 3 days. Only the iodine concentration values from the days that meet this steady state criteria can be factored into the INPO Fuel Reliability Indicator.

Multiple daily isotopic samples were analyzed for the plant restart commencing on September 5th. These analyses showed no iodine activity spikes that would be charac-teristic of leaking fuel rods. The last detected fuel failure was during Cycle 13. The FRl values observed during the later months of Cycle 13 were in the 2.5 X 10-3 to 3.9 X 10-3 microcuries/ gram range.

A Fort Calhoun goal of 7.5 X 10-4 microcuries/ gram will be utilized in 1992. Fo1 Cal-houn recognizes the INPO 1995 U.S. industry goal of 5.0 X 10-4 microcuries/ gram and will revise the annual FRI goal accordingly.

l The FRI was not applicable while the plant was shutdown for the refueling outage in February, March and April, and was not reported during those months.

Data Source: Holthaus/Guliani Accounto :ty: Patterson/Spijker Adver. e Trend: None 1s l

1 4

O Monthly Personnel Rad.abon Exposure Pesonnel Cumulative Radiation Exposure (Porson Rom)

--O- Fort Calhoun Annual Gosi(250 Person. Rem) 1995 INPO Industry Goal (185 Person Rem) 400 -

-C} - Industry Upper 10% (115.6 Person-Rem for a Three Year Avorage) lGo0D1 300- p O O O O O O O O >^ O O O fd22 200-f4,# 4 A A b --A b - --4 A A 6 4

un MM 93.4

  • 00 -
-- V

'd 52 1  ; . -

?

0 i i i i

, '89 '90 '91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 COLLECTIVE RADIATION EXPOSURE During September 1992, 5.44 person-rem was recorded by TLDs worn by personnel while working at the Fort Calhoun Station. The year-to-date exposure is 245.32 person-rem.

The Fort Calhoun goal for personnel radiation exposure (cumulative) during 1992 is 250 person' rem. Cumulative radiation exposure for the Cycle 14 Refueling Outage was 216.899 percon-rem, which exceeds the outage goal of 210 person-rem. The goal was not achieved because the outage was longer than anticipated and there was more exposure than expected due to the stuck reactor vessel stud and the thermal shield inspection.

The 1995 INPO industry goalis 185 person-rem per year. The industry upper ten percentile value (for the three year period frorn 7/89 through 6/92) is approximately

, 115.6 person-rem per year. The three year average for Fort Calhoun Station from 7/89 through 6/9': is 194.3 person-ram per year.

Data Source: Patterson/ Williams (Manager / Source)

Accountability: Patterson/Lovett Adverse Trend: None SEP 54 16

. _ . ~ _

4

Cumulative Dry Active Waste Sent For Processing (in cubic feet) 25000-20000- - - -

15000-10000-6000-0 - , , , , , , , , , , , ,

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 O Radioactive Waste Buried This Month (in cubic feet)

Cumulative Radioactive Waste Buried

-O- Fort Ca!houn Goal For Waste Buried (3,000 cubic feet)

-e- 1995 INPO in0astry Goal (3.884 cubic feet)

- D- Industry Upper 10% (2.077.9 cubic feet) a a a a i a a a a a a a 3000 - O O O O O O O O O O O O

~

1334 1500 -

w. N i 0 - r- i n

'90 '91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 Year end Total VOLUME OF LOW LEVEL SOLID RADIOACTIVE WASTE The upper graph shows the volume of radioactive oil and dry radioactive waste sent for processing. The current increase in the volume shipped is the result of a concerted effort to eliminate the backlog of resins in anticipation of higher storage fees for 1993.

The lower graph shows the volume of the monthly radioactive waste buried, the cumula-l tive annual total for radioactive waste buried, and the year end totals for radioactive waste buried the previous 2 years.

Cumulative amount of solid radwaste shipped off-site for processing (cubic f eet) 19,520.0 Amount of solid radwaste shipped off site for processing during September (Cubic feet) 0.0 Volume of solid radioactive waste which was buried during September (cubic feet) 438.3 Cumulative volume of solid radioactive waste buried in 1992 (cubic feet) 1,306.4 Amount of solid radioactive waste in temporary storage (cubic feet) 120.3 The 1992 Fort Calhoun goal for the volume of solid radioactive waste which has been buried is 3,000 cubic feet. The 1995 INPO industry goalis 110 cubic meters (3,884 cubic feet) per year. The industry upper ten percentile value is approximately 58.85 cubic meters (2,077.9 cubic feet) per year.

Data Source: Patterson/Breuer (Manager / Source)

Accountability: Patterson/Bilau Adverse Trend: None SEP54

( 17 l

l 4

1992 Disabling injuryllliness Frequency Rate

--M- 5 Year Average Disabling injuryllliness Frequency Rate l GOODI 1.6 - d aboun M (03) j 1995 INPO Industry Goal (0.5) 1.2 -

1-0.8 - ,

s A  % d' '

'A A u u M

u u u u% -

u u u A

A 0.4 -

0 0 O- 0 0 0 0 0 0 O- 0 0 0.2 -

0l ); , is , , , , , , , , , , ,

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 DISABLING INJURY /lLLNESS FREQUENCY RATE (LOST TIME ACCIDENT RATE)

This indicator shows the 1992 disabling injury / illness frequency rate. The 5 year aver-age (from 1987 through 1991) disabling injury / illness frequency rate is also shown.

The disabling injury / illness frequency rate for January through September 1992 was 1.12. There were no disabling injury / illness cases reported for the month of September.

The total number of lost time accidents that have been reported during 1992 is 5. The 1992 disabling injury / illness frequency rate goal was set at 0.30. The 1995 INPO Indus-try goal is 0.50.

The disabling injury / illness frequency rate for the past twelve months is 1.03.

> The industry upper ten percentile disabling injury / illness frequency rate for the twelve month time pe;.od from 7/89 through 6/92 is approximately 0.12.

Xfgr Year-End Rate 1989 0.4 1990 0.5 1991 0.4 Data Source: Sorenson/Skaggs (Manager / Source)

Accountability: Patterson/ Richard Adverse Trend: None SEP 25 & 26 18 l

l

l 0 Tnermai output

--O- Fort Calhoun 1495 MW Goal

- Tech Spec 1500 MW Um:t 1500-

< 3 1490-
v g- >

i y '

,y(

1480 - kg p 2Nb@

g ,,;w, ~

~;m ,x .,

s

  1. qQs +p;gfp ,

j? j j$ f ' *'

[1470- ,

E aw w. Qk a W. -w<

,. lam.W, ,

. mV y' ygg' g 1 a .s - k:r +

ga u ., . ,wy .

1450 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 DAILY THERMAL OUTPUT

, The above thermal output graph displays the daily operating power level during Sep-

! tember 1992, the 1500 thermal megawatt average technical specification limit, and the 1495 tharmal megawatt Fort Calhoun goal.

The daily thermal output chart for September reflects the forced outage that began on 8/

22/92 when an AC/DC convener failed in the Turbine Electro Hydraulic Control system.

Pressurizer safety valve RC-142 then opened prior to reaching design pressure and the plant tripped. The generator was brought on line on 9/5/92. Later in the month power was held at a nominal 1493 MWt due to in-core alarms.

Fort Calhoun Station is currently operating at a level of Peak Linear Heat Rate such that, if in-core detector alarm monitoring is not maintained, power must be reduced below 30% within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Data Source
Holthaus/ Gray (Manager / Source)

Accountability: Patterson/Trausch Adverse Trend: None l 19 l

. _ . . __ _ .- __ . . ~ . _ _. _

4 9

Equipment Forced Outage Rato 2- -O- 1992 Fort Calhoun Goal 1.5 -

i l 1-0.53 0.5 l

0.13 l l h fM C O O O -C O O O O O O O M  : .? d'E , o

  • 09 '90 '91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dac92 j EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS The equipment forced outage rate per 1,000 critical hours was 1.4 for the months from -

, January through September 1992.

f he i equipment forced outage that began on 8/22/92 (described below) continued into September. The generator was brought on-line on 9/5/92.

The following two equipment forced outages occurred in August: 1) on 8/5/92 a feeder breaker to the 125V de panel Al 41 A failed. The turbine generator was synchronized to

the grid on 8!6/92; 2) on 8/22/92 an AC/DC converter failed in the Turbine Electro
Hydraulic Control system. Pressurizer safety valve RC 142 then opened prior to reach-ing dnsign pressure during a plant transient and trip. The plant was shutdown for the remainder of the month.

4 4 There was one equipment forced outage during July due to the loss of an inverter and the subsequent reactor trip on 7/3/92.

There was one equipment forced outage during June due tc a dropped control rod. The

rod was dropped at 2305 or. 5/31/92 and reactor shutdown commenced at that time.

The generator was taken off-line at 0234 on 6/1/92 and was brought back on-line at

0852 on 6/2/92.-

There was one equ:pment forced outage during May, This equipment forced outage occurred on May 14 when the turbine generator tripped on a false high level moisture separator trip signal which caused a simultaneous reactor trip.

The 1992 Fort Calhoun goal for this indicator is 0.2.

1 Data Source: Monthly Operations Report & Plant Licensee Event Reports (LERs)

Accountability: Patterson/ Jaworski

. Adverse Trend: None 20

Operations 1992 Budget ($ Million) 80 -M- 1992 Cumulative Total ($ fMiion)

! 00- #

40- -

.str l

20- p . . -

., O Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 Maintenance 1992 Budget ($ Mil l ion)

. 40-

! 30- -H- 1992 Cumulative Total ($ Million) 20-

_ , .__ n -w 10- #4 "

0 Wf i

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 OPERATIONS AND MAINTENANCE BUDGET The Operations and Maintenance Budget Indicator shows the budget year to-date as well as the actual expenditures for operations and maintenance for the Fort Calhoun Station.

The budget year to-date for Operations was 52,127,600 dollars for September 1992 while the actual cumulative expenditures through September totaled 47,237,037 dollars.

The 1992 year-end budget for operations has been revised to 62,009,800 dollars, which

is a reduction of 4,651,000 dollars.

The budget year-to-date for Maintenance was 16,055,100 dollars for September 1992 while the actual cumulative expenditures through September totaled 14,556,122 dollars.

The 1992 year-end budget for maintenance has been revised to 19,088,600 dollars, which is an increase of 934,000 dollars.

i Data Source: Gleason/ Parent (Manager / Source)

, Accountability: Scofield I Adverse Trend: None l

l l 21 l

Documents Scheduled for Review 700-9 Documents Reviewed Overdue Documents c00- 3 1:

9 4

500 -

400-A 300- .

T {

c . -

200- -

f 7 'f j

- :p  : 9

, 1 Y l  ?

.b ;b  : Ji S 100-

]

r

_7 7

-2 j:

tj

.x

}

2

}:-

_ r __ c 2 >; g %_ -:p -. 2- 3; :A 2 '< 9 Z @  %  ? ,% y i 0

L " ] ' 1

  • 1 # '

D ^ ~ #

4 i i l i i 6 1 1 6 i i Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 DOCUMENT REVIEW f This indicator shows the number of completed, scheduled, and overdue (greater than 6 l months past the scheduled due date) biennial reviews for the reporting month. These

! document reviews are performed in house and include Special Procedures, the Site 4

Security Plan, Maintenance Procedures, Preventive Maintenance Procedures, and the l Operating Manual.

l During September 1992 there were 242 document reviews completed while 15 docu-ment reviews were scheduleri. At the end of September, there were no (0) document reviews overdue.

In addition, during the month of September there were 77 new or renamed documents reviewed. These new or renamed documents will need to be reviewed again in 1994 Data Source: Patterson/McKay (Manager / Source)

Accountability: Patterson/Jaworski l

Adverse Trend: None SEP 46 22 i

h

4

@ Number of Failures /20 Demands -n- Trigesr Values for 20 Demands O Number of Failures /50 Demands -V- Trigger Values for So Demands O Number of Failures /1oo Demands -

- Trigger Values for 100 Demands 8-lGOODI G-

+

y y p. y y  ;~ y y y " y +7 4 4 4 4 4 4 4 4 4 4 4 4 4- - - - - - - - - - - - -

E .

3 g_q--g 5-4 3-- = = - -g --g 22 22 22 2 2 2 2- -

, 1 1 1 1 1 1 1 1

$ $  ? ':  ? o o o o o o o o , , , , , , , , , , , ,

Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 EMERGENCY DIESdL GENERATOR UNIT RELIABILITY This bar graph shows three monthly indicators pertaining to the number of failures that were reported during the last 20,50, and 100 emergency diesel generator demands at the Fort Calhoun Station. Also shown are trigger values which correspond to a high level of confidence that a unit's diesel generators have obtained a reliability of greater than or equal to 95% when the failure values are below the corresponding trigger val-ues. The Fort Calhoun 1992 goalis to have fewer failures than these trigger values.

The demands counted for this indicator include the respective number of starts and the

, respective number of load-runs for both Diesel Generators combined. The number of l start demands includes all valid and inadvertent starts, including all start-only demands and all start demands that are followed by load-run demands, whether by automat!c or manualinitiation. Load-run demands must follow successful starts and meet at least one of the following criteria: a load-run that is a result of a realload signal, a load-run test expected to carry the plant's load and duration as stated in the test specifications, and a special test in v"Tich a diesel generator was expected to be operated for a mini-mum of one hour and to be loaded with at least 50% of design load (see exceptions and other demand criteria in the Definition Section of this report).

The demand failure which occurred during the month of August 1991 for DG-2 was due to a seal failure on the jacket water pump.

Data Source: Jaworski/Ronning (Manager / Source) l Accountability: Jaworski/Ronning l Adverse Trend: None 23 l

l l

O DG 1 Failures /25 Demands IGOODI O DG 2 Failures /25 Demands 5- -CH Failure Trigger Value for 25 Demands / Fort Calhoun Goal 4- C O T O O O O O O O O O 3-2 2 2 2 2- -

1 1 1 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 f. 0 g

1 6 i l i 6 4 I i I i 1 Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 DIESEL GENER ATOR RELIABILITY (25 DEMANDS)

This indicator shows the number of failures experienced by each emergency diesel g generator during the last 25 start demands and the last 25 load run demands. A trigger value of 4 failures within the last 25 demands is also shown. This trigger value of 4

, failures within 25 demands is the Fort Calhoun goal for 1991.

, it must be emphasized that in accordance w'th NUMARC criteria, certain actions will take place in the event that any one emergency diesel generator experiences 4 or more failures within the last 25 demands on the unit. These actions are described in the Definitions Section of this report. A Standing Order has been drafted for the Fort Cal-houn Station to institutionalize and formally approve / adopt the required NUMARC ac-tions.

Diesel Generator DG-1 has not experienced any failures during the last 25 demands on the unit.

Diesel Generator DG-2 has experienced one failure during the last 25 demands on the unit. An air damper roll pin failure occurred in July 1991.

Data Source: Jaworski/Ronning (Manager / Source)

Accountability: Jaworski/Ronning Adverse Trend: None 24

4 9

Planned Hours of Diesel Generator No. 2 Unavailability n Unplanned Hours of Diesel Generator No. 2 Unavailabi!ity

@ Estimated Hours of Diesal Generator No. 2 Unavailability 50- E Planned Hours of Diesel Generator No.1 Unavailability f

E C Unplanneu Hours of Diese! Generator No.1 Unavailability a ~

3

$0 , , , , , , , , , , ", ,

Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 20 -

j' -+-- Cumulative Hours of DG 1 Unavailability for 1992 B

$~

E

-@- Cumulative Hours of DG-2 Unavailability for 1992

$ 'U ~

g

?. 41

'? 6 y 5-0  ? ,  ? ,  ? ,  ? ,  ? i , , , ,

Jan92 Feb Mar Apr May Jun Jul Aug Sep92 DIESEL GENERATOR UNAVAILABILITY This indicator provides a monthly illustration of diesel generator unavailability. The top graph shows the diesel generator planned, unplanned, and estimated unavailable hours for DG-1 and DG-2 for each month. The lower graph shows the cumulative hours of unavailability for each diesel generator for the year to-date.

During September 1992 there were no (zero) hours of planned or unplanned unavail-ability for DG-1 and DG-2.

The 1992 Fort Calhoun goalis a maximum of 210.82 hours9.490741e-4 days <br />0.0228 hours <br />1.35582e-4 weeks <br />3.1201e-5 months <br /> of unavailability for each diesel generator.

Data Source: Jaworski/Ronning (Manager / Source)

Accountability: Jaworski/Ronning Adverse Trend: None 25

~

O June 1992 Outstanding MWOs O July 1992 Outstanding MWOs O August 1992 Outstanding MWOs 300- September 1992 Outstanding MWOs 1

200 -

k 5

~

l 100-h -

~

'fg

[$ ,,

M g -

%k XM SM-w XM %V -

O b,f i

(fA hf,',

i h l i

Th 0 3 Months 3 6 Months 6 Months 912 Months >12 Months AGE OF OUTSTANDING MAINTENANCE WORK ORDERS (CORRECTIVE NON-OUTAGE)

This indicator shows the age of corrective non-outage maintenance work orders (MWOs) remaining open at the end of the reporting month.

A review of maintenance work order classifications was completed during September for all non printed MWO packages. These classification changes were in accordance with S. O. #M-101. This has had some effect on lowering the backlog classified as corrective.

Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/ Bobba Adverse Trend: None 20 l

June 1992 0 July 1992

' 400 383 376 August 1992 330 - .. September 1992 300 -

258 264 l 250 - -

,;, 222 200 - 'U 3

i hf 165

, 150 - :h

/',

N 101 M3 M0 3'

100- 1'-

79

/,- ,'.

