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Performance Indicators Dec 1992 Rept
	ML20128C324
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Site:	Fort Calhoun
Issue date:	12/31/1992
From:	; OMAHA PUBLIC POWER DISTRICT
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FORT CALHOUN STATION PERFORMANCE INDICATORS DECEMBER 1992 m

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Prepared by:

Production Engineering Division System Engineering Test and Performance Group I

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l OMAHA PUBLIC POWER DISTRICT-FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT j

Prepared By:

Production Engineering Division System Engineering Test and Performance Group DECEMBER.1992 l

i d

ABSTRACT PURPOSEi The " Performance Indicators Program"is intended to provide selected Fort Calhoun plant perfor-mance information to OPPD's personnel responsible for optimizing unit pertormance. The information 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. Some performance indicators show company goals or industry information. This information can be used for cornparison or as a means of promoting pride and motivation.

SCOPE The conditions. 00als, and projections reflected within this report are current as of the end of the month being reported, unless otherwise stated.

In order for the Perfom1ance Indicator Program to be effective, the following guidelines were followed while irnplementing the program:

1) Data was selected which most effectively monitors Fort Calhoun's performance in key areas.

2) Established corporate goals and Industry information were included for comparison.

3) Formal definitions were developed for each performance parameter 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 Engineering Department's Test and Performance Group. To increase personnel awareness of Fort Calhoun Station's plant perfomunce, it is suggested inat this report be distributed throughout your respective departments.

REFERENCES INPO Good Practices OA-102, " Performance Monitoring - Management Information" INPO Report Dated Novernber 1984," Nuclear Power Plant Operational Data" NUMARC 87-00," Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Black-out at Light Water Reactors', Revision 1, Appendix D,"EDG Reliability Program", dated :

April 6,1990.

. FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT DECEMBER 1992 -@UMMARY '

POSITIVE TREND REPORT INDICATORS NEEDING INCREASED.

MANAGEMENT ATTENTION REPORT The Positive T rend Report highlights several Perfor.

mance Indicators with dath representing continued per-This section hsts the indicators which show inadequacles -

formance above the stated goal and indicators with data -- when compared to the OPPD goal.

representing significant improvement in recent months.

Th& fotbwing indicators have been weix:ted as exhibiting Forced Outaae Rate positive trends for the reporting month:

(Page 5)

The forced outage rate value for the twelve months from -

1/1/92 through 12/31/92 (10.09%) is above the 1992 Fort LLeuLQaoability Factor Calhoun goalof 2.4%.

(Page 25)

The UCF was reported as 100% for th! months of De-Uno!anned Automatic Reactor Scrams ner 7.000 Hours cember, November and October 1992. It increased dur-Crrucal ing August and September after the July forced outage (Page 7) caused by the loss of an inverter.

The number of unplanned automatic reactor serams per 7,000 hours0 days 0 hours 0 weeks 0 months critical year to4 ate value for the reporting Volume of Low 4evel Solid Radioactive Waste month (3.63) exceeds the 1992 Fort Calhoun goal of (Page 35) zero (0).

The 1992 year-end total (2,278.2 cubic feet) for volume of low ~ level solid radioactive waste is well below the goal Unolanned Safety System Actations (INPO Definitignl of a maximum of 3,000 cubic feet per year.

(Page 9)

The number of unplanned safety system actuations heventive Maintenance items Overdue (INPO definition) year-to-date (1) exceeds the 1992 Fort (Page 61)

Calhoun goalof zero.

The percentage of preventive maintenance items over.

due has been below the 1992 goal of a maximum of Uno!anned Safety System A-tuations fNRC Definitient 0.5% for the last six months of the year.

(Page 11)

The number of unplanned safety system actuations Procedura! Noncomoliance incidents (Maintenance)

(NRC definition) year to-date (4) exceeds the 1992 Fort -

(Page 67)

Calhoun goalof a maximum of 3.

l There were no procedural noncoraphance incidents dur-ing the last eight months of the year.

Therma! Performance I'

(Page 21)

Outstandino Modificati9nt The thermal performance value for the reporting month (Page 121)

(99.1%) is below the goalof 99.3%, however the 1992 The total modification packages open has decreased monthly average v, Cue (99.4%) exceeded the goal of.-

from 251 in January 1992 to 127 in December 1992.

99.3%.

Unit Cacability Factor End of Positive Trend Report (Page 25)

The Unit Capability Factor for 1992 (61.3%) is below the ADVERSE TREND REPORT 9 ' " 2%-

A Performance Indicator which has data representing p

2 three (3) consecutive months of declining performance The Unplanned Capability Loss Factor for 1992 (14.0%)

constitutes an adverse trend. The Adverse Trend Report is above the goalof 4.5%.

l explains the conditions under which certain indicators l

are showing adverse trends.

Planned Caoabili'v Loss Factor The following indicator is exhibiting an adverse trend for fhe la ed Capability Loss Factor for 1992 (24.7%) is the reporting month; above G,e goalof 26.3%.

i.

(-

CorrecHvo Maintenance Backloo Greater than 3 Months N Won utag he ye to-date milective radiation exposure for the "O

E n dve e trend is indicated based on three consecu-

* #9 tive months of declining performance.

i.

End of Adverse Trend Report.

INDICATORS NEEDING INCREASED PERFORMANCE INDICATOR REPORT MANAGEMENT ATTENTION REPORT IMPROVEMENTS / CHANGES (cont'd; This section lists signNicant changes made to the report Disablino iniurv/filness Frecuenev Rate (Lost Time Acci-and to specific indicators within the report since the pre-dont Ratet vious month.

(Page 37)

Ths disabling injury / illness frequency rate year-to-date value for the reporting month (1,05) exceeds the 1992 Percent of Comoleted Scheduled Maintenance ActMtieg Fort Calhoun goal of 0.30.

(Pages 68 tb ough 72)

The graphs for those indicators have been revised to Recordable Inlurv/t!! ness Cases Frecuency Rato show data for each month rather than for each week.

(Page 39)

The recordable injury / illness cases frequency rate for the Enoineerino Assistance Roouest Breakdown months f rom January 1992 through December (3.15)

(Page 123) exceeds the Fort Calhoun goal of a maximum of 2.0.

The graphs for this indicator have been revised.

Eculomant Forced Outaces oer 1.000 Critical Hours (Page 43)

The equipment forced outages per 1,000 critical hours End of Performance Indicator Report improvements /'

year-to-date value for the reporting month (0.86) ex-Changes Report coeds the 1992 Fort Calhoun goal of 0.20.

Secondary System Chemistry (Page 83)

The Chemistry Performance Index for the reporting montn (0.488) exceeds the 1992 goal of 0.45.

in-Line Chemistry Instruments Out-of-Service (Page 89)

The number of in-line chemistry instruments outof ser-vice for the reporting month (19) exceeds the 1992 Fort Calhoun goalof a maximum of 6.

Maximum Individual Radiation Froosure (Page 93)

The maximum individual radiation exposure year to-date value for the reporting month (1,860 mrem) exceeds the 1992 Fort Calhoun goalof a maximum of e,500 mrem.

Total Skin and Clothino Contaminations (Page 95)

The cumulative skin and clothing contaminations year-to-date for the reporting month (273) exceeds the 1992 Fort Calhoun goalof a maximum of 144.

Violations!1.000 Insoection Hours (Page 141)

The violations per 1,000 inspection hours value for the last twelve months (2.32) exceeds the 1992 Fort Cal-houn goal of a maximum of 1.5.

End of Management Attention Report.

I l

- Table of-Contents / Summary INPO INDUSTRY KEY PARAMETERS EAGE OPPD lNDUSTRY

.QEED.~

UPPER 10%

QQiL TFHS MONTH LAST MONTH IBQQ UNPl.ANNED AUTOMATIC REACTOR SCRAMS PER 7,000 HOURS CRITICAL...-......... 0.6.... 0 ;...~... 3.63 ;..... 4.16 NMA....7.-

SAFETY SYSTEM PERFORMANCE o.nmoung HIGH PRESSURE SAFETY INJECTON SYSTEM =.....

..00012..

..<0.006..

0.0009 0.0011........ N A.,.. 13 AUXILIARY FEEDWATER SYSTEM................ 0.0038....... <o.01.....o.0062..... 0.0067..._... NA....15 -

EMERGENCY AC POWER SYSTEM...

.m..

...o0055.

.. <0 024.. 0.0015.,... 0.0012...... N A....17 THERMAL PERFORMANCE........ ~............ 99 e%....>99.3% _.:.99.1C... 99.1%....NMA '.. 21 '

UNIT CAPABILITY FACTOR ~..

...................... 89 6L... >s9.2%.. 100L....100% ;..,..NMA.... 25 UNPLANNED CAPABILITY LOSS FACTOR,.............

).a5L....<4.5%... 0%....... 0%........ NMA...;.27 -

FUEL RELIABILITY INDICATOR m==ua y.n

.. NA......co.75x10 3 0.83 10 3..o 896 X10-3 i

..NA..

. 31 -

COLLECTIVE RADIATION EXPOSURE (pmosom).' 115 6/YR.<250/YR. 255.6.......

253.4......NMA...;.33 VOLUME OF LOW LEVEL SOLID RADIOACTIVE WASTE (cutac n.) =

... 2.077.9/YR <3.000/YR '. 2.278.2.~... 2.209.3.

.. N A...... 35.

. INDUSTRIAL SAFETY ACCIDENT RATE / DISABLING INJURY /lLLNESS FREQUENCY RATE..

0.12.~.:

.;<o.3

....1.05 ;...

..1,12....... NMA. 37 -

CHEMISTRYlNDEX/ SECONDARY -

SYSTEM CHE MISTRY

..........,..................... 0.20..... <o.4 5.....

0.488.. ;..J.0.449...... N MA.. 83 i.

INDUSTRIAL SAFETY EAGE NOUSTRY QEEQ QEEQ UPPER 10% QQ6L THIS MONTH I AST MOPUH IBQQ OlS ABLING INJURY /lLLNESS FREQUENCY RATE....o.12..

... <0.3 ;.

....1.05 =

- 1.12..

..NMA '.. 37

- RECORDABLE INJURY /lLLNESS CASES FREQUENCY RATE.....................

.....J. NA...,..,<2.o...... 3.15...-. 3.36..,..,,. N MA... 39 OPERATIONS EAGE NDUSTRY

.QEEQ.

QEED-UPPER 1Mr.

QQ&L THl3 MONTH t AST MONTH 18D0 STATON NET GENERATON (10.000 Mwh)..

... NA..

,.. NA..,,.. 36 = 2..,

34 4..

.. l...... 3 FORCED OUTAGE RATE............-....

...... 0.25L... <2.4%

.10.09%.,.. 10 09%.....NMA... 5 UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7,000 CRITICAL HOURS............. 0.6 L.....

..o.. -... 3.63

.....).16.... NMA. 7 g

- UNPLANNED SAFET( SYSTEM ACTU ATONS - (INPO DEFINITON)....................o......

....o........ 0

...oa NMA....9 iii e

OPERATIONS (Cont'd).

PAGE remar

.oeca.

crec UPPE A in QQM, TH!S IK) NTH LAST hENHH I,8f,20 UNPLANNED SAFETY SYSTEM ACTUATIONS - (NRC DEFINITION)...........

..0.....

. <3......, 0...,.. 0.'..-..... N MA.... 1 1 -

GROSS HEAT RATE...........-.................. NA

.. NA.....,10.044.

10.069........ l...... 19 EOUlVALENT AVAILABILITY FACTOR..............NA..

.. N A..

.100%...._.. 100% -..

.. l...... 23 UNIT CAPABILITY FACTOR..........................89.6%.....>69.2%

.100%.....100%......N'MA 25 UNPLANNED CAPADILITY LOSS FACTOR..........1.85W.... <4.5%.... 0%....... 0%.... NMA... 27 PLANNED CAPADILITY LOSS FACTOR.......... 8.55%... <26.3%... 0% L.

- NMA. 29 FUEL RELIABILITY INDICATOR (microcur:ss/ gram)...NA.

..<0.75x104 0.83x104. 0.896 X 10-3.... N A... 31 DAILY THERMAL OUTPUT (Mwth).

.. NA........ > 1,4 95.... NA,.

..NA.,

.. N A,.... 41 EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS...........,..

............NA....

... <0.2 _

0.86...... 0.99...... N MA.... 43 OPERATIONS AND MAINTENANCE BUDGET...... N A..

.. N A..

.. NA..

.. N A...... 45 DOCUMENT REVIEW...

.. NA..

.. N A..

.. NA.....-.. N A.,. 47 MAINTENANCE PAGE INDUSTRY

,QEgQ, QEgQ UPPER th QQM, TH'S MONTH LAST MONTH Tf!END EMERGENCY DIESEL GENERATOR UNIT RELIABILITY.

.. NA.

.. NA..

.. N A...

.. NA..

.. N A..... 49 DIESEL GENERATOR REllABILITY (25 DEMANDS).

NA

..<4.

.. NA _...

.. NA..

.. NA.,. 51 DIESEL GENERATOR UNAVAILABILITY <cumutanve rra) NA..

.. <210.8/DG.... NA..

...... N A..

,.. NA... 53 AGE OF OUTSTANDING MAINTENANCE WORK ORDERS (CORRECTIVE NON. OUTAGE)... N A..

.. N A..

.. NA.,

.. NA..

.. NA..... 54 MAINTENANCE WORK ORDER BREAKDOWN (CORRECTIVE NON OUTAGE).......NA.,

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

.. NA..... N A.... 55 CORRECTIVE MAINTENANCE BACKLOG GREATER THAN 3 MONTHS OLD -

(NON-OUTAGE)..

. NA.........N A,.. _ BS.0L...... 78/.%...

A.

57 RATIO OF PREVENTIVE TO TOTAL MAINTENANCE.

.. NA..

.. >65%... 77.71.

,. 79.7%..

.. D.... 59 PREVENTIVE MAINTENANCE -

ITEMS OVERDUE.,

.. NA.

.. <0 5%... 0%.

. 0 39%.

l.-. 61 NUMBER OF CONTROL ROOM EQUIPMENT DEFICIENCIES

.. N A.

.. <50..

. 44.

.47

.. l... 63 MAINTENANCE OVERTIME.

... NA..

.. <10%.. 12.6%..

. 6.2%.

.. D... 65 iV

M AINTENANCE -(cont'd))

f1GE wnusTRy

.Qgett ogen urnrR 1h QQ&l, R[19 MONTH I AST MONHi TriND PROCEDURAL NONCOMPLIANCE

..... N A......

...0....

0...

..N A...... 6 7 INCIDENTS (MAINTENANCE)............

PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (ELECTRICAL MAINTENANCE).,

.. N A..

.. >80%...... NA......... N A..

...NA. 68 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES

.. N A..

.. >80%..... N A...... N A.....

NA..... 69 (PRESSURE EQUIPMENT)........

PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (GENERAL MAINTENANCE).

.... NA..

.. >80%..

.. N A..

...... N A...... N A..... 70 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (MECHANICAL MAINTENANCE).

.. NA.,

.. >80%..

.. N A..

.. N A.... 71 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (INSTRUMENTATION & CONTROL)....

.. NA..

.. >80%..

.. NA..

.. N A

.. N A.... 72 NUMBER OF MISSED SURVEILLANCE I

TESTS RESULTING IN LICENSEE EVENT REPORTS.

.... NA...-... 0..

.. 0..

,,0........ N A. 73 COMPONENT FAILURE ANALYSIS REPORT (CFAR)

SUMMARY

.... NA..

,, N A..

.. NA...

.. NA........ N A.... 75 NUMBER OF NPRDS

.. NA..

.. NA...

.. N A..

,. NA..

,. NA...,. 77 MULTIPLE FAILURES.,

MAINTENANCE EFFECTIVENESS..-

... NA....

.. NA..

.. NA...79 CHECK VALVE FAILURE RATE.

.. NA -... <2.00E4.,.1.2 t E4.

1.23E4.

l...... 81

' _ CHEMISTRY AND RADIOLOGICAL PROTECTION -

P/ tie INDUSTRY

.QEED.

QEED UPPrR1 M GQ6L THIS MONTH LAST MOrmi IBEvg COLLECTIVE RADIATION

- EXPOSURE (person-rem).......

................ 115.6/YR...<250/YR 255.6..

253.4..

..NMA... 33 VOLUME OF LOW. LEVEL SOLID RADIOACTIVE WASTE.,

.. 2,078/YR...<3,000/YR. 2.278.2.... 2,209.3..

.. NA

. 35 SECONDARY SYSTEM CHEMISTTlY.....

..o.20 ;,

..<0 45.

J. 0.488 '...

0.449.;..... NMA.... 83 PRIMARY SYSTEM CHEMISTRY -

PERCENT OF HOURS OUT OF LIMIT..-..

.... NA..

.. < 2%........ %.

. 0.55%..

.. l

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

.. N A.._.... N A..... %.

. 8 8%..

.. l..

. 87 IN.LINE CHEMISTRY INSTRUMENTS OUT-OF-SERVICE :..........:

.........-.............HA...

. <6....... 19.......

17-NMA... 89 Y

________m______._______

1 CHEMISTRY AND RAD]QLOGICAL PROTECT 10H (cont'd)

PAGE

.goasinY

.000.

QEc0 um n ta nog, ungsnu l,A11 maH Uggi l

H AZARDOUS WAST E PRODUCCD.......................... NA,..

.. N A.

0,.,

.0.

... N A....... 91 l

i I

MAXIMUM INTVIDUAL RADI ATON EXPOSURE (mRom)............................ NA..... < 1,600NR.. 1.660.....-..1.766....

NMA..... 93 TOTAL SKIN AND CLOTHING CONT / MINATIONS......,.................NA.....=144..... 273......... 268...... H MA... 95 DECONTAMINATED RADIATON CON T ROLLE D ARE A................................ N A.

.A8%..

090%

.. 69 0%.

.. N A....... 97 RADOLOGICAL WORK PRACTICE S PROGR AM............................... NA.

... N A.

...0....

..A..

.. l......... 99 NUMBER C.i HOT SPOT S......,.........

...NA,.. remove 1/mo.. 64.

. 79.

...D......

GASEOUS RADICACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT (curies).....NA..

, c340/yr... 140 7.

.140 7...... N A....103 1,10UID RADOACTIVE WASTE BEING DISCHARGED TO THE ENVIRONI/ENT (curies)..... NA..

.. <225/yr... 39 6..

. 39 6...

.. N A..... 105 ECURITY.

f2GE

DJs1HY QECD QECQ umnsa gog, uns wwm att enn fru.fm LOGGABLE/ncPOR1 ADLE INCIDENTS (SECURITY)...

...................................NA.

.. N A... 53..

. 28.

... D...... 10 7 SECURl1Y NON. SYSTEM FAILURES...........,........NA..

. NA..

.. N A..

... N A....... N A..... 108 SECURITY SYSTEM FAILURES.........

........NA.

.. N A..

.. N A.

. NA..

.. N A..... 109 MATERIALS AND OUTSIDE SERVICES IMGE m miny QtcQ QCEQ ucrrn sa gaat tum enn LAgungu ngga AMOUNT OF WORK ON HOLD AWAITING PARTS (NON. OUTAGE).......

.........NA.

.. <3 6%,..-. 2.11 %..,

.1.9%.

.... D.... 111 SPARE PARTS INVENTORY VALUE ($ million).........NA..

NA..

. 13 1..

. 131...

.. N A..... 113 SPARE PARTS ISSUED ($ thousands),.

..............,NA,

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

. 266.3..

... N A..... 113 INVENTORY ACCUR ACY............................. NA..... >99%... 90%..- u.. 98%..

.. N A......115 STOCKOUT RATE.....................

,..............NA.

x2 6%.,. 0 47%..

. 0%..

... D...,,. 115 EXPE DITE D PURCH AS E S.,.-................................ NA,

.. <0.5%.. 0%..

.0%

...,NA....117 INVOICE GRE AKDOWN.............................. NA,,...-..... NA..

.. NA.

NA..

., N A.. _.119 '

MATERIAL REQUEST PLANNING................

,, N A.,

,.. N A... 41.7%.

. 50%..

... l..... 119 tl

DESIGN ENGINEERING PAGE en ntnv Octu QtED uttg. lug QQ&l, 311t W H LAsfhoNTH THLW OUTST ANDING MODIFICAT ONS................... N A.

., NA.

.127.

.145..

.. l...... 121 TEMPORARY MODIFICATIONS (EXCLUDING SCAFFOLDING)..

...NA.

. 0 1 cycle.. 25...

. 24.

... N A.....122 ENGINEERING ASSISTANCE REQUEST (EAR) BREAKDOWN..

........... N A.

.. NA.

.130..

. 159.

.. l...... 123 ENGINEERING CHANGE NOTICE STATUS....,......NA...

.. N A..

.145....

.14s.

.. N A....125 ENGINEERING CHANGE NOTICE BREAKDOWN......NA.

.. N A..

.. NA.

... N A...

... N A...127 HUM AN RESOURCES P. AGE m ainy DEED 000D overn m gm ites mmt atiucumj ngs NUMBER OF PERSONNEL ERRORS REPORTED IN LERs,..

........ N A..

... NA.

. 1...

.0...

. D......129 LER ROOT CAUSE BREAKDOWN......................NA.

.. NA..

.NA.

.. N A..

NA...130 ST AF F ING LE VEL.................................... N A.

.. N A...

.. NA.

.. N A...

.. NA....131 PERSONNEL TURNOVER RATE.......

... N A..

.. N A...

.. NA.

....NA..,

..... N A.... 131 TRAINING AND OUAllFICATION P. AGE munit occo octu UE1 Huh QQ&L TH!s hormt tnt uontu InrNo N

LICENSED OPERATOR REQU AllFIC AT ON TRAINING.................,........ N A.,.... N A..

.. NA.,

.. N A....

.. N A..... 133 LICENSE CANDID ATE EXAMS............................ N A.

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

.. NA..

... N A....135 TOTAL IN STRUCTON HOURS,.....,................. N A,

..NA.

1.229..

. 2,154..

.. N A..... 137 TOTAL HOURS OF STUDENT TRAINING..

......... N A..

.. N A..

,,6,161

. 9.29 7...

..-.. N A..... 139 OUALITY ASSURANCE PAGE 6n stnv DEED OctD LIPPE.R 10% gD6L THis MONTH L Asi 60 NTH TREND VCLATONS PER 1.000 INSPECTON HOURS......... NA.....

... < 1.5....... 2 32.......... 2.34

... NMA..141 COMPARISON OF VIOLATONS AMONG REGION IV PLANTS.......................... N A.

.. N A..... N A..

.. N A..

.. N A..... 143 CUMULATIVE VIOLATIONS AND NOVs (TWELVE-MONTH RUNNING TOTAL)....

.. N A.

., N A...~.14/2.

102..

..NA..,145 OUTSTANDING CORRECTIVE ACTON REPORTS...........,,...

.... NA..

.. N A.

. 72.

. 81.-

..l....147 vii

OUALITY ASSURAfCE(cont'd)

EAGE IIU1'31 0 01'2 011 0 orrv n in goat inisinmi U.ninttH Ugsa OVERDUE AND EX1 ENDED CORRECTIVE ACTION REPORTS..

..... NA.

.NA.

. 0/11..

M.

. D..

.149 CARS ISSUED vs. SIGNIF. CARS vs.

NRC VOLAllONS ISSUED vs.

LERs REPORTED...

.. N A..

.. N A.

. NA..

.. NA.. 150 BEFUEtIN3 OUIAOL w ustnv onn otta um R % GQ6L fHisinmi ustinma Inggi MWO PLANNING STATUS.,

..... N A..

.. NA..

.. N A.

.. N A..

.. N A...1 $1 OVERALL PROJECT STATUS.

,, N A.

.. N A..

.. N A.

.. N A..

..NA.

. 152 PROGRESS OF CYCLE 15 OUTAGE MODIFICATION PLANNING....

...NA..

N A..

.. NA.

.. NA..

.. N A.. 153 PERFORMANCE INDICATOR DEFINITIONS.......

..1$4 SAFETY ENHANCEMENT PROGRAM INDEX...

..... 10 2 REPORT DISTRIBUTON LIST.......

