Text

Performance Indicators,Oct 1992
	ML20128B488
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Site:	Fort Calhoun
Issue date:	10/31/1992
From:	; OMAHA PUBLIC POWER DISTRICT
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FORT CALHOUN STATION PERFORMANCE INDICATORS OCTOBER 1992 l

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OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT Prepared By:

Production Engineering Division System Engineering Test and Performance Group OCTOBER 1992

ABSTRACT PURPOSE The

Performance Indicators Program"is intended to provide selected Fort Calhoun plant perfor-rnance information to OPPD's personnel responsible for optimizing unit ;.erformance. The information is presented in a way that provides ready identification of trends and a means to track progress toward reaching corporats 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 comparison or as a means of promoting pride and motivation.

SCOPE The conditions, goals, and projections reflected withir ~ is report are current as of the end of the month being reported, unless otherwise stated, in order for the Performance indicator Program to be effective, the following guidelines were followed while implementing 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 talWed 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 performance, it is suggested that this report be distributed throughout your respective departments.

REFERENCES INPO Good Practices OA 102, " Performance Monitoring - Management information" lNPO Report Dated November 1984,"Nuctear 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.

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OCTCBER 1992

SUMMARY

FOSITIVE TREND REPORT ADVERSE TREND REPORT (Cont'd)

The Positive Trond Report hghbghts several Perfor.

mance Indcators with data representing continued pet.

ELoineenno Aintance Roovett (EAR) Breakdown formance obove the stated goal and indcators wrth data (Page 66) representing signihcant improvement in recent months.

An adverse trend is Indicated based on three ensecu-live months of increasing values for Design Engineering The following indicators have been selected as exhitatirg EARr. >6 months old. This increase is partially attribut-positive trends for the reporting month:

able to the forced outages in July and August. An acton plan has been estabhshed which includes a review by System Engineering or Design Engineering of older 11gbon rJet Generatieg EARS (>12 months)that are a lower priorrty to see if they (Page 1) can ba cecolled.

Fort Crilhoun Staten not generation has increased for three consecuttve months since the Jufy 1992 forced out-End of Adverse Trend Report.

aDe caused by the loss of an invertar.

Eauka!9nt AvaitaSStv Fnetor (Page 11)

F# Calhoun Stetion achioved an equivalent availabihty INDICATORS NEEDING INCREASED

'utor of 99.2% for October. The EAF has increased for MANAGEMENT ATTENTION REPORT inroe mnsecutko months.

Thtc section Osts the indcators whch show Ir.adequacios Unft Cggability Factof as mmpared to the OPPD goal and indicators which (Page 12) show inadequacies as compared to the approximate in-Fort Calhoun Staton achieved a unit capabildy f actor dJstry upper ten percentile. The indicators will be com-value of 100% for the month of October 1992. The UCF pared to the approximate industry upper ten percentile has increased for three consecutNo months.

as relwant to that indicator.

Document Review (Page 22)

Forced Outnoe Rate There have been no overdue documents scheduled for (Page 2) review for three consecutNo months.

The forced outage frite value for the twelve months frorn 11/1/91 through 10 3142 (10.09%)is above the 1991 Humber of Personnel Errors Rooorted,lg,M and 1992 Fort Calhoun goals of 2.4%.

(Pege 70)

The number of perr.onr a errors report 4 in LERs for Fort Unclanned htomatic Rondor Setams ner 7.000 Hours Calhoun Station for the months of Septe.nber and Octo.

Critical ber 1992 is 0, (Page 3)

The number of unplanned automatic reactor scrams per 7,000 hours0 days 0 hours 0 weeks 0 months critical year to date value for the reporting End c sitive Trend Report month (4 85) exceeds the 1992 Fort Calhoun goal of zero (0).

ADVERSE TREND REPORT M* "" *d 8 "" 8 ' * * *"'" *"'" * ' "" "

(Pege 4)

The number of unplanned safety system actuations A Performarco indcator waich has data representin9 (INPO definition) year-to date (1) exceeds the 1992 Fort three (3) consecutive months of declining performance Calhoun goalof zero.

onnstitutes an adv.:se trend. The Adverse Trend Report explains the rundttons under which certain indbators Uno!anned Safety Svetem Actuations -(NRC D Scjtj20) are showing.tJverse trends.

(Page 5)

The number of umlannei *fety systora actuations The fo* wing indicators are exhibit;tg adverse trends for (NRC definition) year tomate (4) exceeds the 1992 Fort -

the rep.ng month:

Calhoun goalof a maximum of 3.

Eue! Reliabihtv Indicggi Therma! Porformance (Pags 15)

(Page 10)

The FRI value for the reporting month (8.1 X 10 4) ex-An adverse trend js indicated baseo or, four consacutNo coeds the 1992 Fort Calhoun goal of 7.5 X 104, months of dockning performance, i

INDICATORS NUEDING INCREASED INDICATORS NEEDING INCREASED MANAGEMENT ATTENTION REPORT MANAGEMENT ATTENTION REPORT (Cont'd)

(cont'd) fd llecibe Radiation Frooture

\\*solatb9s'1.000 Intoodbn Hours (Page 16)

(Page 77)

The year-to dato colledive radiaton exposure for the The violations por 1,000 inspection hours value for 15e reporting month (251.2 permRem) exceeds the 1992 last twelve months (2.61) exceeds the 1991 Fort Cal-Fort Calhoun goalof 250 person rom.

houn goal of a maximum of 1.6 and the 1992 Fort Cal.

houn goal of a maximum of 1.5.

Disab!ina in!urv/l!! ness Fr*2genw Rate (Lost TimeM dent Ratit)

(Page 19 End of Management Attenton Ret ort.

The disabling in3ury411 ness frequency rate year.to<f ate value for the reporting month (1.23) exceeds the 1992 Fort Calhoun goal cf 0.30.

rnuiomont rorced outaaes ocr 1.000 Critieni nours PERFORMANCE INDICATOR REPORT (Page 20)

IMPROVEMENTS / CHANGES The equipment forced outages per 1,000 critical hours year to date value for the reporting month (1.15) ex-coeds the 1992 Fort Calhoun goalof 0.20.

This section lists signifcant changes made to the report natio of Preventive to Total Maintenance and to Spoc#c indicators within the report skce the pre-vlous month (pag, pg)

The ratio of preventive to total maintenance for the re' Summary Sodbn porting month (60%) is less than the 1992 Fort Calhoun (Pages i snd it) goalof a minimum of 65%.

As requested by the Quality Assurance department, the s mary sect n has been moved to the front of the re-Secondary Syttom Ch s;jg t

(Page 44)

The CPI value for the reporting month (0.468) exceeds IAble of Contents tne 1992 Fort Celhoun goal of 0.45.

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Forformance indicators indicating adverse trends or In-Line Cherr$rv Instruments Outof. Service needing increased management attention have been (Page 47) nighlighted*

The number of in-line chemistry instruments out of ser-vice for the reporting month (17) exceeds the 1992 Fort Number of Control Room Eauioment Deheie'LCjag Calhoun 9oalof a mari um of 6.

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Maximum Indvidual Radiation Eroosure Control Room instruments *) has been revised due to a e aximum indtvidual radiation exposure year to date n in me s value for the reporting month (1,763 mrem) exceeds the 1992 Fort Calhoun goal of a maximum of 1,500 mRom.

Proaress of Cvele is outnoe Modif 6ation Plannira (Page 85)

Total Skin and Clothina Contamingitan The graph for this indicator has been revised.

(Page 50)

The cumulative skin and clothing contaminations year to-date for the reporting month (264) exceeds the 1992 Fort End of Performance indicator Report improvements /

Calhoun goalof a maximum of 144.

Changes Resat)

RecordaHe IniurvMllness Cases Frocuenev Rate (Page 69)

The recordable injury 411 ness cases frequency rate for the months f rom January through October (3.49) exceeds the Fort Calhoun goal of a maximum of 2.0.

ii t

.a.

Table of Contents / Summary INPO INDUSTRY KEY PARAMETERS f%QE e m inY

.Q!H.

DEED om n a g w, Ytos uwm utt uymi IfiUD UNPLANNED AUTOMATC REACTOR SCRAMS PE R 7.000 HOURS CRITICAL............... 0 6...... 0...... 4 e5.

. 5 os..... H M A..... 3 SAFETY SYSTEM PERFORMANCE tr=+=.w c

HIGH PRESSURE S AFETY INJECT ON GYSTE M...................

..00012.

. 0 008..

0.0012.

..00014.

.. NA..

.6 AUXfLIARY rEEDWATER SYSTEM.,............. 0 0038... 0 01.

..0.0078..

.,0 0065,.... N A.,.... 7 i

EMERGENCY AC POWER $YSTEM.

.... 0 0055..

. 0 024.

..0 0013..

..0 0015..

.. N A..

.8 TH E RM AL PERFORMAN CE..................

..................99 6%.... 99.3%... 99.3%..... 99 4%....... A......1 L UNIT C APADILITY FACTOR................................... 89 6%....692%

..100%..

..77.5%.

.. l...... 12 UNPLANNED CAPABILITY LOSS FACTOR........

.... 1 B5%..

. 4.5%..

. 0%.... 22.5%..

.. l........ 13 FUEL RELIABILITV INDICATOR e==wwm NA....... 7.5:10 4.. 8.1x10 4... 7.76x10 4.....NMA.. 15 COLLECTlVE RADIATON EXPOSURE (perem).115 6/YR 250/YR.... 251.2...... 245.3....._NMA...16 VOLUME OF LOW. LEVEL SOLID RADIOACTIVE WASTElaa to.

. 2.077EYk.. 3,000/YR. 1938 8..,1.306.4.

.. N A..... 17 INDUSTRIAL SAFETY ACCIDENT RATE / DISABLING INJURY /lLLNESS FREQUENCY RATE.....

0.12...

.. o 3...

... 1.23...... 1.12........ N M A.... 18 CHEMISTRY INDEX/ SECONDARY SYSTE M CH E MISTT1Y................................... -.... 0.20...

.0 45...... 0 468....... 0.515...... N MA.....d4 OPERATIONS

!%GE R@$1RY

.QEED,,

OfEQ pm n m ggg, ims ummi Lgt uoema inna STATON NET GENERATON (10,000 Mwh).....,.......NA....-

..NA.

4 35 9.

... 27.2...

.. l......... 1 FORC E D OUTAGE RATE..............................0.25%...... 2.4% ~.10.09%

..12.1 %.... N MA...... 2 UNPLANNED AUTOMAb REACTOR SCRAMS pef 17,000 CRITICAL HOURS.............-...0. 6....... 0...... 4 85....... 5 90...... N MA...... 3 UNPLANNFJ SAFETY SYSTEM -

ACTU AT KsN S - (INPO DE FINITION).............................,0....... 0......... 0.......

....o...-....... N M A...... 4 UNPLAFNED SAFETY SYSTEM ACTU ATONS - (N RC DEFINITON)..................... 0...........,. 3..

. 0... -...... 0....... N MA...... 6 GROS S HE AT RATE..................................... N A...

.. NA... 10.101.

..10.225..

.. l........ 9 EOUlVALENT AVAILABILITY FACTOR................NA....... N A... 99 2%.... 81.0%.

,. l...... 1 1 VillT CAPABILITY FACTOR -.

.......... 8 9 6%..

. 69 2%...100 %.

77.5%.

.. l...... 12 UNPLANNED CAPABILITY LOSS FACTOR............1,85%...

. 4 5%..

. 0%.

..' tis %.......... l...,. 13 PLANNED CAPABil ITY LOSS FACTOR..... -....... 8 55%..

. 26 3%.

.0%.

. 0%..

... l...... 14 i

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QEERATIONS (cont'd)

CAGE enust nv

.open CECD UPPt n 1%

QQM, TH!t u'WTH L Asf M7HH jfjlNQ EUEL RCLIABILITY INDICATOR (m' ocuriWgram)

...NA.

. 7.5 10 4.. 8.1s104.. 7 76:10-4....NMA....15 a

DAILY THERMAL OUTPUT (MM.h)...

.... N A

.1495.

NA.

m NA..

.. N A.... 19 EQUIPMENT FORCED OUTAGES PER 1,000 CRITIC AL HOURS................................ NA.... 0 2.... 1.15....

1.4....... NMA.... 20 OPERATIONS AND MA!NTENANCE BUDGET.

,... N A,.

-. N A.

. N A..

... N A.,

.. N A..... 21 DOCUMENT REVIEW....

.....NA.

..NA.

. N A,.

., N A..

.. N A..... 22 MAINTENANCE EAGE yousint

.ctco, ccca opetnin cou, inis una ust enn Trine EMERGENCY DIESEL GENERATOR UNIT RE LIABilliY......................

.. N A..

.. N A...

.. N A..... 23 DIESEL GENERATOR RELIABILITY (25 DE M AN D S)...........................

........ N A.

. <4.

.. N A..

.... N A..... 24 DIESEL GENERATOR UNAVAILABILITY (cumutam tro ) NA..

... <210 8/DG.... NA..

.. NA.,.

.. N A..... 25 AGE OF OUTSTANDING MAINTENANCE WORK ORDERS (CORRECTIVE NONCUTAGE)......NA..

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

.. N A..

. H A..... 26 MAINTENANCE WORK ORDER BREAKDOWN (CORRECTIVE NON OUTAGE)....... N A....-.... N A -

.. N A...

.. NA....... l..... 27 CORRECTIVE MAINTENANCE BACKLOG GREATER THAN 3 MONTHS OLD (NONOUT AGE)..............

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

.. NA.... 67 9%..

. 63.9%..

.. D...... 20 RATIO OF PREVEN 1lVE TO TOTAL MAIN TE N AN C E................................................ N A........., 65%.... 60 0%... 50.6%......NMA... 29 PREVENTIVE MAINTENANCE IT E M S OVE RD U E..........................

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

0 5%.... 0%..

. 0.38%.

... l..... 30 NUMBER OF CONTROL ROOM EQUIPME NT DE FICIENCIES........................,......NA.

. 60..

.47.

,,12..

.. N A.... 31 MAINTE N ANCE OVE RTIME.............................=.. NA..

.10%.

. 8.9%... 8 6%...,... D..... 32 PROCEDURAL NONCOMPLIANCE INCIDENT S (MAINTENANCE).........,.......

...... N A..

.,NA,

..0.

.. 0.

... l....... 33 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES -

(ELECTRICAL MAINTENANCE)......................... N A.,..... 80%..... N A...

.. N A.,,

.. N A.... 34 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (PRE SSURE EQUIPME NT)................................. N A..

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

.. N A.......-.. N A..... 35 W

m.. _ -. -.

m-m._

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

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MAINTENANCE (cont'd))

IMGL 1

i musiny

,gcca, geta over n m.

gaat ties wwry utt uontH HD12 f

PERCENT OF COMPLETED SCHELULED MAINTENANCE ACTIVITIES (GENERAL MAINT ENANCE).....

..o....... N A..

.._ 80%....-.... N A...

. NA..

._. N A.... 36 I

PERCENT OF COMPLETED SCHEDULED

[

MAINTENANCE ACTIVlilES i

(MECHANICAL MAINTE N ANCE)..............~.....-........ N A........, 80%.,... NA...-. NA..

.. NA.... 37 PERCENT OF COMPLETED SCHEDULED

.t MAINTENANCE ACTIVITIES i

(INSTRUMENTATION & CONTROL)......................NA..

. 80%...

..NA.....

.. NA...

.. NA... 38 NUMBER OF MISSED SURVEILLANCE i

TESTS RESULTING IN LICENSEE i

E VE N T R E POR T S............................................. N A...... 0........ 0 ;........... 0.

...L...,39 COMPONENT FAILURE ANALYSIS i

RE PORT (CF AR) S U M MARY...................,........ -.. N A......... N A..... N A........... N A.......... D.... 40 t

NUMBER OF NPRDS M U LT IP LE FAllU RE S................................................. N A..

... N A..

..NA...... nam....... N A.... 41

+

MAINTENANCE EFFECTIVENESS.......................NA..

.. N A....... N A........... N A......... NA....... 42 CHECK VALVE FAILURE MM......................... NA... 2,00E-6.. 6.16E.7.

. 617E.7. <... l........ 43 I

?

CHEMISTRY AND RADIOLOGICAL PROTECTION PAGE

.1 umnm ca&L nus uowin utiwwtH Inugg

-. COLLECTIVE RADIATION.

EXPOSURE (pernon tem).................................115 6fYR... 2%YR... 2512....

245 3.... NMA.....16 VOLUME OF LOW-LEVEL SOLID RADIOACTIVE WASTE..~.............................. 2.077.EYR. 3,000/YR..1.938 8...

J 1,306 4..... N A.....17 SECONDARY SYSTEM CHEMISTRY...................0.20...,. 0.45..;.0.468..,,... 0.515,.... NMA -... 44 :

?

PRIMARY SYSTEM CHEMISTRY -

P E RC ENT OF HOUR S OUT OF LIMIT '...................... NA...... 2%.......,0%.,......1.18% '...-...... l......... 45.

AUXILIARY SYSTEM (CCW) CHEMISTRY PERCENT

- OF HOURS OUTSIDE STATION LIMITS.................. NA..-....-. NA...... 0%........,,0%....... N A....... 4 6 IN LINE CHEMISTRY INSTRUMENTS -

OUT.0F.SE RVICE......................,;...., NA........ 6

.... 17...._.. 20...... NMA.... 47:

H AZARDOUS WASTE PRODUCED......................... N A.......... NA..-...

0..

0,......... N A....... 4 8 -

" MAXIMUM INDIVIDUAL L.

RADIATION EXPOSURE (mrem)....

c.NA i..s.1.50WYR ;. 1,763..

.. 1.752..

.....NMA..... 49

- TOTAL SKIN AND CLOTHING CONTAMINATIONS

.NA.... 4.,144.... 264..

.. 257.....NMA.. ;50

-V

l CHEMISTRY.Atm RADIOLOGICAL PROTECTION (cont'd)

EAGE, f

_IN mtinY QECD.

DEED Urrtn in ggaL T#etinnH 1*;1)Lw H Ig,1c l

DECONTAMINATED RADIATION CONTROLLED AREA.

..... N A.,

88%.. 88 2L

..BB?%.

. N A.... 51 RADIOLOGICAL WORK PRACTICES PROGRAM.

.... N A.

.. HA.

.3.

.5..

.. l........ 5 2 NUMBER OF HOT SPOTS....

.... NA.romove 1/mo... 67..

.67.

.. N A....... 53 GASEOUS RADOACTIVE WA3TE BEING DISCHARGED TO THE ENVIRONMENT (curies)........NA.

