ML20086P484

Performance Indicators, for June 1995

ML20086P484
Person / Time
Site:	Fort Calhoun
Issue date:	06/30/1995
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20086P483	List: LIC-95-0145, Forwards Fort Calhoun Station Performance Indicators, for June 1995 ML20086P484
References
NUDOCS 9507270026
Download: ML20086P484 (100)

Text

--

FORT CALHOUN STATION PERFORMANCE INDICATORS e

t JUNE 1995 SAFE OPERATIONS PERFORMANCE EXCELLENCE COST EFFECTIVENESS

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J OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT i

l Prepared By:

Production Engineering Division System Engineering Test and Performance Group JUNE 1995 l

i L

l FORT CALHOUN STATION JUNE 1995 MONTHLY OPERATING REPORT j

i 4

OPERATIONS

SUMMARY

During the month of June, FCS operated at a nominal 100% power. Normal plant maintenance, surveillance, and equipment rotation activities were performed during the j

month, in addition to scheduled on-line modification activities. Modifications for the Diesel j

Generator No.1 starting air and for the Control Room Ventilation Units were completed.

On June 2nd, a one-hour report was made to the NRC, in accordance with'10 CFR 50.72(b) (1) (ii) (B), regarding the new fuel storage rack not meeting the technical specification requirements for seismic classification. An evaluation was completed certifying operability without fuel stored in the rack.

l On June 3rd, instrument inverter"D" was declared inoperable due to a shorted cable in the bypass transformer. The eight-hour Technical Specification Limiting Condition for Operation (LCO) 2.7 was entered and the inverter was restored to operable status within the required time-frame.

In response to the leaking fuel experienced by FCS, Westinghouse personnel were in the plant several days performing fuel sipping operations. The sipping equipment has been removed from the Spent Fuel Pool.

O i

FORT CALHOUN STATION JUNE 1995 MONTHLY OPERATING REPORT OPERATIONS

SUMMARY

(Continued)

The NRC Resident Monthly inspection, inspection No. 95-07, was completed during this reporting period. The following Licensee Event Reports (LERs) were submitted during this reporting period:

LER 94-010, Rev. 2 Potential Accident Scenario involving Loss of Control Room Air Conditioners LER 95-003 Manual Reactor Trips Due to Water Leakage into Reactor Coolant Pump Lube Oil LER 95-004 Discrepancy Regarding Seismic Classification of New Fuel Storage Racks 1

e il

i i

I Year-To-Date Value t

i Performance Cateoories ii ii

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a Performance in !ndustry

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$waardesd Unplanned Th, 9, ShinneAag :d Unplanned jjAutomatic fWarTance MI Upper 10% and better Unit than 1995 OPPD goal h

Scrams /7,000 l

p ]j Capability Capability n

Loss Factor i j

Factor Hours Crit lT l

~l Performance Better Than

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t-1995 OPPD Goal l

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Performance Not Meeting Am SaW EM Safey HPSI Safety

, P System System 3 Reliability 4 1995 OPPD Goal Sys h Performance Performance Nindidat6r[

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Year-To-Date

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"ox value 1995 Year-End ll l

Performance Piomarce i

INPO PERFORMANCE INDICATORS m

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Scrams hi Year-To-Date Value Performance Cateaories Crit

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Performance Better Than Industry Average Trend hb i

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fra Performance Better Than 1995 OPPD Goal i

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Performance Not Meeting 1995 OPPD Goal or Industry Average Trend SnNt Forced r

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Exposure NRC PERFORMANCE INDICATORS a

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FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT JUNE 1995 -

SUMMARY

J POSITIVE TREND REPORT POSITIVE TREND REPORT (continued)

A performance indcator with data represenbng three Hazardous Weste Produced consecutrve months of improving performance or three (Page 53) consecutve months of performance that is superior to the stated goal is exhibiting a pcsitive trend per Nuclear Contaminated Radation Controlled Area Operations DMeion Quahty Procedure 37 (NOD-QP-37).

(Page 54) i The following performance indicators exhibited positive End of Positrve Trend Report.

trends for the reporting month:

Safety System Failures ADVERSE TREND REPORT (Page 7)

A performance indicator wth data represenbng three i

Hiah Pressure Safety iniection System Safety System consecutive months of declining performance or three Performance consecutrve months of performance t?at is trending (Page 8) toward dedning as determined by the Manager - Station i

Engineering, constrtutes an adverse trend per Nuclear Emeraency AC Power System Safety Swtem Operabons DMaion Quahty Procedure 37 (NOD-QP-37).

I Performance A supervisor whose performance indcator exhibrts an i

(Page 10) adverse trend by this dellnihon may specify in wntten form (to be pubhshed in this report) why the trend is not i

Emeroenev Diesel Generator Unrt Rehabiltty adverse.

(Page 11)

The folowing performance indicators exhibited adverse j

Diesel Generator Reliabiktv (25 Demandg}

trends for the reporbng month:

(Page 12)

Industrial Safety Accident Rate Emeroency Diesel Generator Unrehabihty (Page 2)

(Page 13)

Disabilina IniurvMuness Freauency Rate (Lgpt-Time Sionificant Events Accident Rate (Page 20)

(Page 3) l Missed Surveillance Tests Results in Licensee Event Maintenance Workload Backloos Reports (Page 46) 1 (Page 21)

End of Adverse Trend Report.

Unolanned Auto Scrams per 7.000 Hours Cnbcal (Page 29)

INDICATORS NEEDING INCREASED i

Unolanned Safety System Actuabons (INPO Definibon)

MANAGEMENT ATTENTION REPORT (Page 30)

A performance indcator with data for the reporting period Unolenned Safety System Actuations (NRC Definttion) that is inadequate when compared to the OPPD goalis (Page 31) defined as *Needing increased Management Attention" per Nuclear Operabons DMaion Quatrty Procedure 37 Pnmary Svetem Chemistry Percent of Hours Out of Limit (NOD-QP-37).

(Page 39)

The following performance indicators exhibited positive Secondary System Chemistry trends for the reporbng month:

(Page 40)

Recordable IniurvMliness Freauenev Rate Cents Per Kilowatt Hour (Page 4) l (Page 42) in-line Chemistry Instruments Out-of-Service (Page 52) v

FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT JUNE 1995 -

SUMMARY

INDICATORS NEEDING INCREASED MANAGEMENT ATTENTION REPORT (continued)

Fuel RehabihtvIndicator Page 14 Temporary Mod 6 cations (Page 58) t PERFORMANCE INDICATOR REPORT IMPROVEMENTSICHANGES This sechon lists significant changes made to the report and to specific indicators within the report since the j

previous month.

Number of Control Room Eauipment De6ciencies (Page 15)

This graph has been revised to indicate the Control Room Deficiencies Added and Completed, Completed with Target Completion Date, and the Completion Rate.

Number of On-Line and Outane Control Room Eauipment De6ciencies (Page 16)

The is a new graph to show the number of Orbline and Outage Control Room Deficiencies, and the number of overdue Control Room Deficiencies.

Open Incident Reoorts (Page 66)

I Open Co-ce Action Reports (CARS) have been

]

removed as a pvrformance in$cator since they are no longe: being useo.

A computer system automebon is currently underway to more efficiently utikze computer equipment to colect, anafyze and produce data for the performance indicator report.

j j

End of Report improvements / Changes Report l

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Table of Contents / Summary enan ooALs...................................................................x SAFE OPERATIONS 6

..........2 Industrial Safety Accident Rate - lNPO..........

....3

. Disabling injury / Illness Cases Frequency Rate.........

Recordable injury / Illness Cases Frequency Rate.................

.4 Clean Controlled Area Contaminations

!>.1,000 Disintegrations / Minute per Probe Area

,. 5 1

Preventable / Personnel Error LERs......................

...... 6 1

i Safety System Failures

.......................... 7 i

Safety System Performance:

High Pressure Safety lnjection System....

.8 j

............... 9 Auxiliary Feedwater System Emergency AC Power System 10 Emergency Diesel Generator

)

Unit Reliability

.. 11 12

'l Reliability (25 Demands)

Unreliability........

13

)

14 i

Fuel Reliability lndicator..

i Control Room Equipment Deficiencies

......................................15 On-Line and outage Control Room Deficiencies............

... 16 i

Collective Radiation Exposure......

17 j

Maximum individual Radiaton Exposure..

18 Violation Trend......

.... 19 20 Significant Events..

Mssed Surveillance Tests Resulting in LERs.......................

21 vii 1

1

Table of Contents / Summary PERFORMANCE P. AGE Station Net Genes ation..................................

.......... 23 Forced Outage Rate.............................

24

.........25 Unit Capacity Factor.....

Equivalent Availability Factor.......

26 Unit Capability Factor 27 Unplanned Capability Loss Factor

...........28 Unplanned Automatic Reactor Scrams per 7,000 Hours Critical.........

29 Unplanned Safety System Actuations INPO Definition..

...... 30 NRC Definition 31 Gross Heat Rate...

.... 32 Thermal Performance.........

.....................................33 Daily Thermal Output...

34 Equipment Forced Outages per 1,000 Critical Hours

................ 35 Component Failure Analysis Report (CFAR) Summary......

.... 36 Repeat Failures 37 Volume of low-Levet Solid Radioactive Waste

...... 38 Primary System Chemistry Percent of Hours out of umit............................

39 Secondary System Chemistry......

40 COST i

Cents Per Kilowatt Hour.

42 Staffing Level

.....43 i

Spare Parts inventory Value

............ 44 1

I i

l v

i

Table of Contents / Summary DMSiON AND DEPARTMENT PERFORMANCE INDICATORS PAGE Maintenance Workload Backlogs (Corrective Non-Outage)..................................... 46 Ratio of Preventive to Total Maintenance & Preventive Maintenance items Overdue........ 47 Percentage of Total MWOs Completed per month identified as Rework...............

48 O ve rtime.................................................

49 P rocedural Noncompliance lncidents

.......... 50 lally Schedule Performance - Percent of Completed Scheduled Actnees............ 51 In-Lin9 Ct.0mistry instruments Out-of-Service

... 52 e

Hazardous Waste Produced.............

.. 53 Contaminated Radiation Controlled Area..

......... 54

...... 55 Radiological Work Practices Program Document Review 56 Loggable/ Reportable incidents (Security)..

57 Modifications j

Temporary..

........... 58 Outstanding

......................59 Engineering Assistance Request (EAR) Breakdown..

60 i

Engineering Change Notices J

61 Status Open 62 1

Licensee Event Report (LER) Root Cause Breakdown.

. 63 Licensed Operator Requalification Training

........ 64 License Candidate Exams..............................................

65

]

Open incident Reports 66 i

l Cycle 17 Refueling Outage i

MWO Planning Status 67 Outage Modification Planning 68 On-Line Modification Planning..

..... 70 Progress of i995 On-Une Modification Planning........

... 69 ACTION PLANS. DEFINITIONS. SEP INDEX & DISTRIBUTION LIST Action Plans........................

...... 72 i

Performance Indicator Definitions.....

74

)

i Safety Enhancement Program index

. 82 1

Report Distribution List

.... 84 i

IX

i OPPD NUCLEAR ORGANIZATION GOALS Vice President-1995 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 Supports: April 1994 Corporate Strategic Plan Goal 3, Obj: 3 & 4 A proactive, self-critical and safety conscious culture is exhibited throughout the nuclear organization. Individuals demonstrate professionalism through self-ownership and personal initiative and open communication.

1995 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.

=

Objectives to support SAFE OPERATIONS.

OBJECTIVE 1-1:

l No challenges to a nuclear safety system.

OBJECTIVE 1-2:

Conduct activities in accordance with applicable policies, technical specifications, procedures, stanrfing orders and work instructions.

Less than 1.4 NRC violations per 1,000 inspection hours.

Fewer significant Corrective Action Documents (CADS) originating from activities.

OBJECTIVE 1-3:

identify conditions BEFORE they affect plant safety and reliability.

i i

OBJECTIVE 1-4:

Achieve all safety-related 1995 performance indicator goals in the Performance Indicator Report.

OBJECTIVE 1-5:

Zero Lost Time injuries and recordable injuries rate BELOW 1.5 percent.

1 X

l

i OPPD NUCLEAR ORGANIZATION GOALS i

Vice President-1995 Priortbes faggjj:

PERFORMANCE Supports: April 1994 Corporate Strategic Plan Goal 3, Obj: 2 and Goal 4, Obj: 1 i

Achieve high standards of performance at Fort Calhoun Station resulting in safe, reliable and cost effective power production.

l 1995 PRIORITIES-Improve Quality, 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.

Objectives to support PERFORMANCE:

OBJECTIVE 2-1:

Achieve an annual plant capacity factor of 70% and a unit capability factor of 81%.

i OBJECTIVE 2 >

Execute the 1995 refuelina outage in 49 days; emphasize shutdown plant safety.

OBJECTIVE 2-3:

j Achieve all performance related 1995 performance indicator goals in the Performance Indicator Report.

OBJECTIVE 2 4:

l All projects and programs are planned, scheduled, and accomplished according to schedules, resource constraints, and requirements.

i OBJECTIVE 2-5:

i Team //ndividualownership, accountability, performance and teamwork is evident by improved plant -

reliability; improved ratings for both INPO and NRC; reduced number of human performance errors and identification of performance problems by effective self assessment and for individuals as measured by the successful compkrtion of department goals & objectives and other specific measures.

e' e

xi

OPPD NUCLEAR ORGANIZATION GOALS Vice President-1995 Priorities goal 3:

COSTS Supports: April 1994 Corporate Strategic Plan Goal 2, Obj: 1,2 and 3, and Goal 6, Obj: 1 l

Operate Fort Calhoun in a manner that cost effectively maintains nuclear generation as an economically viable contribution to OPPD's " bottom line". Cost consciousness is exhibited at alllevels of the organization.

i 1995 Priorities:

Maintain total O&M and Capital Expenditures within budget.