60 64 49 50-  : ':<:-

- -- 42 y; 'y ,-[;

21 20 30 17

v,
,. . // ..,

n l l i i i i i Tota! Open MWOs Open MWOs>3 Total Open Safety Open Safety Open High Priority months old Re!ated MWOs Related MWOs > 3 MWOs Months Old MAINTENANCE WORK ORDER BREAKDOWN (CORRECTIVE NON-OUTAGE)

This indicator shows the total number of corrective non-outage MWOs remaining open

at the end of the reporting month, along with a breakdown by several key categories.

A review of maintenance work order classificM!:ni was compd:d during September

, for all non-printed MWO packaoce i ntce classification changes were in accordance with S. O. #M-100 Tin has nad some effect on lowering the backlog classified as correctirc.

The 1992 goal for this indicator is to have less than 350 total corrective non-outage maintenance work orders remaining open.

Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/Bobba Adverse Trend: None SEP 36 27

4 i

c j -

Corrective Maintenance Backlog > 3 Months Olci -

J IT603 4

80%- y l Cycle 14 -

Refueling F j

60% - Outage

{ {

si 74 s^s

a. g-

,i -

k <> e i. . b' y If3 4

s ,1@ If @

' 40%- , .' ;p g $ g,

, - , a N Y sa; M

i. -

1

  1. . q;
M hi '

s Tj)$

^

fh5 g (gh g g gg

- e:- ,

7 -

pg

^

j 20%- - A M $:. . eg 5 $ $

E Q

! i ' '

d "

M 6 4 E j $ "

4* ,;; A ( [6 ff,i $9 fe 41.

yg  %-'

. s ~ g g .

, e-l $

wt 2

, 9 s

m ft Mt h g M$

n 4{

% P,

, 0%

Oct91 Nov Dec Jan Feb
  • Mar Apr May Jun .Jul Aug Sep92 l ' Programmatic change to reflect change in non outage enteria; i

. CORRECTIVE MAINTENANCE BACKLOG GREATER THAN 3 MONTHS OLD i (NON-OUTAGE) l This indicator shows the percentage of open corrective non-outage maintenance work

orders that were greater than three months old at the end of the reporting month.

!. The percentage of open corrective non outage maintenance work orders that were greater than three months old at the end of September 1992 was reported as 63.95%

i A review of maintenance work order classifications was completed during September-

! for all non printed MWO packages. T hese classification changes were in accordance

~

i with S. O. #M-101. This has had some effect on lowering the tiacklog classified as

- corisctive.

Data Source: Patterson/Schmitz (Manager / Source) 1- Accountability: Patterson/ Bobba .

Adverse Trend: None

'i 4

j SEP 36 4

26

O Ratio of Preventive to To.: : Maintenance

-- O-- 1931 & 1992 fcn Ca'houn Non OAage Goals Ai Cycle 14 l GOOD l 90% - Refue!!ng Outage 80% -

70% -

l 60% - C O [

~~~~

a 50% - -

40% -

30%-

20%

Oc:91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 Y

l RATIO OF PREVENTIVE TO TOTAL MAINTENANCE This indicator shows the ratio of completed non outage proventive maintenance to total comp!cted non outage maintenance.

The ratio cf preventive to total maintenance was 50.57% in September 1992.

The 1992 Fort Calhoun goalis to attain a ratio of preventive to total maintenanc) non-outage greater than 65%. The 1991 Fort Calhoun goal was to attain a ratio of preven-tive to total maintenance greater than 60%.

Accountcbility: Patterson/ Bobba Data Source: Patterson/Schmitz (Manager / Source)

Adverse Trend: None SEP 41 29

4 4%- O Preventive Maintenance items Overdue lGOODI

- O - 1991 & 1992 Fort Calhoun Goals Y 3%-

i 2%-

Cycle 14 Refueling 1%- C O -

n

'o 'o- -

d O O -o g

0%

Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 PREVENTIVE MAINTENANCE ITEMS OVERDUE The purpose of this indicator is to monitor progress in the administration and execution of preventive maintenance (PM) programs. A small percentage of preventive mainte-nance items overdue indicates a station commitment to the preventive maintenance program and an ability to plan, schedule, and perform preventive maintenance tasks as programs require.

During September 1992,523 PM iteTs were completed. 2 PM items (0.38 % of the total 523) were not completed within the allbwable grace period.

- The 1992 Fort Calhoun ' calis to have less than 0.5% per month of the preventive maintenance items oveoue. The 1991 Fort Calhoun goal was to have less than 1% per month of the preventive maintenance items overdue.

Data Source: Patterson/Brady (Manager / Source)

Accountability: Patterson/ Bobba Adverse Trend: None SEP 41 30

Control Room Instruments Repairable On Line 70- O Total Number of Control Room instruments Out of Service

-O- 1991 For1 Calhoun Goal For Total Out of Service Instruments 60- --O- 1992 Fort Calhoun Goal For Total Out of-Service Instruments 50- C O O O O O O O O 40-30-20-IME n ffs

'b h b 7 !b 10- ['%'i tw

$'y zy

M aa E

te

.wa ih~ $

zy - .~

%9,  ;%9 xy .e+ w/

ff: '

gf .y

,a-

/g.

0 i i i i i i t i i i i i Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 NUMBER OF OUT OF SERVICE CONTROL ROOM INSTRUMENTS This indicator shows the number of out of service control room instruments, the number of instruments repairable during plant operations (on line), and the 1991 Fort Calhoun goal.

There was a total of 12 out-of service control room instruments at the end of September i 1992. 3 of these instruments require a plant outage to repair. No instruments were added and none were completed during the month.

l The revised 1992 Fort Calhoun goalis to have less than 50 out-of service control room I instruments. The 1991 Fort Calhoun. goal was to have less than 14 out-of-service l control room instruments.

l l

l Data Source: Patterson/Spilker (Manager / Source)

Accountability: Patterson/ Bobba Adverse Trend: None 31

[] Maintenance Overtimo

-.K- 12 Month Average Maintenance Overtime 4

70% -

1 1991 & 1992 Fort Calhoun "On Une" Goats co a,'. -

Cycle 14

'lefueling 50% - Outage a

40% - _

4 j 30%-

O O-20%- , .x y 4_ -. y--- x- -X' 10%- y__y ,

  • R O O -

Q _Q 0%

Oct91 Nov Dec Jan Feb Mar A pr May Jun Jet Aug Sep92 M AINTEN ANCE OVERTIME The Maintenance Overtime Indicator monitors tim sbility to perform the desired mainte-nance activities with the ahotted resources. Excessive overtime indicates insufhcient resource allocation and can lead to errors due to fatigue.

The percent of overtime hours with respect to normal hours was reported as 8.57%

during the mcnth of September 1992. The 12 month average percentage of overtime hours with respect to normal hours was reported as 10.17% Both July and August overtime were high due to two long term (>2 weeks) forced outages.

The 1992 Fort Calhoun goal for the "on-line' percentage of maintenance overtime hours

. worked is a maximum of 10%.

Data Source: Patterson/Schmitz (Manager / Source)

Accountat,ility: Patterson/ Bobba Adverse Trend: None 32

- .- -~ .-. _-. - .-- _ .

O Open irs Related to the Use of Procedures (Maintenance)

O Closed irs Related to the Use of Procedures (Maintenance)

, O Procedural Noncompliance irs (Maintenance) i Cycle 14

. Refueling age 10-8 l

5-4 3 3-2 2 ,' 2 1 1 1 1 ,- 1 , 11 1 11 1 1 0 ,

0 ,

0 0 0 0 0 , ,

0 0 0 0 >

00 00 i i i i i i i i i i i Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)

This indicator shows the number of open Maintenance incident Reports (irs) that are related to the use of procedures, the number of closed irs that are related to the use of procedures, and the number of open and closed irs that received procedural noncom-pliance cause codes for each of the last twelve months.

l There were no procedural noncompliance incidents for maintenance reported for the

, month of September 1992.

! Data Source: Patterson/McKay (Manager / Source)

. Accountability: Patterson/Bobba Adverse Trend: None SEP 15,41 & 44 f

33

~. - - - - - .

l O Completed Scheduled Activities (EM)

C Fort Ca'houn Goal 1

100 % -

~

90% - -

80%- C O O O' O O O i 70% - - /

4 60% -

k ,.

50% -

s 40% - a l g  ;

l 30% - 47

^

) 20% - s w- , ,

p.

. ~

10% -

T \

g 0% -

- 7/4 7/11 7/18 7/25 8/1 8/8 8/15 8/22 8/29 9/5 9/12 9/19 9/26 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVIT!ES

(ELECTRICAL MAINTENANCE)

This indicator shows the percent of the number of completed maintenance activities as compared to the number of scheduled maintenance activities concerning Electrical Maintenance. Maintenance activities include MWRs, MWOs, STs, PMOs, calibrations, and miscellaneous maintenance activities.

Data for this indicator was not available for the month of July 1992 d ce to the forced 1

outage from 7/3 through 7/23.

Data for this indicator was not trackeo during the Cycle 14 Refueling Outage.

3 The Fort Calhoun Station goal for this indicator is 80%

! Reoortino Month Comoteted Scheduled Activities Week 1 87 %

Week 2 93%

l Week 3 95%

Week 4 94 %

Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/Bobba Adverse Trend: None SEP 33 4

34

l. .

O Completed Scheduled Activities (PE)

--O-- Fort Calhoun Goal 100 % -

90% - _ _ _

80% - o -

o -

o o- 6 -

o -o-o ;::

m  ; ,

70% - +

60%- U:

50% - .

I a 40% - g 30% - ~

+. p n 20% - ic 6 o w
  • 10%- A N ",

S, 7/4 7/11 7/18 7/25 8/1 8/8 8/15 8/22 8/29 9/5 9/12 9/19 9/26 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (PRESSURE EQUIPMENT)

This indicator shows the percent of the number of completed maintenance activities as compared to the number of scheduled maintenance activities concerning Pressure Equipment Maintenance. Maintenance activities include MWRs, MWOs, STs, PMOs, calibrations, and miscellaneous maintenance activities.

Data for this indicator was no+ available for the month of July 1992 due to the forced outage from 7/3 through 7/23.

Data for this indicator was not tracked during the Cycle 14 Refueling Outage.

The Fort Calhoun Station goal for this indicator is 80%.

Reoortino Month Comoteted Scheduled Activities Week 1 89 %

Week 2 87 %

Week 3 - 81 %

Week 4 81 %

- Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/Bobba Adverse Trend: None SEP 33 35 l

O Cov.,1oted Gehoduled Activitios (CM)

-O- Fcrt Calhoun Coal 100 % - -

00*4 - -

80% - O O O O-- O O O- O

'~

70% - ~

G0%- E *

~

50% -- .

40% - ,

aow -

l 20% - '

10% - s "1 0%

7/4 7/11 7/18 7/25 O/. D 'O 8/15 B/22 C '29 9/5 9/12 9/19 9'20 I PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (GENERAL MAINTENANCE)

This indicator shows the percent of the number of completed main'enance activities as compared to the number of scheduled maintenance activities concerning General Main-tenance. Maintenance activities include MWRs, MWOs, STs, PMOs, calibrations, and miscellaneous maintenance activities.

3 Performance was below the goal during the month of September 1992 because work

! scope changes were higher than anticipated and weather holds were necessary for many outside work activities.

Data for this indicator was not available for the month of July 1992 due to the forced outage from 7/3 through 7/23.

Data for this indicator was not tracked during the Cycle 14 Refueling Outage.

The Fort Calhoun Station goal for this indicator is 80%.

Reoorting Month Comoteted Scheduled Activities Week 1 83%

Week 2 67 %

Week 3 71 %

Week 4 90%

Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/Bobba Adverse irend: None SEP 33 36

, - ~ _ . - . -

O Completed Scheduled Activities (Mt"

--O- Fon Calhoun Goal 9 0's. - _ y -

{a m ..-  :- -

80% - O -

O O- O -O -

O -

O -

O

~ ~

70% - "

60% -

D ..

50% - s

^

4 0% - ' '

g 30% - ,

20*/. -

^

10 4-

-.v j 7/4 7/11 7/18 7/25 8/1 8/8 8/15 8/22 8/29 9/5 9/12 9/19 9/26 PERCENT OF COMPLETED SCHEDULE' MAINTENANCE ACTIVITIES (MECHANICAL MAINTENANCE)

This indicator shows the percent of the number of completed maintenance activities as compared to the number of scheduled maintenance activities concerning Mechanical Maintenance. Maintenance activities include MWRs, MWOs, STs, PMOs, calibrations, and miscellaneous maintenance activities.

Data for this indicator was not available for the month of July 1992 due to the forced outage from 7/3 through 7/23.

Data for this indicator was not tracked during the Cycle 14 Refueling Outage.

The Fort Calhoun Station goal for this indicator is 80%.

Reoortina Month Comoleted Scheduled Activities Week 1 96 %

Week 2 92%

Week 3 90%

Week 4 93%

Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/Bobba Adverse Trend: None SEP 33 37

i O compieted senedu!ed Activities (IC)

--O-- Fort Calhoun Goal 90% - _

7 .

}v ] w-80% - O --O.- O O- O -O D- d, 70% - ,  ?> 7' .%

^ '

60%- /

s t 50%~

s-40% - ' '

. f.

  • h h'

^

30% - o ^

! 20% - - T 1 b

% h 10% -

Q 1 -

4" 0%

7/4 7/11 7/18 7/25 8/1 8/8 8/15 8/22 8/29 9/5 9/12 9/19 9/26 a

i PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (INSTRUMENTATION & CONTROL)

This indicator shows the percent of the number of cornpleted maintenance activities as

compared to the number of scheduled maintenance activities concerning Instrumenta-tion & Control Maintenance activities include MWRs, MWOs, STs, PMOs, calibrations, and miscellaneous maintenance activities.

Data for this indicator was not available for the month of July 1992 due to the forced outage from 7/3 through 7/23.

Data for this indicator was not tracked during the Cycle 14 Refueling Outage.

The Fort Calhoun Station goal for this indicator is 80%.

Reoortina Month Comoteted Scheduled Activities Week 1 90%

Week 2 89 %

Week 3 93 %

Week 4 93%

Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/Bobba Adverse Trend: None SEP 33 38

3-O Nurnber of Missed STs Resulting in LERs 2-5 1-0 0 0 0 0 0 0 0 0 0 0 0 0 0 i i i i i i i i i i i i i i i

'90 '91 Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 NUMBER OF MISSED SURVEILLANCE TESTS RESULTING IN LICENSEE EVENT REPORTS This indicator shows the number of missed Surveillance Tests (STs) that result in Lic-ensee Event Reports (LERs) during the reporting month. The graph on the left shows the yearly totals for the indicated years.

During the month of September 1992 there were no missed STs that resulted in LERs, The 1991 & 1992 Fort Calhouri coals for this indicator are zero.

Data Source: Monthly Operating Report & Plant Licensee Event Reports (LERs)

Accountability: Patterson/Jaworski Adverse Trend: None SEP 60 & 61 39

_____ _ _ _ _ _ _ _ _ . I

[ l

@~ -N- # cf Component Categones -A- Total a of Categones 35- .,_4_ a et Apphcaten Categones g 30~ i

-A g  !

  • 82s- s- u -+-c' b a On A N /

h p W  % 'k 3

i 2 Yo~- .Nw m-=-*-*-*~ss , A :: , w /

sny ,g&mE 5-

~~

i i i i i i i i i l i i i 1 1 i i I A91 IA J J A S O fJ D J92 F lA A lA J J A S92

O wear out'A* o O 0:her Devices l [1] IAanuta:tunng Defect O 'Aaintenance rtesting

^ O Engineenng Design O Error 55.0.[

i

_ -- Percerit of Total Failures During the m e.7, Past 18 Months M^ s.3, l

10.0%Q _j E0*/.

COMPONENT FAILURE ANALYSIS REPORT (CFAR)

SUMMARY

The tcp chart illustrates the number of component categories, application categories l and total categories in which the Fort Calhoun Station has significantly higher (1.645 standard deviations) failure rates than the industry failure rates during the past 18 months (from April 1991 through September 1992). Fort Calhoun Station reported a higher failure rate in 12 of the 87 component categories (valves, pumps, motors, etc.)

j during the past 18 months. The station reported a higher failure rate in 12 of the 140 application categories (main steam stop valves, t...xiliary/ emergency feedwater pumps, control element drive motors, etc.) during the past 18 months.

The pie chart depicts the breakdown by INPO cause categories (see the " Definitions" section of this report for descriptions o these categories) for the 176 failure reports that were submitted to INPO by Fort Calhoun Station during the past 18 months.

Data Source: Jaworski/ Dowdy (Manager / Source)

Accountability: Jaworski/ Dowdy Adverse Trend: None i 40

-n- Orcater Than One Failure 40- -+- Greater Than Two Failures

-o- Greater Than Five Failures 30-  %

25 - E E 20 -

15-v-

10- ,p+--+  ;% y e e s-a a e a

,M myst" Oct91 Nov Dec Jan Feb fAar Apr fAay Jun Jul Aug Sep92 NUMBER OF NPRDS MULTIPLE FAILURES This indicator shows the number of multiple NPRDS reportable failures over the preced-ing eighteen snonths sorted by component manufacturer and model number. The indica-tor is divided into three parts: manuf acturer model numbers with more than one failure in eighteen months, manufacturer model numt,ars with more than two failures in eigh-teen months, and manufacturer mudel numbers with more than five failures in eighteen months.

During the past eighteen months, there were 32 model types that had more than one failure in eighteen months.12 of these had more than two failures. 4 component types,

, General Electric 50 570 01 power supplies, Gaulin P18 pumps, Byron Jackson 28RXL l pumps and Jayco incorporated 150 valves had more than five failures. The model types

with more than two failures are
the OSPDS (3 f ailures), S P Manufacturing DA3R valve operators (3 Failures), General Electric 50 570 power supplies (4 failures). General l Electric 50 570 01 power supplies (9 failures), Fau"< Type Y couplings (3 failures),

l Byron Jackson 28 RXL pumps (7 failutas), Gaulin P18 pumps (8 failures), Dresser 19750 valves (3 fanures), Jayco incorporated 150 valves (6 failures), Norgren 11-024 0 l

t valves (3 failures), Copes Vulcan D 100 60 valves (3 f ailures) and Fisher Controls 657-60 valve operators (3 failures).

l Increases in the number of model numbers with more than one failure is mostly due to failures found during the Cycle 14 Refueling Outage.

Data Source: Jaworski/ Dowdy (Manager /Sourco) i Accountability: Jaworski/ Dowdy Adverse Trend: No..e

-+- Components With More Than One Failure lGDODl

-X-- Components With More Than Two Failures l 20- l 1

15-

/

10-4 5-

.Y

\x u u ,

1 s

'N< , x 0

Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 MAINTENANCE EFFECTIVENESS Ttw Maintenance Effectiveness Indicator was developed fc' lowing guidelines set forth by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Opera-

> tional Data (NRO/AEOD). Tne NRC/AEOD is currently developing and verifying a maintenance effectiveness indicator using the Nuclear Plant Reliability Data System (NPRDS) component failures.

This indicator has been revised to show the number of NPRDS components with more than one failure during the last eighteeri months and the number of NPRDS compo-nonts with more than two failures during the last eighteen months The number of NPRDS components with mnre than two failures in an eighteen month period should indicate the effectiveness of plant maintenance.

During the last 18 reporting months there were 19 NPRDS components with more than 1 failure, 2 of the 19 had more than two failures. The tag numbers of the components with more than two failures are CH 1 A and CH 1B.

Data Source: Jaworski/ Dowdy (Manager / Source)

Accountability: Patterson/Bobba Adverse Trend: None 42

, ,.~-,,__g. , , - . _ - . -

10 10-Calcula'ed Check Vane Fai!ure Rate per !A!! ion Component Hours 9-Industry Che:k Va!ve Failure Rate per tuon Component Hours 8-

-O- Fort Calhoun Goal 7-l GOOD l 0-4 o 5-g 4-3- _3 -owa. . a 2- O -O O O O O-us O C C D 1 1 1-i i i i 0

'89 '90 '91 Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 Check Va!vo Failures CHECK VALVE FAILURE R ATE This indicator shows the Fort Calhoun check valve failure rate, the Fort Calhoun goal and the industry check valve failure rato. This rate is based upon failures during the

previous 18 months. The check valve failures at Fort Calhoun Station for the previous three ; ears are shown on the left.

The data for the industry check valve failure rate is three months behind the reporting month due to the time involved in collecting and processing the data.

For June 1992, the Fort Calhoun Station reported an actual check valve f ailure rate of 6.19 E 7, while the industry reported an actual fait-e rate of 2.91 E 6. At the end of September 1992, the Fort Calhoun Station repcLq.i ' calculated check valve failure rate of 6.17 E 7.

The 1992 Fort Calhoun goal for this indicator is a maximum failure rate of 2.00 E G.

Data Source: Jaworski/ Dowdy (Manager / Source)

Accountability: Jaworski/Rollins Adverse Trend: None SEP 43 43

1 O Secondary System CPI

$ eO- Fort Calhoun Goal ( 45) j 1995 INPO Industry Goal (0.30) j 3 . 5 ..  ! Secondary System CPI Limit

! -D- Industry Upper 10% (020) 1- l l l l l l l l l Cycle 14 Refueling

{ o ss -ow 0.5 - o_q.-O-O Outage U-6-3-6-U A 0 6-z @-r b

-0 b' Z b' Z b Z b

' i #0- , , , , , , , , , , , ,

j 89 w Ocl91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 l 5%-

1 0 % of Hours Chemistry ib Outside OG Guidelines l

! 3%- Cycle 14 i Refueling Outage Oy' '"~'

i i

I i I i i i i i i i i i Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 i SECONDARY SYSTEM CHEMISTRY The top graph, Secondary System Chemistry Performance Index (CPI), is calculated using the following three parameters: cation conductivity in steam generator blowdown,

sodium in steam generator blowdown, and condensate pump discharge dissolved l oxygen. The bottom graph shows the percent of total hours of 13 parameters exceed-ing the Owners Group (OG) guidelines during power operation.

4 The CPI was reported as 0.515 for the month of September 1992. The percent of J hours outside the OG guidelines was reported as 0% for the month of September 1992.

The 1991 & 1992 Fort Calhoun goals for the CPI are 0.45. The INPO 1995 Industry goalis 0.30. The industry upper ten percentile value for this indicator was approxi.

mately 0.20 for the twelve months from 7/91 through 6/92.

i Data Source: Franco /Glantz (Manager / Source)

Accountability: Patterson/Schmidt Adverse Trend: None 44

_ - - - _ - - . , _ _ - - - _ . - - -~ ,_ _

P 10%-

O Primary Systern Chemistry Percent of Hours Out of Lirnit

-O- Fort Calhoun Goal -

0%-

4%-

Cycle 14 2%- O O O 5 Refueling Outage C O O U O 0% -- ,

Oct91 NN J'n Feb Mar Apr May Jun Jul Aug Sep92 PRIMAh y 5b.7 2 4Li cHEtilSTRY PERCENT OF HOURS OUT OF LIMIT The Primary System ( hemistry Percent of Hours Out of Limit indicator tracks the pri-mary system chemist / performance by monitoring six key charnistry parameters. Typi-cally, lithium is the parameter that is out of limit.100% equates to all six parameters being out of limit for the month.

The Primary System Chemistry Percent of Hours Out of Limit was reported as 1,18% for the month of September 1992.

The 1992 Fort Calhoun goal for this indicator is a maximum of 2%. The 1991 goal was a maximum of 2%.

Data Source: Franco /Glantz (Manager / Source)

Accountability: Patterson/ Smith Adverse Trend: None 45

10% - _

O  % of Hours Auxiliary System (CCW) Chemistry is Outside Station Umits

-O- 1991 Industry Upper ouartile 8%-

G%-

4%-

Cycle 14 Refueling 2%- Outage o o D O O i i i O*4 , , , , , , , , , , , 1

'89 '90 Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sept 92

[ AUXILIARY SYSTEM (CCW) CHEMISTRY PERCENT OF HOURS OUTSIDE STATION LIMITS

, The Auxiliary System Chemistry Percent of Hours Outside Station Limits indicator tracks the monthly hours that the Component CoolinD Water (CCW) system is outside the station chemistry limit.

The auxiliary system chemistry percent of hours outside station limits was reported as 4 0% for the month of September 1992. The last outside of station limits condition oc-l curred in June 1991 and was due to a low nitrite levelin CCW coolant.

The 1991 Fort Calhoun goal for this indicator was a maximum of 2%.

Data Sourco: Franco /Glantz (Manager / Source)

Accountability: Patterson/ Smith Adverse Trend: None 40

_ _ _ _ _ . _ _ _ _ . - - _ _ _ . . ~.__._--______._.__m . - . _ . _ _ _ - _ . _ _ . _ _ _

O Number of Instruments Out of Servico

-O- Fort Calhoun Goal

] 2&- g4 g4 22- cw .e ,

20 m w en. 20 0-18- $y 3g g m

g g g 7'