..164 TABLE OF CONTENTS /

SUMMARY

TT1END SYMBOLS A. ADVERSE TREND 1 lMPROVED PERFORMANCE D = DECLINING PERFORMANCE NMA - NEEDS MANAGEMENT ATTENTION NA - NOT APPLICABLE /AVAILABLE viii t. mpir i

FOREWORD Performance indicator graphs for the years 1990 and 1991 are included in this report. These graphs are provided where appropriate comparisons can be made. In some instances, for example when the method of reporting an indicator has changed during 1992 or an indicator has been added to the report, the graphr, for previous years are not included.

1

i 1

i

}

i i

E Nel Geratbn (10.0M Mw Nurs) j 50-l l

40-36.17 44 et 35.06

)

31.1e I

j 30-27.9 ly111111i;d

.I t4 7e to es O

i i

Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 i

50-l 3 Net Generation (10,030 Mw hours) l 40 -

34 55

35. t

)

31.27 30-reos f

g,,,

27,ge g

Cycle 13 o

0 47 0

i i

i

i i

i i

Jan90 Feb. Mar Apr May Jun Jul Aug Sept Oct Nov Dec90 l

1990 l

l j

2

\\

50 -

[] Not Generat':n (10,000 Ma tours) 40-as95 se to 3o u st.se 0

i i

i Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Doc 92 STATION NET GENERATION During the month of December 1992 a not total of 3G1,792 MWH was gonorated by the Fort Calhoun Station. There woro no power reductions or unplanned energy lossos during December, November and October.

Unplanned energy lossos for the month nf Sp6tnber woro attributable to the forced outago which began on 8/22/92 when an 10 hO u.nvorter failed in the Turbine Electro Hydraulic Control system. Pressurizer sawr, wia RC 142 then opened prior to reach-ing design pressure and the plant tripped on TM/LP. The generator was brought on line at 2101 hours0.0243 days 0.584 hours 0.00347 weeks 7.994305e-4 months on 9/5/92.

Unplanned energy lossos during August wore the roJult of the forced outage on 8/22/92 (described abovo) and the forced outage that bogan on 8/5/92 when a foodor breaker to the 125V DC panol Al 41 A failed resulting in a controlled shutdown to Modo 2. The turbino generator was synchronized to the grid on 8/6/92.

Unplanned energy lossos for the month of July were a result of the forced outage that 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 0.169 hours 0.00101 weeks 2.32105e-4 months on 7/23.

During the month of Juno 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 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 0.288 hours 0.00171 weeks 3.938175e-4 months and the generator was put on line on 5/3/92. A forced outage occurred on 5/14/92 when the turbino generator tripped on a falso high level moisturo separator trip signal which caused a simultaneous reactor trip.

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

Unplanned onor0y losses for May were: 1) the Cycle 14 Refueling Outage extension; 2) the reduction to 58% power for repair of an inoporable condenser valve: 3) the reactor trip; 4) the hold at 48% power for repair on a feodwater pump suction valve; and 5) the 5/31 dropped control rod caused by a faulty clutch coil.

Data Source: Station Generatlun Report Accountability: Chaso Adverse Trond: None 3

(

I r

20%~

Forced Outage Rate.

i

-O-Fort Calhoun Goal (2.4%)

(

.-D-Industry Upper 10 Percentile (0.25%)

16% -

[

l 10% -

t 5%-

C O

O O

M N

N N

n NA' N--n

-0%

Jan91' Feb Mar Apr May Jun-Jul Aug Sep Oct Nov Dec91 1991 i

2W. -

Forced Outage Rato

-O-Fort Calhoun Goal (2.4%) -

i

-O-Industry Upper 10 Percentile (0.25%)'-

-j 10% -

i 5%-

C O

.O O

O' O

O O

'O.

O 0% ~ -C C ~"

Jan90 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec90 '

1990 4

.i s

,,.4 4

.,--,..v.y+

,I.%..y y

,.rr

..--+w,Eb.

,.3 m,

Forced Outage Rato

[GOODI V

-O-1991 & 1992 Fod Calhoun Goals 20%-

15%-

97 9.3 10%-

_/

/

5%-

14 i

C O

O O

i i

0%

'89 '90 '91 Jan92 Fob Mar Apr May Jun Jul Aug Sep Oct Nov Doc 92 FORCED OUTAGE RATE The forced outage rato (FOR) was reported as 10.09% for the twelve months from 1/1/92 to 12/

31/92. There woro no forced outago hours during the months of December. November and October 1992. Because this is a twelvo month rato, assuming no additional forced outages, the FOR Indicator will not improve until May 1993, when the May 1992 forced outago drops from the twelvo month Interval.

Forcod outage hours for September 1992 were duo to the forced outage that began on 8/22/92 when an AC/DC convertor f allod in the Turbino Electro Hydraulic Control system. Pressurizer safety valve RC 142 then opened prior to roaching design pressure and the plant tripped on TM/

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

During the month of August forced outage hours woro due to the forced outage on 8/22/92 (described abovo) and the forcod outage on 8/5/92 when the turbine was taken off-line to replace a foedor breaker to the 125V DC panol Al-41 A. The turbine generator was synchro-nized to the grid on 8/6/92.

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

3/92. Additionally, RC 142 oponod and failed to recloso. The generator was brought on line at 0610 hours0.00706 days 0.169 hours 0.00101 weeks 2.32105e-4 months 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 lino at 0852 on 6/2/92.

A forced outage occurrod on 5/14/92 at 1557 hours0.018 days 0.433 hours 0.00257 weeks 5.924385e-4 months when the turbine generetor 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 0.319 hours 0.0019 weeks 4.37575e-4 months at 5/15/92 following repairs.

The 1992 Fort Calhoun goal for the Forced Outage Rato is 2.4%.

Data Source: Monthly Operations Report & NERC GAD Forms Accountability: Chase Adverso Trond: Nono 5

5-3 FCS Reactor Scrams

-O-Fort Calhoun Goal 4-3-

2 --

1-0 0

0 0

U ' T-- V - T"~ C U

'M U

U U-T-U i 0----U-r-U i i

i i

i Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Doc 01 1991 5-FCS Reactor Scrams

--O-Fort Calhoun Goal 4-3-

2-1-

C C

C 0

0 0

0 Jan90 Feb Mar Apr Jun Jul -

Aug Sep Oct Nov Dec90 1990 6

Fcs neactor Scrams Per 7,000 Hours Cntical(Year-to date)

-+- FCS Reactor Scrams Per 7.000 Hours Cntical (for the last 36 months)

-O-1991 & 1932 Fort Calhoun Goals 1995 INPO industry Goal 10 -

" C} - Indsstry Uroer 10% (0.6 per 7,000 hours0 days 0 hours 0 weeks 0 months entical over a 36 month time period) e --

6-4-

b, b, b, h, h T~

Yi i

i I

O i

i Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec02 6-4-

E Number of Fcs neactor scrams 3-2 --

1 1

1 0 0 0 0 1-0 0

0 0

0 geum 0

0 0

0 08'09 90 91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 Ut4 PLANNED AUTOMATIC REACTOR SCRAMS PER 7,000 HOURS CRITICAL The upper graph shows the number of unplanned automtic reactor serams por 7,000 hours0 days 0 hours 0 weeks 0 months critical (as defined in INPO's 11/91 publication

Detailed Descriptions of International Nuclear Power Plant Periormanco Indicators and Other Indicators *) for Fort Calhoun Station. This value is calculated by multiplying the total number of scrams in a specified timo porlod by 7,000 hours0 days 0 hours 0 weeks 0 months , then dividing that number by the total number of critical hours in the same timo period.

The year to dato station value is 3.03 for the month of Docornber 1992 and the value for the last 36 months is 1.08.

The lower graph shows the number of unplanned automatic reactor scrams that occurred during each month for the last twelvo months.

The last unplanned automatic reactor scram occurrod on August 22,1992 as a result of the failuro of an AC/DC converter in the Turbino Electro Hydraulic Control system. Pressurizer safety valve RC 142 then opened prior to reaching design pressure 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 occurrod on May 14 at 1557 when the turbino generator tripped on a falso high level moisture separator trip signalwhich caused a simultaneous reactor trip. The last unplanned automatic reactor scram prior to this occurred on July 2,1986.

The 1992 goal for unplanned automatic reactor scrams por 7,000 hours0 days 0 hours 0 weeks 0 months critical has boon set at zero. The 1995 INPO industry goalis one unplanned automatic reactor scram por 7,000 hours0 days 0 hours 0 weeks 0 months critical. The industry uppor ton percontile value is approximately 0.0 scrams por 7,000 hours0 days 0 hours 0 weeks 0 months critical for the 36 month timo period from 7/89 through 6/92.

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

Accountability: Chase Adverso Trond: None 7

3-INPO Safety' System Actuations

-O--

Fort Calhoun Goal

Industry Upper 10 Percentile 2-1-

0--O O

O O

,C O

--G-r--C O

O.,O O

i i

i Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1

l 1991 3-3 INPO Safety' System Actuations -

-O-Fort Calhoun Goal

-O - Industry Upper 10 Percentile-2-

1-0-

~

Jan90: Feb Mar --

Apr May

-Jun.

Jul Aug-Sep

- Oct ;

Nov - Dec90 -

1990 r r

-e wr b.h yei,..

.+m',-

,.vw,i.,

.-,c

,g g

4

i 3-

'E INPO Safety System Actuations

+ 1992 Fort Calhoun Goal

-O-Intetr/ Upper 10 Percentile t-1 1-e fl O--E O

O O

O i

i i

'89 '90 '91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 UNPLANNED SAFETY SYGTEM ACTUATIONS-(INPO DEFINITION)

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

There was one unplanned safety system actuation during'the month of July 1992 d'ue to the loss of an Inver+sr and the subsequent reactor trip on 7/3/92.

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

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

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

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

.._.J

...~ -.

-.. ~. _ _. -

- 12 Month Running TotalNRC SSAs

, Critica1 Hours E NRC Safety System Aduations (SSAs) 1000 to-900 800 8-700 N:a i

600 f

!!6-N Y

500h.

[

E

-f-e a y-

.R S

300 2-200.

i 100 t

0 0

J90 F

M A

M-

.J J

A S

O N

090 r

1990 i

L

'b i

i 10 -

.. ~

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

12 Month Running Total NRC SSAs

-O-cr.;k.at Hours j

Q NRC Safety System Actuations (SSAs) j 10-100o 900-

-l 8-800 7

~700 m

6-600 f

Soo -

g 64-doo

' \\

t i

2 2

-100 g

o

^

o

'89 '90 '91 J FMAMJJASONDJ FMAMJ JASOND 1991 1992 UNPLANNED SAFETY SYSTEM ACTUATIONS-(NRC DEFINITION)

Th's indicator shows the number of unplanned safety system actuations (SSAs), which includes the High and Low Pressure Safety injection Systems, the Safety injection Tanks, and the Emergency Diesel Generators. The NRC classification of SSAs in-ciudes 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 December 1992.

The last 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. Pressur-Izer 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 inverter failure and the subsequent reactor trip; 2) On July 23 there was an.

unplanned diesel generator start when an operator performing a surveillance test inad-vertently pushed the normal start 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 11

_ - ~..

l 0.025 -

3 1991 Monthly High Pressure Safety injection System Unavailability Value

-N-1991 High Pressure Safety injection System Unavailability Value Year to Date 0.02-

-O-1991 Fort Cathoun Goal 0.015 -

l GOODI t

0.01 -

o o

0 0

0.005 -

k 0-Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91

.1991 T-12

E 1992 Monthy High Pressure Salety injection System Unavaltability Value

-M-1932 High Pressure Safety injection System Unnvailability Value Year to-Date

-O--

1992 Fort Calhoun Goal

--h - 1995 INPO Industry Goal (0.02)

-O-Industry Uppor 10% (0.0012) 0.025-0.02-A A

A A

A 0.015-Cycle 14 0.01-Refueling O

O O

Outage 0.005-NE, C, fr== C N

3- - -O O

i i

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 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 Safoty injection System unavailability value for December 1992 was 0.00. There were no (0) hours of planned or unplanned unavailability during the month.

The 1992 year to-date HPSI unavailability value was 0.0009 at the end of December..

In November there were no (0) hours of planned or unplanned unavailability. There were 1.05 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months of planned unavailability in October. There were no (0) hours of.

1 planned or unplanned unavailability in September. There were 1.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of planned unavailability for surveillcnce tests in August, in July there were no (0) hours of planned or unplanned unavailability. In June there were 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months of planned unavailability for surveillance tests and in May there were 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months of planned unavailability for surveillance tests.

The 1992 Fort Calhoun goal for this indicator is 0.008. The 1995 INPO industry goalis 0.02 and the industry upper ten percentile value (for the three year period from 7/89 through 6/92) is approximately 0.0012.

Data Source: Jaworski/Schaffer Accountability: Jaworski/Schaffer A.dverse Trond: None 13

)

t 3

1991 Monthly Auxiliary Feehater System Unavailability Value 1991 Auxillary Fee #ator System Unavaltability Value Year to-date

+ 1991 Fort Calhoun Goal 0.025 -

0.02-C O

O O

lGOOM 0.015 -

t 0.01 -

0.005 -

0 i

i i

i Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 s

a 14

=

]

O 1992 Monthly Auxiliary Feedwater cystem Unav:llabmty Vclue -

-et-1992 Aur.iliary Feodwater System unavailability Value Year.to< late

-O-1992 Fort Ca.un Goal

--s%--

1995 INPO Industry Goal

-cb industry Upper 10% (0.0038) 0.025-A A

A A

A o.02-Cycle 14 0 016-Refuehng A;;;ife_1 3;;;;EEN s-1 oa:

Jan92 ' Feb ' Mar Apr

'a Jun Jul Aug Sep

' Oct ' Nov ' Doc 92 '

AUXil.

.( FEEDWATER SYSTEM SAFET i SYSTEM PERFORMANCE This indicator shows the Auxiliary Feedwater System Unavailability value, as defined by INPO in the Safety System Periormance Indicator Dofinitions, for the reporting month.

The Auxiliary Foodwater System Unavailability Value for December 1992 was 0.0029, There woro 4.33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months of planned unavailability for surveillance tests and FW 6 mainte-nanco during the month. The 1992 year to dato AFW unavailability value was 0.0062 at the end of December, in November, there woro 0.35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months of planned unavailability for surveillance tests.

There were 4.45 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months of planned unavailability for surventance tests and 16.43 hours4.976852e-4 days 0.0119 hours 7.109788e-5 weeks 1.63615e-5 months of unplanned unavailability for FW 6 during October due to problems incurred during surveillance testing.

There were 0.67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months of planned unavailability for surveillance tests in September and 16,43 hours4.976852e-4 days 0.0119 hours 7.109788e-5 weeks 1.63615e-5 months of unplanned unavailability for repair of YCV 1045.

There woro 1.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of planned unavailability for surveillance tests in August and 1.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of plannod unavailability for surveillance tests in July.

In June 1992 there wore 2.82 hours9.490741e-4 days 0.0228 hours 1.35582e-4 weeks 3.1201e-5 months of planned unavailability for a PM an:) ?.33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months of unplanned unavailability for corrective maintenance on a flow instrument, in May 1992 preventive maintenance activities resulted in 2.67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months of planned un-availability and there were 10.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months of unplanned unavailability due to corrective maintenance following the initial attempt to perform a PM.

The 1992 Fort Calhoun goal for this indicator is 0.01. The 1995 INPO Industry goal is 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 Adverso Trend: None 15

L 4

1 3

1991 Monthly Emergency AC Power Unavailability Value l

-N-1991 Emergency AC Power Unavailability Value Year to Date q

i

--O-1991 Fort Calhoun Goal (0.024) l 0.06 -

l GOOD]

0.05-p l

c 0.04-l 0.03-

---C O

O i

^

0.02-i f

O,01 -

0 i

i i

i Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 r

s l

~

i 16

+-...-~---.-.~ --...,_ C.

.--,...-...-...-...,_.-_.-..._.,._~---..-.r.--,._.,-..--4 L.~.

.--~~,..___...-_.-._-..e-.~--

5 1992 Monthly Emergency Af. Power Unavailability Value

-W-1992 Emergency Ao Power Unavailability Value Year to Date I GOODI O.oD-

-O-1992 Fort Calhoun Goal (0.024) 0.05 ~

- 1995 INPO industry Goal (0.025) 0.04 -

-Q-Industry Upper 10 % (.0055)

I 0.03-6 a-o 6

6-6

?

4 4--4 e

0.02 -

0.01 -

o a

o o

-%-n g---g g

g g

n o --+, =,=,=,

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov = Dec92 EMERGENCY AC POWER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Emorgency AC Power System unavailability value, as defined by INPO ln the Safety System Performance Indicator Definitions, for the reporting month.

The Emergency AC Power System unavailability value for December 1992 ls C 0045 There were no (0) hours of planned or unplanned unavailability for DG 1 in December.

There were 6.67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months of planned unavailability for maintenance and no (0) hours of unplanned unavailability for DG 2 in December. The Emergency AC Power System unavailability value year to-date is 0.0015.

There were no (0) hours of planned or unplanned unavailability for DG 1 or DG 2 from September through October. There were 2.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months of planned unavailability for DG 1 in August to inspect relays for contact degradation, in July there were no (zero) hours of planned or unplanned unavailability. In June 1992 there were 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months of planned unavailability for DG 2 for retorqueing radiator fan retain-ing bolts.

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

The 1992 Fort Calhoun goal for this indicator is 0.024. The 1995 INPO industry goal is 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/Ronning Adverse Trend: None 17 2-

13-E Monthly Gross Heat Rate

~

--A-Year to Dato Gross Heat Rato i

11-M mH Hit Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Doc 91 1991 E

Monthly Gross Heat Rato

--A-Year to-Date Gross Heat Rate i

!12-11-Cycle 13 Refueling 10-Jan90 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec00 1990

t 13-i E

Monthly Gross Heat Rate j

-k-Yea 6to Date Gross Heat Rate IGOODI y

h12-e to a

11-10500 g,

'89

'90

'91 Jan92 Feb Mar Apr May Jun Jul Aug Sep' Oct Nov Dec92 l

GROSS HEAT RATE This indicator shows the Gross Heat Rate (GHR) for the reporting month, the year to-dato value, and the year end GHR for the previous 3 years.

The gross heat rate for the Fort Calhoun_ Station was reported as 10,045 BTU /KWH for the month of December 1992. When the plant operates at a nominal 100% power, the monthly gross heat rate improves during winter months as a result of the decrease in river water temperature. This is because the gross heat rate is not normalized to the design river water temperature of 60 degrees Fahrenheit.

The year to date gross heat rate was reported as 10,177 BTU /KWH at the end of De-cember.

Data Source: Holthaus/ Gray (Manager / Source)

Accountability: Chase /Jaworski Adverse Trends: None 19

(This page intentionally left blank.)

(This indicator was not monitored in 1991.)

20

O 1992 Monthly Thermal Performance

- 1992 Year to Date Average Thermal Performance

-- G - 19v.7 ' ort calhoun Goal (99.3%)

[G D]

--/s--

1995 INPO Industry Goal (99.5%)

-O-Industry Upper 10% (99.8%)

100 % -

D D

O--O D-- g O---O O

O O

O A

A A

W M

M Aan A

A

'd 5

5 E

@ c 6

~ - -

99%-

46-y i;l B

Cycle 14 d0 Refueling

[

age 98%-

p il w 1

r$P i

6f j

(f

'M 7..

9 7% --

y k[

li[

b :.

i$

Ib 96%

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 THERMAL PERFORMANCE This indicator shows the Thermal Performance value for the reporting month, the year-to-date average thermal performance value, the 1992 Fort Calhoun goal, the 1995 INPO Industry goal and the approximate industry upper ten percentile value.

The thermal performance value for the reporting month was 99.1%. The year to date average monthly thermal performance value was 99.4%.

The declining thermal performance values in July through October may be due to circu-lating water flow reductions possibly caused by condenser fouling and/or circ. water pump degradation. The decline in November is attributed to initiation of warm water recirculation and the drop in river water level.

System Engineering Department plans to evaluate condenser and cire, water pump conditions during the next available power reduction.

The 1992 Fort Calhoun Goal for this 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: Nnne 21

O Monthly EAF Year to-Date EAF 100%-

p lr N

2 r

/

00%-

r 60%-

tin

+

40%-

g.s 1

,x

.7 T

20%-

.q 0%

Jan91 Feb M r.t Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 O

Monthly EAF Year to Date EAF 100%-

80%-

i Cycle 13 4

60%-

Refueling 3

7

~

Outage y

y 5

n 40% --

3/

H i

y o

m s.

. o.

4 20% --

y s...

0%

i i

Jan90 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec90 1990 22

t O

Monthly EAF lGOODI Year.to Date Average EAF 100 % -

7 j

1l

~

85.6 77 80% '

7 so.c 60%-

Cycle 14 p

i 4

J T

Refuehng A

M f

Outage j

W f

l

\\

?

j en

=

?

r 20%-

y 3

f s

3 a

4:

c

.s 4

0% --

i i

'89

'90

'91 Jan92 Feb Mar Apr May Jun Jul - Aug Sep Oct Nov Dec02 EQUIVALENT AVAILABILITY FACTOR This indicator shows the plant monthly Equivalent Availability Factor (EAF), the year to.

i date average monthly EAF for 1992, and the EAF for the previous 3 years.

The EAF for the month of December was reported as 100%. The year to-date average monthly EAF was reported as 60.8% at the end of December.

The EAF for September 1992 was reported as 81%. This figure is the result of a forced outage that began on 8/22/92 when an AC/DC converter failed in the Turbine Electro Hydraulic Control system. Pressurizer safety valve RC-142 then opened prior to reach-ing 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 DC 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.

Data Source: Dietz/Parra (Manager / Source)

Accountability: Chase Adverse Trend: None 23

D 1991 Monthly Unit Capability Factor

- M--

1991 Year to Date Average Unit Capability Factor

-O-1991 Fort Calhoun Goal 100% -

e m

Q-----

^

O- - o p O-y q

7 l;

ynl V

y l

se t l gp_

60% ~

g y

ll

?

Q

@V V

i' t

']

he l

w "W'

60% ~

u h

m 36 9A pg; g<...

l 4.3 c

\\

y:;

4 e

Fj 1,s t

A k

iz iba M

9 7

[!i M

(p la 2r M

e

.?

40%-

T Q

f d

%c

.p; V

sg.

w x;

n

s ;'

ou

?

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Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 2

24

Q 1SC2 Monthly Unit Capshility Footor

' 1992 Year to-Date Average Unit Capability Factor

-+- 38 Month Average Unit Capaoelity Factor a-C>-

1992 Fort Calhoun Goaf

- tw = 1996 iNPO Industry Goal (80%)

@ industry Upper 10% (89 8% for a Three Year Average)

O O

Q Q - Q - --- Q Q

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=

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i Outage

+

^

Jan92 ' rou ' Mar Apr ' May ' Jun Jul Aug ' Doo ' Oct ' Nov Dec92 UNIT CAPABILITY FACTOR This indicator shows the plant monthly Unit Capability Factor (UCF) value, the 1992 year to-dato average monthly values and goal, the 36 month average values, the 1995 INPO industry goal and the approximato industry upper ton percontilo value. UCF is defined as the ratio of the availablo energy generation over a glvon period of time to the reference energy generation (the energy that could be produced if the unit were operated continuously at full power under refer.

ence amblent conditions) over the same timo period, expressed as a percentage.

The UCF was reported as 100% for the month of Docomber 1992. Tho year to dato avorage monthly unit capability factor was reported as 61.3%

The UCF was reported as 77.5% for the month of September 1992. Unplanned energy lossos 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 hou's on 9/5/92.

The UCF was reported as 62% for the month of August 1992. Unplanned energy losses for tho -

month were a result of the 8/22/92 forced outago (described abovo) and the forced outage on 8/ -

Si32 when a feedor breaker to sho 125V DC panel Al 41 A failed. The turbine generator was -

synchronized to the grid on 8/6/92.