Streamline work process to improve cost effectiveness.

Objectives to support COSTS:

OBJECTIVE 3-1:

Conduct the nuclear programs, projects, and activities within the approved Capital and O&M budgets.

OBJECTIVE 3-2:

Implement nuclear related Opportunity Review recommendations according to approved schedules and attain the estimated cost savings.

i I

Goals Source:

Scofield (Manager) xii

O SAFE OPERATIONS

~

Goal: A proactive, self-critical and safety conscious culture is exhibited throughout the nuclear organization. Individu-als demonstrate professionalism through self-ownership and personal initiative and open communication l

e I

I i

J

-*- Year-to-Date FcS Industrial Safety Accident Rate (INPo Definition)

-e-FCS Average Rate (Last 12 Months)

-*- FCS Year-End Goal (<0.50) l Good]

-e-Industry Current Best Quartile (.24)

-+- 1995 INPo industry Goal (<0.50) k 2-1.5-f 0.5{ j}

((

3 3

O I

I 5

I I

I I

Jan Feb Mar Apr May Jun Jul Aug Sep oct Nov Dec 1995 INDUSTRIAL SAFETY ACCIDENT RATE As stated in INPO's December 1993 publication ' Detailed Descriptions of World Associa-tion of Nuclear Operators (WANO) Performence Indicators and Other Indicators for Use at U.S. Nuclear Power Plant': 'The purpose oj this indicator is to monitor progress in improv-ing industrial safety performance for utility personnel permanently assigned to the station."

The INPO industrial safety accident rate value year to date was 1.81 at the end of June 3

1995. The value for the 12 months from July 1,1994, thicugh June 30,1995, was 0.94.

There were no restricted-time and two lost-time accidents in June 1995. These acci-dents were described as (1) a hurt lower back while completing physical agility crunch test, and (2) a shoulder and cervical strain while crounching under a traveling screen cover to remove bolts. There have been no restricted and seven lost-time accidents during the year 1995.

The values for this indicator are determined as follows:

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

The 1995 Fort Calhoun year-end goal is 50.50. The 1995 INPO industry goal is <0.50.

The approximate industry upper ten percentile value (for the period from 7/93 through 6/94) is 0.12.

.l Data Source:

Sorensen/Skaggs (Manager / Source)

Chase / Booth (Manager / Source)

Accountability:

Chase / Conner Adverse Trend 2

+ 1995 Disabling injury / Illness Frequency

--M-1994 Disabling injury / Illness Frequency

+ Average Rate (Last 12 Months) l GOOD l

-e-1995 Goal (0.50) t 2-1.8 -

.1.6 -

1.4 -

J 1.2 -

0.8

^

0.6 -

0.4

~

~ Y

~

~

E

[

^

0.2 -

03 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1995 DISABLING INJURY /lLLNESS FREQUENCY RATE (LOST-TIME ACCIDENT RATE)

This indicator shows the 1995 disabling injury / illness frequency rate. The 1994 disabling injury / illness frequency rate is also shown.

The disabling injury / illness frequency rate year to date was 1.81 at the end of June 1995.

There was two disabling injury / illness cases reported for the month. - These injuries were described as (1) a lower back injury while completing a physical agility test, and (2) a shoulder and cervical strain while crouching under a traveling screen cover to remove bolts. There have been seven disabling injuries in 1995.

The disabling injury / illness frequency rate for the 12 months from July 1,1994, through June 30,1995, was 1.07.

The 1995 Fort Calhoun year-end goal for this indicator is a maximum value of 0.5.

J t

Data Source:

Sorensen/Skaggs (Manager / Source)

Accountability:

Chase / Conner Adverse Trend SEP 25,26 & 27 3

+

- o-- 1995 Rooordable injuryntiness Frequency

-M - 1994 Recordable injuryntiness Frequency l Good l

-* - Average Rate (Last 12 Months)

+ F.wt Calhoun Goal y

2.s -

2.25 -

2-n 1.5,

~

1.25 -

A 1-0.75 0.5 -

0.25 -

0 :.

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov-Dec 1995 RECORDABLE INJURY /lLLNESS FREQUENCY RATE This indicator shows the 1995 recordable injury / illness frequency rate. The 1994 record-able injury / illness cases frequency rate is also shown A recordable injury / illness case is reported if personnel from any of the Nuclear Division 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.

There have been six recordable injury / illness cases in 1995. The recordable injury /ill-ness cases frequency rate year to date was 1.55 at the end of June 1995. There were two recordable injury / illness case reported for the month of June. These injuries were the result of (1) a lower back injury while completing a physical agility test, and (2) heat exhaustion while fighting fire in a training scenario.

The recordable injury / illness cases frequency rate for the 12 months from July 1,1994, through June 30,1995, was 1.20.

i The 1995 Fort Calhoun year-end goal for this indicator is a maximum value of 1.5.

Data Source:

Sorensen/Skaggs (Manager / Source)

Accountability:

Conner.

l Adverse Trend:

None SEP 15,25,26 & 27 1

M Contamination Events (Monthly)

- *-- contamination Events (YTD) l GOOD l 60 -

Y 60 -

42 g.

39 31

s 30 _

20 -

h ip

r g

3 E

E O

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1995 CLEAN CONTROLLED AREA CONTAMINATIONS 21,000 DISINTEGRATIONSI MINUTE PER PROBE AREA 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 June 1995. There has been a total of 42 con-tamination events in 1995 through the end of June. This compares to 32 at this time last year.

Data Source:

Chase /Cartwright (Manager / Source) l Accountability:

Chase /Lovett Adverse Trend:

None SEP 15 & 54 5

EEER Personnel Errors (Each Month)

Preventable (18-Month Totals)

-e-Personnel Error (18-Month Totals) 4-12 -

10 -

8E

=

=

4-2 3

2-0 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1993 1994 1995 PREVENTABLE / PERSONNEL ERROR LERs 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 totals for Personnel Error LERs and the Personnel Error totals for each month. The LERs are trended based on the LER event data as opposed to the LER report date.

In May1995, there were no events which were subsequently reported as an LER. No LERs were categorized as Preventable or as a Personnel Error for the month of May.

The total LERs for the year 1995 (through May 31,1995) is three. The total Personnel Error LERs for the year 1995 is zero. The total Preventable LERs for the year is one.

The 1995 goal for this indicator is that the year-end values for the 18-month totals be no more than 12 Preventable and 5 Personnel Error LERs.

Data Source:

Trausch/Cavanaugh (Manager / Source)

Accountability:

Chase Adverse Trend:

None SEP 15 6

1 3

Startup Shutdom

[ GOOD l operation

- Industry Average Trend a.

15 1

n i

m a

R ma g

3 0

=

=

=

92-2 92 3 92-4 93-1 93-2 93-3 93 4 94-1 94-2 94-3 94-4 95-1 Year-Quarter SAFETY SYSTEM FAILURES This indicator illustrates 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. First Quarter 1994 through First Quarter 1995 are projected.

The following NRC safety system failures occurred before the second quarter of 1994; none have occurred since then.

First Quarter 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 cer--

tain 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 l

system to meet design requirements during a seismic event.

Fourth Quarter 1993: 1) During surveillance testing, both PORVs for the LTOP system failed to open during multiple attempts. The failures were a result of differential expansion caused by a loop seal, excessive venting line back pressure, and cracked valve disks; 2) Calibration errors of the offsite power low signal relays could have prevented offsite power from tripping and the EDGs from starting in the required amount of time during a degraded voltage condition; 3) Both AFW pumps were inoperable when one was removed from service for testing and the control switch for the other pump's steam supply valve was out of the auto position; 4) Only one train of control room ventilation was placed in recire when both toxic gas monitors became inoperable.

Later during surveillance, the other train auto-started and brought outside air into the control room for a six-minute period.

First Quarter 1994: A design basis review determined that an ESF relay could result in loss of safety injection and spray flow, due to premature actuation of recirculation flow.

Data Source:

Nuclear Regulatory Commission Accountability:

Chase Positive Trend 7

i j-i i

--+- 1ess montMy High Pressure SetWy in>chon System Uneveuebety Value

--m-sees Year to Oste High Pressure Safety in#ceon System UneveNaMity Value

-+- sees Fort Calhoun Goal (e.se4)

+ 1essINPOIndustryGoal(e.s2)

-e-Industry Upper se% (e.cott) 0.03 -

Dl 0.025 -

V t

0.02.

O.015 -

0.01 -

t m5 ;

o.om O!!

b 3

3 5-3 Y

Y 5

Y Y

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1995 i

i 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 repot' ting month.

i j

The High Pressure Safety System unavailability value for the month of June 1995 was i

0.0. There was 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of planned unavailability, and 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned unavailability,

)

during the month. The 1995 year-to-date HPSI unavavailability value was 0.0002 at the l

i end of the month. The unavailability value for the last 12 months was 0.0027.

There has been a total of 1.83 hours9.606481e-4 days <br />0.0231 hours <br />1.372354e-4 weeks <br />3.15815e-5 months <br /> of planned unavailability and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned unavailability for the high pressure safety injection system in 1995.

The 1995 Fort Calhoun year-end goal for this indicator is a maximum value of 0.004. The

-I 1995 INPO industry goal is 0.02 and the industry upper ten percentile value (for the three-year period from 1/92 through 12/94) is approximately 0.001.

Data Source:

Jaworski/Schaffer Accountability:

Jaworski/Schaffer Positive Trend 8

r

)

av.

~

i m Monthly Auxiliary Feedwater System unavailability

-M-Year-to-Date Emergency AC Power unavailability

-e-Fort Calhoun Goal (0.01) lo000l

-*- 1995 INPO Industry Goal (0.025) 9

-e-Industry upper 10% (0.0021)

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0.03 -

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=

0.025 -

b c

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0.02.

A a

a a

a a

a t.

4 kb e.t J

0.015 -

S i

0.01,

0.005 r.q C

=

=

0 0

3 FA n V "=

1994 Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec UnavailabiHty 1995 value AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Auxiliary Feedwater System Unavailability value, as defined by lNPO in the Safety System Performance Indicator Definitions, for the reporting month.

The Auxiliary Feedwater System Unavailability Value for June 1995 was 0.0. There were 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of planned and 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned unavailability during the month. The year-to-date unavailability value was 0.00475 and the value for the last 12 months was 0.00575 at j

the end of the month.

There has been a total of 27.68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> of planned unavailability and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of un-planned unavailability for the auxiliary feedwater system in 1995.

The 1995 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 is ap-proximately 0.002.

Data Source:

Jaworski/Nay Accountability:

Jaworski/Nay Adverse Trend:

None 9

i Monthly Emergency Ac Power Unavailability Value

+4 I

0.06 -

--*- Fort Calhoun Goal (0.024) l GOOD l 0

1995 INPO Industry Goal (0.025)

-e-Industry Upper 10% (0.0035) y

~

0.04 -

~

0.03 -

3 3

3 3

3 3

3 3

3 3

3 0.02 -

0.01 -

0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1995 EMERGENCY AC POWER GYSTEM 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 June 1995 was 0.0042. Dur-ing the month, there were 6.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of planned unavailability for testing, and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned unavailability. The Emerge, icy AC Power System unavailability value year-to-date was 0.00396 and the value for the last 12 months was 0.00672 at the end of the month.

There has been a total of 34.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of planned unavailability and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned unavailability for the emergency AC power system in 1995.

The 1995 Fort Calhoun year-end goal for this indicator is a maximum value of 0.024.

(

The 1995 INPO industry goal is 0.025 and the industry upper ten percentile value is ap-l proximately 0.0035.

Data Source:

Jaworski/Ronning Accountability:

Jaworski/Ronning l

Positive Trend based on performance better than goal l

10 l

l

i M Failures /20 Demands E"-"3 FailuresI60 Demands M Failures /100 Demands

-e-Trigger Values /20 Demands l Good l

--er-- Trigger Valuesf50 Demands

--o-Trigger Values 100 Demands 8 --

7 6

6 a

e a

a 4

3-2 2

1 1

1 1

1 11 111 11 11 11 11 11 00 00 00 00 00 0

0 0

0 0

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 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 values. The Fort Calhoun 1995 goal is to have fewer failures than these trigger values.

The last failure to start was the result of DG-1 damper failure on December 8,1994.

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 followed by load-run demands, whether by automatic or manual initiation. 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 minimum of one hour and to be loaded with at least 50% of design load (see exceptions and other demand cri;eria in the Definition Section of this report).

Data Source:

Jaworski/Ronning (Manager / Source)

Accountability:

Jaworski/Ronning Positive Trend I

1 11 l

- -.~

. -.. ~...