~~~'

w w 5N l

16- 15 15 15 m; E w w #w;: :n 14- E L

~

F ]*m f$

b

@ $'+" '

12- m

w

't w .u s: :w; w w w w 10- w w n W  ;%  % W w  %;  %

8- 6 N o- 9 g-g --

g' g -

q -

gw, g -

g -

g g'b -

g 4- -.~.-

m. w wp ,,: . n w s:.; y,p w w E *' f, h f f hh hi$ h h h h o , , , , , , , , , , , ,

Oc'91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 I l IN LINE CHEMISTRY INSTRUMENTS OUT OF SERVICE This indicator shows the total number of in line chemistry system instruments out of-service at the end of the reporting month. The chemistry systems involved in this indi-cator include the Secondary System and the Post Accident Sampling System (PASS).

At the end of September there was a total of 20 in line chemistry instruments out of-service Of these 20 instruments,16 were from the Seco.ndary System and 4 were from PASS.

The trend for PASS instruments has not changed since August. Tne entire secondary panelis considered out of service because of failure of the data logger and the Al 125 alarm card not being in place. The number of secondary instruments out of service has improved by three due to water plant instruments being returned to service.

The increase that occurred after November 1991 in the number of Secondary instru-monts out of service is due to a new method of determining if an instrument is out of service. The entire instrument channelis considered inoperative if: 1) the instrument is ,

inoperative,2) the chart recorder associated with the instrument is inoperative,3) the alarm function associated with the instrument is inoperative. This change was made because if any of the functions named above are not operational, then the instrument is not performing its intended function.

The 1992 Fort Calhoun goal for the number of in line chemistry system instruments that are out cf service has been tet at 6. Six out-of service chemistry instruments make up 10% of all the chemistry instruments that are counted for this indicator.

Data Source: Patterson/Renaud (Manager / Source)

Accountability: Patterson/Jaworski Adverse Trend: None 47

O Moniniy waste Proeucert (Kooarams)

Yearly Waste Produced (Kilograms)

+ Fodotal & State Monthly Lim 61(Kg) 1000 -  ?  :  :  :  :  : -;  ;  ; ,  :  ;

800-g 600- l e

8' 5 400-200- 154.5 150 155 Nb db Ih[hI O

i O

i

$:,$?l i

0 i

of $I2 i i 0

i 0

i

('lll<{

i 0

i 0

i 0

i Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 HAZARDOUS WASTE PRODUCED This Indicator shows the total amount of hazardous waste produced by Fort Calhoun each month and the year to date total for hazardous waste produced. This hazardous waste consists of non halogenated hazardous waste, halogenated hazardous waste, and other hazardous waste produced.

During the month of September 1992,0 kilograms of non halogenated hazardous waste was produced, O kilograms of halogenated hazardous waste was produced, and 0 kilograms of other hazardous waste was produced. The yearly total for hazardous waste produced is 305 kilograms.

The monthly total for the amount of halogenated hazardous waste increased in Decem-ber 1991 because of a change in the method of record keeping. Hazardous waste is no longer counted on a monthly basis, it is counted based upon a full drum of waste.

Date Source: Patterson/Henning (Manager / Source) l Accountab3ity: Patterson/Henning Adverse Trend None 48 l

r.

-, . . _ , . . . . _ , . . . . . - . . . . .-. . , , . ~ ,

., . ~ . .

~ -. . _ - - . . . -. - _ - _- - - - - . _.

O tbghest Exposure for the Month (rnhem)

O Highest Exp?ture for the Quarter (mf".em)

O Highest Expoture for the Year (mrem) 5000-OPPD 4500 mrem /yr. Limit 4000-3000-2000- 1752 y .,

su ,2, y-Q .

1000- i- MAA 434 548 ifhj((h h/G 0

Ms4ES$$$E NNNd ,

September '92 MAXIMUM INDIVIDUAL RADIATION EXPOSURE During September 1992, an individual accumulated 434 mrem which was the highest individual exposure for the month.

The maximum individual exposure to date for the thbd quarter of 1992 was 548 mrem.

The maximum individual exposure reported for the year 1992 was 1,752 mrem. This exposure is primarily due to the individual's //ork during the Cycle 14 Refueling Outage on the de tensioning and removal of reactor vessel studs, the removal and replacement of the core support barrel, and the reassembly of the reactor vessel head.

The OPPD limit for the maximum yearly individual radiation exposure is 4,500 mrem /

year. The 1992 Fort Calhoun goalis 1,500 mrem / year.

Date Source: PattersonAVilliams (Manager / Source)

Accountability: Patterson/Lovett Adverse Trond: None 49

.- - - _ . - . ~ - _ _ . ..-

O Monthly Personnel Contaminations Cumulative Personnel contaminations l GOOD]

300- -O- Fort Calhoun Annual Goal (144) Y J

l i l 250- Cycle 14 5 Refuehng  !

hs Outage

'p%s 200-M t

Ik ~

O O C C C C C C C C C

'M,

! lN,S i ?4N ' 101

!j){ 100- -

77 E$

Y s5 hkh 5 50~

Ik$ h$ 25 24 kb wm w h$ 5/ II 5 5 4 i i i 0 m, , , ,

i ;_

'90 '91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Doc 02 TOTAL SKIN AND CLOTHING CONTAMINATIONS This indicator shows the number of skin and clothing contaminations for the reporting month. A total of 257 contaminations have occurred during 1992. There were 4 con-taminations during September 1992 The contaminations were: 1) A skin contamination that occurred while setting up for a leak rate test; 2) A clothing contamination that oc-curred while building scaffolding; 3) A skin and clothing contamination that occurred when performing a hydro on CH 1B; and 4) A clothing contamination that occurred during decontamination activities in the RCA.

There was a total of 55 skin and clothing contaminations in 1991. There was a total of 237 skin and clothing contaminations in 1990.

The 1992 goal for skin and clothing contaminations is 144. The goal for the fourth quarter of 1992 is 12.

Data Source: Patterson/ Williams (Manager / Source)

Accountability: Patterson/Lovett Adverse Trend: None SEP 15 & 54 50 1

g C Decontaminated Radiation Controlled Area 100% - GOOD l -O- Fort Calhoun Goal (non outage months)

Cycle 14 Refue!!ng 90%- - - -

Outage

,o O 2 2 60 o -

o -

o' 80%-

70% -

4 60%-  :

50 %

Oct91 Nov Dec Jan Feb Mar Ap. May Jun Jul Aug Sep92 DECOt4TAMit4ATED RADIATIOt1 COf4 TROLLED AREA This indicator shows the percentage of the RCA that is decontaminated (clean) based on the total square footage, a 1991 Fort Calhoun goal of 85% decontaminated RCA for non outage months and a 1992 goal of 88% decontaminated RCA for non outage months.

At the end of the reponing month,88.2 % of the total square footage of the RCA was decontaminated.

Date Source: Patte rso n/Gu nda; (Manag e r/ Source)

Accountability: Patterson/Lovett Positive Trend SEP 54 51

4 O fJumt>cr of Identified PRWPs 80-Cycle 14 70- Il0IUOliH9 Outage co- 3.

p 5 0 +-

M 40- [

m 3,

g 8 ~ -'

6x  %'i 20- .h, &

to-7 M

h M

k[h N

11 r

4 5 2 '

g_ ri o A [=1 W' @ M 1

1 V 1 ff/} _

Oct91 f40v Doc Jan Feb Mar Apr May Jun Jul Aug SopD2 RADIOL.OGICAL WORK PR ACTICES PROGRAM The Radiological Work Practices Program Indicator shows the number of Poor Radio-logical Work Practices (PRWPs) which were identified during the reporting month. The PRWPs are identified through a review of the monthly Radiological Occurrence Reports and Personnel Contamination Reports.

The number of PRWPs which are identified each month chould indirectly provide a -

means to qualitatively assess supervisor accountability for their workers' radiological performance.

During the month of September 1992,5 PRWPs were identified. The PRWPs were: 1)

An individual received a skin and clothing contamination when performing a hydro on CH 1B; 2) An individual received a shoe contamination during decontamination activi-ties in the RCA: 3) An individual entered the RCA without an SRD; 4) An individual entered an airborne area without being signed in on an airborne log; and 5) Chewing gum in the RCA.

The number of PRWPs for the month of July is high due to the forced outage from 7/3 through 7/23. The numbers of PRWPs for the months of February, March and April are higher than the numbers reported fo 3revious months due to the Cycle 14 Refueling Outage.

Data Source: Patterson/ Williams (Manager / Source) ,

Accountability: Patterson/Lovett Adverse Trend; None SEP 52 52

.. - . - _ - - - , _ - . - - . . . - -- --.- - - . - - - -~

O Total Number of Hot Spots O NumDer of Additional Hot Spots ident<fied C Removal Planned

-+- Cumulatwe Hot Spots Removed 80- -O- 1992 Fort Camoun Goal for Hot Spots Removed

.e4 I'"

I .

00- -

40-y - 4- -

+

20- - ,. -

_ +g p . _

++ -

0T "

7 7 7 I p h  ;'I  ! fj -O-- -~~O

l - O

!c k h O

/ - -

9 -

o o , O c  :

0 i i A e i E

i

,[i r, f i

I i I

i i i i Jan92 Feb Mar Apr May June July Aug Sept Oct Nov Doc 92 NUMBER OF HOT SPOTS This indicator shows the total number of hot spots which have been identified to exist in the Fort Calhoun Station and have been documented through the use of a hot spot identification sheet. A hot spot is defined as a smalllocalized source of high radiation. A hot spot occurs when the contact dose rate of an item or piece of equipment is at least 5 times the General Area dose rate and the item or piece of equipment's dose rate is equal to or greater than 100 mrem / hour.

At the end of September, there were 67 hot spots identified. 5 hot spots were removed during the month. No new hot spots were identified during the month.

