Text

FCS Performance Indicators Rept for Mar 1994
	ML20065R153
Person / Time
Site:	Fort Calhoun
Issue date:	03/31/1994
From:	; OMAHA PUBLIC POWER DISTRICT
To:	;
Shared Package
ML20065R152	List: LIC-94-0090, Forwards FCS Performance Indicators Rept for Mar 1994; ML20065R153;
References
	NUDOCS 9405090365
	Download: ML20065R153 (96)
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l 11 FORT CALHOUN STATION !

PERFORMANCE INDICATORS l

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OMAHA PUBLIC POWER DISTRICT FORT CALHOUN -STATION PERFORMANCE INDICATORS REPORT 4

Prepared By.

Production Engineering Division System Engineering Test and Performance Group ,

1 MARCH 1994 I

FORT CALHOUN STATION MARCH 1994 MONTHLY OPERATING REPORT OPERATIONS

SUMMARY

Fort Calhoun Station operated at a nominal 100% power level through the month of March. Uni-form Rating of Generating Equipment (URGE) testing was successfully completed to demon-strate generating capacity for Midcontinent Area Power Pool (MAPP) annual accreditation.

Normal plant surveillance and maintenance activities were conducted during the month. Mainte-nance activities on the Circulating Water System included complete overhaul of Traveling Screens CW-2E and CW-2F.

Erosion / corrosion holes in Bearing Water Cooler Heat Exchanger CW 6B were repaired. Wall thickness checks are being performed on the other bearing water cooler heat exchanger to iden-tify potential failure points.

Main Feedwater Pump FW-4B was out of service at the end of the month after its motor was ob-served to be sparking and experiencing excessive vibration. The motor required a motor bearing housing alignment and a magnetic center alignment.

Work on the radiation monitor upgrade modification continued through the month.

Preparations are in progress for the reracking of the Spent Fuel Pool (SFP) later in 1994. The new racks will maintain sufficient storage capacity to the year 2007.

~

The following NRC inspections were completed during this reporting period:

IER No. Descrintion 94-05 Motor Operated Valves 94-07 Monthly Resident Inspection 94-08 Special Inspection Regarding ESF Supervisory Relay Failure (LER 94-001) 94-10 Security The following LEE was submitted during this period:

LER No. Descriotion 94-001 Safeguards Actuation and Subsequent ReactorTrip Due to Relay Failure Source: Nuclear Licensmg & Industry Affairs i

Year-To-Date Value Performance Cateaories

. ; l4 y -5 Performance in Industry

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Unplaniied5 iThstrn;([, Upper 10% and better x 1 Unit I ,^ c . $nplann,M. [Aut'6matidi . iPENorMance, than 1994 OPPD goal i

>%(C5ph$!t 4 , JCapabilityk flScramsI7,000i ~ ' ' ' ~ ^J

, (Factotif poss{actoir (HouisCriticali_ <

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Performance Better Than

$Qn gjg 5 . 4 ,7 - [_ ___ , _ . . . . . . . . .

1994 OPPD Goal N_.__

AFW Safety bblSafet/ Fuel Performance Not Meeting HPSI Safety System S9$ts' m Re lh6111-ti -

1994 OPPD Goal System Performance l l3erfoiraance Ibdichlor Performance j i

l

!!!!!l! December January

'93* '94 February

'94 behdtf Collective Volume of Industrial .Uses 1993 Goal l hM j Radiation Low-Level Safety eIdi jg i o Exposure Radioactive Waste Accident Rate March 1994 Year-To-Date i

Value Best Possible i Performance 1994 Year-End Performance INPO PERFORMANCE INDICATORS (Performance for the months of January through March 1994)

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iWhile s 4biltisajx Year-To-Date Value Performance Categories

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'A g . E Performance Better Than Industry Average Trend

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+2Kctdations}L - f% ; _ Performance Better Than 1994 OPPD Goal w% ~

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Performance Not Meeting 1994 OPPD Goal or

% m.. . c.et . Industry Average Trend

" . j;Safetyi ' . Forced 7SysiffMa Outage

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sanssj>@l December January 93* '94 February 94

, gg wg s = ; 3, 'Uses 1993 Goal E E E FY *e March 1994 Mi Year-To-Date

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jpggjggi Radiation '

Performance 1994 Year-End TditINrsjp;6 xposure Performance yv,e wq g

, q NRC PERFORMANCE INDICATORS (Safety System Failures and Significant Events ratings are averages for October 1990 through September 1993. Predictor blocks cannot be generated for these performance indicators g because thsy are based on NRC biannual reports.

All otherindicator values are for the months of January through March 1994.)

FORT CALHOUN' STATION PERFORMANCE INDICATORS REPORT MARCH 1994 -

SUMMARY

POSITIVE TREND REPORT POSITIVE TREND REPORT (continued)

A performance indicator with data representing three Contaminated Radiation Controfled Area consecutive months of improving performance or three (Page 53) consecutive months of performance that is superior to the stated goalis exhibiting a positive trend per Nuclear Operations Division Quality Procedure 37 (NODCP-37). End of Positive Trend Report.

The following performance indicators exhibited positive trends for the reporting month: r Industrial Safety Accident Rate -INN ADVERSE TREND REPORT (Page 2)

A Performance Indicator with data representing 3 con-Disablino iniurv/fliness Frecuencv Rate (Lost Time Acci. secutive months of declining performance; or 3 consecu-dont Rate) tive months of performance that is not meeting the estab-(Page 3) lished goal; or four or more consecutive months of per-formance that is trending towards declining as deter-Recordable Iniurv/111 ness Cases Frecuency Rate mined by the Manager + Station Engineering, constitutes (Page 4) an adverse trend per NOD-OP-37. A supervisor wnose performance indicator exhib.is an adverse trend by this Hioh Pressure Safety Iniection System Safety System definition may specify in written form (to be published in '

Performaneg this report) why the trend is not adverse.

(Page 8)

The following performance Indicators were exhibiting ad-Auxiliarv Feedwater System Safety System Performance verse trends for the reporting month.

(Page 9)

Number of Control Room Eouioment Deficiencies Emeroenev Diesel Generator Unit Reliability (Page 15)

(Page 11) An adverse trend is indicated based on more than 3 con-secutive months of performance not meeting the estab-Diesel Generator Reliability (25 Demands) lished goal of a maximum of 45 deficiencies.

(Page 12)

Unolanned Cacability loss Factor Emeroency Diesel Generator Unreliability (Page 26)

(Page 13) An adverse trend is indicated based on three cx)nsecu-tive months of the year-to-date UCLF exceeding the Fuel Reliabilhv Indicator year-end goal of a maximum of 3.97%.

(Page 14)

Document Revigg Violations Per 1.000 Insoection Hours (Page 55)

(Page 18) An adverse trend is indicated based on more than 3 con- l secutive months with document reviews more than 6 Number of Missed Surveifiance Tests Resuftino in Lic. months overdue.

ensee Event Reoorts :

(Page 20) Temocrarv Modifications (Page 57) '

Forced Outace Rate An adverse trend is indicated based on more than 3 con-(Page 23) secutive months of performance not meeting the estab- l i

Although the FOR has risen in recent months, perfor- lished goal of 0 temporary modifications removable on-mance has been superior to the 1993 and 1994 goals line that are >6 months old, since September 1993.

Sggndary System Chemistry End of Adverse Trend Report.

+

(Page 39)

Maintenance Overtime (Page 48)

Hazardous Waste Produced l (Page 52) l

-l IV i

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FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT MARCH 1994 -

SUMMARY

INDICATORS NEEDING INCREASED MANAGEMENT ATTENTION REPORT A periormance indicator with data for the reporting period Percent of Comoteted Schedukd Maintenance Activrties that is inadequate when compared to the OPPD goal is fAff Maintenance Crafts) defined as "Needing increased Management Attention" (Page 50) per NCD-OP-37. The percent of the number of completed scheduled maintenance activities as compared to the number of The following performance indicators are cited as need- scheduled maintenance activities for the reporting month ing irx:reased management attention for the reporting (76.2%) is below the 1994 monthly goal of 80%.

month:

In-Line Chemietrv Instruments Out-of-service Unit Canab4ity Fador (Page 51)

(Page 25) The number of in-line chemistry instruments out-of-ser-The year-to-date UCF value of 93.5% is below the 1994 vice for the reporting month (7) exceeds the monthly goal year-end goal of a minimum of 96.03%. of a maximum of S.

Unotanned Automatic Reactor Scrams oer 7.000 Hours Crrtical End of Management Attention Report (Page 27)

The par-to-date number of unplanned automatic reactor scrams per 7,000 hours0 days 0 hours 0 weeks 0 months critical (3.29) exceeds the 1994 goalof 0. PERFORMANCE INDICATOR REPORT Unoianned Safety System Actuations -(INPO DefinMion) IMPROVEMENTS / CHANGES (Page 28)

The number of INPO unplannsj safety system actua- This section lists significant changes made to the report tions for 1994 (1) exceeds the goal of 0. and to specific indicators within the report since the pre-vious month.

Unotanned SafeN System Actuations -(NRC Definition)

(Page 29) Annunciator Windows have been revised to include a The number of NRC unplanned safety system actuations " predictor blo&* for some performance indicators. This for 1994 (1) exceeds the goal of 0. block represents the best possible 1994 year-end perfor-mance based on year-to-date values and predicted opti-Eauioment Forced Outaces oer t000 Critical Houm mum performance values for the remainder of the year.

(Page 33) Predictor blocks for other indicators will be developed as The year-to-date number of equipment forced outages information on future performance becomes available per 1,000 critical hours (0.47) exceeds the 1994 year. from data sources.

end goalof 0.20.

Recordable Iniurvminess Cases Frecuency Rate Maintenance Workk)ad Backfoas (Page 4)

(Page 45) This indicator has been revised to show lower rates for The badiog of non-outage Maintenance Work Orders for January and February 1994. This was necessary due to corrective maintenance for the reporting month (451) the Safety Department's reclassification of 2 cases that exceeds the 1994 monthly goal of a maximum of 325. were originally assigned to the month of January.

Ratio of Preventive to Tetal Maintenance & Preventive Emeroency AC Power Safety System Perfnrmance Maintenance frems Overdue (Page 10)

(Page 46) The graph for this indicator has been revised to reflect The percentage of preventive maintenance items over. corrections in January and February 1994 data.

due for the reporting month (0.79%) exceeds the 1994 monthly goal of a maximum of 0.5%. Comoonent Failure Ana!vsis Reoort (CFAR) Summarv (Page 34)

Percentaae of Total MWOs Comoleted oer Month identi The CFAR categories have been revised.

fled as Rework j (Page 47) Check Valve Failure Rate j The percentage of total MWOs completed per month (Page 36) j identified as rework for the reporting month (5.2%) ex. Data and text have been revised. l coeds the 1994 monthly goal of a maximum of 3%.

Maintenance Workload Back!oos (Page 45) l The graphs for this indicator have been revised.

V ,

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PERFORMANCE INDICATOR REPORT IMPROVEMENTS / CHANGES (continued)

Outstandina Modifications (Page 58)

The graph for this indicator has been revised to show the line representing the 1994 year-end goal as declining evenly from 150 in December 1993 towards 80 in De-cember 1994.

Encineerina Chance Notice Status (Page 60)

Graphs for this indicator have been revised.

Enaineerina Chance Notices Ooen (Page 61)

Graphs for this indicator have been revised.

End of Performance Indicator Report improvements /

Changes Report l

vi

i Table of Contents / Summary l

l PAGE !

l GOALS .. . . . . . . . . . . . . . . . . . . . . . . . . . . ..XI '

SAFE OPERATONS PAGE l l

INDUSTRIAL SAFETY ACCIDENT RATE - INPO . . . . . . . . . . . . . . . . .. . . . . 2 DISABLING INJURY /lLLNESS FREQUENCY RATE. 3 RECORDABLE INJURY /lLLNESS CASES FREQUENCY RATE . . . . . . . .. . 4 CLEAN CONTROLLED AREA CONTAMINATIONS 21,000 DISINTEGRATIONS / MINUTE PER PROBE AREA. . . . . . . . . . . . . - . .

.; 5 PREVENTABLE / PERSONNEL ERROR LERs . .. .. .. ..6 SAFETY SYSTEM FAILURES . . . .. . . . -7 SAFETY SYSTEM PERFORMANCE HIGH PRESSURE SAFETY:

INJECTON SYSTEM .. .. .. . .. . .. 8 AUXILIARY FEEDWATER SYSTEM -. .... .. . 9 EMERGENCY AC POWER SYSTEM . . . . . _10 EMERGENCY DIESEL GENERATOR .

UNIT RELIABILITY . . . . . . . . . . .. .. .. .. 1 1 EMERGENCY DIESEL GENERATOR RELIABILITY (25 DEMANDS) .. . . . . . .... . . . . .. .12 EMERGENCY DIESEL GENERATOR UNRELIABILITY - . . . . . . . .. . ... .. .. . .. .. . 13 FUEL RELIABILITY INDICATOR 14 NUMBER OF CONTROL ROOM EOUlPMENT DEFICIENCIES .. . . . . . . . . .. . 15 COLLECTIVE RADIATION EXPOSURE. 16 MAXIMUM INDIVIDUAL RADIATON EXPOSURE- . . . . . . - . . .17 VOLATIONS PER 1,000 INSPECTON HOURS . . .18 SIGNIFICANT EVENTS . . . . . . . . . . . . - . . . . . .. .19 NUMBER OF MISSED SURVEILLANCE TESTS RESULTiNG IN LERS . ;20 PERFORMANCE EAGE STATON NET GENERATON = . -= 22 FORCED OUTAGE RATE - -. =- . . . . . . . . . 23 vii

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PERFORMANCE (continued) PAGE EQUIVALENT AVAll. ABILITY FACTOR.. . . . . .. .. .. . .. 24 I l

UNIT CAPABILITY FACTOR.. . . . . . . . . . . . . . . . 25 l l

UNPLANNED CAPABILITY LOSS FACTOR . . . . . . . . . . . . .. 26 I i

UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7,000 HOURS CRITICAL... . .. .. . . . . . . . . . . - 27 UNPLANNED SAFETY SYSTEM ACTUATONS -(INPO DEFINITON). .. . . . .. . . .. . . . . .. 28 UNPLANNED SAFETY SYSTEM ACTUATONS - (NRC DEFINITON).. .- . 29 GROSS HEAT RATE __ .. .-. . . . . . . . . . .. . 30 THERMAL PERFORMANCE.. . . . . . .. . .. . 31 DAILY THERMAL OUTPUT .. .. . .. . .. .. . .. .. . 32 EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS .. . . . . . -- .. . . . . . . .. . 33 COMPONENT FAILURE ANALYSIS REPORT (CFAR) SUMt.ta.RY ; ., . . . .. . . . . . . . .. . 34 REPEAT FAILURES. . . .. . =35 CHECK VALVE FAILURE RATE .. .. .. . .. . ... .. . .. .. 3 6 VOLUME OF LOW-LEVEL SOLID RADIOACTIVE WASTE 37 PRIMARY SYSTEM CHEMISTRY PERCENT OF HOURS OUT OF LIMIT - . . . . . . . . . . . . . . 38 CHEMISTRY INDEX/ SECONDARY SYSTEM CHEMISTRY _ . . . . . . . . . . . . . . .. .. . . . 39 COST PAGE CENTS PER KILOWATT HOUR . . . . ., . . . . . . . . . . ... .. . 41 STAFFING LEVEL.. . ... . . . . . . . . . . . . . . . . . . . . 42 SPARE PARTS INVENTORY VALUE.. .. . . . . .. 43 DIVISON AND DEPARTMENT PERFORMANCE INDICATORS PAGE MAINTENANCE WORKLOAD BACKLOGS (CORRECTIVE NON. OUTAGE).... .. . . .. . 45 viii

DIVISON AND DEPARTMENT PERFORMANCE INDICATORS (continued) PAGE RATIO OF PREVENTIVE TO TOTAL MAINTENANCE

& PREVENTIVE MAINTENANCE ITEMS OVERDUE . . . . . . 46 l

PERCENTAGE OF TOTAL MWOs COMPLETED PER MONTH IDENTIFIED AS REWORK.. .. .. . . 4 7 '

MAINTENANCE OVERTIME .. .. . . . . . . . .~. .. . 48 -

PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE).. . . . . . . . . . .. . 49 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (ALL MAINTENANCE CRAFTS).. ._ . . . . 50 IN LINE CHEMISTRYINSTRUMENTS OUT-OF-SERVICE ,, . . . . :51 HAZARDOUS WASTE PRODUCED . . . . . . . . . 52 CONTAMINATED RADIATION CONTROLLED AREA .. . .. .. . 53 RADIOLOGICAL WORK PRACTICES PROGRAM.. . . . .. . . 54 DOCUMENT REVIEW. ...

. . . . . 55 LOGGABLE/ REPORTABLE INCIDENTS (SECURITY) . . . - . . . . . . . . . 56 TEMPORARY MODIFICATIONS.. .. .. ..~ . 57 OUTSTANDING MODIFICATIONS . . . . . . . . . . . . 58 ENGINEERING ASSISTANCE REQUEST (EAR) BREAKDOWN. = 59 ENGINEERING CHANGE NOTICE STATUS : . . . . . .. .. . . . . . .60 ENGINEERING CHANGE NOTICE BREAKDOWN . . . ... =61 LER ROOT CAUSE BREAKDOWN .. .. .. .. . .. .62 LICENSED OPERATOR REQUALIFICATION TRAINING . . _ _ 63 L! CENSE CANDIDATE EXAMS . .. .. . . . .- . . . 64 OPEN CORRECTIVE ACTION REPORTS AND INCIDENT REPORTS . . . . . . .. . . 65 MWO PLANNING STATUS (CYCLE 16 REFUELING OUTAGE) . . . . . . . . . . . . .... . . 66 PROGRESS OF CYCLE 16 MODIFICATION PLANNING . . .67 PROGRESS OF 1994 ON-LINE MODIFICATION PLANNING .. . .. 68 lx

43 --

ACTON PLANS. DEFINITONS. SEP INDEX & DISTRIBUTION LIST PISE ACTION PLANS FOR ADVERSE TRENDS .. .. ... .. ... .. . . . . .. .. .. .. 69 PERFORMANCE INDICATOR DEFINITIONS . .71 SAFETY ENHANCEMENT PROGRAM INDEX .._ .. . .. .. .. 78 REPORT DISTRIBUTION LIST.. . . . . . . . . 80 N

X

OPPD NUCLEAR ORG ANI7;ATION GOALS Vice President - 1994 Priorities MISSION The safe, reliable and cost effective generation of electricity for OPPD customers through the professional use of nuclear technology. The Company shall conduct these operations prudently, efficiently and effectively to assure the health, safety and protection of all personnel, the general public and the environment.

GOALS Goal 1: SAFE OPERATIONS To ensure the continuation of a " safety culture" in the OPPD Nuclear Program and to provide a professional working environment, in the control room and throughout the OPPD nuclear organi-zation, that assures safe operation so that Fort Calhoun Station is recognized as a nuclear indus-try leader.