-- ~..

i CD DG-1 Failureel25 Demands l

DG-2 Fa61ures/25 Demands l0000l l

5-7 4-C 2

0 O

C 3

j t

3-i k

2-1 1

1 1

1 1

1 '

1-I oo eo ee oe oo o

e e

o o

e e

0 Jul Aug sep oct Nov Dec Jan Feb Mar Apr -

May Jun 1994 1995 i

DIESEL GENERATOR RELIABILITY (25 DEMANDS) 7 i

This indicator shows the number of failures experienced by each emergency diesel gen-1 erator 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-j within 25 demands is the Fort Calhoun goal for 1995.

i i

it must be emphasized that, in accordance with NUMARC criteria, certain actions will take 1

place in the event that any one emergency diesel generator experiences 4 or more fail-ures within the last 25 demands on the unit. These actions are described in the Defini-l tions Section of this report. A System Engineering instruction has been approved for the I

I Fort Calhoun Station to institutionalize and formally approve / adopt the required NUMARC actions.

Diesel Generator DG-1 has experienced one failure during the last 25 demands on the i

unit. On December 8,1994, DG-1 failed its monthly surveillance test because the inlet air damper would not open. The cause of the failure was found to be ice buildup on the j

damper louvers from a previous snowstorm.

l i

Diesel Generator DG-2 has not experienced any failures during the last 25 demands on the unit.

ll t

Data Source:

Jaworski/Ronning (Manager / Source)

Accountability:

Jaworski/Ronning j

Positive Trend due to performance better than goal j

12 l

.i

• D01 Unreliability Value MIlm DO-2 UnreliabilityValue l Good l

--+- Station Unreliability Value p

--e-- 1995 Goal

--e-- Industry Upper 10% (0.002 for a 3-Year Average) 0.07 -

0.06 -

O.05 -

C 0

0 0

0 0

0.04 -

0.03 -

0.02 -

00 00 00 00 00 0

00 00 00 00 00 00 9

9 9

9 9

9 0

9 9

9 9

9 m

Jul Aug Sep oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 i

EMERGENCY DIESEL GENERATOR UNRELIABILITY The purpose of this indicator is to monitor the likelihood that emergency AC power gen-erators will respond to off-normal events or accidents. It also provides an indication of the effectiveness of maintenance, operation and test practices in controlling generator unreliability.

The year-to-date station EDG unreliability at the end of May 1995 was 0.0. The 1995 goal i

for this indicator is a maximum value of 0.05.

l t

For DG-1:

There were 6 start demands for the reporting month without a failure.

i in addition, there was 2 load-run demand without a failure.

For DG-2:

There were 5 start demands for the reporting month without a failure.

In addition, there was 1 load-run demand without a 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 I

number of valid start demands LU = Load-run Unreliability = number of unsuccessful load-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

l Fuel Reliability

-*-- 1995 INPO Industry Fuel Defect Reference (5 x 10-4 Microcuries/ Gram) l GOOD l 1995 Goal y

a 5 20 -

3 5

~

cycle is l jg _

(

Remg

']

Outege f

0 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 FUEL RELIABILITY INDICATOR The FUEL RELIABILITY INDICATOR (FRI) for June 1995 was 19.15 X 104 microcuries/ gram. The pur-pose of the FRIis to monitorindustry progressin achieving and maintaining a high level of fuelintegrity. An effective fuel integnty and performance monitoring program provides a means to detect fuel failures and assess the fuel failure number, physical condition, exposure, mechanism, and location.

Cycle 16 plant operation started on April 13 and attained 100% power was achieved on April 23. During May, the plant operated at 100% power until May 11th when the plant was tripped and remained at hot shutdown ":onditions for repairs. The plant commenced power increase on May 15th obtaining 100% power on May 17th. The plant remained at 100% power until May 23rd when the plant was tripped and brought to a cold shutdown condition for replacement of Reactor Coolant Pump lubricant oil coolers. The plant re-mained at cold shutdown through May 28th. The plant once again commenced a power increase on May 29th. During the month of June the plant operated at 100% power.

The June FRI value of 19.15 X 104 microcuries/ gram indicated a significant increase from the May FRI value of 3.176 X 10-' microcunes/ gram due to an increase in fuel pin failures.. The Xenon activity has shown an increase throughout the cycle. In May, there were several lodine-131 spikes during the plant trips and also increasing lodine-131 values during 100% operation, indicating one or more failed fuel pins.

The INPO September 1992 report, "Petformance Indicators for US 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 x 10d microcuries/ gram indicates a high probability of reactor core operation with one or more fuel defects. The determination of current defect-free operation requires more sophisti-cated analysis by utility reactor engineers." The value of 5.0 x 104 microcuries/ gram is defined as a " Fuel i

Defect Reference" number of a "Zero LeakerThreshold." Each utility will evaluate whether the core is defect free or not. The 1995 Fort Calhoun Station FRI Performance Indicator goalis to maintain a monthly FRI

]

~

below 5.0 x 10-* microcuries/ gram.

Data Source:

Holthaus/ Weber Accountability:

Chase /Spijker Trend:

Needs increased Management Attention 14

m ControlRoomDeficiencies Added Controf Room Deficienciea completed i

M Completed within Target Completion Date O

Completion Rate 50 --

- 100.0 %

$7.5%

Goal. Corglete 80%of C.ft. De Aconces by TargetCormletan Date

• ~

-- 60.0%

E 30 -

?

8'

-- 40.0%

24 24 E

E

$ 20 -

2.

2.

20.0 %

u 10 i

t' I

- 0.0%

M ay 22-29, '95 Jun-95 Jul-95 Aug-95 Control Room Deficiencies NUMBER OF CONTROL ROOM EQUIPMENT DEFICIENCIES This indicator measures the timeliness of closing Control Room Deficiencies.

Target Completion Dates are established by the Emergent Work Committee. The goal is to close at least 80% of all CRD's within the Target Due Date.

l There were 24 Control Room Deficiencies completed during June 1995, and 16 were completed within the target completion date.

A Scheduling Coordinator has been assigned to track performance on a weekly basis and identify problem areas.

The 1995 Fort Calhoun goal for this indicator is a completion rate of 80%.

Data Source:

Chase / Walling (Manager / Source)

Accountability:

Chase /Faulhaber Adverse Trend:

None 4

15

Overdue

-+-- Number of On-Line Control Room Deficiencies -

35 82 30 -

^,

25 -

20 -

[

15 -

i 10 -

0 i

i t

i f

May45 Jun45 Jul45 Aug45

=

Number of On-Une CRD's l

overdue

-+- Number of Outage Control Room Deficiencies l

21*

+

20 -

to 15 -

l 10 -

i 5-a a

0 May-95 Jun45 Jul45 Aug45 Number of Outage CRD's Note: Overdue llems are those older then 18 months i

i NUMBER OF ON-LINE AND OUTAGE l

CONTROL ROOM EQUIPMENT DEFICIENCIES This indicator shows the total number of On-Line and Outage Control Room Deficiencies,,

and the number of overdue Control Room Deficiencies.

l 1

There were 30 on-line (6 were overdue) and 21 outage (2 were overdue) Control Room

)

Deficiencies at the end of June 1995.

The 1995 Fort Calhoun goal for these indicators are less than 8 overdue on-line and no overdue outage Control Room Deficiencies.

1 Data Source:

Chase / Waiting (Manager / Source)

Accountability:

Chase /Faulhaber/Clemens Adverse Trend:

None 16 1

)

m Monthly Personnel Radiation Exposure

-*-- Cumulative Personnel Radiation Exposure l GOOD l Fcs Goal (143.1 Person-Rem) 150 -

9 130,

0 120 -

110-100 -

)

$ m-w,o.

~

l 70 -

g 60 --

v 50 -

40 -

?:p 30 -

4 i

N" 1

0 e,-

Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec 1995

)

l COLLECTIVE RADIATION EXPOSURE The 1995 Fort Calhoun goal for collective radiation exposure is less than 143.1 person-Rem.

The exposure for June 1995 was 3.485 person-Rem (ALNOR).

The year-to-date exposure through the end of June was 132.083 person-Rem (TLD). The biggest contributor to dose in May was i

the outage (s) to repair RCW motor CCW cooler leakage.

The 1995 INPO industry goal for collective radiation exposure is 185 person-rem per year. The current industry best quartile is 145 person-rem per year. The yearly average for Fort Calhoun Station for the three years from 7/92 through 6/95 was 113.62 person-i rem per year.

Data Source:

Chase /Cartwright (Manager / Source)

Accountability:

Chase /Lovett Adverse Trend:

None SEP54 17

D Highest Exposure (June)

II Highest Exposure (1995)

OPPD 4500 mRemlyr. Limit 4000 -

3000 -

2000 -

1,2es 1000 --

242 I

I 0

l I

Highest Highest Exposure Exposure (June)

(1995)

MAXIMUM INDIVIDUAL RADIATION EXPOSURE During June 1995, an individual accumulated 242 mrem, which was the highest indi-vidual exposure for the month.

The maximum individual exposure for the year of 1,000 mrem was exceeded during March 1995 when an individual received 1,266 mrem (875 mrem of this was received during orifice plate repairin a steam generator). However, the OPPD 4500 MRemlyr limit is not expected to be exceeded.

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

year. The 1995 Fort Calhoun year-end goal is a maximum of 1,000 mrem.

l l

l l

1 Data Source:

Chase /Cartwright (Manager / Source)

Accountability:

Chase /Lovett Adverse Trend:

None I

l 18 j

l L___________.________________________________________________________

l 1

4 e FCS CatedViolations(Monthey)

C FCS Non4sted Vioiellons (Monthey)

GOOD l

- FCS Cated Wh (12-Month Average)

-e--

FCS Non40ted Violations (12-Month Average).

f

-e--

flogion IV Chad Vioistions (12 Month Average for llegion IV top aguertile) 14 -

12 -

~

~

l

~

10 -

~

~

~

8-1 6-I U

U' E

0 Jun Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May l

m 1984 1995 VIOLATION TREND This indicator illustrates a 12-month trend for Fort Calhoun Station Cited Violations, Non-Cited Violations and Cited Violations for the Top Quartile plants in Region IV. Addition-ally, the Fort Calhoun Station cited and non-cited violations for the past 12 months will be illustrated monthly. The 12-month trend for the Region IV top quartile lags 2-3 months behind the Fort Calhoun Station trend. This lag is necessary to compile information on other Region IV plants.

The following inspections were completed during June 1995:

i IER No.

Tina

~95-09 Monthly Resident Inspection To date, OPPD has received four violations for inspections conducted in 1995.

Levelill Violations 0

LevelIV Violations 2

Level V Violations 0

Non-Cited Violations 2

Total 4

The 1995 Fort Calhoun Station Goal for this performance indicator is to be at or below the cited violation trend for the top quartile plant in Region IV.

Data Source:

Trausch/Cavanaugh (Manager / Source)

Accountability:

Trausch Adverse Trend:

None 19

i Em NRc Significant Events

]

GOOD l 1

-e-Industry Average Trend 1

V g

0.5 --

p l

2 T

T l

0 2

92-2 92-3 92-4 93-1 93-2 93-3 93 4 94-1 94-2 94-3 94 4 95-1 Year - Quarter INPo significant Events (sERs) lo000l 2

I f

1 1

1 1

1 l

l 0

Id 0

i 92-2 92-3 92 4 93-1 93-2 93-3 93-4 94-1 94-2 94-3 94-4 95-1 r

Year - Quarter SIGNIFICANT EVENTS This indicatorillustrates the number of NRC and INPO Significant Events for Fort Calhoun Station as reported by the Nuclear Regulatory Commission's Office for Analysis and Evalu-ation of Operational Data in the biannual" Performance Indicators for Operating Commer-cial Nuclear Power Reactors" report and INPO's Nuclear Network.

I The following NRC significant events occurred between the second quarter of 1992 and the first quarter of 1995:

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),

occuaed between the second quarter of 1992 and the First Quarter of 1995:

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 Qua.'ter 1993: Unexpected CEA Withdrawal.

First Quarter 1994: Unplanned dilution of Boron concentration in the RCS.

Data Source:

Nuclear Regulatory Commission & INPO Accountability:

Chase Positive Trend 20

]

~

D Missed sTs Resulting in LERs 2-1 4

1

)

hiy O

Sj o

e o

o o

o i

': 0 93 94 Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec 1995 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 June 1995.

On December 28,1994, during the performance of OP-ST-SHIFT-0001, data was not entered for Steam Generator level per Surveillance Requirements.

The 1995 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 21

l l

l i

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

i 1

I e

e 22

l l

D Net oeneration (10,000 Mw hours) 40 38.21 38.22 j

34.ss 34.88 34 34.12 34,34 33,,,

H E aa e

h

[Uf th 4

2 30 -

4 g

g#

i p

y i

~

z 4

22.s2 2

gg gi 21.18

=

}.,,

b g.,

$g 9

h 7

e!

f@%]

$j 54

.m 4

2 p

A l

si n

,3

[4;

+9 gi fjf)

}

g%j

%p 2

16.28 gj j

dl

&g c;;;- g g

y 8

rr g

gj

'l "1

Ikfl

[f hp h.

T2 gp f

l 10 -

$l 8!

((

.g

)i i!

($

[$j'p1

&g gj f-Y

4 h$l Q

h@

h

^l i

D is

!s i

Mj

{K

1. fi T*

31

((

~

4,%{

H f3 R!i

!D T

jg S

k'k 0

g' i

~

0 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 STATION NET GENERATION During the month of June 1995, a net total of 341,221.6 MWH was generated by the Fort Calhoun Station. Cumulative net generation for Cycle 16 was 722,386.6 MWH at the end of the month.

i Energy losses for May 1995 were attributable to: (1) the component cooling water, which was leaking into the lube oil system of RC-3D reactor coolant pump motor; and (2) the generator and reactor were again manually tripped because of a similar leak. The gen-erator was put on-line after replacement of all of the reactor coolant pump lube oil cooler heat exchangers.

l Data Source:

Station Generation Report Accountability:

Chase Adverse Trend:

None 23

l l

C Forced Outage Rate (Monthly)

J

-+- Forced Outage Rate (12 Months) lo000l

-e-Fort Calhoun Goal (2.4%)

l 30% -

25% -

20%-

15% -

1.

tais 10%.