34&yr....140 7..

..140.7.... N A....... 54 i

i LOUlD RADDACTIVE WASTE DEING DISCHARGED TO THE ENVIRONMENT (curies)....NA.

. 229yr... 39 6..

..39 5..

. NA..... 55 SECURITY PAGE veutinY DECD QrED Urer n th QQal tinslA>ma uttinm4 Inne LOGGADLE/ REPORTABLE INCIDENTS (SECURITY)..................

...... N A..

.. NA... 43.

. 23..

... D..... 56 SECURITY NON. SYSTEM FAILURES.....................NA....

NA...

.. N A..

.... N A.,

.. N A...... 57 SECURITY SYSTEM FAILURES.....................NA.

N A.,... N A..

.. N A..

.. N A.... 58

.~.

MATERIALS AND OUTSIDE SERVICES EAGE unutinv QEED QfED over n in gogg, tins wwmi utt wwity Inwg AMOUNT OF WORK ON HOLD AWAITING PARTS (NON.OUT AGE)........................ NA.

. 3 5%... 1 91 L..

..2.34%.

.. l...... 59 SPARE PARTS INVENTORY VALUE ($ milhon).........NA.

.. N A..

,.12 96.

.12.7.

.. N A...... 60 SPARE PARTS ISSUED ($ thousands).................,-..NA

.. N A.... 446 4.

..123 9.....,. NA...... 60 INVENTORY ACCURACY...........

..... N A..

.98%...,.99%..

..95 3%.

.l.

61 S TOC KOUT RATE...................................... N A,

.26%

. 0%.

..0.30%.

,,-. l.,.... 61 EXPEDITE D PURCH ASES,.............................NA.

. 0 5%.... 0%.

..0 45 %.... l..... 62 INVOICE BREAKDOWN..................,,

... NA..

.. NA ;.

., N A..

.. N A.

.._ NA.

..63 MATE RI AL REQUEST PLANNING............................NA..

.. N A.

. 32 4%...

..45.7%.

... l.... 63 QESIGN ENGINEERINCa EAGE itounat Qeco OceQ upprn sa goat, mtt wann utT w*nn intno OUTSTANDING MODIFICATONS.......................... NA..

.. N A...... 146..

.148.

.. l...... 64 vi T

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t DESIGN ENGINEERING (cont'd)

PAGE j

rausint QEED QEED over n m.

goat in!t Lov u uti ottu Inuo TEMPORARY MODIFICATIONS (EXCLUDING SCAFFOLDING).....

.. NA.

. 0..

. 21.

..NA.

.65 ENGINEERING ASSISTANCE I

REQUE ST (E AR) DRE AKDOWN.......................... N A...

.. N A... -. 163,... 133..

... A...... 6 6 ENGINEERING CHANGE NOTICE STATUS.,..... N A..

.NA.

.162.

.162..

..D....,67 ENGINEERING CHANGE NOTICE DREAKDOWN.

....NA

.. N A..

.NA.

.. N A..

,.. N A..68 1MDUSTRfAL SAFETY PAGE te ostnv QEED DEED ornn m agag, ints LennH LAST WHu 1 PDC DIS ABLING ifLIURY/lLLNESS FREQUENCY RATE.. 012..

. 0 3.... 1.23..... t.12.

..NMA..18 RECORDABLE INJURY /llt. NESS CASES FREQUENCY RAT E.......... m.......

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

. 2 0...... 3 4 9..... 3 68....... NMA.. 69 HUMAN RESOURCES jMCE umsiny acto orco opern m gg&L Tu's ncy utt LotnH Inng}

NUMBER OF PERSONNEL ERRORS REPORTED IN LER............

.... N A.

.NA.

.0..

.0,

. l....... 70 LER ROOT CAUSE BRE AKDOWN.,..................NA.

.. N A..

.. N A.

.. N A..

.. NA.. 71 STAFFING LEVEL. -.............

...NA

.. N A.,

.. N A.

, N A..

.. N A.. 72 PERSONNEL TURNOVER RATE....................NA..

... N A..

.. N A.

-. N A.,

.. N A.... 72 TRAINING AND OLIALIFICATION PAGE tenusiny DEED QEED een n a goat ints Leum uti Lomi TREND LICENSED OPERATOR REQUALIFICATION TRAINING........................NA.;

.. N A..

.. N A.

.. N A.... _... N A..... 73 LICENSE CANDIDATE EXAMS....

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

. N A..

.. N A..

.. N A...... 74 TOTAL INSTRUCTION HOURS,................

4.

.., N A...

.. N A..

. 1,965..

. 2.024..

. N A...... 75.

TOTAL HOURS OF STUDENT TRAINING...............NA..

,.... N A.,. 8.076.... 8.c41..

NA.,.. 76 vil

OUAllTY ASSURANCE EAGE ltL741111 CitD QPID gr,Im rgy,1, in!s uymi ust uynn. Intun VOLATIONS PER 1,000 lNSPECTON HOURS..........NA

...115 m.

. 2 61.

2.71...

N MA... 77 COMPARISON OF VIOLATONS AMONG REGION IV PLANTS.

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

.. N A.

.. N A

.. N A..

.. N A.... 78 CUMULATIVE VIOLATIONS AND NCVs (TWELVE.MONTli RUNNING TOTAL)................ N A..

.. NA

.1:U2..

. W2..

.. l....... 7 9 OUTSTANDING CORRECTIVE ACTON REPORTS...............

... -..... N A..

.. N A..

. 83.

.. 91.

.. l........ 8 0 OVERDUE AND EXTENDED CORRECTIVE ACTlON REPORTS..

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

. NA..

.S6..

.. O'9....

.. D...... 81 CARS ISSUED vs, SIGNIF. CARS vs.

NRC VOLATONS ISSUED vs.

L E R s R E POR TE D....................................... N A..

.. N A..

.. N A.

... N A..

.. NA... 82 REFUEt ING OUTAGE enisiny gggg grra umna gag suts ummt ant uvny inun MWO PLANNING STATUS..

...... N A...

.. NA..

.. N A.

.... N A..... 83 OVERALL PROJECT STATUS...................... N A.... -.... N A..

.. NA

.. N A....... NA...... 84 PROGRESS OF CYCLE 1% OUTAGE MODIFICATlON PLANNING.............................. NA..

.. N A...

.. NA.

.. N A..

..NA..,.85 PERFORMANCE INDl0ATOR DEFINITONS....................

............................86 S AFETY E N H AN CE MENT PROGRAM lNDEX...................................................... _............. 94 RE PORT DIST R I D U T ON LIS T.........................................................................,....-......... 9 6 TABLE OF CONTENTS

SUMMARY

TREND SYMBOLS A. ADVERSE TREND 1 IMPROVED PERFORMANCE D - DECLl:41NG PERFORMANCE

- NMA - NEEDS MAN AGEMENT ATTENTON NA - NOT APPLICABLE /AVAILABLE vill s

50 O N:t Generation (10,000 Mw hours) 40-35 os 36 17 3595 t 30~

Cycle 14 tue t'

3 20-Refueling o

I I

I......

I..

i i

Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 STATION NET GENERATION During the month of October 1992 a not total of 359,495.9 MWH was generated by the Fort Calhoun Station. There were no power reductions or unplanned energy losses in October.

Unplanned energy losses for the month of September were attributable to the forced outage which began on 8/22/92 when an AC/DC converter failed in the Turbine Electro Hydraulic Control system. Pressurizer safety valve 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 losses during August were the result of the forced outage on 8/22/92 (described above) and the forced outage that began on 8/5/92 when a feeder breaker to the 125V DC panel Al 41 A failed resulting in a controlled shutdown to Mode 2. The turbine generator was synchronized to the grid on 8/6/92.

Unpianned energy losses forthe 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 June 1992 unplanned energy losses were a result of a forced outage that occurred on 6/1/92 due to a dropped control rod. The plant was returned to 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 turbine generator tripped on a falso high level moisture separator trip signal which caused a simultaneous reactor trip.

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

Unplanned energy losses for May were: 1) the Cycle 14 Refueling Outage extension; 2)-

the reduction to 58% power for repair of an inoperable condenser valve: 3) the reactor trip; 4) the hold at 48% power for repair on a feedwater pump suction valve; and 5) the 5/31 dropped control rod caused by a faulty clutch coil.

Data Source: Station Generation Report Accountability: Patterson Positive Trond

Forced Outtg3 Rito lGOODI

--O - 1991 & 1992 Fori Calhoun Goals

+

-O-1991 Industry Upper io Porcentile (0.25%)

2'f4 -

15%-

J U;.3 8

=

-c

=

'89 '90 '91 Nov91 Doc Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 FORCED OUTAGE RATE The forced outage rate was reported as 10.09% for the twelve months from 11/1/91 to 10/31/92.

There were no forced outage hours during the month of October 1992.

Forced outage hours for September 1992 woro due to the forced outage that began on 8/22/92 when an AC/DC convertor failed in the Turbino Electro Hydraulic Control system. Pressurizer safety valvo RC 142 then opened prior to reaching design pressure and the plant tripped on TW LP. The generator was brought on lino 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 outago hours were due to the forced outage on 8/22/92 (described abovo) and the forced outage on 8/5/92 when the turbine was taken off line to replace a foodor breakor to the 125V DC panot Al 41 A. The turbine generator was synchro-nized to the grid on 8/6/92.

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

3/92. Additionally, RC 142 opened 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 line at 0852 on 6/2/92.

A forced outage occurred on 5/14/92 at 1557 hours0.018 days 0.433 hours 0.00257 weeks 5.924385e-4 months when the turbino generator tripped on a falso high lovel 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.

During the months of September and October 1991 a forced outage occurred when the station battorios woro declared inoperable. The gonorator was taken off line on 9/12/91 and remained off lino until 10/6/91.

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

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

Data Source: Monthly Operations Report & NERC GAD Forms Accountability: Patterson Adverso Trond: None 2

- FCS nz ctor Lct ms P:t 7.000 Hours Cntic;t (Ye r to dit3)

-+-- FCS neactor Scrams Por 7,000 Hours Cntcal (for the last 36 months)

--O-1991 a 1992 Fort cathoun Goals

-tr-1995 INPO Industry Goal 10-

-O-Industry upper 10% (0 6 por 7,000 hours0 days 0 hours 0 weeks 0 months entical over a 36 month time porod) 8-6-

4-2-

x 1

x_

0 --

U U

U

'J r-VyV=y-V, U U

Uy Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug sep Oct92 5-Q Number of FCs neactor Ccrams 2-1 1

1 0 0 0 0 o

o o

o m

o py regg o

88 '89 90 91 Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7,000 HOURS CRITICAL The upper graph shows the number of unplanned automatic reactor scrams per 7,000 hours0 days 0 hours 0 weeks 0 months critical (as defined in INPO's 11/91 publication ' Detailed Descriptions of intomational Nuclear Power Plant Performance Indicators and Other Indicators *) for Fort Calhoun Station. Thio value is calculated by multiplying the total number of scrams in a specified time period 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 4.85 and the value for the last 36 months is 1.08 for the month of October 1992. The lower graph shows the number of unplanned automatic reactor scrams that occurred during each month for the last twelve months.

There were no unplanned automatic reactor scrams during October or September 1992.

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

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

There was one unplanned automatic reactor scram in May 1992. This scram occurred on May 14 at 1557 when the turbine generator tripped on a falso high level moisture separator trip signal which caused a simultaneous reactor trip. The last unplanned automatic reactor scram prior to this occurred on July 2,1986.

The 1992 gcal for unplanned automatic reactor scrams per 7,000 hours0 days 0 hours 0 weeks 0 months critical has been set at zoro. The 1995 INPO industry goalis one unplanned automatic reactor scram por 7,000 hours0 days 0 hours 0 weeks 0 months critical. The industry upper ten percentile value is approximately 0.6 scrams por 7,000 hours0 days 0 hours 0 weeks 0 months critical for the 36 month time period from 7/89 through 6/92.

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

Accountability: Patterson Adverso Trond: None 3.

.A d

4 3-D INPO Safety System Actuations

-O-1992 Fort Calhoun Goal

-G-Industry Upper to Percentile 2-l 1

1-7 j

kh i

3 p

y iA Ak Ni i o 0 i o i a i a r-c i o i $,oic,cicici

'89'90 '91 Jan92 Feb Mar Apr May - Jun Jul Aug Sep Oct Nov Dec92 l

UNPLANNED SAFETY SYSTEM ACTUAYlONS-(INPO DEFINITION)

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

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

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

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

Data Source: Monthly Operations Report & Plant Licensee Event Reports (LERs) l Accountability: Jaworski/Foley/Ronning Adverse Trend: None I

4 Ly

.2.

~

12 Month 14unnino Total Ni1C SSAs

-- O - critical Hours Q

NltC Safety System Actuations (SSAs) 10-1000 000 U-600 y

700 6 --

GOO E

6 19 5

%j J; 4 --

400

=

4

.9 300 2 --

n e

200 o

h h

b O

O i

i

" i

'80 *00 '91 O JDJ FMAMJ ASONDJ FMAM ASO UNPLANNED SAFETY SYSTEM ACTUATIONS-(NRC DEFINITION)

This 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-cludes actuations when major equipment is operated and when the logic systems for these safety systems are challenged.

There were no unplanned safety system actuations during the months of October and September 1992.

An unplanned safety system actuation occuired on August 22,1992 due to the failure of an AC/DC converter in the Turbine Electro Hydraulic Control system. Pressurizer safety valve RC-142 then opersed 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 gen, rator start when an oporator 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 falso high level moisture separator trip signal which caused a simultaneous reactor trip and subsequent anticipatory start signal to both diesel genera-tors.

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

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

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

1 E

1992 Monthly High Pressure Safety injection System Unavailability Valvo

--et-1992 High Prost,ure Safety injecton Systom Unavailability Value Year to Date

- o - 1991 & 1992 Fort Calhoun Goals i

+ 1991 High Pressure Safety injecten System Unavailability Value Year to-Date 1995 INPO Industry Goal (0.02)

- C)--

Industry Upper 10% (0.0012) 0.026 -

0.02 -

A 6

A A-A 6

6 6

6 0.015 -

Cycle 14 Refueling 0.01 -

c.;

Outege C

O O

O O.005 -

C E

5 C

2 O

O 9

Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the High Pressure Safety injection System unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for the report-ing month.

The High Pressure Safety injection System unavailability value for October 1992 was 0.00047. There was 1.05 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months of planned unavailability for surveillance tests during the month. The 1992 year to-date HPSI unavailability value was 0.00125 at the end of October.

There were no (zero) hours of 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 surveillance tests in August.

In July there were no (zero) hours of planned or unplanned unavailability. In June there were 1.G hours 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, f:

The 1992 Fort Calhoun goal for this indicator is 0.008. The 1995 INPO industry goalls 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 So'urce: Jaworski/Schaffor Accountability: Jaworski/Schaffer Adverse Trend: None G

x.-

.__.m

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

3 1992 Monthly Austliary Foodwater System Unavadabihty Value

-M-1992 Austhary Feedwater System Unavailabihty Value Year to-dato

-O-1991 & 1992 Fort Calhoun Goals 1991 Austhary Foodwater System Unavailabihty Value Year to-date

~4-1995 INPO Industry Goal

--C}-

Industry Upper 10% (0.0030) 1 0.025 -

A---A A

A A

l 0.02 -

C Ref li 0 015 -

Outage Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Auxiliary Feedwater System Unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for the reporting month.

The Auxiliary Feedwater System Unavailability Value for October 1992 was 0.014. The 1992 year to-date AFW unavailability value was 0.0078 at the end of October. There was 4.45 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months of planned unavailability for surveillance 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 were 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 planned unavailability for surveillance tests in July.

In June 1992 there were 2.82 hours9.490741e-4 days 0.0228 hours 1.35582e-4 weeks 3.1201e-5 months of planned unavailability for a PM and 7.33 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 goalis 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.

7 Aoverse Trend: None l

t E

1992 Monthly Emef 9ency Ac Power Unavailab!!ity Value j

-at-1932 Emergency Ac Power Unavailability Value Year to Date t

O--

1991 &1992 Fort calhoun Gosis (0.024)

IGOODI t

+ 1991 Emergency Ac Power Unavailability Value Year to Date 0.00- 1995 INPO Industry Goal (0.025) 0.05-

-C)--

Industry Upper 10% (.00$$)

0.04-0.03-D D

D=

D 8~~~*~D3mmD M --D - D-4--4 0.01 -

D C

O O

O W ---C g

y D"

0-

=

x

=

T Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 EMERGENCY AC POWER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Emergency AC Power System unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for the reporting month.

The Emergency AC Power System unavailability value for October 1992 is 0.00. The Emergency AC Power System unavailability value year to date is 0.00135.

There were no (zero) hours of planned or unplanned unavailability for DG 1 or DG 2 in September. There were 2.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months of planned unavailability for DG-1 in August to in-spect 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 retalning 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 starting air solenoid valve.

The 1992 Fort Calhoun goal for this indicator is 0.024. The 1995 INPO industry goalls 0.025 and the industry upper ten percentile value (for the three year period from 7/89

~

through 6/92) is approximately 0.0055.

Data Source: Jaworski/Ronning Accountability: Jaworski/Ronning Adverse Trond: None 8

m

,ww

+

13-Q Monthly Gross Heat Rt

-b Year to Date Gross He late lGOODI-h12-em b

11-i i

i i

m

'89

'90

'91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Doc 92 GROSS HEAT RATE This indicator shows the Gross Heat Rato (GHR) for the reporting month, the year to-dato value, and the year end GHR for the previous 3 years.

The gross heat rato for the Fort Calhoun Station was reported as 10,101 BTU /KWH for the month of October 1992.

The year-to-dato gross heat rate was reported as 10.223 BTU /KWH.

Data Source: Holthaus/ Gray (Manager /Sourco)

Accountability: Patterson/Jaworski Adverso Trends: None 9

O 1992 Monthly Thermal Performanco

-W-1992 Year to Date Average Thermal Performance 4

--O-1992 rort Calhoun Goal (99.3%)

l GOOD l

-A--

1995 INPO Industry Goal (99.5%) Industry Uppor 10% (99 0%)

100 % -

0--G -

-O-

-O O

U -O O

O -- 0-0 0

A a

a A--W-o-N

-o --fL

=

A A

o O

O-o O

O U -o

--C O

99% --

4 Cycle 14 Refueling 3

p Outage

~'

90%-

0 1

1 97% --

j 3

g e

o t

y e

'9 A

4 96%

~(h 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-dato average thermal performance value, the 1992 Fort Calhoun goal, the 1995 INPO industry goal and the approximate industry upper ten percontile value.