1994 Priorities:

Improve SALP ratings.

Improve INPO rating.

Reduce NRC violations with no violations more severe than level 4.

No unplanned automatic reactor scrams or safety system actuations.

Goal 2: PERFORMANCE To strive for Excellence in Operations utilizing the highest standards of performance at Fort Calhoun Station that result in safe, reliable plant operation in power production.

1994 Priorities:

Improve Qur.lity, Professionalism, and Teamwork.

Improve Plant Reliability.

Meet or exceed INPO key parameters and outage performance goals.

Reduce the number of human performance errors.

Identify programmatic performance problems through effective self assessment.

Goal 3: COSTS Operate Fort Calhoun Station in a manner that cost effectively maintains nuclear generation as a viable source of electricity.

1994 Priorities:

Maintain total O & M and Capital expenditures within budget.

Streamline work processes to improve cost effectiveness.

l l

a Goals Source: Scofield (Manager) I Xi 1

SAFE OPERATIONS Goal: To ensure the continuation of a " safety culture" in the OPPD Nuclear Program and to provide a professional work-ing environment in the control room and throughout the OPPD Nuclear Organization that assures safe operation so that Fort Calhoun Station is recognized as a~ nuclear indus-try leader.

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1

1 i

-+-- Year-to-Date INPO Industrial Safety Accident Rate

-O-- Fort Calhoen Year-End Goal ( 0.50)

--C}- Industry Upper 10%

0.6 - 1995 INPO todustry Goal ( 0.50) 0.5 - D- 0 0 0 0 0 0 0 0 0 0 0 0.4-0.3 -

0.2 -

0.1-C 0 0 , 0 , O i , , , , , , , , ,

Jan94 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec94 INDUSTRIAL SAFETY ACCIDENT RATE-INPO As stated in INPO's December 1993 publication ' Detailed Descriptions of World Asso-ciation of Nuclear Operators (WANO) Performance Indicators and Other Indicators for Use at U.S. Nuclear Power Plants': "The purpose of this indicator is monitor progress in improving industrial safety performance for utility personnel permanently assigned to the station. Accident rate was chosen by INPO as the personnel safety indicator over other Indicators, such as the injury rate or severity rate, because the criteria are clearly de-fined, utilities currently collect this data, and the data is least subjective."

The INPO industrial safety accident rate value year-to-date was 0.0 at the end of March 1994. The value for the 12 months from April 1,1993 through March 31,1994 was 0.51.

The values for this indicator are determined as follows:

(number of restricted-time + lost-time accidents + fatalities) X 200.000 (number of station person-hours worked)

The 1994 Fort Calhoun year-end goalis 50.50. The 1995 INPO industry goalis 5;0.50.

The approximate industry upper ten percentile value (for the period from 1/93 through 12/93) is 0.12.

Data Source: Sorensen/Skaggs (Manager / Source) ;

Chase / Booth (Manager / Source) ;

Accountability: Chase / Conner i Positive Trend i l

2 I

1 j

-@- 1994 Disabling injury / Illness Frequency Rate X 1993 Disabling injury / Illness Frequency Rate l GOOD l <

-O-- V Fort Calhoun Year-End Goal ( 0.5) 1.2 -

L 1-0.8 -

0.6 -

C O O O O 'O 0.4 -

0.2 -

0 , _ , O , , , , , , , , , ,

Jan94 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec94 DISABLING INJURY /lLLNESS FREQUENCY RATE (LOST TIME ACCIDENT RATE)

This indicator shows the 1994 disabling injury / illness frequency rate. The 1993 dis-abling injury / illness frequency rate is also shown.

The disabling injury / illness frequency rate year-to-date was 0.0 at the end of March 1994. There were no lost time accidents reported for March.

The disabling injury / illness frequency rate for the 12 months from April 1,1993 through March 31,1994 was 0.13.

The 1994 Fort Calhoun year-end goal for this indicator is a maximum value of 0.5.

l Data Source: Sorenson/Skaggs (Manager / Source)- j

-l Accountability: Chase / Conner i Positive Trend SEP 25, 26 & 27 j i

~

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5- -@-- 1994 Recordable Injury / Illness Frequency Rate

--X-- 1993 Recordable injury / Illness Frequency Rate IGOODI 4.5 -

V

-O-. 1994 Fort Calhoun Year End Goal ( 1.5) 3.5 -

3-2.5 -

2-1.5 - C O O O O O O q 1- Y A 0.5 -

0 . , . , , , , , , , , , , ,

Jan94 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec94 RECORDABLE INJURY /lLLNESS CASES FREQUENCY RATE This indicator shows the 1994 recordable injury / illness cases frequency rate. The 1993 recordable injury / illness cases frequency rate is also shown.

A recordable injury / illness case is reported if personnel from any of the Nuclear Divi-sions are injured on the job and require corrective medical treatment beyond first aid.

The recordable injury / illness cases frequency rate is computed on a year-to-date basis.

The recordable injury / illness rate year-to-date was 1.10 at the end of March 1994.

There were 2 recordable injury / illness cases, a finger laceration and a knee strain, reported forthe month of March. There have been a total of 2 recordable injury / illness cases in 1994.

The recordable injury / illness rate for the 12 months from April 1,1993 through March 31,1994 was 1.40.

The 1994 Fort Calhoun year-end goal for this indicator is a maximum value of 1.5.

Data Source: Sorenson/Skaggs (Manager / Source)

Accountability: Conner Positive Trend SEP 15,25,26 & 27 4

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

Contamination Events l GOOD l

- - Fort Calhoun Year-End Goal ( 65) y 75 -

70-65 - C O O O O O O O O O O O 60-3 55-550-i Lu 45-

.E40- '

N 35- '

l30-

$25-U 20-15- ,

10-5- {

0 i i i i i i , i i i ,

i '

Jan94 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec94 ~

CLEAN CONTROLLED ' AREA CONTAMINATIONS 21,000 DISINTEGRATIONS /

MINUTE PER PROBE AREA ;

9 This indicator shows the Personnel Contamination Events in the' Clean Controlled Area for contaminations 21,000 disintegrations / minute per probe area for the reporting month.

There were 3 contamination events in March 1994. There has been a total of 14 con- ;

tamination events in 1994. !

The 1994 year-end goal for this indicator is a maximum of 65 contamination events.

l Data Source: Chase /Little (Manager / Source) >

Accountability: Chase /Lovett Adverse Trend: None SEP 15 &' 54 5

, ww -

--5-- Preventable (18 Month Totals)

-O- Personnel Error (18 Month Totals)

@ Personnel Errors (Each Month) 40-35-30-25- ,

20-15- - E ~

10-5-

0 N A R m

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, m m s c 3 o, ' m '

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a f a' %$ 4 2 8 8 8 8 8 Q u.

PREVENTABLE / PERSONNEL ERROR LdRs This indicator depicts 18 month totals for numbers of " Preventable" and " Personnel Error" LERs.

The graph shows the 18 month totals for preventable LERs, the 18 month total for Personnel Error LERs and the Personnel Error totals for each month. The LERs are trended based on the LER event date as opposed to the LER report date.

In February 1994, there was 1 event that was subsequently reported as an LER. No LERs were categorized as Preventable or Personnel Error.

The total LERs for the year 1994 (through February,1994) is 1. The total Personnel Error LERs for the year 1994 is 0.

The 1994 goals for this indicator are that the year-end values for the 18 month totals be no more than 12 Preventable and 5 Personnel Error LERs. (Note: Because this indica-tor is based on an 18 month period, the 1994 year-end totals willinclude LERs occur-ring in 1994 and the last 6 months of 1993.)

Data Source: Short/Cavanaugh (Manager / Source)

Accountability: Chase Adverse Trend: None SEP 15 6

1 1

@ Operation lGOODI g O Shutdown

~

- PWR Average Trend E

dy2- -

I $5 y $

1-Q g 0 i i i i i i i i 91-4 92-1 92-2 92-3 92-4 93-1 93-2 93-3 Year-Ouarter SAFETY SYSTEM FAILURES This indicatorillustrates the number of NRC Safety System Failures as reported by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data in the biannual" Performance Indicators for Operating Commercial Nuclear Power Reactors" report. .

The following NRC safety system failures occurred between the fourth quarter of 'i991 and the third quarter of 1993:

First Quarter 1992: 1) Defective control switches in the 4KV switchgear could have rendered safety equipment inoperable. 2) All 4 channels of the SG DP trip for RPS had been calibrated nonconservatively. This occurred due to an incorrect procedure which specified a tolerance band that was too wide.

Second Quarter 1992: Fuse and breaker coordination problems for the DC buses could cause a loss of the entire bus if a fault occurred on one of the loads.

First Ouarter 1993: The SG low pressure scram signal block reset values, for all 4 channels of both SGs, were greater than the allowed limits, rendering this scram input inoperable during certain operating conditions.

Second Quarter 1993: A section of the piping configuration for the borated water source of the safety injection system was not seismically qualified. This could have resulted in a failure of the system to meet design requirements during a seismic event.

Data Source: Nuclear Regulatory Commission Accountability: Chase Adverse Trend: None 7

i

Q 1994 Monthly High Pressure Safety injection System Unavailability Value

-M- 1994 High Pressure Safety injection System Unavailability Value Year-to Date

-O- 1994 Fort Calhoun Goal ( 0.004) 1995 INPO Industry Goal (0.02)

-O- Industry Upper 10% (0.0011) 0.02- a a a a a a a a a a a A l GOOD l 0.015 - y 0.01 -

0.005 -

C O O O O O O O O O O O 0.00036 g g g g g g g g g g g g i 50 , , , , .. , , , , , , , , , ,

1993 Unavailability Value Jan94 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec94 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 the month of March 1994 was 0.00049. There was 1.1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of planned unavailability for surveillance tests and no hours of unplanned unavailability during the month. The 1994 year-to-date HPSI unavailability value was 0.00017 at the end of March. The unavailability value for the last 12 months was 0.00034.

There has been 1.1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of planned unavailability (for surveillance tests) and no hours of unplanned unavailability for the HPSI system in 1994.

The 1994 Fort Calhoun year-end goal for this indicator is a maximum value of 0.004.

The 1995 INPO industry goal is 0.02 and the industry upper ten percentile value (for the three year period from 1/91 through 12/93) is approximately 0.0011.

Data Source: Jaworski/Schaffer Accountability: Jaworski/Schaffer Positive Trend 8

@ Monthly Auxiliary Feedwater System Unavailability Value 1994 Auxiliary Feedwater System Unavailability Value Year-to-Date lGOODI j

--O- 1994 Fort Calhoun Goal ( 0.01)

V

--b-- 1995 INPO Industry Goal ( 0.025)

-D- Industry Upper 10% (0.0029) 0.025 - A A A A A A- A A A A A A 0.02-0.015 -

0.01 - C O---C O O O O O O O O O U

i D si

,0 h, k , ik

, , , i i , , , , , ,

1993 Unavailability Value Jan94 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec94 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 March 1994 was 0.0016.

There was a total of 2.45 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months of planned unavailability (due to work on FCV-1369) and no hours of unplanned unavailability during the month. The year-to-date unavail-ability value was 0.0015, and the value for the last 12 months was 0.0021 at the end of March.

There has been a total of 3.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months of planned unavailability and 2.76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months of unplanned unavailability for the auxiliary feedwater system in 1994.

The 1994 Fort Calhoun year-end goal for this indicator is a maximum value of 0.01.

The 1995 INPO industry goal is 0.025 and the industry upper ten percentile value (for .

the three year period from 1/91 through 12/93) is approximately 0.002.

Data Source: Jaworski/Nay l

Accountability: Jaworski/Nay Positive Trend l

9 I

B Monthly Emergency AC Power Unavailability Value

-se- Emergency AC Power Unavailability Value Year-to Date

-O- Fort Calhoun Goal lGOODI

-A- 1995 INPO Industry Goal (0.025)

-O- Industry Upper 10% (0.004) 0.07-0.06 -

0.05-0.04 -

% = = = = = = = = =

0.01 - ;

O i i i i i i i i a i i Jan94 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec94 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 March 1994 was 0.0066.

During the month, there were 9.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months of planned unavailability for testing, and no hours of unplanned unavailability. The Emergency AC Power System unavailability value year-to-date was 0.025 and the value for the last 12 months was 0.007 at the end of March. The large unavailability value for February is due to maintenance outages on both diesel generators.

There has been a total of 103.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months of planned unavailability (for surveillance tests and maintenance) and 6.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months of unplanned unavailability for the emergency AC power system in 1994.

The 1994 Fort Calhoun year-end goal for this indicator is a maximum value of 0.025. ;

The 1995 INPO industry goal is 0.025 and the industry upper ten percentile value (for !

the three year period from 1/91 through 12/93) is approximately 0.004.

l Data Source: Jaworski/Ronning Accountability: Jaworski/Ronning Adverse Trend: None 10 ;

l l

@ Number of Failures /20 Demands --5-- Trigger Values for 20 Demands O Number of Failures /50 Demands Trigger Values for 50 Demands

@ Number of Failures /100 Demands --

Trigger Values for 100 Demands 8- l lG00DI

+

6-Y T Y Y Y Y Y Y Y Y Y Y 4-

= = = = = = = = = =

2 2 2 2- g 7

$g $ b 1 1 1 1 1 1 1 1 1 1 -

< y m e ; m e 00 I( 00 f 00 $ 00 1 00 #

00 :' 00 3 00 I 60 ! 00 i OO E 00 [

0 , , , --, , , , , , , , ,

Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 EMERGENCY DIESEL GENERATOR UNIT RELIABILITY This bar graph shows three monthly indicators pertaining to the number of failures that were reported during the last 20,50, and 100 emergency diesel generator demands at the Fort Calhoun Station. Also shown are trigger values which correspond to a high level of confidence that a unit's diesel generators have obtained a reliability of greater than or equal to 95% when the failure values are below the corresponding trigger val-ues. The Fort Calhoun 1994 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, including all start-only demands and all start demands that are fol lowed by load-run demands, whether 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 test expected to carry the plant's load and duration as stated in the test specifications, and a special test in which a diesel generator was expected to be operated for a mini-mum of one hour and to be loaded with at least 50% of design load (see exceptions and other demand criteria in the Definition Section of this report).

Data Source: Jaworski/Ronning (Manager / Source)

Accountability: Jaworski/Ronning Positive Trend 11

l O DG 1 Failures /25 Demands l GOOD l E DG-2 Failures /25 Demands V

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

4- C O O O O O O O O O O O 3-2-

1-00 00 00 00 00 00 00 00 00 00 00 00 l I I i i i i i i i i l-Apr93 May Jua Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 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 1994.

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 approved 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 not experienced any failures during the last 25 demands on the unit.

Data Source: Jaworski/Ronning (Manager / Source)

Accountability: Jaworski/Ronning Positive Trend 12

O DG-1 Unreliabi!ity Value

@ DG-2 Unreliability Value lGOODI

-+-- Station Unreliability Value

~

Industry Upper 10% (0.002 for 0.0025-. a Three Year Average) 0.002 - O O O O O O O O O O O O 0.0015 -

0.001 -

0.0005 -

0,0 0,0 0,0 0,0 0,0 0,0 0,0 0,0 0,0 0,0 0,0 0,0 v g v g y v g v l v g v l v v v v v 3 g l g g g Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 EMERGENCY DIESEL GENERATOR UNRELIABILITY The purpose of this indicator is to monitor the likelihood that emergency AC power generators will respond to off-normal events or accidents. it also provides an indication of the effectiveness of maintenance, operation and test practices in controlling genera-tor unreliability.

The year-to-date station EDG unreliability value at the end of March 1994 was 0.0. The 1994 goal for this indicator is a maximum value of 0.05.

For DG-1: There was 1 start demand for the reporting month without failure.

In addition, there was 1 load-run demand without failure.

For DG-2: There was 1 start demand for the reporting month without failure.

In addition, there was 1 load-run demand without failure.

Emergency diesel generator unreliability is calculated as follows:

value per DG = SU + LU - (SU x LU) where SU = Start Unreliability = number of unsuccessful starts number of valid start demands LU = Load-run Unreliability = number of unsuccessfulload-runs number of valid load-run demands Station Value = average of DG-1 and DG-2 values Data Source: Jaworski/Ronning (Manager / Source)

Accountability: Jaworski/Ronning Positive Trend 13

5 Fuel Reliability Indicator 10-

--O-- 1994 & 1993 Fort Calhoun Goals +

E 8-E C O O O O O j Cycle 15

.g 6 - Refueling g g * * *

g Outage g , 3 3

.!! 4-lE 7

o 2- e 0

I i I i i i i 6 4 4 6 I Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 FUEL RELIABILITY INDICATOR The Fuel Reliability Indicator (FRI) value for March 1994 was 2.015 X 10-4 microcuries/

gram. The purpose of the FRl is to monitor industry progress in achieving and maintain-ing a high level of fuelintegrity. The March FRI value, which is less than the zero defect threshold value, discussed below, indicates a defect free core. The plant operated at full power during the entire month. The March FRI was calculated based on the aver-age fission product activities present in the reactor coolant during the steady state full power operation days, March 1 through 31. -

The March FRI value of 2.015 X 104 microcuries/ gram is comparable to the February value of 0.931 X 104 microcuries/ gram. The very low FRI value will see a wide range of values due to many outside factors (i.e., which chemist analyzes the sample can pro-vide a significant shift in the data point).

Fission product activity data from March full power operation show no Xenon-133 activ-ity increase and no iodine spiking due to fuel defects. The last detected fuel failure was during Cycle 13.

The INPO September 1992 Report " Performance Indicators for U.S. Nuclear Utility Industry" (INPO No.92-011) states that "...the 1995 industry goal for fuel reliability is that units should strive to operate with zero fuel defects. A value larger than 5.0 X 104 microcuries/ gram indicates a high probability of unit operation with one or more fuel defects. The determination of current defect-free operation requires more sophisticated analysis by utility reactor engineers." The value of 5.0 X 104 microcuries/ gram is de-fined as a " Fuel Defect Reference" number or a "Zero Leaker Threshold". Each utility will calculate whether the core is defect free or not. The 1994 Fort Calhoun Station FRI performance indicator goal will be to maintain a monthly FRI below 5.0 X 10-4 microcu-ries / gram. ;

i Data Source: Holthaus/Guliani j Accountability: Chase /Spilker Positive Trend 14

l l

O Control Room Equipment Deficiencies Repairable On-Line !

lGOODI -

@ Total Number of Control Room Equipment Deficiencies V

80- -O- Fort Calhoun Goat For Total Equipment Deficiencies 70- -

60- - T -

- - T S0 -

I : - -

- F C C C C C C C C C' C C C 40- ,7 ,; _

) ,

30- */

. / : -

, '. / /

20- '

5: [ f

, , [ [ '

10-0

[

['

[

k

[ '

I,<

', k'

, , , , i i , , , , , ,

Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 Q Operator Work Around items Repairable On-Line O Total Number of Operator Work Around items 10- -O- Fort Calhoun Goal for Total Operator Work Around items 8-

~

C O O O O O O O O O O O 4-7 0

l i i i l i i I 4 1 6 i Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 NUMBER OF CONTROL ROOM EQUIPMENT DEFICIENCIES This indicator shows the number of control room equipment deficiencies that are repair-able during plant operations (on-line), the total number of control room equipment defi-ciencies, the number of Operator Work Around (OWA) Items repairable on-line, the total number of OWAs and the Fort Calhoun goals.