Cycle is Refueleg 5% -

on c

=

=

=

3 3

O m > 0%

O 92 93 94 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr - May Jun 1994 1994 FORCED OUTAGE RATE The forced outage rate (FOR) was reported as 3.0% for the twelve months from July 1, 1994, through June 30,1995. The 1995 year-to-date FOR was 7.3% at the end of the month.

Energy losses for May 1995 were attributable to: (1) the component cooling water, which was leaking into the lube oil system of RC-3D reactor coolant pump motor; and (2) the generator and reactor were again manually tripped because of a similar leak. The gen-erator was put on-line after replacement of all of the reactor coolant pump lube oil cooler heat exchangers.

The 1995 Fort Calhoun year-end goal for this indicator is a maximum value of 2,4%.

Data Source:

Monthly Operations Report Accountability:

Chase Adverse Trend:

None 24

t 4

C""3 Monthly Unit Capacity Factor

-G-- Unit Capacity Factor for Cycles is & 18

-dr-- 38-Month Average Unit Capacity Factor 12 5 -

--M-FCs Goal (7s.H%)

100 % -

80% -

/}/

60% -

40% -

25 -

0%

-I Jul Aug Sep oct Nov Dec Jan Feb Mar Apr May Jun 1884 1995 UNIT CAPACITY FACTOR This indicator shows the plant monthly Unit Capacity Factor, the Unit Capacity Factor for the current fuel cycle and the 36-month average Unit Capacity Factor.

At the end of the month, the Cycle 16 Unit Capacity factor was 69.23%, and the Unit Capacity Factor for the last 36 months was 78.58%. The 1995 Fort Calhoun goal for this indicator is 79.65%.

i Energy losses for May 1995 were attributable to: (1) the component cooling water, which was leaking into the lube oil system of RC-3D reactor coolant pump motor; and (2) the i

generator and reactor were again manually tripped because of a similar leak. The gen-erator was put on-line after replacement of all of the reactor coolant pump lube oil cooler heat exchangers.

The Unit Capacity Factor is computed as follows:

Net Electrical Enerov Generated (MWH) i Maximum Dependable Capacity (Mwe) X Gross Hours in the Reporting Period l

Data Source:

Monthly Operating Report Accountability:

Chase Adverse Trend:

None 25

)

1

Monthly EAF - Year.to-Date Avere0e Monthty EAF g

-dr-- 12-Month Average EAF

--M-- Industry Median Value (78.7% for a 3-Year Averag4 l Goo %

i F.2

=-

=

r e

5-?

1 1*~

\\~

A E

g p

gg

"~

i i

Y

=

g

~

S~E/

m.

~

40% -

Cycle 15 20%.

Refueling Outa08 0%

Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May Jun g g g 1994 1995 EQUIVALENT AVAILABILITY FACTOR I

This indicator shows the plant monthly Equivalent Availability Factor (EAF), the year-to-date aver-age monthly EAF, and the year-end average monthly EAF for the previous three years.

The EAF for June 1995 was reported as 96.4%. The year-to-date monthly average EAF was 73.2% at the end of the month.

Energy losses for May 1995 were attributable to: (1) the component cooling water, which was leaking into the lube oil system of RC-3D reactor coolant pump motor; and (2) the generator and reactor were again manually tripped because of a similar leak. The gen-erator was put on-line after replacement of all of the reactor coolant pump lube oil cooler heat exchangers.

The Fort Calhoun average monthly EAF for the three years prior to this report was 86.0%. The industry median EAF value for the three-year period from 7/90 through 6/93 was 76.7%.

Cata Source:

Dietz/Kulisek (Manager / Source)

Accountability:

Chase Adverse Trend:

None 26

s C"] Monthly Unit Capability Factor

-e-Year-to-oste Unit Capability Factor h

--*- 36-Month Unit Capability Factor l GOOD l I

--M-1W4 ad 1935 Fort Calhoun Goals

- 1994 and 1995 INPO Industry Goals 100% --

w 90%

\\_

m r

80% -

70% -

60%

2 50% -

7 c,ci. is 30% -

a**e i

20'A <

10% -

0%

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun

)

1994 1995 UNIT CAPABILITY FACTOR i

This indicator shows the plant monthly Unit Capability Factor (UCF) value, the year-to-date UCFs, the 36-month average UCFs, and the UCF goals. 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 continuously at full power under reference ambient conditions) over the same time period, expressed as a percentage (refueling periods excluded).

The UCF for June 1995 was reported as 100%. The year-to-date UCF was 55.6%, the UCF for the last 12 months was 77.6%, and the 36-month average UCF was reported as 82.7% at the end of the month.

Energy losses for May 1995 were attributable to: (1) the component cooling water, which was leaking into the lube oil system of RC-3D reactor coolant pump motor; and (2) the generator and reactor were again manually tripped because of a similar leak. The gen-erator was put on-line after replacement of all of the reactor coolant pump lube oil cooler heat exchangers.

The 1995 INPO industry goal is 80% and the industry current best quartile value (for the three-year period ending 12/94) is approximately 85%. The 1995 Fort Calhoun year-end goal for this indicator is a minimum of 85%.

Data Source:

Generation Totals Report & Monthly Operating Report Accountability:

Chase Adverse Trend:

None 27

4 Monthly Unplanned Capability Loss Factor lo000j

--G-- Year-To-Date Unplanned Capability Loss Factor

--*-- 12-Month Average Unplanned Capability Loss Factor T

-M-Fort Calhoun Goal (3.97%)

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

40% -

--*- Industry Current Best Quartile

~

35% -

30% -

25% -

A 20% -

/

7 15% -

10% -

g[g===d,==,==, =g 5% -

0%

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 UNPLANNED CAPABILITY LOSS FACTOR This indicator shows the plant month!y Unplanned Ct.pability Loss Factor (UCLF), the year-to-date UCLF and the goal. 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 ambient conditions), expressed as a percentage.

Unplanned energy losses for February 1995 were due to a problem with a control element as-sembly sealleakage of reactor coolant. Unplanned energy losses for March 1995 were due to the start of the plant's 15th refueling outage,19 days prior to the originally scheduled start date.

The UCLF for the month of June 1995 was reported as 0.0%. Unplanned energy loss is defined as the energy that was not produced during the period of unscheduled shutdowns, outage exten-sions, or load reductions due to causes under plant management control. Energy losses are considered to be unplanned if they are not scheduled at least fourweeks in advance. The year-to-date UCLF was 17.58%, the UCLF for the last 12 months was 11.57%, and the 36-month average UCLF was reported as 7.53% at the end of the month.

Energy losses for May 1995 were attributable to: (1) the component cooling water, which was leaking into the lube oil system of RC-3D reactor coolant pump motor; and (2) the generator and reactor were again manually tripped because of a similar leak. The generator was put on-line

~

after replacement of all of the reactor coolant pump lube oil cooler heat exchangers.

The 1995 INPO industry goal is 4.5% and the industry current best quartile value is approxi-mately 3.2% or lower. The 1995 Fort Calhoun year-end goal for this indicator is a maximum value of 3.97%.

Data Source:

Generation Totals Report & Monthly Operating Report Accountability:

Chase Adverse Trend:

None 28

S.

- FCS Reactor Scrams Per 7,000 Hours Critical Year to Date

-+- FCs Reactor Scrams Per 7,000 Hours Critical for last 36 months

-+- 1995 & 1994 Fort Calhoun Gosis (0.0)

-*-- 1995 INPO Industry Goal (1)

-M-- Industry Upper 10% (1 per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical) 3-2 0

=

=

1 9

6 6

i 6

6 6

0:

Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May Jun IlI FCS Reactor Scrams 3'

3

~

2 2-

~

1 1

]'

o o

e o

o o

o o

o o

o o

o

~

O M 82 # 88 Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 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 <br />0 hours <br />0 weeks <br />0 months <br /> critical (as defined in INPO's 12/93 publication " Detailed Descriptions of interna-tional Nuclear Power Plant Performance Indicators and Other Indicators") for Fort Calhoun Station. The lower graph shows the number of unplanned automatic reactor scrams that occurred during each month for the last twelve months.

The year-to-date station value was 0.0 at the end of June 1995. The value for the 12 months from July 1,1994, through June 30,1995, was 0.0. The value for the last 36 months was 1.62.

The 1995 Fort Calhoun goal for this indicator is 0. The 1995 INPO industry goal is a maximum of one unplanned automatic reactor scram per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical. The indus-try upper ten percentile value is approximately 0.48 scrams per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical.

I Data Source:

Monthly Operations Report & Plant Licensee Event Reports (LERs)

Accountability:

Chase Positive Trend l

29 l

3-CD safety system Actuations (INPO Definition)

FCS Goal (0)

->- Industry Upper 10 Percentile (0) 2-1 1

0 c.

0 0

0 0

0 0

0 0

0 0

0 0

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995-UNPLANNED SAFETY SYSTEM ACTUATIONS -(INPO DEFINITION)

There were no INPO unplanned safety system actuations during the month of June 1995.

There was one INPO unplanned safety system actuation during the month of February 1994. It occurred on February 11,1994, when supervisory relay 86BICPHSS failed, which resulted in tripping relay 86BICPHS. 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 au-tomatically closed both main stam isolation valves, which resulted in a concurrent turbine and reactor trip.

An INPO unplanned safety sytem actuation also occurred during the month of July 1992 due to the loss of an inverter and the subsequent reactor trip on 7/3/92.

The 1995 Fort Calhoun goal for this indicator is 0.

I Data Source:

Monthly Operctions Report & Plant Licensee Event Reports (LERs)

Accountability:

JaworskJFoley!Ronning i

Positive Trend 30 l

i t

l..

}

J aan seesty system Actuations (NRC Dennition) l CD 19s5 FCs Goal (0) Month Running Total ssAs (NRc DeBr.ition)

--+- critic i Hours i

1. ;

=

g q

>m j

F.

j f

]

r l

see g.

.,1 q

f, h mf ii

\\

j

/

92 - 93 to J AS 0NDJ FMAMJ J AS O N D J F J F M A~M J 84 1983 1995 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,-

I and the Emergency Diesel Generators. The NRC classification of SSAs includes actua-I tions when major equipment is operated and when the logic systems for these safety 1

systems are challenged.

An unplanned safety system actuation occurred in December 1993 when the main turbine and reactor tripped during Electro-Hydraulic Control pump start testimg. Also, there was an unplanned Safety system actuation during the month of February 1994 when supervi-sory relay 868/CPHSS failed, which resulted in a concurrent turbine and reactor trip.

There has been no unplanned safety system actuations in the last 12 months. The 1995 Fort Calhoun goal for this indicator is 0.

4 Data Source:

Monthly Operations Report & Plant Licensee Event Reports (LERs)

Accountability:

Jaworski/Foley/Ronning Adverse Trend:

None 31

I i

11 -

M Monthly Gross Heat Rate

--M-Year-to-Data Gross Heat Rate l GOOD l p

1994 & 1995 Fort Calhoun Goals 10.75 -

10.5 -

I na g,

gy fS 10 Sb ~

I M

f i h-f b

E men Ip 10 i

b i

?#

e,;

f:.

y;l 1,

g

~]

.g f

R; T'm g.

g w

.c c

~

k cre.is-

/

f N

N y

G 9.75 -

[

[

l, l

[.

fg j &

~

la

[ii N

((.

k fj

[f h

h i

k k

E is k

h l

9.5

~.

~

=

F-92 93 94 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 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 three years.

The gross heat rate for Fort Calhoun Station was 10,288 for the month of June 1995.- The 1995 year-to-date GHR was 10,169 at the end of the month.

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 1995 Fort Calhoun year-end goal for this indicator is $10,157.

Data Source:

Holthaus/Willett (Manager / Source)

Accountability:

Chase /Jaworski Adverse Trend:

None 32

m Monthly Thermal Performance C""3 12-Month Average

-M-Year 4o Date Average Monthly Thermal Performance k

1995 Fort Calhoun Goal (39.8%)

l

-+- 1996 INPO Industry Goal (98.5%)

-G-Industry Upper 10% (90.7%)

GOOD 100 % -

e

=

=

=

=

=

=

=

=

=

g

_a

=

= _ _ -

M

[f

[

b lI 99% -

hl l'

u

)

Cycle is i

stefueling

~

g outage 4

M g

?

98 %

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

The thermal performance value for June 1995 was 99.63. The year-to-date average monthly thermal performance value was 99.4, at the end of the month. The average monthly value for the 12 months from June 1,1994, through May 31,1995, was 99.3%.

The 1995 Fort Calhoun year-end goal for this indicator is a minimum of 99.6%. The 1994 Fort Calhoun goal was a minimum of 99.5%. The 1995 INPO industry goal is 99.5% and the industry upper 10 percentile value is approximately 99.9%.

Data Source:

Jaworski/Shubert Accountability:

Jaworski/Gorence Adverse Trend:

None 33

-+-- Thermal Output

+ Fort Calhoun 1495 MW Goal

--*- Tech Spec 1500 MW Limit 1599 - 1 ai 9

1499 -

1498 -

1497 -

J 1496-im 1496 - 0 0

: : : :N:::

1494 -

1493-1492-1491 1

3 6

7 9

11 13 16 17 19 21 23 26 27 29 DAILY THERMAL OUTPUT The thermal output graph displays the daily operating power level during June 1995, the 1500 thermal megawatt average technical specification limit, and the 1495 thermal mega-watt Fort Calhoun goal.