The thermal performance value for the reporting month was 99.3% The year.to dato average thermal performance value was 99.5% Thermal power level was maintained low during October due to concerns with control valve No.1 minor fluctuations.

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

Data Source: Jaworski/Popek Accountability: Jaworski/Popek Adverse Trond: An adverse trend is indicated based on four consecutive months of declining performance.

10

[]

Monthly EAF Year to oate Avorago EAF

_ 4 100 % -

[ GOOD]

b 77 80% -

~

$6 6 60%-

Cycle 14 nOfuehng Outage

/

40% -

/

f l

p 20% ~

0%-

i i

'80

'90

'91 Jan02 Feb Mar Apt May Jun Jul Aug Sep Oct Nov osc92 EQUlVALENT AVAILABILITY FACTOR This indicator shows the plant monthly Equivalent Availability Factor (EAF), the year to-date EAF for 1992, and the EAF for the previous 3 years.

The EAF for the month of October was reported as 99.2%. The year to-dato average EAF was reported as 52.9% at the end of October.

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: Patterson Positive Trond 11

Q icd 7 Monthly Unit C:paboity Fcctor

-- M-ion 2 Yc:r to D:t2 Av:r:gs Unit Capcbuity Fcctor

-+- 1991 Year to Date AveraDe Unit Capability Factor 4

I GCCD1

-O-1901 &1992 Fort Calhoun Goals

-A-199,1 INPO Inrtustry Goal (80%)

-C)-

Irdustry Uppor 10% (09.6% for a Throo Year Avocago) 00%-

'0 *

^

E

% [f b

'0%~

Cycle 14 es M

b Nov91 Doc Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 UNIT CAPABILITY FACTOR This ind Pator shows the plant monthly Unit Capability Factor (UCF) value, the 1991 and 1992 year-to c Ito average values and goals, the 1995 INPO industry goal and the approximato industry u spor ten porcentilo valuo. UCF is defined as the ratio of the available onorgy gonora-tion over a given porlod of timo to the reference onorgy generation (the onorgy that could be produced it the unit were operated continuously at full power under reference ambient condi-tions) over the same timo period, expressed as a percentage.

The UCF wa.; reported as 100% for the month of October 1992. The year to dato average unit capability f actor was reported as 53.55%.

The UCF was reported as 77.5% for the month of September 1992. Unplanned energy lossos for the month wore a result of the forced outage that began on 8/22/92 when an AC/DC con-vorter failed in the Turbine Electro Hydraulic Control system. Pressurtzer sa%y valve RC 142 then opened prior to reaching design pressure during a plant transient and trip. The generator was brought on lino at 2101 hours0.0243 days 0.584 hours 0.00347 weeks 7.994305e-4 months on 9/5/92.

The UCF was reported as 62% for the month of August 1992. Unplanned onorgy lossos for the monto were a result of the 8/22/92 forced outa00 (described above) and the forced outage on 8/

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

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

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

The 1995 INPO lndustry goal is 80% and the industry upper ten percontilo value (for the throo year period from 7/89 through 6/92) is approximately 89.6%.

The 1992 Fort Calhoun goal for Unit Capability Factor is S9.2%. The basis for this goal is 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: Generation Totals Report & Monthly Operating Report Accountability: Patterson Positive Trend 12

D 1992 Monthly Unplanned Ceptbility Lot.s Factor

)

+ 1992 Year to-Date Average Unplannsd Capability Loss Factor

+ 1991 Year to Date Average Unptanned Capabmty Loss Factor

--O-1991 & 1992 Fort Calhoun Goals

--h--

1995 INPO Industry Goal (4.5%)

c.

-O-Industry Uppor 1o% (1.85% for a Throo Year Avorage) 60% -

Cycle 14 f

Refuohng Y

40% ~

Outage 20% --

w

~

t o*4 -

--,k O

m

_t 5

.k

^

i io

, - i - i -, -, -, - i -,

i Nov01 Doc Jan Fob Mar Apr May Jun Jul Aug Sep Oct92 UNPLANNED CAPABILITY LOSS FACTOR r

This indicator shows the plant monthly Unplanned Capability Loss Factor (UCLF), the 1991 and 1992 year to-date average values and goals, the 1995 INPO lndustry goal and the approximate industry upper ten percentile value. UCLF is defined as the ratio of the unplanned energy losses during a given period of time, to the reference energy generation (the energy that could be produced if the unit were operated continuously at f sil power under reference ambient condi-tions), expressed as a percentage.

The UCLF was reported as 0% for the month of October 1992. The year to date average monthly UCLF for 1992 is 16,82%

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 Hydraulle Control system. Pressurizer safety valve RC 142 then opened prior to reaching design pressure during a plant transient and trip. The generater was brought on line at 2101 hours0.0243 days 0.584 hours 0.00347 weeks 7.994305e-4 months on 9/5/92.

The UCLF was reported as 62% for the month of August 1992. Unplanned energy losses for the month were a result of the 8/22/92 forced outage (described above) and the forced outage on 8/5/92 when a feeder breaker to the 125V DC panel Al-41 A f ailed. The turbine generator -

was synchronized to the grid on 8/6/92.

The UCLF was repor1ed as 66% for the month 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 Totale Report & Monthly Operating Report.

Accoun. ability: Patterson -

Adverse Trond: None 13-

_.. _. _ __.. _ __ _.,_ u.

Q 1902 Monthly f*42nned Cepubasty Lost I cctor

-et-1E92 Ye2r-to DSID Averepe f*CLF

-4G - 1991 Yest to.D2ts Average l'CLF

[ GOOD]

@ 1991 & 1997 Fort Calhoun Goale

.-C)-

Industry Upper 10% (G 65% for a Three Year Average)

Cyclo 14 Refueling OutaDe

$.$i

^

x

--u w

W], A,

Put n

-.m-e:{Ly R y R y A __-.Fs -- R,

m Nov91 0 00 Jan Feb Mar Apr May Jun Jul AUG Gep Oct92 PLANNED CAPABILITY LOSS FACTOR This indicator shows the plant monthly Planned Capability Loss Factor (PCLF), the PCLF year to-date monthly average, and the Fort Calhoun yearly average goals for 1991 and 1992. PCLF is defined as the ratio of the planned energy losses during a given period of time, to the reference energy generation (the energy that could be pro-duced if the unit were operated continuously at full power under reference ambient conditions), expressed as a percentage.

The PCLF was reported as 0% for the month of October 1992. The year to date aver-age monthly PCLF was reported as 29.63%.

The PCLF was reported as 0% for the month of September 1992. Energy lossoc 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 Hydrsulic 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 for the month were due to the forced outage on 8/22/92 (described above) and the forced outage on 8/5/92 when a feeder breaker to the 125V de panel Al 41 A failed. The tur-bine generator was 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.

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

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

The PCLF industry upper 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: Patterson Adverse Trend: None 14

O Fuel Reliabihty indicator

--6--

1995 INPG Industry Goal (0.5 X 10-3 Microcuries/ Gram) lG00D]

h 5-k

-O-1992 Fort Calhoun Goal p 4_

3" FRINo:

3-8 Cycle 14 Available for g 2-

.Q Outage gg--g

-g Refuelin9 July 92 f.

g Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 FUEL RELIABILITY INDICATOR The Fuel Reliability Indicator (FRI) was reported as 8.10 X 10 4 microcuries/ gram for the month of October 1992. The monthly FRIis a calculated value based on fission product activities present in the eactor coolant. Its purpose is to monitor industry progress in achieving and maintaining high fuelintegrity.

The current INPO FRI value is defined as the steady stato primary coolant lodine 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 be-tween the reactor coolant system and letdown conditions. Tramp activity results from the fissioning of uranium and plutonium from past fuel failures that has plated to Intemal reactor surfaces. The FRl can be expected to increase overy month for the remainder of Cycle 14 since the current INPO FRI calculation does not adequately correct for the presence of tramp plutonium in the core, especially if a significant amount of tramp material is present, as is the case in the Fort Calhoun Station reactor core.

8.10 X 10-4 microcuries/ gram is a favorable FRI value for the Fort Calhoun Station and indicates a defect free core when no Xe-133 activity increases and no iodine 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 October 1992 FRI was calculated using the d 'a from October 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 7.5 X 10 4 microcuries/ gram has been utilized in 1992. This goal has proven to be unattainable for Cycle 14 with the present coolant activity and plutonium levels. INPO will be proposing a new worldwide 1993 FRI calculation. The 1993 goal will be adjusted accordingly to account for the new FRl calculation method and to be more realistic for the coolant activities encountered in a known defect free core at Fort Calhoun Station.

Data Source: Holthaus/Guliani Accountability: Patterson/Spilker Adverse Trend: None 15

O Monthy PersonnelRadiation Exposure t

Personnel Cumulative Radiation Exposure (Person Rem) l

-O-Fort Calhoun AnnualGoal(250 Person Rem) l

-b-1995INPOIndustryGoal(185 Person-Rem) f

-O-Industry Upper 10% (115.6 Person Rom for a Three Year Average) l IG00D]

i 276 k

~

C 0

0 o

o o

o c

%--c o.

L I

200 b

A A

A' 93.4 100-d 52 j

]

, 0_

i

'89

'90

'91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 COLLECTIVE RADIATION EXPOSURE During October 1992,5.891 person rem was recorded by TLDs worn by personnel-while working at the Fort Calhoun Station. This exposure is due to several radwaste resin shipments that were made during the month. The year to date exposure is -

251.233 person rem.

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

inspection.

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

115.6 person rem per year. The three year average for Fort Calhoun Station from 7/89 through 6/92 is 194.3 person rom per year.

Data Source: Patte_rson/ Williams (Manager / Source)

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

=

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

15000-10000-5000-0-

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 3

Radioactive Waste Buried This Month (in cubic feet)

Curnulative Radioactive Waste Buried

-O-Fort Calhoun Goal For Waste Buried (3.000 cubic feet)

- 1995 INPO Industry Goat (3.884 cubic feet)

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

A A

3000-C O

O O

O--C O

O O

O 1334 1500-FJ 0-r 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.

Cumulative amount of solid radwaste shipped off site for processing (cubic feet) 21,600.0 Amount of solid radwaste shipped off site for processing during October (cubic feet) 2,080.0 Volurne of solid radioactive waste which was buried during October (cubic feet) 632.4 Cumulative volume of solid radioactive waste buried in 1992 (cubic feet)

.1,938.8-Amount of solid radioactive waste in temporary storage (cubic feet)..

204.4 The 1992 Fort Calhoun goal for the volume of solid radioactive waste which has been buried is 3,000 cubic feet.. The 1995 INP_O 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: Patterson/Breuer (Manager / Source)

' Accountability: Patterson/Bilau Adverse Trend: None

-: S E P 5 4 17

1992 Disabling injury / Illness Frequency Rate 1

--X-5 Year Average Disabling injuryll!! ness Frequency Rate lGOODI 1.6 -

Y

--6--

1995 INPO Industry Goal (0.5) 1.2 -

1-0.8 -

~

24mM i

i i

v L

i i

u u

a 0.4-C O

O O

O 0.2 -

0-X h

Jan92 Feb Mar Ap.

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

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

The disabling injury / illness frequency rate for January through October 1992 was 1.23.

There was one disabling injury / illness case, a knee injury, reported for the month of October. The total number of lost time accidents that have been reported during 1992 is 6. The 1992 disabling injury / illness frequency rate goal was set at 0.30. The 1995 INPO Industry goalis 0.50.

The disabling injury / illness frequency rate for the past twelve months is 1.22.

The industry upper ten percentile disabling injury / illness frequency rate for the twelve months from 7/89 through 6/92 is approximately 0.12.

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

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

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

i O

Thermal Output

--O-Fon Calhoun 1495 MW Goal Tech Spec 1500 MW Limrt 1500 -

mn ya 1499-l M

1480-I d

$1470-2

'~

1400-l 1450-1 3

5 7

9 11 13 15 17 19 21 23 25 27 29 31 DAILY THERM AL OUTPUT The above thermal output graph displays the daily operating power level during October 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 during October 1992. As a conser-vative approach to this condition, reactor power was allowed to drift below the goal of 1495 Mwth until troubleshooting could begin.

I Data Source: Holthaus/ Gray (Manager / Source)

Accountability: Patterson/Trausch l

Adverse Trend: None l

l l

19 e

1

-.-.,-..-.._,,,,,,......~..,,...-,,,..-..,.,,,,-...-.-.._m..--__.-.m.,,.

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

-.w-

Equipment Forced Outage Rate 2-

--O-1992 Fort Calhoun Goal 1.5 -<

1-0 f.3 0,5 0.5 -

C C

C O

C C

C yg [

'09

'90 91 Jan92 Feb Mar Apr May Jun Jul Aug sep Oct Nov Docs 2 EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS The equipment forced outage rate per 1,000 critical hours was 1.15 for the months from January through October 1992. There were no equipment forced outages during the month.

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 oxurred in August: 1) on 8/5/92 a feeder breaker to the 125V DC panel Al 41 A failed. The turbine generator was synchronized to the grid on 8/6/92; 2) on 8/22/92 an AC/DC converter failed in the Turbine Electro Hydraulic Control system. Pressurizer safety valve RC 142 then opened prior to reach-ing 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: Patterson/ Jaworski Adverse Trend: None 20-

Operations 1992 Budget ($ Million) 80-

--M--

1992 Cumulative Total ($ Million) l'.

40-20-

/

0-Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 Maintenance 1992 Budget (5 MUion) 40-30-

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

w a

10-Jan92 Feb Mar Apr -

May Jun Jul Aug Sep Oct Nov Dec',2 OPERATIONS AND MAINTENANCE BUDGET The Operations and Maintenance Budget Indicator shows the bum mar to-date as well as the actual expenditures for operations and mainianance to crt C&lhoun Station.

The budget year-to-date for Oprations was 57,038,800 dollars for October 1992 while the a%.11 cumulative expenuttures through October totaled 52,150,310 dollars. The 1992 ycar end budget for operations has been revised to 61,420,800 dollars, which is a reduction of 5,240.000 dollars.

The budget year-to-date for Maintenance was 16,761,200 dollars for October 1992 while the actual cumulative expenditures through October totated 14,882,419 dollars.

The 1992 war end budget for maintenance has been revised to 19,088,600 dollars,_-

yhich is an increase of 934,000 dnllars.

Drta Source: Gleason/ Parent (Manager / Source) t Accountability: Scofield Adverse Trend: None 21

. ~. - ~.

.. ~.

<7 V

G O. Documents Scheduled for Review-'

y w

g,,

@ 1 Documents Reviewed

< 700 -

Q - Overdue Documents d

600 -

n t

500 -

[

400 -

I 300-lf l

200 -

~

g 6

100 -

7

_]

g g

e 0

i.

Nov91 Dec Jan-Feb Mar Apr May.

Jun_. Jul Aug Sep LOct92 L '

DOCUMENT REVIEW.

. This indicator shows the number of completed, scheduled, and overdue (greater than 6 R-months past the scheduled due date) biennlaheviews for the reporting mnnth. These document reviews are performed in-house and include Special Procedures, the Site L a

e Security Plan, Maintenance Procedures, Preventive Maintenance Procedures, and the.

- Operating Manual.

During October 1992 there were 187 document reviews completed whl!r 70 document reviews were scheduled. At the end of October, there were no documei..aviews

' overdue, in addition, during the month of October there were 21 new or renamed' documents

~

1 reviewed. These new c' renamed documents will need to be reviewed again ing1994.

-,4 Data Source: Patterson/McKay (Manager / Source)

I Accountability: Patterson/Jaworski i

Piitive Trend.

SEP 46 l

22 V

Number of Failures /20 Domands

-m-Trigger Values for 20 Demands O

Nvmber of Failures /So Demands

-Y-Trigger Values for So Domands O

Number of Failures /100 Domands Tngger Values for 100 Demands e-l GOOD l 6-V V

V V

V 7

Y Y

y y

4 4

4-5 m

g 9

9

= $

=

22 h 1

l

}

22 C 2

2 )

2 7 ;

j

- j y

j y

y 2-l j

1 j

1 l

1 1

1 1 l 1

l 1 j 1

j n

4 s

- i 3

of a

g j

o a

o t o 9

o l

i i

s o

L o

q o a

g I

I I

i i

1 i

Nov91 Doc Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 l

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 omergency diesel generator demands at the Fort Calhoun Station. Also shown are trigger values which correspond to a high level of confidence that a unit's diesel generators have obtained a reliability of greater than or equal to 95% when the failure values are below the corresponding trigger val-ues. T ie Fort Calhoun 1992 goal is to have fewer failures than these trigger values; The demands counted for this indicator include the respective number of starts and the respective number of load runs for both Diesel Generators combined. The number of start demands includes all valid and inadvertent starts, includinD.all start only demands l'

and all start demands that are followed by load-run demands, whethe; by 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 L

- 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).

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

Data Source: Jaworski/Ronning (Manager / Source)

Accountabliity: Jaworski/Ronning-Adverse Trend: None g

O DG 1 Failures /25 Demands 1GOODl-E DG-2 Failures /25 Demands V--

5-

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

O O

3-2 2

2 1

1 1

0 0-0 0

0.

0 I

i i

i Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep _ Oct92 DIESEL GENERATOR RELIABILITY (25 DEMANDS)

This indicator shows the number of failures experienced by each emergency diesel generator during the last 25 start demands and the last 25 load-run demands. A trigger value of 4 failures within the last 25 demands is also shown. This trigger value of 4 failures within 25 demands is the Fort Calhoun goal for 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 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: Nnne 24

O Planned Hours of Diesel Generator No. 2 Unavailability

@ Unplanned Hours of Diesel Generator No. 2 Unavailab!Lty 50-

@ Estimated Hours of Diesel Generator No. 2 Unavailability

. 40-M Planned Hours of Diesel Generator No.1 Unavailability 530-0 Unplanned Hours of Diesel Generator No.1 Unavailability 3

Estimated Hours of Diesel Generator No.1 Unavailability 20-m

$10-I, W

O i

Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 20-

-+-- Cumulative Hours of DG-1 Unavailability for 1992 El l

j15-

+ Cumulative Hours of DG-2 Unavailability for 1992 l

2

'U~

g t-5-

e 0

?

i i

i Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct92 DIESEL GENERATOR UNAVAILABILITY This indicator provides a monthly illustration of diesel generator unavailability. The top graph shows the diesel generator planned, unplanned, and estimated unavailable hours for DG-1 and DG-2 for each month. The lower graph shows the cumulative hours of unavailability for each diesel generator for the year-to-date.

During October 1992 there were 0.00 hours0 days 0 hours 0 weeks 0 months of planned or unplanned unavailability for DG 1 and DG-2.