There was a total of 70 control room equipment deficiencies at the end of March 1994.

37 of these deficiencies are repairable on-line and 33 require a plant outage to repair.

There was 1 deficiency added and 2 deficiencies were completed during the month.

There were 2 identified Operator Work Around items at the end of the month.

The 1994 Fort Calhoun monthly goal for this indicator is a maximum of 45 deficiencies and 5 OWAs.

Data Source: Chase / Tills (Manager / Source)

Accountability: Chase /Faulhaber Adverse Trend: An adverse trend is indicated based on more than 3 consecutive months of performance not meeting the established goal.

15 1

I O Monthly Personnel Radiation Exposure (Non Spent Fuel Rerack)

-@-- Personnel Cumulative Radiation Exposure (Non-Spent Fuel Rerack) l GOOD]

--O-- Fort Calhoun Annual Goal ( 44 Person Rem) ,

b40- C O O O O O O O O O O O o~ 30 -

g 20-g 10- ,

3 g0 -

Jan94 Feb M ar Apr May Jun Jul Aug Sep Oct Nov Dec04

@ Monthly Personnel Radiation Exposure for Spent Fuel Rerack l GOOD l

- Personnel Cumulative Radiation Exposure for Spent Fuel Rerack V

-O-- Fort Calhoun Annual Goal ( 23 Person-Rem)

E

$l: C O O O O O O O O O O O s1: -

S : i : .

, . . , , , , , . i Q- Jan94 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec94 COLLECTIVE RADIATION EXPOSURE The 1994 Fort Calhoun goal for collective radiation exposure, excluding the spent fuel rerack, is less than 44 person-Rem.

The exposure for March 1994 was 1.516 person-Rem.

The year-to-date exposure was 4.580 person-Rem at the end of March.

The Fort Calhoun goal for collective radiation exposure to complete the Spent Fuel Rerack is less than 23 person Rem.

The Spent Fuel Rerack exposure for March was 0.055 person-Rem.

The Spent Fuel Rerack exposure year-to-date was 0.099 person-Rem at the end of March.

The collective radiation exposure at the end of March (i.e., the sum of non-spent fuel rerack expocure and spent fuel rerack exposure) was 4.679 person-Rem. The collec-tive radiation exposure for the last 12 months was 155.5 person-Rem at the end of March.

The 1995 INPO industry goal for collective radiation exposure is 185 person-rem per year. The industry upper ten percentile value (for the three year period from 1/91 through 12/93)is approximately 110.5 person-rem per year. The yearly average for Fort Calhoun Station for the three years from 4/91 through 3/94 was 150.9 person-rem per year.

Data Source: Chase /Little (Manager / Source)

Accountability: Chase /Lovett Adverse Trend: None SEP54 16 l

O Highest Exposure for the Month (mrem) .

O Highest Exposure for the Year (mrem) 5000 -

OPPD 4500 mrem /yr. Limit 4000 -

3000 -

E E

2000 -

Fort Calhoun 1,000 mrem /yr. Goal 1000 -

298 ~

0 March 1994 MAXIMUM INDIVIDUAL RADIATION EXPOSURE During March 1994, an individual accumulated 91 mrem, which was the highest indi-vidual exposure for the month.

The maximum individual exposure for the year was 298 mrem at the end of March.

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

year. The 1994 Fort Calhoun year-end goalis a maximum of 1,000 mrem. ;

Date Source: Chase / Utile (Manager / Source) i Accountability: Chase /Lovett [

Adverse Trend: None l

17

l I

4- Violations per 1,000 Inspection Hours g l GOOD l S --O-- Fort Calhoun Goal Y 3.03

( i l

~E l 82-o.

N _

lB3i ~

1.4 : C O O O O O O O O n l' i i 0 , , , , , , , , , , , ,

92 '93 Mars 3 Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb94 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 in-volved with collecting and processing the data.

The violations per 1,000 inspection hours indicator was reported as 1.34 for the twelve months from March 1,1993 through February 28,1994. -

The following inspections ended during this reporting period:

IER No. Title No. of Hours 94-05 MOV Phase 11 Inspection 120 94-07 Resident Monthly inspection 480 94-08 Special Inspection - Supv. Relays 120 94-10 Security 40 To date, OPPD has received 1 violation in 1994:

Level ill Violations (0)

Level IV Violations (1)

Level V Violations (0)

Non-Cited Violations (NCV) (0)

The 1994 Fort Calhoun goal for this indicator is a maximum of 1.4 violations per 1,000 inspec-tion hours.

Data Source: Short/Cavanaugh (Manager / Source)

Accountability: Short I Positive Trend l 18 l 1

l

)

Q 'NRC Significant Events lGOODI

- Industry Average Trend Y 2-1

~

@ sa 0 i i i i i e i i 91-4 92-1 92-2 92-3 92-4 93-1 93-2 93-3 Year - Quarter

@ INPO Significant Events (SERs) l GOOD]

V 2

2-0 i i

/////b i i i Y e h i i f i 91-4 92-1 92-2 92-3 92-4 93-1 93-2 93-3 93-4 Year - Quarter SIGNIFICANT EVENTS This indicator illustrates the number of NRC and INPO Significant Eve'nts for Fort Calhoun Station as reported by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data in the biannual" Performance Indicators for Operating Commercial Nuclear Power Reactors" report and INPO's Nuclear Network.

The following HBG significant events occurred between the fourth quarter of 1991 and the third quarter of 1993:

Third Quarter 1992: The failure of a Pressurizer Code safety valve to reseat initiated a LOCA with the potential to degrade the reactor coolant pressure boundary.

The following INPO significant events, as reported in Significant Event Reports (SERs), oc-curred between the fourth quarter of 1991 and the fourth quarter of 1993:

Second Quarter 1992: Intake of Transuranics during Letdown Filter Change-out.

Third Quarter 1992: 1) RC-142 LOCA; and 2) Premature Lift of RC-142.

First Quarter 1993: Inoperability of Power Range Nuclear instrumentation Safety Channel D.

Second Quarter 1993: SBFU Breaker Relay (Switchyard) Plant Trip Fourth Quarter 1993: Unexpected CEA Withdrawal.

Data Source: Nuclear Regulatory Commission & INPO Accountability: Chase Adverse Trend: None 19 i

3-

@ Number of Missed STs Resulting in LERs 2-1-

ff 0 0 0 0 0 0 0 0 0 0 0 0 0 i i i i i i i i i i i a a i i

'92 '93 Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 NUMBER OF MISSED SURVEILLANCE TESTS RESULTING IN LICENSEE EVENT REPORTS This indicator shows the number of missed Surveillance Tests (STs) that result in Lic-ensee Event Reports (LERs) during the reporting month. The graph on the left shows the yearly totals for the indicated years.

There were no missed surveillance tests resulting in LERs during March 1994.

During the month of January 1993 it was discovered that during December 1992 an ASME Section XI Code required surveillance was not completed not corrective mainte-nance performed as a result of AC-10A falling into the " Alert Range" (LER 93-003 Fail-ure to Satisfy inservice Testing Requirements for Raw Water Pump).

The 1994 Fort Calhoun monthly goal for this indicator is 0. '

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

Accountability: Chase /Jaworski Positive Trend SEP 60 & 61 20

PERFORMANCE Goal: To strive for Excellence in Operations utilizing the highest standards of performance at Fort Calhoun Station that result in safe, reliable plant operation in power produc-tion.

i l

21

50 -

B Net Generation (10,000 Mw hours) 40-35.03 35.12 34.6 e 31.21 RE2 MW; cycie is 33 58 g g j30- {y 28.01 shh uta e 27.8 2

3 i .. e c.1 . ,. n 25.03 Mt .. . " '

w.. 3g (:/t : C . .'

o 19,94 [.- .u c r. t;t hg f" 8 20- 4%

o :

? : .. .-: ..

e:i?[h p mi ;,.

a

..'l . 1. . . .f:if ['. .l ',

jp{ '

10- L: - 9 U '

?; f ,.l l j. .gf ff Q 0 i 4 i i i i 6 1 4 4 i i Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 STATION NET GENERATION During the month of March 1994 a net total of 362,151 MWH was generated by the Fort Calhoun Station. Cumulative net generation for Cycle 15 was 1,337,740 MWH at the end of the month.

Energy losses for the month of February 1994 were attributable to a generator and reactor trip that occurred following the failure of the relay for the Containment High Pressure Supervisory Circuit. Energy losses for the month of January 1994 were attrib-utable to derates to repair condenser tubes and a failed level control valve on a heater drain tank. ,

Energy losses for the month of December 1993 were a result of a forced outage that began on December 6 and ended on December 7. The outage was caused by an EHC test failure. Energy losses for September, October and November 1993 were attribut-able to the shutdown for the Cycle 15 refueling outage, which began on September 25 and ended on November 26.

Unplanned energy losses forthe months of June and July 1993 were attributable to a forced outage that began on June 24 when the inadvertent jarring of a 345 KV fault relay in the switchyard caused a turbine and reactor trip. The plant retumed to 100%

power on July 2nd.

Planned energy losses for the months of April and May 1993 were the result of a main-tenance outage.

Data Source: Station Generation Report Accountability: Chase Adverse Trend: None 22

Forced Outage Rate 1GOODI 12%- --O- Fort Calhoun Goal ( 2.4%) y 10.1 10%-

8%-

6%_ Cycb 15 Refueling Outage 4%-

C O O O O O O O O O O

~

1.38 f 91 '92 $3 Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 FORCED OUTAGE RATE The forced outage rate (FOR) was reported as 2.06% for the twelve months from April 1,1993 to March 31,1994.

A forced outage occurred on February 11 due to a generator and reactor trip that oc-curred following the failure of the relay for the Containment High Pressure Signal Super-visory Circuit. The generator was off-line for 48.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months .

A forced outage occurred on December 6,1993 when the plant tripped during weekly testing of the turbine EHC system. The generator was off-line for 27.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . There was one forced outage during the month of June 1993. This outage, which occurred when the inadvertent jarring of a 345 KV fault relay in the switchyard caused a turbine -

and reactor trip, lasted 70.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The 1994 Fort Calhoun year-end goal for this indicatoris a maximum value of 2.4%

The 1993 Fort Calhoun year-end goal was a maximum value of 2.4%

Data Source: Monthly Operations Report & NERC GAD Forms Accountability: Chase Positive Trend 23

o Monthly EAF Year-to-Date Averago Monthly EAF k l GOOD l 's

-ll9- Industry Median Value (76.7%)

100 % -

,,, - Cycle 15 - T~

85.6 g

Refueling g (V Outage q

[ k(

4 76.2 80%- L- T ~ ~

E E h G-G-G-G-G--E M-0-G-Bas gpp ; - a ; ;,

60.8 h **~ ,>

h g k n

ex

y p g y$kh] s ? M w

am sy; 4 , m M .m " g 2 :,

hf h3 w;- y g

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y if g g ya AO% ~ ~ _

y&

< Gy 'M je g

, -, u e

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$ogl4 ,g g

. m y a M

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W !!$$$ h w 4,,

$ !$ " ? N

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b? Q@

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ig 7

8 i 8 i i i i i i i e i a i i i

'91 '92 '93 Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 EQUIVALENT AVAILABILITY FACTOR This indicator shows the plant monthly Equivalent Availability Factor (EAF), the year-to-date average monthly EAF, and the year-end average monthly EAF for the previous 3 years.

The EAF for March 1994 was reported as 100%. The year-to-date monthly average EAF was 94.2% at the end of the month.

Energy losses for the month of February were due to a generator and reactor trip that occurred following the failure of the relay for the Containment High Pressure Signal Supervisory Circuit. Energy losses for the month of January were due to derates for condenser tube repair and a failed level control valve on a heater drain tank.

The April, May and June 1993 EAF values are the result of a maintenance outage and a forced outage that occurred when the inadvertent jarring of a 345 KV fault relay in the switchyard caused a turbine and reactor trip.

The industry median EAF value for the three year period from 7/90 through 6/93 was 76.7%. The Fort Calhoun average monthly EAF for the three years prior to this report was 75.1%.

Data Source: Dietz/Parra (Manager / Source)

Accountability: Chase Adverse Trend: None 24 !

l l

O Monthly Unit Capability Factor Year-to-Date Unit Capability Factor

--+- 36 Month Average Unit Capability Factor 4

'(

-O-- Fort Calhoun Goal l GOOD l 1995 INPO Industry Goal ( 80%) j industry Upper 10% (86.7% for a Three Year Average) 100 % - xx- xr

. . . =- m 4 4 60%-

o-6 g fjg fgf 6-5l%-yM_V d Cycle 1s N $

N 2 5 iff$fI f 40% -

M%-

h g fEf fp @k ph g lI r- e Refueling Outage

g g -

g g h[f{p 0%

W i i

i e

zh i

i i e

kW i

i i

h i

Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 )

UNIT CAPABILITY FACTOR This indicator shows the plant monthly Unit Capability Factor (UCF) value, the 1994 and 1993 year-to-date UCFs, the goals, the 36 month average UCFs, the 1995 INPO indus-try goal and the approximate industry upper ten percentile value. UCF is defined as the ratio of the available energy generation over a given period of time to the reference energy generation (the energy that could be produced if the unit were operated continu- l ously at full power under reference ambient conditions) over the same time period, expressed as a percentage.

The UCF for March 1994 was reported as 100.0%. The year-to-date UCF was 93.5%,

the UCF for the last 12 months was 75.3%, and the 36 month average UCF was re-ported as 75.8% at the end of March.

Energy losses for the month of February 1994 were due to a generator and reactor trip that occurred following the failure of the relay for the Containment High Pressure Signal Supervisory Circuit. Energy losses for the month of January were due to derates to repair condenser tubes and a failed level control valve on a heater drain tank.

Energy losses for the month December 1993 were due to rampup from the Cycle 15 Refueling Outage and a plant trip that occurred on December 6 during testing of.the EHC system. Energy losses for the month of June 1993 were due to Moderator Coeffi-cient Testing and a forced outage from June 24 through June 27.

The 1995 INPO industry goal is 80% and the industry upper ten percentile value (for the three year period from 1/91 through 12/93) is approximately 86.7%. The 1994 Fort Calhoun year-end goal for this indicator is a minimum of 96.03%.

Data Source: Generation Totals Report & Monthly Operating Report Accountability: Chase Adverse Trend: Although the year-to-date UCF has been below the 1994 year-end goal for three consecutive months, an adverse trend is not indicated based on planned operation at 100% power for the remainder of the year.

O Monthly Unplanned Capability Loss Factor Year-to-Date Unplanned Capability Loss Factor 60%- lGOODI

--O- Fort Calhoun Goal 9

50% - 1995 INPO Industry Goal ( 4.5%)

4o%- Industry Upper 10% (1.48% for a Three Year Average) 30% - Cycle 15 Flefueling Outage 20%-

5 5 -

1 o%- $ % $

o%

c

, C 0 is--c

,^,

o ,o -

o 5-3

,~

gn 7

Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 UNPLANNED CAPABILITY LOSS FACTOR This indicator shows the plant monthly Unplanned Capability Loss Factor (UCLF), the year-to-date UCLF, the goal, the 1995 INPO industry 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 full power under reference ambi-ent conditions), expressed as a percentage. -

The UCLF for the month of March 1994 was reported as 0.0%. The year-to date UCLF was 6.5%, the UCLF for the last 12 months was 5.1%, and the 36 month average UCLF was reported as 8.4% at the end of March.

Unplanned energy losses for the month of February 1994 were due to a generator and reactor trip that occurred following the failure of the relay for the Containment High Pressure Signal Supervisory Circuit. Unplanned energy losses for the month of January were due to derates to repair condenser tubes and a failed level control valve on a heater drain tank.

Unplanned energy losses for the month of December 1993 were the result of a plant trip that occurred during EHC testing. Uqplanned energy losses for the month of June 1993 were the result of a forced outage that occurred as a result of the inadvertent jarring of a 345 KV fault relay in the switchyard.

The 1995 INPO industry goal is 4.5% and the industry upper ten percentile value (for the three year period from 1/91 through 12/93)is approximately 1.48%. The 1994 Fort Calhoun year-end goal for this indicatoris a maximum value of 3.97%.

Data Source: Generation Totals Report & Monthly Operating Report Accountability: Chase Adverse Trend: An adverse trend is indicated based on 3 consecutive months of the year-to-date UCLF exceeding the year-end goal of s3.97%.

26

l

- FCS Reactor Scrams Per 7,000 Hours Critical (Year-to-date)

-+- FCS Reactor scrams Per 7,000 Hours Critical (for the last 36 months) ,

--O- 1994 & 1993 Fort Calhoun Goals 1995 lNPO Industry Goal Industry Upper 10% (011 per 7,000 hours0 days 0 hours 0 weeks 0 months critical over a 36 rnonth time period) 6-5-

4-3-

,r . . . .4 0

'~

0 o,<[-

b $ $

,-o,-c

$ 0 $ b i o i o,-o,-c 6 o, d

- e oi%

b Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 3 5 Numberof FCS Reactorscrams Ref li

,2- Outage j j i

0 0 (ii j 0 i

0 i

g 1

0 i

0 0 i

m i 0 m 0 i i 6 i e i i 90 91 92 93 Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 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 12/92 publication " Detailed Descriptions of Interna-tional Nuclear Power Plant Performance Indicators and Other Indicators") for Fort Cal-houn Station. The lower graph shows the number of unplanned automatic reactor scrams that occurred during each month for the last twelve months.

The 1994 station value is 3.29 at the end of March 1994. An unplanned automatic reactor scram occurred on February 11 when supervisory relay 868/CPHSS failed. The ;

value for the 12 months from April 1,1993 through March 31,1994 is 2.98. The value for the last 36 months ir I

i An unplanned automatic reactor scram occurred or: December 6,1993 during EHC I testing. An unplanned automatic reactor scram occurred on June 24,1993 when the ,

inadvertent jarring of a 345 KV fault relay in the switchyard caused a turbine and reactor trip.

The 1994 Fort Calhoun monthly goal for this indicator is 0. The 1995 INPO industry goalis a maximum of 1 unplanned automatic reactor scram per 7,000 hours0 days 0 hours 0 weeks 0 months critical.

The industry upper ten percentile value is approximately 0.51 scrams per 7,000 hours0 days 0 hours 0 weeks 0 months critical for the 36 month time period from 1/91 through 12/93.

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

Accountability: Chase Adverse Trend: None 27

3-

@ Safety System Actuations (INPO Definition)

O Fort Calhoun Goal 'x 1 O Industry Upper 10 Percentile 2-1 1-l Cycle 15 ;qe

] Refueling i Outage g ,

$ h '

5 m i

O i

i i

0 io m ,m , m , m , m , m , m ., m , m , m 4

, m , c, .