The UCF was reported as 34% for the month of July 1932. Energy lossos for the month were due to the forced outago 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 1995 INPO industry goal is 80% and the industry upper ton percentilo value (for the three year period from 7/89 through 6/9F is approximately 89.6%

The 1992 Fort Calhoun goal for Unit Capability Factor is 69.2% The basis for this goalis 86 -

days for the Cycle 14 Refueling Outage,20 days rampup (10 full power equivalent days),

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

Data Source: Ger' oration Totals Report & Monthly Operating Report Accountability: Chase Positive Trond

S u

m-

. ~ -..

l-Q 1991 Monthly Unplanned Capability Loss Factor -

100% -

--M--

1991 Year-to-Date Average Unplanned Capability Loss Factor-lGOODI 80%-

--O-1991 Fort Calhoun Goal 4

- 1995 INPO Industry Goal 60%-

g s

l 40%-

[11 0 m

,A-I 20%-

AA v

{!,

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I

=

y

/

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=

n C

_i A

A

^

M 0%

i i

Jan91 Feb Mar Apr -

May -Jun Jul.

Aug

.Sep.

Oct Nov Dec91 1991 i-(:

-t

-26

Q 1992 Monthly Unplanned Capabihty Losa Fcetor

-M-1902 Ynar to Date Average Unplanned Capability Loss Factor

-O-1992 Fort Calhoun Goal s s--

1995 thPO trdustry Goal (4.5%)

lGOODI a

t

-O-Irdustry Upper 10% (1.05% for a Three Year Average) 80% -

"%~

Cycle 14 40% -

Refueling

+

Outage C,O,#

y Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec02 UNPLANNED CAPABILITY LOSS FACTOR This indicator shows the plant monthly Unplanned Capability Loss Factor (UCLF), the1992 year-to-date average monthly values and goal, the 1995 INPO :ndustry goal and the approximate industry upper ten percentile value. UCLF is defined as the ratio of the unplanned energy losses during a given pellod of time, to the reference energy ganeration (the energy that could be produced if the unit were operated continuously at f6 power under reference ambient condi-tions), expressed as a percentage.

The UCLF was reported as 0% for the months of December, November and October 1992. The year-to4 ate average monthly UCLF for 1992 is 14.0%

The UCLF 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 0.584 hours 0.00347 weeks 7.994305e-4 months on 9/5/92.

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

The UCLF was reported as 66% for the n.onth of July 1992. Unplanned 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 and operating at less than full power from 7/23 through 7/31 after bringing the unit back on line.

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 1992 Fort Calhoun goal for Unplanned Capability Loss Factor is 4.5% The basis for this goal is an unplanned loss of 11.5 full power equivalent days and 10 day rampup (5 full power equivalent days).

Data Source: Generation Totels Report & Monthly Operating Report Accountability: Chase Adverse Trend: None 27

0 1991 Monthly Planned Capability Loss Factor 100 % -

-M-1991 Year to-Date Average PCLF _

'lGOODI

+

80% -

-O-1991 Fort Calhoun Goal 60%-

40% -

20%~

C C

Q C

C O

M E

0%

,M Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 28 l

c3 4

3 M.,1,,,, ms,,,,

c t, e. r ot.

i

- - S esa v.u-tp-DM Averaga PCLF

~ < ' > - 1 pus P ort C.it,ourt oost i GC 3DI

+

ir,.u.., u o, e, ~...,to,. n,.

v..,

A..,.

.t*1',a Outage 2

[

i

g

P M7w=

m _

S E ', M 5

a

' R : _ %,92RZ AZ Rd.

5 s

J.r F.o M.r Apr M.y J ur, ' Jul Aug ' Sep ' Oct Nov ' DecW2 '

PLANNED CAPABILITY LOSS FACTOR This indicator shows the plant monthly Planned Capability Loss Factor (PCLF), the PCLF year-to-date average monthly value, and the Fort Calhoun yearly average goal for 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 produced 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 months of December, November and October 1992. The year to-date average monthly PCLF was reported as 24.7%

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 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. These energy losses were classified as unplanned.

The PCLF was reported as 0% for the month of August 1992. Energy losses forthe month were classified as unplanned and 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 dc panel Al 41 A failed. The turbine generator was synchronized to the grid on 8/6/92.

The PCLF was reported as 0% for the month 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.

Tha 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 PCLF industry upper ten percentile value (for the three year period from 7/89 through 6/92) is approximately 8.55%.

Data Source: Generation Totals Report & Monthly Operating Report Accountability: Chase Adverse Trend: None a

t (This page intentionally left blank.)

(This indicator was revised during 1992.)

.j-

N Fuel Reliability Indicator 5-

--A--

1995 INPO Industry Fuel Defect Reference (o.5 X 10 3 Microcuries/ Gram)

-O--

1992 Fort Calhoun Goal

@ 4-8*3-lGOODI FRI Not 4

2-Cycle 14 Available for Refueling July 92 21-Outage o

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov DecG2 FUEL RELIABILITY INDICATOR The Fuel Reliability indicator (FRI) was reported as 0.831 X 10-3 microcuries/ gram for the month of December 1992. This value is comparable to the reported November value of 0.896 X 10-3 microcuries/ gram. The monthly FRI is a calculated value based on fission product activi-ties present in the reactor coolant. Its purpose !S to monitor industry progress in achieving and maintaining high fuelintegrity.

The current INPO FRl value is defined as the steady stato primary coolant iodine 131 activity corrected for the tramp uranium contribution only and normalized to a common purification rate.

The INPO FRI value is also corrected for the density difference between the reactor coolant system and letdown conditions. Tramp activity results from the fissioning of uranium and pluto-nium from past fuel failures that has plated to intemal reactor surfaces.

On December 22,1992 INPO issued changes to the FRI calculation. These changes will be implemented in the January 1993 FRI report. The changes include an improved correction for tramp materials from past fuel defects and normalization of the indicator results to 100 percent power and a standard linear heat generation rate.

0.831 X 10 3 microcuries/ gram is a favorable FRI value for the Fart Calhoun Station at this time in core life and indicates a defect free core when no Xe-133 activity increases and no lodine spiking are present, which is the case with the current coolant activity samples. This has been confirmed with the Westinghouse Coolant Activity Data Evaluation Code, CADE, and with discussions with Olga Correal-Pulver (W Nuclear Fuel Division).

The December 1992 FRi was calculated using the data from December 1 through 31.

)

The last detected fuel failure was during Cycle 13. The FRI 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 0.75 X 10-3 microcuries/ gram has been utilized in 1992. This goal has proven to be unattainable for Cycle 14 with the present coolant activity and tramp plutonium levels. The 1995 INPO industry goal is that " units should strive to operate with zero fuel de-fects" The value of 0.5 X 10-3 microcuries / gram is defined as a " Fuel Defect Reference" number or a "Zero Leaker Threshold".

Data Source: Holthaus/Guliani Accountability: Chase /Spijker Adverse Trend: None 31

.~

.t 400.

Personnel Cumulative Radiation Exposure -

(Person-Rem) -

y

' O-Fort Calhoun Annual Goal (75 Person Rem) 300-A - 1995 INPO Industry Goal (185 Person Rem) '

-G-Industry Upper 10 Percentile (166 Person-Rem);

200-C O

m m

r, m

m r,

m-m m

w w

100 -

C C

C O

/

l

~

0 Jan91 Feb Mar Apr May Jun Jul -

Aug Sep Oct Nov Dec91 1991 Personnel Cumulative Radiation Exposure (Person-Rem) i L

--O-Fort Calhoun Annual Goal a

1995 INPO Industry Goal (185 Person-Rem)_

C C

C.

C O~

C O--

^

f 200 ~

u u

a u

u u

a c

100 -

0

'Dec91 Jan Feb

- Mar Apr May -

Jun

- Jul Aug-Sep

- Oct Nov92

~

1990-

7

~5 Monthly Personnel Radiation Exposure <

Personnel Cumulative Radiation Exposure (Person Rem) <

--O-Fort Calhoun Annual Goal (250 Person Rem)

--6--

1995 INPO Industry Goal (185 Person Rem) 400 -

-O-Industry Upper 10% (115.6 Person-Rem for a Three Year Average):

IGOODI-276

~

c c

-e a

a a

a 93.4 h

O

}

O O

O

- O O

O O

O 1

100_

/Y l

0 i

i

.i i

'89

'90

'91 Jan92 = Feb Mar ' Apr _ May Jun Jul Aug Sep Oct ; Nov Dec92 COLLECTIVE RADIATION EXPOSURE During December 1992,2.194 person-rem was recorded byTLDs worn' by personnel-while working at the Fort Calhoun Station. The year-to-date exposure is 255.617 per-son-rem.

q 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 person 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 expos _ure 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 from 7/89 through 6/92) is approximately 115.6 person-rem per year. The three year average for Fort Calhoun Station from 7/89 j

through 6/92 is 194.3 person-rem per year.

Data Source: Chase / Williams (Manager / Source)

Accountability: Chase /Lovett

' Adverse Trend: None SEP 54 m

m a

J 4

m-a p.-

V Cumulative Dry Active Waste Sent For Prodessing'(th cubic f$et).;

25000 -

20000-15000-10000-5000 -

O o

Jan91 Feb Mar Apr

- May -.Jun Jul.

Aug Sep-Oct _' _ Nov - Dec91 1991 l

E Radioactive Waste Buried This Month (in cubic feet):_

Cumulative Radioactive Waste Buried

- O-Fort Calhoun Goal For Waste Buried (4500j - 1995 INPO Industry Goal (3884)

-O-Industry Opper 10 Percentile Waste Buried (3072)'.

4500-C O

O O

O O-O O-O

. O' A

A A

'A 3000-D D

D O

O O

Ol O.

D-

.D_

O--O 1500-0 i

i i

i -.

i i

-i

. i :.

Jan91 Feb_

Mar -

Apr May Jun Jul '

Aug Sep' -Oct Nov-Dec91-1991 ju l

l,

~

Cumulative Dry Active Waste Sent For Processing (in cubic feet) 25000-20000-15000-10000-5000-0

- i i

i i

i Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 E

Radioactive Waste Buried This Month (in cubic feet)

Cumulative Radioactive Waste Buried

-O-Fort Calhoun Goal For Waste Buried (3,000 cubic feet)

--6--

1995 INPO Industry Goat (3,884 cubic feet)

-O-Industry Upper 10% (2,077.9 cubic feet) 7 A

A A

A

--- A A

A A

3000-C O

O O--C O

O O

-O O

O O

1334 1500-E m 0

i i

j i

i i

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-tive annual total for radioactive waste buried, and the year-end totals for radioactive waste buried the previous 2 years.

Curnulative amount of solid radwaste shipped oft site for processing (cubic feet) 21,600.0 Amount of solid radwaste shipped off site for processing during December (cubic feet) -

0.0 Volume of solid radioactive waste which was buried during December (cubic feet) 68.9 Cumulative volume of solid radioactive waste buried in 1992 (cubic feet) 2,278.2 Amount of solid radioactive waste in temporary storage (cubic feet) 0.0 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 goal is 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: Chase /Breuer (Manager / Source)

Accountability: Chase /Lovett Positive Trend SEP54 s

1.6 -

1991 Disabling injury / illness Frequency Rate

-M-

5 Year Average Disabling injury / Illness Frequency Rate 1.4 -

--O-Fort Calhoun Goal.

1.2 -

--6--

1995 INPO Industry Goal 1-0.8 -

A.

./

"~

3 t

0.4 -

C O

O O

O O~-

l' j

0.2 -

l' l

0 x i :s i

i i

i i-Jan91 Feb Mar Apr -

May Jun Jul Aug Sep Oct Nov -Dec01 1991 1990 Disabling injury / Illness Frequency Rate 1.6 -

X 5 Year Average Disabling injury / Illness Frequency Rate:

1.4 -

-O-Fort Calhoun Goal i

--A-1995 INPO Industry Goal -

1.2 -

1-0.8 -

0.6 -

A A

'A A

A A

^

C O

QO O

O

^

0.2 -

_4 s-0 X

m Jan Feb Mar.

Apr May _

Jun Jul

.Aug Sep

. Oct _

Nov.

Dec 1990 36

w

~

- 1992 Disabling injury / Illness Frequency Rate.E

--M-5 Year Average Disabling injury /lllness Frequency Rate IGOODit

-O-Fort Calhoun Goal (0.3)

~

- 1995 INPO Industry Goal (0.5) -

1.4 -

1.2 -

'1-0.8 -

A A

d h

b T

A A

A-0.4 -

C O

O O

O O_

O-O O-0.2 -

y H

0

'~, h i.

Jan92 Feb Mar Apr -

May: Jun Jul Aug Sep Oct Nov L Dec92 ;

DISABLING INJURY /lLLNESS FREQUENCY RATE (LOST TIME ACCIDENT R ATE)-

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.

l The disabling injury / illness frequency rate for January through December 1992 was 1.05. There were no lost time accidents reported for the month of December. - The total number of lost time accidents that have been reported during 1992 is 6.. The 1992 -

7j disabling _ injury / illness frequency rate goal was set at 0.30. -The 1995 INPO Industry.

goal is 0.50.

The disabling injury / illness frequency rate for the past twelve' months is 1.05.

The industry upper ten percentile disabling injury / illness frequency rate for the twelve.

months from 7/91 through 6/92 is approximately 0.12.

Ygat Year-End Ratt -

1989 0.4

-1990 0.5 -

'1991 0.4 1992 1.05 Data Source: Sorenson/Skaggs (Manager / Source)

Accountability: Chase / Richard Adverse Trend:- None SEP 25 & 26 37 -

' 1991 Recordable injury / Illness Frequency Rate IGOODI

--M-5 Year Average Recordable injury / illness Frequency Rate

- y 5-

- O - 1991 Fort Calhoun Goal (2.0)-

4.5 -

4_

3.5 -

3-2.5 -

,e

%--D

^

2-C 1.5 -

1-0.5 -

0 3

Jan91 Feb Mar Apr May Jun Jul

.Aug Sep Oct Nov Dec91:

1991-GQ.

1990 Recordable injury / Illness Frequeng Rate 4.5 -

.Y-4-

3.5 -

3-2.5 -

2-1.5 -

1-0.5 -

0 i.

Jan90 Feb Mar Apr May Jun Jul Aug Sep Oct

. Nov Dec90 1990 33

1992 Recordable lojury/ Illness Frequency Rate.

-X-5 Year Average Recordable injury / Illness Frequency Rate iGOODI

--O--

1992 Fort Calhoun Goal (2.0) y 5-4.5 -

4-3.5 -

3-

\\

A m

w 2-O Q

C 0

1.5 -

1-0.5 -

Jan92 Feb M,ar 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 shown.

A recoroable injury / illness case is reported if Nuclear Operations Division personnel are injurert 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.

The recordable injury / illness rate for January through December 1992 was reported as 3.15. There were no recordable injury / illness cases reported for the month of Decem-ber. There has been a total of 18 recordable injury / illness cases in 1992.

The recordable injury / illness rate for the past twelve months is 3.15.

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

Year Recordable Cases Year-End Rate 1989 11 2.2 1990 11 2.1 1991 18 3.3 1992 18 3.15 Data Source: Sorenson/Skaggs (Manager / Source)

Accountability: Richard Adverse Trend: None SEP 15,25 & 26 s

(This page intentionally left blank.)

m

O Tnermai output

-O-rort Calhoun 1495 MW Goal loch Spec 1500 MW Umrt 1500 -

f.

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m. gy T* VTT, ' 3:7y Q":ygy.? T_f yy;;f:(,Wn K.

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4.r _2.mcJ%y.m p, m. ~~%..#.:.y~,

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3 4

1450 -

1 3

5 7

9 11 13 15 17 19 21 23 25 27 29 31 DAILY THERMAL OUTPUT The above thermal output graph displays the daily operating power level dunng Decem-ber 1992, the 1500 thermal megawatt average technical specification limit, and the 1495 thermal megawatt Fort Calhoun goal.

Main Turbine Control Valve (CV-1) was fluctuating dunng December 1992. As a con-servative approach to this condition, reactor power was allowed to dntt below the goal of 1495 Mwth.

Data Source: Holthaus! Gray (Manager / Source)

Accountability: Chase! Tills Adverse Trend: None 41 1

4

- J 2-Equipment Forcod Outage Rate 11.8 -

~

1.6 -

1.4 -

12-1-

0.8 -

0.6 -

0.4 -

02-i O

Jan91 Feb Mar Apr

.May Jun Jul

-Augl Sep-Oct Nov _ Dec91 1991-2-

Equipment Forced Outage Rate l

1.8 -

1.6 -

I 1.4 -

' 1.2 -

1-0.8 -

0.6 -

0.4 -

0.2 -

O Jan90 Feb Mar Apr May Jun Jul' Aug bep Oct Nov Dec90 -

1990 42

Equipment Forced Outage Rate

--O-1992 Fort Calhoun Goal 2-p 1.5 -

'N 1-0.53 0.5 0.5 -

0.13 C

O O

O DFil o

'89

'90

'91 Jan92 Feb Mar Apr May Jun Jul Aug-Sep Oct Nov Dec92 EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS l

The equipment forced outage rate per 1,000 critical hours was 0.86 for the months from January through December 1992. There were no equipment forced outages during the months of December, November and October.

The equipment forced outage that began on August 22,1992 (described below) contin-ued 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 DC panel Al-41 A failed. The turbine generator was synchronized L

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 design pressure during a plant transient and trip. The plant was shutdown for the remainder of the month.

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 to a dropped control rod. The rod was dropped at 2305 on 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 equipment 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.

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

Accountability: Chase /Jaworski Adverse Trend: None 43

Operations 1991 Budget ($ Million) 80-

-W-1991 Cumulative Total l$ Million)_

60 -

40-

.fg 20-m 0

Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct

. Nov Dec91 1991 40-Maintenance 1991 Budget ($ Million) 30-

--W-1991 Cumulative Total ($ Million) 10-o

~

m 0

W Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 Operations 1990 Budget ($Million) 80 -

-W--

1990 Cumulative Total ($Million) 60-40-20-0 Jan90 Feb Mar Apr May Jun Jul Aug Sep Oct Nov ' Doc 00 1990 40-Maintenance 1990 Budget ($ Million) 30-

-N-1990 Cumulative Total ($ Million) 20-

~

10-0 Jan90 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec90 1990 44

Operations 1992 Dudget ($ Million) 80-

-M-1992 Cumulative Total ($ Million) 60 -

40-20-0 Jan92 Feb Mar Apr May Jun Jul -

Aug Sep-Oct Nov Doc 92 Maintenance 1992 Budget ($ Million) 40-30-

-M-1992 Cumulative Total ($ Million) 20-i

,0-1 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 tc-cate as well as the actual expenditures for operations and maintenance for the Fort Calhoun _

Station.

The budget year-to date for Operations was 66,660,800 dollars for December 1992 while the actual cumulative expenditures through December totaled 62,684,306 dollars.

The 1992 year-end budget for operations had been revised to 60,543,800 dollars.-

The budget year ta-date for Maintenance was 18,154,600 dollars for December 1992 while the actual cumulative expenditures through December totaled 16,224,280 dollars.

The 1992 year-end budget for maintenance had been revised to 18,838,600 dollars.

Data Source: Gleason/ Parent (Manager / Source)

Accountability: Scofield

- Adverse Trend: None 45~

O Documents Scheduled for Review Documents Reviewed 700-Q Overdue Documents 600-500-400-5 s!

300-T 200-I

$2 i

100-7-

j s

~

Ji ril-h J,dortor_iFM

~3 rk L rh 0

i i

i Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 O Documents Seneduiedior Review 8 Documents Reviewed Overdue Documents 1400-e 1300 -

1200 -

1100-1000-900-800-l 700 -

600 -

500-400-300 -

200 -

100-5

~

0

~

4 i

i i

e i

i i

i Jan90 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec90 1990 46

c O - Docurnents Scheduled for Review Q -. Documents Reviewed

-700 -

D Overdue Documents 600-500 -

400 -

300 -

200-

=

Y

_z g

l 200-7 0

Jan92 Feb Mar Apr.

May Jun Jul

-Aug Sep Oct

Nov Dec92 Y

DOCUMENT REVIEW This indicator shows the number of completed, scheduled, and overdue (greater than 6 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 Security Plan, Maintenance Procedures, Preventive Maintenance Procedures, and the --

Operating Manual.

During December 1992 there were 96 document reviews completed while 55 document '

reviews were scheduled. At the end of December, there were 6 document reviews overdue.

la addition, during the month of December there were 24 new or renamed documents.

. reviewed. These new or renamed documents will need to be reviewed again in 1994.

Data Source: Chase /McKay (Manager / Source)

Accountability: Chase /Jaworski Adverse Trend: None SEP 46 l

a l

Number of Failures /20 Demands Trigger Values for 20 Demands O

Number of Failures /50 Demands

-V-Trigger Values for 50 Demands 15 Number of Failures /100 Demands

- - Trigger Values for 100 Demands 8-6-

]

V V

T Y

Y Y

-Y Y

Y Y

4 4

~

3 3

__E_

E 3

i j

j i

22 22 22 22 22 2-If h

h,

{d ((l-l l

l 0

y 0

l 0

g0 g

0 0

7 0

i i

Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 Q

Number of Failures /20 Demands

-N-Trigger Values for 20 Demands O

Number of Failures /50 Demands

-V-Trigger Values for 50 Demands G

Number of Failures /100 Demands Trigger Values for 100 Demands 8-6-

Y Y

Y 4

4 4

4 3

2 2

2 2-7

'^

0 i

i i

Aug90 Sep Oct Nov Dec90 1990 48

i i

G Number of Failures /20 Demands Trigger Values for 20 Demands O

Number of Failures /50 Demands

-V-Trigger Values for 50 Demands Trigger Values for 100 Demands D

Number of Failures /100 Demands 8-l GOOD l

+

6-V V

V V

Y Y

4 4

4 3

g g

2 3 2 h 2 ;

q i

i 2-41 9

A l

1 1 1

1 1

1

}

1 1

j z

. m]

1 1

1 q

g 9

?

$ @.?i 0 6

0

@ 0 O

O O

0-

~,

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 EMERGENCY DIESEL 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 diesei 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 vaidac.

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 r.:.:mber of 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 oy automatic 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 real load 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 which 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).

Data Source: Jaworski/Ronning (Manager / Source)

Accountability: Jaworski/Ronning Adverse Trend: None 49

Q DG 1 Failures /25 Demands l GOOD l E

DG 2 Failures /25 Demands 4

5-O Failure Trigger Value for 25 Demands / Fort Calhoun Goal 4-C O

O O

O O-3-

2-1 1-00 00 00 00 00 00 0

0 0

0 0-i Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov. Dec91 1991 50

,i O

DG-1 Failures /25 Demands 1 GOOD 1 E

DG 2 Failures /25 Demands

- y 5-Failure Trigger Value for 25 Demands / Fort Calhoun Goal-4-

C C

C D

3-2 2-1 1

1 1

1 1 -.

1 1

-1 0

0 0.

0 0

0 i

_i i

i i

i

_i.

i

.i i

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 DIESEL GENERATOR RELIABILITY (25 DEMANDS) _

This indicator shows the number of failures experienced by each emergency diesel generator duang 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 1992.

It must be emphasized that in accordance with 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 System Engineering Instruction has been drafted for the Fort Calhoun Station to institutionalize and formally approve / adopt the required j

NUMARC actions.

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 51 l

4.

O Planned Hours of Diesel Generator No.1 Unavailability

- @ Unplanned Hours of Diesel Generator No.1 Unavailabilly

@ Estimated Hours of Diesel Generator No. 2 Unava. lability E Planned Hours of Diesel Generator No. 2 Unavailab!!ity 0. Unplanned Hours of Diesel Generator No. 2 Unavailability 180 -

G Estimated Hours of Diesel Generator No. 2 Unavaltabikty 160-140-p

$ 1M-2 4 100-e 3 80-l 0

e 60-Y 40-20-O

.n

.m I,

,O n

0 i

i i

Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct

-Nov Dec91 1991

--+- Cumulative Hours of DG-1 Unavailability for 1991 4>-

Cumulative Hours of DG-2 Unavailability for 1991 g_

400 -

.& 350-300 -

m

& 250 -

C 3 200 -

b 150-7 8I 100 -

50 -

0-d,

i.

Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 52

O Planned Hours of Diesel Generator No.1 Unavailability

. @ Unplanned Hours of Diesel Generator No.1 Unavailability-.