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

Data Source: Jaworski/Ronning (Manager / Source)

Accountability: Jaworski/Ronning Adverse Trend: None l

l l

25 l

[

g.

1 July 1992 Outstanding MWOs

~

. O August 1992 Outstanding MWOs O septomber 1992 Outstanding MWOs 300 -

'O - October 1992 Outstanding MWOs 200 -

l h_

100-7 oc w

' h

.k 0

0 3 Months 3-6 Months 6-9 Months 12 Months -

>12 Months -

AGE OF OUTSTANDING MAINTENANCE WORK ORDERS (CORRECTIVE NON-OUTAGE)

This indicator shows the age of corrective non-outage maintenance work orders.-

(MWOs) remaining open at the end of the reporting month, s

Data Source: Patterson/Schmitz (Manager /Sourec)

Accountability: Patterson/ Bobba

- Adverse Trend: None I-i 26' f

b n

~

9

' July 1992

- 0 August 1992 00 O September 1992-376

'350 -

O Mober1992

- 300 -

258

'264 250 -

W 222

$ 215 M ]

200-

/

165

$g_

jsj E

146

~

a q1 113 110 9

s:

/.

100 -

1 f

64 60 55 42 42 50-

?~

7

-30 z ;

aM//

g 20 17 16 Q

A-M h!L !//

Why p t

m -

,w, a.

TotalOpen MW0s Open MWOs>3 : Total Open Safety - ' Open Safety __

Open High Priority; neths old Related MWOs-Related MW0s > 3

' MW0s Months Old '

MAINTENANCE WORK ORDER BREAKDOWN (CORRECTIVE NON-OUTAGE)--

This indicator shows the total number of corrective non outage MWOs_ remaining open =

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

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

Data Source: Patterson/Schmitz (Manager / Source)

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

1 w

w w

+=w

=

y,,--

e t

r t

O Corrective Maintenance Backlog > 3 Months Oki lGOODI 80%-

4 Cycle 14 Refueling g,

Oubge 60% _

?$

y;:

g w

40%-

8

,(

i I

F

'S

+.

S q

20%-

ty j l 0

1 n.

h h

I a 0%

'Sj-

"j

.4 i

j Nov91 Dec Jan Feb

' Mar Apr May Jun Jul Aug Sep Oct92

Programmatic change to reflect change in non outago criteria.

CORRECTIVE MAINTENANCE BACKLOG GREATER THAN 3 MONTHS OLD (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 October 1992 was reported as 67.91%.

Data Source: Panerson/Schmitz (Manager / Source)

Accountability: Patterson/ Bobba Adverse Trend: None SEP 36 28

C Ratio of Preventive to Total Maintenance

_ --O-1991 & 1992 Fort Calhoun NonOutage Goals' k

Cycle 14 l GOOD l -

Refueling 1

- ~

Outage 80% -.

74 w

v

!!l 5

' fl!

h 70%-

E6 C

O O

O-f 65-C

[. jj

{4 fj;

(( l 51 %

%l T@

p$wp e

50%- T 59

~

Ms 2

Ba fy}

W

?%

a hh u

m 1.

3 h

T 40%-

g$,

$$h... @

Q h'

ph e-

-, J 9e 4 s d

'S

l ed i

j p

LJ Nov91 -Dec Jan.

Feb Mar Apr May Jun Jul Aug Sep Oct92 RATIO 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 60% in October 1992, The 1992 Fort Calhoun goalis to_ attain a ratio of preventive to total maintenance non-outage greater than 65%. The 1991 Fort Calhoun goal was to attain a ratio of preven -

tive to total maintenance greater than 60%.

Accountability: Patterson/ Bobba Data Source: Patterson/Schmitz_ (Manager / Source)

Adverse Trend: None SEP 41 s

k m

4%-

E Preventive Maintenance items Overdue l GOOD l

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

2%-

Cyde 14 Refueling 1%-

Outage O

O O

m

M;M; N 0.,,

i i

o Nov91 Dec Jan Feb Mar Apr May Jun-Jul Aug Sep Oct92 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 October 1992,610 PM items were completed._ None (0%) of these PM ltems were not completed within the allowable grace period.

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

maintenance items overdue. The 1991 Fort Calhoun goal was to have less than 1% per month of the preventive maintenance items overdue.

Data Source: Patterson/Brady (Manager / Source)

Accountability: Patterson/ Bobba Adverse Trend: None SEP 41 1

-30 j

i m.

Control Room Equipnient Deficiencies Repairablo On Line 70-O Total Number of Control Room Equipment Deficiencies

--O-1991 Fort Calhoun Goal For Total Out-of Service instruments 60-

--O-1992 Fort Calhoun Goal For Total Equipment Deficiencies so-C C

C C

40-30-

"~~~

20-6:

10-o I

I I

I e

i i

1 4

i Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 NUMBER 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 1991 and 1992 Fort Calhoun goals.

There was a total of 47 control room equipment deficiencies at the end of October 1992.

16 of these deficiencies require a plant outage to repair. 4 deficiencies were added and 6 were corrected during the month.

The revised 1992 Fort Calhoun goalis to have a maximum of 50 control room equip-ment deficiencies. The 1991 Fort Calhoun goal was to have a maximum of 14 out of-service control room instruments.

Data Source: Patterson/Spilker (Manager / Source)

Accountability: Patterson/ Bobba Adverse Trend: None. Although the number of control room equipment deficiencies has increased for four consecutive months, an adverse trend is nol indicated because the criteria for defining out-of-service control room instruments changed in September 1992. This change was necessary because INPO no longer tracks this item due to difficulty in establishing consistency among plants reporting this indicator.

31 1

1

Maintenance Overtirne 2

80%-'

I GOODI

--X- - 12 Month Average Maintenance Overtime 4'

70%-

- O - 1991 & 1992 Fort Calhoun'On-Line Goals 60%-

Cycle 14 50%-

Refueling Outage -

40%-

p ly, y

g lh

@j.

30%-

[$

C

?

0

$e y

n T

C 20%-

f d{

14 d-M X

X_

h K

g f

A O-O O ---A

.Q.

10%-

a S

O kg

@iL p$

k hf f$

k,jg m

k

~

w y

g w

s w

m v

0%

Nov91 Dec Jan Feb Mar Apr -

May Jun-

=Jul

Aug - Sep : Oct92.

MAINTENANCE OVERTIME -

i The Maintenance Overtime Indicator monitors the ability to perform the desired mainte-nance activities with the allotted resources. Excessive' overtime indicates insufficient resource allocation and can lead to errors due to f atigue.

The percent of overtime hours with respect to normal hours was reported as 8.93% -

during the month of October 1992. The 12 mo_ nth average percentage of overtime j

hours with respect to normal hours was reported as-18.65W 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: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/ Bobba -

~

Adverse Trend: None

- 32 s

w,

w

~ - -.

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

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

1 O Procedural Noncompliance irs (Maintenance) i Cycle 14 Refueling 10-9 9

~

a W

5 e

l 4

4 3-3 1

I 8 7 1]

2 s /

2 I

h 1

1 1

1

/

11 1

1-1

,t y

0 I 30 0$0 Ok,~00 k])

0 0 :0 30

~

O 00 00 Nov91 Dec - -Jan Feb Mar Apr May Jun

> Jul

.Aug '. Sep ' Oct92 PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)

This indicator shows the number of open Maintenance incident Repor prs) that are related to the use of procedures;the number of closed irs that are re~iiad 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 October 1992.

Data Source: Patterson/McKay (Manager / Source)

' Accountability: Patterson/Bobba

. Adverse Trend: None

- SEP 15,'41 & 44 ~

u 33

~

4 4

O Completed Scheduled Activities (EM) j i

O Fort Calhoun Goal i

100 % -

7 2

3 0 0"'* ~

O M

7 z

y a

70% -

[

61 )

k Y

l N

60%-

.h fl k

?

h h

h f

Q 50% -

4 f

h h

[

b 40% -

k k

h 30% -

M[

p 9

j

+D p

m i

L ij l $

O 20%-

h i

n f.

x a

}

l 10% -

s u

8/1 8/8 8/15 8/22 8/29 9/5 9/12 9/19 9/26 10/3 10/10 10/17 10/24 10/31*

' Revised 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%.

Reponino Month Comoleted Scheduled Activities Week 1 92 %

Week 2 92 %

Week 3 95%

Week 4 96%

Week 5 65%*

Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/Bobba Adverse Trend: None SEP 33 34

O Completed Scheduled Activities (PE)

--O-Fort Calhoun Goal 100% -

90%-

U 5

E A

Q-Q-O -O-- g g

-.- Y

-o 80%-

i w

n eg e

Ps

$p

)i f,

[d)3)4 70%-

f r

60%-

g w

(g yf 50%-

jy 3d

]

J l

l

(#

m g

Tj l

fj L

g L

l hl 3o%-

i 20%-

h h

l 10% -

{hj l

??

$1

~

0%

8/1 8/8 8/15 8/22 8/29 9/5 9/12 9/19 9/26 10/3 10/10 10/17 10/24 10/31' l

Revised Method of Calculating Completion %

PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (PRESSURE EQUIPMENT)

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

The Fort Calhoun Station goal for this indicator is 80%

Reoortina Month Comoteted Scheduled Activities Week 1 87 %

Week 2 86 %

Week 3 81 %

Week 4 87 %

Week 5 63%*

Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/Bobba l

Adverse Trend: None SEP 33 l

-35

?>

m l

il E

Completed Scheduled Activities (GM)-'

y

-O-Fort Calhoun Goal

]

1 90 0 80 0 C

70 0 60U SOU 40 0 30 0 20 %

10U 0%

811 8/8 8/15 8/22 8/29 9/5 9/12 9/19 ' 9/26 ~ 10/3 -10/10 -10/17-10/24 10/31* ( _

4

Revised Method of Calculating Completion %

PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES

=

(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-d tenance.- Maintenance activities include MWRs, MWOs, STs, PMOs, calibrations, and -

miscellaneous maintenance activities.

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

Begortina Month-Comoteted Scheduled Activities -

Week 1 84 %

Week 2 86 %

Week 3 95%

Week 4 98%

Week 5 79%*

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

- Accountability: Patterson/Bobba.

4 Adverse Trend: None SEP 33 l

36-4,,4 y--e m--3,

--e

O completed Scheduled Activities (MM) i

--O-Fort Calhoun Goat 100*/. -

w 7

]+

g. ; j 7,

90%-

i Q

--O 80%-

Q C

ff Y

]

f 70%-

60%-

.L k

t

@W 4

F 50% -

Yk f

f p

40% --

30%-

D(

h9 e

20%-

h l

10% -

0%

=

8/1 8/8 8/15 8/22 8/29 9/5 9/12 9/19 9/26 10/3 10/10 10/17 10/24 10/31'

' Revised Method of Calculating Completbn %

PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (MECHANICAL MAINTENANCE)

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

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

Reoortino Month Comoteted Scheduled Activities Week 1 90 %

Week 2 95%

Week 3 92 %

Week 4 93%

Week 5 61 %*

Data Source: Patterson/Schmitz (Manager / Source)

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

D Completed Schoduted Activities (IC)

--O-Fort Calhoun Goal 7

I T

T'

}

mw 3

90%-

pt 5

y c;

x e

a w

F g

s w

a LL

(- C - Q' d

C - 6 Q

4

% --O 80% -

O l::

y M

4 h

t-W p

Q 70% -

p j

k cll y$

[f i

(

5 M

$l 3

60% -

[,

9 Pd fb

).

b.

6 1

50% -

Q 40%-

M M

l {

C f

N k

l

\\

N Il

$ k@

i

(

p} f h

Y f

3 '* ~

h W

20% -

W D

k

?

($

$l) M h

l 4

10%-

1.5 k

1 l,l f

b h

9 3

0%,-

8/1 8/8 8/* 3 8/22 8/29 9/5 9/12 9/19 9/26 10/3 10/10 10/17 10/24 10/31'

' Revised Method of Calculating Completion %

PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (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%.

Reoortino Month Comoteted Scheduled Activities Week 1 93%

Week 2 95%

Wesk 3 93%

Week 4 96 %

Week 5 62%*

Data Source: Patterson/Schmitz (Manager / Source)

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

3-l D Number of Missed STs Resulting in LERs 2-1-

0 0

i i

i

'90

'91 Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 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 Repcrts (LERs) during the reporting month. The graph on the left shows the yearly totals for the indicated years.

~

During the month of October 1992 there were no missed STs that resulted in LERs.

The 1991 & 1992 Fort Calhoun goals for this indicator are zero.

Data Source: Monthly Operating Report & Plant Licensse Event Reporte (LERs)

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

.- # of Component categories 40-

- +-- # of Apphcation categories 35-

--A - Total # of categories g 30-25-

)'

A g

pg y 20-

~

?

N hA

- 10 - =

=

5 9=

=

0 M91 J J

A s

O N

D J92 F

M A

M J

J A

s 092 3 WearOut/Agirg Q Other Devices Q Manufactunng Defect O uaintenancerrosting s6.0%

O Engineenng' Design O Error Percent of Total Fallures During the Past 18 Months 9,o.,,

/,/

6.0%

16 M 11.0.D3 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) failure rates than the industry failure rates during the past 18 months (from May 1991 through October 1992). Fort Calhoun Station reported a higher failure rate in 13 of the 87 component categories (valves, pumps, motors., etc.) during _

the past 18 months. The station reported a higher failure rate in 13 of the 140 applica-tion categories (main steam stop valves, auxiliary / emergency feedwater pumps, control _

-i element drive motors, etc.) during the past 18 months.

The pie chart depicts the breakdown by INPO cause categories (see the " Definitions" section of this report for descriptions of these categories) for the 181 failure reports that were submitted to INPO by Fort Calhoun Station during the past 18 months.

Data Source: Jaworski/ Dowdy (Manager / Source)

Accountability: Jaworski/ Dowdy l

Adverse Trend: None 40

--G--

Greater Than One Failure 40-

--+-- Greater Than Two Failures 35-30-25-

~

20-15-10-c c

c v

v 5-

'l o

Nov91 Doc Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 NUMBER OF NPRDS MULTIPLE FAILURES This indicator shows the number of multiple NPRDS reportable failures over the preced-ing eighteen months sorted by component manufacturer and model number. The Indica-tor is divided into three parts: manufacturer model numbers with more than one failure in eighteen months, manufacturer model numbers with more than two failures in eigh-teen months, and manufacturer model numbers with more than five failures in eighteen months.

During the past eighteen months, there were 32 model types that had more than one failure in eighteen months.13 of these had more than two failures. 4 component types:

General Electric 50-570 01 power supplies, Gaulin P18 pumps, Byron Jackson 28RXL -

pumps and Jayco incorporated 150 valves had more than five failures. The model types with more than two failures are: Electromotive Diesel Generator Motor (3 failures), the OSPDS (3 failures), S-P Manufacturing DA3R valve operators (3 Failures), General' Electric 50-570 power supplies (4 failures), General Electric 50-570-01 power supplies L

(8 failures), Faulk Type Y couplings (3 failures), Byron Jackson 28 RXL pumps (7 fail-

. ures), Gaulin P18 pumps (7 failures), Dresser 1975C valves (3 failurest Jayco incorpo-rated 150 valves (6 failures), Norgren 11-024 0 valves'(3 failures), Copes-Vulcan D-

-100-60 valves (3 failures) and Fisher Controls 657-60 valve operators (3 failures).

L

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

Data Source: Jaworski/ Dowdy (Manager / Source)

Accountability: Jaworski/ Dowdy Adverse Trend: None 41

--+-- Components With More Than One Failure l GOOD l t

X Components With More Than Two Failures 20-15-10-5-

o u

1^

X X

)

0 Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 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 (NPRDS) component failures.

This indicator has been revised to show the number of NPRDS ccmponents with more than one ti.ilure during the last eighteen mon'.hs and the number of NPRDS compo-nents with more than two failures during the last eighteen months. The number of NPRDS components with more than two f ailures in an eighteen month period should indicate the effectiveness of plant maintenance.

During the last 18 reporting montns there were 17 NPRDS components with more than 1 failure. 3 of the 17 had more than two failures. The tag numbers of the components with more than two failures are CH-1 A, CH 1B and EE-1G.

Data Source: Jaworski/ Dowdy (Manager / Source)

Accountability: Patterson/Bobba Adverse Trend: None 42

=_.

10-

- Calcutated Check Valve Failure Rata per Million Component Hours 9-

~ -

Industry Check Valve Failure Rate per Million Component Hours 8-

-O-Fort Calhoun Goal 7-l GOOD l 6-y eg 5-4-

3-g 3

_g___ + __g a

2-C C

C C

O--C C

C C

C 1

1 1-l-

0 L

'89 '90 '91 Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 Check Valve Failures CHECK VALVE FAILURE RATE This indicator shows the calculated Fort 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 check valve failures at Fort Calhoun Station for the -

previous three years are shown on the left.

L 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 July 1992, the Fort Calhoun Station reported an actual check valve failure rate of 6.19 E-7, while the industry reported an actual failure rate of 2.44 E-6. At the end of a

October 1992, the Fort Calhoun Station reported a calculated check valve failure rate of 6.19 E-7.

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 L

Adverse Trend: None SEP 43 L

43 N

-a

E Secondary System CPI

-O--

Fort Calhoun Goal (.45)

-e-1995 INPO Industy Goat (0.30).

1.5 -

l Secondary System CPI Limit

-C}--

Industry Upper 10% (0.20) 1-l l

l l

Cycle 14 Refueling -

0.5 Outage Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 5%-

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

Cycle 14 Refueling Outage 0%

Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 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 operation.-

The CPI was reported as 0.468 for the month of October 1992. The percent of hours-outside the OG guidelines was reported as 0% for the month of October 1992.

The 1991 & 1992 Fort Calhoun goals for the CPI are 0.45. The INPO 1995 Industry goalis 0.30. The industry upper ten percentile value for this indicator was approxi-mately 0.20 for the twelve months from 7/91 through 6/92.

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

)

Accountability: Patterson/Schmidt Adverse Trend: None 44

0%-

1

-5 Primary System Chemistry Percent of Hours Out of Limit

[_ GOOD l 8%-

-E 6%-

r 4%-

Cycle 14 2%- 'C Refuelin9

-C O

Outage M

./

0%

Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 PRIMARY SYSTEM CHEMISTRY PERCENT OF HOURS OUT OF LIMIT

- The Primary System Chemistry Percent of Hours Out of Limit inoicator tracks the pri-mary system chemistry performance by monitoring six key chemistry parameters. Typi-cally, lithium is the parameter that is out of limit.100% equates to all six parameters -

being out of limit for the month.