'91 '92 '93 Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 -'

UNPLANNED SAFETY SYSTEM ACTUATIONS -(INPO DEFINITION) i There were no INPO unplanned safety system actuations during the month of March 1994.

There was 1 INPO unplanned safety system actuation during the month of February.

1994. It occurred on February 11 when supervisory relay 868/CPHSS failed, which !

resulted in tripping relay 86B/CPHS. The CPHS relay trip actuated the Safety injection ;

Actuation Signal, Containment Isolation Actuation Signal, Ventilation isolation Actuation Signal and Steam Generator isolation Signal. The' Steam Generator isolation Signal automatically closed both main steam isolation valves, which resulted in a concurrent turbine and reactor trip.

An INPO unplanned safety system actuation occurred during the month of July 1992.' It '

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

The 1994 Fort Calhoun goal for this indicator is 0.

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

Accountability: Jaworski/Foley/Ronning Adverse Trend: None 28 i

p

- 12 Month Running Total SSAs (NRC Definition)

--+-- Critical Hours

@ Safety System Actuations (NRC Definition) 4 10- 1000

-900 ,

$ cycie is -800 j RefueEng Omage

- 700 e

$ 6- -600 8 f, - 500 E

[ 4 -. - 400 f 2 g -300 o g ] 2 -- - 200

, , , , o , ,

'91 "32 '93 Cycle 14

[AMJ JASONDJ FMAMJJASONDJFM 1992 1993 1994 RefueEng Outage 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 Emer-gency Diesel Generators. The NRC classification of SSAs includes actuations when major equipment is operated and when the logic systems for these safety systems are challenged.

There was 1 NRC unplanned safety system actuation during the month of February 1994, it occurred on February 11 when supervisory relay 86B/CPHSS failed, which resulted in a concur-rent turbine and reactor trip.

There were 3 NRC unplanned safety system actuations in 1993: 1) In December 1993 the main turbine and reactor tripped during Electro-Hydraulic Control pump start testing; 2) In June 1993 the inadvertent jarring of a 345 KV fault relay in the switchyard caused a turbine and reactor trip; and 3) In April 1993 a non-licensed operator mistakenly opened the wrong potential fuse drawer, causing a low voltage alarm on bus 1 A1, a loadshed on ous 1 A1 and an auto start of an EDG.

There were 4 unplanned safety system actuations in 1992: 1) In August, due to the failure of an AC/DC converter in the Turbine Electro Hydraulic Control system, pressurizer safety valve RC-142 opened prior to reaching design pressure during a plant transient and trip; 2) On July 3 there was an inverter failure and the subsequent reactor trip; 3) On July 23 there was an unplanned diesel generator start when an operator performing a surveillance test inadvertently pushed the normal start button instead of the alarm acknowledge button; and 4) In May the .

turbine generator tripped on a false high level moisture separator trip signal which caused a simultaneous reactor trip and subsequent anticipatory start signal to both diesel generators.

There have been 4 unplanned safety system actuations in the last 12 months. The 1994 Fort .I Calhoun goal for this indicatoris 0. )

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

Accountability: Jaworski/Foley/Ronning Adverse Trend: None 29 i

G Monthly Gross Heat Pate

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

g

)

V l C 1994 &1993 Fort Calhoun Goals l 10.5-10177

[

x :-

- g g Refueling m

" g Outage

' y ; qxn m :n :

5

( '@ b l.jg -(n4 di m10- % ~ M % M M M O M %g m

8 df

? >?

Qa "2.Uf 1l .n TQa M

y, :f: 4 st g n. +

W QQ N W Ehi sq M4 $p; @::: : %

L.;

9.5 -

Q M) f[ $M ib Q 17 ;-.,

. c .g ..--

p.;g p v.

d '; (ifl Iff hlp*.

g. 7g aj p:; g7 h/ #

f(f(( hi fih - bl 3; i i 9 d@li $$

e s i i i a i i i i i i i i 91 '92 '93 Apr93 May Jun Jul Aug Sep Od Nov Dec Jan Feb Mar 94 GROSS HEAT RATE This indicator shows the Gross Heat Rate (GHR) for the reporting month, the year-to-date GHR, the goals and the year-end GHR for the previous 3 years.

The gross heat rate for Fort Calhoun Station was 10,039 for the month of March 1994.

The 1994 year-to-date GHR was 10,072 at the end of the month.

The GHR was not calculated for the months of October and November 1993 because of the Cycle 15 Refueling Outage.

The GHR varies with fluctuations in river water temperature. In general, the GHR im-proves during the winter months and degrades during the summer. This is because the gross heat rate is not normalized to the design river water temperature of 60 degrees Fahrenheit.

The 1994 Fort Calhoun year-end goal for this indicator is s10,190.

Data Source: Holthaus/ Gray (Manager / Source)

Accountability: Chase /Jaworski Adverse Trend: None 30

O Monthly Thermal Performance 1

- Year-to-Date Average Monthly Thermal Performance I k 'S l

-O- 1994 & 1993 Fort Calhoun Goals l GOOD l

- + - - 1995 INPO Industry Goal ( 99.5%)

a industry Upper 10% (99.9%)

100 % - , , , , , , , _

M d# $1 Thermal .e. %. c. - in @ PC Perform.

value noi D

M Q

N - gw 7 Q

?

L

C Q-- C P

w 99%- required ,

'( y y) Cycle 15 h ~

Of .

\ -" 9 ; Refueling *y ,

trendable ; : / ; ; Outage ?. i i r i Y d below _

, j p: ;. ;g 80% ~g j js 3 g .y n d 3; k Q,$

98 %

P **'

i i ,

8 '

4 al ,

D ,

Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 THERMAL PERFORMANCE This indicator shows the Thermal Performance value for the reporting month, the year-to-date average thermal performance value, the 1994 and 1993 Fort Calhoun goals, the 1995 INPO industry goal and the approximate industry upper ten percentile value.

The thermal performance value for March 1994 was 99.3%. The year-to-date average monthly thermal performance value was 99.2% at the end of the month. The average monthly value for the 12 months from April 1,1993 through March 31,1994 was 99.5%.

The low thermal performance value for February 1994 is attributable to level control problems on heaters 3A and 58, and to spring runoff resulting in screen carryover and condenser fouling. Improvements made during the month of March are: warm water recirc. was taken off-line; some recovery in condenser performance was achieved due to backwashing at regular intervals; and the level control problems for heater 3A were corrected.

The 1994 Fort Calhoun year-end goal for this indicator is 99.5%. The 1993 Fort Cal-houn Goal was a minimum of 99.4%. The 1995 INPO industry goalis 99.5% and the industry upper ten percentile value (for the one year period from 1/93 through 12/93) is approximately 99.9%.

Data Source: Jaworski/Popek Accountability: Jaworski/Popek Adverse Trend: The definition of an adverse trend cannot be applied to this perfor-mance indicator because the inherent nature of this parameter will decline gradually over time. Actual performance so far in 1994 is improved over 1993 on an average of 0.3% (1.53 MWe).

31-

O ThermalOutput

-O- Fort Calhoun 1495 MW Goal .

ke 4

- Tech Spec 1500 MW Limit 1500 1499.5-1499-1498.5 -

1498 -

1497.5-1497- ,

1496.5 - M

^

1496- ,

u, [jijh <

.. wc .

1495.5-

+

ch & W ~J -

" ~ 4f ,

@ , \gp.. ,

,3, 1495< )-

, egm , ...,

g*3 wp 1494.5- ~ aM _ .# .w.:

e

',.,. ,<.eg%,

L e +.

e > s -

, m, :4 7

~, , < . , nr .,

'W m; e' p'i s" 1494- ,. '

x

,, i

"~sO ~ 4;n <

9s Js GU.:

7.T

..... e 3 ." ':T5 ^ %

"W s + :. <

3

-' "Q::l

M., ,

1493.5- ', ,' naA> iO~$.?M , '

'M gv-g r s > re

_' m~ - ,

5.

+ r c:. . %.

y,..,.y

/ +

,_:m.pn ca

^^

f .- d,.,,,-p.r# I 3, v >

'( ::.T:.,

1f.Mgm,j. - A 1493-

-< ' -mde ->

s <

m.

!;i.%

yGi.

g 4lgf- [s'"

w : .. , l ggl},

R:g.

' _ g'7,',

ip' t l ' Q$;ih* , ,-

< e~ m:;p.3.

, p 1492.5- 3

w. . :

g; - . , . . . . .

r,p;.

w M

g:<.

(gay < N,.w:.;fy

.u .

x xe pf'W "

'A.1 3:' , , , . , , bsy : [L': t 1492- 4 f"' [:'>

bW' : , f[# ^

S. ' ~ "[O i

.c.., 2:9

.y. ^

.;;;[

m ,

s..,

, < > < yg ,.

s

. =y

y, , 8 .x - <: ,.

. g-,:: .

> .,.x , s w. : g'y x <>

1491.5- -

, m <

-. f* #p. . < '

%, g . h@..w 'W ,j' <,:.

ou ,.

f, >

' w ,,. ~.;.

% ..n

' :?p':>

' L- x

., :.x -

4 : 2 ::-

, x,;48.;; m' '..

1491 - '

9 -

m:

-.~

+

I':N ,.S(:l,.

';* A.'".;

e "r 3

1490.5- -

J' M ,-

1-gg:;. - , -

> - m:.,

nw %::, -.

O " l{ hp , ,

1490 i i i i i i i i e i i i i i i e iiiiiiiiiiiii 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 DAILY THERMAL OUTPUT The thermal output graph displays the daily operating power level during March 1994, l the 1500 thermal megawatt average technical specification limit, and the 1495 thermal !

megawatt Fort Calhoun goal.

Data Source: Holthaus/ Gray (Manager / Source)

Accountability: Chase / Tills l Adverse Trend: None 32

I~

--t$- Equipment Forced Outage Rate /1,000 Critical Hours

-O- 1994 Fort Ca!houn Year End Goal (02) \(

0.75 -

0.5 0.5 -

025-O -C O O--C O O O O O O O O

3 8 ' i 0 ., , , , , , , , , , , ,

31 '92 93 Jan94 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec94 EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS The equipment forced outage rate per 1,000 critical hours was 0.47 for the months from January through March 1994. An equipment forced outage occurred on February 11, 1994 when the plant experienced an unplanned automatic reactor trip as a result of the failure of the supervisory relay 86B/CPHSS. The value for the 12 months from April 1, 1993 through March 31,1994 is 0.14.

An equipment forced outage occurred in August 1992 and continued through Septem-ber. It was due to the failure of an AC/DC converter in the Turbine Electro Hydraulic Control System.

The 1994 Fort Calhoun year-end goal for this indicator is a maximum value of 0.20.

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

Accountability: Chase /Jaworski Adverse Trend: None 33

1

of Cornponent Categoiies

]

i 40 _ -+- # of Application Categories ,.

l

'i I 35- -*- Total # of Categories j m 30 -

.g .

25 25 -

cm j 20-T: Wh

!o ol' - -

-v-5-

0 , , , , , , , , , , , ,. , , , , , ,

092 N D92 J93 F M A M J J A S O N D93 J F M94 E WearOut/ Aging D Other Devices 8 Manufacturing Defect O Maintenance / Action 2.7%

8.0% 0 Engineering / Design @ Error / Operating Action 5.3%

40.0 %

_ $ Percent of Total Failures During the -

Past18 Months

, gg x

, hh , ' ' '

,o L. & ,

37.3 %

/ h 6.7tdllll ..

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 July 1992 through December 1993). Fort Calhoun Station reported a higher failure rate in 7 of the 87 component .

categories (valves, pumps, motors, etc.) during the past 18 months. The station reported a higher failure rate in 7 of the 173 application categories (main steam stop valves, auxiliary / .

emergency feedwater pumps, control element drive motors, etc.) during the past 18 months.

The pie chart depicts the breakdown by INPO cause categories (see the " Definitions" section of this report for descriptions of these categories) for the 90 failure reports that were submitted to INPO by Fort Calhoun Station during the past 18 months. Of these, the failure cause was known for 75. The pie chart reflects known failure causes.

Data Source: Jaworski/ Edwards (Manager / Source) .;

Accountability: Jaworski/ Edwards j Adverse Trend: None 34 i

I

I l

1

Components With More Than One Failure !

X Components With More Than Two Failures V i 25-20-15 15-11 11 11 11 11

~ ' ' '

10- g g 8 6

5- 4 1 1, 1, 0

Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 REPEAT FAILURES .

The Repeat Failures Indicator (formerly called tt e " Maintenance Effectiveness" perfor-mance indicator) was developed in response to p.uidelines set forth by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (NRC/

AEOD). The NRC requirement for a Maintenance Effectiveness Performance Indicator has been dropped, but statica management considers it useful to continue to track repetitive component failures using the Nuclear Plant Reliability Data System (NPRDS).

This indicator shows the number of NPRDS components with more than 1 failure during the last eighteen months and the number of NPRDS components with more than 2 failures during the last eighteen months.

During the last 18 reporting months there were 7 NPRDS components with more than 1 failure.1 of the 7 had more than 2 failures. The tag number of the component with more than 2 failures is AC-10C. Recommendations and actions to correct these repeat component failures are listed in the quarterly Component Failure Analysis Report.

1 Data Source: Jaworski/ Edwards (Manager / Source)

Accountability: Chase I Adverse Trend: Nnne i 1

l 35

I l

l Calculated Check Valve Failure Rate per Million Component Hours jgl Calculated Industry Check Valve Failure Rate per Million Component Hours k \

3- '

--O- Fort Calhoun Goal 2.5 - g ;

)q 2- C O O O O O O O O v4N h i 1 .5-

,f tu i

3 y

) 4-h 0.5 -

i i

b i i 0 , , , , , , , , , , , ,

'91 '92 '93 Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 No. of 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 average. The failure rates are based on submitted failure reports for an 18 month time interval. They do not include failure reports outside of the 18 month time interval. The interval starts 21 months prior to the current month and ends 3 months prior to the current month. For example, the March 1994 Component Failure Analysis Report (CFAR) covers the 18 month interval from June 1,1992 through November 31,1993. This delay is due to the time involved in collecting and processing failure report data.

The actual number of NPRDS reportable check valve failures at Fort Calhoun Station are shown above on the graph at the left side of the page.

For March 1994, the CFAR provided the following failure rates:

Fort Calhoun Station 0.585 E-6 l

Indust.af (excluding FCS) 1.81 E-6 {

The recent increase in the FCS failure rate is due to two reportable failures of RC-374; one occurred in October and another in November 1993.

l The 1994 Fort Calhoun monthly goal for this indicator is 51.75 E-6. I l

Data Source: Jaworski/ Edwards (Manager / Source)

Accountability: Jaworski/Rollins Adverse Trend: None SEP 43 36 ,

l

O Radioactive Waste Buried This Month (in cubic feet)

Cumulative Radioactive Waste Buried lGOODI (

-O-- Fort Calhoun Goal For Waste Buried (500 cubic feet) V

--a-- 1995 INPO Industry Goal (3,884 cubic feet)

-O- industry Upper 10% (1,045.12 cubic feet) 600 -

C O O O O O 450 -

300--

150 - M fE 4/Mg ,

gj Jan94 Feb Mar Apr 'May Jun94 VOLUME OF LOW-LEVEL SOLID RADIOACTIVE WASTE This indicator shows the volume of the monthly radioactive waste buried, the cumulative annual total for radioactive waste buried, the Fort Calhoun and INPO goals, and the approximate industry upper 10%.

Arnount of solid radwaste shipped off-site for processing during March (cubic feet) 0.0 Volurne of Solid Radwaste Buried during March (cubic feet) 187.8 Cumulative volurne of solid radioactive waste buried in 1994 (cubic feet) 276.2 l Arnount of solid radioactive waste in temporary storage after July 1,1994 (cubic feet) 0.0 1

A graph will be added to this indicator in July 1994 to depict the amount of solid radioac-tive waste in temporary storage.

The 1994 Fort Calhoun goal for the volume of solid radioactive waste which has been buried is 500 cubic feet. The 1995 INPO industry goalis 110 cubic meters (3,884 cubic feet) per year. The industry upper ten percentile value from 1/91 through 12/93 is approximately 29.59 cubic meters (1,045.12 cubic feet) per year. I l

i Data Source: Chase /Breuer (Manager / Source)

Accountability: Chase /Lovett Adverse Trend: None SEP 54 37 l

E Primary System Chemistry Percent of Hours Out of Limit .

I G000i]

--O- 1994 & 1993 Fort Calhoun Goals v 3%-

2%- O O O O O O C Cycb 15 Refueling Outage Wa '

6 Apr93 May I i Jun i

Jul i

Aug r Ii1 Sep 4

Oct Nov

't Dec -Jan i t Feb Mar 94 t

PRIMARY SYSTEM CHEMISTRY PERCENT OF HOURS OUT OF LIMIT The Primary System Chemistry Percent of Hours Out of Umit indicator tracks the pri-mary system chemistry performance by monitoring six key chemistry parameters. The key parameters are: lithium, dissolved oxygen, chlorides, fluoride, hydrogen and sus-pended solids.100% equates to all six parameters being out of limit for the month.

The Primary System Chemistry Percent of Hours Out of Umit was 0.0% for the month of ,

March 1994.

The 1994 and 1993 Fort Calhoun monthly goals for this indicator are a maximum of 2%

Hours Out of Umit.

Data Source: Smith / Spires (Manager / Source)

Accountability: Chase / Smith Adverse Trend: None I

38 l

I

@ Secondary System CPI 2-

[ GOOD l

-O- Fort Calhoun Goal 1.9 -

4 1.8 -

1.7 -

1.6 -

1.5 - C O O O O O O O O O O O 1.4-1.3 -

g 1.2 - l -

1.1-1 i i i a i i i i i i i i Jan94 Feb Mar Apr May Jun Jul Aug Sep. Oct Nov Dec94 SECONDARY SYSTEM CHEMISTRY Criteria for calculating the Secondary System Chemistry Performance Index (CPI) are:

1) The plant is at greater than 30% power; and 2) the power is changing at less than 5%

perday.

The CPI for March 1994 was 1.20. The year-to-date average monthly CPI value was 1.31 at the end of March.

The CPI for December 1993 was 1.92. This relatively higher number was due primarily to iron transport following the plant startup.

The 1994 Fort Calhoun monthly goal for the CPI is a maximum value of 1.5.

The CPI calculation is different from that reported in 1993 in that it reflects the recent INPO revision to the calculation. This revision addresses the penalties for the beneficial effect of attemative chemistry, i.e., morpholine, such as used at Fort Calhoun Station, and focuses more on specific impurities.

Data Source: Smith / Spires (Manager / Source)

Accountability: Chase / Smith l Positive Trend 39

COST Goal: To operate Fort Calhoun Station in a manner that cost effectively maintains nuclear generation as a viable source of electricity.

40

~

- Actuals -[}- Budget -*-- Plan 3.75 -

3.5 -

I 3:

I 3.25 -

E 3-2.75 -

2.5 , , , , , , , , , , , , , , , , , , ,

D91 D92 D93 J94 F M A M J J A S O N 094 D95 D96 D97 D98 Months CENTS PER KILOWATT HOUR The purpose of this indicator is to quantify the economical operation of Fort Calhoun Station.