Data Source:

Holthaus/Willett (Manager / Source)

Accountability:

Chaseffills Adverse Trend:

None 34

1

-4*- Equipment Forced Outage RateI1,000 Critical Hrs. (12-Month Interval)

)

-4>-

1994 & 1995 Fort Calhoun Year-End Goals (0.2)

)

0.8 -

~'

l GOOD l 0.6 -

i y "

0.4 -

o.11 0.2; E

2 g

g g

g 2

pf 0

g L

o

+

32 33 N

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 2-Number of Equipment Forced Outages Per Month n

a 1

is 0

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 j

EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS '

The equipment forced outage rate per 1,000 critical hours for the 12 months from July 1, 1994, inrough June 30,1995, was 0.409. The year-to-date rate per 1,000 critical hours for the months from January through June 1995 was 1.03.

An equipment forced outage also occurred on February 20,1995, when the plant experi-enced a problem with a control element assembly motor drive and a related small leak of reactor coolant.

Two equipment forced outages also occurred during May 1995, which were attributable to the component cooling water, which was leaking into the lube oil system of RC-3D reactor coolant pump motor.

The 1995 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)

Accontability:

Chase /Jaworski Adverse Trend:

None 35

i i

-e-component categories 20 -

- + ",,

^. Categories 9g.

-e-Totalcategories 16 -

.)

j L12 -

~

~

',10 -

O r

1 s<

^

8-

=

=

=

=

i I

4-2-

0 JS4 F

M A

M J

J A

s o

N D04 J86 F

M A

M JD6 Error / operating Action s

11.4%

Maintenance /

AC'"

Wear out/

27.1%

g 4s.s%

Percent of Total Failures uring During the Past 18-Month Devices Engineering /

4J%

Design CFAR Period

}

42%

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-month Component Failure Analysis Report (CFAR) reporting period (from September 1993 through February 1995). Fort Calhoun Station reported a higher failure rate in 5 of the 87 component categories (valves, pumps, motors, etc.) during the past 18-month CFAR period. The station reported a higher failure rate in 5 of the 173 application categories (main steam stop valves, auxiliary / emergency feedwater pumps, con-trol element drive motors, etc.) during the past 18-month CFAR period.

The pie chart depicts the breakdown by INPO cause categories (see the " Definitions" section of this report for descriptions of these categories) for the 71 failure reports with known failure causes that were submitted to INPO by Fort Calhoun Station during the past 18-month CFAR period.

The pie chart reflects known failure causes. A total of 86 failure reports were submitted to INPO during the past 18-month CFAR period.

Data Source:

Jaworski/ Frank (Manager / Source)

Accountability:

Jaworski/ Frank Adverse Trend:

None 36

y.

-y, c

s

' 18 "

-+--. Components with more than one FaNute l Good l n

- M - Components with more than Two FaNures 1

. ie -

i i

a a

s-a a

1 l

Li f

8-4 4

4 3

3 l

l 1

1 1

1 1

1 1

-i S

I O

)

Jul -

Aug sep Oct Nov Dec Jan Feb Mar Apr May Jun :

1994 190s REPEAT FAILURES

}

The Repeat Failures indicator (formerly called the " Maintenance Effectiveness Perfor-mance Indicator) was developed in response to guidelines set forth by the Nuclear Regu-i latory Commission's Office for Analysis and Evaluation of Operational Data (NRC/AEOD).

i The NRC requirement for a Maintenance Effectiveness Performance Indicator has been dropped. but station management considers it useful to continue to track repetitive com-l ponent failures using the Nuclear Plant Reliability Data System (NPRDS).

]

This indicator shows the number of NPRDS components with more than one failure during the 18-month Component Failure Analysis Report (CFAR) period and the number of NPRDS

.i components with more than two failures during the 18-month CFAR period.

~

l During the last 18-month CFAR period, there were 4 NPRDS components with more than

)

one failure. None of these 4 had more than two failures. The tag numbers of the compo-i nents with more than one failure are: Raw Water Pump AC-10C, Excore Detector.

1 Preamplifier NT 001, Safety injection Tank "D" Level Channel (narrow range) Power Supply LQ-2964Y and Pressurizer Spray Line Check Valve RC-374. Recommenda-tions and actions to correct these repeat failures are listed in the biannual CFAR.

Data Source:

Jaworski/ Frank (Manager / Source)

~ Accountability:

Chase Adverse Trend:

None 37 j

l

l 5

m Radioactive Waste Buried This Month (cu.ft.)

• Cumulative Radioactive Weste Buried l GOOD l 0

1995 Fort Calhoun Goal (900 cu.ft.)

900-C

^

^

~

o 800 -

700 -

600 -

)

w 500 -

C r

^

c

^

^

400 -

U 300 -

200 -

100-0 Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 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 approximately industry upper 10%.

Cu Ft.

Amount of solid radwaste shipped off-site for processing during current month 0

Volume of solid radwaste buried during current month 0

Cumulative volume of solid radioactive waste buried in 1995 0

Amount of solid radwaste in temporary storage 0

The 1995 Fort Calhoun goal for the volume of solid radioactive waste (buried) is 900 cubic feet. The 1995 INPO industry goal is 110 cubic meters (3,884 cubic feet) per year. The industry upper ten percentile value is approximately 27.33 cubic meters (965.3 cubic feet) per year.

Data Source:

Chase /Breuer(Manager / Source)

Accountability:

Chase /Lovett Adverse Trend:

None SEP54 38

I i

3%--

M Primary System Chemistry Percent of Hours Out of Limit l GOOD l

--+-- Fort Calhoun Goal (0.02) 2% -

C 0

0 0

0 0

0 0

0 0

^

0 e

NN[

f a

$h 1%

Cycle 15 w

Refueling

!!?

outage h

y p.

b hh.

k R$

0%

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun PRIMARY SYSTEM CHEMISTRY PERCENT OF HOURS OUT OF LIMIT The Primary System Chemistry Percent of Hours Out of Limit indicator tracks the primary system chemistry performance by monitoring 6 key chemistry parameters. The key pa-rameters are: lithium, dissolved oxygen, chlorides, flouride, hydrogen and syspended sol-ids.100% equates to all 6 parameters being out of limit for the month.

The Primary System Chemistry Percent of Hours Out of Specification was 0.0% for the month of June 1995.

The 1995 Fort Calhoun monthly goal for this indicator is a maximum of 2% hours our of limit.

Data Source:

Smith / Spires (Manager / Source)

Accountability:

Chase / Smith Positive Trend 39

U D

1.6 O

12-Month Average '

l GOOD l

- dr-- Fort Calhoun Goal (1.4)

I 1.5 -

1.4 -

1 i

1 1

1 1

1 1

i i

1 1.3 -

).l.

1.2 -

{,

b g;

r 1.1 -

g

)

k 1

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1995 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% per day.

The CPI for June 1995 was 1.34. The 12-month average CPI value was 1.17 at the end of the month.

The 1995 Fort Calhoun monthly goal for the CPI is a maximum value of 1.40.

Data Source:

Smith / Spires (Manager / Source)

Accountability:

Chase / Smith Positive Trend due to performance better than goal 40

f COST i

Goal: Operate Fort Calhoun Station in a manner that cost effectively maintains nuclear generation as an eco-nomically viable contribution to OPPD's bottom line.

Cost consciousness is exhibited at all levels of the or-ganization.

e 41 4

---

u m

--+- Actual Revised Budget

-*-- original Budget

-M-Plan 4-3.75 -

3.5 -

3.25 -

?

D 3

E U

M 2.75 -

0 l

2.25 -

2 D91 D92 D93 D94 J95 F M

A M J

J A

s o

N D95 D96 D97 D98 D99 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 kilowatt hour on a 12-month rolling average for the current year. The basis for the budget curve is the approved 1994 and 1995 revised budgets. The basis for the actual curve is the Finan-cial and Operating Report.

The December 31 amounts are also shown for the prior years 1992,1993 and 1994. In addition, the repcrt shows the plan amounts for the years 1996 through 1999 for refer-ence. The basis for the dollars are the Nuclear Long Range Financial Plan and the 1995 Corporate Planning and Budget Review. The basis for the generation is provided by Nuclear Fuels.

The unit price (3.01 cents per kilowatt hour for June 1995) averaged lower than budget due to expenses being below budget while generation exceeded the budget.

Data Source:

Scofield/Jamieson (Manager / Source)

Accountability:

Scofield Positive Trend due to performance better than goal 42

t E Nuclear Services Division D Production Engineering Division 5 Nuclear Operations Division E TotalNuclear 900 -

800-785 tes ts:

'*8 788 727 727 700 -

600 -

500 887 4se as 44 a

m y

y 400 300 8"'

20 182 11 tes 17 ies too 11 117 1

116 11 11 11 11 100 so 0

Jan-92 Jan-93 Jan 94 Apr-94 Jul-94 Oct-94 Dec-94 Mar-95 Jun-95 r

Actual stamng Level (Updated Quarterty) i STAFFING LEVEL l

The actual staffing levels for the three Nuclear Divisions are shown on the graph above.

The authorized staffing levels for 1995 and 1996 are:

Authorized Staffing 1995 1996 440 432 Nuclear Operations Division 181 175 Production Engineering Division 114 113 Nuclear Services Division 735 720 Total Data Source:

Ponec/Kobunski i

Accountability:

Ponec Adverse Trend:

None SEP 24 43

--*-- Spare Parts inventory Value ($ Million) 16.8 -

+

16.6 -

' 16.4 -

f 16.2 -

8 I 16 ;

e b

• 15.8 -

g 15.6 -

t 15.4 -

15.2

+

Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 l

Spare Parts inventory Value The spare parts inventory value at the Fort Calhoun Station at the end of June 1995 was reported as $15,772,951.

l t

t i

e I

Data Source:

Steele/Huliska (Manager / Source)

Accountability:

Wilfrett/McCormick Adverse Trend:

None f

44

i r

i DIVISION AND DEPARTMENT PERFORMANCE INDICATORS Goal: Achieve high standards at Fort Calhoun Station resulting in safe, reliable and cost effective power pro-duction.

)

l a

4 45 4

4 Corrective Maintenance

• • Preventive Maintenance

• • e Non-Corrective / Plant improvements -e-Fort Calhoun Goal 1000 -

E h

(20 E

ss7 800 -

400 -

I, 0

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 199s 1994 Non-Outage Maintenance Work Order Backlog 3 MWOs Which Exceed Maintenance Completion Goals O Total MWOs 600-500 M5 400-300-200-188

> 90 deve h

"r3 2en 162 N

0 Priority 1 Priority 2 Priority 3 Priority 4 Priority 5 Priority 6 Non-Outage Maintenance Work Order Backlog 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 1995 goal for this indicator is 400 non-outage corrective maintenance MWOs. To ensure that the MWO backlog is worked in a timely manner, non-outage maintenance completion goals have been established as follows:

Goal Priority 1 Emergency N/A Priority 2 Immediate Action 2 days Priority 3 Operations Concern 14 days Priority 4 Essential Corrective 90 days Priority 5 Non-Essential Corrective 180 days Priority 6 Non-Corrective / Plant improvements N/A Improvements in the maintenance planning and scheduling process will allow more timely re-sponses to maintenance work requests. Implementation is scheduled for 8/14/95.

This indicator is considered an adverse trend. An action plan has been established to identify problem areas and reduce the backlog.

Data Source:

Chase /Schmitz (Manager / Source)

Accountability: Chase /Faulhaber Adverse Trend SEP 36 46

100 %

Ratio of Preventive to Total Maintenance 90% -

80%

70% -

60% -

50% -

40 %

30% -

20% -

10%-

0%

i i

i t

i i

I i

i i

I l

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 m Preventive Maintenance items Overdue l GOOD]

O Fort Calhoun Goal 1%

0%

1 i

I i

I I

I I

I I

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 RATIO OF PREVENTIVE TO TOTAL MAINTENANCE &

PREVENTIVE MAINTENANCE ITEMS OVERDUE Tho top graph shows the ratio of completed non-outage preventive maintenance to total completed non-outage maintenance. The ratio was 62.8% for the month of June 1995.

The lower graph shows the percentage of scheduled preventive maintenance items for June that are overdue. During June 1995,292 PM items were completed. All of these PM items were completed within the allowable grace period orwere administratively closed.

The 1995 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 47

M Rowork as identlSed by Craft

-o-Fort Calhoun Goal (<3%)

6%.

8.9%

] 5%

4.7%

2J%

A 4%

1.

'a 3.0%

g 3%

c 0

o

^

2%

1.9%

1% -

0%

i I

i l

l I

l l

Nov-94 Dec-94 Jan-95 Feb-95 Mar-95 Apr-85 May-05 Jun-05 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 pir nning and craft.

This indicator is calculated from the 15th to the 15th of each month due to delay in closing open MWO's at the end of each month.

The Fort Calhoun monthly goal for this indicator is <3%.

+

\\

l Data Source:

Faulhaber/Schmitz (Manager / Source) l Accountability:

Chase /Faulhaber Adverse Trend:

None 48

I s

j m Maintenance Overtirne

-M-12-Month Awrage Maintenance Overtime l0000l

)

~

Fort Calhoun "On Line" Goel(10%)

j 0.45 -

]

I 0.4 -

0.35 -

0.3 0.25 -

I 0.2 -

l 0.15 -

j 0.1 -

j 0.05 -

O i

i i

i i

i i

l i

i i

i Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 MAINTENANCE OVERTIME The Maintenance Overtime Indicator monitors the ability to perform the desired mainte-nance activities with the allotted resources.