( Removalis planned for 17 hot spots.

The 1992 Fort Calhoun goalis to remove one hot spot per month.

I Data Source: Patterson/ Williams (Manager / Source)

Accountability: Patterson/Lovett Adverse Trend: None 53

O Monthly Rad:cactive Gas D.scharged (Cunes) 500 -

"" " " '* ' S 8C 3'9 "" *

$ -O- Cumu!auve Annua! Goal (Curies) 400-359 O O O-O O O O O O O O O 300 -

5 0

000 -

100 -

h W

f

~

kIf a,.

,, wg. .

I I I I I I I I i i i i i i 1

'90 '91 Jan92 Feb Mar Apr May Jun Jul Aug Sept Oct Nov Doc 92 GASEOUS RADIOACTIVE WASTE BEING DISCHARGED TO THE Et4VIRONMEt4T.

, The gaseous radioactive waste being discharged to the environment is shown for Janu-ary 1,1992 through June 30,1992. A total of 140.7 curies have been released to the environment during this time.

The Fort Calhoun Station cumulative annual goal for 1992 is 340 curies for this indica-tor.

The gaseous radioactive waste being discharged to the environment is calculated every six months.

Data Source: Franco /Krist (Manager / Source)

Accountability: Patterson/Trausch Adverse Trend: None 54

O f.*onthly Radioactwe Liquid D$ charged

' umv!atwo Rad.cactive Liquid O$ charged

-O- cumulatwo Annual Goal I GOODI 250 -

228 O O O O O O O O O O O O 200-175 17s 150 -

(

8 100-50-15.7 i , , , 0 , , , , , , , , , ,

'89 '90 '01 Jan92 Feb Mar Apr May Jun Jul Aug 3ept Oct Nov Doc 02 LIQUID RADIOACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT The liquid radioactive waste being discharged to the environment is shown for January 1,1992 through June 30,1992. The liquid radioactive waste that was discharged to the environment from all sources totaled 39.5 curies during this time.

The Fort Calhoun Station cumulative annual goal for 1992 is 225 curies.

The liquid radioactive waste being discharged to the environment is calculated every six months, Data Source: Franco /Krist (Manager / Source)  !

l Accountability: Patterson/Lovett j l

Adverse Trend: None 55

O raon sysiem Fai!ures lGOODI i

30- Y 25 -

20- 17 15 -

10- 8 7

~ ~

5-  ? 3 2 2 0 -

' ' I""~I '~~'

, '-' i i i , i i i i > i i Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct tJev Dec92 l GOOD l 0 System Failures i 80- 73 Y 70 - T 60- f 56 59 50- $$ d 43 $

40- [$'! e U M

?.$ 33 28 g 30-- j$ ;j@ yy 7 ,,

21 20-10- y g;s gg g y

a zy y g

g 26 7 g

jyj  ; gg g4 0  ; , , , , 3 3  ;  ; , , ,

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 LOGG AB LE/R EPORTABLE INCIDENTS (SECURIT Y)

The Loggable/ Reportable incidents (Security) Indicator is depicted in two separate graphs. The top graph depicts the total number of loggable/ reportable non system failures concerning Security Badges, Access Contrul and Authorization, and Security Force Error, and Unsecured Doors. The bottom graph shows the total number of l loggable/ reportable incidents concerning system failures which occurred during the

! repc ting month.

During the month of September 1992, there were 23 loggable/ reportable incidents identified. System failures accounted for 21 (91%) of the loggable/ reportable incidents, and 12 (52%) of these were environmental failures. Microwave environmental failures were the result of several severe storms during this reportirg period. CCTV environ-mental failures were caused by sun glare. A temporary modification was generated during September installing sun shades on two selected cameras. To date, the installa-tion of these sun shades has produced positive results.

Data Source: Sefick/Woerner (Manager / Source)

Accountability: Sefick l

Adverse Trend: None SEI56 56 l.. _ _ _ - _ , . _ _ ___ _ ___ _

5 I? 25-S O June'92 O August '92 b

July '92 O Se ternber'92 0-

%gi s-bm 10-3n W

h 5- 3 g 2 m i 1 1 1 1 1 1 k g. 70 _

0 i i0 i i i i0 0 0 i i 0 r, , .i

_ i e i i 4 i C Badges Access Control Security Force Error Unsecured Doors SECURITY NOtJ SYSTEM FAILURES This indicator shows the number of loggable/ reportable non system failures for the reporting month. "5ese items include: Security Badges, Access Control and Authoriza-tion, Security Force Error, and Unt.acured Doors.

Non System Failure.s Number of Incidents Seotember '92 August '9P. i Security Badges 0 1 Access Control and Authorization 1 0  !

Security Force Error 0 0  !

i Unsecured Doors 1 1 i Total 2 2 Data Source: SefickAvoerner (Manager / Source)

Accountability: Sefick Adverse Trend: None SEPSS 57

l 4

O Env>ronmental O Fadure I nrnri]

20-15 ..

10- 7 5

G- n y 3

' ' ' i ' I I 0- , , i , i Alarms CCTV Computer Search Equipment Doors O 1991 system Fadures O 1992 System Fadures [ (pp[)]

v' i 100 -

g 80- -

73 3 -

70 03 67 52 $

~

60-43 -

53 63 $ 42 40- 33 pg pg

~

pg_

~ ~

16 M

' L 0- 4 4 6 i i i i i i i i I Jan Feb t,iar Apr May Jun Jul Aug sep Oct Nov Doc SECURITY SYSTEM FAILURES This indicator shows the number of loggable/ reportable system failures for the reporting month. These items include: Alarm System Failures, CCTV f ailures, Security Computer Failures. Search Equipment Failures and Door Hardware Failures. Alarm systems and CCTV failures will be divided into two categories: environmental failures and failures as defined in the performance indicator definitions. Also, the 1991 and 1992 System Failures will be compcred on a monthly basis.

System Uumber of inej2nts 4

Sfnlember'92 Aucutt '92 Environs flihngs Environs Failures

, Alarms 5 1 3 3 CCTV 7 1 4 2 Computer N/A 2 N/A 2 Search Equipment N/A 2 N/A 0 Door Hardware ((3 3 d3 2 Totals 12 9 7 9 Data Source: SefickAVoerner (Manager / Source)

Accountability: Sefick/Patterson Adverse Trend: None SEP 58 58

4 10% -

O Arnount of Work On Hold Awaiting Parts 9%-

-O-- 1991 & 1992 ron Ca:houn Goals 8%-

7%-

0%- Cycle 14 Refuehng 5%- 0;tage 4%- -

C C C O- -

O C C O C ---C C C 3%- -

~

2%- -

~

_ Tj yt 1%- -

3 Oc191 Nov Doc Jan Feb Mar Apr May Jun Jul Aug Sep92 AMOUNT OF WORK ON HOLD AWAITING PARTS (NON OUTAGE)

This procurement indicator displays the percentage 01 open, non outage maintenance items that are on hold awaiting parts, to the total amount of open, non outage mainte-nonce items.

There was a total of 938 open, non outage maintenance work orders (MWOs) with 22 (2.34%) of these MWOs on hold awaiting parts at the end of the reporting month.

The 1991 and 1992 Fort Calhoun Goals for this indicator are to have less than 3.5% of the total number of open, non outage MWOs awaiting parts.

Data Source: Willrett/ CHAMPS (Manager /Sw .e)

Accountability: Willrett/Fraser Adverse Trend: None 59

20-

- Spare Parts inventory Value ($ Mithon) 15-10-5-

i i i i i i i i i i i I 0:19 1 N;e Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 SPARE PARTS INVENTORY VALUE The spare parts inventory value at the Fort Calhoun Stntion at the end of September 1992 was repor ed as $12,686,556.

Data Source: Steele/Huliska (Manager / Source)

Accountability: Wiltrett/McCormick Adverse Trond: None I

-+-- Spare Parts lotued ($ Thousands) 800- , .

( 600-

)

400-200-1 4 i i 6 l 4 i l i i i Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 SPARE PARTS ISSUED The value of the spare parts issued during September 1992 totaled $ 123,871. The value of the spare parts issued for Noverr.her and December 1991 was not available due to a printer problem.

Data Source: Steele/ Miser (Manager / Source)

Accountability: Willrett/McCormick Adverse Trend: None 60

(,,] Inventory Accuracy

--O- Fort Cathoun Goal (98%)

100% - - - -

o o-o-U-o-U o O O o- -

o o

os%- _ _

90%

a Oct91 rJov Doc Jan Feb Mar Apr May Jun Jul Aug Sep92 i

lNVENTORY ACCURACY l This indicator shows the accuracy of the actual parts count for the warehouse compared to the counts contained in the MMIS computer system for the reporting month.
During September,639 different line items were counted in the warehouse. Of the 639
line items counted,30 items needed count adjustments. The inventory accuracy for the l month of September was reported as 95.3%. The Fort Calhoun 1991 & 1992 goals for this indicator are 98%

2 l Data Source: Willrett/McCormick (Manager / Source) l Accountability: Willrett/McCormick Adverse T rend: None 1

4 O  % of Pick Tickets Generated When Parts are net Available etc.

7%- -O- Fon Calhoun Goal 4

0%-

s%-

4%-

g _._5_p A O O O O O O O I- I l- -l R i i b -

Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 STOCKOUT R ATE This indicator shows the percentage of the number of Pick Tickets generated when the amount of parts requested is equal to or less than the minimum stocking level and parts 4

are not available.

During September 1992, a total of 1,063 Pick Tickets were generated. Of the 1,063 Pick Tickets generated,4 Pick Tickets (0.38%) were generated when the amount of parts requested was equal to or less than the rrinimum stocking level and parts were not available. The Fort Calhoun 1992 goal for this indicator is a maximum of 2.6% and the 1991 goal was a maximum of 2.0%

Data Source: Willrett/McCormick (Manager / Source)

Accountability: Willrett'McCormick Adverse Trend: None 61

O *i of Total Purchases that are Expedited

-O- 1991 & 1992 Fort Calhoun Goals (0.5%)

/

4%- Cycle 14 Refueling Outage

~

3%-

2%-

1%- -

C O O O O O -O O O O O l'L 0% i i

i i i i i i i i i Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 EXPEDITED PURCHASES This indicator shows the percentage of expedited purchat.es compared to the total number of purchase ordo s generated during the reporting month.

During September, there was a total of 443 purchase orders generated. Of the 443 purchase orders generated, two (0.45%) were expedited purchases.

The 1992 Fort Calhoun goal for this indicator is 0.5%. The 1991 goal was 0.5%.

The number of expedited purchases was above the Fort Calhoun goal during the months of February, March and April 1992 due to the ordering of items related to the Cycle 14 Refueling Outage.-

Date Source: Willrett/Fraser (Manager / Source)

Accountability: Willrett/Fraser Adverse Trend: None 62

100-80-0B 60-

'M ?:';W ,

hhh.

~

20- $hy,h$hki, ' 13

'!,Nd'NII,'d l l 0 i i i Service invoices COE Invoices Miscellaneous INVOICE BREAKDOWN This indicator shows the number of service invoices, COE invoices, and miscellaneous invoices for the month of September 1992.

Date Source: Willrett/Fraser (Manager / Source)

Accountability: Willrett/Fraser Adverse Trend: None Percentage of Material Requests for issue with the O Request Date the same as the Need Date 100*/. -

-O- 1991 For1 Calhoun Goal 80%- ~~""

00%- C O O .

r , j' ;

40%- _ , j u

i 20%- + c k .,

" e l_4.:.

0*/

Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 M ATERIAL REQUEST PLANNING This i.M.;cator shows the percentage of material requests (MRs) for issue with their request date the same as their need date compared to the total number of MRs for issue for the reporting month. The 1991 goal of 60% is also shown.

During the month of September, a total of 1,063 MRs were received by the warehouse.

Of the 1,063 total MRs received by the warehouse, 45.7 % of the MRs (486) were for issue with their request date the same as their need date.

Data Source: Willrett/McCormick (Manager / Source)

Accountability: Wilfrett/McCormick Adverse Trend: None 63

500 -

O TotalIAccif, cat:en Packages Open 426 425 7 E  :

j g; 400--

A-) m-

$m$):

337

,, 9 3g: -

h 41 $

us

?# 300 -

es- /A zg n u ca 2

270 ca

@ GM: - ',,,,,, 3g

$Ysl h $

$ $ E 5%: >:c: M i t,,9 St- M: 2 200 - - 189

[,h! h h,f

~ 176 17g 173 ce e gc cm - 160 gp n - 48 cc

. gg w:.

n n

ge

- ~~

v 2 %V  !% 'h ce n" n'

a J i i 4 i 100 i i i i i i i i i i i >, .

'88 '89 '90 Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 OUTSTANDING MODIFICATIONS This indicator shows the total number of outstanding modifications (excluding outstand-ina modifications which are oroDosed to be cancelled).

Categorv Reoorting Month Form FC 1133 Backlog /in Progress 17 Mod. Requests Being Reviewed 19 Design Engr. Backlog /!r, Progress 64 Construction Backlog /In Progress 23 Design Engr. Uodate Backlog /In Progress 25 Total 148 At the end of September,40 additional modification requests had been issued this year and 23 modification requests had been cancelled. The Nuclear Projects Review Com-mittee (NPRC) had completed 134 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) had completed 95 backlog modification request reviews this year.

Data Source: Jaworski/ Turner (Manager / Source)

Scofield/Lounsbery (Manager / Source)

Accountability: Scofield/Phelps Adverse Trend: None 64

O Temporary Moeitications >, cycto oid inro requ> red for nemovai)

O Temporary Mod:fications >0 months old (Removable on4ne)

--O- Fort Calhoun Goal for TempE w Mottications >1 cycle old (0) 0-5-

4 j 4-l 3-b a 2 2 2-1 ',,l  ::::0

.y . :

o . .::

1 1-  :: ,

-:2,:;,:
l1
0, 0;:&:.
0 ,' ' '

O 05'NE o Z :'!$

0- O

, O , O' ,

July '92 August '92 September '92 ,

TEMPORARY MODIFICATIONS (EXCLUDING SCAFFOLDING)

This indicator provides inforalation on the number of temporary modifications greater than one fuel cycle old requiring a refueling outage (RFO) for removal and the number of temporary modifications removable on line that are greater than six months old. Also provided is the Fort Calhoun goal for temporary modifications.

There are currently no temporary modifications that are greater 'han one fuel cycle old requiring a refueling outage to remove. In addition, at the end of September there were

, 2 temporary modifications installed that were greater than six months old that can be

, removed on line. These were: 1) handjack close of CCW/RW valves,in which OPS will determine the appropriate controlling mechanism for RW/CCW interface valves as outlined in memo PED SYE 321015. The progress of this task will be tracked by CID t 920953; 2) potable water supply piping temporary repair, which is awaiting completion

of MWOs 894520 and 92718.

l At the end of September, there was a total of 21 TMs installed in the Fort Calhoun Station.12 of the 21 installed TMs require an outage for removal and 9 are removable on line. In 1992 a total of 59 temporary modifications have been installed.

Data Source: Jaworski/ Turner (Manager / Source)

Accountability: Jaworski/Gorence Adverse Trend: None SEP 62 & 71 65 l

i u____ _ ._ _. . _ . _ _ __ _ _ ..._ -- _ __ - - -

O June'92 so - O J"If '92 40- O Aug.ast '92 30~ O september 92 22 3, 20 ai idd3?d) 0-0 0 0 0 3 2 1 o M ,

0-3 months 3 6 months >6 months l

System Engincoring C June '92 O July '92 60~ O August '92 sa l ,,

  1. 4 43 42 O septembsr '92
  1. 0~ Y._ _ 34 & 24:

32 33 30- .'

3 25 28 ,{,g og9,"

20- _

;yy% y,yp,;

10-hb x ~ ,,:

h?ib

'/8[d' O , ,

0 3 months 3 6 months >G months Design Engineering ENGINEERING ASSISTANCE REQUEST (EAR) BREAKDOWN This indicator shows a breakdown of the number of EARS assigned to Design Engineer-Ing and System Engineering awaiting a technical response from engineering.

4 At the end of September 1992, 47 EARS had been resolved and were going through.

d the closecut process. There was 1 EAR awaiting a technical response from Nuclear Projects.

i Total EAR breakdown is as follows:

EARS opened during the month 13 EARS closed during the month 13 Total EARS open as of the end of the month 133 Data Source: Phelps/Pulverenti (Manager / Source)

Accountability: Jaworski/Phelps Adverse Trend: An adverse trend is indicated based on three consecutive months of increasing values for System Engineering and Design Engineering EARS >6 months old. This increase is partially attributable to the forced outages in July and Aug . An effort is in progress to investi-

' gate older EARS (>12 months) that are a lower priority to see if they

can be cancelled.

SEP 62 l

gg i

400-O ECNs Backlogged in DEN R

350- O EClu Opened During the Month O ECNs Completed During the Month 300-250-Cycle 14 Refueting 200- Outage

~ ~

150- -

100-

- r

_ _ r x 50- -

b

~

b . -

[ -

i -

~

,7 _7

~

h k b ',

f k -

k ,

~p h)

[  ;

  • j' y

i Q '

fj V

3 '

0 i i

i i i e  ! i i i i i Oct91 Nov Dec Jan Feb Mar /spr May Jun Jul Aug S6' :2 ENGINEERING CHANGE NOTICE STATUS This indicator shows the number of Engineering Change Notices (ECNs) awaiting completion by DEN, the number of ECNs opened during the reporting month, and the number of ECNs completed by DEN during the reporting month.