The cents per kilowatt hour indicator represents the budget and actual cents per kilo-watt hour on a 12 month rolling sverage for the current year. The basis for the budget curve is the approved 1993 and 1994 revised budget. The basis for the actual curve is the Financial and Operating Report.

The December 31 amounts are also shown for the prior years 1991,1992 and 1993. In addition, the report shows the plan amounts for the years 1995 through 1998 for refer-ence. The basis for the dollars are the Nuclear Long Range Financial Plan and the 1994 Corporate Planning and Budget Review. The basis for the generation is provided by Nuclear Fuels.

The unit price is averaging higher than budget due to a shortfall in February's genera- l tion and a moderate overage in March's expenses. I l

Data Source: Scofield/Jamieson (Manager / Source)

Accountability: Scofield Adverse Trend: None l

O Actuai civision staffing

@ Authorized Division Staffing 500 -

452 453 400 - m 7.x s y

f.c 7.1 f......-:.;.

E : ;7'i ...:a I .L :J. ? ': .h 300 -

{ l 200 - k .. 4..k. 191 191 4c. <a .

ymnawa y;i . :.

. . ; c.!. h

Y$hkk 3

411 ~ 116 117 100 -

p+.

.I

;g fhj ; Atg 2:; . aa Ws.-

' kN 9$

ktO m p N!:;)jkYI ww a 3

l $2N$

O "' **' 1 gg;

""A 6 .

l .'- .I Nuclear Operations Production Engineering Nuclear Services STAFFING LEVEL The authorized and actual staffing levels at the end of March 1994 are shown for the three Nuclear Divisions.

Data Source: Ponec (Manager & Source)

Accountability: Ponec Adverse Trend: None SEP 24 -

i 42

.. - - . . . . . -- - . . . .. . - - --. . . . = . . -

e

- Spare Parts inventory Value ($ Million) 17- Cycle 15 Refueling Outage 16-15-14-13-12-11 -

10 i , , , , ',

Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 SPARE PARTS INVENTORY VALUE The spare parts inventory value at the Fort Calhoun Station at the end of March 1994 was reported as $15,433,538.

Data Source: Steele/Huliska (Manager / Source)

Accountability: Willrett/McCormick Adverse Trend: None 43

l DIVISION AND

~

DEPARTMENT PERFORMANCE INDICATORS These indicators may be deleted from this report if the responsible group con-tacts the Manager - Station Engineering to request their removal. Indicators referencing SEP ltems require documentation to ensure that the original intent and scope of the SEP item will not be altered by removal of the Indicator from this report.

l l

l 44

O Corrective Maintenance @ Non-Corrective / Plant improvements O Preventive Maintenance O Fort Calhoun Goal 800 776

= = .

700- =

600 -

500 -

p W

400- /7 300-200-C O O O O O O O O O O g

'7 .

Apr93 May i

rm , m , R . PZ Jun tu , R , m , m , rm . M i Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 Non-Outage Maintenance Work Order Backlog O TotalMwos B MWOs Which Exceed Maintenance Completion Goals 120-100-80- Data for this graph was not available for March due to establishment of the new priority system.

60 -

40-20- >3 >14 days 80 0

d ys days s s s a n e Priority 1 . Priority 2 Priority 3 Priority 4 Priority 5 Priority 6 Non-Outage Maintenance Work Order Aging MAINTENANCE WORKLOAD BACKLOGS This indicator shows the backlog of non-outage Maintenance Work Orders remaining open at the end of the reporting month. It also includes a breakdown by maintenance classification and priority. The 1994 goal for this indicator is less than 325 non-outage corrective MWOs. To ensure that the MWO backlog is worked in a timely manner, non-outage maintenance completion goals have been established as:

Goal Priority 1 Emergency N/A Priority 2 Immediate Action 3 days Priority 3 Operations Concem 14 days Priority 4 Essential Corrective 90 days Priority 5 Non-Essential Corrective 180 days Priority 6 Non-Corrective /Piant improvements N/A l

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

Accountability: Chase /Faulhaber l

Adverse Trend: None SEP 36 l 45 l l

1 1

I

@ Ratio of Preventive to Total Maintenance 100% -

'~'~ ~

90%- ~

80%- IE S $3 ;" 4 -

N

a 2' 70%-

60%-

5+

' h' '

M 5

ys 'd

(

g 7

(; $ h'~ .i" 4; 50%- g {*

g h 'E ps "gg g I E[

40%- Ks

.m <

M <<-

.~

^

'i ^ >

sg%. vt mm > ^

4- ,

30%-

x .4 ,

'pg s .,.._s ft ;gy i% g! !$ # %g 7 Ns::

20%- (% ,

p@]

7 *

$g? 'g g

$g

J*

p M

gg g 10%- ps 4 n gj *Ns A >

x *

7 ya % g ,

0%

Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan feb Mar 94 2%- Preventive Maintenance items Overdue GOOD

-O- Fort Calhoun Goal V

1%- Data Unavailable O.- O. - - -C O O O due to Cycle ,,o g g 15 Refueling 3 _

' .i i i Outage S 0% i i a i e i i i i i i i Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 RATIO OF PREVENTIVE TO TOTAL MAINTENANCE & PREVENTIVE MAINTENANCE ITEMS OVERDUE The top graph shows the ratio of completed non-outage preventive maintenance to total completed non-outage maintenance.

The ratio of preventive to total maintenance was 60.8% in March 1994.

The lower graph shows the percentage of preventive maintenance items overdue.

During March,636 PM items were completed. 5 of these PM items (0.79% of the total) were not completed within the allowable grace period.

The 1994 Fort Calhoun monthly goal for the percentage of preventive maintenance items overdue is a maximum of 0.5%.

Accountability: Chase /Faulhaber Data Source: Chase /Schmitz/Meistad (Manager / Sources)

Adverse Trend: None SEP 41 46

i l

Rework As identified By Planning or Craft j l

-O- Fort Calhoun Goal !

5.2%

5%- Cycle 15 Refueling Outage 4.56 % #Nn gjlgy o

C C C f hh

$4%- lr

, i nye l MM 3

p 3%- 2.7 W

'b-2.57 % 2.58 % E$i 3 2.38 % _

h[b h ? -

h ihh$

02%- ll i 8

&M g -l [I '

p"gg l

$ g $ kOk

! i'

,!f i 1.06 %

g f

., ._ _. >s i i i i i a i Sep93 Oct Nov Dec Jan Feb Mar 94 PERCENTAGE OF TOTAL MWOs COMPLETED PER MONTH IDENTIFIED AS REWORK This graph indicates the percentage of total MWOs completed per month identified as rework. Rework activities are identified by maintenance planning and craft.

The 1994 Fort Calhoun monthly goal for this indicator is <3%. I Data Source: Faulhaber/Schmitz (Manager / Source) l l

Accountability: Chase /Faulhaber '

Adverse Trend: None 47

80*/. -

5 Maintenance Overtime 70%- X Month Average Maintenance Ovedime l GOOD l 3

-O-- Fort Calhoun "On-Line" Goal k ,

60%-

50%- Cycb15 '

Refueling Outage '

40%-

30%- i l l }

l I 20%-

4 :

10%- ll - o o v C C O 1Q --C 0 f .

0% l l " A i '

i i i i i i i i i i i i Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 MAINTENANCE OVERTIME The Maintenance Overtime indicator monitors the ability to perform the desired mainte-nance activities with the allotted resources.

The percent of overtime hours with respect to normal hours was reported as 6.0% for the month of March 1994. The 12 month average percentage of overtime hours with respect to normal hours was reported as 12.0% at the end of the month.

The 1994 Fort Calhoun monthly "on-line" goal for this indicator is a maximum value of 10%.

Data Source: Chase /Schmitz (Manager / Source)

Accountability: Chase /Faulhaber Positive Trend 48

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

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

@ Closed irs Related to the Use of Procedures (Maintenance) !

E Procedural Noncornpliance irs (Maintenance) l J

2-l 4

l 1- 1 1

e 000 00 000 000 000 0 0 0 , , , , , ,

0 000 000 000 000 00 ,

Apr93 May Jun Jul Aug Sep ,

Oct Nov Dec Jan Feb Mar 94 i PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)

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

There were no procedural noncompliance incidents for maintenance reported for the month of March 1994. There was 1 open IR related to the use of procedures (IR 940123) for the month. The incident involved an individual entering the RCA without logging on the access control computer.

There was 1 procedural noncompliance incident (IR 930225) reported in September 1993.

Data Source: Chase / Keister (Manager / Source)

Accountability: Chase / Conner-Adverse Trend: None SEP 15,41 & 44 49

e. - , ,_e

l

@ Completed Scheduled Activities (All Crafts)

Q Numberof Emergent MWOs Completed O Fort Calhoun Goal m

110 100% - !

100 u k 9W'~

- 90 5 8 80% - A ^ a

, O E

- 80

! 70%- Data Not S ' 65 .- - 70

.E 60%- Available // Ma** '// O

/

%:1 i />

fY jIfl7iW

$N/I[//

- 60 3 u 5%- jg$ ; /;: l 2

( r // ;

,pp 50 g

$ 40%-

?

@8 M I[I < ,

fN :

h j $hgl'(( - 40 b g 30%- h t < rtM '/< #

3%su '

dllbl b'//, ff; j - 30 g u) g 20%-

A

/

&y L

/

m

~

7

gggq T.jp; jf - 20 0 5 10% - hhI M

e

[I 10 $

o 0% ,

< < 3[$ RtlEE hh: m 3[3 0 , , 0 December '93 January February March '94 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (ALL MAINTENANCE CRAFTS)

This indicator shows the percent of the number of completed scheduled maintenance activities as compared to the number of scheduled maintenance activities concerning all Maintenance Crafts. Maintenance activities include MWRs, MWOs, STs, PMOs, cali-brations, and miscellaneous maintenance activities. The number of emergent MWOs completed for the month is also shown.

The percent of the number of completed scheduled maintenance activities as compared to the number of scheduled maintenance activities for March 1994 was 76.2%. Also, there were 71 emergent MWOs completed during the month.

Due to the Cycle 15 Refueling Outage, data for this indicator was not available until after the first month on-line during Cycle 15.

The 1994 Fort Calhoun monthly goal for completed scheduled maintenance activities is 80%.

Data Source: Chase /Schmitz (Manager / Source)

Accountability: Chase /Faulhaber Adverse Trend: None SEP 33 50

@ Number of instruments Out-of-Service l GOOol

--O-- Fort Calhoun Goal y 24 -

20-18 17 17 Cycle 15 16- Refueling 14 .

Oumge 12- .

11 8- -

7 0 - '

i i

1:,8' i

i i

g M

O 6 i e i i Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 IN-LINE CHEMISTRY INSTRUMENTS OUT-OF-SERVICE This indicator shows the total number of in-line chemistry systeni instruments out-of-service at the end of the reporting month. The chemistry systems involved in this indi-catorinclude the Secondary System and the Post Accident Sampling System (PASS).

At the end of March 1994 there were 7 in-line chemistry instruments out-of-service.

There were no instruments out-of-service from PASS.

The trend for PASS instruments for this reporting period has not changed. The trend for Secondary instruments this reporting period has increased from 1 to 7. The blowdown sample panel had 2 instruments out-of-service, the primary water storage tank had 3 instruments out-of-service and the waste gas sample panel had 2 instruments out-of-service at the end of the reporting month.

The entire instrument channel is considered inoperative if: 1) the instrument is inopera-tive, 2) the chart recorder associated with the instrument is inoperative, or 3) the alarm function associated with the instrument is inoperative. If any of the functions listed above are not operational, then the instrument is not performing its intended function.

The 1994 Fort Calhoun monthly goal for this indicatoris a maximum of 5. Six out-of-service chemistry instruments make up 10% of all the chemistry instruments that are counted for this indicator.

Data Source: Chase /Reneaud (Manager / Source)

Accountability: Chase /Jaworski Adverse Trend: None 51

@ Waste Produced Each Month (Kilograms)

Monthly Average Waste Produced During the Last 12 Months (Kilograms)

--O- Fort Calhoun Monthly Average Goal Federal & State Monthly Umit (Max. of 1,000 Kg) -

1000 - = = = = = = = = = = = g 800 -

E 600 -

i, E

E Q 400- l 200-C O O > M .

O O , , , , , . , , , . . ,

Apr93 May Jun Jul Aug Sep Oct Nov Dhc Jan Feb Mar 94 HAZARDOUS WASTE PRODUCED This indicator shows the total amount of hazardous waste produced by the Fort Calhoun Station each month, the monthly average goal and the monthly average total for hazard-ous waste produced during the last 12 months. This hazardous waste consists of non-halogenated hazardous waste, halogenated hazardous waste, and other hazardous waste produced.

During the month of March 1994,0.0 kilograms of non-halogenated hazardous waste was produced,0.0 kilograms of halogenated hazardous waste was produced, and 0.0 kilograms of other hazardous waste was produced. The total for hazardous waste produced during the last 12 months is 149.5 kilograms. The monthly average for haz- ,

ardous waste produced during the last 12 months is 12.46 kilograms.

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

The 1994 Fort Calhoun monthly average goal for this indicator is a maximum of 100 ;

kilograms.

Date Source: Chase / Smith (Manager / Source)

Accountability: Chase / Smith ,

l Positive Trend 52 l 1

l

E Contaminated Radiation Controlled Area 25%- -O-- Fort Calhoun Goal (non-outage months)

-O- Fort Calhoun Goal (outage months) 20%-

15%-

C O O O O O O O O > + -o 10%-

~

0%

l;l;i Jan94 Feb 3

Mar ' Apr May Jun Jul Aug Sep i ; ; i Oct Nov Dec94 CONTAMINATED RADIATION CONTROLLED AREA This indicator shows the percentage of the RCA that is contaminated based on the total square footage. The 1994 monthly non-outage goalis a maximum of 12% contami-nated RCA and the monthly outage goal is a maximum of 15% contaminated RCA.

At the end of March 1994, the percentage of the total square footage of the RCA that .

was contaminated was 9.6%.

Data Source: Chase /Gundal(Manager / Source)

Accountability: Chase /Lovett Positive Trend SEP54 53

Number of Identified PRWPs Year-To-Date IGOODI

-O- 1994 Fort Calhoun Goa!(<25) y 25 - C O O O O O O O O -O O O 5 20-8 g 15-5 E

5 g 10-O 5-O n a I s s o s s s s s n Jan94 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec94 RADIOLOGICAL WORK PRACTICES PROGRAM The Radiological Work Practicos Program Indicator shows the number of Per Radio-logical Work Practices (PRWPs) which were identified during the reporting month.

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

During the month of March 1994, there was 1 PRWP identified. The PRWP involved an individual entering the RCA with their ALNOR turned off and without being logged into HIS-20. There have been 2 PRWPs in 1994.

The 1994 year-end goal for the number of PRWPs is a maximum of 25.

Data Source: Chase /Little (Manager / Source)

Accountability: Chase /Lovett Adverse Trend: None SEP 52 54

l Documents Scheduled for Review 250 .

2 Documents Reviewed O Overdue Documents 200 - '

150- 4 ^

100- -

~

1_

50 -- ~

7

_ / - -

/

O N-- ,

Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 DOCUMENT REVIEW This indicator shows the number of completed, scheduled, cad overdue (greater than 6 months past the scheduled due date) biennial reviews for the reporting month. These document reviews are performed in-house and include Special Procedures, the Site Security Plan, Maintenance Procedures, Preventive Maintenance Procedures, and the Operating Manual.

During March 1994 there were 36 document reviews scheduled, while 160 document reviews were completed. At the end of March, there was 1 document review more than 6 months overdue.

There were 41 new documents initiated in March.

Data Source: Chase / Keister (Manager / Source)

Accountability: Chase /Jaworski Adverse Trend: An adverse trend is indicated based on more than 3 consecutive (nonths with document reviews more than 6 months overdue.

SEP 46 55

i l

D Non-System Failures 30- lGOODI 25- V 20-15- 12 12 10- 6 8 T 7 7

%]

N ,

I I

h . . . , ,

Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 90- @ System Failures '

l GOOD l 80-70-60 -

40 33 32 30 31 30- 24 25 ,

26 /

V

/ r E 23 /

h

~

- b

~

i 1 , I I e i I , 4 4 i Ap63 May Jun Jul Aug Sep Od Nov Dec Jan Feb mag 4 LOGG ABLE/REPORTAB LE INCIDENTS (SECURITY)

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

reportable incidents conceming system failures which occurred during the reporting month.

During the month of March 1994, there were 42 loggable/ reportable incidents identified.

System failures accounted for 38 (90%) of the loggable/ reportable incidents. System failures rose considerably during the reporting month due to an increase in microwave, search equipment, and door failures. CCTV environmental failures also showed an -

increase due to sun / shadow problems, which is typical during this time of the year.

Data Source: Sefick/Woerner(Manager / Source)

Accountability: Sefick l

Adverse Trend: None SEP 58 l I

l 56

E Temporary Modifcations >1 cycle old (RFO required for Removal)

O Temporary Modifcations >6 months old (Removable on-line) 8-Fort Calhoun Goals for Temporary Modifcations >1 cycle old &

7- Temporary Modifcations >6 months old 6-5-

4 4 4 N2E 3~

'hI

'/ '/h$'h's '$'/' /

bfhh hhf' Af// hlll' 2- %% %%: :%% bhhl 1- // /

o V I

V I V 4

I December '93 January '94 February '94 March '94 TEMPORARY MODIFICATIONS This indicator provides information on the number of temporary modifications greater than one fuel cycle old requiring a refueling outage (RFO) for removal and the number of temporary modifications removable on line that are greaterthan six months old. The 1994 Fort Calhoun monthly goals for this indicator are 0.

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 March 1994 there were 5 temporary modifications installed that were greater than six months old that can be removed on-line. These were: 1) Local indication for BAST CH-11 A and CH-118, in which Operations is reviewing a draft FLC. After review, Ucensing is to issue an FLC, and the NRC is to approve; 2) LP-30 transformer, in which ECN 93-183 is approved for accomplishment prior to 8/31/94; 3) Refrigerated air dryer for Rm-057, which is awaiting installation of MR-FC-84-155D, scheduled completion date of 6/30/94; 4) Epoxy repairs ,

to ST-4B, which is awaiting completion of MWO 931325, scheduled start date 1995 l Refueling Outage; and 5). Door 1011-7 lockset replacement,in which ECN 93-408 is approved for accomplished prior to 9/30/94.

i At the end of March 1994, there was a total of 25 TMs installed in the Fort Calhoun l'

Station. 9 of the 25 installed TMs require an outage for removal and 16 are removable on line. In 1994 a total of 19 temporary modifications have been installed.

Data Source: Jaworski/ Turner (Manager / Source)

Accountability: Jaworski/Gorence Adverse Trend: An adverse trend is indicated based on more than 3 consecutive months of performance not meeting the established goal for the number of temporary modifications removable on-line that are greater than six months old. Actions to remove these are defined and no additional action plan will be prepared.