50-Q Estimated Hou's of Diesel Generator No.-1 Unavailability 40-E - Planned Hours of Diesel Generator No. 2 Unavailability 30-0 Unplanned Hours of Diesel Generator No. 2 Unavailability; 2

" 20-

@. Estimated Hours of Diesel Generator No. 2 Unavailability-ej10-g I-

-l 0

,n Jan92 Feb Mar Apr May Jun Jul Aug Sep, ' Oct '

Nov Dec92L

+ Cumulative Hours of DG 1 Unavailability for 1992

~

Cumulative Hours of DG 2 Unavailability for 1992 Eg 15-2

$ 10~

I s-

/'

i d.

0-Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92,-

DIESEL GENERATOR UNAVAILABILITY This indicator provides a monthly illustration of diesel generator unavailability. The top graph shows the diesel generator planned, unplanned, and estimcted unavailable hours.

for DG-1 and DG-2 for each month.- The lower graph shows the year-to-date cumulative -

hours of unavailability for each diesel generator.

During December 1992 there were no (0) hours of planned or unplanned unavailability for DG 1. There were 6.67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months of plan:1ed unavailability for maintenance, to correct wiring problems associated with a 1992 refueling outage modification, and no (0) hours of unplanned unavailability for DG-2 in December.

The 1992 Fort Calhoun goalis a maximum of 210.8? hours of unavailability for each diesel generator.

Data Source: Jaworski/Ronning (Manager / Source)

Accountability: Jaworski/Ronning Adverse Trend: None 53

r

~

Q Seplenber 1992 Outstarding MWOs O october 1992 outatinoing Mwos D - November 1992 Outstanding MWOs

-300-O Decenber1992-200 -

100-(W Q

^

0 3 Months -

3 6 Months C 9 Monthe 912 Months __ l 1

4 l

>12 Months "GE OF OUTSTANDING MAINTENANCE WORK ORDERS (CORRECTIVE h0N-OUTAGE)

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

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

1 Accountability: Chase / Bobba Adverse Trend: None 54-9 e f

-c~-

y e--. -,

w w

-?vr-

.y u

a y--

>-W'

-e.--

- ~ ew e n

-*,~3,

/

e.

s w

O September 1992 O october 1992 400 O November 1992 O December 1992 350-300-2r>8

~

250-215

~

200-170 165 id3

~

3 134 150-7""

123 hh Y.</,.

100-

//

h'l

. h' 60 ss i

42 42 37 34

'h' 1 35

~

h[

50-r e

17 16

//

///

T'

,0 0

% ;//

d ; /,. p f/,,-

/,/

s 0-i i

i Total Opon MWOs Open MWOs>3 Total Open Safety Open Safety Open High Prionty months old Related MWOs Related MWOs > 3 MWOs Months Old MAINTENANCE WORK ORDER BREAKDOWN (COPRECTIVE NON-OUTAGE)

This indicator shows the total number of correctivo non outage MWOs remaining open at the end of the reporting month, along with a breakdown by soveral key categories.

The 1992 goal for this indicator is to have loss than 350 total correctivo r.on outago maintenance work orders romalning open.

Data Source: Chase /Schmitz (Managor/ Source)

Accountability: Chase /Bobba Adverso Trond: None SEP 36 55

i E

Correctivo Maintenance Backlog > 3 Months Old l

-G-Industry Upper Quartile 00% -

)

I I

C O

O O

40%-

i 20%-

0%

Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 i

1991 i

l E

corrective Maintenanco Backlog > a Monins oks 80%-

-G-Industry Upper Quartile 1

60% -

l 40% -

l 20%-

I

/.

)

Jan90 Feb Mar Apr May Jun Jul -

Aug Sep Oct Nov Dec90

)