At the end of September 1992, there was a total of 152 DEN backlogged open ECNs. 3 There were 37 ECNs ope: ed, and 45 ECNs completed during the month.

Although the number of open ECNs is currently high, activities are in progress to reduce the backlog of open ECNs. It is expected that the number of open ECNs will continue to decrease.

Data Source: Phelps/Pulverenti (Manager / Source)

Accountability: Phelps/Jaworski soverse Trend: None SEP 62 67

O DEN Engineer?ng not complete O system Eng:neering - Engineerine complete, response under roiew Q Maintenar.ce! Construction MWO/CWO scheduled, but work not complete O Maintenance / Construction MWO/CWO con.plete, awaiting ;loseout

(:

- 60 82 20 13 6 ", 4 F- ' 0 0 i 1

WS$

I 1 0 - 3 months 3 - 6 months > 6 months EON FACILITY CHANGES OPEN O DEN Engineering not complete O System Enr eering - Engineering complete, response under review Q Maintenancewonstruction MWO!CWO scheduled, but work not complete O Maintenance / Construction - uWO/CWO comptete. awaiting cioseou

- 85 79 2 46 2 6 12 15 ,

f< _ g , 5 0 5 5 O - 3 months 3 - 6 months > 6 months ECN SURSTITUTE REPLACEMENT ITEMS OPEN O DEN - Engineering not complete O System Engineering - Walkdown or confirmation not complete 64 70 60 )

50 -

b20-23

+ 8 10 1g- O , ,

0 ,

0 - 3 months 3 6 months > 6 months ECN DOCUMENT CHANGES OPEN

. ENGINEERING CHANGE NOTICE BREAKDOWN This indicator shows a breakdown of the number of Engineering Change Motices (ECNs) that are assigned to Design Engineering Nuclear (DEN), System Engineering, and Maintenance or Construction for the reporting month. The graphs provide data on-ECN Facility Changet Open, ECN Substitute Replacement items Open, 'nd ECN Document Changes Open.

Data Source: Phelps/Pulverenti (Manager / Source)

Accountability: Phelps/Jaworski Adverse Trend: None SEP 62 68 1

)

1992 Recordable in;,uryaliness Frequency Rate

--x-- 5 Year Average Recordat 'o injury /l;l ness Frequency Rate IGOODI

-O- 1992 Fort Cainoun Ocal (2.0) y 3.5 -

3-2- O- -O O = =--

M b d J 1.5 -

1-0.5 -

0 e i i i i i i c' ~. i i Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 RECORDABLE INJURY /lLLNESS CASES FREQUENCY RATE This indicator shows the 1992 recordable injury / illness cases frequency rate. The 5 year average (from 1987 through 1991) recordable injury / illness cases frequency rate is also shov>n.

A recordable injury / illness case is reported if Nuclear Operations Division personnel are injured on the job and require corrective medical treatment beyond first aid, The record-able injury / illness cases frequency rate is computed on a year-to-date basis.

1 1

The recordable injury / illness rate for January through September 1992 was reported as 3.58. There were 2 recordable injury / illness cases, an employee inhaled insecticide and anotL.r employee injured a foot, reported during the month of September. There has baen a total of 16 recordable injury / illness cases in 1992.

The recordable injury / illness rate for the past twelve months is 3.79.

The 1992 goal for this indicator is a maximum value of 2.0.

Year Recordable Cases Year-End Ra.ig 1989 11 2.2 1990 11 2.1 i 1991 18 3.3 1

Data Source: Sorenson/Skaggs (Manager / Source)

Accountability: Richard Adverse Trend: An adverse trend is indicated based on three consecutive months of declining performance.

SEP 15,25 & 26 69

e D lxencee Event Repons 46 O Personnel Errors Reported in L ERs M

X 40-Cumu'ative Licensee Event Reports g

g -+- Cumu! alive Personnet Errors Aeported in LERs IE yb 31 32 29 .6 30-g@ T T j 26 .:

': O' Q

e

'lg E I; sy 3: y:

h V

h f; A

20-I lii .j b:-

'1 c

. ; 12 & --

s (y- pk _

Jj . -:

S

_) 10-h . ,

@; i y s - p/  : -

i T i i

4 i

.g q Aq  ? 2 s,p] gq 4 4 i i i i i , i i i i i i

'88 '89 '90 '91 Jan92 Feo Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 NUMBER OF PERSONNEL ERRORS REPORTED IN LERS This indicator shows the number of Licensee Event Reports _ERs) submitted during s each month of 1992, the LERs attributed to personnel errors for each month, and the cumulative totals of both. The year-end totals for the four previous years are also shown.

In September, there was a total of 2 LERs reported; none of which were attributed to licensed personnel error.

Data Source: Short/ Lippy (Manager / Source)

Accountability: Patterson Adverse Trend: None SEP 15 70 i _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _

O Administrative Control Problem O Ucensed Operator Error

@ Other Personnel Error y Maintenance Problem 5-

@ Equipment Failures 4-3-

2- - . _ . . . . . ,

1- - -

r r -: - - - - -- -

I;  ?

,a i .

\l 3 3 's i i i i i 4 4 I i 4 I I Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sop 92 LICENSEE EVENT REPORT (LER) ROOT CAUSE BREAKDOWN This indicator shows the LERs by report date broken down by Root Cause Code for each of the past twelve months from October 1,1991 through Septemis 30,1992.

The cause codes are intended to identify possible programmatic deficiencies, in order to be consistent with industry reporting, the Root Cause Codes have been revised to reflect the NRC's sequence coding. For detailed descriptions of these codes, see the

" Performance Indicator Definitions" section of this report.

Data Source: Short/ Lippy (Manager / Source)

Accountability: Patterson Adverse Trend: None 71

e O Actuai Division statt no Autnorizee civicion starring 3

600 - 518 533

! 400-

> 217 -

226 1 200 -

50 50

O 3  ; ,

Nuclear Operations Production Engineering Nuclear Services STAFFING LEVEL The authorized and actual staffing levels are shown for the three Nuclear Divisions.

! Data Source: Sorenson/ Burke (Manager / Source)

Accountability: Waszak 2

Adverse Trend: None SEP 24

-C}- Nuclear Operations D, vision Tumover Rate e

--A- Production Engineering Division Turnover Rate 10% - -O- Nuclear Services Division Turnover Rate i

8%-

6%- 0 4%- __

W O g3 4 3 3

2%- D O O O v -

0% v O O O-M91 J91 J91 A91 S91 091 N91 D91 - J92 F92 M92 A92 M92 J92 J92 A92 S92 1

PERSONNEL TURNOVER R ATE

The turnover rates for the three Divisions are calculated using only resignations from
OPPD.

1 Division Turnover Rate NOD 2.51 %

PED 3.69 %

NSD 0.0%

Currently, the OPPD corporate turnover rate is being reported as approximately 2.5%.

' This OPPD corporate turnover rate is based on the turnover rate over the last four years.

Data Source: Sorenson/ Burke (Manager / Source)

Accountability: Waszak

. Adverse Trend: None 72

GO- O Tctai nequalitication Training Hours O Simulator Training Hours O Non-Requalification Training Hours O Number of Exam Failures 41

~~"

40-36 36 36 36 30- E E

20-b 16

~~

14 14 14 10- e ,

~ '

- s , s r' 4 ',- ~~

4 .: 4 4 4

~

- . - - -- '/ - 4 2

o i i i i i i i Cycle 91-6 Cycle 91-7 Cycle 921 Cycle 92 2 Cycle 92 3 Cycle 92-4 Cycle 92 5 LICENSED OPERATOR REQUALIFICATION TRAINING This indicator provides information on the total number of hours of training given to each crew during each cycle. The Simulator training hours shown on the graph are a subset of the total training hours. Non Requalification Training Hours are used for AOP/EOP verification & validation, INPO commitments, GET, Fire Brigade, Safety Meetings, and Division Manager lunches.

Exam failures are defined as failures in the written, simulator, and Job Performance Measures (JPMs) segments of the Licensed Operator Requalification Training.

The 4 exam failures in Cycle 92-5 are indicative of individuals who failed rotational simulator evaluations. Additionally, one crew failed a rotational simulator evaluation.

There were no written exam failures, The individuals and crew who failed their simula-tor scenarios were remediated and returned to shift by the end of the requalification week.

Data Source: Gasper /Guliani (Manager / Source)

Accountability: Gasper /Guliani Adverse Trend: None SEP 68 73

l

'! 30- l D SRO Exams Administered l l

O SRO Exams Passed O RO Exams Administered 1

) RO Exams Passed J

20-F4 9 4

i _.

10- -

7 .

, i.-

. t ,

O 3 ,

i i i , , , i  ; i i e i l Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul . Aug Sep92 j LICENSE CANDIDATE EXAMS This indicator shows the number of Senior Reactor Operator (SRO) and Reactor Opera-4 tor (RO) quizzes and exams taken and passed each month. These internally adminis-tered quizzes and exams are used to plot the SRO and RO candidates' monthly

progress.

i During the month of September 1992, there were 4 internally administered SRO exams taken and all 4 of these exams were passed.

l

! There were no internally administered RO exams given during September because these individuals were performing On The Job training (OJT) during time period.

There were no NRC administered SRO or RO exams during September, 1 Data Source: Gasper / Herman (Manager / Source)

Accountability: Gasper /Guliani Adverse Trend: None SEP 68 74 4

O Other Tra ning (1.000 Hrs.)

@ General Employee Training (1,000 hrs.)

O Technical Support (1,000 Hrs.)

4_ O chemistry and Radiation Protection (1,000 Hrs.)

O Maintenance (1,000 Hrs )

to a @ Operations (1,000 Hrs.)

I E

B

$2-e g o

js -

za -

3 nn y-.

O iE E =

.- ny ~~

O , , , , , , , , , , , ,

Sep91 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug92 TOTAL INSTRUCTION HOURS This indicator shows the total number of instruction hours for Operations, Maintenance, Chemistry and Radiation Protection, Technical Suppori, General Employee Training, and Other Training conducted for the Fort Calhoun Station.

1 Due to the transition of responsibilities for training performance indicators, data for the

month of May was unavailable for this indicator, t

i This indicator is normally one month behind the reporting month dt'e to the time re-quired for data collection and processing.

DEPARTMENT Aucust '92

, Operations 605 j Maintenance 408 Chemistry and Radiation Protection 424 l Technical Support 256 General Employee Training 258 I Other 73 Total 2,024 6

Data Source: Gasper /Podoll (Manager / Source)

Accountability: Gasper Adverse Trend: None 75

O Otner Training (1,000 Hrs.)

@ General Employee Training (1,000 hrs )

30- Q Technical Support (1,000 Hrs.)

O Chem:stry and Radiation Protection (1,000 Hrs.)

25~

, O Ma:ntenance (1,000 Hrs.)

E 3 8 Operations (1,000 Hrs.)

E 3

$ 15-0 E Im 2o 10- -

E C

b A

5- @ z y EE g g _

= _

0  ; , , , , , , 3 , i i 3 Sep91 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug92 TOTAL HOURS OF STUDENT TRAINING This indicator shows the total number of student hours for Operations, Maintenance, Chemistry and Radiation Protection Technical Support, General Employee Training, and Other Training conducted for the Fort Calhoun Station.

Due to the transition of responsibilities for training performance indicators, data for the month of May was unavailable for this indicator.

This indicator is normally one month behind the reporting month due to the time needed

.to collect and evaluate the data.

DEPARTMENT Aucust '92 Opera' ions 2,719 Maintenance 1,522 Chemistry and Radiation Protection 1,053 Technical Support 1,261 General Ernployee Training 1,851 Other 235 Total 8,641 Data Source: Gasper /Podoll (Manager / Source)

Accountability: Gasper

- Adverse Trend: None-76 l

9_

Violations per 1.000 Inspection Hours

-O- For: Cawn Goal I OI m +

5

.6 6 -

E a

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'89 '90 '91 Sep91 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug92 VIOLATIONS PER 1,000 INSPECTION HOURS This indicator displays the number of NRC violations cited in inspection reports per 1,000 NRC inspection hours. This indicator is one month behind the reporting month due to the time involved with collecting and processing the data.

The violations per 1,000 inspection hours indicator was reported as 2.71 for the twelve months from September 1,1991 through August 31,1992.

The following NRC inspections ended during this reporting period:

l IER No. Title No. of Hrs..

92-15 Residents' Monthly inspection 480 92 16 GL 8817 Loss of Decay Heat Removal 80 92-17 Emergency Operating Procedures Follow-up 120 The 1992 Fon Calhoun goalis a maximum of 1.5 violations per 1,000 inspection hours.

The goal was a maximum of 1.6 violations per 1,000 inspection hours for 1991.

Data Source: Short/ Lippy (Manager / Source) l Accountability: Short Adverse Trend: None 77

For1 Calhoun 2.71 Cooper 1.03 River Bend 2.61 Commanche Peak 1.5 Wolf Creek 3.57 Arkansas One 1.61 South Texas 2.54 Waterford 236 0 0.5 1 1.5 2 2.5 3 3I5 4 Violations per 1,000 Inspection hours COMPARISON OF VIOLATIONS AMONG REGION IV PLANTS This indicator provides a comparison of violations per 1,000 inspection hours among Region IV nuclear power plants. The data is compiled for a twelve month period from

, September 1,1991 through August 31,1992.

The Fort Calhoun goal for 1992 is a maximum of 1.5 violations per 1,000 inspection hours. The goal for 1991 was a maximum of 1.6 violations per 1,000 inspection hours.

t This indicator is one month behind the reporting month due to the time involved with

! collecting and processing the data.

Data Source: Short/ Lippy (Manager / Source)

Accountability: Short Adverse Trend: None 1

78

25-

-+- Number of Violations During the Last 12 Months

-<>- Number of NCVs During the Last 12 Months 20-16 15 15

13 l 10-e l 7 7 7f 5- 4 4 V

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Sep91 Oct Nov Dec Jan Feb Mar Apr May Jun .lut Aug92 l CUMULATIVE VIOLATIONS AND NCVs (TWELVE-MONTH RUNNING TOTAL) f The Cumulative Violations and Non-Cited Violations (NCVs) indicator shows the cumu-lative number of violations and the cumulative number of NCVs for the last twelve months.

The were no new violations included in this reporting period.

This indicator is one month behind the reporting month due to the time involved with collecting and processing the data for this indicator.

Data Source: Short/ Lippy (Manager / Source)

Accountability: Short Positive Trend

.1 9

79

4 O TotalOutstanding CARS O Outstanding CARS > Six Months Old

@ - Outstanding CARS That Are Modification Related a 100- _

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Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 OUTSTANDING CORRECTIVE ACTION REPORTS

This indicator shows the total number of outstanding Corrective Action Reports (CARS),

l the number of outstanding CARS that are greater than six months old, and the number of outstanding CARS that are modification related, i

At the end of September 1992, there were 91 outstanding CARS,37 CARS that were greater than six months old, and 2 CARS that were modification related. The increase

in the total number of outstanding CARS for September is due to audits that were con-ducted during the month in Training and Materials Identification and Control.

]

Data Source: Orr/Gurtis (Manager / Source)

Accountability: Andrews/Gambhir/ Gates Adverse Trend: None 1

80

20-0 NOD Overdue CARS 15-0 NOD CARS With Extensions Granted 10-5 5- 3 p 1 3 p 2

OR On 00 Od 0 OR Od 01 Op 00 0 On i Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 20 -

O PED Overdue CARS 15-O PED CARS With Exte: sions Granted 10-6 6 5 ~ 5 5- [ [ g 3 g

[ g [ [

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Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 20 -

0 Other Overdue CARS O Other CARS With Extensions Granted 5- 3 3 0

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OR i Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 OVERDUE AND EXTENDED CORRECTIVE ACTION REPORTS This indicator shows the number of overdue CARS and the number of CARS which received extensions broken down by organization.

Overdue CARS Overoue CARS July '92 August '92 September '92-NOD 0 0 --O PED 0 0 0 Otners 1 0 0 lotal 1 0 0

! Extended CARS Extended CARS July '92 August 92 September '92 NOD 0 5 2 PED 2 4 4 I Otners 1 0 3-i Total 3 9 9 I

. Data Source: Orr/Gurtis (Manager / Source)

Accountability: Andrews/Gambhir/ Gates Adverse Trend: None 81

1991 SALP Funct.

Area CARS Signit. C ARs NRC Viola. LERs A) Plant Operat c ns 30 1 1 6 B) Radiolog Controir 12 0 3 0 C) Maint/ Surveil 66 0 2 9 D) Emergency 16 0 0 0 Preparedness E) Security 5 0 1 3 F) Engr / Tech Suppor1 93 3 1 12 G) Safety Assess' 27 1 1 2 Qual Verit H) Other 0 0 0 0 Total 249 5 9 32 1992 SALP Funct.

Area CARS Signit. C ARs NRC Viola. LERs A) Plant Operations 14 0 0 7 B) Radiolog. Cor.trols 11 0 6 0 C) Maint/ Surveil. 109(15) 1 4 12(1)

D) Emergency 5 (1) 1 1 0 Preparednest E) Security 8 0 1 0 F) Engr / Tech Suppor1 42 (18) 0 0 12 (1)

G) Safety Assess 26(1) 0 0 0 Ouat Verit.

H) Other 0 0 0 0 Tota! 215(35) 2 (0) 12(0) 31 (2)

Note: ( ) Indicate valuas for the reporting month.