4 The percent of overtime hours with respect to normal hours was reported as 23% for the month of June 1995. The 12-month average percentage of overtime hours with respect to normal hours was reported as 12.7% at the end of the month.

The high overtime usage in May was the result of two forced outages.~ Due to reporting methods, the overtime from the second outage carried in the first week of June. Overtime i

usage from 6/3/95 to 7/1/95, was approximately 5%.

The 1995 Fort Calhoun monthly "on-line" goal for this indicator is a maximum value of 10%.

Data Source:

Chase /Schmitz (Manager / Source)

' Accountability:

Chase /Faulhaber Adverse Trend:

None 49

d t

This page has been left intentionally blank.

r PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)

A new (maintenance) human relations indicator is being developed for the July 1995 report.

t 9

I l

l i

t 50 t

1

i m Completed Scheduled Activities (All Crafts)

--e-Fort Calhoun Goal (85%)

100% -

90% -

C O

O O

. $ 80% ~

T 70% -

i-

=

50% -

ass a a-h m-8 m-u 10% -

0%

t-1-----

t-------

1 June '95 July '95 August '95 september '95 DAILY SCHEDULE PERFORMANCE PERCENT OF SCHEDULED ACTMTIES COMPLETED This indicator shows the percent of Integrated Plant Schedule activities completed on schedule. All work groups and activities are included. Measurement of daily performance was initiated in June.

The Plant Manager has established schedule performance as a high priority. Daily schedule performance is discussed at the 7:15 A.M. and 12:30 P.M. plant meetings. Weekly cri-tique meetings will be held to identify problem areas.

The 1995 Fort Calhoun monthly goal for completed scheduled maintenance activities is 85%.

Data Source:

Chase /Schmitz (Manager / Source)

Accountability:

Chase /Faulhaber i

Adverse Trend:

None SEP 33 51

M % of Hours the in-Line Chernistry instruments are Inoperable

-4>- 1995 Fort Calhoun Goal (10%)

10% -

c 8% -

W[

[

6% -

Q(

.g J

L'j M

f-

E y

4 S

9 a,.

4% -

vc n-g 7;

9 g

g g

A A

a,

(;;;.

g, 2 ;(

w, p

g g,

}

Q-L;

'.J:

V)

K l

6 3

y 3[

E.'

i'z

'?;t p

e y

j;.

p.;

-#p t

.g h

[.

-Q

[j

};$.

fM os Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 IN-LINE CHEMISTRY INSTRUMENTS OUT-OF-SERVICE This indicator shows the percentage of hours the in-line chemistry system instruments are inoper-able for the reporting month. The chemistry systems involved in this indicatorinclude the Second-ary System and the Post Accident Sampling System (PASS).

i At the end of June 1995, the percentage of hours the in-line chemistry system instruments were inoperable was 7.91%. The following instruments were out of service during the month of June 1995:

• CD-1582A - B Cation Bed Conductivity YE-1535 - Primary Water Storage Tank Dearator Dissolved Oxygen

. YI-6767A - A Steam Generator Sodium Analyzer YI-6767B - B Steam Generator Sodium Analyzer The entire instrument channel is considered inoperative if: 1) the instrument is inoperative,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 1995 Fort Calhoun monthly goal for this indicator is a maximum of 10% in-line chemistry instruments inoperable. 5 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 Positive Trend due to performance better than goal 6

52

m Weste Produced Each Month (Kilograms)

-de-- Monthly Average Weste Produced During the last 12 Months (Kilograms)

-e-- Fort Calhoun Monthly Average Goal (150 kilograms)

I

-M-- Federal & State Monthly Limit (Max. of 1,000 kg) 1000 x x

x x

x x

x x

x x

x x

800 --

)

600 -

12 ao-

'" i O'

Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May -

Jun 1994 1995 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 wast 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 June 1995,0.0 kilograms of non-halogenated,0.0 kilograms of halo-genated and 0.0 kilograms of other hazardous waste was produced. The total hazardous waste produced during the last 12 months is 654.1 kilograms.

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

The 1995 Fort Calhoun monthly average goal for hazardous waste produced is a maxi-mum of 150 kilograms.

i Data Source:

Chase /Carlson (Manager / Source)

Accountability:

Chase / Smith Positive Trend 53

m Contaminated Radiation Controlled Area l GOOD l

-e-Fort Calhoun Goal (10%)

10% -

c o

q if?

N M

4 R':p j

8.:

y e

+

6 e

a rv gg pg 8$

Qi ji' E'

b w

9% -

if Ril

i

??

'j fj Q

M

!a p

g pf h$l

lsl, hgb Nf l::

^ '

h; Q

sa a

s M

7 y+;

E t

1 X

l; l;

ti; f.

e n;;

6 l

(q..

h(

j M

s'::

e:

t 2

6s

.IQ l.;

k E.li

'P's ep i:1 A. :

h 05 2l 8%

--i Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 CONTAMINATED RADIATION CONTROLLED AREA This indicator shows the percentage of the RCA that is contaminated based on the total square footage. The 1995 monthly non-outage goal is a maximum of 9.5% contaminated RCA.

At the end of June 1995, the percentage of the total square footage of the RCA that was contaminated was 9.3%.

Data Source:

Chase /Gundal(Manager / Source)

Accountability:

Chase /Lovett Positive Trend SEP 54 54

^

+ Identified PRWPs (Year to Date) l GOOD l

+ 1995 Fort Calhoun Goal (<20) 20 0

0 0

0 18 16 94 13

'3 14 -

j 12 10 -

l 8-

~

4 4-t 1

0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1994 1995 RADIOLOGICAL WORK PRACTICES PROGRAM The Radiological Work Practices Program Indicator shows the number of Poor Radiologi-cal 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 June 1995, there was 1 PRWPs identified.

There have have 14 PRWPs in 1995.

The 1995 year-end goal for PRWPs is a maximum of 20.

Data Source:

Chase /Cartwright (Manager / Source)

Accountability:

Chase /Lovett Adverse Trend:

None SEP 52 55

O Documents Scheduled for Review 5 Documents Reviewed 5 Documents Overdue 3g,

300-250 -

200 -

Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 DOCUMENT REVIEW This indicator shows the number of completed, scheduled, and overdue (greater than 6 months past the scheduled due date) biennial reviews for the reporting month. These document reviews are performed in-house and include Special Procedures, the Site Se-curity Plan, Maintenance Procedures, Preventive Maintenance Procedures, and the Op-

]

erating Manual.

i J

During June 1995, there were 109 document reviews scheduled, while 86 reviews were completed. At the end of the month, there was 1 document review more than 6 months overdue. There were 9 new documents initiated during June.

Data Source:

Chase /Plath 4

Accountability:

Chase /Jaworski Adverse Trend:

None 56

60 -

System Failures jooool 50 -

I 37 g,

wp y_

es wu f

21 22 20 gg gj e

l 20 -

i

,4 h

E-55 gj yl]

g g4 4

'n to

(

E

?,. I d d

b d.

O b

s fM 10 -

P d

as 0

Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995' 16 -

Non-System Failures 15 14 -

12 -

)

c,

[

l 10 -

8-s s

O s

j 6

4 4

7 1

4-3 3

h ai 3

ip 2

4.h 4

t 2

R PEI M

d E

b 2-

$d

$N b

d b!!

N O

Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 LOGGABLEIREPORTABLE INCIDENTS (SECURITY)

The Loggable/ Reportable incidents (Security) Indicator is depicted in two separate charts.

The first chart shows the total number of loggable/ reportable incidents conceming system

{

failures which occurred during the reporting month. The second chart depicts the total number of loggable/ reportable incidents non-system failures conceming Security Badges, Access Control and Authorization, Security Force Error, and Unsecured Doors.

During the month of June 1995, there were 17 loggable/ reportable incidents identified compared to 24 for the previous month. System failures accounted for 14 (82%) of the loggable/ reportable incidents. Microwave Zone 17, which is scheduled for repair in Sep-tember 95, contributed to four (4) of the loggable environmental incidents. The non-system failures were a result of two (2) security badges being removed from site.

Data Source:

Sefick/Woemer(Manager / Source)

Accountability:

Sefick Adverse Trend:

None SEP 58 57

. ~.

j t

i

'l C"""I Temporary

>14ycle old plFO seguired for removal) f M Temporary

>S monIhs old Stemovelde on.line)

' + Fort Calhoun Goal for Temporary

> 1<ycle old f

' 8-

- M-Fort Calhoun Goal for Temporary blodIlications > S months chl 8

. s-l l

1 March 15

" April'96 May '95 June '95 -

4 1

TEMPORARY MODIFICATIONS r

This indicator provides informaticn on the number of temporary modifications greater than j

one fuel cycle old requiring a refueling outage (RFO) for removal and the number of tem-porary modifications removable on-line that are greater than six months old. The 1995 Fort Calhoun monthly goals for this indicator are zero; However, one temporary modifica- -

3 tion (BAST level indication) has been approved by management to exceed these goals

'due to cost effectiveness considerations (reference PED-STE-94-042) j There is currently 1 temporary modification that is greater than one-fuel cycle old requiring a refueling outage to remove: RC-3D cover gasket pressure indicator, which is awaiting j

completion of MWO 941450, which is scheduled for a future refueling outage whenever j

cover gaskets are replaced. In addition, at the end of June 1995, there were 6 temporary j

modifications installed that were greater than six months old that can be removed on-line.

j These were: 1) Local indication for BAST CH-11 A and CH-11 B, in which Licensing sent 1

FLC 94-001 to the NRC 6/27/95.for approval; 2) Control system for intensifier on HCV-2987, which is awaiting completion of ECN 94-280, scheduled for completion as 1995 on.

j line 9/95; 3) brace to IA header "T" to water plant, which is awaiting completion of ECN 94-j 482, scheduled for issue from DEN-Mechanical 8/25/95; 4) braces on main instrument P!r i

header,' which is awaiting completion of ECN 94-482, scheduled for issue from DEN-l Mechanical 8/25/95; 5) intake raw water securiity cage, which is awaiting ~ completion of ECN 94 454, scheduled for completion 8/95; and 6) sleeving of HCV-403F connecting.

L

' rod, which is awaiting completion of MWO 943620, tentative schedule date 8/30/95.

J l

At the end of June 1995, there was a total of 19 TMs installed in the Fort Calhoun Station.

5 of the 19 installed TMs require an outage for removal and 10 are removable.'on-line.1 in -

1995, a total of 20 temporary modifications have been installed.-

a j

Data Source:

Jaworski/ Turner (Manager / Source) 1 Accountability:

Jaworski/Gorence Trend:

Needs increased Management Attention SEP 62 & 71 58 la

Total Modification Packages Open

+ Fort Cathoun Year-End Goal 100 100 -

80 -

L LHq Wl-illli.li_l_li u

'92

'93

'94 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 OUTSTANDING MODIFICATIONS This indicator shows the total number of outstanding modifications (excludino outstandino modi-fications which are proposed to be cancelled).

Reporting Cateaorv

'93

'94

'95

'96

'97

'98 Month Form FC-1133 Backlog /in Progress 0

0 0

0 0

0 0

Mod. Requests Being Reviewed 0

0 1

0 0

0 1

Design Engr. Backlog /In Progress 0

0 3

26 0

5 34 Construction Backlog /In Progress 5

3 25 2

0 0

35 Design Engr. Update Backlog /In Progress 1

4 3

0 0

0 8

Totals 6

7 32 28 0

5 78 (Outage + OnLine)

(3+3)

(0+7) (19+13) (19+9)

(0+0)

(5+0)

(46+32)

At the end of June 1995,10 additional modification requests had been issued this year and 4 modification requests had been cancelled. The Nuclear Projects Review Committee (NPRC) had completed 34 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) had completed 4 backlog modification request reviews this year.

i

• A review of the reports used to determine the tota! number of outstanding modifications and their various stages of accomplishment was undertaken at the request of the Nuclear Planning De-partment. The results of the review determined that the reports were not providing complete /

accurate data. The reports have been corrected. The revised totals beginning with the March 1995 data are reflected in the current graph.

The 1995 year-end Fort Calhoun goal for this indicator is a maximum of 63 outstanding modifica-tions.

Data Source:

Skiles/Ronne (Manager / Source)

Scofield/Lounsberry (Manager / Source)

Accountability:Scofield/Phelps Adverse Trend *-

None 1

59 i

80 -

EARS Requiring Engineering closeout - Not in Closeout 80 -

5 SE D DEN 40 -

20 -

0

.U.

-i Apr May Jun Apr May Jun Apr May Jun Apr May Jun 0-3 Months 3 6 Months 6-12 Months

>12 Months June 1995 Overdue EARS O Engineering Response 5 Clooeout(SE) 80 -

60 -

W M

Priority 0 Priority 1 Priority 2 Priority 3 Priority 4 Priority 5 Priority 6 l C Priority 1 & 2 m Priority 3

- Total open EARS]

150 --

100 -

0 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 to2 EARS 77 EARS yy %

102 Owenha W

has*** sad ci o.os assenese (y

43.o%

57 0%

\\j N

hj

=

J ENGINEERING ASSISTANCE REQUEST BREAKDOWN This indicator shows a breakdown of the number of EARS assigned to Design Engineer-ing and System Engineering. The 1995 year-end goal for this indicator is a maximum of 140 outstanding EARS.