-The Primary System Chemistry Percent of Hours Out of Limit was reported as 0% for the month of October 1992.

The 1992 Fort Calhoun goal for this indicatoris a maximum of 2%. The 1991 goal'was a maximum of 2%.

Data Source: Franco /Glantz (Manager / Source)

Accountability: Patterson/ Smith

- Adverse Trend: None 45' s

10%-

5

% of Hours Auxiliary System (CCW) Chemistry is Outside Station Limits 1

-O-1991 Industry Upper Ouartile 8%-

6%-

4%-

. Cycle 14 Refueling 2%-

Outage 0

-0 C

D.

i i

io%

o

'89 '90

Nov91 'Dec Jan Feb Mar Apr May ' Jun Jul Aug 7 Sept Oct92 AUXILIARY SYSTEM (CCW) CHEMISTRY PERCENT OF HOURS OUTSIDE.

STATION LIMITS' The Auxiliary System Chemistry Percent of Hours Outside Station Limits indicator tracksE the monthly percent of hours that the Component Cooling Water (CCW) system is -

1outside the station chemistry limit.

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

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

t Data Source: Franco /Glantz (Manager / Source)-

Accountability: Patterson/ Smith.

Adverse Trend: None' l-.,

..46' L-

.~_

Q Number of Instruments Out of-Service

--O--

Fort Calhoun Goal 26-24 g4 24-23 22--

l' 20 20 20-

$3 m

i L,

m j

1s 15 15 14-

~ -

~

12-10-i L

8-g o_

p.

^^-

0 Nov91 Doc Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 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 October there was a total of 17 in line chemistry instruments out-of-ser-vice. Of these 17 instruments,13 were from the Secondary System and 4 were from PASS. The Al-125 data logger was repaired during the month, resulting in a significant reduction in the number of out of service instruments, but subsequently failed due to circuit board corrosion.

The tren ' for PASS instruments has not changed since September. The entire second-ary panelis considered out-of-service because of failure of the Al-125 data logger. The number of secondary instruments out of-service has improved by three due to steam generator blowdown instruments being retumed to service.

The increase that occurred after November 1991 in the number of Secondary instru-ments out of service is due to a new method of determininc if an instrument ic out of service. The entire instrument channel is considered inoperative if: 1) the instrument is inoperative,2) the chart recorder associated with the instrument is inoperative,3) the alarm function associated with the instrument is inoperative. This change was made because if any of the functions named above are not operational, then the instrument is not performing its intended function.

The 1992 Fort Calhoun goal for the number of in-line chemistry system instruments that are out-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: Patterson/Renaud (Manager / Source)

Accountability: Patterson/Jaworski Ad"erse Trend: None 47

8 Monthly Waste Produced (Kilograms) -

- Yearly Waste Produced (Kilograms) 400 -

200 -

154.5 150 155 1,

'g'/f 0

0

, J 0

0

//g 0

0 0

I I

6 1

I i

i i

i 1

4 I

Nov91 Dec Jan Feb Mar Apr May Jun

-Jul Aug Sep _ Oct92 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 produceri.

During the month of October 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 305 kilograms.

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

Date Source: Patterson/Henning (Manager / Source)

Accountability: Patterson/Henning Adverse Trend: None 48

O Highest Exposure for the Month (mrem)

@ Highest Exposure for the Quarter (mrem) 3 Highest Exposure for the Year (mrem)

~

OPPD 4500 mrem /yr Limit 4000-3000-2 2000-1763 tiB1 0- - - - - - -

-- -- i Odober '92 MAXIMUM INDIVIDUAL RADIATION EXPOSURE During October 1992, an individual accumulated 561 mrem which was the highest individual exposure for the month.

The maxin.Jm individual exposure to date for the foudh quarter of 1992 was 561 mrem.

The maximum individual exposure reported for the year 1992 was 1,763 mrem. This exposure is primarily due to the individual's work during the Cycle 14 Refueling 0 ;tage on the de-tensioning and removal of reactor vessel studs, the remomi 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 Ca'houn goalis 1,500 mrem / year.

Date Source: FattersonAvilliams (Manager / Source)

Accountability: Patterson/Lovett Adve se Trend: None 49

l C

Month!/ Peis.onnel Contaminations f

Cumulative Personnel Contaminutions

[ GOOD 1 300-p.,

Fort Calhoun Annual Goal (144)

Y l

s 237 Outage s'

/

160-O - O-

-O - O O-O-

O-O-O O

O 100-4 x

[hd Q) 55 50-j hg eu e<

w 0-

^

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

'90

'91 Nov Dec92 TOTAL SKIN AND G.OTHING CONTAMINATIONS 1

This indicator shows the number of skin and clothing contaminat:ons for the reporting mor,ih. A total of 264 contaminations have occurred during 1992. There were 6. con-taminations during October 1992. The contaminations were: 1) A cloth!ng contamination.

that occurred when a machinist was working in room 71; 2) A clothing contamination that occurred when a fitter was working on RWP 386 in a Clean Controlled Area; 3) A clothing contamination that occurred when a contractor bollermaker was welding in a new valve; 4) A clothing contamination that occurred when a contractor was working on ISl walkdowns in Room 23; 5) A clothing contam! nation that occurred when a OC inspector was in Room 7 snooping welds; and 6) A shoe contamination that occurred in Room 60 when a OC inspector'was inspecting a valve behind a sample sink.

l There was a total of 55 skin and clothing _ contaminations in 1991 There was a' total of-237 skin and clothing contaminations in 1990,-

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

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

L Accountability: Patterson/Lovatt Adverse Trend: None SEP 15 & 54 50:

o

-4

~

.am.-

g D

Decontaminated Radiation Controlled Area 100% -

GOOD

-O-Fort Calhoun Goal (non-outage months)

Cyc'a 14 Refueling 90%~

m Outage f

g,,o o

,q pg-o

^

W lA 7

iw A

n 0;

3

$y/

es d

y g

si q$

[

h y

h 80% -

9 8

d e

3 S

4

(#

W 4

h

]

70% -

d W

I 1

h!

k

}

l i

l'

$1 60% -

Y9 b

e L

q q.

u

.J l

50 %

~

^

- 1' r

Nov91 Doc Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 DECONTAMINATED RADIAT4!1 CONTROLLED AREA This indicator shows the percentage of the RCA that is decontami,iated (clean) based on the total square footage, a 1991 Fort Calhoun goal of 85% decontaminated RCA for non-outage months and a 1992 Doal of 88% decontaminated RCA for non outage j

months.

At the end of the reporting month,85.2% of the total square footage of the RCA was decontaminated.

l 1

Date Source: Patt e rso n/G u ndal (Manag e r/Sou rce)

Accountability: Patterson/Lovett Adverse Trend: None SEP54 l

51 l

l l.

[3 Number of identified PRWPs 80' Cycle 14 Refueling 70-OURM 60-M 50-40-39 r

30-I i

20-1s h

h

~

s 4

I o-NovD1 Deo Jan Feb Mar Apr May Jun Jul Atg Sep Oct92 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 ;hrough a review of the monthly Radiological Occurrence Reports and Personnel Coritamination Reports.

The number of PRWPs w..ich are identified each month should indirectly provide a means to qualitatively assess supervisor accountability for their workers' radiological performance.

During the month of October 1992,3 PRWPs were identified. The 3 PRWPs were: 1) an ROR that was due to an employee entering en air'oorne contamination area on the wrong RWP; 2) a PCR that occurred when a contractor boilermaker was welding in a valve; and 3) a PCR that occurred when a contractor was working on ISI walkdowns in Room 23.

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: Patterson/ Williams (Manager / Source)

Accountability: Patterson/Lovett Adverse Trond: None SEP52 j

52 w

Q lotal Nuinbor of Hot Spots l

O Number of Additional Hc: Spots identified D

Removal Planned

-+-- Curnulative Hot Spots Romovoa 80-

-O-1992 Fort Calhoun Goal for Hot Spots Removed 60-

?

)

a 20-y y

Nok EPl B

~

Jan92 Feb Mar Apr May June July Aug Sept Oct Nov Doc 92 NUMBER OF HOT SPOTS This indicator shows the total number of hot spots which have been identified to exist in the Fort Calhour' Station and have been documented through the use of a hot spot identification sheet. A hot spot is defined as a smalllocalized source of high radiation.

A hot spot occurs when the contact dose rate of an item or piece of equipment is at least 5 times the General Area dose rate and the item or piece of equipment's dose rate is equal to or greater than 100 mRom/ hour, At the end of October, there were 67 hot spots identified. No hot spots were removed during the month and no new hot spots were identified during the month.

Removalis planned for 17 hot spots.

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

Data Source: PattersonAVilliams (Manager / Source)

Accountability: Patterson/Lovett Adverse Trend: None 53 l

l-

.m.

._ _ _ _ ____. m __ _ _ _ _ _ - _

l3 Monthly Radioactive Gas Discharged (Curios) umWaWe Radoa@e Gas Di.eargM (Curies)-

500 -

45

-O-Cumulative AnnualGoal(Curies) lGOODI

,gg _

3 58 C

O 300-200-100 -

/ '

0 I

i i

I i

i i

1 1

1 90

'91 Jan92 Feb Mar Apr May Jun Jul Aug Sept Oct Nov Doc 92 -

GASEOUS RADIOACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT.

The gaseous radioactive waste being discharged to the environment is shown for Janu-aty 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 diacharged to the environmer. 's calculated every six months.

Data Source: Franco /Krist (Manager / Source)

Accountability: Patterson/Trausch Adverse Trond: None

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

i

t, s

Monthly Radioactive Uguid Discharged Cumulative Radioactive Uquid Discharged i'i

-O-Cumulative AnnualGoal lGOODI k

250 -

t 220 C

O O

O t., M

'O 200-l 90 175 176 g

7,

s

r n-150 -

j i?.fl h

i g

Q.4 g

99' 0,b l

0-1 100 _

sfi

d Q

Q 23 a

4 y

]os g 50-W cr gg

/

r 15.

~

.1 s.2 6.7 7A

't n,

0 i

i i

.i i

i i-i i

'89

'90

'91 Jan92 Feb Mar Apr May Jun Jul Aug Sept Oct - Nov Dec92 LIQUID RADIOACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT The !iquid radioactive waste being discharged to the environment is shown for January 1,1992 through June 30,1992. The liquid radioactivo waste that was discharged to the environment from all sources totaled 39.5 curies during this time.

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

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

Data Source: Franco /Krist (Manager / Source)

Accountability: Patterson/Lovett Adverse Trend: None-l

.i

~

55-

~,,

-,,.,y

.-i,.,,,

0 Ervironmental D Failure j GOOD 1 Y

20 -

15-10-5-

3 3

I I

'I 0-i i

Alarms CCTV Computer Search Equipment Doors O 1991 System Faiiuret E 1992 System Failures lGoogl t

100-77 80 -

3 70 67 63 2

0--

i i

mm 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 Equipment Failures and Door Hardwaro Failures. Alarm systems and CCTV failures will be divided into two categories: environmental failures and failures as defined in the performance indicator definitions. Also, the 1991 and 1992 System Failures will be compared on a monthly basis.

System Number of incidents QCt2b2L12 Sectember 92 EDYitDDS Failures fnvirons Eallutna Alarms 3

3 5

1 CCTV 15 1

7 1

Computer N/A 3

N/A 2

Search Equipment N/A 6

N/A 2

Door Harcr.vate

[1%

3 LL%

3 Totals 18 16 12 9

1 Data Source: Sefick/Woerner (Manager / Source) i Accountability: Sefick/Patterson Adverse Trend: None SEP58 58 1

_ _ _ _ _ _ _ = _ _ _.

10*/. -

3 Amount of Work On Hold Awaiting Parts LGOODl 9%-

Y

-O-1991 & 1992 Fort Calhoun Goals 0%-

7%-

Cycle 14 6%-

Refueling 5%-

Outage 4%-

C O-0 O

O O-O O

O 3%-

Nov91 Doc Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 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.

There was a total of 994 open, non outage maintenance work orders (MWOs) with 19 (1.91%) of these MWOs on hold awaiting parts at the end of the reporting month.

1 The in91 and 1992 Fort Calhoun Goals for this indicator are to have less than 3.5% of the total number of open, non outage MWOs awaiting parts.

Data Source: Willrett/ CHAMPS (Manager / Source) l_

Accountability: Willrett/Fraser Adverse Trend: None 1

59

20-Sparo Parts Inventory Value ($ Milron) 15-10-5-

0-Nov91 Doc Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 SPARE PARTS INVENTORY VALUE The spare parts inventory value at the Fort Calhoun Station at the end of October 1992 was reported as $12,961,195, Data Source: Steele/Huliska (Manager / Source)

Accountability: Willrett/McCormick Adverse Trend: None

- Spare Parts issued ($ Thousands) 800 -

600-400-200-0 i

i i

i

_i_

i i_

i Nov91 -Dec Jan Feb Mar _

Apr May Jun Jul =

Aug Sep ' Oct92

- SPAHE PARTS ISSUED The value of the spare parts issued during October 1992 totaled $ 446,439. The w'ue; of the spare parts issued for November and December 1991'was not available due to a

. printer problem.

. Data Source: Steele/ Miser (Manager / Source)

Accountability: Willrett/McCormick-Adverse Trend: None 6A

__~ _ __ _

_.__ ~. _..

E inventory Accuracy

-O-Fort Calhoun Goal (98%)

~

q p

-e O

95% -

E 3

e Nov91 Doc Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 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.

i During October,782 different line items were counted in the warehouse. Of the 782 line-items counted, 5 items needed count adjustments. The inventory accuracy for the month of October was reported as 99%. The Fort Calhoun 1991 & 1992 goals for this indicator are 98%.

Data Source: Willrett/McCormick (Manager / Source)

Accountability: Willrett/McCormick Adverse Trend: None 3

7%-

E

% of Pick Tickets Generated When Parts are not Available, etc.

+ Fort Calhoun Goal 5

4%--

l E_ &N eme

==

_z a

C C

C 4*-

0%

Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug

-Sep Oct92 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 minimum stocking level and parts are not available.

During October 1992, a total of 1,313 Pick Tickets were generated. Of the 1,313 Pick Tickets generated, no Pick Tickets (0%) were generated when the amount of parts requested was equal to or less than the minimum stocking level and pa : were not available. The Fort Calhoun 1992 goal for this indicator is a max mum of 2.6% and the 1991 goal was a maximuir. of 2.0%.

Data Source: Willrett/McCormick (Manager / Source)

Accountability: Willrett/McCormick Adverse Trend: None -

61-4

--,n w

w

--w,

---,-.-,---,.,w

,,,w-

, -~-....,.-

,,r...-

.,am e

s e---

7 i

D

% of Total Purchases that are Expedited

-O--

1991 & 1992 Fort Calhoun Goals (0.5%)

4%-

Cycle 14 ~

L Refueling Outage 3%-

[

b@

7,.

P4-

{l 1%-

rM m

t' 1

0-- Q --0-- 6

i. --C O-

. --C O

o os 4 B.

5 5%

33 rm i9 Nov91 Dec Jan Feb Mar Apr May Jun

. Jul1 Aug Sep Oct92 EXPEDITED PURCHASES This indicator shows the percentage of expedited purchases compared to the total number of purchase orders generated during the reporting month.

During October, there was a total of 483 purchase orders generated. Of the 483 pur-chase orders generated, there were no expedited purchases.

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

The number of expedited purchases was above the Fort Calhoun goal durin0 the -

months of February, March and April 1992 due to the ordering of items related to the -

Cycle 14 Refueling Outage.

i Date Source: Wilfrett/Fraser (Manager / Source) 1 Accountability: Willrett/Fracer AdverseTrend: None 62

_+

,,_-.,,_m,

--.,,-,y Je,

.. -. C m,-

L L,

100-80-60 -

17 0-13 Service invoices COE Invoices Miscellaneous lNVOICE BREAKDOWN This ind!cator shows the number of service invoices, COE invoices, and miscellaneous invoices for the month of October 1992.

Date Source: Wilfrett/Fraser(Manager / Source)

Accountability: Wilfrett/Fraser Adverse Trend: None Percentage of Material Roquests for issue with the Request 5

Date the same as the Nood Date 100% -

-O--

1991 Fort Cathol' Goal 80%~

GO% -

C O

.2 E!IE Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 MATERIAL REQUEST PLANNING This indicator shows the percentage of material requests (MRs) forissue with their request date the same as their need date compared to the total number of MRs for L

issue for the reporting month. The 1991 goal of 60% is also shown.

l During the month of October, a total of 1,313 MRs were received by the warehouse. Of the 1,313 total MHs recolved by the warehouse,32.4% of the MRs (425) were for issue with their request date the same as their need date.

Data Source: Willrett/McCormick (Manager / Source)

. Accountability: Willrett/McCormick Adverse Trond; None 63

i 500 -

)

E TotalModification Packages Opon 1

425 425 400 -

337 300--

270 m

'88

'89

'90 Nov91 Doc Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 OUTSTANDillG MODIFICATIONS This indicator shows the total number of outstanding modifications (excludina outstand-ina modifications wh'ch are oroposed to be cancelled).

Category Reoorting Month Form FC 1133 Backlog /in Progress 18 Mod. Requests Being Review 3d 17 Design Engr. Backlog /In Progress 64 Construction Backlog /in Progress 27 Desion Engr. Undate Backlog /In Progress 20 Total 146 At the end of October,40 additional modification requests had been issued this year and 27 modification requests had been cancelled. The Nuclear Projects Review Com-mittee (NPRC) had completed 150 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) had completed 103 backlog modification request reviews this year.

Data Source: Jaworski/ Turner (Manager / Source)

Scofield/Lounsbery (Manager / Source)

Accountability: Scofield/Phelps l

Adverse Trend: None l

p j

0 Temporary Modifications >1 cycle old (RFO required for Removal)

O Temporary Modifications >e months old (Removabie on line)

-O-Fort Calhoun Goal for Temporary Modifications >1 cycle old (0) 0-l 5-i 4-3-

2 2

2 f/

bf,fhh:

hb b//hh:

1-

/

//////-

~

h

//

/

0 V

i V

I V

i August '92 September '92 October '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 greater than 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 October there were 2 temporary modifications installed that were greater than six months olo that can be removed on line. These were: 1) handjack close of CCW/RW valves, in which OPS is i

scheduled to reviso S.O. O 44 by 12/31/92. The progress of this task will be tracked by l

ClD 920953; 2) potable water supply piping temporary repair, which is in progress I

awaiting completion of MWOs 894520 and 92718.