CARS ISSUED vs. SIGNIFICANT CARS vs NRC VIOLATIONS ISSUED vs. LERs REPORTED The above matrix shows the number of Corrective Action Reports (CARS) issued by the Nuclear Services Division (NSD) vs. the number of Significant CARS issued by NSD vs.

the number of violations issued by the NRC for the Fort Calhoun Station in 1991 and 1992. Included in this table is the number of Licensee Event Reports (LERs) identified by the Station each year. The number of NRC violations reported is one month behind the reporting month due to the time involved in collecting and processing the violations.

Data Source: Orr/Gurtis (Manager / Source)

Short/ Lippy (Manager / Source)

Accountability: Andrews/GambhiriGates Adverse Trend: None SEP 15,20,21 1

I 82

Tota! Outage MW0s -+- Parts Hold

-O- MWOs Ready to Work -: t - Engineering Hold 500 -

-V-- Octage MWR Backlog -G- Planning Hotd I,

4 400-

l 300 -

200 -

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1 100-

..-y Jun92 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep93 MWO PLANNING STATUS (CYCLE 15 REFUELING OUTAGE)

This indicator shows the total number of Maintenance Work Orders (MWOs) that have

been approved for inclusion in the Cycle 15 Refueling OuMge and the number of MWOs
that are ready to work (parts staged, planning complete, and all other paperwork ready for field use). Also included is the number of MWOs that have engineering holds (ECNs, procedures and other miscellaneous engineering holds), parts hold, (parts i staged, not yet inspected, parts not yet arrived) and planning hold (job scope not yet completed). Maintenance Work Requests (MWRs) will also be shown that have been identified for the Cycle 15 Refueling Outage and have not yet been converted to MWOs.

Approximately 2,176 Maintenance Work Orders were completed during the Cycle 14

, Refueling Outage.

Data Source: Patterson/Clemens (Manager / Source)

Accountability: Patterson/Johansen Adverse Trend: None SEP 31 83

1993 OUTAGE PROJECTS STATUS REPORT 100-E % ActuaiCompiet:en tast uontn 90-

% Actual Complet;on TNs Month O % Scheduled Compietion 70-

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e OVER ALL PROJECT STATUS (CYCLE 15 REFUELING OUTAGE)

This indicator shows the status of the projects which are in the scope of the Cycle 15 Refueling Outage. There are currently 13 approved outage projects.

Additional data points will be added to this indicator as information becomes available.

The goal for this indicator is to have all projects 100% complete (ready to work) by July 16,1993. The "% Scheduled Completion" category in the graph represents the percent-age of the project that should be complete as of the end of the reporting month.

Data Source: Patterson/Clemens (Manager / Source)

Accountability: Jaworski/Boughter Adverse Trend: None SEP 31 84 l

Current Schedule with Respect to Original Schedule

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PROGRESS OF CYCLE 15 OUTAGE MODIFICATION PLANNING (FROZEN SCOPE OF 24 MODIFICATIONS)

This indicator shows the status of modifications approved for completion during the Cycle 15 Refueling Outage. The data is represented with respect to the original sched-

ule and the current schedule, showing days ahead or behind the original schedule. This

, information is taken from the Modification Variance Report produced by the Design l Engineering Nuclear group.

The goal for this indicator is to have all mod;fication packages PRC approved by June

1993.

l Additional data points will be added to this indicator as information becomes available.

Data Source: Patterson/Clemens (Manager / Source)

Accountability: Gambhir/Phelps/Faulhaber Adverse Trend: None SEP 31 85 I - -

PERFORM Af1CE If4DICATOR DEFifJlTIOi4S ACE OF OUTSTANDING MAINTENANCE WORK OR. COMPONENT FAILURE AN/4YSIS REPORT (CFAR)

DERS

SUMMARY

This indicator tracks the total number of outstanding cor- The number of INPO categoses for Fort Oc!houn Staten rective non-outage Maintenance Work Orcers at the Fort mth significantly higher (1445 standard deviatons) f aib Calhoun Staten versus their age in months. Ura ? 's than the rest of the industry for an eighteon to io penod. Failures are reponed as component AMOUNT OF WORK ON HOLD AWAITING PARTS (u m ps, motors, valves, ete=) and apphcation (i o.

This indicator is defined as the percentage of open, non- ch..wng pumps, main steam stop valves, control ele-outage, maintenance work orders that are on hold await- ment drive motors, etc.) categories.

ing parts, to the total number of open, non-outage, main. Failure Cause Categones are:

tenance work orders. Wear OuyAging a failure thought to be the conse-quence of expected wear or aging.

AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM Manufacturing Defect a f ailure attributable to inad-PERFORMANCE equate assemb!y or initial quahty of the responsible com-The sum of the known (planned and unplanned) unavail- ponent or system.

able hours and the estimated unavailable hours for the Engineering' Design a f ailure attributable to the inad-auxiliary foodwater system f or the reporting ponod de equate design of the responsible component or system.

vided by the critica! hours fof the reporting pered multi- Other Devices a f ai;ure attnbutable to a failure or phed by the number of trains in the auxihary feedwater misoperation of another component or system, including syr.t em. associated devices.

Maintenance' Testing a f ailure that is a result of im-AUXILIARY SYSTEMS CHEMISTRY PERCENT CF proper maintenance or testing, lack of mxntenance, or HOURS OUTSIDE STATION LIMITS personnel errors uat occur during maintenance or tost-The cumulative hours that the Component Coohng Water ing activities performed on the responsible component or system is outside tne station chemistry limit. The hours system, including f ailurt to f ollow procedures, are accumulated from the first sample exceeding the limit Errors failures attributable to incorrect procedures that until additonal sampling shows the parameter to be Jack were followed as wntten, improper installaton of equip-within limits. mont, and personnel errors (including 1ailure to fotlow proceduros prcperly). Also included in this category are CARS ISSUED vs. SIGNIFICANT CARS vs. NRC VIO - f ailures for which the cause is unknown or cannot be as-LATIONS vs. LERs REPORTED signed to any of the preced ng categories.

Provides a comparison of CARS issued, NRC volations, and LERs reported. This indicator tra:ks performance CORRECTIVE MAINTENANCE BACKLOG GREATER for SEP #15,20, & 21. THAN 3 MONTHS OLD The percentage of totaloutstanding corrective rnainte-CHECK VALVE FAILURE RATE nance items, not requiring an outage, that are greater Comparos the Fort Calhoun check valve failure rate to than three months oid at the end of the period reponod.

the industry check valvo f ailure rate (failures per 1 million component hours). The data for the industry f ailure rate CUMULATIVE VIOLATIONS & NON CITED VIOLA-is three months behind the PI Report reporting month. TlONS (12 MONTH RUNNING TOTAL)

This indicator tracks performance for SEP #43. . The cumulative number of viitations and Non-Cited Vo-lations for the last 12 months.

COLLECTIVE RADIATION EXPOSURE Collective radiaton exposure is the total external whole- DAILY THERMAL OUTPUT body doso received by all on sito personnel (including This indicator shows the daily core thermat output as contractors and visitors) during a time period, as mea- measured from computer point XC105 (in thermal mega-sured by the thermoluminescent dosimeter (TLD). Col- watts). The 1500 MW Tech Spec limit, and the unmot lective radiation exposure is reported in units of person- portion of the 1495 MW FCS daily goal for the reporting rem. This indicator tracks radiological work performance month are also shown.

for SEP #54, DIESEL GENERATOR RELIABILITY (25 DEMANDS)

COMPARISON OF VIOLATIONS AMONG REGION IV This indicator shows the number of failures occurring for PLANTS each emergency diesel generator during the last 25 start Provides data on violations per 1,000 inspection hours demands and the last 25 load run demands.

for Region IV nuclear power plants.

DIESEL GENERATOR UN AVAILABILITY This indicator provides monthly data on the number of hours of dieselgenerator planned and unplanned un-availability.

86-

PERFORM ANCE IIIDICATOR DEFINITIOtJS (Cont'd)

DECONTAMINATED RADIATION CONTROLLED AREA The percentage of the Radiation Controlled Area, which tomatic or manualinstiation.

includes the auxiliary building, the radwaste budding, and B) A load run test to satisfy the plant's load and duration areas of the C/RP building that is decontaminated based as stated in each test's specifications.

on the total square footage. This indicator tracks perfor- C) Other special tests in which the emergency generator mance for SEP # 54. is expected to be operated for at least one hour while loaded with at least 50% of its design load.

DIS ABLING INJURY FREQUENCY RATE (LOST TIME 4) Number of Load Run Failur( " A load-run failure ACCIDENT RATE) should be counted for any reass n in which the emer-This indicator is defined as the number of accidents for gency generator does not pick up load and run as pre-all ut;l!!y personnel permanently assigned to the station, dicted. Failures are counted during any vahd loadon involving days away from work per 200,000 man-hours demands.

worked (100 man years). This does not include cc t . e- 5) Exceptions: Unsuccessful attempts to start or load run tor personneh This indicator tracks personnel perf9i should not be counted as vahd demands or failures when mance for SEP #25 & 26. they can be attributed to any of the following:

A) Spurious trips that would be bypassed in the event of DOCUMENT REVIEWt BIENNIAL) an emergency.

The Document Review Indicator shows the number of B) Manunction of equipment that is not required during documents reviewed, the number of documents sened- an emergency.

uled for review, and the number of document reviews C)Intentionaltermination of a test because of abnormal that are overdue for the reporting month A document conditions that would not have resulted in major d+esel review is considered overdue if the review is not com- generator damage of repair, plete within 6 mor..as of the assigned due date. This D) Malfunctions or operating errors which would have not indicator tracks performance Ic,r SEP #46. prevented the emergency generator from being restarted and brought to load within a f ew minutes.

EMERGENCY AC POWER SYSTEM SAFETY SYSTEM E) A failure to start because a portion of the starting sys-PERFORMANCE tem was disabled for test purpose, if followed by a suc-The sum of the known (planned and unplanned) unavail- cessful start with the starting system in its normal abgn-able and the estimated unavailable hours for the emer- mont.

gency AC power system for the reps rting period divided Each emergency generator f ailure that results in the gen-by the number of hours in the reporting period multiplied erator being declared inoperable should be counted as by the number of trains in the emergency AC power sys- one demand and one failure. Exploratory tests during tem. corrective maintenance and the successf ul test that fol-lows repair to venty operability should not be counted as EMERGENCY DIESEL GENERATOR UNIT RELIABIL. demands or failures when the EDG has not been de-ITY clared operable again.

This indicator shows the number of failures that were reported during the last 20,50, and 100 emergency die- ENGINEERING ASSISTANCE REQUEST (EAR) selgenerator demands at the Fort Calhoun Station. Also BREAKDOWN shown are trigger values which correlate to a high level This indicator shows a breakdown, by age of the EAR, of of conhdence that a unit's dieselgenerators have ob- the number of EARS assigned to Design Engineering tained a reliabihty of greater than or equal to 95% when Nuclear and System Engineering. This indicator tracks the demand f ailures are less than the trigger values, performance for SEP #62.

1) Number of Start Demands: All valid and inadvertent start demands, including a!! start-only demands and all ENGINEERING CHANGE NOTICE (ECN) BREAK.

start demands that are followed by load run demands. DOWN whether by automatic or manualinitiation. A start only This indicator breaks down the number M Engineenng demand is a demand in which the emergency generator Change Notices (ECNs) that are assigned to Design is started, but no attempt is rnade to load the generator- Engineering Nuclear (DEN), System Engineering, and

2) Number of Start Failures: Any failure within the emer- Maintenance. The graphs provide data on ECN Facihty gency generator system that prevents the generator from Changes open, ECN Substitute Replacement Parts achieving specified frequency and voltage is classified as open, and ECN Document Changes open. This indicator a vahd start failure. This includes any condition identified tracks performance for SEP #62.

in the course of maintenance inspections (with the emer-gency generator in standby mode) that definitely would ENGINEERING CHANGE NOTICE (ECN) STATUS have resulted in a start failure if a demand had occurred. The number of ECNs that were opened, ECNs that were

3) Number of Load Run Demands: For a vahd load run completed, and open backlog ECNs awaiting completion demand to be counted the load run attempt must meet by DEN for the reporting month. This indicator tracks one or more of the It" sing cntena: performance for SEP c62.

A) A load run of any duration that resuhs from a real au-87 l

e PERFORMANCE INDICATOR DEFINITIONS (Cont'd)

EQUIPMENT FORCED OUTAGES PER 1,000 CRITI. GASEOUS RADIOACTIVE WASTE BEING DIS.

CAL HOURS CHARGED TO THE ENVIRONMENT Equipment forced outages per 1000 critica aurs is the This indicator displays the total number of Curies of all inverse of the mean time between 1orced outages gaseous radioactive nuclides released f rom FCS.

caused by equipment failures. The mean 1:me is equal to the number of hours the reactor is criticalin a pened GROSS HEAT RATE (1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />) divided by the number of forced outages Gross heat rate is defined as the ratio of total thermal caused by equipment tailures in tnat pened. energy in Bntish Thermal Units (BTU) produced by the reactor to the total gross electrical energy produced by EQUIVALENT AVAILABILITY FACTOR the generator in kilowatt hours (KWH).

This indicator is defined as the rato of gross available generaton to gross maximum generaton, expressed as HAZARDOUS WASTE PRODUCED a percentage. Available generaton is the energy that The total amount (in Kilograms) of non halogenated haz-can be produced if the unit is operated at the maximum ardous waste, haicgenated hazardous waste and other power level permitted by equipment and regulatory limi- hazardous waste produced by FCS each month.

tations. Maximum generation is the energy t*,at can be produced by a unit in a given penod if operated continu- HIGH PRESSURE SAFETY INJECTION SYSTEM ously at maximum capaaty. S AFETY SYSTEM PERFORMANCE The sum of the known (ptanned and unplanned) unavail-EXPEDITED PURCHASES able hours and the estimated unavailable hours for the The percentage of exped:ted purchases occurring during high pressure safety injecten system for the reporting the reporting month compared to the total number of pur- pennd divided by the erttical hours for the reporting pe-chase orders generated. nod multiphed by the number of trains in Je high pres-sure safety injection system, FORCED OUTAGE RATE This indicator is defined as the percentage of time that IN LINE CHEMISTRY fNSTRUMENTS OUT OF SER.

the unit was unavailable due to iorced events compared VICE

'.o the time planned for electrical generaton. Forced Total number of in line chemistry instruments that are events are failures or other unplanned cond:tions that out of service in tha Secondary System and the Post require removing the unit from service before the end of Accident Sampling Systern (PASS).

the next weekend. Forced events include start up fail-ures and events initiated while the unit is in reserve shut- INVENTORY ACCURACY down (i.e., the unit is available but not in service). The percentage of line items that .re counted each month by the warehouse which need count adjustments.

FUEL RELIABtLITY INDICATOR This indicator is definec is the steady state primary cool- INVOICE BREAKDOWN ant 1-131 activity, corrected for the tramp uranium contri- The number of invoices that are on hold due to shett life, buton and normahzed to a common purification rate. COE, and miscellaneous reasons.

Tramp uranium is f uel which has been deposited on re-actor core internals from previous defective fuel or is LICENSE CANDIDATE EXAMS present on the surface of fuel e'ements from the manu- This indicator shows the number of SRO and/or RO quiz-facturing process. Steady state is defined as continuous zes and exams that are administered and passed each operaton for at least three days at a power level that - month. This indicator tracks training performance for does not vary more than + or 5%. Plants should collect SEP #68, data for this indicator at a power level above 85%, when possible. Piants that did not operate at steady-state LICENSED OPERATOR REQUALIFICATION TRAIN-power above 85% should collect data for this indicator at ING the highest steady-state power level attained during ttie The total number of hours of training g:ven to each crew month. during each cycle. Also provided are the simulator train-The density correction factor is the ratio of the specif:c ing hours (which are a subset of the total training hours),

volume of coolant at the RCS operating temperature the number of non-requahfication training hours and the (540 degrees F., Vf - 0,02146) divided by the specific number of exam f ailures. This indicator tracks training volume of coolant at normalletdown temperature (120 performance for SEP #68.

degrees F at outlet of the letdown cooling heat ex-changer, Vf = 0.016204), which resu!!s in a density cor.

rection factor for FCS equal to 1,32.

t 88

PERFORM ANCE INDlCATOR DEFINITIONS (Cont'd)

LICENSEE EVENT REFORT (LER) ROOT CAUSE MAINTENANCE OVERTIME BREAKDOWN The % of overtime hours compared to normal hours for This indicato'shows the number cnd root cause code for maintenance. TSis includes OPPD personnel as we'! as Lic mee Event Reports. The root cause codes are as contract personnel.

folioss:

1) Administrative Control Problem - Management and MATERIAL REQUEST PLANNING supervisory deficiencies that affect plant programs or The percent of material requests (MRs) for issues with activities (i.e., poor planning, breakdown or lack of ad- their requert date the same as their need date compared equate management or supervisory control, incorrect to the total number of MRs.

procedures, etc.)