SEP 62 & 71 57

O Total Modifcation Packages Open 264

~

250- --O- Fort Calhoun Year End Goal A

200-W

[o v-150- C O O O O O O O b

4 100 & T -

% A - 100- ?g 4 fi N @g Tfr 7

'T g 4 b M 5 7 -

7 ""'

a s. & & $w n$

g a y &

WE Q., :. s$

w w p

"y$

$ C $3 w$$ N M $ M @ h h

&]N ;

50-

$n 5)p j@f R ?f g M 16 b $ d U % . .a @M g x=. ;ig i y 3 w% M;

.- m w g g y g < a a m: A jp *

$E bT g ig gf ($ ~d: @ MI

'y" u 4 g w g ~$ m p j$ $ b) ig jg n#1 jg @ ( d g& gg i i i i i i i a i i i i i i e i

'91 '92 '93 Apr93 May Jun Jul Aug sep Oct Nov Dec Jan Feb Mar 94 OUTSTANDING MODIFICATIONS This indicator shows the total number of outstanding modifications (excludina outstand-ina modifications which are orocosed to be cancelled).

Cateoorv Reoortino Month Form FC-1133 Backlog /In Progress 1 Mod. Requests Being Reviewed 3 Design Engr. Backlog /In Progress 45 Construction Backlog /in Progress 26 Design Engr. Uodate Backloc/In Procress 12_

Total 87 At the end of March 1994,5 additional modification requests had been issued this year and 36 modification requests had been cancelled. The Nuclear Projects Review Com-mittee (NPRC) had completed 73 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) had completed 24 backlog modification request reviews this year.

The 1994 year-end Fort Calhoun goal for this indicatoris a maximum of 80 outstanding modifications.

Data Source: Jaworski/ Turner (Manager / Source)

Scofield/Lounsbery (Manager / Source)

Accountability: Scofield/Phelps Adverse Trend: None 58

EARS Requiring Engins: ring Closeout - Not in Clostout O DEN G sE 50-40- 40- 40- 40-30- -

30- 30- 30-20- 20- 20- 20-

, , , ,- o ",N 7 Jan Feb Mar Jan Feb Mar Jan Feb Mar Jan Feb Mar 0-3 months 3-6 months s.12 months >12 months March '94 Overduo EARS O Closeout O Engineering Response 40-30- I&M '

20-10- j j , ..

O i i . . . . i Priority 0 Prionty 1 Priority 2 Priority 3 Priority 4 Priority 5 Priority 6 Priority 1 & 2 @ Priority 3 Total Open EARS 200-150- Data --

100- Not 50 - ;, w Available -

g ~~~~

gA .w g ;o j 3 1 4 i i i i i i i l I i Apr94 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94

@ 46 EARS Resolved and in Closeout O O OveMue Responses O 37 Overdue Closeouts O 113 EARS Requiring Response 8 82 EARS on Schedule 23.3 %

y \

28.9% 71.1 % ,

N_ ..egl 25.2Y ,# j N " % _ - __ _ __ __ # -

digasumuissDSNP"*

ENGINEERING ASSISTANCE REQUEST BREAKDOWN This indicator shows a breakdown of the number of EARS assigned to Design Engineer-ing and System Engineering. The 1994 year-end goal for this indicator is a maximum of 140 outstanding EARS.

Total EAR breakdown is as follows:

EARS opened during the month 12 EARS closed during the month 11 Total EARS open as of the end of the month 159 Data Source: Skiles/Pulverenti (Manager / Source)

Accountability: Jaworski/Skiles Adverse Trend: None SEP 62 59

[ s

.. O In DEN = 214 o

[kg% a 0-3 Months = 32)

30.0% O in system Engineering - 204 38.8 %

j M,l O 3-6 Months = 118 18.0% ~ In Procurement /Constr. = 129 28.5 % 16.5 e O >6 Months = 277 O in Cioseout = 168 ECH STATUS - OVERALL BACKLOG B ECNs Backlogged ECNs Received During the Month

- ECNs Completed During the Month 250- [

200- 1

~'

D 0-3 Months =121

} 22.0Y.

150- i g@!$ S e-n h'i 100- b 21.5'.

Y 56.5 % 3-6 Months = 46 j a E_ w>

ew y JhB' (g f ] F 0 >6 Months = 47 i i a a i i i Jan94 Feb Mar Apr May Jun Jul94 (Year to-Date monthly average of ECNs received was 48.6)

ECN STATUS - DEN 250-200- p g g p 24.0Y 0-3 Months = 49 150- O p% 9 ew ~ v 100- $ 55.0Y 3-6 Months = 43 h 21.0Y.

50 - $)

f'% $ M >6 Most.hs = 112 0 I* '

i i 6 i i i i Jan94 Feb Mar Apr May Jun Jul94

__ g _.

_ .__ _ _ _ E,g,N S,,LATU_S, S,E_ ,,_ __, __ __, _ ,,_ ,,_ _

200- g 0-3 Months = 36 150 - $ p8.W. l

\M 100- 5 3 58.0% O 3-6 Months = 18

~

a 50 - 3 0

i

l i N

i i i e i 14'0 %

O >6 Months - 75 l Jan94 Feb Mar Apr May Jun Jul94 ,

ECN STATUS - PROC /CONSTR l 250 -

200 - h y 150 - l 25.6% gg[g5 0-3 Months = 114 100- l h 6f6Y 6h. N h Q 4 i l

i i e i i Mjts,, O >6 Months = 43 Jan94 Feb Mar Apr May Jun Jul94 ECN STATUS - CLOSEOUT ENGINEERING CHANGE NOTICE STATUS Data Source: Skiles/McShannon (Manager / Source)

Accountability: Skiles/Jaworski Adverse Trend: None SEP 62 60

E FC Type - 210 B Priority 1 &2 - 125]

$ SRIType -250 38M y- @ Priority 3 & 4 - 318 5.0% 0 oC Type - 255 (N45*/?

~ -

O Priority 5 & 6 -272 TOTAL OPEN ECNS BY TYPE 915 TOTAL) TOTAL OPEN ECNs BY PRIORITY P15 TOTAL)

D DEN Engineering Not Complete .

. O System Engineering - Response, Confirmation Not Complete G Maintenance / Construction / Procurement - Work Not Complete E DEN - Closecut or Drafting Not Complete 250 -

203 199 210

@ Priority 1 or 2 150 - 27M 100 - 90

@ Priority 3 or 4 50 - ( 57.6 of 0 Priority 5 or 6 0 i j i i

- -- l Jan94 Feb Mar Apr May Jun Jul94 Facility Change ECNs Open 239 246 2%

250 -

200- 74 5 Priority 1 or 2 150 - 70 8 Priority 3 or4 100 -

39 50- 2.4%Y O Priority 5 or 6 67 w 0 i i ; ; i ; i Jan94 Feb Mar Apr May Jun Jul94 i Substitute Replacement item ECNs Open !

300-2ss !

~

86 7.5% B Priority 1 or2 200 - g .

150 - f .

/f 121 66.7%

100-0 Priority 5 or 6 50- //4 . ,

f' y 0 , , , , , , ,

Jan94 Feb Mar Apr May Jun Jul94 Document Change ECNs Open ENGINEERING CHANGE NOTICES OPEN Data Source: Skiles/McShannon (Manager / Source)

Accountability: Skiles/Jaworski Adverse Trend: None SEP 62 61

I l

O Administrative Control Problem O ucensed operator Error

@ Other Personnel Error

@ Maintenance Problem 3- B Design / Construction / installation / Fabrication Problem 6 Equipment Failures 2- g 5 :

E 1- - -

E - , ,-

_~ < , '

i : : .

0 i i i i i i i i . . i i Mar 93 Apr May Jun Jul - Aug Sep Oct Nov Dec Jan Feb94 LICENSEE EVENT REPORT (LER) ROOT CAUSE BREAKDOWN This indicator shows the LERs by event date broken down by Root Cause Code for each of the past twelve months from March 1,1993 through February 28,1994. To be consistent with the Preventable / Personnel Errors LER indicator, this indicator is re-ported by the LER event date as opposed to the LER report date.

The cause codes are intended to identify possible programmatic deficiencies. For detailed descriptions of these codes, see the " Performance Indicator Definitions" section of this report.

There was 1 event in February 1994 that resulted in an LER.

Data Source: Short/Cavanaugh (Manager / Source)

Accountability: Chase Adverse Trend: None 62 I

I 1

i O Total Requalification Training Hours i O Simulator Training Hours O Non-Requalification Training Hours 50- O Numberof Exarn Failures 40- 36 36 .5 33 ""~ ~

33 33 30- 27 20-18 4

12 )4 13 4 10- 7 j; 7 8 7

/

3

/,

3 #/ 2 *

. /. 3 7 4

3

/[ 2 n

M y5hg 0 i

~"'

i i

' ~~'

i

,i

' ' E e i Cycle 93-2 Cycle 93 3 Cycle 93-4 Cycle 93 5 Cycle 93-6 Cycle 93-7 Cycle 94-1

' Note: The Simulator was out-of-service for maintenance and modifications during Cycle 93-6.

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.

There were 3 written exam failures, and 2 individual simulator exam failures for Cycle 94-1. The failure of the 2 individuals in the simulator also caused that crew to fail. All individuals were remediated without impacting the Operations Department shift sched-ule.

Data Source: Gasper /Guliani (Manager / Source)

Accountability: Gasper /Guliani Adverse Trend: None SEP 68 63

35- @ SRO Exams Administered O sRO Exams passed 30- E RO Exams Administered O RO Exams Passed 25-20-15 -

10-NRC Exams 5- - - -

6 i 1 4 i 4 i i i i Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan i 1 feb Mar 94 LICENSE CANDIDATE CPAMS 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-tered quizzes and exams are used to plot the SRO and RO candidates' monthly progress.

There were no OPPD Reactor Operator or Senior Reactor Operator exams adminis-tered during March 1994.

Currently, there is no Hot Ucense class being conducted. The next Licensed Operator class will convene on April 11,1994.

Data Source: Gasper /Guliani(Manager / Source)

Accountability: Gasper /Guliani Adverse Trend: None SEP68 64

l l

@ Total Open CARS B TotalOpen irs D Open CARS > Six Months Old @ Open irs > Six Months Old 320- ~

cyda 15 _

- 320 280- Refueling ;

outage _ _ _

- 280 240- [ [ -240 200 - :

: : - 200 160-

_ = _ _

_ h f

160 120- : : : : _ : : : _- : : 120 80- 2 = = 2 2 - 2 2 2 2 2

~

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: : - 7 40- _ _ :

- 40 t

0 e u s e e s e e s s s s

'O '

Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 E Open Significant CARS Cyde 15 80- Refueling out*9' E

, 0 Open Significant irs so .

54 50- 45 -

40- 37 ' - -

28 27 30- 25 ~ 24 l 20-10- 2 2 2 2 2 2 4 5 5 4 6 7 0 , , , , , , , , , , , ,

Apr93 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar 94 OPEN CORRECTIVE ACTION REPORTS AND INCIDENT REPORTS This indicator shows the total number of open Corrective Action Reports (CARS), CARS

>6 months old, the total number of Open irs, irs >6 months old, the number of open significant CARS and the number of open significant irs.

At the end of March 1994 there were 68 open CARS.12 of these CARS were greater than 6 months old. There were 7 Open Significant CARS at the end of the month.

Also, at the end of March there were 335 open irs. 68 of these irs were greater than 6 months old. There were 67 Open Significant irs at the end of the month.

The 1994 monthly goal for the number of CARS greater than 6 months old is less than 30.

Data Source: Orr/Gurtis (Manager / Source) & CHAMPS Accountability: Andrews/Gambhir/ Gates Adverse Trend: Although the number of irs has been increasing, an adverse trend is not indicated because the increase is a result of a revision to Standing Order R-4 that lowers the threshold for writing irs and requires completion of all corrective actions prior to closing irs. g3

i

Engineering Hold -+- Planning comploie

-G- Planning Hold Ready

--V- Part Hold Total 425-400-375 -

350 -

325- )

300-m 275-

@ 250 -

f 225-

< 200-175-H 150 -

125-100 - '

75- ,

50 -

25-Doc 93 Jan94 Feb Mar Apr May Jun ' '

Jul sep Oct Nov Dec Jan95 Feb Mar 95 MWO PLANNING STATUS (CYCLE 16 REFUELING OUTAGE)

This indicator shows the total number of Maintenance Work Requests (MWRs) and Maintenance Work Orders (MWOs) that have been approved for inclusion in the Cycle 16 Refueling Outage. This graph indicates:

Parts Holds (part hold removed when parts are staged and ready for use)

Engineering Holds (Engineering hold removed when appropriate engineering paper-work or support is received for the package) -

Planning Holds (Planning hold removed when planning is completed to the point when package is ready or other support is necessary to continue the planning process)

Planning Complete (status given when only items keeping the job from being ready to work are parts or engineering support)

Ready (status when all planning, supporting documentation, and parts are ready to go)

Data Source: Chase /Schmitz (Manager / Source)

Accountability: Chase /Johansen Adverse Trend: None SEP 31 66

1995 OUTAGE MODIFICATIONS

--+ - Baseline Schedule for PRC Approval Projected / Actual Schedule for PRC Approval Final Design Package issued 20-Total Modification Packages (17) (2 added after 1/14/94 To Be Scheduled) 1s- llllllll!lllll'lll ll 'l'lll lll'lll'2 ' '

l'lllll 10- m

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8 o.

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9

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i a s i i s

PROGRESS OF CYCLE 16 OUTAGE MODIFICATION PLANNING (FROZEN SCOPE OF 15 MODIFICATIONS)

This indicator shows the status of modifications approved for installation during the Cycle 16 Refueling Outage. The data is represented with respect to the baseline schedule (established 1/14/94) and the current schedule. This information is taken from the Modification Variation Report produced by the Design Engineering group.

In March,5 modifications were deleted and 3 were added.

The goal for this indicator is to have all modification packages identified prior to 1/14/94 PRC approved by October 15,1994. Modifications added after 1/14/94 will be sched-uled as soon as possible.

Data Source: Skiles/Ronne (Manager / Source)

Accountability: Phelps/ Ski les Adverse Trend: None SEP 31 67

1994 ON-LINE MODIFICATIONS i

--+-- Baseline Schedule for PRC Approval & Projected / Actual Schedule for PRC Approval 1

Final Design Package issued (7 FD DCPs issued prior to 1/14/94) l Total Modification Packages (18)(2 are Close Out Only) 20-9

$ ': l: : :: !' l: ':::, ll . ': . ': ::':'::':

7B "* 15-2 -8 8 >

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3 5 $ $ 8 8 $ $ 8 8

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PROGRESS OF 1994 ON-LINE MODIFICATION PLANNING (FROZEN SCOPE OF 16 MODIFICATIONS)

This indicator shows the status of modifications approved for on-line installation during 1994. The data is represented with respect to the baseline schedule (established 1/14/

94) and the current schedule. This information is taken from the Modification Variance Report produced by the Design Engineering Nuclear group, in March,2 modifications were deleted and 1 was added.

The goal for this indicator is to have all modification packages identified prior to 1/14/94 PRC approved by August 15,1994.

l l

i Data Source: Skiles/Ronne (Manager / Source)

Accountability: Phelps/Skiles Adverse Trond: None ,

08 l

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l ACTION PLANS FOR ADVERSE TRENDS i

I 69 l

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- . - . -_ _ _ _ .- _ - - _ _ _ - _ - - _w

ACTION PLANS FOR ADVERSE TRENDS This section lists action plans that have been developed for the performance indicators cited as exhibiting adverse trends during the three months preceding this report.

The action plan for Document Review follows:

Actions to reverse the Adverse Trend (cited in the February 1994 report) for overdue document reviews are:

1) Continue to provide resources to perform biennial review assignments.

2) A Facility License Change (FLC) request has been submitted to reduce the number of required periodic reviews.

3) A PRC subcommittee has been formed to take the maximum advan-tage of the FLC request to reduce the number of periodic document reviews.

An overdue document review is not safety significant, in that OPPD's dynamic proce-dural review process ensures documents are kept up-to-date.

Progress is shown by March data indicating only 1 document review overdue at the end of the month.

The action plan for Number of Control Room Equipment Deficiencies follows:

Actions to reverse the Adverse Trend (cited in the February 1994 report) for the number of control room equipment deficiencies are:

1) Control room deficiencies are being worked and closed routinely by the maintenance department. A target closure rate of 10 per week has been established. Once the goalls met, the target will be adjusted periodically to ensure a positive or neutral trend.

2) To ensure that these deficiencies are being pursued with the best tech-nical solutions and that all departments are supporting the Control Room Deficiency Goal, a working group of Maintenance, Engineering, and Operations personnel has been established.

70

i PERFORMANCE INDICATOR DEFINITIONS 1

i AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM CENTS PER KILOWATT HOUR !

PERFORMANCE The purpose of this indicator is to quantify the economi-The sum of the known (planned and unplanned) unavail- ,

caloperation of Fort Calhoun Station. The cents per '

able hours and the estimated unavailable hours for the kilowatt hour indicator represents the budget and actual auxiliary feedwater system for the reporting period di-cents per kilowatt hour on a 12 month rolling average for vided by the critical hours 1or the reporting period multi-the current year. The basis for the budget curve is the plied by the number of trains in the auxiliary feedwater system.

approved 1993 budget. The basis for the actual curve is the Financial and Operating Report.

CHECK VALVE FAILURE RATE Compares the Fort Calhoun check valve failure rate to CLEAN CONTROLLED AREA CONTAMINATIONS 21,000 DISINTEGRATIONS / MINUTE PER PROBE the industry check valve f ailure rate (f ailures per 1 million AREA component hours). The data for the industry failure rate The personnel contamination events in the clean con-is three (nonths behind the Pl Report reporting month.

trolled area. This indicator tracks personnel performance This indicator tracks performance for SEP #43.

for SEP #15 & 54.

COLLECTIVE RADfATION EXPOSURE Collective radiation exposure is the total external whole- CONTAMINATED RADIATION CONTROLLED AREA The percentage of the Radiation Controlled Area, which body dose received by all on-site personnel (including includes the auxiliary building, the radwaste building, and contractors and visitors) during a time period, as mea-areas of the C/RP building, that is contaminated based sured by the thermoluminescent dosimeter (TLD). Col-on the total square footage. This indicator tracks perfor-lective radiation exposure is reported in units of person- mance for SEP # 54.

rem. This indicator tracks radiological work performance for SEP #54 DAILY THERMAL OUTPUT This indicator shows the daily core thermal output as COMPONENT FAILURE ANALYSIS REPORT (CFAR) measured from cx>mputer point XC105 (in thermal mega.

SUMMARY

watts). The 1500 MW Tech Spec limit, and the unmet The number of INPO categories for Fort Calhoun Station portion of the 1495 MW FCS daily goal for the reporting with significantly higher (1.645 standard deviations) fail- month are also shown.

ure ratas than the rest of the industry for an eighteen month time period. Failures are reported as component (i.e. pumps, motors, valves, etc.) and application (i.e. DIESEL GENERATOR RELIABILITY (25 DEMANDS)

This indicator shows the number of failures occurring for charging pumps, main steam stop valves, control ele-each emergency diesel generator during the last 25 start ment drive motors, etc.) categories.

demands and the last 25 load-run demands.