1990 L

se

'I w,- eim,-- w w N, - v,

--,-.e.-~A--n,_

vAnan.,,...-..s-~+

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

u..,u-

~~~~s~~-

1 IGOODI 100%-

E Corrective Maintenanco Backlog > 3 Months Old V

80%-

Cycle "

Refue Outag lEl llll 0%-

Jan92 Feb

' Mar Apr May Jun Jul Aug Sep Oct Nov Dec92

'Programmate change to reflect change in non+utago criteria.

CORRECTIVE MAINTENANCE BACKLOG GREATER THAN 3 MONTHS OLD 1

(NON-OUTAGE)

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 December 1992 was reported as 86.0%.

i Data Source: Chase /Schmitz (Manager / Source) l Accountability: Chase / Bobba Adverse Trond: An adverse trend is indicated based on three consecutive months of declining Performance.

SEP 36 i

{

l 57 e.-

-.-m...m.m m,.__,,..,.,-,.,,m,,..,,%,e,-,3,m-,,,,w,,ww.v,vm.--,.,.-,.%v,-

.m s-.-w--me.

.e.

O Ratio of Proventivo to Total Maintenance 90%-

@- Industry Uppor Quartile (57.7%)

80%-

--O-Fort Calhoun Goal (60%)

70%-

d 5-O O-d-U--d d

Q----Q

^

60%-

m m

yld d

R I

q e

3

}iU

'jN E

P 50%-

h if li E

o u

.'I

?

A ltp{l N;

h j

J 40%-

~

l t

t y

]

T-l y

4 94 yd!)

L 30% ~

g g

ij y

qp jij iH fd.

W 20%

Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 Ratio of Proventive to Total Maintenanco

-C}- Industry Upper Quartilo (57.4%)

--O-Fort Calhoun Goal (60%)

80%-

T 70%-

y j'

f '{

-;g

p;

b la 4

d, 4

00%-

i y y p

50%- T

! )

M w

1 1

s k "

l l

40% -

f b

h 4,

% l M

f1

\\

a 2

n g

MI i/h

}@l

[I 9"

30%-

4. 'i g

.a db ys 4

to M

1 V

J' d' i:

d Y

k

^

20%

Jan90 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec90 1990 58

.g.

D Ratio of Preventive to Total Maintenance

-O-1992 Fort Calhoun Non-Outage Goal l GOOD l Cycle 14 90%-

Refueling Outage 80%-

\\

3 l%~

)p C

O O

g 60%-

j s

50%-

pf

!)

f%

(

ih y

(

b E

s i:

l"~L U

d Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 R ATIO OF PREVENTIVE TO TOTAL MAINTENANCE This indicator shows the ratio of completed non-outage preventive maintenance to total completed non outage maintenance.

The ratio of preventive to total maintenance was 77.7% in December 1992.

The 1992 Fort Calhoun goalis to attain a ratio of preventive to total non outago mainte-nance greater than 65%

Accountability: Chase / Bobba 1

Data Source: Chase /Schmitz (Manager / Source)

Adverse Trend: None SEP 41 i

l l

~

3 Prevertive Maintenance items Overdue

-C}- Industry Upper Quartile ~

-O-Fort Calhoun Goal 3%-

2%-

0 0

D 1%--

C O

O O

O 0* '.

i i

i Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991

~

E Preventive Maintenance items Overdue

--C}-

Industry Upper Quartile

-O-Fort Calhoun Goal 3% --

2%-

0 3

0 0

0 D

C O

O 1%-

E; 0%

j i

i i

g Jan90 Feb Mar Apr May Jun Jul Aug' Sep Oct Nov Dec90 1990 00

4%-

E Preventive Maintenance items Overdue IGOOD]

-O-1992 Fort Calhoun Goal 3%~

2%-

r Cycle 14 1%-

Refueling i

I

--C Outage O

O O

M M; Ow i

i a

i i

i Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 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 December 1992,603 PM items were completed. All of these PM ltems were completed within the allowable grace period.

i The 1992 Fort Calhoun goalis to have less than 0.5% per month of the preventive.

maintenance items overdue.

Data Source: Chase /Brady (Manager / Source)

Accountability: Chase / Bobba Positive Trend GEP 41 61

(This page intentionally left blank.)

(His indicator was revised in 1992.).

l f

k i

l 5

t

Control Room Equipment Deficiencies Repairable On Line O

Total Number of Control Room Equipment Deficiencies

~

-O-1992 Fort Calhoun Goal For Total Equipment Deficiencies 60-50-O O

O O

40-30-

~

20-n p

b

/

I I

i I

i i

I 4

4 I

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 HUMBER OF CONTROL ROOM EQUIPMENT DEFICIENCIES This indicator shows the number of control room equipment deficiencies, the number of deficiencies repairable during plant operations (on line), and the 1992 Fort Calhoun goal.

There was a total of 44 control room equipment deficiencies at the end of December 1992,12 of these deficiencies require a plant outage to repair.

The large increase in the number of out-of service control room instruments that oc-curred in October was due to a change in the criteria for defining out-of service control room instruments. This change was necessary because INPO no longer tracks this item due to difficulty in establishing consistency among plants reporting this indicator.

The revised 1992 Fort Calhoun goalis to have a maximum of 50 control room equip-ment deficiencies.

Data Source: Chase /Spilker (Manager / Source)

Accountability: Chase / Bobba Adverse Trend: None m

~

Maintenance Overtime k

70%-

-M-12 Month Average l

--O-Fort Calhoun GoalIor Non-Outage Months _

[

60%-

3 1

50%-

40%-

f L

30%-

m m

m

.-m O-O w

w w

20% ~

10%-

u

,,,meng l

o o

n r

n n-n m-esa F*.

l F.?

p p:

lig'

.. M Q

m C

$?

iM h.

?

a 0%

Jan91 Feb Mar Apr -

May Jun Jul Aug

. Sep Od:

Nov Dec91 1991

+

80%-

j O

Maintenance overtime 70%-

.-M--

12 Month Average a

60%-

-O-Fort Calhoun Goal 50%-

ycle 1 Refueling 40%-

Outage.

@D jig M

.f 30%-

W e$;

$e

?g g

-n m.

m m-m m

L O

7 w

w w

20% -

&m G.

y "M

o m

m m

o u-.

M a

4 n

n n.

1 4 m

a a

'j$

U?p if ':

Mf j

d 10%-

%n s - W W

W "d""i'

- -i e

A#

t

,.;i M.

i T

nr 33 1 is Wi

$y

$w lY

$a 6

E

@e R

yk r

o u

m o

a ep; gw e

-e nu 0%

Jan90 ' Feb Mar -

Apr-- ; May ~ 'Jun' Jul Aug Sep"

.Oct ' LNov-Dec90 1990-64

i k

t i

D Maintenance Overtime i

80*/. -

I

-M-12 Month Average Maintenance Overtime

+

70% -

-O-1992 Fort Calhoun "On-Une" Goal i

60%-

Cycle 14 Refueling 50%-

Outage t

40% -

7

.i d

x&

ts L:

30%-

p f

gij y

n e

pf >-

4

@'[

/

maya, 20% -

n L

?

e u

u o

u u.

T 11 M

a n

o

~

g,gi

K p ds Al; e

M

.s, m

M h - ;Q, O-- Q g-

@6

.g

,Q, 0-- Q

^

10% -

m a

g 1.

p.

g M

T M

/d 9

N/

R GE

{ll;;

M N

'f,;'

e g;

n m

t 9

m a

w m

e Jan92 Feb Mar

. Apr May Jun Jul

' Aug. Sepi ='Oct Nov - 'Dec92

' Note: December 1992 information was provided by the Payroil dept. '

MAINTENANCE OVERTIME -

The Maintenance Overtime Indicator monitors the ability to perform the d' sired mainte-e nance activities with the allotted resources. Excessive overtime indicates insufficient-resource allocation and can lead to errors due to fatigue.

The percent cf overtime hours with respect.to normal hours was reported as 12.6%.

during the month of December 1992. The 12 month average percentage of overtime hours with rer.pect to' normal hours was reported as 18.5% at the end of the month.

Both July and August overtime were high due to two long term (>2 weeks) forced out-ages.

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

. worked is a maximum of 10%

Data Source: Chase /Schmitz (Manager / Source)

Accountability: Chase / Bobba

' Adverse Trend: None

. es -

= -.. -.

.,--...;._,,-..--.---..-.L_a,..

l

.~

- - - ~ -

l 15-O Open irs Related to the Use of Procedures (Maintenance) 3 Closed 19s Related to the Use of Procedures (Maintenance)

O Procedurel Noncompliance irs (Maintenance) 4 10-5-

4 3

3 27 2

2 2

0 1

1 I

i 6

I I.

I i

- l 4

I Jan91 Feb Mar Apr May Jun Jul

.Aug Sep

' Oct Nov Dec91 -

1991 15-O Open irs Related to the use of Procedures (Maintenance)

B Closed irs Related to the Use of Procedures (Maintenance)-

Q Procedural Noncompliance irs (Maintenance) '

10~

. Cycle 13 Refueling 88 Outage l1 1

5-

'3' 2

2 2

22.

1 1

11

-1 1

1

~

30 0'0 0 0 0 0-'

0-00-00 l0 '

0 g4

/

1 1

1 I

I i

l I

4 4

- 1 I

Jan90 Feb

- Mar Apr May Jun Jul -

Aug Sep-Oct

'Nov-Dec90 1990

.es L

w,,,

,,,.,.--&+-

s-

--en,

-,n,-

,,~.,a-+.,,-,...w,-w a

w

.n nv

,,5

O open ins notated to ine use of Procedures (Maintenar$e)

B Closed irs nelated to the Use of Procedures (Maintenance)

~'

O Procedural Noncompliance irs (Maintenance)

Cycle 14 Refueling Outage 10-4 4

3 2

2 1

1 y

11 1

1 11 1

1 lo lo 0l0 Oh 00 00 ONO 30 ll 0

00 00 0

i i

i I

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)

This indicator shows the number of open Maintenance incident Repor1s (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.

There were no procedural noncompliance incidents for maintenance reported for the month of December 1992.

Data Source: Chase /McKay (Manager / Source)

Accountability: Chase /Bobba Positive Trend SEP 15,41 & 44 G7

E Completed Scheduled Activities (EM)

-O--

Fort Calhoun Goal l

100%-

90% -

80%-

70%-

60%-

1 50%-

40%-

30*/. -

i 20% -

10%-

l 0%

j August September October November December

' Corrected Method of Calculating Completion %

PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (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.

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

Reoortino Month Comoleted Scheduled Activities August 88.7 %

September 92.2%

October 87.9 %

i November 69.1 %

December 70.2 %

l l

Data Source: Chase /Schmitz (Manager / Source)

Accountability: Chase /Bobba Adverse Trend: None SEP 33 O

i r

-. -, ~.

._,,_--..._..-..--,..__.--m...-_.-,-._,....,~,.._--...-....--m-,...--_..--,-..m_--m.-.-,-,~,--..-,-

4 t

3 Completed Scheduled Activities (PE) a

t

-O--

Fort Calhoun Goat 100% -

90%-

)

l i

80%-

70%--

l 60% -

50%-

40%-

^

30%~

20%-

i 10% --

0%

August September October' November December

' Corrected Method of Calculating Completion %

l i

PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (PRESSURE EQUIPMENT) i This indicator shows the percent of the number of completed maintenance activities as I

compared to the number of scheduled maintenance activities concerning Pressure Equipment Maintenance. Maintenance activities include MWRs, MWOs, STs, PMOs, calibrations, and miscellaneous maintenance activities.

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

Reoortino Month Comoteted Scheduled Activities August 83.5 %

September 84.5 %

October 80.7 %

November 60.7 %

i l

December 78.3 %

Data Source: Chase /Schmitz (Manager / Source)

- Accountability: Chase /Bobba Adverse Trend: None SEP 33 09

i l

1 1

i E

Completed Scheduled Activities (GM) 1

--e-Fort Calhoun Goal 4

100 % -

l 90%-

3 80% -

70%-

60%-

50%-

40%-

30%-

20%-

10%-

0%

l August September October

November December i

i

Corrected Method of Calculating Completion %

PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES i

(GENERAL MAINTENANCE)

This indicator shows the percent of the number of completed maintenance 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.

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

i Rooortina Month Comoleted Scheduled Activities August 61.7 %

September 77.7 %

October 88.4 %

November 70.4 %

December 49.2 %

l i

Data Source: Chase /Schmitz (Manager / Source)

Accountability: Chase /Bobba Adverse Trend: None SEP 33 l

l 70 l

.. ~ -

..__._ 7 i

l 3

Completod Scheduled Activities (MM) l 1

i

--O - Fort Calhoun Goal g

l 100% -

l j

90%-

80% -

70%-

l y

60%-

t 50%-

1 40%-

30%-

20%~

i

(

10%-

l 0%

l August September October November December f

l

' Corrected Method of Calculating Completion %

PERCENT OF COMPLETED SCHEDULED 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, STe, PMOs, calibrations, and miscellaneous maintenance activities.

1 i

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

Reoortina Month Comoleted SCbeduled Activities August 92.0 %

September 92.7 %

October 86.3 %

November 65.8 %

i_

December 65,6 %

Data Source: Chase /Schmitz (Manager / Source) l Accountability: Chase /Bobba i

i Adverse Trend: None SEP 33 t

-l l

71 j

i

E Completed Scheduled AdMties (IC)

--O--

Fort Calhoun Goal 100% -

90%-

80%-

70%-

60%-

50%-

40%-

30%-

20%-

10%-

0%

August September Odober

November December

'Correded Method of Calculating I;ompletion %

PERCENT OF COMPLETED SCHEDULED MAINTENANCE AC'IVITIES (INSTRUMENTATION & CONTROL)

This indicator shows the percent of the number of completed 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.

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

Reoortina Month Comolgted Scheduled Activities Aegust 92.2 %

September 91.2 %

Octobcr 87.8 %

November 74.2 %

December 75.9 %

Data Source: Chase /Schmitz (Manager / Source)

Accountability: Chase /Bobba Adverse Trond: None SEP 33 72

3--

l 8 Number of Missed STs Resulting in LERs 2-j t

j._

t 0

0-0 0.

0-0 0

0 0

0:

0 0

i i

i

'90

'91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov. Dec92

-I 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 December 1992 there were no missed STs that resulted in LERs.

The 1992 Fort Calhoun goal for this indicator is zero, q

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

Accountability: Chase /Jaworski Adverse Trend: None SEP 60 & 61

.=

=

(this page intentionally left blank.)

74

-m-

of Component Categories 40-

-v-e of Appication Categories i

3 5 --

--A-Total e of Categories 30-i 25-g4 20-

/

-%y,__

is-a m__

~

-,o-..

J01 'A'S O ' N ' D ' J92 F 'M'A 'M' J 'J 'A S- ' O ' N 'D92 3 Wear OvVAging G Other Devices Q Manufacturing Defect O MaintenancWTosting O EngineonnWDosgn O Error 33.3 0.5%

9.0%

Percent of Total Fallures Durir.g the Past 18 Months

/

\\

Y

,,og

/

15.1 %

,. m.

8 i.

COMPONENT FAILURE ANALYSIS REPORT (CFAR)

SUMMARY

The top chart illustrates the number of component categories, application categories and total categories in which the Fort Calhoun Station has significantly higher (1.645 standard deviations) -

failuro rates than the industry failure ratos during the past 18 months (from July 1991 through December 1992). Fort Calhoun Station reported a higher failure rate in 12 of the 87 component categories (valves, pumps, motors, etc.) during the past 18 months. The station report - ) a higher failure rate in 16 of the 140 application catogories (main steam stop valves, auxillary /

emergency foodwater pumps, control otomont 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 of those categories) for the 196 failure reports that were submitted to INPO by Fort Calhoun Station during the past 18 months.

The recent increase in the failure rates for Fort Calhoun Station is under investigation by the System Engineering Department's Test and Performance Group. The investigation is expected to be completed next month.

Data Source: Jaworski/ Dowdy (Manager / Source)

Accountability: Jaworski/ Dowdy Adverse Trend: None. This indicator does not meet the current definition of an adverse trend, L

but does show an increasing failure rate that is above the industry failure rates for the past 18 months.

75

-m-Greater Than One Failure

-+-- Greater Than Two Failures Greater Than FNe Faltries 40-35-30-R_

25-20-x 15-0 10-

?

0 5-0 0

I I

I i

l i

Jul91 Aug Sep Oct Nov Dec91 1991 76

I

--R-Greater Than One Failure 4s-

-+- Greater Than Two Failures

--e Greater Than Fhte Failures 40-i 35-

=

~

30-2s-

=

~

20-15-i 10-p

we 0

0_

s-

=

= -.-

=

=,

y o

i m -- i i

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 NUMBER OF NPRDS MULTIPLE FAILURES This indicator shows the number of multiple NPRDS toportable failures over the preced-ing eighteen months sorted by component manufacturer and model number. The Indica-tot is divided into three parts: manufacturer model numbers with more than one failure in elghteen months, manufacturer model numbers with more than two failures in eigh-toen months, and manufacturer model numbers with more than five failures in eighteen months.

During the past eighteen months, there were 40 model types that had more than one failure in eighteen months. 20 of thece had more than two failures. 4 component types:

General Electric 50 570 01 power supplies, Byron Jackson 28RXL pumps, Jayco incorporated 150 valves and Gaulin P18 pumps had more than five failures. The model types with more than two failures are: GE AK 2A-25 circuit breakers (4 failures), GE THEF circuit breakers (4 failures), Electromotive Diesel Generator Motor (3 failures), CE DT-1748-1 (3 failures), Fisher 546 controllers (3 failures), S P Manufacturing DA3R controllers (3 failures), General Electric 50 570 power supplies (12 failures), Faulk Type Y reducers (3 Failures), Byron Jackson DVMX pumps (3 Failures), Byron Jackson 28 RXL pumps (8 failures), Gaulin P1B pumps (10 falturns), GE CR120A relays (3 failures),

GE 12HEA61 relays (4 failures), Crosby HB-BP 86 valves (4 failures), Dresser 19750 valves (3 failures), Dresser 3707RAX1 RT-22 valves (3 failures), Jayco incorporated 150 valves (6 failures), Norgren 11-024 valves (4 fauures), Copes Vulcan D-100-60 valve operators (3 failures) and Fisher Controls 657 60 valve operators (3 failures).

Data Source: Jaworski/ Dowdy (Manager / Source)

Accountability: Jaworski/ Dowdy Adverse Trend: None T1 4

4 e

20-Componerds With More Than One Failure -

--+-

15-

+ Components With More Than Two Failures 10-5-

o u

'N u

u v

v o.

o, m

n n

n Jan91 Feb Mar Apr May.

Jun Jul-Aug Sep Oct Nov Dec91 1991

=,

5 20-Components With More Than One Failure

+

15-

+ Components With More Than Two Failures 10-5-

u u

u o

n n

n 7

X X

X 0

Jan90 Feb Mar Apr May. - Jun -

Jul.

.Aug Sep Oct Nov 1Dec90 1990

}-

L

--f 1

.a.-..

.i l

Components With More Than One Failure

+

IGOODI 25-

-X-Components With More Than Two Failures 9

20-15-10-5-

<M "N,

M o,

o o,

n n

n 0

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92

^

MAINTENANCE EFFECTIVENESS The Maintenance Effectiveness Indicator was developed following guidelines set forth by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Opera-tional Data (NRC/AEOD). The NRC/AEOD is currently developing and verifying a maintenance effectiveness indicator using the Nuclear Plant Reliability Data System T i"

(NPRDS) component failures.

This indicator shows the number of NPRDS components with more than one failure during the last eighteen months and the number of NPRDS components with more than two failures during the last eighteen months.

During the last 18 reporting months there were 20 NPRDS components with more than 1 failure 4 of the 20 had more than two failures. The tag numbers of the components with more than two failures are CH 1 A, CH 1B, EE-1G M and RC 142.

The recent increase in component failures during the last eighteen months for Fort Calhoun Station is under investigation by the System Engineering Department's Test

- and Performance Group. The investigation is expected to be completed next month.

Data Source: Jaworski/ Dowdy (Manager / Source)

Accountability: Chase /Bobba Adverse Trend: None 79

r. _.., w,

,.-e w

i

I i

1991 Calcutated Check Valve Failure Rate per Million Cornponent Hours

.9- -

Industry Check Valve Failure Rate per Millbn Cornponent Hours 8-7-

l 6-5-

l 4-A A

A A'

^

b-1-

\\f 0

Jan91 Feb Mar Apr May Jun Jul Aug

.Sep Oct-tjov Dec91 1991 1990 Calculated Check Valve Failure Rate per Million Component Hours 15-14-13-

--a-Industry Check Valve Failure Rate per Million Component Hours 12-11 -

10-9-

e 8-10 7-6-

5-4-

.N 3-

-u a-a; h-.-----L u

u u

u a

~

g, 1-0-

Jan90 Feb Mar Apr May _Jun Jul Aug Sep LOct Nov-_ Dec90 1990 80-

10 10-

- Calculated Check Vake Failure Rate per Million Cornponent Hours Irdustry Check Vane Failure Rate per Million Component Hours

+ Fort Calhoun Goal 7-IGOODI 6~

85-4-

4 3-4 44 4 a

2-O C

C C

C O---C C

1 1

1-f 0

'89 '90 '91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 No. of Check Vane Failures CHECK VALVE FAILURE RATE This indicator shows the calculated Fod Calhoun check valve failure rate, the Fort Calhoun goal and the industry check valve failure rate. This rate is based upon failures during the previous 18 months. The number of check valve failures at Fort Calhoun Station for the previous three years 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 September 1992, the Fort Calhoun Station reported an actual check valve failure rate of 1.21 E-6, while the industry reported an actual failure rate of 2.51 E-6. The increase in the failure rate for the month of August is due to the failure of check valve CH 288. At the end of December 1992, the Fort Calhoun Station reported a calc'ulated check valve failure rate of 1.21 E 6.

The 1992 Fort Calhoun goal for this indicator is a maximum failure rate of 2.00 E 6.-

Data Source: Jaworski/ Dowdy (Manager / Source)

Accountability: Jaworski/Rollins Adverse Trend: None.

SEP 43 81 i

i

)

E _ Secondary System CPI

-O-Fort Calhoun Goal (.45) l GOOD l l '0 ~

4-6--

1995 INPO Industry Goc!(0.30) -

i

]

N l

Secondary Systom CPI Limit i

1-l l

l l

l

-+

l-i.

0 i

i i

i Jan91. Feb Mar Apr-May -Jun

_ Jul

/.ug -Sep Oct

' Nov Dec91 1991-10%-

E % of Hours Chemistry is'Outside OG Guidelines l GOOD l 8%-

6%-

l 4%-

2%-

0%

i i

i

(

Jan91 Feb Mar Apr May: Jun Jul Aug Sep Oct Nov _ Dec91 1991

l 3

Secondary System CPI

-O-Fort Calhoun Goal (.45)

--h-1995 INPO Industry Goal (0.30) 1.5 -

l-Secondary System CPI Limit

-O-Industry Upper 10% (0.20) 1-

+

l l

Cycle 14 Refueling 0.5 -

Outage r

i i0 i

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 6%-

E % of Hours Chemistry is Outside OG Guidelines 3%-

Cycle 14 Refueling Outago 0%

i i

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 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 oxygen. The bottom graph shows the percent of total hours of 13 parameters exceed-ing the Owners Group (OG) guidelines during power eneration.

The CPI was reported as 0.488 for the month of December 1992. The percent of hours outside the OG guidelines was reported as 0.29% for the month of December 1992.

This value is atributable to boron concentration in the steam generators being higher than specifications.

The 1992 t' ort Calhoun goal for the CPIis 0.45. The INPO 1995 Industry goalis 0.30.

The industry upper ten percentile value for this indicator was approximately 0.20 for the twelve months from 7/91 through 6/92.

Data Source: Franco /Glantz (Manager / Source)

Accountability: Chase /Schmidt Adverse Trend: None

...... _. ~

1

~ 1' 0% -

.E Primary System Chemistry Percent of Hours Out of Umit 8%-

-O-Fort Calhoun Goal 6%-

4%~

2%-

C C

.C C

C l

N M;N M

M 0*,,

i i

Jan91 Feb Mar Apr May Jun Jul Aug Oct

'Nov Dec91-1991 L

10%-

l' E Primary System Chemistry Percent of Hours Out of Limit t

8%-

i 6%-

Cycle 13 4%-

Refueling Outage 2%-

~

,M; l

0%

i i

Jan90 Feb Mar Apr May

'Jun Jul -

Aug Sep Oct -

Nov Dec90 1990 84 l!

10%-

E ' Primary System Chemistry Percent of Hours out of Limit -

_ l GOOD l;

--O-

/ ort Calhoun Goal k

6%-

4%-

Cycle 14 Refueling C

O O

2%-

Outage

E 0%,

i i

Jan92-Feb Mar Apr May - Jun Jul Aug _ -Sep._

- Oct - -Nov Dec92-PRIMARY SYSTEM CHEMISTRY PERCENT OF HOURS OUT OF LIMIT-i The Primary System' Chemistry Percent of Hours Out of Liinit indicator tracks the pri-mary system chemistry performance by monitoring six key chemistry parameters. Typl-cally, lithium is the parameter that is out of limitc-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 0% for the month of December 1992.

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

Data Source: Franco /Glantz (Manager / Source)

Accountability: Chase / Smith-Adverse Trend: None i

85

=

.=

i-1 4

10%-

E

% of Hours Auxiliary l System (CCW) Chemistry is outside Station Limits ~

--O-Industry UppelOuartile' 8%-

ll 6%-

1 4%-

2%-

O O

O

'O O

O O

O C

Oct Nov Dec91 -

Jan91 Feb Mar Apr May -

Jun

.Jul

.Aug Sep.

1991 10%-

3 Auxiliary System (CCW) Chemistry Hours Outside Station Limits.

-D-Industry Upper Quartile 8%-

6%-

-4%-

0 2%-

0%

O O_,

Jan90 Feb Mar Apr

. May Jun Jul

-Aug Sep.-

Oct

.Nov.Dec90 1990 86

.e

o E % of Hours' Auxiliary System (CCW) Chemistry is Outside Station Limits 10%-

8%-

6%-

4%-

Cycle 14 Refueling Outage g_

0 0

0%

i j.

4

- g i

i i

'89 '90 Jsn92 Feb Mar Apr - May Jun Jul' Aug Sept Oct - Nov Dec92 AUXILIARY SYSTEM (CCW) CHEMISTRY PERCENT OF HOURS OUTSIDE STATION LIMITS The Auxiliary System Chemistry Percent of Hours Outside Station Limits indicator tracks the monthly percent of hours that the Component Cooling Water (CCW) system is i

outside the station chemistry limit.

The auxiliary system chemistry percent of hours outside station limits was reported.as 0% for the month of December 1992. The high value (8.8%) reported for November was attributable to nitrates, which were lower than specifications. Prior to November, the last outside of station limits condition occurred in June 1991 and was due to a low

- nitrito level in CCW coolant.

Data Source: Franco /Glantz (Manager / Source)

Accountability: Chase / Smith Adverse Trend: None 87

.i

ii -

4 20-B Number of instruments Out of Service 18 -

-O-Fort Calhoun Goal '

37 16-14 -

12-10-8-

6-

^O O-

--O--

P

---O--

Jan91 Feb Mar Apr.

May Jun Jul

.Aug~

Sep

.- Oct Nov Dec91 1991

- l E3 Number of Out-of-Service Instruments

-O-Fort Calhoun Goal 18-16-

~

'2

'a l

2_

10-(

(

8-l Jan90 Feb Mar Apr May Jun

'Jul Aug--

Sep Oct Nov: Dec90 1990 i

i

. ~ _. ~. -

=

~ ~

-~

O Number of instruments Out of Service

-- O - Fort Calhoun Goal 4.-

23 19 18-17 17 16-15 15 15 O

'^

Jan92 Feb Mar Apr May Jun.,

Jul Aug Sep Oct Nov Dec92 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 December there was a total of 19 in line chemistry instruments out of-service. Of these 19 instruments,16 were from the Secondary System and 3 were from PASS.

The trend for PASS instruments for this reporting period has decreased by one because of repair to the SL-19 sample flask. The trend for Secondary instruments this reporting period is increasing. The entire secondary panel remains out-of service because of failure of the Al 125 data logger. (ECN 92-469 has been issued to replace the data logger.) Three instruments are out of service on Al-107, two because of recorder failure -

and one because of instrument malfunction. Two instruments are out-of-service on Al-105 because of malfunction The entire instrument channel is considered inoperative if: 1) the instrument is inopera-tive, 2) the chart recorder associated with the instrument is inoperative, 3) the alarm -

function associated with the instrument is inoperative.- If any of the functions listed 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 of service has been set at 6. Six out-of-service chemistry instruments make up -

10% of all the chemistry instruments that are counted for this indicator.

Data Source: Chase /Renaud (Manager / Source)

Accountability: Chase /Jaworski Adverse Trend: None 89

.s

- E Total Waste Produced (Kilograms) =

Yearly Waste Produced (Kilograms) :

+ Federal A State Monthly Limit (Kg)::-

1000 -

'i 0

- 800 -

600-m E

E 8'

r=

M 400 -

200-

-154.5-f 24.9

/ 9.9 34.9-15 4.9

'15-

--9.7 Mm 0-0 0

0 i

i i

_.i

. i i

i.

i i.-

i Jan91 Feb91 Mar 91 Apr May91 Jun91 Jul91 Aug91 ' Sep91 Oct91 - Nov911 Dec

~ 991 1

I l.

B Total Waste Produced (Kilograms).

Yearly Waste Produced (Kilograms)

~

+ Federal & State Monthly Limit (Kg):

1 1200 -

-1000 -

d E

800-5' 600-

'I 398.8 400-204.2-222.2 200 164.5:

144.5 ~

0 i

i i

.i i

i Jan90- Feb Mar Apr May Jun Jul-Aug Sep

. Oct Nov Dec90 1990 90

J. ~ Monthly Waste Produced (Kilograms)

Yearly Waste Produced (Kilograms)_-

'. 4-= L Federal & State Monthly Umit (Kg) 1000-0 0

0 0

0 800 -

g 600-

-G 8'

5 400-200-150 155 o[

o o

o 0

3 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 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 December 1992, O 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 005 kilograms.

Hazardous waste is counted based upon a full drum. of waste.

Date Source: Chase /Henning (Mariager/ Source)

Accountability: Chase /Henning -

Adverse Trend: None 91

4 500 -

O Highest Exposure for the Month (mrem) '

@ Highest Exposure for the Quarter (mrem) 4000 -

E Highest Exposure for the Year (mrem) 3000 -

2000 -

i 1182 259 0

i December 1991 1

-)

O Highest Exposure for the Month (mrem) 5000 -

@ Higrisst Exposure for the Quarter (mrem) 4000 -

E Highest Exposure for the Year (mRom)

-)

l 3000 -

l

-2223-2000 -

l 1073 1073 i

1 1000 -

y

/ // /,"

i 0

l l

December 1990 92 i

O l Highest Exposure for the Month (mrem)

@ Highest Exposure for the Quarter (mrem)

E Highest Exposure for the Year (mrem)

~

OPPD 4500 mrem /yr. Limit 4000-3000-2000 -

1860 l

1000-374 0

December '92 -

MAXIMUM INDIVIDUAL RADIATION EXPOSURE During December 1992, an individual accumulated 374 mrem which was the highest individual exposure for the month.

The maximum individual exposure to date for the fourth quarter of 1992 was 561 mrem.

The maximum individual exposure reported for the year 1992 was 1,860 mrem. This exposure is primarily due to the individual's work 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: Chase / Williams (Manager / Source)

Accountability: Chase /Lovett Adverse Trend: None m

7 p

r-4 L

- 300-B ' Monthly Personnel Contaminations

' Cumulative Personnel Contaminations

- 250 -

-O-Fort Calhoun AnnualGoal(90);

' i

.200 -

150 -

F

~

~ O C

C C

'O C

C.

lC.

C C

50-f 10-9s7'6 3-3

'4 3-4 2'-

4

=0~

0-C3 -" ' '

i i

i.

i -,

i i.

-Jan91-Feb Mar -- :Apr May

Jun' Jul:.Aug Sep Oct Nov:, Dec91 1991 3

Monthly PersonnelContaminations Cumulative Personnel Contaminations.

300-

-O Fort Calhoun Annual Goal'-

250 -

Cycle 13 y

Refueling.

200 -

- Outage 150 -

-C C'

O C

C C

_O; O

r 100 -

-68 68

$p_;4 1ME? DN 50-12 15 g M NR 5

J M:

5 1

4-2._

5 g

0 i _

Jan90 Feb Mar -

Apr May Jun -'

Jul

.Aug;

.Sep-. Oct. _ Nov.' DecSO 1990 l:

e

-94<

O Monthly Personnel Contaminations -

Cumulative Personnel Contaminations l GOODI 300 -

--O-Fort Calhoun AnnualGoal(144)'

k.

250 -

Cycle 14 237 Refueling Outage 200 -

C O

v v

101 100-

?p, 77 W E 55 jg gg 50-g$

-25 g$s. ?y 24 t

5/m$+ d. y.

jljj 5 M S 4 6 4 5 a m na n '90 '91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Doc 92 l TOTAL SKIN AND CLOTHING CONTAMINATIONS This indicator shows the number of skin and clothing contaminations for the reporting month. A total of 273 contaminations have occurred during 1992. There were 5 con-taminations during December 1992. The contaminations were: 1) A skin contamination that occurred when an individual was undressing; 2) A clothing contamination received during routine decon. In clean controlled areas; 3) A clothing contamination received during welding and grinding in Room 5; 4) A clothing contamination received while an individual was working on a limit switch on the Radwaste roll-up door; and 5) A clothing l contamination received while checking pump oil levels in clean controlled areas. There was a total of 55 skin and clothing contaminations in 1991. There was a total of 237 skin and clothing contaminations in 1990. l The 1992 goal for skin and clothing contaminations is 144. The goal for the fourth quarter of 1992 is 12. Data Source: Chase / Williams (Manager / Source) Accountability: Chase /Lovett Adverse Trend: None SEP 15 & 54 l 96 t.

.. -... ~.. - - - E Decontaminated Radiation Controlled Area --O-Fort Calhoun Goal (non-outage months). 100% - 90%- 80%- .l l 70% - 60%- 50 % Jan91 Feb Mar Apr May Jun-Jul ~ Aug Sep Oct Nov ' Dec91 1991 l i

1 i O Decontaminated Radiation Controlled Area 100% - lG000l .-O-Fort Calhoun Goal (nonoutage rnonths) Cycle 14 Refueling 90% - Outage C ^ ^ $i id 0 Pp .;p; 80% - /l, f.'. T e .h I-3; w 70%- 7' T m h.k,

u x

v bl 60% - [ -[ N i:s Wi 49 M lQ j ^l 50% - Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 DECONTAMINATED RADIATION CONTROLLED AREA This indicator shows the percentage of the RCA that is decontaminated (clean) based on the total square footage and a 1992 goal of 88% decontaminated RCA for non-outage months. At the end of the reporting month,89% of the total square footage of the RCA was decontaminated. Date Source: Chase /Gundal(Manager / Source) Accountability: Chase /Lovett Adverse Trend: None SEP 54 97

80 - Nurnber of identified PRWPs 70-60 - 50-40-30-20-10-4 1 1 0 1 2 3 2 0 M i, pyyj 0 4 m 0 ,m, i i i i i Jan91 Feb Mar Apr May Jun Jul Aug. Sep Oct Nov Dec91 1991 80-9 Number of Identified PRWPs 70-60 - 50 - 40-30-20-10-7 0 Jan90 Feb Wlar Apr May Jun Jul Aug Sep ' Oct Nov Dec90 1990 m

@ Number of identified PRWPs 80-Cycle 14 Refueling 70 - Outage 59 60-50-39 40-L 30-20-15 11 10-S 4 3 f/J 1 gg g o g 1 1 0 i i i i i i i i i i Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec RADIOLOGICAL WORK PRACTICES 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 should indirectly provide'a means to qualitatively assess supervisor accountability for their workers' radiological pedormance. During the month of December 1992, no PRWPs were identified. 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 for previous months due to the Cycle 14 Refueling Outage. Data Source: Chase / Williams (Manager / Source) Accountability: Chase /Lovett Adverse Trond: None SEP 52 99

a E Total Number of Hot Spots O Number of Additional Hot Spots identified = 75-Fort Calhoun Goal 63 63 llllllIl 53 53 54 54 54 55 53 25-T 10 10 0 0' 1 0 0 1 1 0 1 1 0 i i i i i i Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov -Dec91 1991 E Total Number of Hot Spots 75-0 Number of Additional Hot Spots identified 49 50-46 46 46 25-1 2 0-Jun90 Jul Aug Sep Oct Nov Dec90 1990 100 y y - ---Frmt+r~'--t v'T " 9 r-m+ -F-- --e ' = * ' ' - ^ - - - - - - - - - - - - -

E TotalNumberof Hot Spots "O Number of Additional Hot Spots identified Rernoval Planned - -+-- Cumulative Hot Spots Rernoved -CH-1992 Fort Calhoun Goalfor Hot Spots Removed 80 60 40 1 A m Jan92 Feb Mar Apr May June July - Aug. Sept Oct. Nov Dec92 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 4 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 r is equal to or greater than 100 mrem / hour. At the end of December, there were 84 hot spots identified. No (0) hot spots were removed during the month. 4 new hot spots were identified and one was re-posted (in j Room 61 on a CVCS line) during the month. Following is a list of the locations of the-new hot spots: 3 were_found in Room 60; 1 on a letdown line,1 on an RC sample line' and 1 on a flex sample line inside a sample hood.1 hot spot was found in Room 59'on - an overhead sample line. Removalls planned for 20 hot spots. The 1992 Fort Calhoun goal is to remove one hot spot per month. Data Source: Chase / Williams (Manager / Source) Accountability: Chase /Lovett Adverse Trend None 101

-1 n ) l -1 @ __ Monthly Radioactive Gas Discharged (Curies) 500-Cumulative Radioactive Gas Discharged (Curies) ~ -O-Cumutative AnnualGoal(Curies)- C 'O O .O O O 'O Of ~d 300-m E d r 200-100-l r 0 ,---- i - i " ", ", i _i _i Jan91 Feb_ Mar Apr-May Jun1 Jul - Aug Sept. Oct - Nov'. Dec91 - 1991 Monthly Radioactive Gas Discharged (Curies) I" 500 - -O-- Cumulative AnnualGoal(Curies) 400-L C O 'O O O O. O O O O E 300-o m l~ f _. . 0 200- -100-E - """ N 0 i. i. i i i t i i _i i i Jan90 Feb Mar ' Apr May Jun. Jul .Aug -Sep-Oct . Nov ' Dec90 1990 102 s t '.. i.. '

$ Monthly Radioactive Gas Discharged (Curies) Cumulative Radioactive Gas Discharged (Curles) - 465 --O-Cumulative Annual G;al(Curies) lG0001 400 - g_ C O O O O O O O O O O O-300 -- d 200 - 100 - 0 i i i i i i i i .i i. i i 90 '91 Jan92 Feb Mar Apr May Jun Jul - Aug. Sept Oct. Nov Dec92-GASEOUS RADIOACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT. 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 dischargod to the environment is calculated every six months. Data Source: Franco /Krist (Manager /Sourca) l Accountability: Chase / Tills - Adverse Trend: None i l -103 l l 1

@ _ Monthly Radioactive Lk uid Discharged l Cumulative Radioactive Liquid Discharged 250- -O-Cumulative AnnualGoal e C O O O C O O O O -- O O O 200-150-E 'EO 100-33.9 28.4 28.2 g 22.7 @/ ' "8.4 9.1 5.3 6.3 4.8 8.3 2.3 M 0 ~" i i i i i i i i i i i i Jan91 Feb Mar Apr_ May Jun Jul Aug Sept Oct Nov Dec91 1991 Monthly Radioactive Liquid Discharged Cumulative Radioactive Liquid Discharged i -O-Cumulative AnnualGoal C O O O O O O O O O O O 250_ 200-150-0 'Eo 100-54.8 50-23 [ 17.1 15.3 17 0 l Jan90 Feb Mar Apr May Jun Jul Aug Sept Oct Nov Dec90 1990 104

n Q Monthly Radioactive Uquid Discharged ; - Cumulative Radioactive Uquid Discharged _~ - --O-- Cumulative Annual Goal - l GOODI - 250 - 228 y C' O O O O O O O O 'D 6 O-w% 200 - k, _175 176-A N 1 h' '150 - flh jy; .h L a s a% g {l$i 100 - k &' Nik M 9 Wi f; Sk. hk #$ 50-gi

j$

g f3 k)s Uk ( 15.7 M' siH-WT' 7.1 6.7 7A 7

8 FE "r"i O

i i .i i i i i i i i i- '89 '90- '91 - Jan92 Feb Mar Apr May Jun Jul Aug _ Sept ~Oct : Nov Dec92 : 1 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 - l environment from all sources totaled 39.5 curies during this time, a The Fort Calhoun Station cumulative annual goal for 1992 is 225 curies. 1 The liquid radioactive waste being discharged to the environment is calculated every six1 . months. . Data Source: Franco /Krist (Manager / Source). q l Accountability: Chase /Lovett - Adverse Trend: None-1 i i 105 I l

..-.a 1.at- ,.x I a a w 30-25-E Loggable/ Reportable Incidents (Does not include' System Failures)- 20-15-10-6 i i i g Jan91 Feb Mar Apr May Jun Jul. Aug' Sap Oct Nov Dec91. 1991 @ Security System Failures. 82 84 I'. 80-70 67 63 70-61-58 60-53 -53 56 50-p / 42 i f Jan91 Feb Mar Apr May ' Jun. - Jul ~ Aug Sep Oct Nov : Doc 91-1991 106

E Non-Systern Failures l GOOD l 30-V 25-20-17 14 15-10-8 7 5 6 5- % -0 M BE 2 3 2 2 2 ~ 0 i i i i i i i i i i Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 lGOODI @ System Failures 4 70-60 - ! j 56 52 47 50-i 43 h 28 29 26 30- [/ 21 V// 1 1 I i i i i I 4 4 4 4 1 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 LOGG ABLE/ REPORT ABLE INCIDENTS (SECURITY) 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 Control and Authorization, and Security Force Error, and Unsecured Doors. The bottom graph shows the total number of loggable/ reportable incidents concerning system failures which occurred during the reporting month. During the month of December 1992, there were 53 loggable/ reportable incidents identi-fied. System failures accounted for 47 (89%) of the loggable/ reportable incidents, and 25 (53%) of these were environmental failures. The majority of the environmental failures continue to be camera sun glare (14 of the 20 loggables). It should also be noted that 10 of the 12 microwave system failures were attributed to one microwave zone which has since been repaired. Further,3 of the 4 Unsecured Door incidents occurred when a ventilation fan froze in the Auxiliary Building causing severe air pres-sure problems. There was a total of 553 loggable events in 1992 compared to 829 loggable events in 1991. These figures depict a very positive trend for the Security Services Department. Data Source: Sefick/Woerner (Manager / Source) Accountability: Sefick Adverse Trend: None SEP 58 107

. ~.. - -~~. o. ~ ! j5- .a segember s2-b: . D - October 92: -l. " 20 - 2 O - November 92 $ December 92 f15-8 i .+ 10- $ 5-4 4-Q 3 1-1 1- ~1 -. '1 "1 1 1 0 0 0g i.0 g "$ 0 . 0 7,p _i i i i I C Badges Access Control Security Force Error . Unsecured Doors SECURITY-NON-SYSTEM FAILURES - This indicator shows the number of loggable/ reportable non system failures fdr the - reporting month. These items include: Security Badges, Access Control and Authoriza-tion, Security Force Error, and Unsecured Doors. Non System Failures Number of incidents ,-j . December '92 November '92 - 3 t Security Badges -1 1 Access Control and Authorization 'O O-Security Force Error 1 0 Unsecured Doors. _4 1 Total 6 2 J Data Source: SeficloWoerner(Manager / Source) Accountability: Sefick [ ' Adverse Trend: None SEP 58.

10s :

n 'y. v..

O Environmental 3 Failure 1GOODI 1 4 15-12 10-6 A' 5-O O 6 0 M -0._ 0 i i i Alarms CCTV Computer Search Equipment Doors 0 1991 System Failures E 1992 System Failures lGOODI t- ~ 84 82 80-73 77 70 g Jan Feb Mar Apr May Jun Jul Aug Sep. Oct Nov Dec SECURITY SYSTEM FAILURES This indicator shows the number of loggable/ reportable system failures for the reporting - month. These items include: Alarm System Failures, CCTV failures, Security Computer Failures, Search Equirment Failures and Door Hardware Failures. Alarm systems and CCTV failures will W divided into two categories: environmental failures and failures as defined in the performance indicator definitions. Also, the 1991 and 1992 System Failures will be compared on a monthly basis. System Number of incidents - December '92 November '92 Environs Failures "EYEtDs Failures - Alarms 5 12 3 -4 CCTV 20 0 11 0 Computer N/A 0 N/A 0-Search Equiprnent N/A 4 N/A 5 Door Hardware R% fi Rd 3 Totals 25 22 14 12 Data Source: Sefick/Woernor(Manager / Source) Accountability: Sefick/ Chase Adverse Trend: None SEP 58 109

- _ -. _. --~ -. _.-..._. 10Y. - 3 Arnount of Wo* On Hold Awalting Parts 9%- -O-- Fort Calhoun 1991 Goal 7% ~ 0% - 5%- 4%- ---C O-- C-: O C -C O 3%- e Jan91 Feb Mar Apr May Jun Jul Au0 Sep Oct Nov Dec91 1991 10% - gy, _ E Araount of Work On Hold Awalting Parts 8%- 7%- 6%- 5%- 4%- l 3y, _ 0% Jan90 Feb Mar Apt May - Jun Jul Aug -Sep Oct Nov Dec90 1990 110 -._.__..____..__._..-...,_______._.______---_..m__--

c: 10% - E Amount of Work On Hold Awaiting Paris 9%- V -O-1992 Fort Calhoun Goal 8%- i 7%- Cycle 14 0%- Refueling 5%-- 4%- I ---C O O O O O O O --- O ^ 3%- 0% Jan92 Feb Mar Apr May -Jun Jul Aug Sep Oct Nov Dec92 AMOUNT OF WORK ON HOLD AWAITING PARTS (NON OUTAGE) This procurement indicator displays the percentage of open, non outage maintenance items that are on hold awaiting parts, to the total amount of open, non outage mainte-nance items. Thare was a total of 1,044 open, non outage maintonance work orders (MWOs) with 22 (2.11%) of thoso MWOs on hold awaiting parts at the end of the repotting month. The 1992 Fort Calhoun Goal for this indicator is to havo less than 3.5% of the total number of open, non outage MWOs awaiting parts. Data Source: Willrett/ CHAMPS (Manager / Source) Accountability: Willrett/Fraser Positive Trend 111

20- - Coare Parts inventory Value ($ Million) 15 -- 10-5- 0-i i i i i i i i i i .. i Jan91 Feb Mar Apr May Jun Jul Aug Sep _ Oct Nov Dec91 1991-20-Spare Parts inventory Value ($ Million) 15- ~ ~ = 10-5- 0 i i i _ i i i i i i i Jan90 Feb Msr Apr May Jun Jul Aug Sep Oct Nov Dec90 1990 000 - - Spare Parts issued ($ Thousands) 000-400-200-0 -- i Jan91 Feb Mar Apr May Jun Jul Aug . Sep Oct. Nov Dec91 1991 e00 - Spare Parts issued ($ Thousands) 600 - 400-200-y 0-Jan90 Feb Mar Apr May Jun . Jul Aug Sep Oct Nov Dec90. 1990 112 i

20-Sparo Parts inventory Value ($ Million) 10-5- 0 i i Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 SPARE PARTS INVENTORY VALUE The spare parts inventory value at the Fort Calhoun Station at the end of December 1992 was reported as $13,152,981. Data Source: Steele/Huliska (Manager / Source) Accountability: Willrett/McCormick Adverse Trend: None - Sparo Parts issued ($ Thousands) s 800-600-400-200-0 i i Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 SPARE PARTS ISSUED The value of the spare parts issued during December 1992 was unavailable due to a printer problem. Data Source: Steele/ Miser (Manager / Source) Accountability: Wiltrett/McCormick Adverse Trond: None a 113

L E Inventory Accuracy --O-Fort Calhoun Goal (98%) 1 90% Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 i E Inventory Accuracy l 100% - 85 % Jan90 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Doc 90 1990 10% - E % of Pick Tickets Generated When Parts are not Available, etc. i 8%- --O-Fort Calhoun Goal. C O O Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 E % of Pick Tickets Generated When Parts are not Available, etc. 10%- 8%- l 0%- 4%- 2%- E E 0% Jan90 Feb Mar Apr-May Jun Jul Aug Sep . Oct Nov Dec00 1990 114 l

E inventory Accuracy -O-Fort Calhoun Goal (98%) EmL1tiTira Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec02 INVENTORY ACCURACY 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 December,728 different line items were counted in the warehouse. Of the 728 line items counted,21 items needed count adjustments. The Inventory accuracy for the month of December was reported as 98% The Fort Calhoun 1992 goal for this indica-tor is a minimum of 98% Data Source: Willrett/McCormick (Manager / Source) Accountability: Willrett/McCormick Adverse Trend: None 7%- E % of Pick Tickets Generated When Parts are not Available, etc. ~ -O-Fort Calhoun Goal 4%- 3g c c o o e o o e o o o o st~ M E M in am M___ Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 STOCKOUT RATE 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 min' tum stocking level and parts - are not available. During December 1992, a total of 1,267 Pick Tickets wer generated. Of the 1,267 Pick Tickets generated,6 Pick Tickets (0.47%) were generated when the amount of parts requested was equal to or less than the minimum stocking level and parts were not available. The Fort Calhoun 1992 goal for this indicator is a maximum of 2.6% Data Source: Willrett/McCormick (Manager / Source) Accountability: Willrett/McCormick Adverse Trend: None 115

4%- 5 % of Total Purchases that are Expedited -O-Fort Calhoun 1991 Goal (0.5%) 3%- 2%- 1%~ c c c c -- 0 O o-rs-o-o- E EE n,,, i i i i i i i i e i i i Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 4%- D Percentage of Total Purchases that are Expedited a 3%- 2%- 1%- [5; ([ .y 7 .y h ![;; {$l?{ .'r ~ 0% 1 I i i l i I 4 4 4 i i Jan90 Feb Mar Apr May Jun Jul Aug Sep Oct - Nov Dec90 1990 - 116 1

.q 5 % of Total Purchases that are Expedited -O-1992 Fort Calhoun Goal (0.5%) 4%- Cycle 14 Refueling Outage 3%- 2%- 1%- C C C O-~ ~ M 0% Jan92 Feb Mar Apr. May Jun Jul Aug Sep Oct Nov Dec92 EXPEDITED PURCHASES This indicator shows the percentage of expedited purchases compared to the total number of purchase orders generated during the reporting month, During December, there was a total of 322 purchase orders generated.- Of the 322 purchase orders generated, there were 0 expedited purchases. The 1992 Fort Calhoun goal for this indicator is 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 o. 117

i u en ge of Material Requests for Issue wth the Request Date the sarne as 100% - E h','"Ne --O-1991 Fort Calhoun Goal ) 80%- i 00%- 4 O O O O O O O l l---l-l-l---l 40%- 0% Jan91 Feb Mar Apr May Jun Jul Aug Sep Det Nov. Dec91 1991 t 100% - E 7,*,'a$,*s in7s',*,d# ",7* * *"* * **

i eo 80%-

l 60%- 40%- 20%- 0% Jan90 Feb Mar Apr May Jun Jul Aug Sep Oct Nov - Dec90 1990 118 - avyae 9.c.'gre ew,---wry-e e-r ww =-e e-w-v s e-w-w w- *e ev = v. 1 r+ v -e v-w +e v- -e*e--+-w-w wr + %- = r e w sh-wwwww-e,*=w m---

i 100-80-t ~ 44 l 1 Service invoices COE invoices Miscellaneous j INVOICE BREAKDOWN This indicator shows the number of service invoices, COE invoices, and miscellaneous involcos for the month of December 1992. Date Source: W!!! rett /Fraser (Manager / Source) Accountability: Willrett/Fraser Adverse Trend: None I Percentage of Material Requests for issue with the Request Date the same g as the Need Date i 80%- EIII.I...,I.,._.l,,.I-..nn F / Jan92 Feb M3r bor May Jun Jul Aug Sep' Oct Nov Dec92 MATERIAL REQUEST PLANNING This indicator shows the percentage of mateHal requests (MRs) for issue with their request date the same as their need dato compared to the total number of MRs for issue for the reporting month. During the month of December, a total of 1,267 MRs were received by the warehouse. Of the 528 total MRs received by the warehouse,41.67% of the MRs (528) were for issue with their request date the same as their need date. i Data Source: Willrett/McCormick (Manager / Source) Accountability: Willrett/McCormick . Adverse Trend: None 119 ~-

1 E Total Modification Packages Open i i 400 - 312 312 312 303 g ~ 271 274 gyn m l 200 - ) Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 ) 1991 E Total Modification Packages Open i 400 - 392 200-I'N. 1 I I I i i i i i i Jan90 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Doc 90 i 1%

500 - E Total Modification Packages Open 425-400-337 300-264 0- '89 '90 91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 OUTSTANDING MODIFICATIONS This indicator shows the total number of outstanding modifications (excluding outstand-Ina modifications which are oronosed to be cancelled). Category" Rooortina Month Form FC 1133 Backlog /in Progress 7 Mod Requests Belng Reviewod - 18 Design Engr. Backlog /l_n Progress' 61 Construction Backlog /In Progress 29 Design Engr. UndMa Backloc/In Prooross 12 Total 127 At the end of December,50 additional modification requests had been issued this year and 36 modification requests had been cancelled. The Nuclear Projects Review Com-mittee (NPRC) had completed 186 backlog modification request reviews th'e year. The Nuclear Projects Committee (NPC) had completed 108 backlog modification request reviews this year. Data Source: Jaworski/ Turner-(Manager / Source) Scofield/Lounsbery (Manager / Source) 1 Accountability: Scofield/Phelps l L Positive Trend 121 -__..__u,

3 Ternporary Modificatioins >1 cycle old (RFO required for Removal) Q Temporary Modifications >6 months old (Removable on line) --O-Fort Calhoun Goal for Temporary Modifications >1 cycle old (0) 6-5. 4-3- I l 2 2 'i 2- 'e ) f 5 '// / / y 1-S S S 'l! 0-{-- October '92 November '92 December '92 TEMPORARY MODIFICATIONS (EXCLUDING SCAFFOLDING) This indicator provides information 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 greaterthan six months old. Also provided is the Fort Calhoun goal for temporary modifications. There are currently no temporary modifications that are greater than one fuel cycle old requiring a refueling outage to remove, in addition, at the end of December 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 is scheduled to revise S.O. O-44 by 2/15/93. The progress of this task will be tracked by CID 920953; 2) potable water supply piping temporary repair, which is in progress awaiting completion of MWOs 894520 and 92718. At the end of December, there was a total of 25 TMs installed in the Fort Calhoun Sta-tion 15 of the 25 installed _TMs require an outage for removal and 9 are removable on-line, in 1992 a total of 75 temporary modifications were installed.- Data Source: Jaworski/ Turner (Manager / Source) Accountability: Jaworski/Gorence AdverseTrend: None SEP 62 & 71 122 -l q q

.~ r O October C2 O November 92 [ Q December 92 10 10-I i i i 0-i O -3 rnonthe 3

6 months 6 12 months

>12 rnonths System Engineering I O October 92 O November 12 50-O Decernbar12 25 30 22 ~ 0 0 0 0 0 -3 monthe 3 6 months 6 12 monthe >12 months Design Engineering 60 - Q Overdue EARS 50 - 40-32 30-w 20-gi 8 10-3 g, 73 m 1 o Priority 1 Priority 2 Priority 3 Priority 4 Priority 5 Pr6ority 6 8 Priority 1 & 2 O Priority 3 Total Cpen EARS j 200 - 150-Data unavailable ~ N 100-for March and April 60-o T' i e i e i i i i Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct .Nov Dec92 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. At the end of December 1992. 38 EARS had been resolved and were going through the closeout process. There was 1 EAR awaiting a technical response from Nuclear Projects and 1 EAR awaiting a technical response from Nuclear Procurement. ' Total EAR breakdown is as follows: EARS opened during the month 10 - EARS closed during the month ' _11 Total EARS open as of the end of the month 136 Data Source: Phelps/Pulverenti(Manager / Source) Accountability: Jaworski/Phelps Adverse Trend: None SEP 62 123 O

~ E ECNs Ba& logged in DEN O EcNs Opened During the Month 300 - i @ ECNs Cornpleted During the Month { 250-200-M 3 Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 400-E ECNs Backlogged in DEN 350-O ECNs Opened During the Month 00-G ECNs Completed During the Month 250-200 - 150-b' Jan90 Feb: Mar Apr - May -Jun ' Jul _ Aug. Sep Oct .Nov Dec90 1990 124 ~. -. ..w.

~ N ECNs Backlogged in DEN 350-O ECNs Opened During the Month O ECNs Cornpletod During the Month 300 - ~ Cycle 14 Refueling Utage 200-150-O Jan92 Feb Mar Apr May Jun Jul Aug 'Sep Oct Nov - Dec92 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 i number of ECNc completed by DEN during the reporting month. At the end of December 1992, there was a total of 145 DEN backlogged open ECNs. There were 37 ECNs opened, and 56 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 - 1 decrease. 1 Data Source: Phelps/Pulverenti(Manager / Source) Accountability: Phelps/Jaworski Adverse Trend: None-SEP 62 l 125

i e D DEN Engineering not complete O System Engineering Engineering complete. MWO not written j @ Maintenance MWOcomplete,awaitingcloseout E Maintenance work not complete 39 38 39 40-31 24 30-s- 20- .l. 16 12 m. y. 0 E YN 0-g -EN) 5 10-3 0 1 i i i 0 3 months 3 6 months > 6 months ECN FACILITY CHANGES OPEN December 1991: I O DEN Engineering not complete O System Engineering Engineering complete, MWO not written i @ Maintenance MWO complete, awalting closeout E Maintenance work not complete f 70 - 65 60 - 50 - ; 40-30 30 - 24 20-U 11 8 11 11 [ .f...j M C i '?' O 1 1 0 3 months 3 6 months - > 6 months '- ECN SUBSTITUTE REPLACEMENT ITEMS OPEN - December 1991 E DEN Engineering not complete 1 70 - O system Engineering Waikoown or confirmation not complete - 60 - 50 - 41 40-5 0 2 0 i i i - 0 3 months 3 6 months > 6 months ') ECN DOCUMENT CHANGES OPEN December 1991: 126 , i T-g 1r--wdp.-3 g -e yya e p = g waLa op ym r--- -io=qvy em 4g,, w er air ,,gy,y .-em.------.w..,y ygy- ,p~-.--y y-.m .ea r-et+- a u---m-y

- i D DEN Engineering not complete O system Engin.oring Engineering complete, response under review O Maintenance / Construction MWO/CWO scheduled, but work not completo g Maintenance / Construction MWO/CWO complete, awaiting closoout 100 - 77 85 00-1 60-33 25 40-12 9 I 20-m.g 5 -o o 1 o lm4 o i o 3 months 3 6 months - > 6 months ECN FACILITY CHANGES OPEN f O DEN Engineering not complete } F O system Engine. ring Engine. ring compieie, response und.r review - I Q Maintenance / Construction MWO/CWO scheduled, but work not complete 3 Maintenance / Construction MWO/CWO complete, awaiting closeout T78 77 80-60-40-31 8 . 3 o 0 3 months 3 6 months > 6 months ECN SUBSTITUTE REPLACFMENT ITEMS OPEN E DEN Engineering not complete j O System Engineering Walkdown or confirmation not complete 60-36 40-20-14 7 0-o 3 months 3 6 months > 6 months ECN DOCUMENT CHANGES OPEN ] ENGINEERING CHANGE NOTICE BREAKDOWN t This indicator shows a breakdown of the number of Engineering Change Notices - (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 Changes Open, ECN Substitute Replacement items Open, and ECN Document Changes Open, Data Source: Phelps/Pulvere nti (Manager / Source) Accountability:- Phelps/Jaworski AdverseTrend; None _ SEP 62 127: .,d, mw-..,me ry.,-#s .--.wo,e -c--.w.r. n., - .,,-%,,.4,-- ,-,w.,-w,-4,_,,v .-,.v-3em e eme', -9 P 9

i i J S0-i Licensee Event Reports O Personnel Errors Reported in LERs 40- -+- CumulatNo Licensee Event Reports --+-- CurnulatNe Personnel Errors Reported in LERs 30-- i 20-10- / M ] y v I O-i i i i i e i i i i i Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91-1991: 50-O Lbensee Event Reports O Personnel Errors Reported in LERs 40-CumulatNe Licensee Event Reports -+- CumulatNe Personnel Errors Reported in LERs 30- / 20-10- -X' gr. ~I, IG 0 i. i i i i i i i Jan90 Feb Mar Apr May Jun Jul .Aug Sep Oct Nov Dec90 1990 -128 .a;---

Sol y Ucensee Event Reports S O Personnel Errors Reported in LERs Curnulatke Licensee Event Roports -+- Curnulatke Personnel Errors Reported in LERs 31 J 29 30-E 20-

14

^ ~ 'i 12 ) 9 10-

A o

j N73fl fil, h,3i, 5, @ $l,@ s y h.s N k. I n m i i i i i0 i i i i i i i i '88 '89 '90 '91 Jan92 Feb 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 (LERs) submitted during 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 December, there was a total of one (1) LER reported which was LER 92 030 "Fallure to Satisfy Fire Watch Requirements for inoperable Fire Barrier". This LER was attributed to personnel error. Data Source: Short/ Lippy (Manager / Source) Accountability: Chase Adverse Trend: None SEP 15 129

O Administrative Control Problem O ucensed operator Error @ Other Personnel Error ] @ Maintenance Problem s n ins a na ca%n ProWm 5- $ Equipment Failures 4_ 3-i 2-l 1-i ~ E 0-i i I i I I i i i i l 1-Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92. 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 January 1,1992 through December 31,1992. 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. There was one LER submitted in December 1992. The LER was attributed to Other Personnel Error. Data Source: Short/ Lippy (Manager / Source) Accountability: Chase Adverse Trend: None -130 - .+

4 O Actuai Division Statting. l E Authorized Division Statilng ~ 469 472 400-203 207 200-O i i i Nuclear Operations Productbn 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 Adverse Trend: None SEP 24 r -Q-- Nuclear Operations Division Turnover Rate --6-- Production Engineering Division Turnover Rate 10*/. - --O-Nuclear Services Division Turnover Rate 8%- 6%- l: i

w O-O--O-O--O-O--

0% A91 S91 091 N91 D91 J92 F92 M92 A92 M92 J92 - J92 A92 S92 092 N92 D92 PERSONNEL TURNOVER RATE The turnover rates for the three Divisions are calculated using only resignations from OPPD. Divislor) Turnover Rate NOD 2.9% PED 3.7% 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 131-s r'I.. v, i - ..y-,.. ,.,-re-e-. ms,-., ..,y .c.- --,-,-.,-q..-- m,-e- -m,-+ r.,,. --,w,,i-w .---,--w..... ---s r

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60 - O Total Requalification Training Hours 0 - Simulator Tralning Hours Q Non Requalificatloa Training Hours E Number of Exam Failures 40-l x x x x U U 30-- 25-20 - 14 14 14 10-a ~~ 6 6 /, ^ 5 4 4 4 /, 4 ~4 j) h, 3 g h' ~ '/ 0' o o f. 4 -Jo', 6 i i i i i i Cycle 921 Cycle 92 2 Cycle 92-3. Cycle 92-4 Cycle 92 5 - Cycle 92 6 Cycle 92 7 r ' Note: The Simulator was out-of service for rnodifications during Rotation 92 7. LICENSED OPERATOR REQUALIFICATION TRAINING This indicator providos 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. Data Source: Gasper /Guliani (Manager / Source) Accountability: Gasper /Guliani Adverse Trend: None SEP 68. [ 133'

) 40-O SRO Exams Administered - l O SRO exams passed 30-E RO Exams Administered O nO Exams passed 20-10- -l l i i i i i i i i i i i i-Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 l O SRO Exams Administered 40-3 O SRO Exams Passed E RO Exams Administered O RO Exams Passed 20- { / 7 l 10-( l u l n [ [ i g, 1 i 3 i i i i I I i i 1 Jan90 Feb Mar Apr May Jun Jul Aug Sep Oct .Nov Doc 90 1990 134

@ SRO Exams Administered O SnO Exams eassed E RO Exams Administered 30-O RO Exams Passed 20-I ~ { [ 10~ 'l k h [ 7 T-g p 0 i i i i i i i. i i i i i Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct. Nov Dec92 LICENSE CANDIDATE EXAMS This indicator shows the number of Sentur Reactor Operator (SRO) and Reactor Opera-tor (RO) quizzes and exams taken niid passed each month. These internally admints-tored quizzes and exams are used to plot the SRO and RO candidates' monthly progress. During the month of December 1992, there were two intemally administered SRO oxams and one RO exam given. All three individuals passed those exams. There were no NRC administered SRO or RO exams during December. Dt-ta Source: Gaspor/ Herman (Manager / Source) / acountability: Gasper /Guliani Adverse Trend: None SEP 68 135

l D TotalHours Other Tralning (1,000 Hrs.) 11 General Ernployeo Training (1,000 hrt) @ Technical Support (1,000 Hrs.) D Chemistry and RarSation Protection (1,000 Hrs.) - e O Maintenance (1,000 Hrs.) 10 - m n. Q Operations (1,000 Hrs.) g 8-7 $r 94. b 6- .h T b c g Y tji.,.. 4-4 -l"4 T 2~ e 0 Jan91 Feb Mar Apr May Jun Jul Aug~ Lep Oct Nov Dec91 1991 136

O Other Trainirg (1,000 Hrs.) @ General Employee Training (1,000 hrs.) @ Technical Support (1,000 Hrs.) D Chemistry and Radiation Protection (1,000 Hrs.) p O ' Maintenance (1,000 Hrs.) G Operations (1,000 Hrs.) 8 3 ~ 32-t F h. QEf 4 %= m_- I E 2 4 m = m E E 5 E a 5 5 = = 0 i i i i i i i i i i i i Dec01 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nos92 TOTAL INSTRUCTION HOURS This Indicator shows the total number of instruction hours for Operations, Malntenance, 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 munth behind the reporting month due to the time re-quired for data collection and processing. DEPARTMENT Novernber '92 Operations 253 Maintenance 376 Chemistry and Radiation Protection 148 Technical Support 359 . General Employee Training 93 Other 0 Total 1,229 Data Source: Gasper /Podoll (Manager / Source) Accountability: Gasper Adverse Trend: None 137