2) Licensed Operator Error This cause code captures MAXIMUM INDIVIDUAL RADIATION EXPOSURE errors of omission / commission by Lcensed reactor opera- The total maximum amount of radiation received by an tors during plant activities. individ.ial person working at FCS on a monthly, quarterly,
3) Other Personnal Error - Errors of emissiomcommis- and annual basis.

sion committed by non licensed personnel involved in plant activities. MWO PLANNING STATUS (CYCLE 15 REFUELING

4) Maintenance Prob!em - The intent n'" = cause OUTAGE) code is to capture the ful1 - s ut prob l ems whicn can The total number of Maintenance Work Orders that have be attributed in any way to programmatic deficiencies in been approved for ' lusion in the Cycle 15 Ref ueling the maintenance f unctiona1 organization. Act:vities in- ')utage and the number that are ready to work (parts ciuded in this category are maintenance, testing, surves- staged, planning complete, and all other paperwork lance, calibration and radiation protection. ready for field use). Also included is the number of
5) Design / Construction /Instaliation/ Fabrication Problem MWOs that have engineering holds (ECNs, procedures This cause code covers a full range of programraatic and other miscellaneous engineering holds), parts hold, deficiencies in the areas of design, construction, installa- (parts staged, not yet inspected, parts not yet arnved) tion, and f abricetion (i.e., loss of control power due to and planning hold (job scope not yet completed). Main-underrated fese, equipment not qualified for the environ- tenance Work Requests (MWRS) are also shown that ment, etc.). hace been identified for the Cycle 15 Refueling Outage
6) Equipment Failures (Electronic Piece-Parts or Lnvi- and have not yet been converted to MWOs.

ronmental-Related Failures)- This code is used for spuri-ous failures of electionic piece-parts and failures due to NUMBER OF HOT SPOTS ma'aorological conditions such as lightning, ice, high The number of radiological hot spots which have been winds, etc. Generally, it includes spurious or one time identified and documented to exist at FCS at the end of f allures. Electric components included in this category the reporting month. A hot spot is a smalllocalized are circi, it cards, rectifiers, bistables, f uses, capacitors, source of radiation. A hot spot occurs when the contact diodes, resistors, etc. dose rate of an item is at least 5 timea the General Area dose rate and the item's dose rate is equalto or greater LIQUID RADIOACTIVE WASTE BEING DISCHARGED than 100 mrem / hour.

TO THE ENVIRONMENT This indicator displays the total number of cunes from all NUMBER OF NPRDS MULTIPLE FAILURES liquid releases f rom FCS to the Missouri River. The number of NPRDS reportable f ailures over the pre-ceding eighteen months sorted by component manufac-LOGG ABLE/ REPORTABLE INCIDENTS (SECURITY) turer and model number.

The tr tal number of security incidents for the reporting month depicted in two graphs. This indicator tracks se- NUMBER OF OUT OF SERVICE CONTROL ROOM curity performance for SEP #58. INSTRUMENTS A control room instrument that cannot perform its design MAINTENANCE EFFECTIVENESS function is considered as out of service. A control room The number of Nuclear Plant Rehability Data System instrument which has had a Maintenance Work Order -

(NPRDS) components with more than 1 f ailure and the (MWO) written for it and has not been repaired by the.

number of NPRDS components with more than 2 f ailures end of the reporting period is considered out of service for the last eighteen months. and willbe counted. The duration of the out-of service condition is not considered. Computer CRTs are not MAINTENANCE WORK ORDER BREAKDOWN considered as control room instre ents.

This indicator is a breakdown of corrective non outage  !

maintenance work orders by several categones that re- j main open at the end of the reporting month This inds- j cator tracks maintenance performance for SEP #36.

89

PERFORMANCE INDICATOR DEFINITIONS (cont'd)

NUM3ER OF PERSONNEL ERRORS REPORTED IN OVERALL PROJECT STATUS (C(CLE 15 REFUEL.

MS 11G OUTAGEj The number of Licensee Event Repont LERs) atributed This indicator shws the status of the projects which are to prsonnel error on the original LER omittat This in the scope of the Cycle 15 Refueling Outage.

indcator trends personnel periormance for SEP P15, OVERDUE ANL EXTENDED CORRECTIVE ACTION NUMBER OF MISSED SURVEILLANCE TESTS RE. REPORTS SULTING IN LICENSEE EVENT REPORTS The number of overdue Corrective Action Reports The number of Surve;llance Tests (STs) that result in (CARS) and the number of CARS which received exten-Licensee Event Reports (LERs) during the reocrting sions broken down by organl2ation for the last 6 months, month. This indicator tracks missed STs for SEP #60 &

61. PERCENT OF COMPLETED SCHEDULED MAINTE-NANCE ACTIVITIES OPERATIONS AND MAINTENANCE BUDGET The % of the number of completed maintenance activi-The year 10- date budget compared to the actual expen. ties as compared to the number of scheduled mainte-ditures for Operations and Maintenance departments. nance activities each week. This % is shown for each maintenance craft. Maintenance activities include MWRs, OUTSTANDING CORRECTIVE ACTION REPORTS MWOs, STs, PMOs, cahbrations, and other miscella-This indicator displays the total number of nutstanding neous activities. These indcators track Maintenance Corrective Action Reports (CARS), the number of CARS performance for SEP #33.

that are older than six months and the number of modifi-cation related C ARs, PERSONNEL TURNOVER RATE The ratio of the number of turnovers to average employ.

OUTSTANDING MODIFICATIONS ment. A turnover is a vacancy created by voluntary res.

The numbqr of Modification Requests (Mhs)in any state ignation from the company Retirement, death, termina-between the issuance of a Modif cation Number and the tion, transfers within the company, and part tune employ-completion of the orawing update. ees are not considered in turnover,

1) Form FC 1133 Backlog /In Progress. This number rep-resents modifcation requests that have not been plant PLANNED CAPABILITY LOSS FACTOR approved during the reporting month. The ratio of the planned energy losses during a given
2) Modification Requests Being Reviewed. This category penod of time, to the reference energy generation (the 4 includes: energy that could be produced if the unit were operated A.) Modifcation Requests that are not yet reviewed. continuously at full power under ref erence ambient con-B.) Modifcation Reavests being reviewed by the Nuclear ditions), expressed as a percentage.

Projects Review Committee (NPRC).

C.) Modifcation Requests being . viewed by the Nuclear PREVENTIVE MAINTENANCE ITEMS OVERDUE Projects Committee (NPC) This indicator is defined as the % of preventive mainte-These Mod]ication Requests may be reviewed several nance items in the month that were not completed by the times before they are approved for accomplishment or scheduled date plus a grace period equal to 25 % of the cancelled. Some of these Moscation Requests are scheduled interval, This indcator tracks preventive returned to Engineering for more information, some ap. maintenance activities for SEP #41.

proved for evaluation, some approved for study, and some approved for planning. Once planning is com. PRIMARY SYSTEM CHEMISTRY % OF HOURS OUT pleted and the scope of the wsik is clearly defined, these OF LIMIT Modtfication Requests may be approved Mr accomplish. The % of hours out of limit are for six primary chemistry ment with a year assigned for construction or they may parameters divided by thc total rmmber of hours possible be cancelled. All of these different phases require re. for the month, The key parameters used are: Lithium, view, Chloride Hydrogen Dissolved Oxygen, Fluoride, and

3) Design Engineering Backlog'In Progress. Nuclear Suspended Solids. EPRI hmits are used.

Planning has assigned a year in which construction will be completed anJ design work may be in progress. PROCEDUR AL NONCOMPLIANCE INCIDENTS

4) Construction Backlog /In Progress. The Construction (MAINTENANCE)

Package has been issued or construction has begun but The number of identified incidents concerning mainte-

_ the modification has not been accepted by the System nance procedural problems, the number of closed irs Acceptance Committee (SAC). related to the use of procedures (includes the number of
5) Design Engineering Update Backlog'In Progress. PED closed irs caused by procedural noncomphance), and has received the Modification Completion Report but the the number of cicsed procedural noncompliance irs.

drawings have not been updated. This indcator trends personnel performance for SEP The above mentioned outstanding modifications do not #15,41 & 44.

include mod:f cations which are proposed for cancella-tion.

90

PERFORM ANCE INDICATOR DEFINITIONS (Cont'd)

PROGRESS OF CYCLE 15 OUTAGE MODIFICATION PLANNING (FROZEN SCOPE OF 04 MODIFICA.

TIONS)

This indicator shows the status of modifications ap- 3) Security Force Error - Events caused by members of proved for completion during the Cyc'e 15 Ref ueling Out- the security force that are found to be inattentive to their age.

duties or who noglected to properly perform assigned funciions (e.g., required search procedure or patrol).

RADIOLOGICAL WORK PRACTICES PROGRAM 4) Unsseured Doors Doors which are found to be unse.

The number of identified poor radiological work pract,ces cured with no compensatory officer posted or where the (PRWP) for the reporting month. This ind:cator tracks individual causing the alarm did not remain at the radiological work performance for SEP #52. alarmed door until a security officer rs sponded. Events where an unsecured door is caused by sr c'essu'e are RATIO OF PREVENTIVE TO TOTAL MAINTENANCE included in thrs category unless there is an indication that The ratio of preventive maintenance (includ:ng surveil- an adjustment was made to the door, lance testing and caLbration procedures) to the sum of This indicatur tracks security performance for SEP #58.

norcoutage corrective maintenance and preventive main.

tenance completed over the reporting period. The ratio, SECURITY SYSTEM FAILURES expressed as a percentage, is calculated based on man. The following components are the types of loggab!e',e-hours. This indica'cr tracks preventive ma:ntenance ac- portable SECURlW SYSTEM FAILURES represented in tivities for SEP #41. this indicator. Incidents in this category include alarm system f allures, CCTV f allures, security computer f ail-RECORDABLE If4JURYl1LLtJESS CASEb FRE- ures, search equipment f ai:ures, and door hardware fail.

QUENCY RATE ures. These system f ailures are further categorized as The number of injules requiring more than normal first jollows.

aid per 200,000 man hours worked. Th:s indicator 1) Alarm System Failure - Detection system events in-trends personnel periormance for SEP #15,25 & 26. volving f alse! nuisance alarms and mechanical f ailures.

2) Alarm System Environs - Degradations to detection SECONDARY SYSTEM CHEMISTRY PERFORMANCE system performance as a result of environmental condL INDEX tions (i.e., rain, snow, frost).

The Chemistry Performance Index (CPI)is e calculation

3) CCTV Failures - Mechanical failures to all CCTV hard-based on the concentration of key impurities in the sec- ware components.

ondary side of the plant. These key impunt;es are the 4) CCTV Environs Degradat<ons to CCTV performance most hkely cause of deterioration of the steam genera- as a result of environmental conditions (i e., rain, s~.w, tors. The chemistry parameters are reported only for the frost, fog, sunspots, shade).

period of time greater than 30 percent power. 5) Security Computer Failures - Failure of the multi-The CPIis calculated using the following equation: CPI = plexer, central processing unit, and other computer hard-(Ka'0.8) + (Na/20) + (0/10)) / 3 where the following are ware and software. This category does not include soft-monthly averages of: Ka = average blowdown cation ware problems caused by operator error in using the conductivity, Na - average blowdown sodium concen- software.

tration, O, - average condensate pump discharge dis- 6) Search Equipment Failures Failures of x ray, metal, solved oxygen concentration. or explosive detectors and other equipment used to search for contraband. This also includes incidents SECURITY NON SYSTEM FAILURES where the search equipment is found to be defective or The following components are the types of loggable/re- did not function properly during testing.

portable non system f a: lures represented in tnts indica-

7) Door Hardware Failures Failure of the door alarm t#, incidents in this category include secunty badges. and other door hardware such as latches, electric strikes, access control and authonzat on. secunty force error, doorknobs, iocks, etc.

and unsecured doors. 8) 1991 versus 1992 System Failures - Statistics from

1) Secunty Badges - incidents associated with improper 1991 will be compared on a monthly basis with 1992 use and handiing of security badges. Incidents include loggable/ reportable system failures. This indicator tracks 4 security badges tnat are lost, taken out of the protected security performance for SEP #58.

area, out of control on-site, or inadvertently destroyed or broken. SPARE PARTS INVENTORY VALUE a) Access Controland Authorization Administrative and The dollar value of the spare parts inventory for FCS dur-procedural errors associated with the use of the card- ing the reporting period.

access system such as tailgating, incorrect secunty badge issued, and improper escon procedures. This SPARE PARTS ISSUED also includes incidents that were caused by incorrect The dollar value of the spare parts issued for FCS dunng access authonzation information entered into the secunty the reporting period system computer.

91

PERFORMANCE INDICATOR DEFINITIONS (Cont'd)

STAFFING LEVEL TOTAL INSTRUCTION HOURS The actual stathng level and the authorced stathng twol The total number and department breakdown of training for the Nuclear Operatens Divis on, the Production Engi- instruction hours administered by the Training Center.

neerit' Division, and the Nuclear Services Division. This indica , tracks periormance for SEP #24. TOTAL SKIN AND CLOTHING CONTAMINATIONS Reportabte skin and clothing contammations above STATION NET GENERATION background levels greater than 5000 dpm/100 cm The net generation (sum) procuced by the FCS during squared. This indicator trends personnel performance the reportmg month, for SEP #15 & 54.

STOCKOUT RATE UNIT CAPABILITY FACTOR The total number of Pick Tickets that were generated . The ratio of the available energy generation over a given dunng the reporting month and the total number of Pck time period to the reference energy generation (the en-Tckets that were generated curing the reporting month ergy that could be produced if the unit were operated when the amount of pa'ts requested is equal to or less continucusly at full power under raference ambient con-than the minimum stocking level and carts are not avail- ditons) over the same time period, expressed as a per-able. centage.

TEMPORARY MODIFICATIONS UNPLANNED AUTOMATIC REACTOR SCRAMS The number of temporary mechanical and electrical con- WHILE CRITICAL figurations to the planus systems. This mdicator is defined as the number of unplanned au-

1) Temporary conf.guratens are cehned as electrical tomatic scrams (reactor protecton system logic actua-jumpers, electrical blocks, mechantcal jumpers, or me- tions) that occur per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of entical operation.

Chanical blocks wht are installed in the plant operating The value for this indcator is calculated by multiplying systems and are nr.a ; awn on the latest revision of the the total number of unplanned automate reactor scrams PalD, scbmatic, connection, winng, or flow diagrams. in a specifc time penod by 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, then dividing

2) Jumpers and blocks wh!ch are installed for Surveil- that number by the total number of hours enticalin the lance Tests, Maintenance ProceNres, Cahbration Pro- same time period. The indcator is further defined as cedures, Special Procedures, or Op ating Procedures follows:

are not considered as temporary modif etons unless the 1) Unplanned means that the scram was not an antici.

jumper or block remains in place ahar the test or oroce- pated part of a planned test.

dure is complete. Jumpers and blocks installed in test or 2) Scram means the automate shutdown of the reactor 4 lab instruments are not considered as temporary modifi- by a rapid insertion of negative reactivity (e.g., by control cations. rods, liquid injection system, etc.) that is caused by ac-

3) Scaffolding is not considered a temporary modifica- tuation of the reactor protection system. The scram sig.

tion. Jumpers and blocks which are installed and for nal may have resulted from exceeding a setpoint or may which MRs have been submitted will be considered as have been spurious.

tamporary modifcations untilfinal resolution of the MR 3) Automatic means that the initial signal that caused and the jumper or block is removed or is permanently actuation of the reactor protection system logic was pro-recorded on the drawings. This indicator tracks tempo- vided from one of the sensors monitoring plant param-rary modifications for SEP #62 8 71. eters and condrtions, rather than the manual scram switches or,in manual turbine trip switches (or push but-THERMAL PERFORMANCE tons) provided in the main control room,

! The ratio of the design gross heat rate (corrected) to the 4) Crit; cal means that during the steady state conoition of adjusted actual gross heat rate, expressed as a percent- the reactor prior to the scram, the effective multiplication age. f actor (k,) was essentsally equal to one.

TOTAL HOURS OF STUDENT TR AINING UNPLANNED CAPABILITY LOSS FACTOR The total number of student hours of training for Opera- The ratio of the unplanned energy losses during a given

, tLns, Maintenance, Chemistry / Radiation Protection, period of tirre, to the reference energy generation (the Technical Support, General Employee Training, and energy that could be produced if the umt ware operated Other Training conducted for FCS. continuously at full power under reference ambient con-ditions) over the same time period, expressed as a per-

[

i centage.

l 92 l

l l

O PERFORMANCE INDICATOR DEFINITIONS (cont'd)

UNPLANNED SAFETY SYSTEM ACTUATIONS.

(INPO DEFINITION)

This indicator is defined as the sum of the following safety system actuations:

1)The number of unplanned Emergency wore Cochng System (ECCS) actuations that result from reaching an ECCS actuation setpoint or from a spuroushnadvenent ECCS signal.

2) The number of unplanned emergency AC power sys-tem .actuatons that result from a loss of power to a safe-guards bus. An unplanned saf ety system actuation oc-
curs when an actuation setpoint for a safety system is reached or when a spurious or inadvertent s'gnalis gen-i erated (ECCS only). and major equipment in the system is actuated. Unplanned means that the system actuation 4

was not part of a planned test or evoluton. The ECCS actuations to be counted are actuat ons of the high pres-sure injection system, the low pressure injection system,

or the safety injection tanks.

'. UNPLANNED SAFETY SYSTEM ACTUATIONS(NRC DEFINITION)

The number of safety system actuatons which include

(uk) the High Pressure Safety Injection System, the Low Pressure Safety injection System, the Safety injec-tion Tanks, and the Emergency Diesel Generators. The NRC classification of saf ety system actuations includes actuatons when major equipment is operated p.M when the logic systems fnr the above safety systems are chal.

4 lenged.