Failure Cause Categories are:

Wear Out/ Aging a failure thought to be the conse-DISABLING INJURY /lLLNESS FREQUENCY RATE quence of expected wear or aging.

Manuf acturing Defect - a f ailure attributable to inad- (LOST TIME ACCIDENT RATE)

This indicator is defined as the number of accidsnts for equate assembly or initial quality of the responsible com- j all utility personnel permanently assigned to the station, :

ponent or system.

involving days away from work per 200,000 man-hours Engineering / Design a failure attributable to the inad-worked (100 man-years). This does not include contrac-equate design of the responsible component or system. ,

tor personnel. This indicator tracks personnel perfor- l Other Devices - a failure attributable to a failure or mance for SEP #25 & 26. i misoperation of another component or system, including associated evces.

Maintenance / Testing - a fdure that is a result of im- DOCUMENT REVIEW (BIENNIAL)

The Docurnent Review Indicator shows the number of proper maintenano or testing lack of maintenance, or documents reviewed, the number of documents sched.

personnel errors that tw Guring maintenance or test

uled for review, and the number of document reviews ing activities performed on the responsble component or that are overdue for the reporting month. A document system, including failure to follow procedures.

review is considered overdue if the review is not com.

Errors - failures attrbutable to incorrect procedures that plots within 6 months of the assigned due date. This were followed as written, improper installation of equip- indicator tracks performance for SEP #46.

ment, and personnel errors (including f ailure to follow procedures properiy). Also included in this category are EMERGENCY AC POWER SYSTEM SAFETY SYSTEM failures for which the cause is unknown or cannot be as- PERFORMANCE ,

signed to any of the preceding categories. The sum of the known (planned and unplanned) unavai!-

able and the estimated unavailable hours for the emer-gency AC power system for the reporting period divided by the number of hours in the reporting period multiplied by the number of trains in the emergency AC power sys-tem, 71

PERFORMANCE INDICATOR DEFINITIONS EMERGENCY DIESEL GENERATOR UNIT RELIABIL-ITY EMERGENCY DIESEL GENERATOR UNRELIABILITY This indicator measures the total unreliability of emer.

This indicator shows the number of failures that were gency diesel generators. In general, unreliability is the reported during the last 20,50, and 100 emergency dio-solgenerator demands at the Fort Calhoun Station. Also ratio of unsuccessful operations (starts or load-runs) to the number of valid demands. Total unreliabilrty is a shown are trigger values which correlate to a high level combination of start unreliability and load-run of confidence that a un't's r dieselgenerators have ob- unreliability.

tained a reliability of greater than or equal to 95% when the demand f ailures are less than the trigger values.

1) Number of Start Demands: All valid and inadvertent ENGINEERING ASSISTANCE REQUEST (EAR)

BREAKDOWN start demands, including all start only demands and all This indicator shows a breakdown, by age and priority of start demands that are followed by load run demands, the EAR, of the number of EARS assigned to Design En-whether by automatic or manual initiation. A start-only gineering Nuclear and System Engineering. This indica-demand is a demand in which the emergency generator tor tracks performance for SEP #62.

is started, but no attempt is made to load the generator.

2) Number of Start Failures: Any failure within the emer-ENGINEERING CHANGE NOTICE (ECN) STATUS gency generator system that prevents the generator from The number of ECNs that were opened, ECNs that were achieving specified frequency and voltage is classified as completed, and open backlog ECNs awaiting completion a valid start failure. This includes any condition identified by DEN for the reporting month. This indicator tracks in the course of maintenance inspections (with the emer- performance for SEP #62.

gency generator in standby mode) that definitely would have resulted in a start failure if a demand had occurred. ENGINEERING CHANGE NOTICES OPEN

3) Number of Load-Run Demands: For a valid load run This indicator breaks down the number of Engineering demand to be counted the load-run attempt must meet Change Notices (ECNs) that are assigned to Design one or more of the following criteria: Engineering Nuclear (DEN), System Engineering, and A) Aload run of any duration that results from a real au-Maintenance. The graphs provide data on ECN Facility tomatic or manualinitiation. Changes open. ECN Substitute Replacement Parts B) A load-run test to satisfy the plant's load and duration open, and ECN Document Changes open. This indicator as stated in each test's specifications. tracks performance for SEP #62.

C) Other specialtests in which the emergency generator is expected to be operated for at least one hour while EQUIPMENT FORCED OUTAGES PER 1,000 CRITI-loaded with at least 50% of its design load. CAL HOURS

4) Number of Load-Run Failures: A load-run f ailure Equipment forced outages per 1000 critical hours is the l should be counted for any reason in which the emer- inverse of the mean time between forced outages gency generator does not pick up load and run as pre- caused by equipment failures. The mean time is equal dicted. Failures are counted during any valid load-run to the number of hours the reactor is critical in a period demands. (1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months ) divided by the number of forced outages

5) Exceptions: Unsuccessf ul attempts to start or load-run caused by equipment failures in that period, should not be counted as valid demands or failures when they can be attributed to any of the following: i EQUIVALENT AVAILABILITY FACTOR j A) Spurious trips that would be bypassed in the event of This indicator is defined as the ratio of gross available j an emergency. generation to gross maximum generation, expressed as B) Malfunction of equipment that is not required during a percentage. Available generation is the energy that an emergency. can be produced if the unit is operated at the maximum C)Intentionaltermination of a test because of abnormal power level permitted by equipment and regulatory limi-conditions that would not have resulted in major diesel tations. Maximum generation is the energy that can be generator damage or repair. produced by a unit in a given period if operated continu-D) Malfunctions or operating errors which would have not ously at maximum capacity.

prevented the emergency generator from being restarted '

and brought to load within a few minutes. FORCED OUTAGE RATE E) A f ailure to start because a portion of the starting sys- This indicator is defined as the percentage of time that tem was disabled for test purpose, if followed by a suc- the unit was unavailable due to forced events compared cessful start with the starting system in its normal align- to the time planned for electrical generation. Forced ment, avents are failures or other unplanned conditions that Each emergency generator failure that results in the gen- require removing the unit from service before the end of erator being declared inoperable should be counted as the next weekend. Forced events include start up fail-one demand and one failure. Exploratory tests during ures and events initiated while the unit is in reserve shut.

oorrective maintenance and the successful test that fol- down (i.e., the unit is available but not in service).

lows repair to verify operability should not be counted as demands or failures when the EDG has not been de-clared operable again.

72

PERFORMANCE INDICATOR DEFINITIONS FUEL RELIABluTYINDICATOR UCENSED OPERATOR REQUALIFICATION TRAIN-This indicator is defined as the steady state primary cool- ING ant 1131 activity, corrected for the tramp uranium contri- The total number of hours of training given to each crew bution and normalized to a common purification rate. during each cycle. Also provided are the simulator train.

Tramp uranium is fuel which has been deposited on re-ing hours (which are a subset of the total training hours),

actor core internals from previous defective fuel or is the number nf non-requalification training hours and the present on the surface of fuel elements from the manu-number of exam iailures. This indicator tracks trainirq facturing process. Steady state is defined as mntinuous performance for SEP #68.

operation for at least three days at a power level that does not vary more thara or 5%. Plants should collect LICENSEE EVENT REPORT (LER) ROOT CAUSE data for this indicator at a power level above 85%, when BREAKDOWN possible. Plants that did not operate at steady-state This indicator shows the number and root cause code for power above 85% should collect data for this indicator at Licensee Event Reports. The root cause codes are as the highest steady-state power level attained during the follows:

month. 1) Administrative Control Problem - Management and The density wrrection f actor is the ratio of the specific supervisory deficiencies that affect plant programs or volume of coolant at the RCS operating temperature activities (i.e., poor planning, breakdown or lack of ad.

(540 degrees F., Vf - 0.02146) divcled by the specific equate management or supervisory control, incorrect volume of coolant at normalletdown temperature (120 procedures, etc.)

degrees F at outlet of the letdown cooling heat ex- 2) Licensed Operator Error This cause code captures changer, Vf . 0.016204), which results in a density cor- errors of omission / commission by licensed reactor opera-rection factor for FCS equal to 1.32. tors during plant activities.

3) Other Personnel Error - Errors of omission /commis-GROSS HEAT RATE sion committed by non-licensed personnel involved in Gross heat rate is defined as the ratio of total thermal plant activities.

energy in Bntish Thermal Units (BTU) produced by the 4) Maintenance Problem - The intent of this cause reactor to the total gross electrical energy produced by code is to capture the full range of problems which can the generator in kilowatt-hours (KWH). be attributed in any way to programmatic deficiencies in the maintenance functional organization. Activities in-HAZARDOUS WASTE PRODUCED c!uded in this category are maintenance, testing, surveil-The total amount (in Kilograms) of non-halogenated haz. lance, calio* ration and radiation protection, ardous waste, hajogenated hazardous waste, and other 5) Design / Construction / Installation / Fabrication Problem hazardous waste produced by FCS each month. This cause code covers a full range of progrr,mmatic deficiencies in the areas of design, construction, installa-HIGH PRESSURE SAFETY INJECTION SYSTEM tion, and f abrication (i.e., loss of control power due to SAFETY SYSTEM PERFORMANCE underrated fuse, equipment not qualified for the environ-The sum of the known (planned and unplanned) unavail- rnent, etc.).

able hours and the estimated unavailable hours for the 6) Equipment Failures (Electronic PieceParts or Envi-high pressure safety injection system for the reporting ronmental-Related Failures) - This code is used for spuri-period divided by the critica! hours for the reporting pe- ous failures of electronic piece-parts and failures due to riod multiplied by the number of trains in the high pres- meteorological conditions such as lightning, ice, high sure safety injection system, winds, etc. Generally, it includes spurious or one-time failures. Electric mmponents included in this category INDUSTRIAL SAFETY ACCIDENT RATE-INPO are circuit cards, rectifiers, bistables, fuses, capactors, This indicator is defined as the number of accidents per diodes, resistors, etc.

200,000 man-hours worked for all utility persor:nel per-manentty assigned to the station that result in any of the LOGGABLE/ REPORTABLE INCIDENTS (SECURITY) following: 1) one or more days of restricted work (ex- The total number of security incidents for the reporting cluding the day of the accident); 2) one or more days month depicted in two graphs. This indicator tracks se-away from work (excluding the day of the accident); and curity performance for SEP #58.

3) fatalities. Contractor personnel are not included for this indicator. MAINTENANCE OVERT 1ME 1he % of overtime hours compared to normal hours for IN-UNE CHEMISTRY INSTRUMENTS OUT OF SER. maintenance. This includes OPPD personnel as well as VICE contract personnel.

Total number of in-line chemistry instruments that are out-of-servica in the Secondary System and the Post Accident Sampling System (PASS).

LICENSE CANDIDATE EXAMS This indicator shows the number of SRO and/or RO quiz-zes and exams that are administered and passed each month. This indicator tracks training performance for SEP #68.

73

PERFORMANCE INDICATOR DEFINITIONS MAINTENANCE WORKLOAD BACKLOGS NUMBER OF CONTROL ROOM EQUIPMENT DEFI- l This indicator shows the backlog of non outage Mainte. CIENCIES '

nance Work Orders remaining open at the end of the A control room equipment deficiency (CRD)is defined as reporting rnonth. Maintenance classifications are de, any component which is operated or controlled from the fined as.' Control Room, provides indication or alarm to the Control Room, provides testing capabihties from the Control Corredive - Repair and restoration of equipment or mm- Room, provides automatic actions from or to the Control ponents that have failed or are malfunctioning and are Room, or prov,i des a passive function for the Control ,

j not performing their intended function. Room and has been identified as defc, ient, i.e., does not perform under all conditions as designed. This definition Preventive - Adions taken to maintain a piece of equip- also applies to the Alternate Shutdown Panels Al-179, ment within design operating conditions, prevent equip- Al-185, and Al-212.

ment failure, and extend its life and are performed prior A plant component which ,si defc, ,ent i or inoperable ,s i

to equipment f ailure. considered an " Operator Work Around (OWA) Item"if some other action is required by an operator to compen-Non-Corrective / Plant improvements Maintenance ac- sate for the condition of the component. Some examples tivities performed to implement station improvements or f OWAs are: 1) The control room level indicator does to repair non-plant equipment. not work but a local sightglass can be read by an Opera-tor out in the plant; 2) A defcient pump cannot be re-Maintenance Work Priorities are defined as: paired because replacement parts require a long lead time for purchase / delivery, thus requiring the redundant Emergency - Conditions which significantly degrade sta- pump to be operated continuously; 3) Special actions tion safety or availability. are required by an Opwator because of equ,pment i de-sign problems. These actions may be described in Op-Immediate Action - Equipment deficiencies which signifi- erations Memorandums, Operator Notes, or may require cantly degrade station reliability. Potential for unit shut- changes to Operating Procedures. 4) Defcient plant down or power reduction. equipment that is required to be used during Emergency Operating Procedures or Abnormal Operating Proco-Operations Concern - Equipment deficiencies which dures. 5) System indication that provides critical infor.

hinder station operation. m tion during normal or abnormal operations.

Essential- Routine mrrective maintenance on essential NUMBER OF MISSED SIJRVEILLANCE TESTS RE-station systems and equipment. SULTING IN LICENSEE EVENT REPORTS The number of Surveillance Tests (STs) that result in Non Essential - Routine corrective maintenance on non- consee Event Reports (LERs) during the reporting essential station systems and equipment. month. This indicator tracks missed STs for SEP #60 &

Plant improvement Non wrrective maintenance and plant improvements. OPEN CORRECTIVE ACTION REPORTS & INCIDENT REPORTS This indicator tracko maintenance performance for SEP This indicator displays the total number of open Correc-

36' tive Action Reports (CARS), the number of CARS that are older than six months and the number of open significant MAXIMUM INDIVIDUAL RADIATION EXPOSURE CARS. Also displayed are the number of open locident The total maximum amount of radiation received by an Reports (irs), the number of irs that are greater than six individual person working at FCS on a monthly, quarterly, months old and the number of open significant irs.

and annual basis.

OUTSTANDING MODIFICATIONS The number of Modification Requests (MRs)in any state MWO PLANNING STATUS (CYCLE 15 REFUELING OUTAGE) between the issuance of a Modification Number and the The total number of Maintenance Work Orders that have p on t pdat p B p been approved for inclusion in the Cycle 15 Refueling Outage and the number that are ready to work (parts resents modification requests that have not been plant staged, planning complete, and all other paperwork appr ved during the reporting month.

ready for field use). Also included is the number of 2) Modification Requests Being Reviewed. This category MWOs that have engineering holds (ECNs, procedures and other miscellaneous engineering holds), parts hold, M jication Requests that are not yet reviewed.

(parts staged, not yet inspected, parts not yet arrived) B.) Modification Requests being reviewed by the Nuclear and planmng hold (job scope not yet completed). Ma.in- Projects Review Committee (NPRC).

tenance Work Requests (MWRs) are also shown that C.) Modification Requests being reviewed by the Nuclear have been identified for the Cycle 15 Refueling Outage 1. *

,, c,t nF ussts may be reviewed several and have not yet been converted to MWOs.

t mes before they are approved for accomplishment or l 74 ,

PERFORMANCE INDICATOR DEFINITIONS cancelled. Some of these Modification Requests are event for which the cause is attributed to a problem with retamed to Engineering for more information, some ap- the original design of the plant would not be considered pre ved for evaluation, some approved for study, and preventable),

some approved for planning. Once planning is com- For purposes of LER event classification, a " Personnel plated and the scope of the work is clearly defined, these Error LER is defined as follows: An event for which the Modification Requests may be approved for accomplish- root cause is inappropriate action on the part of one or ment with a year assigned for construction or they may more individuals (as opposed to being attributed to a de-be cancelled. All of these different phases require re- partment or a general group). Also, the inappropriate view.

action must have occurred within approximately two

3) Design Engineering Backlog /in Progress. Nuclear years of the " Event Date" specified in the LER.

Planning has assigned a year in which construction will Additionally, each event classified as a " Personnel Error" be completed and design work may be in progress.

should also be classified as " Preventable." This indicator

4) Construction Backlog /In Progress. The Construction trends personnel performance for SEP ltem #15.

Package,has been issued or construction has begun but the modification has not been accepted by the System PRIMARY SYSTEM CHEMISTRY % OF HOURS OUT Acceptance Committee (SAC). OF UMIT

5) Design Engineering Update Backlog /in Progress. PED The % of hours out of limit are for six primary chemistry has received the Modification Completion Report but the parameters divided by the total number of hours possble drawings have not been updated. for the month. The key parameters used are: Lithium, The above mentioned outstanding modifications do not Chloride, Hydrogen, Dissolved Oxygen, Fluoride, and include modifications which are proposed for cancella. Suspended Solids. EPRI limits are used.

tion.

PROCEDURAL NONCOMPLIANCE INCIDENTS OVERALL PROJECT STATUS (REFUELING OUTAGE) (MAINTENANCE)

This indicator shows the status of the projects which are The number of identified incidents concerning mainte-in the scope of the Refueling Outage. nance procedural problems, the number of closed irs related to the use of procedures (includes the number of PERCENTAGE OF TOTAL MWOs COMPLETED PER closed irs caused by procedural noncompliance), and MONTH IDENEFIED AS REWORK the number of closed procedural noncompliance irs.

The percentage of total MWOs completed per month This indicator trends personnel performance for SEP identified as rework. Rework activities are identified by #15,41 & 44.

maintenance planning and craft. Rework is: Any main-tenance work repeated to correct a deficiency which has PROGRESS OF CYCLE 16 REFUEL!NG OUTAGE re-occurred within 60 days following similar work activi- MODIFICATION PLANNING (FROZEN SCOPE OF 21 ties. Any additional work required to correct deficiencies MODIFICATIONS) discovered during a failed Post Maintenance Test to on. This indicator shows the status of modifications ap-sure the component / system passes subsequent Post proved for completion during the Refueling Outage.

Maintenance Tests. This definition can be found in S. O.

M-101.

PROGRESS OF 1994 ON-LINE MODIFICATION PLAN-NING (FROZEN SCOPE OF 19 MODIFICATIONS)

PERCENT OF COMPLETED SCHEDULED MA!NTE- This indicator shows the status of modifications ap-NANCE ACTIVITIES proved for completion during 1994.

The % of the number of completed maintenance activi-ties as compared to the number of scheduled mainte- RADIOLOGICAL WORK PRACTICES PROGRAM nance activities each month. This % is shown for all The number of identified poor radiological work practices maintenance crafts. Also shown are the number of (PRWPs) for the reporting month. This indicator tracks emergent MWOs. Maintenance activities include MWRs, radiological work performance for SEP #52.