~~~' ~ ~ 30 - O Other Training (1000 Hrs.) - @ General Employee Training (1000 hrs.) 25- . @1 Techrncal Support (1000 Hrs.) - E Chernistry and Radiation Protecton (1000 Hrs.).- g 20 - O Maintenance (1000 Hrs.): ej @ Operations (1000 Hrs.) $15-- o a 10 - T h 88 5-md

== E-E E S 0 '~' ~ l I l 8 I I I I I I i I Jan91 Feb Mar Apr May Jun Jul Aug iSep Oct Nov. Dec91 199 O Other Training (1000 Hrs ; @ General Employee Training (1000 hrs.) 30- @ Technical Support (1000 Hrs.) E Chemistry and Radiation Protection (1000 Hrs.)- ~ O Maintenance (1000 Hrs.) f- @ Operations (1000 Hrs.) 20 2 g e t '"O $ 15-c.o g gj lllll h 5~ El = Z E C E E = ~ = ~ 0-i i i i i i i. Jan90 Feb-Mar Apr May Jun Jul-Aug.Sep Oct Nov -Dec90 - 1990 138

O Other Training (1,000 Hrs')- @ General Employee Training (1,000 hrs.) 00-D Technical Support (1,000 Hrs.) E ' Chemistry and Radiation Protection (1,000 Hrs.) 25 ~ O Maintenance (1,000 Hrs.) gf S Operations (1,000 Hrs.) - 20-E 3- $ 15-o 3 10-h b EA 6-L E =

= = = e = , m, Dec91 Jan - Fob Mar Apr May Jun Jul Aug Sep Oct Nov92 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 November '92 Operations -1,566 Maintenance 1,172 Chemistry and Radiation Protection 641 ~ Technical Support 1,404 General Employee Training 1,348 Other 0 Total 6,161 Data Source: Gasper /Podoll (Manager / Source) Accountability: Gasper Adverse Trend: None ' '139 -

9-Violations per 1000 Inspection Hours - + 1GOODI- --O-Fort Calhoun Goal p, .6 8o. 83-E~ .o5 C C -C C C C C C C. C -Q 0 Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct _., _i i i i i i i i i Nov Dec91-1991 Violations per 1000 Inspection Hours l GOOD l. --O-Fort Calhoun Goal i-9- C-C C C C C C C C C C C e 8 I Q .W ~ 8-o. 83- ~ .E _ ~ \\ ~ w B 0 i i i i i 1. .i- -Jan90 Feb ' Mar Apr May Jun Jul Aug-Sep Oct Nov ' Dec90'- 7 1990 140

I ~ Violations per 1,000 Inspection Hours lGOODI -O-Fort Galhoun Goal t .56 - 1 ? E3-j N 2.3 ? O O O-- -C O O O O 1.2 O i i i i i i i i i i i i i i i '90 '91 Doc 91 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov92 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 indicatoris 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 re ported as 2.32 for the twelve months from December 1,1991 through November 30,1992. The following NRC inspections ended during this reporting period: IER No. Iitig No. of Hrs. 92-29 Residents' Monthly inspection 464 92-31 Plant Procedures 80 No violations were issued during this reporting period. The 1992 Fort Calhoun goalis a maximum of 1.5 violations per 1,000 inspection hours. The goa) was a maximum of 1.6 violations per 1,000 inspection hours for 1991. Data Source: Short/ Lippy (Manager / Source) Accountability: Short Adverse Trend: None 141 d-

_ ~. Fort Calhoun 1.24 Cooper l: 0.73 River Bend l 1.7 -1 Commanche Peak l' 1.34 Wolf Creek l-2.02 Arkansas One l 1.61 South Texas l 1.58 + Waterford l 2.14 0 0.5 1 1.5 5 2.5 5 3.5. -4 Violations per 1,000 -Inspection Hotrs December 1991 142

l Fort Calhoun 2.32 Cooper l 1.13 River Bend l 2.81 Commanche Peak l 1.29 Wolf Creek l 2.09 Arkansas One l 1.93 South Texas l 2.71 Waterford l 2.91 1 0 0.5 1 1.5 2 2.5 3 3.5 d 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 December 1,1991 through November 30,1992. 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. 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: Ebert Adverse Trend: None i 143 1

. Y J '- t f = 25- -+-- Number of Violations During the Last i 2 Months O'

Number of NCVs During the Last 12 Months ;

20-18 1_6 16 15-P 11 11 t 10-7 7 7 7 7 h '3z 2 2-2 2f v v v v v. O i y Jan91 Feb Mar _ Apr May Jun Jul -.Aug Sep _ Oct --- - Nov _ Dec91 = 1991 -+-- Number of Violations During the Last 12 Months Number of NCVs During the Last 12 Months 50 - p 41 41_- 40-38 37 34 3_4 30-28 27 21 21 1 20-19 V T ~ 16 16 14 N 14 14N 2-1,2 < v 11 ~ 10-V -0 Jan90 Feb Mar _ Apr - May Jun Jul Aug Sep-Oct Nov.x Dec90 1990 - 144

.~ -+ - ; Number of Violations During the Last 12 Months - -H>--. Nurnber of NCVs During the Last 12 Months. 'i . 20-i c 16-15 15 15-14 14 14 14 13 13 l-i, 8 7 7f .t 5-4_ 4 4 i ~ ~ 2 2' 2 2 V V V .P = ~. 0 i i i i i i i -i i i i Dec91 Jan Feb Mar-- Apr-May. Jun Jul Aug -Sep-Oct - Nov92 - CUMULATIVE VIOLATIONS AND NCVs (TWELVE-MONTH RUNNING TOTAL) The Cumulative Violations and Non Cited Violatio_ns (NCVs) indicator shows the cumu-

lative number of violations and the cumulative number of NCVs for the last twelve

months, There were no violations issued during this reporting period.