VIOLATIONS PER 1,000 INSPECTION HOURS This indicator is defined as the number of volations sited in NRC inspection repons for FCS per 1,000 NRC in-spection hours. The volations are reported in the year that the inspection was actually performed and not based on when the inspecton repon is received. The hours reported for each inspection report are used as the in-spection hours.

t VOLUME OF LOW LEVEL SOLID RADIOACTIVE WASTE This indicator is defined as the volume of low-level solid l radioactive waste actual'y shipped for burial. This indica-tor also shows the volume of low level radcactive waste which is in tempora y storage, the amount of radcactive oil that has been shipped off-site for processing, and the volume of solid dry radioactive waste which has been shipped off-site for processing. Low level solid radioac-tive waste consists of dry active wa-te, sludges, resins, and evaporator bottoms generated as a result of nuclear power plant operation a- i maintenance. Dry radioactive waste includes contaminated rags, cleaning materials, disposable protective clothing, plastic containers, and any other material to be d sposed of at a low level radio-active waste disposal site, except resin, sludge, or evaporator bottoms. Low-level refers to all cadcactive waste that is not spent f uel or a by prodtet of spent fuel processing. This indicator tracks rad:clogeal work per-i formance for SEP #$4.

93

SAFETY Ef4HAl4CEf4Et4T PROGRAfA It4DEX The purpose of the Safety Enhancemeni Program (SEP, Portormance Indicaiors Index is to list perfor- .,

mance indicators related to SEP ltems with parameters that can be trended. ..

SEP Reference Number 15 Paae increase HPES and IR Accountability Through Use of Performance Indicators Procedural Noncompliance Incidents (Maintenance) . , , .33 Total Skin and Clothing Contaminations . . , , . .50 t Recordable injury / Illness Cases Frequency Rate . . . . . 09 Number of Personnel Errors Reported in LERs . . .. . . .70 CARS issued vs Significant CARS issued vs NRC Violations issued vs LERs Reported . .. 82 SEP Reference Number 20 Quality Audits and Surveillance Programs are EvaluMed. Improved in Depth and Strengthened CARS issued vs Significant CARS issued s NRC . iolations issued vs LERs Reported . .82 SEP Reference Number 21 Develop and Conduct Safety System Functional inspections CARS issued vs Significant CARS issued vs NRC Violations issued vs LERs Reported . . 82 l

SEP Reference Number 21 Complete Staff Studies Staffing Level .. . . .. .. . . 72 SEP Reference Number 25 Training Program for Managers and Supervisors tr.1plemented Disabling injury /lliness Frequency Rate . , , . .18 Recordable injury / Illness Cases Frequency Rate . . . . . . 69 SEP Reference Number 26 Evaluate and Imptament Station Standards for Safe Work Practice Requirements

, Disabling injury /litness Frequency Rate . . .. . .18 Recordable injury / Illness Cases Frequency Rate . . 69 SEP Reference Number 31

Develop Outage and Maintenance Planning Manual and Conduct Project Management Tsaining

! MWO Planning Status. , . . . , , , .. .. .83

! Overall Project Status . . . 84 Progress of Cycle 15 Outage Modification Planning . , . 85 SEP Reference Number 33

!. Develop On Line Maintenance and Modification Schedule

+

Percent of Completed Scheduled Maintenance Activities

. (Electrical Maintenance), . . . ,. . 34

(Pressure Equipment) . . . . . . . . .. .

....,.35 (General Maintenance).. . . . .36 (Mechan: cal Maintenance) . .... . . . . . . . . . . 37 (Instrumentation & Control) . . . . . . . . . . . 38 SEP Reference Number 36

_ Reduce Corrective Non-Outage Backlog Maintenance Work Order (MWO) Breakdown (Corrective Non Outage Maintenance). . . 27 Corrective Maintenance Backlog Greater than 3 Months Old (Non-Outage) . . 28 i SEP Reference Namber 41 Develop and Implement a Preventive Maintenance Schedule Ratio of Preventive to Total Maintenance . . . . . . . 29 -

Preventive Maintenance items Overdue . . .30 Procedural Noncompliance incidents. . 33 94

l SEP Reference Number 43 Implement the Check Valve Test Program Check Valve Failure Rate. . . . 43 SEP Reference Number 44 Compliance With and Use of Procedures Procedural Noncompliance incidents (Maintenance) . . . 33 SEP Reference Numbgt43 Det.gn a Procedures Control and Administratt.e Program Document Review . .. . . . . . 22 Sf, P Refe7nce Number 52 Est 7 ish Supervisory Accountability for Workers Radiological Practices Radiulogical Work Practices Program. . . 52 SEP Reference Number 54 Complete implementation of Radiological Enhancement Program Collective Radiation Exposure . h Volume of Low-Level Solid Radioactive Waste. .. . . . . .. .17 Total Skin and Clothing Contaminations . . . .50 Decontaminated Radiation Contnlied Area. . . 51 SEP Reference Number 58 Revise Physical Security Training and Procedure Program Loggable/ Reportable incidents (Security; . . .56 Secunty Non System Failurer. . . , , . .57 Security System Failures . .. . . . . 58 SEP Reference Number 60 Improve Controls Over Surveillance Vest Program Number of Missed Surveillance Tests Resulting in Licensee Event Reports. . . 39 SEP Reference Number 61 Modify Computer Program to Correctly Schedule Surveillance Tests Number of Missed Surveillance Tests Resulting in Licensee Event Reports. . .39 SEP Reference Number 62 Establish Interim System Engineers Temporary Modifications . . . . . . . . 65 Engineering Assistance Request (EAR) Breakdown.. . 66 Engineering Change Notice Status . . .G7 Engineering Change Notice Breakdown . - . . . . . 68 SEP Reference Number 68 Assess Root Cause of Poor Operator Training and Establish Means to Monitnr Operator Training Licensed Operator Requalification Training . .. . . . 73 License Candidate Exams. . 74 SEP Reference Number 71 Improve Controls over Temporary Modifications Temporary Modifications . . .. . ... . .65 95 a

1 REPORT DISTRIBUTION LIST R. L Andrews D J Golden D C. Mueller G L Anglehart Li C Gorence H J Mueller W R Bateman R E. Gray M W Nichols K. L Belek M J Guinn C. W. Norris T. G. Blair G. E. Guhani Nuclear Licent.ing B. H Blome K. B. Guhani & industry Affairs C. N Dloyd E. R. Gundal J. T. O Connor J.P.Bobba R H. Guy W. W. Orr C E. Boughter R. fJ. Hawkins L L Parent IA. A Breuer M. C. Hendrickson T. L Patterson C. J. Brunner1 R R. Henning R T. Pearce M W. Butt K. R Henry R. L Phelps C A Carlson J. B. Herman W. J. Ponce J W. Chase G. J Hal L M. Pulnrenti o R. Chatfield K. C. Holthaus T. M. Reisdorf f A G. Christensen L G. Hultska A. W. Richard A J. Clark C. J Husk D. G. Ried O J. Clayton R. L. Janov ski G. K. Samide R. P. Clemens R. A Johansen T.J Sandene J. L. Connolley W. C. Jones B. A. Schmidt G M. Cook J. D F .. S. T Schmitz M. R Cr 9 J. D. Kepp?ct F C. Scofield S. R. Cntes D. D. Kloock H. J. Sefick D. W. Dato J. C. Knight J. W. Sharmon R. C. DeMoulmeester D. M. Kobunski R. W. Short R.D.DeYoung G. J, Krause C. F. Simmons D. C. Dict 2 J, G. Krist E. L Skapgs K.S. Dowdy L. T Kusek J. L Skilet, J. A. Drahota L E. Labs F. K Smith T. R, Dukarski M. P. Lazar R. L Sorenson D. L Eid R. C Learch J. A. Spilker R. G. Eurich R. E. Lewis K. E. Steele H. J. Faulhaber R. C. Llebentritt W. Steele M. A. Ferdig B. Lisowyj H. F. Sterba F. F. Franco D. R Livingston G. A. Teeple M. T. Frans J H. MacKinnon M. A. Tesa:

H. K. Fraser G. D Mamoran J. W. Tills J. F. W, Friedrichsen J. W. Marcil D R.Trausch S. K. Gambhir N. L Mariice P. R. Turner J. K. Gasper D. J. Matthews J. M. Uhland W. G. Gates J. M. Mattice C. F. Vanecek M. O. Gautls . T. J. Mcivor J. M. Waszak S. W. Gebers K. S. McCormick G. R. Wilhams J. M. Giantz R. F. Mehaff ey S. J. Willrett J. T. Gleason K. G. Melstad W. C. Woerner L V. Goldberg K. J. Morris 96

POSITIVE TREND REPORT INDICATORS NEEDING INCREASED The Posttive Trend Report highbghts severa! Pertor.

MANAGEMENT ATTENTION REPORT mance indicators with data representing cont nued pet. This stction hsts the indicators which show inadequacios formance above the stated goal and indcators with cata as compared to the OPPD goal and inacators which representing significant impfovement in recent months. show inadequacies as compared to the industry upper ten percentile. The indicators will be compa'ed to the The following indicators have been selected as enh:bmng industry upper ten porcentile as relevant to that indicaior, posrbve trends:

Forced outace Rate DemntamMsted Rsta'en Centr 9ed Ag (Page 2)

(Pege 51) The forced outage rate value for the twelve months from The percentage of the R' A that h decontaminated for 10/1/91 through 9'30/92 (12 06%) is above the 1991 and September (68.2%)is above the Fort Calhoun goal 1992 Fort Calhoun goals of 2.4%

(88%n for the first time since the Cycle 14 Refuehng Out-age. Uno!anned Automare Reser Serams cer 7.000 Hourg C2:21 Comubtive Violatient end NCVs (Twelve Month Run4na (Page 3)

Jetd) The number of unplanned automatic reactor scrams par (Page 79) 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical year to date value for the reporting The number of violations for Fort Calhoun Station for the month (5.86) exceeds the For1 Calhoun 1992 goal of tast twelve months has decreased for two consecutive zero (0),

months.

Vtplanned Ss'etv Svitem Actuat!cns flNPO Dehnson)

(Page 4)

End of Positive Trend Repon The number of unplanned saf 6ty system actuations (INPO definition) year to date (1) exceeds the 1992 Fort Calhoun goalof 2ero.

Uno'anned Safety System Actuations rNRC Dehn00n)

ADVERSE TREND REPORT (Pages)

The number of unplanned safety system actuations A Performance Indicator which has data representing (NRC definition) year to date (4) exceeds the 1992 Fort three (3) consecutive months of declining performance Calhoun goalof a maximum of 3.

constitutes an adverso trend. The Adverse Trend Report explains the conditions under which certain indcators are Eue! Reliabibiv fnd, eater showing adverse trends, % explanation will be provided (Page 15) for indicators with data ter esenting three months of de. The FRI value for the reporting month (7.76 X 104 mi-clining performance that have been labeled as adverse crocuries/ gram) exceeds the Fort Calhoun goal of 7.5 X trends. 10-4 microcuries/gtam.

The following indicators are exhibiting adverse trends for the reporting month: D!sablino Iniurv/luness Frecuenev Rate (Lost T!me Acci-diU$i!ld (Page 18)

Encineerino Atsbtant Reauett (E AR) Breakdown The disabling injury / illness frequency rate year to date (Page 66) _

value for the reporting month (1.12) exceeds the 1992 An adverse tiend is indcated based on three consecu. Fort Calhoun goalof 0.30, tive months of increasing values for System Engineering and Design E ngineering E ARs >G months old. This in. Eculoment Forced Outaces oer 1000 Cntical Hours crease is partially attributab!e to the forced outages in (Page 20)

July and August. An effort is in progress to investigate The equipment forced outages per 1,000 critical hours older EARS (>12 months) that are a lower priority to see year to-date value for.the reporting month (1,4) exceeds if they can be cancelled, the 1992 Fort Calhoun goalof 0.20.

Bemedable INuevilHness Cases Frecuenev Rate Ratio of Preventive to Totat Mai_n,tenance (Non Outace)

(Page 69) (Page 29)

An adverse trend is indicated based on three consecu. The ratio of preventive to total maintenance for the to.

tive months of dechning performance, porting month (50.57%) is lower than the Fort Calhoun goalof 65%.

End of Adverse Trend Report.

97

INDICATORS NEEDING INCREASED PERFORMANCE INDICATOR REPORT MANAGEMENT ATTENTION REPORT IMPROVEMENTS / CHANGES (Continued)

This secton lists significant changes made to the report go . owe Svttem CM and to specif e indicators within the report since the pre.

(Page 44) vrous month, The Chemistry Performance Index (CPI) value for tha reporting month (0 515) ereeeds the Fort Calhoun goal U' INPO Indreators . Approximate upper ten percentile val.

vos have been revised based on the INPO 1992 IAdyear in Une Chemittev int 9umeatt Out of. Service

"'PON (Page 47)

The number of 14ne chemittry instruments out of ser. g, , gg, ,,,,, p ,, g vce for the repo:, ..g month (20) exceeds the fort Cal. a houn goalof a maximum of 6. e 1991 Disabling injury /lllnbst Frequency Rate line on the graph has been replaced with the 5 year average M3ximum Individuai R>d nSon Ercoture Disabling injury /litness Frequency Rate.

(Page 49)

The maximum ir.dividual radiation exposure for the year No O M e e Con 9M h intu w enM at the end of the reporting month (1,752 mnem) exceeds age 3 the Fort Calhoun goal of 1,500 mrem, , g08 for this indicator has been revised because INPO no longer tracks this item due to diffculty in estab.

Total Skin and Ciothina Contaminnue nt lishing consistency among plants reporting this indcator, (Page 50) lhe cumulative skin and clothing contaminations at the Recordable in!urve l!Iness caset FrecueD22.fhl2 end of the reporting month (257) exceeds the Fort Cal.

ago 69) houn goal of 144. gg Recordoble injury / Illness Cases Frequency Rate fine on the graph has been replaced with the 5 year inventerv Axurney average Recordable injury /I'! ness Cases Frequency (Page 61) j Rale.

The inventory accuracy value for the repo' ting month (95.3%)is less than the 1M fort Calhoun goal of 90%.

Encineerina Ati!stant Recuett (E AR) Breakdown Vicistions oor 1000 Intocction Hourt, (Page 66)

The graph for this indicator has been revised to show 4 (pag,77) m nths' data.

The number of NRC vo!ations per 1,000 inspection hours value f or the reporting month (2.71) exceeds the Overall Proiect Status (Cvele 15 Refuelino Outace)

I, ort Calhoun goal of a maximum of 1.5, p q This indicator hn been revised to include more detail Proarets of Cvele 15 Outase Moddiention Plannina (Fro.

End of Management Attention Report. ren Scoce of 24 Modifientionti (Page 85)

This indicator has been revised to include more detail.

End of Performance Indicator Report improvements /

Changes Report 98

~

I H.,h1 LAu1Ruti b i Ah0N

, OPERATING CYCLES AND REFUELING OUTAGE DATES Event Date Rcngo Production (MWH) Cumulative (MWH)

Cycle 1 09/26/73 02/01/75 3,299,639 3,299,639 1st Refueling 02/01/75 05'09/75 '

  • Cycle 2 05/097/5 10/01/70 3,853,322 7,152,961 2nd Refueling
  • 10/01/76 12/1376 '

Cycle 3 12/13/76 9/30 77 2,805,927 9.958,888 3rd Refueling 09/30,77 12/09/77 ' '

Cycle 4 12/09/77 10/14/78 3.026,832 12,985,720 4th Refueling *

  • 10/14778 12/24'70 Cycle 5 12/24/78 01/18'80 3,882,734 16,868,454 hh Refueling 01/18l80 06/11/80 *
  • I Cyclo 6 06/11/80 09/10'81 3,899,714 20,768,160 Sth Retuoling *
  • 09/18:01 12/21/81 Cycle 7 12/21/01 12/06/82 3,561,066 24.330,034 7th Refueling 12/06/82 04/07/03 '
  • Cycle 8 04/07/83 03/03/84 3,406,371 27,736,405 8th Refueling 03/03/04 07/12/04 *
  • Cycle 9 07/12/84 09/28!85 4,741,488 32,477,893 9th Refueling *
  • 09/28/05 01/16!86 Cycle 10 01/16/06 03/07/87 4,356,753 36,834,646 10th Refueling 03/07/87 06/08/87 '
  • Cycle 11 06/08/87 09/27/88 4,936,859 41,771,505 11th Refueling 09/27/88 01/31/89 *
  • Cycle 12 01/31/89 02/17/90 3,817,954 45,589,459 12th Refueling
  • 02/17/90 05/29/90 '

Cycle 13 05/29/90 02/01/92 5,451,069 51,040,528 13th Refueling 02/01/92 05/03/92 '

Cycle 14# 05!03/92 09/18/93 (Plannes Jatos) 14th Refueling *

  • 09/18/93 11/13/93 Cycle 15 *
  • 11/13/93 03/11/95 15th Refueling *
  • 03/11/95 05/06/95 FORT CALHOUN STATION CURRENT PRODUCTION AND OPERATIONS " RECORDS" First Sustalnod Reaction August 5,1973 (5:47 p.m.)

First Electricity Supplied to the System August 25,1973 Commercial Operation (160,000 KWH) September 26,1973 Achloved Full Power (100%) May 4,1974 Longest Run (477 days) June 8,1987 Sept. 27,1988 Highest Monthly Net Generation (364,460,000 KWH) October 1987 Most Productive Fuel Cycle (5,451,069 MWH)(Cycle 13) May 29,1990-Feb.1,1992

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