Total EAR breakdown is as follows:

EARS opened during the month 22 EARS closed during the month 23 Total EARS open at the end of the month 179 Data Source:

Skiles/McShannon (Manager / Source)

Accountability:

Jaworski/Skiles 60

Closecut = 174 DEN = 167

> 6 Months =

0 3 Monthe =

30 7 %

27.7%

225 242

~

'" '7es'

• 3 8 "aar** =

1. ' YO con.,

= e i

ECN Status = Overall Backlog

> 6 Months =

O-3 Months =

O Bacidogged D Received D Completed 50 n

31.a %

as4%

hl

{ " a2 j

y j

=

y

{

100 -

,o 50 i

f 1

.i 22

=

3.e monen,. mi E

31 5

' ~

0 w

Jan45 Feb Mar Apr May Jun45 Design Engineering 260 0-3 Me =

> 6 Months

= 49 18 200 7 6d [

.[

(

i&O _

,00 4 :

J'

=

a a

e

$0 i n,.

1 ""

Eun E n s.

E,,,.

S*

0+

+

+

+

+

3-8 Months =

J a n-S S Feb Mar Apr May Jun 96 22

• • ~5' System Engineering 250 -

o 3,,,,,,,

> 6 Monthe =

49 200 -

in m

70 150 -

s.s 47 3 32 es s.s 7

g 7

g 100 -

i 5

)

5 b

i i

5 5

i i

^j 60 '

d u,,

k",,

i it' n i

in.

b ss no

,e I+

0-4-

+

+

+

3-6 Months =

Jan45 Feb M ar Apr May Jun45 27 Procurement / Construction 250-

>8"=**=

se 3 2.2 m 200 -

i t.

.s u ww. =

160 -

3 in 100 -

=

r

=

8 e.,

60 -

L ai n E was

[-

f 3,

E

?

no O--

T +- T +

- a-+

3""'"**

+

4 Jan46 Feb Mar Apr M ay Jun46 11 ss Draft na/ Closeout ENGINEERWG CEANGE NOTICE STATUS Data Source:

Skiles/McShannon (Manager / Source)

Accountability:

Skiles/Jaworski Adverse Trend:

None SEP 62 61

Pnodty 5 &

Priorny 1 &

Priority 5 &

Priority 1 &

6 = 123 2 = 11t 6 = 123 2=110 2

19A%

21.

19A%

NINlIBBl IElllWIlWIWilIIIWll IIIMlllliggglggg Nff j l !

lhlllll

,l

' Priority 3 &

0 sll s

'I

,co m

! Prionty 3 &

l p.'

L

,,%.I q "L

/

4 >=

.. u

.k.

Es.s%

88 8%

Total Open ECNs by Priority (567 Total)

Total Open ECNs by Priority (567 Total)

D DEN. Closeout or Drafting Not Complete 5 Maintenance / Construct 6on/ Procurement. Work Not Complete Priorities Priorttles D System Engineering Response, Confirmation Not Complete 5&8 1&2 B DEN. Engineering Not Complete 21.1%

15.7%

.jg2

[

gjjggi 8'

38 87 q

p 150 100-s2 so s4 so 7

l l

-l ll..-l ahj,i ot [

i k,,"j'*..._l;].

8 l

ll lI l

50 2

5 e

a n

I 1I I

l.

a,

2 53 s4 62 ss 7

Jan46 Feb Mar Apr May Jun45 4

Facility Change ECNs Open 63.2%

360 3,,

3,,

Priorttles Priortues 2so 300 ass S&6 1&2 se s4 s'

122 14.4%

25.9%

250 7 (j(

111lllll1, 200 -

l 160-es 7,

es i

0 f

l U**

Jan45 Feb Mar Apr May Jun46 3'4 Substitute Replacement item ECNs Open 160 -

14e Priorities 140-IE2 120 -

I 30 100 -

3:

l

(, J-l

.m.

t j

p L

,d.\\

• * ~

'1

=

e$

e

=s g,,

l, g

g a

,e 2s 3&4 20 -

30 so at 36

""E~.

8' 0-H Jan46 Feb Mar Apr May Jun46 6

Document Change ECNs Open 57.s %

ENGINEERING CHANGE NOTICES OPEN Data Source:

Skiles/MicShannon (Manager / Source)

Accountability:

Skiles/Jaworski Adverse Trend:

None SEP 62 62

i l

D Administrative Control Problem 3-E Licensed Operator Error E Other Personnel Error 5 Maintenance Problem D Design / Construction / installation /Fabriation Problem E Equipment Failures 2-J 1

l:

11 0

Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 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 June 1,1994, through May 31,1995. To be consistent with the Preventable / Personnel Error LERs indicator, this indicator is reported by the LER.

event date, as opposed to the LER report date.

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

i There were no events in May 1995 that resulted in an LER.

Data Source:

Trausch/Cavanaugh (Manager / Source)

Accountability:

Chase Adverse Trend:

None 63

1 0 Total Requalification Training Hours 5 simulator Training Hours D Non-Requalification Training Hours B Number of Exam Failures 40 -

37 37 37 37 35.5 35 -

32 30 30 -

25 -

20 -

17 1

14 15 -

12

. 3,s 10 10 -

.s g3 s

5-3 3

33 3

2.5 0

Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle 94-3 94 4 94-5 94-4*

94-7 95-1 95-2 95-3

• Note 1: The Simulator was out.of-service during Cycle 94-4.

" Note 2: Includes 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of General Employee Training.

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 APO/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 two (2) written exam failures and three (3) crew simulator failures during rotation 95-3. All individuals and crews were remediated without impacting the opera-1 tions schedule. IR #950447 was written to document the circumstances surrounding the simulator failures.

l I

l Data Source:

Gasper /Guliani(Manager / Source) l Accountability:

Gasper /Guliani Adverse Trend:

None SEP 68 I

l

E SRo Exams Administered O SRo Exams Passed D Ro Exams Administered B Ro Exams Passed 20 -

15 -

10 -

i 5-0 Jul Aug Sep oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 LICENSE CANDIDATE EXAMS This indicator shows the number of Senior Reactor Operator (SRO) and Reactor Operator (RO) quizzes and exams taken and passed each month. These internally administered quizzes and exams are used to plot the SRO and RO candidates' monthly progress.

For the month of June 1995, no RO or SRO examinations were administered, with the exception of one remedial examination. The examinee passed his remedial examination.

l Data Source:

Gasper /Guliani(Manager / Source)

Accountability:

Gasper /Guliani Adverse Trend:

None SEP 68 65 l

m Open irs >6 Months Old C Open Significant irs

-+- Total Open irs 600 -

500-m

)

i 400

. - - ~

300 -

228 231 200 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun 1994 1995 OPEN INCIDENT REPORTS This indicator shows the total number of Open irs, irs greater than 6 months old, and the number of open significant irs.

Also, at the end of June 1995, there were 499 open irs.170 of these IRS were greater than 6 months old. There were 100 Open Significant irs at the end of the month. These numbers have been restated to reflect the elimination of CARS from the system. As of April 21,1995, CARS are no longer being issued. All future corrective actions will be documented on irs.

t Data Source:

Conner /Plott (Manager / Source)

Accountability:

Andrews/Phelps/Patterson Adverse Trend :

None 66 l

l f

l l

l Data for the 1996 Refueling Outage will not be available until the summer of 1995.

MWO PLANNING STATUS (CYCLE 16 REFUELING OUTAGE)

This indicator shows the total number of Maintenance Work Requests (MWRs) and Main-tenance 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 to 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) 1 8

l.

Data Source:

Chase /Schmitz l

Accountability:

Chase /Faulhaber Adverse Trend:

None 67

-+- Baseline Schedule for PRC Approval

-G-Projected / Actual Schedule for PRC Approval 7

Total Modifk:stion Packages (19)(4 Added Late. 3 review for Cancel) 10 9-

}B8-o ml 7'

'~

5 a.

'5

.g 4 3-2-

^0000.

a.

EL 1 0

,;.H

,l EE$$E$h.kEEhEEEE$E Ihk$e E

• 8-a;e nE8 Bn**=8a nn na aM-a n

a ae n~a.

g PROGRESS OF CYCLE 17 OUTAGE (1996 OUTAGE MODIFICATION PLANNING)

(FROZEN SCOPE OF 10 MODIFICATIONS)

This indicator shows the status of Modifications approved for installation during the Cycle 17 Refueling Outage. Modifications added to the outage list after May 1,1995, are not part of this indicator. The data is represented with respect to the baseline schedule (es-tablished June 16,1995) and the current schedule. This information is taken from the modification variation report produced by Design Engineering Nuclear.

1 The goal for this indicator is to have all modification packages identified prior to May 1, 1995 PRC approved by March 22,1995. 4 Modifications added after May 1,1995, not included.

June 1995 Modifications added: 0 Deleted = 0 t-1 Data Source:

Skiles/Ronne (Manager / Source)

Accountability:

Phelps/Skiles Adverse Trend:

None SEP 31 68

.x

--+-- Baseline Schedule for PRc Approval

-e-- Projected / Actual Schedule for PRC Approal Total Modification Packages (12)(1 is Close Out Only) 12 -

g h 10 -

!5

.. f_. 7 '

a-ke S #

2e 8

34 4 4

EE E?j2 e.

0 EElEEEE$$$EEEEE$$E$EEEE

$8a cRE5 g:..E $ G E 5 a - E :. G. E G E n

--a

~

a g g PROGRESS OF 1995 ON LINE MODIFICATION PLANNING (FROZEN SCOPE OF 11 MODIFICATIONS)

This indicator shows the status of modifications approved for on-line installation during 1995. The data is represented with respect to the baseline schedule (established 1/13/

95) and the current schedule. This information is taken from the Modification Variation Report produced by the Design Engineering Nuclear group.

The goal for this indicator is to have all modification packagas identified prior to 1/13/95 PRC approved by October 30,1995.

June 1995 Modifcations Added: 2 Deleted = 0 Mod FC94-008 Carry over from '95 out - Const. only FC94-012 Carry over from '95 out - Const. only Data Source:

Skiles/Ronne (Manager / Source)

Accountability:

Phelps/Skiles Adverse Trend:

None SEP 31 69

I l

-+- asemane schedues ser Pnc Approves

-e-ProjecteeActual schecide for Pac Approve Totes neoencation Pacheses fe) p Added t.ees,1 review for cances) s --

s-7-

6 l

^

g4-s-

g I3-

^ :: :1

^::::::.

2-1-

0 h

If!$f$f fk!$

$ff$f 5

5s 5S E

,;;j$E,C N-5 PROGRESS OF 1996 ON-LINE MODIFICATION PLANNING (FROZEN SCOPE OF 6 MODIFICATIONS)

This indicator shows the status of modifications approved for on-line installation during 1996. Modifications added to the on-line list after May 1, W5, are not part of this indica-tor. The data is represented with respect to the base':ae schedule (established June 16, 1995) and the current schedule. This information is taken from the modification variation report produced by Design Engineering Nuclear.

The goal for this indicator is to have all modification packages identified prior to May 1, 1995 PRC approved by March 25,1996. 2 Modifications added after May 1,1995, not included.

June 1995 Modifications Added: 0 Deleted = 0 L

i I

Data Source: Skiles/Ronne (Manager / Source)

Accountability:

Phelps/Skiles Adverse Trend:

None SEP 31 70

O ACTION PLANS O

71

1 ACTION PLANS This section lists action plans that have been developed for the performance indicators cited as Adverse Trends during the month preceding this report. Also included are Action Plans for indicators that have been cited in the preceding month's report as Needing increased Management Attention for three (3) consecutive months.

In accordance with Revision 3 of NOD-OP-37, the following performance indicators would require action plans based on three (3) consecutive months of performance cited as "Needing increased Management Attention"-

. Industrial Safety Accident Rate (page 2)

. Temporary Modifications (page 57)

The action plan for industrial Safety Accident Rate (page 2) is as follows:

REVERSING THE INDUSTRIAL SAFETY ADVERSE TREND

• RESTATED ACCIDENT REPORTING PROCEDURES / PROTOCOL

-Necessary because 3 Lost Times involved late reporting and delayed Physician care

• lSSUED EXPECTATIONS THAT THOSE WHO CAN WORK SUBSEQUENT TO AN INJURY ARE EXPECTED TO DO SO

• PROVIDING TREND ANALYSIS BY DEPARTMENT, TO RESPONSIBLE FIRST LINE SUPERVISORS

-Information is from documented injury reports.

-OSHALOG 200, Manager Plus will provide future information to Trend Breakdown and Cost Benefit Analysis alNDUSTRIAL SAFETY COORDINATOR ATTENDING EMERGENT WORK MEETINGS TO OVERSEE PRIORITY ASSIGNED TO SAFETY RELATED WORK PROJECTS

• SAFETY COMMITTEE IS ASSIGNING DEADLINES TO WORKING SAFETY SUGGESTIONS 72

ACTION PLANS (continued)

The action plan for Industrial Safety Accident Rate (page 2) continues as follows:

• ERECTED A STATION INDUSTRIAL SAFETY STATUS BOARD

• SAFETY PERFORMANCE ENHANCEMENT COMMITTEE WILL MEET DAILY UNTIL WINDOW IMPROVES

• REQUESTED AN INPO STAFF ASSISTANCE VISIT (Action completed)

• lNDUSTRIAL SAFETY IS ON PLANT MANAGERS PRIORITY LIST ON PLAN OF DAY The action plan for Maintenance Workload Backlogs (page 46) is as follows:

A detailed review is being conducted to determine which stage of the maintenance process has a higher than expected backlog. Areas being reviewed are:

Planning Scheduled Maintenance Bulk Work Package closeout Corrective actions will be initiated based on the results of that review.