This indicator is one month behind the reporting month due to the time involved with= collecting and processing data. Data Source: Short/ Lippy (Manager / Source) Accountability: Short Adverse, rend: None a 145' i

4 ~ E Total Outstanding CARS O - Outstanding CARS > Six Months Old 150-E Outstanding CARS That Are Modification Related. E E O ~Nov Dec91 Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct - i E Total Outstanding CAR's. O Outstanding CAR's > Six Months Oki E Outstanding CAR's That Are Modification Related 150-100-50-l E l 0 Jan90 Feb Mar Apr May Jun Jul Aug Sep Oct Nov- - Dec90

00- ~ .E TotalOutstanding CARS O Outstanding CARS > Six Months Old E Outstanding CARS That Are Modification Related 4 100 - 0-- Jan92 Feb Mar ' Apr May Jun Jul-Aug -Sep Oct Nov Dec92' OUTSTANDING CORRECTIVE ACTION REPORTS - This indicator shows the total number of outstanding Corrective Action Reports (CARS),. the number of outstanding CARS that are greater than six months old, and the number. of outstanding CARS that are modification related. At the end of December 1992, there were 72 outstanding CARS,30 CARS that were - greater than six months old, and 2 CARS that were modification related. Data Source: Orr/Gurtis (Manager / Source) u Accountability: Andrews/Gambhir/ Gates Aoverse Trend: None + 147 i .l

20-3 NOD Overdue CARS' G NOD CARS With Extensions Granted 15-10-8 r, o 5-4 3 '/ 3 2 '/ 2 '/ 2 2 1 1 '/ 1 /- 1 '/ 1- '/ 0 '/ Og 0 y gf, g'/, 0 '?, 0 :'/ 0 '/ O m, O m, 0 '/,. 00 0 c-- i i Jan91 Feb Mar Apr May Jun Jul Aug-Sep Oct Nov Dec91 1991 O PED Overdue CARS 20-Q PED CARS With Extensions Granted 15-12 12 ff' ./ 10- // 9 9 // // 8 r -r // // n '/, // // // // '/. /s /, // /s '/, // // 5 // /- '/s 4 // /- 4 4 4 S- _4 // '/. // // // i /, '/. y . '/ // // ~/, g ./ // g // ~. i '/ j p /,< j '/. '/ ,// // // /,- 3 '/. 1 1 0-i i i i i i i i i - i i i Jan91 Feb Mar Apr May Jun Jul Aug Sep . Oct Nov Dec91 1991 20-4 Other Overdue CARS-15-O Other CARS With Extensions Granted - 10-5- 3 1 1 1 11 1 7 0 00 00 0 0 00 0 00 0 00 0 / M M M C M 0 I 1 I i i i i i i l i i Jan91 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec91 1991 148

20-D NOD Overdue CAHs 15-Q NOD CARS With Extensions Granted 10 - 5 d 5-3 m 3 3 3 0 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 20-O PED Overdue CARS 15-O PED CARS With Extensions Granted 10-6 6 5 5 5 4 4 5-2 3 3 7 7 2 7 2 0 j: 0 00 OR k%' 0 [ Op 0 %: 0 3 OR 0 I: 0 3 1 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 20 - O Other Overdue CARS 15 - O Other CARS With Extensions Granted 4 5-3 3 00 00 00 00 M00 00 OR [ 0 00 - Op 11 4 4 4 6 i 4 i i i i l 1 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 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 Overdue CARS October '92 November 92 December '92 NOD 1 0 0 PED 0 0 0 Otheis 4 0 0 Total 5 0 0 Extended CARS Extended CARS October 92 November '92 December '92 NOD 3 3 3 PED 3 5 5 Others 0 0 3 Total 6 8 11 Data Source: Orr/Gurtis (Manager / Source) Accountability:- Andrews/Gambhir/ Gates Adverse Trend: None 149

1991 SALP Funct. Area CARS Signif. CARS NRC Viota. LERs A) Plant Operations 30 1 1 -6 B) Radiolog. Controls 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 Assesss 27 1 1 2 Qual. Verif H) Othei 0 0 0 0 Total 249 e 9 32 1992 SALP Funct. Area CARS Signif. CARS NRC Viola. LERs ~ A) Plant Operations 18(3) 0 0 7 B) Radiolog. Controls 11 0 6 1 C) Maint/ Surveil. 123 (5) 1 4 13 (1) D) Emergency 8 1 1 0 Preparedness E) Security - 14 (1) 0 1 0 F) Engr / Tech Suppor1 63 (8) 0 0 12 G) Satety Assess! 35(3) 1 (1) 1 0 Qual. Verif. H) Other 0 0 0 J Total 272(20) 3 (1) 13(0) 33 (1) Note: ( ) Indicate values 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/Gambhir/ Gates Adverse Trend: None SEP 15,20,21 150

4 rg = TotalOutage MWOs . -+- - Parts Hokt - -O-: MWOs Ready to Work _- -M--' Engineedng Hold -V-Outage MWR Backlog -E Planning Hold - 700-600-500 - - 400-300 - ' 200 - - 100 - ,/ v 0 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 Outage 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 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: Chase /Johansen (Manager / Source) Accountability: Chase /Johansen Adverse Trend: None SEP 31 d 151 I

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1 9 o - Baseline Schedule for PRC Apprwal - G- - Projected Schedule for PRC Apprwal - Final Design Package issued l Total Modification Packages (24) ll'llll W ;lL llllll l;;llll: lll;lllll.: : l l !;1111A mmmu g j 20-89 3.s ot 8 y 15-e t> E b O O 10-BC a- .a & E 2.!2 85-2 nnnn ~ .. ___ m _ me-~~ ---wwwwwm va ,333x3 o iiiiiiiiiiiiiiiiiii1 iiiiiiiiiiiiiiiiiii iiiiiiiii E E 8 3 6 E 0 h h j. { E PROGRESS OF CYCLE 15 OUTAGE MODIFICATION PLANNING (FROZEN SCOPE OF 24 MODIFICATIONS).:. This indicator shows the status of modifications approved for installation during the Cycle 15 Refueling Outage. The data is represented with respect to the baseline - schedule (established 6/19/92) and the current schedule.' This information is taken from the Modification Variance Report produced by the' Design Engineering Nuclear group, The goal for this indicator is to have all modification packages PRC approved by June 30,1993. Additional data poi.. ~ be added to this indicator as information becomes available. Data Source: Phes .,nne (Manager / Source) Accountability: Gamonir/Phelps Adverse Trend: None SEP 31 - 153

~ PERFORMANCE INDICATOR DEFINITIONS AGE OF OUTSTANDING MAINTENANCE WORK OR. COMPONENT FAILURE ANALYSIS REPORT (CFAR) DERS SOf44ARY This indicator tracks the total number of outstanding con The number of INPO categories for Fort Calhoun Station rective non outage Maintenance Work Orders at the Fort with significantly higher (1.645 standard deviations) fail. Calhoun Station versus their age in months, ure rates than the rest of the industry for an eighteen month time perod. Failures are reported as component AMOUNT OF WORK ON HOLD AWAITING PARTS (i.e. pumps, motors, valves, etc.) and application (i.e. This indicator is defined as the percentage of open, non. charging pumps, main steam stop valves, control ele-outage, maintenana work orders that are on hold await-ment drive motors, etc.) categories. Ing parts, to the total number of open, non outage, main-Failere Cause Categories are: tenance work orders. Wear Out/ Aging a failure thought to be the conse-quence of expected wear or aging. AUXIUARY FEEDWATER SYSTEM SAFETY SYSTEM Manutacturf: g Defect a failure attributable to inad-PERFORMANCE equate assembly or initial quality of the responsble com-The sum of the known (planned and unplanned) unavall-ponent or system. able hours and the estimated unavailable hours for the Engineering / Design a f ailure attrbutable to the inad-auxihary fedwater system for the reporting period di-equate des'gn of the responsible component or system. vided by the critical hours for the reporting period multi-Other Devices a f allure attributab!e to a f ailure or plied by the number of trains in the auxihary feedwater misoperation of another component or system, including system. associated devices. Maintenance 4esting a f allure that is a result of im. AUXIUARY SYSTEMS CHEMISTRY IPERCENT OF proper maintenance or testing, lack of rnaintenance, or HOURS OUTSIDE STATION LIMITS e tsonnel errors that occur during maintenance or test. The cumulative hours that the Component Coohng Water og activities performed on the responsible component or system is outside the station cliemistry hmit. The hours system, including failure to follow procedures. are accumulated from the first sample exceeding the lima Errors failures attributable to incorrect procedures that until additional samphng shows the pa'amster to be bacis were followed as written, improper installation of equip-within limits. ment, and personnel errors (including f ailure to follow procedures property). Also incluried in this category are CARa ISSUED vs. SIGNIFICANT CARS vs. NRC VIO-failures for which the cause is unknown or cannot be as. LATIONS vs LERs REPORTED signed to any of the preceding categories, Provides a comparison of CARS issued, NRC violations, and LERs reported. This indicator tracks performance CORRECTIVE BAAINTENANCE BACKLOG GREATER for SEP #15,20, & 21. THAN 3 MONTHS OLD The percentage of total outstanding corrective mainte. CHECK VALVE FAILURE RATE nance items, not requiring an outage, that are greater Compares the Fort Cathaun check valve failure rate to than three months old at the end of the period reported. the industry check valve f ailure rate (f ailures per 1 million component hours). The data for the industry Iailure rate CUMULATIVE VIOLA 110NS & NON CfTED VIOLA-is three months behind the Pl Report reporting month. TIONS(12 MONTH RUNNING TOTAL) This indicate, tracks performance for SEP #43. The cumulative number of violatons and Non-Cited Vio-lations for the last 12 months. COLLECTIQ DADIATION EXPOSURE Collective radiation exposure is the total external whole-DAILY THERMAL OUTPUT body dose received by all on-site personnel (including This indicator shows the daily core thermal output as contractors and visitors) during a time period, as mea-measured from computer point XC105 (in thermal mega-sured by the aermoluminescent dosimeter (TLD). Col-watts). The 1500 MW Tech Spec limit, and the unmet lective radiation exposure is reported in units of person-portion of the 1495 MW FCS daily goal for the reporting rem. This indicator tracks radological work performance month are also shown. for SEP #54. DIESEL GENERATOR RELIABluTY (25 DEMANDS) COMPARISON OF VIOLATIONS AMONG REGION IV This indicator shows tho number of f ailures 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. tor Reg on IV nuclear power plants. DIESEL GENERATOR UNAVAILABluTY This indicatcr provides monthly data on the number of hours of diesci generator planned and unplanned un-availability. 154

i 1 PERFORMANCE INDICATOR DEFINITIONS (Cont'd) DECONTAMlHATED RADIATION CONTROLLED AREA The percentage of the Radiation Controlled Area, which B) A load-run test to satisfy the plant's load and duration includes the auxiliary building, the radwaste building, and as stated in each test's specifications. areas of the CEP building, that is de ontaminated based C) Other special tests in which the emergency generator on the total square footage. This indcator tracks perfor-is expected to be operated for at least one hour while mance for SEP # 54. loaded with at least 50% of its design load.

4) Number of Load-Run Failures: A load-run f allure DISABLING INJURY /lLLNESS FREQUENCY RATE should be counted for any reason in which the emer.

(LOST TIME ACCIDENT RATE) gency generator does not pick up bad and run as pre. This indicator is defined as the number of accidents for deted. Failures are counted during any valid load-run all utility personnel permanently assigned to the station,

demands, involving daya away from work per 200,000 man-hours

5) Exceptions: Unsuccessf ul attempts to start or load-run worked (100 man years). This does not include contrac.

should not be munted as valid demands or failures when tor personnel. This indicator tracks personnel perfor-they can be attributed to any of the following: mance for SEP #25 & 26. A) Spurious trips that would be bypassed in the event of an emergency, DOCUMENT REVIEW (BIENNIAL) B) Maltunction of equipment that is not required during The Document Review Indicator shows the number of an emergency, documents reviewed, the number of documents sched. C) Intentionaltermination of a test because of abnormal uled for review, and the number of document reviews conditions that would no have r sulted in major dieset that are overdue for the reporting month. A document generator damage or repair, review is considered overdue it the review is not com-D) Ma!! unctions or operating errors which would have not plete within 6 months of the assigned due date. This prevented the emergency generator from being restarted indicator tracks performance for SEP #46. and brought to load within a few minutes. E) A f ailure to start because a portion of the starting syt - EMERGENCY AC POWER SYSTEM SAFETY SYSTEM tem was disabled for test purpose, if followed by a suc-PERFORMANCE cessiut start with the starting system in its normal align-The cum of the known (planned and unplanned) unavail-ment. able and the estimated unavailable hours for the emer. Each emergency generator failure that results in the ge 1 gency AC power system for the reporting period divided orator being declared inoperable should be counted as by the number of hourt in the reporting period multiplied one demand and one failure. Exploratory tests during by the number of trains in the emergency AC power sys-corrective maintenance and the successf ul test that fol-

tem, lows repair to venty operability should not be munted as demands or f ailures when the EDG has not been de-EMERGENCY DIESEL GENERATOR UNIT RELIABIL.

clared operable again. ITY This indicator shows the number of f ailures that were ENGINEERING ASSISTANCE REQUEST (EAR) reported during the last 20,50, and 100 emergency die-BREAKDOWN set generator demands at the Fort Calhoun Station. Also This indicator shows a breakdown, by age and priority of shown are trigger values which correlate to a high level the EAR, of the number of EARS assigned to Design En-of confidence that a umt's diesel generators have ob-gineering Nuclear and System Engineering. This indica-tained a reliability of greater than or equal to 95% when for tracks performance for SEP #62. the demand f ailures are less than the trigger values.

1) Number of Start Demands: All valid and inadvertent ENGINEERING CHANGE NOTICE (ECN) BREAK.

start demands, including all start-only demands and all DOWN start demands that are followed by load run demands, This indicator breaks down the number of Engineering whether by automatic or manual initiaten. A start only Change Notices (ECNs) that are assigned to Design demand is a demand in which the emergency generator Engineering Nuclear (DEN), System Engineering, and is started, but no attempt is made to load the generator. Maintenance. The graphs provide data on ECN Faciltty

2) Number of Start Failures: Any failure within the emer-Changes open, ECN Substitute Replacement Parts gency generator system that prevents the generator from open. and ECN Document Changes open. This indicator achieving specified frequency and voltage is classified as tracks performance for SEP #62.

a valid start f ailure. This includes any condition identified in the course of maintenance inspectons (with the emer-ENGINEERING CHANGE NOTICE (ECN) STATUS gency generator in standby mode) that def mitely would The number of ECNs that were opened, ECNs that were have resulted in a start failure if a demand had occurred, completed, and open backlog ECNs awaiting completion

3) Number of Load Run Demands: For a valid load run by DEN for the reporting month. This indicator tracks demand to be counted the load run attempt must meet performance for SEP #62.

one or more of the following cnteria; l A) A load-run of any duration that results from a real au-l tomatic or manualinitiation. 155 l

PERFORMANCE INDICATOR DEFINITIONS (cont'd)- EQUIPMENT FORCED OUTAGES PER 1,000 CRITl-GASEOUS RADIOACTIVE WASTE BEING DISJ CAL HOURS CHARGED TO THE ENVIRONMENT Equipment forced outages per 1000 critical hours is the This indicator displays the total number of Curies of all-inverse of the mean time between forced outages gaseous radicar:tive nuclides released from FCS.- caused by equipment failures. The mean time is equal i to the number of hours the reactor is criticalin a period GROSS HEAT RATE - (1000 hours) divided by the number of forced outages Gross heat rate is defined as the ratio of total thermal caused by equipment failures in that period, energy in British Thermal Units (BTV) produced by the reactor to the total gross electrical energy produced by EOUlVALENT AVAILABILITY FACTOR the generator in kilowatt-hours (KWH). This indicator is defined as the ratio of gross available generation to gross maximum generation, expressed as HAZARDOUS WASTE PRODUCED a percentage. Available generation 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, halogenated hazardous waste, and other power level permitted by equipment and regulatory limi-hazardous waste produced by FCS each month. tations. Maximum generaten is the energy that can be produced by a unit in a given period if operated continu-HIGH PRESSURE SAFETY INJECTION SYSTEM ously at maximum capacity. SAFETY SYSTEM PERFORMANCE - The sum of the known (plannad and unplanned) unavail-EXPEDITED PURCHASES able hours and the estimated unavailable hours for the The percentage of expedited purchases occurring during high pressure safety injection system for the reporting the reporting month mmpared to the total number of pur-period divided by the criucal hours for the reporting po-chase orders generated, riod multiplied by the number of trains in the high pres-sure safety injection system. FORCED OUTAGE RATE - This indicator is defined as the percentage of time that IN-UNE CHEMISTRY INSTRUMENTS OUT OF SER-the unit was unavailable due to forced events compared VICE to the time planned for electrical generation. Forced Total number of in-line chemistry instruments that are events are failures or other unplanned conditions that out of service in the Secondary System and the Post require removing the unit from service before the end of Accident Sampling System (PASS). the next weekend. Forced events include start up f ail-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 are counted each l month by the warehouse which need count adjustments. FUEL RELIABILITYINDICATOR This indicator is defined as the steady-state primary co6 INVOICE BREAKDOWN ant I-131 activity, corrected for the tramp uranium contr. The number of invoices that are on hold due to shelf life, bution and normalized to a common purification rate. COE, and miscellaneous reasons. Tramp uranium is fuel which has been deposited on re-actor core internals f rom previous defective fuel or is UCENSE CANDIDATE EXAMS - present on the surf ace of fuel elements from the manu-This indicator shows the number of SRO and/or RO quiz-facturing process. Steady state is defined as mntinuous zes and exams that are administered and passed each operation for at least three days at a power level that month. This indicator tracks training performance for o does not vary more than + or 5% Plants should collect SEP #68. data for this indicator at a power level above 85%, when possible. Plants that did not operate at steady-state UCENSED OPERATOR REQUAUFICATtON TRAIN-power above 85% should collect data for this indicator at ING ' the highest steady state power level attained during the . The total number of hours of training given to each crew

month, during eacn cycle. Also provided are the simulator train-The density correction factor is the ratio of the specific ing hours (which are a subsat of the total training hours),

i volume of coolant at the RCS operating temperature the number of non-requalifcaton training hours _and the. (540 degrees F., VI - 0.02146) divided by the specific number of exam f ailures. This indicator tracks training volume of coolant at normal letdowr, temperature (120 performance for SEP #68. degrees F at outlet of the letdown coofing heat ex-changer, VI. 0.016204). which results in a density cor-rection factor for FCS equal to 1.32. g s

PERFORMANCE INDICATOR DEFINITIONS (cont'd) L MAINTENANCE OVERTIME - LICENSEE EVENT REPORT (LER) ROOT CAUSE BREAKDOWN The % of overtime hours compared to normal hours for This indicator shows the number and root cause code for maintenance. This includes OPPD personnel as well as Licensee Event Reports. The root cause codes are as contract personnel. - follows:

1) Administrative Control Problem Management and MATERIAL REQUEST PLANNING supervisory c'efic encies that affect plant programs or The percent of materia! requests (MRs) for issues with activttles (i.e., poor planning, breakdown or tack of ad-their request date the same as their need date compared I

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 hconsed reactor opera-The total n.aximum amount of radiation received by an tors during plant activities, individual person working at FCS on a monthly, quarterly,

3) Other Personnel Error. Errors of omissiorvcommis-and annual basis; sion committed by ron-heensed personnet involved in plant activities.