At the end of October, there was a total of 21 TMs installed in the Fort Calhoun Station.

13 of the 21 installed TMs require an outage for removal and 8 are removable on line.

In 1992 a total of 64 temporary modifications have been insta+:d.

Data Source: Jaworski/ Turner (Manager / Source)

Accountability: Jaworski/Gorence l

Adverse Trend: None SEP 62 & 71 65 l

n e

~

O July 12 60-O August '92 50-40-Q Septemter'92 O October 92 20 21 22 0

0 0

0 2

1 o

2 5

0 3 months 3 6 months

>6 months System Engineering D July '92 O August '92 Q September 92 61 60-53 do 7

50-43 0 ocioder12 46 1 30 30 28 31

/

(,

EI hh hh ff[

I 0 3 months 34 months

>6 months Design Engincoring 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.

Atthe d of October 1992,37 EARS had been resolved and were going through the a

process. Wre was 1 EAR awaiting a technical response from Nuclear Myy luta LIAR oreakdown is as follows:

EAas opened during the month 18 EARS closed during the month 21 Total EARS open as of the end of the month 163 Data Source: Phelps/Pulverenti(Manager / Source)

Accountability: Jaworski/Phelps Adverse Trend: An adverse trend is indicated based on three consecutive months of increasing values for Design Engineering EARS >6 months old, This increase is partially attributable to the forced outages in July and AugM An action plan has been established which includes a review by System Engineering and Design Engineering of older EARS (>12 months) that are a lower priority to see if they can be cancelled.

SEP 62 06

~

Q ECNs BacMogged in DEN 350-O ECNs Opened During the Month Q ECNs Completed During the Morith 300-250-Cycle 14 Refueling 200-Outage m

150-g

}

h I

l 1

\\

100-l 1

R

)

E h

fc 4

m h}8 l h

Y I

9' 1

t 4

50-5 2

t 3

}

}j

.X 9

+

^

h h

1 1 i,g i,1 t

h t

m z

t 3

0 Nov91 Doc Jan Feb Mar Apr May Jun Jul Aug Sep Oct92 ENGINEERING CHANGE NOTICE STATUS This indicator shows the number of Engineering Change Notices (ECNs) awaiting completion by DEN, the number of ECNs opened during the reporting month, and the number of ECNs completed by DEN during the reporting month.

At the end of October 1992, there was a total of 162 DEN backlogged open ECNs.

There were 37 ECNs opened, and 46 ECNs completed during the month.

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

Data Source: Phelps/Pulverenti(Mana0er/ Source)

Accountabilit). Phelps/Jaworski Ad.arso Trend: None SEP 62 67 1

O DEN Engineering not complete O System Engineering Engineering complete, ter.ponse under review G Maintenance / Construction MWO/CWO scheduled, but work not complete D Mrfntenance/Constructicn MWO/CWO complete, awaiting closeout 86

{

71

c. s,

E 27 34

?y/s 10 1s SU

~

l l 5 2

0 1

1 W

W r --

i i

i 0 3 months 3 6 months

> 6 montic.,

ECN FAQlLITY CljANGES QPIN O DEN Engineering not complete O System Engineering Engineering complete, response under review Q Maintenance / Construction MWO/CWO scheduled, but work not complete D Maintenance / Construction MWO/CWO complete, awaiting closoout 78 81 51 E

10 11 10 10 16 3

2 0

ayj 7/1 i --

I I

m i

i 7

0 - 3 months 3 6 months

> 6 months ECN SUBSTIIRTE F1EPLACEMENT ITEMS OPES E DEN Engineering not complete O system Engineering Waikdown or confirmation not compiate 70-60-35 34 kI 0

~~ *

~

1 3

2 y

0 3 months 3 6 months

> 6 months ECN DOCUMENT CHANGES OPEN ENGINEERING CHANGE NOTICE BREAKDOWN 1

This indicator rt 'ws a breakdown of the number of Engineering Change Notices l

(ECNs) that art, ssigned to Design Engineering Nuclear (DEN), System Engineering, I

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.

l l

Data Source:, helps /Pulverenti(Manager / Source) l Accountability: Phelps/Jaworski l

Adverse Trond: None SEP 62 60 l

l

1932 Recordable injury /Itiness Frequency Hate

-M-6 Year Average Recordable injury / Illness Frequency Rate I GCOD 1

--O-1D92 Fon Calhoun Goal (2.0) y 3.5 -

3-2.5 -

y f,

.A o-ogC 0----o C

0 0

0 o

2-o --c

1. 5 -

1-0.s -

o-Jan92 Feb Mar Api 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 avera00 (from 1987 through 1991) recordable injury /i!! ness cases frequency rate r

is also shown.

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

The recordable injury / illness rate for January through October 1992 was reported as-3.49. Thore was one recordable injury / illness case, a knee injury that occurred during security training drills, reported for the month of October. There has been a total of 17 recordable injury / illness cases in 1992.

The recordable injury / illness rate for the past twelve months is 3.99.

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

Year Recordable Cases Year-End Hate 1989-11 2.2 1990 11 2.1 -

1991 18 3.3 L

Data Source: Sorenson/Skaggs (Manager /Sourco)

Accountability: Richard Adverse Trend: None SEP 15,25 & 26 69

~

O Licenseo Event Reports 46 O

Personnel Errors Reported in LERs g

- Cumulathe Licensee Event Reports e

-+- CumulatNe Personnel Errors Reoorted in LERs

{

N Dil 31 7

29 30-F' b'1 [

h 20-1 14 3'

12

' i

'i 9 10-i

?

c 0

Vii i

~

o 2

E W ;n in i

ti ha hm.

i i

iO 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.

There were no LERs submitted in October 1992.

Data Source: Short/ Lippy (Manager / Source)

Accountability: Patterson Positive Trond -

SEP 15 -

70

O Administratwo Control Problem

(',~) Licens.od Operator Error G Other Pers.onnel Error D Maintenanco Problem DostgrVConstructiorvinctallatiorvFabricatbn Problem 5-

@ Equipment Failutes 4-3-

2 -.

1-

-I-,--l l -1 ll l

o Nov91 Doc Jan Feb Mar Apr May sun Jul Aug Sep Oct92 LICENSEE EVENT REPORT (LER) ROOT CAUSE BREAKDOWN This indicator shows the LERs by report dato broken down by Root Cause Code for each of the past twelve months from November 1,1991 through October 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 sequenco coding. For detailed descriptions of those codes, see tho

'Porformanco Indicator Definitions" section of this report.

There were no LERs submittod in October 1992.

Data Source: Short/ Lippy (Manager /Sourco)

Accountability: Patterson Adverso Trend: Nono 71

O Actual Division Staffing Q Authorized DMsion Steffing 600*

510 533

'4

_C ) ' $;

400 -

>('

219 220 200 -

K M

@' ' g V

@ch 50 50 0-Nuclear Operations Production Engineering Nuclear Services j

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

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

Accourebility: Waszak A&erse Trend: None SEP 24 1

- C}- Nuclear Operations DMsion Turnover Hate

--b-Production Engineering DMsion Turnover Rate 10%-

--O-Nuclear Services DMsion Turnover Rate 8%-

l 6%~

[

4 % --

K 2%-

o-::

0%

J91 J91 A91 S91 091 N91 D91 J92 F92 M92 A92 M92' J92 J92 A92 S92 092 PERSONNEL TURNOVER RATE The turnover rates for the three Divisions are calculated using only resignations from OPPD.

Division Turnover Rate

i NOD 2.7%

PED 3.6%

NSD 0.0%

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

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

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

Accountability: Waszak -

Adverse Trend: None-72 -

,...c,.

7 y

m...-,

.,,.....;..w......

......, _.. +

J.

~ ~

w.---

p 60-O Totai nequalification Training sours O simutator Trainir o Hou,5 O Non Requalification Training Hours O Nurnberof Exam Failures 4

40-30 36 36 36 30-E 2

2 20-16 2

3 3

3 h

k 10-a a

p

~

/

~

6 s

- /

0 O

Cyclo 917 Cycle 921 Cycle 92 2 Cycle 92 3 Cycle 92-4 ~ Cycle 92 5._

Cycle 92 6 LICENSED OPERATOR REQUALIFICATION TRAINING This indicator provides information on the total number _of hours of training given to each crew during each cycle. The Simulator training hours shown on the graph are a subset -

of the total training hours. Non Requalification Training Hours are used for AOP/EOP verification & validation, INPO commitments, GET, Fire Brigade, Safety Meetings, and -

Division Manager lunches.

Exam failures are defined as failures in the written, simulator, and Job Performance

. Measures (JPMs) segments of the Licensed Operator Requalification Training.

Annual Requalification Exams we_re conducted during Rotation 92-6. All crews and all -

individuals tested passed all areas of the Exam,;'One individuai was absent during the.

Annual Requalifbation Exams. That individualis scheduled to be completed with his exam on November 17,'1992.

Data Source: Gaspet/Guliani (Manager / Source)

Accountability! Gasper /Guliani 1 Adverse Trend: None SEP 68

~73

.c

. 2

O SRO Exams Administered O SRO Exams Passed 5 RO Exams Administered 30-O Ro exams Passed a

20-7

?~

I

{.

j

'~

I i

T I,n-T,

o-Nov91 Doc Jan Fob Mar Apr May Jun Jul Aug Sep Oct92 LICENSE CANDIDATE EXAMS This indicator shows the number of Senior Reactor Operator (SRO) and Reactor Opera-tor (RO) quizzes and exams taken and passed each month. These internally adminis-tarod quizzes and exams are used to plot the SRO and RO candidates' monthly progress.

During the month of October 1992, there were no internally administered SRO or RO exams given.

There were no NRC administered SRO or RO exams during October.

Data Source: Gasper /Harman (Manager / Source)

Accountability: Gaspor/Guliani Adverse Trend: None SEP 68 I

74 u____________________________

0 Other Training (1,000 Hrs.)

@ General Employee Training (1,000 hrs.)

O Technical Support (1,000 Hrs.)

O Chorristry ard Radiation Protection (1.000 Hrs.)

O Maintenance (1.000 hrs-)

h O Operations (1,000 Hrs.)

I E8 58 2-g A

g

_u M

nD 8

E

=

~

n 5,,,,

l a

9

r.

=

g m

w

~

E m:

Z

=

15

~

]E E

=

Z E

E

=

E z

E E

25:

E

=

E E

E

=

0-

~,,,,

i Oct91 Nov Doc Jan Feb Mar Apr May Jun Jul Aug Sep92 TOTAL INSTRUCTION HOURS This indicator shows the total number of instruction hours for Operations, Maintenance, Chemistry and Radiation Protection, Technical Support, General Employeo Training, and Other Training conducted for the Fort Calhoun Station.

Due to the transition of responsibilities for training performance indicators, data for tb9 month of May was unavailable for this indicator.

This indicator is normally one month behind the reporting month due to the time re-quired for data coliection and processing.

DEPARTMENT Sectember '92 Operations 681 Maintenance 399 Chemistry and Radiation Protectbn 130 Technical Support 404 General Employee Tralning 183 Other 168 Total 1,965 Data Source: Gasper /Podoll (Manager / Source)

Accountability: Gasper Adverse Trend: None 75

j O Other Training (1,000 Hrs.)

@ Genorat Employee Training (1,000 hrs.)

30 -

@ Technical Support (1,000 Hrs.)

E Chemist y and Radiation Protection (1,000 Hrs.)

25' O Maintenance (1,000 Hrs.)

z

@ Operations (1,000 Hrs.)

@ 15-O E

g10-M

[W S-b g

g g

M h

-M m

=

m

=

,=,=,",

=,*

0 i

i i

i Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep92 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 indicatoris normally one month behind the reporting month due to the time needed to collect and eva!uate the data.

DEPARTMENT Sootember '92 Operations 2,128 Maintenance 1,664 Chemistry and Radiation Protection 530 Technical Support 2,661 General Employee Training 924 Other 168 Total 8,075 Data Source: Gasper /Podoll (Manager / Source)

Accountability: Gasper Adverse Trend: None 76

9-Vlotations per 1.000 inspect:on Hours

-O-Fort Cathoun Goal a

fD-a 3.7 a

2.6 l03-N j

~

0

~

i i

a i

00

00

'91 Oct91 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep02 VIOLATIONS PER 1,000 INSPECTION HOURS This indicator displays the number of NRC violations cited in inspection reports per 1,000 NRC inspection hours. This indicator is one month behind the reporting month due to the time involved with collecting and procoscing the data.

The violations per 1,000 inspection hours indicator was reported as 2.51 for the twelve months from October 1,1991 through September 30,1992.

The following NRC inspections ended during September 1992:

IER No.

Thlg No. of Hrs.

92-19 Radiological Envirenmental Monitoring 40 92-21 SpecialInspection: August RC-142 Event 216 92-23 Instrumentation & Calibration Maintenance 40 92 24 Engineering & Technical Support 240 There were no violations issued during September 1992.

The 1992 Fort Calhoun goalis a maximum of 1.5 violations per 1,000 inspection hours.

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

Data Source: Short/ Lippy (Manager / Source)

Accountability: Short Adverse Trend: None 77

Fort Caltoun

~

I'5 " i v:

9 N'

2.51 Cooper 1.12 River Bend 2.95 Commancho Peak 1.5 Wolf Creek 3.58 Arkansas One 1.61 South Texas 2.21 Waterford 2.96 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 October 1,1991 through September 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: Short Adverse Trend: None 78 u

--+- Nur her of Violations Juring the Last 12 Months i

-H>--

Numb;;. of NCVS During the Le"t 12 Months

+

ue 15 15 y1"

~13 I.

10-8 I

7/

N S4 4

4 4

3_ 7 N

3 w 9

0 OctSI Nov Dec Jan Feb Mar Ap

'My hn Jul Aug Sep92 CUMULATIVE ' '.>. ETlONS AND NCVs (TW. VE-MC'rs1H RUMNING TOTAL)

The '%.ulative Violatio 1s and Non-Cited Violations (NCVs) indicator shows the cumu-lative number of v%istions and the cumulative number o' NCVs for the last twelve months.

' no were no viohtions issued during September 1992.

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

Data Source: E5crt/ Lippy (Manager / Source)

Accountability: Short Adverse Trend: None it 79 (y

~

$ Tota! Outstanding CARS O Outstanding CARS > Six Months Old u s an ng A a Ar caibn ReW 150-100 -

50-

~

0-L l

Nov91 Dec Jan

-Feb Mar Apr May Jun Jul -

Aug Sep Oct92 l

OUTSTANDING CORRECTIVE ACTION REPORTS -

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

the number of outstanding CARS that are greater than six months old, and the number.-

l of outstanding CARS that are modification related, At the end of October 1992, there were 83 outstanding CARS,36 CARS that VGra greater than six months old, and 2 CARS that were modificatioa related.

Data Source: Orr/Gurtis (Manager / Source)

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

f

- 80 s

4.

r 20-Ot DD Overdue CARS 15-0 NOD CARS With Extensions Granted 10-5-

4 3

3 2

2 2

On 00 O d 0l?

0@ 01 Od om 00 0 k Opj M Nov91 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oc' ?

20-O PED Overdue CARS 15-O PED CA9s W4h Exten.ibns Granted 10-6 6

5 g

k 27 3

3 0~

2 2

0 Q p y 0 3 Od 00 0@ n f 0 ?:

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O ?

O :f OR O

Nov91 Dec Jan Feb Mar ivr May Jun Jul Aug Sep Oct92 20-D Other Overdue CARS in_

D Other CAP.s With Extensions Granted 4

5-3 3

.M 0 0 0@ YO 00 0@

00 00 00 00 1.1 00 0-i i

Nov91 Dec Jan Feb Mar Apr Mr Ja.1 Jul Aug Sep Oct92 OVERDUE AND EXTENDED CORRECTIVE ACTION REPORTS This indicator shows the rtmber of overdue CARS and the number of CARS which received extensions bcken down by c rganization.

Ov. irdue CARS Ove due CARS August 92 September 92 October 92 NOD 0

0 1

PED 0

0 0

Others 0

0 4

-[

Total 0

0 5

Extended CARS Extended CARS August 92 September $2 October 92 NOU 5

2 3

PED 4

4 3

Othem 0

3 0

To.at 9

9 6

Data Source: Orr/Gurtis (Manager / Source)

A_ccountability: Andrews/Gambhir/ Gates Adverso Trend: None 81 4,,

' i, f

1991 SALP Funct LERs Area CARS Signif. CARS NRC Viola -

A) Plant Operations 30 1

1 6--

B) Radiologl 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) (:ngr/ Tech SupporI 93 3

1 12 G) Safety Assess; 27 1

1 2

Qual. Verif.

H) Othei 0

0 0-0 Total 249 5

9 32 -

I t

r 1992 SALP Funa Area CARS Signit. CARS NRC Viola.

LERs i

3 A) Plant Operations 0-0 7-B) Radiolog. Controls 11-0 6

0 --

C) Maint/ Surveil, 116 (7) 1 4

-12 D) Emergency 6 (1) 1 1

0-Preparedness E) Sccurity 10(2) 0

.1

.O F) Engr / Tech Suppori 48 (6) -

0 0

12 G) Safety Assess /

29 (3) 0 0 Qual. Verif.

H) Other n

0 0

'O

.I Total 234 (19) 2 (0)

- 12 (0) '

31 (0)

]

Note:() Indicate values for the reporting month.-

CARE ISSUED vs. SIGNIFICANT CARS vs NRC VIOLATIONS ISSUED vs. LERs -

REPORTED The above matrix shows the number of Corrective Act' ion Reports (CARS) issued by the Nuclear Services Division (NSD) vs. the number of.Significant CARS' issued by NSD vs.-

- the number of violatio_ns 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) 16ntified -

by_the Siatioq each year. (ne number of NRC violations reported is one month behind :

the reporting month due to the time involved in collecting and processing the violations.

4 Data Source:- Orr/Gurtis L(Manager / Source)

Short/ Lippy (Manager / Source)-

Accountability: Andrews/Gambhir/ Gates AdverseTrend: None SEP 15,20,21; I

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MWOs Ready to Work

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Outage MWR Backlog

-B-Planning Hold 600 -

500 -

400 -

300 -

200 -

/

p 100 -

~~

0 Jun92 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep93 MWO PLANNING STATUS (CYOLE 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 numbcr of MWOs

- that are ready to work (parts staged, planning complete, and all other paperwork ready for fie;d use). Also lacluded 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 (lob scope not yet crimpleted). Maintenance Work Requests (MWRs) will also be shown that have been identified for the Cycb '5 Refueling Outage and have not yet been converted to MWOs.