MWOs, STs, PMOs, calibrations, and other miscella-neous activities. This indicator tracks Maintenance per- RATIO OF PREVENTIVE TO TOTAL MAINTENANCE &

formance for SEP #33. PREVENTIVE MAINTENANCE ITEMS OVERDUE The ratio of preventive maintenance (including surveil-PREVENTABLE / PERSONNEL ERROR LERs lance testing and calibration procedures) to the sum of This indicator is a breakdown of LERs. For purposes of non. outage corrective maintenance and preventive main-LER event classification, a preventable LER is defined tenance completed over the reporting period. The ratio, as: An event for which the root cause is personnel error expressed as a percentage, is calculated based on man- ;

(i.e., inappropriate action by one or more individuals), hours. Also displayed are the % of preventive mainte- )

inadequate administrative controls, a design /construc- nance items in the month that were not completed by the i tion / installation /f abrication problem (involving work com- scheduled date plus a grace period equal to 25 % of the pleted by or supervised by OPPD personnel) or a main- scheduled interval. This indicator tracks preventive tenance problem (attributed to inadequate or improper maintenance activities for SEP #41. 1 upkeep / repair of plant equipment). Also, the cause of '

the event must have occurred within approximately two years of the " Event Date" specified in the LER (e.g., an 75 I

PERFORMANCE INDICATOR DEFINITIONS RECORDABLE INJURY /lLLNESS CASES FRE- SIGNIFICANT EVENTS QUENCY RATE Significant events are those events identified by NRC The number of injuries requiring more than normal first aid por 200,000 man-hours worked. This indicator staff through detciled screening and evaluation of operat-ing experience. The screening process includes the trends personnel performance for SEP #15,25 & 28.

daily review and discussion of all reported operating re-actor events, as well as other operational data such as REPEAT FAILURES special tests or construction activities. An event identi-The number of Nuclear Plant Reliability Data System fied from the screening process as a significant event (NPRDS) components with more than 1 failure and the candidate is further evaluated to determine if any actual number of NPRDS components with more than 2 failures or potential threat to the health and safety of the public for the last eighteen months.

was involved. Spocific examples of the type of criteria are summarized as follows: 1) Degradation of important SAFETY SYSTEM FAILURES safety equipment; 2) Unexpected plant response to a Safety system failures are any events or conditions that transient; 3) Degradation of fuelintegrity, primary mol-could prevent the fulfillment of the safety functions of ant pressure boundary, important associated features; structures or systems. If a system consists of multiple 4) Scram with complication; 5) Unplanned release of redundant subsystems or trains, failure of all trains con- radioactivity; 6) Operation outside the limits of the Tech-stitutes a safety system failure. Failure of one of two or nical Specifications; 7) Other.

more trains is not counted as a safety system failure. INPO significant events reported in this indicator are The definition for the indicator parallels NRC reporting SERs tSignificant Event Reports) which inform utilities of requirements in 10 CFR 50.72 and 10 CFR 50.73. The significant events and lessons learned identified through following is a list of the major safety systems, sub- the SEE-IN screening process.

systems, and components monitored for this indicator:

Accident Monitoring instrumentation, Auxiliary (and SPARE PARTS INVENTORY VALUE Emergency) Feedwater System, Combustible Gas Con. The dollar value of the spare parts inventory value for trol, Component Cooling Water System, Containment FCS during the reporting period.

and Containment isolation, Containment Coolant Sys-tems, Control Room Emergency Ventilation System, STAFFING LEVEL Emergency Core Cooling Systems, Engineered Safety The actual staffing level and the authorized staffing level Features instrumentation, EssentialCompressed Air for the Nuclear Operations Division, the Production Engi-Systems, Essential or Emergency Service Water, Fire nepring Division, and the Nuclear Services Division. This Detection or Suppression Systems, Isolation Condenser, indicator tracks performance for SEP #24.

Low Temperature Overpressure Protection, Main Steam Line isolation Valves, Onsite Emergency AC & DC STATION NET GENERATION Power w/ Distribution, Radiation Monitoring instrumenta. The not generation (sum) produced by the FCS during tion, Reactor Coolant System, Reactor Core Isolation the reporting month.

Cooling System, Reactor Trip System and Instrumenta-tion, Recirculation Pump Trip Actuation instrumentation, TEMPORARY MODIFICATlONS Residual Heat Removal Systems, Safety Valves, Spent The number of temporary mechanical and electrical con-Fuel Systems, Standby Liquid Control System and Ulti- figurations to the plant's systems.

mate Heat Sink. 1) Temporary configurations are defined as electrical jumpers, electrical blocks, mechanical jumpers, or me-SECONDARY SYSTEM CHEMISTRY PERFORMANCE chanical blocks which are installed in the plant operating INDEX systems and are not shown on the latest revision of the The Chemistry Performance Index (CPI) is a calculation P&lD, schematic, connection, wiring, or flow diagrams.

based on the concentration of key impurities in the sec- 2) Jumpers and blocks which are installed for Surveil-ondary side of the plant. These key impurities are the lance Tests, Maintenance Procedures, Calibration Pro-most likely cause of deterioration of the steam genera- cedures, Special Procedures, or Operating Procedures tors. Criteria for calculating the CPI are: 1) The plant is are not considered as temporary modifications unless the at greater than 30 percent power; and 2) The power is jumper or block remains in place after the test or proce-changing less than 5% per day. The CPI is calculated dure is complete. Jumpers and blocks installed in test or using the following equation: CPI - (sodium /0.90) + lab instruments are not considered as temporary modifi-(Chloride /1.70) + (Sulfate /1.90) + (Iron /4.40) + (Copper / cations.

0.30)/5. Where: Sodium, sulfate and chloride are the 3) Scaffolding is not considered a temporary modifica-monthly average blowdown concentrations in ppb, iron tion. Jumpers and blocks which are installed and for and copper are monthly time weighted average which MRs have been submitted will be considered as feedwater mncentrations in ppb. The denominator for temporary modifications until final resolution of the MR each of the 5 factors is the INPO median value. If the and the jumper or block is removed or is permanently monthly average for a specific parameter is less than the recorded on the drawings. This indicator tracks tempo-INPO median value, the median value is used in the cal- rary modifications for SEP #62 & 71.

culation.

76

PERFORMANCE INDICATOR DEFINITIONS THERMAL PERFORMANCE erated (ECCS on!y), and major equipment in the system is The ratio of the design gross heat rate (corrected) to the actuated. Unplanned means that the system actuation adjusted actual gross heat rate, expressed as a percent- was not part of a planned test or evolution. The ECCS age, actuations to be countod are actuations of the high pres-sure injection system, the low pressure injection system, UNIT CAPABILITY FACTOR or the safety injection tanks.

The ratio of the available energy generation over a given time period to the reference energy generation (the en-orgy that could be produced if the unit were operated UNPLANNED SAFETY SYSTEM ACTUATIONS(NRC DEFINITION) continuously at full power under reference ambient con- The number of safety system actuations which include dations) over the same time period, expressed as a per- (gnk) the High Pressure Safety injection System, the Low contage.

Pressure Safety injection System, the Safety injection Tanks, and the Emergency Diesel Generators. The NRC UNPLANNED AUTOMATIC REACTOR SCRAMS PER classifcation of safety system actuations includes actua-7,000 CRITICAL HOURS tions when major equipment is operated and when the This indicator is defined as the number of unplanned au- logic systems for the above safety systems are chal-tomatic scrams (reactor protection system logic actua- lenged, tions) that occur per 7,000 hours0 days 0 hours 0 weeks 0 months of critical operation.

The value for this indcator is calculated by multiplying VIOLATIONS PER 1,000 INSPECTION HOURS the total number of unplanned automatic reactor scrams This indicator is defined as the number of violations sited in a specific time period by 7,000 hours0 days 0 hours 0 weeks 0 months , then dividing in NRC inspection reports for FCS per 1,000 NRC inspec-that number by the total number of hours critical in the tion hours. The violations are reported in the year that the same time period. The indicator is further defined as inspection was actually performed and not based on when follows: the inspection report is received. The hours reported for t

1) Unplanned means that the scram was not an antici- each inspection report are used as the inspection hours.

pated part of a planned test.

2) Scram means the automatic shutdown of the reactor VOLUME OF LOW-LEVEL SOLID RADIOACTIVE by a rapid insertion of negative reactivity (e.g., by control WASTE rods, liquid injection system, etc.) that is caused by ac- This indicator is defined as the volume of low-level solid ,

tuation of the reactor protection system. The scram sig- radioactive waste actually shipped for burial. This indica- '

nal may have resulted from exceeding a setpoint or rnay tor also shows the volume of low-level radioactive waste have been spurious, which is in temporary storage, the amount of radioactive

3) Automatic means that the initial signal that caused oil that has been shipped off-site for processing, and the actuation of the reactor protection system logic was pro- volume of solid dry radioactive waste which has been vided from one of the sensors monitoring plant param- shipped off-site for processing. Low-level solid radioactive eters and conditions, rather than the manual scram waste consists of dry active waste, sludges, resins, and switches or, in manual turbine trip switches (or push-but- evaporator bottoms generated as a result of nuclear power tons) provided in the main control room. plant operation and maintenance. Dry radioactive waste

4) Critical means that during the steady-state condition of includes contaminated rags, cleaning materials, dispos-the reactor prior to the scram, the effective multiplication able protective clothing, plastic containers, and any other factor (k,,) was essentially equal to one. material to be disposed of at a low-level radioactive waste disposal site, except resin, sludge, or evaporator bottoms.

UNPLANNED CAPABluTY LOSS FACTOR Low-level refers to all radicactive waste that is not spent The ratio of the unplanned energy losses during a given fuel or a by-product of spent fuel processing. This indica-period of time, to the reference energy generation (the tor tracks radiological work performance for SEP #54.

energy that could be produced if the unit were operated continuously at full power under reference ambient con-ditions) over the same time period, expressed as a per-centage.

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 result from reaching an ECCS actuation setpoint or from a spurious / inadvertent ECCS signal.

2) The number of unplanned emergency AC power sys-tem actuations that result from a loss of power to a safe-guards bus. An unplanned safety system actuation oc-curs when an actuation setpoint for a safety system is reached or when a spurious or inadvertent signal is gen-77

SAFETY ENHANCEMENT PROGRAM INDEX The purpose of the Safety Enhancement Program (SEP) Perfortnance Indicators index is to list perfor-mance indicators related to SEP items with parameters that can be trended.

SEP Reference Number 15 .

EaSa increase HPES and IR Accountability Through Use of Performance Indicators Procedural Noncompliance Incidents (Maintenance) ... . . . . . . .. . .. .49 Clean Controlled Area Contaminations 21,000 Disintegrations / Minute Per Probe Area.. . .5 Recordable injury / Illness Cases Frequency Rate . . .. . . . , . .4 Preventable / Personnel Error LERs . . . . .. . .. .. .. . ...6 SEP Reference Numbar 24 Complete Staff Studies Staffing Level . .. ... . .. . . . . . 42 SEP Reference Numbar 25 Training Program for Managers and Supervisors implemented Disabling injury / Illness Frequency Rate . .. .. . .. . . .. ....3 Recordable injury / Illness Cases Frequency Rate ... . . . . . . . . .4 SEP Reference Number 26 Evaluate and implement Station Standards for Safe Work Practice Requirements Disabling injury / Illness Frequency Rate . . .. . . . ..3 Recordable injury / Illness Cases Frequency Rate . . . .4 SEP Reference Numbar 27 Implement Supervisory Enforcement of Industrial Safety Standards Disabling injury / Illness Frequency Rate . . . . . . . .. .3 Recordable injury / Illness Cases Frequency Rate . . . . . . .4 SEP Reference Number 31 Develop Outage and Maintenance Planning Manual and Conduct Project Management Training MWO Planning Status (Cycle 16 Refueling Outage). . . . .. . .. . . . . 66 Overall Project Status (Cycle 16 Refueling Outage).. . ..Not Reported until Laterin 1994 Progress of Cycle 16 Outage Modification Planning . . .. .. .. . . . 67 SEP Reference Number 33 Develop On-Line Maintenance and Modification Schedule Percent of Completed Scheduled Maintenance Activities (All Maintenance Crafts).. .. . . . .. . .. . . . . . . 50 SEP Reference Number 38 Reduce Corrective Non-Outage Backlog Maintenance Workload Backlogs (Corrective Non-Outage). . . . . . . 45 SEP Reference Number 41 Develop and implement a Preventive Maintenance Schedule Ratio of Preventive to Total Maintenance & Preventive Maintenance items Overdue . . .46 Procedural Noncompliance Incidents... . . . . .

.. 49 SEP Reference Number 43 Implement the Check Valve Test Program Check Valve Failure Rate.. . . .. . .. . . . . . . . . . . . .36 78

SAFETY ENHANCEMENT PROGRAM INDEX (continu::d)

SEP Reference Numbar 44 Pace Compliance With and Use of Procedures Procedural Noncompliance incidents (Maintenance) . . . . .. . . . .. . . . 4 9 SEP Reference Number 48 Design a Procedures Control and Administrative Program Document Review ... . . .. . .. . . .. .. .. . 55 SEP Reference Number 52 Establish Supervisory Accountability for Workers Radiological Practices Radiological Work Practices Program. . .. . . . . . . . 54 SEP Reference Number 54 Complete implernentation of Radiological Enhancement Program Collective Radiation Exposure .. . . .. ..... ... .. . . . . . .16 Volume of Low-Level Solid Radioactive Waste. . .. . . .. . .. .. .37 Clean Controlled Area Disintegrations 21,000 Counts / Minute Per Probe Area . . . . . .5 Contaminated Radiation Controlled Area.. . .. . . . . . . . . . . . . . . . 53 SEP Reference Number 58 Revise Physical Security Training and Procedure Program Loggable/ Reportable incidents (Security) . .. . . . . 56 SEP Reference Number 60 Improve Controls Over Surveillance Test Program Number of Missed Surveillance Tests Resulting in Licensee Event Reports. . . . 20 SEP Reference Number 61 Modify Computer Program to Correctly Schedule Surveillance Tests Number of Missed Surveillance Tests Resulting in Licensee Event Reports. . .. . 20 SEP Reference Number 62 Establish Interim System Engineers Temporary Modifications. )

. . . . . . . . .. . . . . . . . . . . . .. . . 57 !

Engineering Assistance Request (EAR) Breakdown.... . .. . .. . . . . 59 Engineering Change Notice Status . . .. . . . . . . . . . . . . . . . .. .. . 60 Engineering Change Notices Open. .. ... . . . . . .. . .. .. .. 61 SEP Reference Number 88 Assess Root Cause of Poor Operator Training and Establish Means to Monitor Operator Training Licensed Operator Requalification Training . . .. . .. . . .. . 63 License Candidate Exams.. . . . . . .. . . . . . . . . .. . .. . . . 64 SEP Reference Number 71 Improve Controls over Temporary Modifications Temporary Modifications. .. . . . . . . . . . . .... ..... ..57 79

REPORT DISTRIBUTION LIST R.L Andrews B. R. Livingston G. L. Anglehart D. L Lovett K. L Belek J. H. MacKinnon B. H. Biome J. W. Marcil C. E. Boughter N. L Marfice C. J. Brunnert R. D. Martin G. R. Cavanaugh T. J. Mcivor J. 'N. Chase K. A. Miller A. G. Christensen Nuclear Licensing O. J. Clayton & Industry Affairs R. P. Clemens J. T. O'Connor R. G. Conner W. W. Orr J. L. Connolley T. L Patterson G. M. Cook R. T. Pearce D. C. Dietz R. L. Phelps H. J. Faulhaber R. L. Plott M. T. Frans W. J. Ponec D. P. Galle C. R. Rice S. K. Garrbhir A. W. Richard J. K. Gasper D. G. Ried W. G. Gates G. K. Samide

. M. O. Gautier M. J. Sandhoefner S. W. Gebers F. C. Scofield L. V. Goldborg H. J. Sefick R. H. Guy J. W. Shannon J. B. Herman R. W. Short -

K. C. Holthaus C. F. Simmons C. K. Huang E.L.Skaggs C.J. Husk J. L Skiles T. W. Jamieson F. K. Smith R. L. Jaworski R. L. Sorenson R. A.Johansen K. E. Steele W. C. Jones M. A. Tesar i

J. D. Keppler J. J. Tesarek '

D. D. Kloock J. W. Tills L T. Kusek J. M. Waszak M. P. Lazar S. J. Wilfrett i

1 80

FORT CALHOUN STATION OPERATING CYCLES AND REFUELING OUTAGE DATES i Event Date Range Production (MWH) Cumulative (MWH)

Cycle 1 09/26/73 -02/01/75 3,299,639 3,299,639 1st Refueling 02/01/75 -05/09/75 *

Cycle 2 05/09/75 -10/01/76 3,853,322 7,152,961 2nd Refueling 10/01/76-12/13/76 * *

)

Cycle 3 12/13/76 - 9/30/77 2,805,927 9,958,888 3rd Refueling 09/30/77 -12/09/77 *

Cycle 4 12/09/77-10/14/78 3,026,832 12,985,720 4th Refueling 10/14/78-12/24/78 *

Cycle 5 12/24/78- 01/18/80 3,882,734 16,868,454 Sth Refueling 01/18/80 - 06/11/80 *

Cycle 6 06/11/80 - 09/18/81 3,899,714 20,768,168 6th Refueling 09/18/81 - 12/21/81 *

Cycle 7 12/21/81 - 12/06/82 3,561,866 24,330,034 7th Refueling 12/06/82 - 04/07/83 *

Cycle 8 04/07/83 - 03/03/84 3,406,371 27,736,405 8th Refueling 03/03/84 -07/12/84 *

Cycle 9 07/12/84 - 09/28/85 4,741,488 32,477,893 9th Refueling 09/28/85- 01/16/86

Cycle 10 01/16/86 - 03/07/87 4,356,753 36,834,646 10th Refueling

03/07/87 - 06/08/87

Cycle 11 06/08/87 - 09/27/88 4,936,859 41,771,505 ;

11th Refueling 09/27/88 - 01/31/89 *

Cycle 12 01/31/89- 02/17/90 3,817,954 45,589,459 12tb Refueling 02/17/90- 05/29/90 *

Cycle 13 05/29/90- 02/01/92 5,451,069 51,040,528 13th Refueling 02/01/92- 05/03/92 *

Cycle 14 05/03/92-09/25/93 4,981,485 56,022,013 14th Refueling 09/25/93-11/26/93 *

Cycle 15 *

11/26/93 - 03/11/95 151h Refueling 03/11/95- 04/29/95 (Planned Dates) )

1 FORT CALHOUN STATION CURRENT PRODUCTION AND OPERATIONS " RECORDS" First Sustained Reaction August 5,1973 (5:47 p.m.)

First Electricity Supplied to the System August 25,1973 i Commercial Operation (180,000 KWH) September 26,1973 I Achieved Full Power (100%) May 4,1974 l Longest Run (477 days) June 8,1987 Sept. 27,1988 Highest Monthly Net Generation (364,468,800 KWH) October 1987 i Most Productive Fuel Cycle (5,451,069 MWH)(Cycle 13) May 29,1990 Feb.1,1992 l l

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ML20065R153

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