MWO PLANNING STATUS (CYCLE 15 REFUELING

4) Maintenance Problem - The intent of this cause OUTAGE) code is to capture the full range of problems which can The total number of Maintenance Work Orders that have be attributed in any way to programmatic deficiencies in been approved for inclusion in the Cycle 15 Refueling the maintenance functional organization. Activities in _

Outage and the number that are ready to work (parts cluded in this category are maintenance, testing, surveil-staged, planning complete, and all other paperwork lance, calibraton and radiation protecton. ready for field use). Also included is the number of

5) Design / Construction / Installation / Fabrication Problem MWOs that have engineering holds (ECNs, piocedures This cause code covers a full range of programmatic and other miscellaneous engineering holds), parts hold.

def ciencies in the areas of design, constructon, installa-(parts staged, not yet inspected, parts not yet arrived) tion, and Iabrication (i.e., loss of control power due to a_nd planning hoki (job scope not yet completed). Main-underrated fuse, equipment not quahfied ter the environ-tenance Work Requests (MWRs) are also shown that s ment, etc.); have been identified for the Cycle 15 Refueling Outage

6) Equipment Failures (Electronic Piece-Parts or Envi-and have not yet been convened to MWOs.

ronmental-Related Failures) This code is e ad fot spuri-ous failures of electronic piece parts and failures due to NUMBER OF CONTROL ROOM EQUIPMENT DEFl-meteorological conditions such as lightning, ice, high CIENCIES winds, etc. Generfy, it includes spurious or one-time Control room equipment that cannot perform its design f ailures. Electric compcnents included in this category __ function is considered as def cient; Control room equip-are circuit cards, rectifiers, bistables, fuses, capacitors, ment _that has had a Maintenance Work Order (MWO) dodes, resistors, etc. written for it and hnnot been repaired by the end of the toporting period is considered deficient and will be UQUID RADIDACTIVE WASTE BEING DISCHARGED counted. The duration of the deficient condition is not TO THE ENVIRONMENT ' considered. This indicator displays the total number of curies from all liquid releases from FCS to the Missouri River. NUMBER OF HOT SPOTS The _ number of radiological hot spots whir;h have been LOGGABLE/ REPORTABLE INCIDENTS (SECURITY) identified and documented to exist at FCC at the end of The total number of security incidents for the reporting the_ reporting month.. A hot spot is a small lealized month depicted in two graphs, This indicator tracks se-source of radiation..A hot spot occurs when the contact curity performance for SEP #58. dose rate of an item is at least 5 times th', General Area dose rate and the item's dose rate is equal to or greater MAINTENANCE EFFECTIVENESS than 100 mrem / hour. s The number of Nuclear Plant Retiability Data System (NPRDS) components with more than 1 failure and the NUMBER OF NPRDS MULTIPLE FAILURES number of NPRDS components with more than 2 failures The number of NPRDS reportable failures over the pre-for the last eighteen months. ceding eighteen months sorted by component manufac-turer and model number. MAINTENANCE WORK ORDER BREAKDOWN This indicator is a breakdown of corrective non-outage maintenance work orders by several categories that re-main open at the end of the reporting month. This indi-cator tracks maintenance performance for SEP #36 157

PERFORMANCE INDICATOR DEFINITIONS (Cont'd) j NUMBER OF PERSONNEL ERRORS REPORTED IN OVERALL PROJECT STATUS (CYCLE 15 REFUEL-LERS ING OUTAGE) The number of Licensee Event Reports (LERs) attrbuted This indicator shows the status of the projects which are to personnel error on the original LER submittal. This in the scope of the Cycle 15 Refueling Outage; indcator trends personnel performance for SEP #15. OVERDUE AND EXTENDED CORRECTIVE ACTION - NUMBER OF MISSED SURVEILLANCE TESTS RE-REPORTS SULTING IN_ LICENSEE EVENT REPORTS The number of overdue Corredive Action Reports The number of Surveillance Tests (STs) that result in (CARS) and the number of CARS which received exten. Licensee Event Reports (LERs) during the reporting sions broken down by organization for the last 6 months. month. This indicator tracks missed STs for SEP #60 & 61. PERCENT OF COMPLETED SCHEDULED MAINTE-NANCE ACTIVITIES OPERATIONS AND MAlfGENANCE BUDGET The % of the number of completed maintenance activi-The year to-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 month. This % is shown for each maintenance craft. Maintenance activities include MWRs, OUTSTANDING CORRECTIVE ACTION REPORTS MWOs, STs, PMOs, calibrations, and other miscella-i This indicator displays the total number of outstanding neous activities. These indicators track Maintenance - Corrvelive Action Reports (CARS), the number of CARS performance for SEP #33. that are older than six months and the number of modifi-cation related CARS. 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 number of Modification Requests (MRs)in any state ignation from the company, Retirement, death, termina-between the issuance of a Modification Number and the tion, transfers within the company, and part-time employ-completion of the drawing update, eos are not considered in turnover.

1) Form FC-1133 Backlog /in Progress. This number rep-resents modification 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 period of time, to the reference energy generatiori Ghs includes:

energy that could be produced tf the unit were operated A.) Modification Requests that are not yet reviewed. continuously at full power under reference amoient cx)n-B.) Modification Requests being reviewed by the Nuclear - ditions), expressed as a percentage. Projeds Review Committee (NPRC). C.) Modification Requests being reviewed by the Nuclear PREVENTIVE MAINTENANCE ITEMS OVERDUE L Projects Committee (NPC) This indicator is defined as the % of prevent.ve mainte. These Modification Requests may be reviewed several nance items in the month that were not completed by the times before they are approved for accomplishment nr scheduled date plus a grace period equal to 25 % of the cancelled. Some of these Modification Requests are scheduled interval. This indcator tracks preventive retumed 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 work is clearly defined, these OF LIMIT Modification Requests may be approved for accomplish-The % of hours out 7f limit are for six primary chemistry ment with a year assigned for construction or they may parameters divided by the total number 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 limits are used.

Planning has assigned a year in which construction will be completed and design work may be in progress. PROCEDURAL 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 related to the use of procedures (includes the number of Acceptance Committee (SAC). closed irs caused by procedural noncompliance), and S) Design Engineering Update Backlog /In Progress. PED has received the Modification Completion Report but the the number of closed procedural noncompliance irs. drawings have not been updated. This indicator trends personnel performance for SEP The above mentioned outstanding modifications do not

15,41 & 44.

include modifications which are proposed for cancella-tion. 158

f m-

PERFORMANCE INDICATOR DEFINITIONS (Cont'd) PROGRESS OF CYCLE 15 OUTAGE MODIFICATION PLANNING (FROZEN SCOPE OF 24 MODIFICA. T10NS) This indcator shows the status of modifications ap-system computer. proved for completion during the Cycle 15 Refueling Out-3) Security Force Error Events caused by members of age. the secunty force that are found to be inattentNo to their duties or who neglected to properly perform assigned RADIOLOGICAL WORK PRACTICES PROGRAM functions (e g., required search procedure or patrol). The number of identified poor radological work practices

4) Unsecured Doors Doors which are found to be unse.

(PRWPs) for the reporting month. This indicator tracks cured with no compensatory officer posted or where the radiological work performance for SEP #52. Individual causing the alarm did not remain at the alarmed door until a security officer responded. Events RATIO OF PREVENTIVE TO TOTAL MAINTENANCE where an unsecured door is caused by airmassuit are The ratio of preventive rnaintenance (including surveil-included in this category unless there is an indcation that lance testing and calibration procedures) to the sum of an adjustment was made to the door, non-outage corrective maintenance and preventive main- 'Ihis indcator tracks security performance for SEP #58. tenance completed over the reporting period. The ratio, expressed as a percentage, is calculated based on man-SECURITY SYSTEM FAILURES hours. This ind cator tracks preventive maintenance ac-The following components are the types of loggable/re-tivities for SEP #41, portable SECURITY SYSTEM FAILURES represented in this indicator, incidents in this category include alarm RECORDABLE INJURY /lLLNESS CASES FRE-system f ailures, CCTV f ailures, security computer f ail-QUENCY RATE ures, search equipment iailures, and door hardware f all-The number of injuries requiring more than normal first ures. These system failuros are further categorized as aid per 200,000 man-hours worked. This indcator follows: trends personnel performance for SEP #15,25 & 26.

1) Alarm System Failure Detection system events in-volving f alse/ nuisance alarms and mechanical f ailures.

SECONDARY SYSTEM CHEMISTRY PERFORMANCE

2) Alarm System Environs Degradations to detection INDEX system performance as a result of environmental condi-The Chemistry Performance Index (CPI) is a calculation tions (i.e., rain, snow, frost).

based on the mncentration of key impurities in the sec-

3) CCTV Failures Mechanical failures to all CCTV hard-ondary side of the plant. These key impurities are the ware components, most likely cause of deterioration of the steam genera-

4) CCTV Environs Degradations to CCTV performance tors. The chemistry parameters are reported only for the as a result of environmental conditons (i.e., rain, snow, period of time when the plant is operated at greater than frost, fog, sunspots, shade).

30 percent power.

5) Security Computer Failures Failure of the multi-The CPI is calculated using the following equation: CPI =

plexer, central processing unit, and other computer hard. (Ka/0.8) + (Na'20) + (O,/10) / 3 where the following are ware and schware. This category does not include soft-monthly averages of: Ka average blowdown caton ware problems caused by operator erro-in using the conductivity, Na = average blowdown sodium concen-

software, tration, O, - average condensate pump dischargo 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 of The following components are the types of loggable/re-did not function property during testing. portable non system f ailures represented in this indica-

7) Door Hardware Failures Failure of the door alarm tor. Incidents in this category include secur ty badges, and other door hardware such as latches, electric strikes, access control and authonzaton, secunty force error, doorknobs, locks, etc.

and unsecured doors.

8) 1991 versus 1992 System Failures - Statistes from

1) Secunty Badges Incidents associated with improper 1991 will be compared on a monthly basis with 1992 use and handling of securrty badges. Incidents include loggable/ reportable system failures. This indcator tracks security badges that are lost, taken out of the protected security performance for SEP #58.

area, out of control on stte, or inadvertently destroyed or broken. SPARE PARTSINVENTORY VALUE

2) Access Control and Authorizatica - Adminstrative 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 security badge issued, and improper escort procedures. This SPARE PARTS ISSUED also includes incidents that were caused by incorrect The dollar value of the spare parts issued for FCS during access authorization information entered into the secunty the reporting period. 159

~. PERFORMANCE INDICATOR DEFINITIONS (Cont'd) STAFFING LEVEL TOTAL INSTRUCTION HOURS - The actual staffing level and the authorized staffing level The total number and department breakdown of training a for the Nuclear Operations Division, the Produdion Engl-instruction hours administered by the Training Center, neering Division, and the Nuclear Services Division. This indicator tracks performance for SEP #24. TOTAL SKIN AND CLOTHING CONTAMINAT ONS Reportable skin and clothing contaminations above STATION NET GENERATION background levels greater than 5000 dpm/100 cm -- The not generation (sum) produced by the FCS during squared, This indicator trends personnel performance - the reporting month. for SEP #15 & 54, STOCKOUT RATE UNIT CAPABILfTY FACTOR The total number of Pick Tckets that were generated - The ratio of the available energy generation over a given during the repurting month and tho total number of Pck time period to the reference energy generation (the on-Tickets that were generated during the reporting month ergy that could be produced if the unit were operated when the amount of parts requested is equal to or less continuously at full power under reference ambient con-than the minimum stocking level and parts are not avail-ditions) over the same time period, expressed es a per-able. contage. TEMPORARY MODIFICATIONS UNPLANNED AUTOMATIC REACTOR SCRAMS PER The number of temporary mechanical and electrical con-7,000 CRITICAL HOURS. Igurations to the plant's systems. This indicator is defined as the number of unplanned au-

1) Temporary configurations are defined as electrical tomatic scrams (reactor pmtection system logic actua-jumpers, electrical blocks, mechanical jumpers, or me-tions) that occur per 7,000 hours of critical operation.

chanical blocks which are installed in the plant operating The value for this indicator is calculated by muhiplying systems and are not shown on the latest revision of the the total number of unplanned automatic reactor scrams PalD, schematic, mnnection, wiring, or flow diagrams. in a specific time period by 7,000 hours, then dividing

2) Jumpers and blocks which are installed for Surveil-that number by the total number of hours criticalin the lance Tests, Maintenance Procedures, Calibration Pro-same time period. The indcator is further defined as cedures, Special Procedures, or Operating Procedures follows:

are not considered as temporary modifications unless the 1) Unplanned rneans that the scram was not an anticii jumper or block remains in place after the test or proco-pated part of a planned test. dure is complete. Jumpers and blocks installed in test or 2) Scram means the automatic shutdown of the reactor lab instruments are not considered as temporary modifi-by a rapid insertion of negative reactivity (e.g., by mntrol 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.

temporary modifications until final 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 r-odifications for SEP #62 & 71, eters and conditions, rather than the manual scram -

switches or, in manual turbine trip switches (or push-but. TH.JAL PERFORMANCE tons) provided in the main control room. The ratio of the design gross heat rate (mtracted) to the

4) Critical means that during the steady state condition of adjusted actual gross heat rate, expressed as a percent-the reador prior to the scram, the effective meltiplication age.

factor (k,) was essentially equal to one. TOTAL HOURS OF STUDENT TRAINING UNPLANNED CAPABluTY LOSS FACTOR The total number of student hours of trair',g for Opera-The ratio of the unplanned energy losses during a given tions, Maintenance, Chemistry / Radiation f otection, period of time, to the reference energy generation (the Technical Support, General Employee Tral ing, and energy that could be produced if the unit were operated Other Training conducted for FCS. continuously at full power under reference ambient mn-ditions) over the same time period, expressed as a per-Centage. I 160

PERFORMANCE INDICATOR DEFINITIONS (Cont'd) UNPLANNED SAFETY SYSTEM ACTUATIONS-(1NPO DEFINITION) This indicator is defined as the sum of the following safety system actuations:

1) The number of unplanned Emergency Core Cooling System (ECCS) actuations that result from reaching an ECCS actuation setpoint or f rom a spurious / inadvertent ECCS signal

2) The number of unplanned emergency AC power sys-tem actuations that result from a loss of power to a safe-guards bus. An unplanned safety system actuation oc-curs when an actuaton setpoint for a safety system is reached or when a spurious or inadvertent signal is gen-erated (ECCS only), and major equipment in the system is actuated. Unplanned means that the system actuation was not part of a planned test or evolution. The ECCS actuations to be counted are actuations 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 actuations which include (2n!Y.) the High Pressure Safety injection System, the Low Pressure Saf ety injection System, the Safety injec-tion Tanks, and the Emergency Diesel Generators. The NRC classification of safety system actuations includes actuations when major equipment is operated and when the logic systems for the above safety systems are chal-lenged. VIOLATIONS PER 1,000 INSPECTION HOURS This indicator is defined as the number of violations sited in NRC inspection reports for FCS per 1,000 NRC in-spection hours. The violations are reported in the year that the inspection was actually performed and not based on when the inspection report is received. The hours reported for each inspedian report are used as the in-spection hours. VOLUME OF LOW LEVEL SOLID RADIOACTIVE WASTE This indicato is defined as the volume of low-level solid radioactive waste actually shipped for burial This indica-tot also shows the volume of low-level radioactive waste which is in temporary storage, the amount of radioactive 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 radoac-tive waste consists of dry active waste, sludges, resins, and evaporator bottoms generated as a result of nuclear power plant operation and maintenance. Dry radioactive waste includes contaminated rags, cleaning materials, d:sposable protective clothing, plastic containers, and any other material to be disposed of at a low level radio-active waste deposal site, except resin, sludge, or evaporator bottoms. Low-level refers to all radioactive waste that is not spent f uel or a by-product of spent f uel processing. This indicator tracks radidagical work per-formance for SEP #54. 1 61 1

SAFETY ENHANCEMENT PROGRAM INDEX.

'The purpose of the Safety Enhancement Program (SEP) Performance indicators Index 0 to list periso mance indicators related to SEP items with parameters that can be trended.- SEP Reference Number 15

Pagg increase HPES and IR Accountability Through Use of Performance Indicators Procedural Noncompilance_ incidents (Maintenance).............................................................. 67 l Total Skin and Clothing Co nta minations.............................................................................'.95 -

Recordable injury /Illne ss Cases Frequency Rate..................................................................... 39 Number of Personnel Errors Reported in LE Rs............................................................129 CARS issued vs Significant CARS issued vs NRC Violations issued vs LERs Reported.............150 ' SEP Reference Number 20 - Quality Audits and Surveillarue Programs are Evaluated, improved in Depth and Strengthened CARS issued vs Significant CARS issued vs NRC Violations issued vs LERs Reported............150 SCP Reference Number 21 Develop and Conduct Safety System Functionalinspections CARS issued vs Significant CARS issued vs NRC Violations issued vs LERs Reported............150 SEP Reference Number 24 Complete Staff Studies Staffing Level ...................................................................................................131 i i SEP Reference Number 25 Training Program for Managers and Supervisors implemented Disabling Injury / Illness Fraquency Rate...................................................................... 37 Recordable injury /lllness Cases Frequency Rate........................................................... 39 SEP Reference Number 26 Evaluate and Implement Station E*andards for Safe Work Practice Requirements Disabling injury /lliness Frequency Rate............................................................... 37. j Recordable injury /lliness Cases Frequency Rate....................... .....................................39 i q SEP Reference Number 31 j Develop Outage and Maintenance Planning Manual and Conduct Project Management Training l M WO PlanrJng Statu s..................................................................................... 151 1 Ove rall Proj ect S tatu s........................................................................................... 152 Progress of Cycle 15 Outage Modification Planning............. ........ 153 SEP Reference Number 33 Develop On.Line Maintenance and Modification Schedule Percent of Completed Scheduled Maintenance Activities ( Elect rical M alnt e na nce)..............................................-............................................... 68 1 (Pressure Equipment).... ... 69 (General Maintenance). ...,.... 70 (M echanical M aint e na nce)............................................................. -............................. 71 q (Instrumentation & Control)...... .......................,.............72 1 SEP Reference Number 36 -i Reduce Corrective Non-Outage Backlog _ '1 Maintenance Work Order (MWO) Breakdown (Corrective Non-Outage Maintenance)........... 55 Corrective Maintenance Backlog Greater than 3 Months Old (Non-Outage)........................ 57 i SEP Reference Number 41 Develop and implement a Preventive Maintenance Schedule - Ratio of Preventive to Total Maintenance.. .......... 59 Preventive Maintenance items Overdue.. .. 61 Procedural Noncompliance incidents..................... . 67 162 i

S E P R et e re nce Nu mbe r 4 3.................................................................................. EaQA Implement the Check Valve Test Program Check Vatve Failure Rate..............,... ............ 81 SEP Reference Number 44 Compliance With and Use of Procedures Procedural Noncompliance incidents (Maintenance)....... .............................67 i SEP Reference Number 48 Design a Procedures Control and Administrative Program Document Review..... ..... 47 ) SEP Reference Number 52 Establish Supervisory Accountability for Workers Radiological Practices Radiological Work Practices Program. ..................99 SEP Reference Number 54 Complete implementation of Radiological Enhancement Program Collective Radiation Exposure.................... .......... 33 Volume of Low Level Solid Radioactive Waste... ... 35 Total Skin and Clothing Contaminations............. ,................95 Decontaminated Radiation Controlled Area.. .. 97 SEP Reference Number 58 Revise Physical Security Training and Procedure Program Loggable/ Reportable tncidents (Security).... ,,.10 7 Security Non-System Failures...... ....... 108 Security System Failures... ..109 SEP Reference Number 60 Improve Controls Over Surveillance Test Program Number of Missed Surveillance Tests Resulting in Licensee Event Reporte.... ... 73 SEP Reference Number 61 Modify Computer Program to Correctly Schedule Surveniance Tests Number of Missed Surveillance Tests Resulting in Licensee Event Reports.. ........ 73 SEP Reference Number 62 Establish Interim System Engineers Temporary Modifications........ ..122 Engineering Assistance Request (EAR) Breakdown................. .123 Engineering Change Notice Status.. . 125 Engineering Change Notice Breakdown. ..... 127 SEP Ref erence Number 68 Assess Root Cause of Poor Operator Training and Establish Means to Monitor Operator Training Licensed Operator Requalification Training..... ..133 License Candidate Exams... ..... 135 SEP Reference Numbar 71 Improve Controls over Temporary Modifications ..122 Temporary Modifications.... 163 i

3 REPORT DISTRIBUTION LISTL 1 R. '. Mueller-' l R.L. Andrews . R. E, Gray J G. L. Arglehart-MiJ. Guinn M. W. Nichols.- . W. R. Bateman G. E. Guliani. C. W. Norris: K. L Belek . K. B. Gullani Nuclear Licensing - _T. G. Blair : E. R. Gundal. & Industry Affairs-B. H. Biome R. H. Guy. _ J. T. O'Connor C. N. Bioyd - R. M. Hawkins W, W. Orr J.P.Bobba M. C. Hendrickson L L Paren C. E. Boughter R. R. Henning : T. L Patterson 1, M. A. Breuer K. R. Henry - ' R. T. Pearce C. J. Brunnert J. B, Herman _ R. L. Phelps ~W.J.Ponec M. W. Butt G. J. Hill. .L. M. Pulverenti C. A.Carlson K. C. Hotthaus J. W. Chase L. G. Huliska T. M. Reisdorff G. R. Chatfield C. J. Husk A. W. Richard - A. G. Christensen R. L. Jaworski R. T. Ridenour A. J. Clark R.A.Johansen D. G. Ried, O. J. Clayton W.C. Jones. G. K. Samide R. P. Clemens J. D. Kecy. T.J.Sandene J. L. Connolley J. D. Keppler M. J. Sandhoefner G. M. Cook D. D. Kloock B.- A. Schmidt J.E. Cook J. C. Knight S. T. Schmitz M. R. Core D. M. Kobunski ' F. C, Smfield i S. R. Crites - G. J. Krause H. J. Seficki - D. W. Dale J. G. Krist J. W. Shannon R. C. DeMeulmeester L.T.Kusek-R. W. Short ' O. C. Dietz -L.E. Labs C. F. Simmons K.S. Dowdy M. P. Lazar E.L.Skaggs J. A. Drabota R. C. Learch J. L. Skiles ? T. R. Dukarski R. E. Lewis - F. K. Smith R._G. Eurich - R. C. Liebentritt ' R. L. Sorenson H. J. Fauhiaber D. L. Lippy J. A. Spilker M. A. Ferdig-B. Lisowyj K. E. Steele ' - F. F. Franco B. R. Livingston W.-- Steele M. T. Frans J. H. MacKinnon. H. F. Stert>a - H. K. Fraser - G. D. Mamoran ' - G. A.- Teeple, J. F. W. Friedrichsen J. W. Marcil M. A. Tesar S. K. Gambhlr N, L. Mastice J. W. Tills J. K. Gasper R. D. Martin D. R. Trausch : W. G. Gates D. J. Matthews - P.' R. Tumer - M. O. Gautier J. M. Mattice J. M. Uhland S. W. Gebers T. J. Mcivor C. F. Vanecek 3 J, M. Glantz K. S. McCormick J. M. Waszak = J. T, Gleason R. F. Mehaffey G. R. Williams L. V. Goldberg . K. G. Meistad S. J. Willrett D. J. Goklen . K; J. Morris - W. C. Woerner-D. C. Gorence D. C. Mueller 164-

FORT CALHOUN STATION OPERATING CYCLES AND REFUELIN3 OUTACE DATES '~ kvent Date Range Production (MWH) Cumulative (MWH) Cycle 1 09/26/13 -02/01/75 3,299,639 3,299,639 1st Refuellog 02/01/75-05/09/75 Cycle 2 05/09/75-10/01/76 3,853,322 7,152,961 2nd Refueling 10/01/76 12/13/76 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 10/14/78-12/24/78 Cycle 5 12/24/78- 01/18/80 3,882,734 16,868,454 5th Refueling 01/18/SO 06/11/80 Cycle 6 06/11/80 - 09/18/81 3,899,714 20,768,168 6th Refueling 09/18/81 - 12/21/81 Cycle 7 12/21/81 -12/06/82 3,561,866 24,330,034 71h Refueling 12/06/82 - 04/07/B3 Cycle 8 04/07/83 - 03/03/84 3,406,371 27,736,405 8th Refueling 03/03/P4 07/12/84 Cycle 9 07/12/B4 - 09/28/85 4,741,488 32,477,893 Sch Refueling 09/28/85 - 01/16/86 Cycle 10 0 t/16/86 - 03/07/87 4,356,753 36,834,646 10th Refueling 03/07/87 - 06/08/87 Cycle 11 06/08/87 - t 9/27/88 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 121h Refueling 02/17/90 05/29/90 Cycle 13 05/29/90 -02/01/92 5,451,669 51,040,528 131h Refueling 02/01/92- 05/03/92 Cycle 14# 05/03/92-09/18/93 (Planned Dates) 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 Sustained Reaction August 5,1973 (5:47 p.m.) First Electricity Supplied to the Systc m August 25,1973 Commercial Operation (180,000 KWh) September 26,1973 Achieved Full Power (100%) May 4,1974 Longest Run (477 days) June 8,1987-Sept. 27,1988 Highest Monthly Net Generation (364,468,800 KWH) October 1987 Most Productive Fuel Cycle (5,451,069 MWH)(Cycle 13) May 29,1990-Feb.1,1992 _ _ _-_-}}

ML20128C324

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