Approximately 2,176 Maintenance Work Orders were completed during the Cycle 14 Refueling Ou; age.

Data Source: Patterson/Johansen (Manager / Source)

Acccuntability: Patterson/Johansen Aoverse Trend: None SEP 31 83 4

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

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

ule and the current schedule. This information is tak. irom the Modification Variance-l-

Repert produced by the Design Engineering Nuclear group.

L The goal for this indicator is to have all modification packages PRC approved by June

.1993.

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

Data Source: Patterson/Clemens (Manager / Source) i Accountability: Gambhlr/Phelps Adverse. Trend: Nene SEP 31 85 4

t

1 l

PERFORMANCE INDICATOR DEFINITIONS AGE OF OUTSTANDING MAINTENANCE WORK OR.

COMPONENT FAILURE ANALYSIS REPORT (CFAR) -

DERS

SUMMARY

This indicator tracks the total number of outstanding cor-The number of INPO categories for Fort Calhoun Station rective non-outage Maintenance Work Orders at the Fort wah signifcantly higher (1.645 standard deviations) faib Calhoun Station versus their age in months.

' ute rates than the rest of the industry for an eighteen month time period. Failures are reported as component AMOUNT OF WORK ON HOLD AWAITING PARTS (i.e. pumps, motors, valves, etc.) and appleation (i.e.

This indicatoi.s defined as the percentage of open, non-charging pumps, main steam stop valves, control ele-

. outage, maintenance work orders that ara on hok! await-ment drive motors, etc.) categories, ing parts, to the total number of open, no outage, main-Failure Cause Categories are:

tenance work orders.

Wear Out/ Aging a failure thought to ba the conse-quence of expected wear or aging.

AUXIU ARY FEEDWATER SYSTEM SAFETY SYSTEM Manufacturing Defed a failure attributable to inad-PERFORMANCE equate assembly or initial quality of the responsible com-The sum of the known (planned and unplanned) unavaib ponent or system.

able hours and the estimated unavailable hours for tne Engineering / Design - a failure attributable to the inad-auxiliary feedwater system for the reporting penod di-equate design of the responsNe component or system.

vided by the critical hours for the reporting period multi-Other Devices a f ailure attributable to a failure or plied by the number of trains in the auxiliary feedwater misoperation of another component or system, including system.

associated devices.

Maintenance / Testing - a f ailure that is a result of im-AUXILIARY SYSTEMS CHEMISTRY PERCENT OF proper maintenance or testing, lack of maintenance, or HOURS OUTSIDE STATION LIMITS personnel errors that occur during maintenance or test-Tha cumulative hours that the Component Cooling Water ing activities performed on the responsible component or system is outside the station chemistry limit. The hours system, including failure to follow procedures, are accumulated from the first sample exceeding the limit Errors failures attributable to incorrect procedures that until additional sampling shows the parar eter to be back were followW as written, improper insta!Iation of equip-within limits.

ment, and personnel errors (including f allure to follow procedures properly). Also included in this category are CARS ISSUED vs. SIGNIFICANT CARS vs. NRC VIO-f ailures for which the cause is unknown or cannot be as-LATIONS vs. LERs REPORTED _

signed to any of the preceding categories.-

Provides a comparison of CARS issued, NRC violations, and LERs reported. This indicator tracks performance CORRECTIVE MAINTENANCE BACKLOG GREATER '

for SEP #15,20, a 21.

THAN 3 MONTHS OLD The percentage of total outstanding conective mainte-CHECK VALVE FAILURE RATE nance items, not requiring an outage, that are greater Comperes the Fort Calhoun check valve f ailure rate to than three meaths 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 industrv failure rate CUMULATIVE VIOLATIONS & NON-CITED VIOLA-is three months behind the PI Report reporting month.

TlONS(12 MONTH RUNNING TOTAL)

This indicator tracks performance for SEP 841 The cumulative number of violatbns and Non-Cited Vio-lations for the last 12 months.

COLLECTIVE RADIATION 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 therrr.at output as contractors and visitors) during a time period, as mea-measurad f rom computo point XC105 (in thermal mega-sured by the thermoluminescent dosimeter (TLD). col watts). : The 1500 MW Tech S;,ec limit, and the unmet lective radiation exposure is reported in units of person-portion cf the f 495 MW FCS daily goal for the reporting rem This indicator trucks radological work performance month are ain shown, for SEP E4.

' DIESEL GENERATOR RELIABILITY (25 DEMANDS) _

COMPARISCN OF VIOLATIONS AMONG REGIOt1IV This indicator shows the 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 demanos.

for Region IV nuclear power plants.

DIESEL GENERATOR UNAVAILABILITY l-This indicator provides monthly oata on 'ha number of hours of diesel generator planned and unplanned un-availability.

B6 9

PERFORMANCE INDICATOR DEFINITIONS (Cont'd)

DECONTAMINATED 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 radweste bui_iding, and as stated in each test's specifications, areas of Ihe C/RP building, that is doo:ataminated based C) Other special tests in which tha emergency generator i

on the total square footage. This indcator trads perfor.

is expected to be operated for at least one hour while mance for SEP # 54.

loaded with at least 50% of its design bad.

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

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

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

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

should not be counted as valid demands or f ailures when tot personnel. This indicator tracks personnel perfor.

they can be attributed to any of the following:

mance for SEP #25 & 26.

A) Spurious trips *at would be bypassed in the event of an emergency, DOCUMENT REVIEW (BIENNIAL)

B) Malfunction of equipment that is not required during i

The Document Review Indicator shows the number of an emergency, documents reviewed, the number of documents sched.

C) Intentional termination of a test because of abnormal uled for review, and the number of documont reviews conditions that would not have resulted in major diesel that are overdue for the reporting month. A document generator damage or repair.

review is considered overdue if the review is not com.

D) Malfunctions or operating errors which would have not plete wrthin 6 months of the assigned due date. This prevented the emergency generator from being restarted indcator tracks performance for SEP #46.

and brought to load within a few minutes.

E) A failure to start because a portion of the starting sys-EMERGENCY AC POWER SYSTEM SAFETY SYSTEM tem was disabled for test purpose, if followed by a suc-PERFORMANCE cessful start with the starting system in its normal align.

The sum of the known (planned and unplanned) unavail-

ment, able and the estimated unavailable hours for the emer.

Each emergency generator failure that results in 9" a gen-gency AC power system for the reporting period divided erator being declared inoperable should be counted as by the number of hours in the reporting period multiplied one demand and one failun.. Exploratory tests during by the number of trains in the emergency AC power sys-corrective maintenance and the cuccessfuitest that foi-

tem, low 1 repair to verify operabiiity should not be counted 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 failures that were ENGINEERING ASSISTANCE REQUEST (EAR) reported during the last 20,50, and 100 emergency die.

BREAKDOWN sel generator demands at the Fort Calhoun Station. Also This indicator shows a breakdown, by age of the EAR. of -

shown are ingger values which correlate to a high level the number of EARS assigned to Design Engineering of confiuence that a unit's diesel generators have ob-

- Nuclear and System Engineering. This indicator tracks tained a reliability of greater than or equal to 95% when performance for SEP #62.

the demand f ailures are less than the trigger values.

1) Number of Start Demands: All valid and ir,sdvertent ENGINEERING CHANGE NOTICE (ECN) DREAK-start demands, including all start-only demands and all-DOWN start damands that are followed by load-run demands, This indicator breaks dcym the number of Engineering whether by automatic or manualinitiaton. 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 Facility

2) Number of Start Failures: Any failure within the emer, Changes open ECN Substitute Replacement Parts gency ponerator system that prevents the generater from open, and ECN Document Changes open. This indicator -

achieving specified foquem and voltage is classified as tracks perform-nce for SEP #62.

a valid start f ailure. This includes any condition identified in the course of maintenance inspections (with the emer.

ENGINEERING CHANGE NOTICE (ECN) STATUS gency generator in standby mode) that definitely would The number of ECNs that were opened. ECNs tha* wure -

have resulted in a start failure If a demand had ex: curred.

completed, and open backlog ECNs awaiting completion

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

' one or more of the following criteria:

A) A load run ci any duration that results from a real au-tomatic or mamaiinttiation.

p

, a a

PERFORMANCE INDICATOR DEFINITIONS (Cont'd)

EQUIPMENT FORCED OUTAGES PER 1,000 CRIT).

GASEOUS RADIOACTIVE WASTE BEING DIS-CAL HOURS CHARSED TO WE ENVIRONMENT F.quipment forced outages per 1000 cntcal hours is the This indcator displays the total number of Curies of all inverse of the mean time between forced outages gaseous radioactive nuclides released from FCS.

caused by equipment failures. The mean time is equal to the number of hours the reactor is critical in a perod GROSS HEAT RATE (1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months ) divided by the number of forced outages Gross heat rate is defined as the ratio cf total thermal caused by equipment f ailures in that period.

energy in Bntrsh Thermal U.mts (BTU) produced by the reactor in the total gross electrical energy produced by EQUIVALENT AVAILABluTY FACTOR the generator in kilowatt hours (KWH).

This indcator is defined as the ratio of gross available generation to gross maximum generaton, expressed as HAZARDOUS WASTE PRODUCED a perwentage. Available generaton is the energy that The total amount (in Kilograms) of non-halogenated haz-can be produced if the unit is operated at the maximum ardous waste, halogenated hazardous waste, and other power level permitted by equipment and regulatory limi-hazardous waste produced by FCS each month.

tations. Maximum generation is the energy 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 cf the known (planned 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 munth mmpared to the total number of pur-period divided by the critical hours for the reporting pe-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 mmpared VICE a the ome planned for electrical ger". 7 tion. Forced Total number of in-line chemistry instruments that are events are failures or other unplanneo 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 fail-ures and events initiated while the unit is in reserve shut-INVENTORY ACCURACY down (i.e., the unit is available but not in service).

The percentage of line items that are counted each month by the warehouse which need count adjustments.

FUEL REUABILITY INDICATOR This indicator is defined as the steady + tate primary cool-INVOICE BREAKDOWN ant 1131 activity, corrected for the tramp uranium contri-The number of invoices that are on hold due to shelf life, bution and normalized to a common purificaton rate.

COE, and miscellaneous reasons.

Tramp uranium is fuel which has been deposited on re-actor coro 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 does not vary more than + or SE Plants should collect SEP #68.

data for this indcator at a power level above 85%, when possible. Plants that did not operate at steady state UCENSED OPERATOR REQUAUFICATION TRAIN-power above 85% should collect data for this indcator at ING the highest steady-state power level attained during the The total number of hours of training given to each crew

month, during each cycle. Also provided are the simulator train-The density correction f actor is the ratio of the specific ing hours (which are a subset of the total training hours),

volume of coolant at tne RCS openg temperature the number of non-requalification training hours and the (540 degrees F., Vf - 0.0214L <. W by the specific number of exam f ai!ures. This indicator tracks training volume of coolant at norma:ler, terperature (i20 performance for SEP #68.

degrees F at outlet of tha letdowa axWing heat ex-changer, Vf = 0.016203), wnch results in a density cor-recton factor for FCS equal to 1.32.

88 x

PERFORMANCE INDICATOR DEFINITIONS (Cont'd)

LICENSEE EVENT REPORT (LER) ROOT CAUSE MAINTENANCE OVERTIME 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.

foluws:

1) Administrative Control Problem Management and MATERIAL REQUEST PLANNING supervisory defciencies that affect plant programs or The percent of material requests WRs) for issues with activities (i.e., poor planning, breakdown or lack of ad-their request date the same as their need date compared equate management or supervisory control, incorrect to the total number of MRs.

procedures, etc.)

2; Leensed Operator Error This cause code captures MAXIMUM INDIVIDUAL RADIATION EXPOSURE errors of omission / commission by Icensed reactor opera-The total maximum amount of radiaton received by an tors dunng plant activities.

individual person working at FCS on a monthly, quarterly,

3) Other Personnel Error - Errors of omissiorvcommis-and annual basis.

sion committed by non-Icensed personnelinvolved 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 attnbuted in any way to programmatic deficiencies in been approved for inclusion in the Cycle 15 Refueling the maintenance functonal organization. Activities in-Outage and the number that are ready to work (parts cluded in this category are maintenance, testing, surveil-staged, planning mmplete, and all other paperwork lance, calibration and raddtion protection.

ready 1or field use). Also included is the number of

5) Design /Constructionnnstallation/ Fabrication ProtSem MWOs that have engineering holds (ECNs. procedures

- This cause code covers a full range of programmatic and other miscellanoon engineering holds), parts hold, defeiencies in the areas of design, construction, installa-(parts stageA not yet inspected, parts not yet arrived) tion, and f abrication (i.e., loss of control power due to and planrag hoki(job scope not yet completed). Main-underrated fuse, equipment not qualified for the environ-tenance Work Requests fMWRs) are also show%at mont, etc.).

have been identified for the Cycle 15 Refueling Outage

6) Equipment Failures (Electronic Piece-Parts or Envi-and hav9 not yet been converted to MWOs.

ronmental Related Failures) - This code is u'ed for spuri-ous f ailures of electronic piece parts and faims due to NUMBER OF CONTROL ROOM EQUIPMENT DEFI-meteorological conditions such as lightning, ici., high CIENCIES winds, etc. Generally, it includes spurious or one-time Control room equipment that cannot perform its design f ailures. Electnc components included in this category function is considered as deficient. Control room equip-are circuit cards, rectifiers, bistables, fuses, capacitors, ment that has had a Maintenance Work Order (MWO) diodes. resistors, etc.

written for it and has not been repaired by the end of the reporting period is considered deficient and will be LIQUID RADIOACTIVE WASTE BEING DISCHARGED counted. The duration of the deficient condition is not TO WIE ENVIRONMENT considered.

This indicator displays the total number of curies from all liquid releases from FCS to the Mesouri River.

NUMBER OF HOT SPOTS D' e number of radiological hot spots which have been LOGGABLE/ REPORTABLE INCIDENTS (SECURITY) w,ufied and documented to exist at FCS at the end of The total number of security incidents for the reporting the reporting month. A hot spot is a small localized month depicted in two graphs. This indicator tracks se, source of radiation. A hot spot occurs when the contact cunty performance for SEP #58.

dose rate of an item is at least 5 times the General Area dose rate and the item's dose rate is equal to or greater MAINTENANCE EFFECTIVENESS than 100 mrem / hour.

The number of Nuclear Plant Reliability Data System -

(NPRDS) components wrth 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 f ailures over the pie-for the last eighteen months.

coding 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-rrsin open at the end of the reporting month. This indi-cator tracks mal,tenance performance for SEP #36.

89

PERFORMANCE INDICATOR DEFINITIONS (Cont'd)

NUMBER OF PERSONNEL ERRORS REPORTED IN OVERALL PROJECT STATUS (CYCLE 15 REFUEL.

LERS ING OUTAGE)

The number of Lcensee Event Reports (LERs) attributed This indcator 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 perf.stmance for SEP #15.

OVERDUE AND EXTENDED CORRECTIVE ACTION NUMBER OF MISSED SURVEILLANCE TESTS RE-PEPORTS SULTING IN UCENSEE EVENT REPORTS Ne number of overdue Corrective 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 indcator tracks missed STs for SEP #60 &

61.

PERCENT OF COMPLETED SCHEDULED MAINTE-NANCE ACT1VITIES OPERATIONS AND h.AlNTENANCE BUDGET The % of the number of completed maintenance activi-The year to date budget compared to the actual expen-ties as comptred to the number o' ";heduled mainte-drtures for Operatons and Maintenance departments.

nanen actrvities each week. This % is shown tor each nw r,tenance craft. Maintenance activities include MWRs, OUTSTANDING CORRtECTIVE ACTION REPORTS MWOs, STs, PMOs,.:alibrations, and other miscella-This indicator 6isplays the total number of outstancing r:sous activities. These indicators track Maintenance Corrective Action Reports (CARS), the number of CARS performance for SEP #33.

that are older than six months and the number of modifi-cation related 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 Modifcation Requests (MRs)in any state ignation from the company. Retirement, death, termina-between the issuance of a Modification Number and ;he tion, transfers within the company, and part time employ.

completion of the drawing update, ses are not considered in tumover.

1) Form FC-1133 Backlogrin Progress. This number rep-resents modifcation requests that have not been plant PLANNED CAPABluTY 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 generation (the includes:

energy that could be produced if the unit were operated A.) Modification Requests that are not yet reviewed.

cmtinuously at full power under reference ambient con-B.) Modifcation Requests being reviewed by the Nuclear ditions), expressed as a percentage, Projects Review Committee (NPRC).

C.) Modification Requests being reviewed by the Nuclear PREVENTIVE MAINTENANCE ITEMS OVERDUE Projects Committee (NPC)

This indicator is defined as the % of preventive mainte-These Modification Requests may be reviewed several nance items in the month that were not completed by the tirnes before they are approved for accomplishment or scheduled date plus a grace period equal to 25 % of the cancelled. Some of these Modification Requests are schedu'ed 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 plated and the scope of the work is clearly defined, these OF UMIT Modifcation Requests may be approved for accomplish-The % of hours out of limit are for six primary chemistry r

ment with a yaar assvjned for construction or they may parameters divided by the total number of hours possible be cancetted. All of these different phases require re-for the month. The key parameters used are: Lithium, view.

Chloride, Hydrogen, Disse'ved Oxygen, Fluoride, and

3) Design Engineering Backlog /In Progiess. Nuclear Suspended Solids. EPRIlimits are used.

Planning hn assigned a year in which constructen will be cormleted and design work may be in progress.

PROCEDURAL NONCOMPLIANCE INCIDENTG

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 mod;fication has not been acc9pted by the System nance procedural problems, the number of closed irs Acceptance *.,ommittee (SAC).

related to the use of procedures (inciudes the number of

5) Design Engineering Update Backlog'in Progress. PED closed irs caused by procedural noncompliance), and has received the Modification Completon Report but the the number of closed procedural noncompliance irs.

drawings have not been updated.

This indicator trends personnel performance ur SEP The above mentioned outstanding modificatons du not

15,41 & 44, include modificatons which are proposed for canco!!a-tion.

90 s

PERFORMANCE INDICATOR DEFINITIONS (Cont'd)

PROGRESS OF CYCLE 15 OUTAGE MODIFICA110N PLANNING (FROZEN SCOPE OF 24 MODIFICA-RONS)

This indicator shows the status of modifcations ap-system computer, proved for completion during the Cycle 15 Refueling Out-

3) Security Force Error - Events caused by members of age.

the security force that are found to be inattentive to their duties or who neglected to properly perform assigned RADIOLOGICAL WORK PRACTICES PROGRAM functions (e g., required search pro dure or patrol).

The number of identified poor radiological work practices

4) Unsecured Doors Doors which are found to be unse-(PRWPs) for the reporting month. This indicator trads cured with no compensatory offcer 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 RADO OF PREVENTIVE TO TOTAL MAINTENANCE where an unsecured door is caused by air oressure are The ratio of preventive maintenance (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-This indicator tracks security performance for SEP #58.

tenance completed over the reporting period. Tha ratio, expressed as a percentage, is calculatad bat An man-SECURITY SYSTEM FAILURES hours. This indicator tracks preventive maintenance ac-The following components are the types of loggable/re-tivities for SEP #41.

portable SECURITY SYSTEM FAILURES represented in this indcator, incidents in this category include alarm RECORDABLE INJURY /lLLNESS CASES FRE-system f ailures, CCTV f ailures, security computer f ail-OUENCY RATE ures, search equipment f allures, and door hardware f ail-The number of injuries requiring more than normal first uros. These system f ailures are further categorized as aid per 200,000 man hours worked. This indcator follows:

trends personnel performance for SEP #15,25 8 26.

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

SECONDARY SYSTEM CHEMISTRY PERFORMANCE

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

based on the concentration of key impurities in the sec-

3) CCTV F ahures - Mechanical f ailures to all CCTV hard-ondary side of the plant These key impurities are the ware components.

most likeby 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 er:viromaental conditions (i.e., rain, snow, period of time when the plant is operated at greater than frost, fog, sunspots, shade).

30 percent power.

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

plexer, central processing unit, and other computer t d.

(Ka o.8) + (Na/20) + (0,/10)) / 3 where the following are ware and software. This category does not include 5 -

r monthly averages of: Ka = average blowdown cation ware probtems caused by operator error in using the conttuctivity, Na - average blowdown sodiurr.concen-software.

tration, O, - average condensate pump discharge dis-

6) Search Equipment Failures - Failures of x-ray, metal, solved oxygen concentration.

or explosive detectors and other equipment used to search for contraband. This also includes incidents SECURITY NON-SYSTEM FAILURES -

whare the search equipment is found to be defective or The following components are the types of loggable/re-c'id not function property during testing.

portable non-system f ailuros represented in this indica-

7) Door Hardware Failures - Failure of tne door alarn tor, incidents in this category include security badges, and other door hardware such as latche Tic strikes.

- access control and authorization, secunty force error, doorknobs, locks, etc.

and unsecured doors.

8) 1991 versus 1992 System Failures Statistes from

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

area, out of control on-cite, or inadvertent!y destroyed or broken.

SPARE PARTS INVENTORY VALUE

2) Access Control and Autho i?.ation Administrative and The dollar value of the spare parts inventory for FCS dur-procedural errors associated with the use of the card-ing the reporting period.

access system such as tailgating, incorrect securrty tmdge iscued, and improper escort procedures. This SPARE FARTS ISSUED also includes incidents that were caused by incorrect The dollar value c.f the spare parts issued for FCS during access authorization information entered into the security the repcrting period.

91

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 for the Nuclear Operations Division, the Producten Engi-instruction hours administered by the Training Center.

neering Division, and the Nuclear Services Divison. This indcator tracks performance for SEP #24.

TOTAL SKIN AND CLOTHING CONTAMINATIONS Reportable skin and clothing contaminatons above STATION NET GENERATION background levels greater than 5000 dpnV100 cm The net generaton (sum) produced by the FCS during squared. This indratar trends personnel performance the reporting month.

for SEP #15 & 54 STOCKOUT RATE UNIT CAPABILITY FACTOR The total number of Pick Tckets that were generated The ratio of the available energy generation over a given during the reporting month and the 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 as a per-able.

centage.

TEMPORARY MODIFICATIONS UNPLANNED AUTOMATIC REACTOR SCRAMS PER The number of temporary mechanical and electrical con-7,000 CRITICAL HOURS f gurations to the plant's systems.

This indicator is defined as the number of unplanned au-

1) Temporary configuratons are det ned as electrical tomatic scrams (reactor protection system logic actua-jumpers, electrical blocks, mechancal jumpers, or me-tions) that occur per 7,000 hours0 days 0 hours 0 weeks 0 months of critical operation.

chanical blocks which are installed in the plant operating The value for this indicator is calculated by multiplying systems and are not shown on the latest revision of the the total number of unplanned automatic reactor scrams P&lD, schematic, mnnection, wiring, or flow diagrams.

in a specific time period by 7,000 hours0 days 0 hours 0 weeks 0 months , then dividing

2) Je npers and blocks which are insed for Surveil-that number by the total nurr.ber of hours critical in the lance Tests, Maintenance Procedures, Calibration Pro-same time period. The indicator is further defined as cedures, Special Proceduies, or Operating Procedures follows:

are not considered as temporary modifications unless the 1) Unplanner' +9ans that tha scram was not an antici-jumper or block remains in place after the test or proce-pated part of a p:;.nnsd 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 control catons.

rods, liquid injection system, etc.) that is caused by ac-

3) Scaffolding is not considered a temporary modifica-tuation of the reactnr protection system. The scram sig-tion.- Jumpers and blocks which are instaried 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 untilfinal resolution of the MR

3) Automatic meant. ' hat 69 initial signal that caused and the jumper oi olock is removed or is permanenS actuation of the reactor protection system logic was pro-recorded on the drawings. This indicator tracks tempo-vided from one of the sensors monitaring p! ant param-rary modificatbns for SEP #62 & '71.

eters and conditions, rather than the manual scram switches or,in manual turbine trip switches (of push-but.

THERMAL FERFORMANCE lons) provided in the main contr toom.

The ratio of the design gross heat rate (mrrected) to the

4) Critical means thn during the steady state conditic of adjusted actual gross haat rate, expressed as a percent-the racctor prior to the scram, the effective multipfcation age.

factor (k,) was essentia0y equal to one.

TOTAL HOURS OF STUDENT TRAINING UNPLANNED CAPABILITY LOSS FACTOR The total number of student hours cf training ior Opera.

The ratio of the unplanned energy losses during a given tons, Maintoaance, Chemistry / Radiation Protection, period of time, to the reference energy generation (the Technical Support, General F.moloyee Training, and en9rgy that could be produced if the unC were operated Other Training canducted for (0s.

continuously at futt power under ref erence ambient con-dMions) over the same time period, expressed as a per-centago.

- 92 E

m+

m n'

PERFORMANCE INDICATOR DEFINITIONS (cont'd)

UNPLANNED SAFETY SYSTEM ACTUATIONS-(INPO DEFINITION)

This indicator is defined as the sum of the following safety system actuations:

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

2) The number of unplanned emergency AC power sys-tem actuatons that result from a loss of power to a safe-guards bus. An unplanned safety system actuaton oc-curs when an actuation 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 xtuated. Unplanned means that the system actuation was not part of a planned test or evolution. The ECCS actuatons to be counted are aduatons of the high pres-sure injection system, the low pressure injection system, or the safety injection tanks.

UNPLANNED SAFETY SYSTEM ACTUATIONS(HRC DEFINITION)

The number of swety system actuations which include

(@) the High Pressure Safety injection System, the Low Pressure Safety injedion System, the Safety injec-tion Tanks, and the Emergency Diesel Generators. The NRC claesification of safety system actuations includes r.:tuatons when major equipment is operated god when the logic systems for the above safety systems are chal-1ervyd.

VIOLAT10NS PER 1,000 INSPECTION HOURS This indicator is defined as the number of violations shed in NRC incpoction reports for FCS per 1,000 NRC in-spection hours. The volations are reported in the year that the inspection was ectually performed and not based on when the inspecton report is received. The hnurt reported for each inspection report are used as the in-spection hours.

VOLUME OF LOW-LEVEL SOLIO RADIOACTIVE WASTE This indtcatzst io defined ss the volume of low levet solid radcactive waste actually thipped for burial. This mde,a.

tot also shows the volumo of low-leve! radioactive waste which is in temporary storege, the amount of radioactive oli that has been shipped off--site for proccasing, and the volume of solid dry radioactive waste which has been shipped off-sits fsr processirg. Low-level solid radioac-14 waste consists of dry active waste, sludges, resins, and evaporator bottoms ganerated as a result of ns.c! car power plant operation and maWenance. Dry radioactive waste includes contaminated rags, cleaning ma'eria!s, disposable protactrve clothing, plastic containe - and any other rnatorial to be disposed of at a low-level radio-active wasta disposal site, except resin, stuoga, or evaporator bottoms, los devel refers to all radcactive -

waste that is not spent fuel or a byproduct of spent fuel

. processing. This indicator tracks radological work per-formance for SEP #54.

93

SAFETY ENHANCEthENT PROGRAM INDEX Th3 purpose of th1 Safety Enhancement Program (SEP) Partormance Indicators Index is to list pertor-mince indicctors related to SEP ltems with partmeters that can be trended.

SEP Reference Number 15 Eaga increase HPES and IR Accountability Through Use of Performance indicators Procedural Noncompliance incidents (Maintenance).

...... 33 Total Skin and Clothing Contaminations.

..... 50 Recordable injury / illness Cases Frequency Rate..... _. _...

.. 69 Number of Personnel Errors Reported in LERs..

.. 70 CARS issued vs Significant CARS issued vs NRC Violations issued vs LERs Reported...........

SEP Reference Number 2Q Quality Audits and Surveillance Programs are Evauated, improved in Depth and Strengthened CARS issued vs Significant CARS issued vs NRC Violations issued vs LERs Reported...

.. 82 SEP Reference Numbar 21 Develop and Conduct Safety System Functionalinspections CARS issued vs Significant C ARs issued vs NRC Violatior:s issued vs LERs Reported....... 82 SE.P Reference Number 24 Complete Staff Studies Staffing Level.

. 72 SEP Reference Number 25 Training Program for Managers and Supervisors Implernented Disablin0 injury /ntness Frequency Rate...

.18 Recordable injury /fliness Cases Frequency Rate..

..... 69 SEP Reference. Number 26 Evaluate and implement Station Standards for Safe Work Practice Requirements Disablinginjury/!!! ness Frequency Rate..

..13 Recordable injury / Illness Cases Frequency. Rate......

. 69 SEP Reference Number 31 Develop Outage and Maintenance Planning Manual and Conduct Project Management Training MWO Planning Status.......

....,83 Overal: Project Stalus.....

.. 84

....m...

Progress of Cycle 15 Outage Modification Planning.

.. 85 SEP Reference Number 33 Develop On Line Maintenance and Modification Scheduto

'I Percent of Completed Schaduled Maintenance ActiWties (Electrkal Maintenance)...

.._.. 34 (Pressure Equipment).

....... 35 (Generai Makitenance)._.....

... 36 (Mechanical Maintenance).

....... 37 (Instrumentation & Control).

.... 38 SEP Reference Number 36 Reduce Corrective Non-Outage Backlog t 'mintenance Work Order (MWO) Breakdown (Corrective Non-Outage Maintenance)..

.. 27 w actmt Maintenance Backlog Greater than 3 Months Old (Non4utage)....

....a..

. 28 SEP Reference Number 41 Develop and implement a Preventive Maintenance Schedule Ratio of Preventhe to Total Maintenance c..

...,,. 29 -

' reventive Maintenance K5ms Overdue.

....... 30.

, cocedural Noncompliance incidents.......

.. 33 94-

- ~.-

Mi i

- SEP Reference Numberg, implement the Check Valve Test Program Check Valve Failure Rate..............................

...... 43 '

1 SEP Heference Number 44 Compliance With and Use of Procedure,;

Procedural Noncompliance incidents (Maintenance)...,.....

................33 SEP Reference Number 48 Design a Procedures Control and Administrative Program Docu me nt R e view............................................................................. 22 SEP Reference Number 52 Establish Supervisory Accountabluty for Workers Dadiological Practices Radiological Work Practices 6ogram.

................52 SEP Reference Number 54 Complete implemernation of Rediological Enhancement Program Collective Raduttion Exposure................................................................................... 16 -

Volume of Low-Level Solid Radioactive Waste...,.,.

...................,..................17 T otal Skin ard Clot hing Co nta minations -........................................................................... 50 -

4 t

Decontaminated Radiation Controlled Area..

..,......,.....................................51 SEP Reference Number 58 Revise Physi at Security TmIning and Procedure Program Loggable/ Reportable incide.its (Seeurity)..................-...................................................... 56 Security Non-System Failure s.'.....................................................

.................... 57 Secu rtt y Sy st e m Failure s.................................................................................... 58 '

. SEP Reference Number 60 Improve Controls Over Surveillance Test Program Number of Missed Surveillance Tests Resulting in Licensee Event Reports........................ 39 4

jEP Reference Number C1 Modify Cortputer Program to Correctly Schedule Surveillance Tests a

- Number of Miesed Surveillance Tests _Resulting in Licensee Evtet Reports......................... 39 SEP Resference Number 62 Estabitch interim System Engineers Te mpc rary M odif icat ions. _...................................

.............................................. 65 a

. Engineering Assistance Request (EAR) Breakdown.:......................................................., 66

- Engin eerin0 Change Notice Status..,................................................................... 67.

Engineering Change Notice Breakdown -............._.._..............

........~.............. 68 '

SEP Reference Number 68 -

Assess Root Cause of Poor Operator Training and Establish Means to Monttor Operator Training.

Licensed Operator Requalification T/aining................................

........................... 73 -

x Uce nse Cand dat e Ex ams................

..........................................................,747 L

- SEP Reference Number 71 Improve Contro!s ovei "emporary Modifications

- Te rrporary Modificw bns.............................~...-~ ~......-~.m...

.. - ~..-.. ~. 65 -

L i

95

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11 4

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.m-REPORT DISTRIBUTION LIST I R. L Andrews 1

-R.E.GQ R. J. Mueller, i

G. L. Anglehart M.J. Guinn M. W. Nichols.

W. R; Bateman G. E. Guliani C. W. Norris -

K. L. Belek K. B. Guliant Nuclear Licensing

.> T. G. Blair E. R. Gundal

& Industry Affairs -

B. H. Biome R. H. Guy -

J. T. O'Connor.

4

- C. N. Bloyd :

R. M. Hawkins W. W. Orr

. J.P.Bobba M. C. Hendrickson L L. P. rent C.' E. Boughter R. R. Henning T. L. Patterson Mc A. Breuer K. R. Henry -

R. T. Pearce C. J. Brunnert J. B. Herman R. L Phelps M. W. Butt G. J. Hill W.J.Ponec-C. A.Carlson K. C. Holthaus L. M. Pulverenti J. W. Chase L G. Huliska T. M. Reisdorft G. R. Chatfield C. J. Husk A. W. Richard A. G. Christensen R. L. Jaworski D. G. Ried A. J. Cla;P R. A.Johansen G. K. Samide y

O. J. Clayton W. C. Jones T.J;Sandene R. P. Clemens '

J. D. Kecy B. A. Schrnidt J. L. Ccnnolley J. C. Kepplar S. T. Schmitz G. M. Cook D. D. Kloock F. C. Scofield M L Core J. C. Knight i t. J. Sefick.

S. H. Crlies D. M. Kobunski J. W. Shannon D. W. Dale G. J. Krause R. W. Short R. C. DeMeulmeester J. G. Krist

. C. F. Simmons.

D. C. Dietz L T. Kusek E.L.Skaggs K.S. Dowdy L E. Labs J. L. Skiles -

J. A. Drahota M. P. Lazar F. K. Smith T. R. Dukarski R. C. Learch R.. L. Sorenson R. G. Eurich R. E. Lewis

' J. A. Spilker

' H. J. Faulhaber R.~ C. Liebentritt K. E, Steele M. A. Ferdig D. L. Lippy _

-W.

Steele -

I F. F. Franco.

B. Lisowyj

11. F. Sterba L

. M. T, Frans -

B. R. Livingston

-G. A. Teeple H. K. Fraser J. H. MacKinnon -

Mc A. Tesari J. F. W. Friedrichsen G. D. Mamoran J. W. Tills '

S. K. Gambhir J. W. Marcil D. R. Trausch

. J. K. Gasper N. L. Martice

P. R. Tumer

- W. G; Gates -

. D. J. Matthews -

J. M. Uhland.

M. O. Gautier J. M; Mattice C. F. Vanecek.'

- S. W. Gebers -

- T. J. Mcivor J.' M. Waszak J. M. Giantz K. S. McCormick G. R. Williams J. T. Gleason R. F. Mehaffey S. J. Willrett

- L. V. Goldberg K. G. Melstad :

W.- C. Woemer D. J. Gokien-.

K. J. Morris D. C. Gor. enco

_ D. C. Mueller ?

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FOR1 CALHOUN STATION OPERATING CYCLES AND REFUELING OUTAGE DATES Ev2nt Dat? Ringe Production (MWH)

Cumulativ3 (MWH)

Cycle 1 09/26/73 -02/01/75 3,299,639 3,299,639 1st Refueling 02/01/75 05/09/75 Cycle 2 05/09/75 10/0t/76 3,853,322 7,152,961 2nd Refueling 10/01/76 12/13/76 Cycle 3 12/13/73 9/3077 2,805,927 9,958,888 3rd Refueling 09/30/77 12;v9/77 Cycle 4 12/09/77 10/14/78 3,020,832 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 01/18/80 06/11/80 Cycle 6 06/11/80 09/18/81 3,899,714 20,768,168 6th Refueling 09/18/01 12/21/81 Cycle 7 12/21/81 - 12/06/82 3,561,866 24,3K,,03I.

71h Refueling 12/06/82 - 04/07/83 Cycle 8 04/07/83 03/03/84 3,406,371 27,736,405 3

8th Refueling 03/03/84 G7/12/84 Cycle 9 07/12/84 09/28/B5 4,741,488 32,477,893 9th Refueling 09/28/85 01/16/86 Cycle 10 01/16/06 - 03/07/87 4,356,753 36,834,646 10th Refueling 03/07/87 - 06/08/87 Cycle 11 06/08/87 09/27/88 4,936,859 41,771,505 lith Refueling 09/27/88 - 01/31/89 Cycle 12 01/31/89 - 02/17/90 3,817,954 45,589,459 12th Refueling 02/17/90 05/29/90 Cycle 13 05/29/90 - 02/01/92 5,4!1,069 51,040,528 13th RefuellnD 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 I

CURRENT PRODUCTION AND OPERATIONS " RECORDS" First Sustained Reaction August 5,1973 (5:47 p.m.)

First Electrk:lty Supp!!ed to the System 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 VWH)

October 1987 Most Productive Fuel Cycle (5,451,069 MWH)(Cycle 13)

May 29,1990 Feb.1,1992

'

ML20128B488

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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