The action plan for Temporary Modifications (page 57) is as follows:

The Temporary Modification program needs to have its program goals revised to reflect current NPRC scheduling practices. This will be completed by August 1,1995.

O 73

_. _~

_-~.-

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PERFORMANCE INDICATOR DEFINITIONS j

AUXLIARY FEEDWATER SYSTEM SAFETY SYSTEM CLEAN CONTgens a srn' AREA CONTAMelATIONS > 1,000 PERFORMANCE DISINTEGRATIONS / MINUTE PER PROSE AREA I

The sum of the imown (planned and unplanned) unevatobie The personnel oontammation svents in the cisen oontround eren.

hours and the sehmeted uneveBoble hours for the munihery This indestor tracks personnel performance for SEP #15 & 54.

feedwater system for the reportmg perted dMded ty the crtlical hours for the reporting period muluphed try the number of trains CONTAMINATED RADIATION CONTROLLED AREA

~

in the sumihery feedwater system The percentage of the Radshnq ControNed Area, which includes COLLECTIVE RADIATION EXPOSURE.

the sumilary building, the r=d==s= bulidmg, and areas of the C/RP buedmg, that is contaminated bened on the tetel square r

Colecthe redulen myosure is the total eetemed whole-body done footage. This indcolor tracks performance for SEP #54.

~

received by en on-one pwoonnai (including contractors and victors) dunng a tone period, as moseured by the DAILY THERMAL OUTPUT thermolummencent dommeter (TLD). Conective redation oposure is reported in unas of person-rem. This indcator tracks This indicator shows the daily core thermal output as measured t

rodeiogcol work perfwmence fw SEP #54.

from computer point XC105 (in thermal megewetts). The 1500 MW Tech Spec limit, and tie unmot portion of the 1495 MW FCS _

COMPONENT FAILURE ANALYSIS REPORT (CFAR) daily goal for the reportmg month are eleo shown.

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SUMMARY

DIESEL GENERATOR RELIABILITY (26 Demands)

The summary of INPO categones for Fort Calhoun Station with egndicently higher (1.645 standard devishone) failure rates then.

This indicator shows the number of failures occumng for each the rest of the industry for en eghteen-month time period.

emergenoy stesel generator dunng the lset 25 etert demands end Failures are reported as component (i.e., pumps, motors, mom the last 25 load-run demands steem stop vehes, control element motors, etc.) categones DISABUNG INJURYALLNESS FREQUENCY RATE 6

Failure Cause Categones are:

(LOSS TIME ACCIDENT RATE)

Wear Out/ Aging. a future thought to be the consequence of This indcator is dermed as the number of accidents for eN uhtly expected weer or agmg.

personnel permanently asegned to the station, invoMng days many from work por 200,000 men-hours worked (100 man-years).

Manufacturing Defect a feHure attributobie to irW=i=

This does not incksde cordnector personnel. This indmetor tracks essembly or initial quauty of the responsible component or personnel performance for SEP #25,26 S 27.

system.

3 DOCUMENT REVIEW (BIENNIAL)

EngineeringfDosign a failure attributable to the inadequate desegn of the responsible component or system.

The Documert Review indkator shows the number of documents reviewed, the number of documeres scheduled for review, and the Other Devices a failure attributable to a feNure or number of document reviews that are overdue for the reportmg misoperation of another w..,~,-,a or system, mcludmg morth. A documart review is considered overdue if the review is estociated devees not complete within six months of the seeigned due dele. This J

indicator tracks performance for SEP #46.

MaintenanceITesting - a failure that is a result of improper memtenance or testing, lack of memtenance, or personnel errors that occur during mantenance or testeg actMties EMERGENCY AC POWER SYSTEM SAFETY SYSTEM performed on the responable component or system, including PERFORMANCE failure to follow procedures.

The sum of the known (planned and unplanned) unevetable and Errors - futures attributobis to incorrect procedures that were the estimated unevellable hours for the emergency AC power i

followed as wrtiten, improper inetmashon of equement, and system for the reporting period omded ty the number of hours in i

personnel wrors (inctueng feature to fonow procedures the reportmg period nP by the number of trains in the property). Also included in the category are feMuros for which emergency AC power system.

cause a unknown or cannot to esegned to any of the precedeg categones CENTS PER KILOWATT HOUR The purpose of this indicolor is to quenhfy the economest operation of Fort Calhoun Staten. The cents per idlowatt hour inckuler repreewes the budget and actual cents per idlowett hour on a twehe-morfh euerage for the current year. The basis for the budget curve is the approved yeerty budget. The base for the actual curve is the Financial and Operating Report.

i 74

PERFORMANCE INDICATOR DEFINITIONS EMERGENCY DIESEL GENERATOR UNIT RELIABILITY E) A failure to start because a portion of the starting system was disabled for test purpose, if followed by a successful This indicator shows the number of failures that were reported start wth the starting system in its normal ahgnment.

dunng the last 20, 50, and 100 emergency diesel generator demands at the Fort Calhoun Staten. Also shown are tngger Each emergency generator failure that results in the generator values which correlate to a high level of confdence that a unit's being declared hoperable should be counted as one demand and diesel generators have obtained a rehabihty of greater than or one fature. Exploratory tests during correctrve maintenance and equalto 95% when the demand failures are less than the trigger the successful test that follows repair to venfy operability should j

values.

not be counted as demands or failures when the EDG has not j

been declared operable again.

1) Number of Start Demande: AX vahd and inadvertent start demands, including all start only demands and sti start EMERGENCY DIESEL OENERATOR UNRELIABILITY demands that are followed by load-run demands, whetner by j

automate or annud initiatort A startonly demand is a This rdicator measures the total unreliabihty of emergency desel J

demand h which the emergency generator is started, but no generators. In general, unrehabihty is the ratio of unsuccessful attempt is made to load the generator, operatons (starts or load-runs) to the number of vahd demands.

l Total unreliabihty is a combinaton of start unrehability and load-

2) Number of Start Failures: Any failure within the run unrehabihty.

j emergency generator system that prevents the generator

~

from achMMng specified frequency and voltage is classified ENGINEERING ASSISTANCE REQUEST (EAR) as a vand start failure. Thrs includes any conditon identified BREAKDOWN in the course of maintenance inspectons (with the emergency generator in standby mode) that definitety would This indcator shows a breakdown, by age and pnonty of the have resulted in a start failure if a demand had occurred.

EAR, of the number of EARS assigned to Design Engineenng Nuclear and System Engineenng. This indcator tracks

3) Number of Load-Run Demands: For a vahd load-run performance for SEP #62.

demand to be courded the load-run attempt must meet one or more of the foilowing enteria.

ENGINEERING CHANGE NOTICE (ECN) STATUS A) A load-run of any duration that results from a real The number of ECNs that were opened, ECNs that were automate or manualinitiation.

cortpleted, and open backlog ECNs awaiting complebon by DEN for the reporting month. This indicator tracks performance for B) A load-run test to satisfy the plant's load and duraton SEP #62.

es stated in each test's specifcatons.

ENGINEERING CHANGE NOTICES OPEN C) Other special tests in whch the emergency generator is expected to be operated for at least one hour while This indcator breaks down the number of Engineenng Change loaded with at least 50% of its design load.

Notees (ECNs) that are assigned to Design Engineering Nuclear (DEN), System Engineenng, and Maintenance. The graphs

4) Nuriter of Load-Run Failures: A load-run failure should provide data on ECN Facihty Changes open ECN Substitute be counted for any reason in which the emergency Replacement items open, and ECN Document Changes open.

generator does not pck up load and run as predcted.

This indcator tracks performance for SEP #62.

Failures are counted dunng any valid load-run demands.

EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL

5) Exceptions: Unsuccessful attempts to start or load-run HOURS should not be counted as vahd demands or failures when they can be attributed to any of the following:

Equpment forced outages per 1,000 critcal hours is the inverse of the mean time between forced outages caused by equipment A) Spunous tnps that would be bypassed in the event of failures. The mean time is equal to the number of hours the an emergency.

reactor is critcal in a period (1,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />) divided by the number of forced outages caused by equipment failures in that pened B) Malfmetion of equpmert that is not required dunng an emergency.

EQUNALENT AVAILABILITY FACTOR C) Intentional terminaton of a test because of abnormal The inck:stor is defined as the ratio of gross avaliable generaton condtons that would not have resulted in major diesel to gross maximum generston, expressed as a percentage a

generator damage or repar.

Avahbie generston is the energy that can be produced if the unit is operated at the maximum power level permitted by equipiTent D) Marmetions or operating errors which would not hme and reguWory Imtations. Maximum generaton is the energy that prevented the emergency generator from being can be produced by a unit in a given penod if operated restarted and brought to load within a few minutes continuously at maximum capacity.

75

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r PERFORMANCE INDICATOR DEFINITIONS ~

FORCED OUTAGE RATE DIDUSTRIAL SAFETY ACCE3ENT RATE RS'O This indicator is defined as the percordage of time that the unR The hecutoris defined as the number of accidents per 200,000 f

was uneveNetdo due to forced events compared to the tune morehours worked for aN uttly personnel permanorgy esogned pionned for elocincel genershon. Forced events are futures or to the stelion that result in any of the foRowmg-other unplanned condhons that require removing the unit from service before the and of the nemt weekend Fotood events

1) One or more days of reatnoted work (exclueng the day tf f

includs el.rt-u,- and overds met.d w o ho un. s.

ihe.co.ordx -

reserve shutdown (i.e., the unit is ausgletdc but not in service),

i

2) One or mose days away from work (excludmg the dtf of the f

FUEL RELIABILITYINDICATOR accident); and The indcolor is deAned as the steady-etste pnmary cooient 1-131

3) Feleimos actMty, corrected for the tramp ureneum contreuhon and

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normehend to a common punAcehon rate. Tromp urean as fuel Contractor personnel are not included for this indcator j

which has been deposted on reactor core intemels from previous 6

defechvo fuel or is presord on the surtees of fueleio nents from IN LINE CIEMISTRY INSTRUMENTS OUT OF SERVICE the manufacturing process Stoody siste is defined as

[

conhnuous opershon for et loest three days et a power level that Totsi number of in-ilne chemetry instruments that are out<W-

'l does not wry more then + or -5%. Plants should collect dets for memos in the Secondary System and the Poet Accident Samphng f

the hecolor et a power level above 85%, when possible Plants Syalam (PASS).

j that did not operate et steady-elete painer above 85% should collect date for this inecator et the highest op power UCENSE CANDEATE EXAMS level attained dunng the month.

}

This indcutor shows the number of SRO and/or RO quizzes and i

The densay conochon factor is the robo of the spacec volume of enoms that are admmatored and pensed each month. This cocient et the RCS operahng temperature (540 degrees F., Vf =

indeslor trooks trening performance for SEP908.

0.02146) dMded by the speclAc volume of cooient et normel leidsontemperature (120' F at outlet of the letdown coolmg heat UCENSED OPERATOR REQUALFICATION TRARBIG authanger, Vf = 0 018204), which rootdie in a donemy correchan

+

fedor for FCS equel to 1.32.

The toted number of hours of treewng given to each crew during each cycle. Also pnuded are the simuncor trekAJ hours (which i

OROSS HEAT RATE are a subest of the total trommg hows), the number of non-REQUALIFIC# TION traming hours and the number of enom t

Gross heet rate is dehned as the raho of total thermal energy in futures. The iru,1cator tracks trening performance for SEP 888.

l t

Brihsh Thermal Units (BTU) produced by the reactor to the total groes electncel energy produced by the generator in talowatt-hours (KWH).

HAZARDOUS WASTE Penrmn j

i The total amount (in Kilograms) of non :

^ J hazardous weele, hebgenseed hazenseus weste, and other hemordous weste l

produced by FCS each month.

i HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PEWFORMANCE hatra and the eshmeted uneveinstue hours for the high pressure

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The sum of the known (planned and unplanned) unevelleele I

safety infection system for the reportmo pened duded by the amtd hours for the reporting perted mumphed by the number of trams in the hgh pressure safety injecton system

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PERFORMANCE INDICATOR DEFINITIONS UCENSEE EVENT REPORT (LER) ROOT CAUSE Preventive - Actions taken to meirt.ain a piece of equipment BREAKDOIMN wthin design operstmg condihons, prevent equipment failure, and udend as Ife and are performed prior to equipment faNure.

This indicator shows the number and root cause code for l

Liconese Event Reports. The root cause codes are as foNows:

Non4ctractivertent __

.. _. _ - Memtenance l

actMbes performed to implement station improvements or to t

1) Administrative Control Problem - O.

;._a and repair non pient equipment l

e supervloory donciencies that affect plant programs or acWhos (i e., poor pierwung, brank*mm or lack of sh umsa Maintenance Woric Priorities are dehnod as:

f i

management or supervisory control, incorrect procedures, etc).

Ernergency. Conditens whch significantly degrade station l

safety or avellately.

2) Licensed Operator Error. TNs cause code captures enors of omissorWoommeson by licensed reactor operators lenmediate Action - Equipment deficiencies which i

dunng plant actMhos sagruficantly degrade stehon rehetely Potential for unit shutdown or power reduction.

3) Other Personnel Error Errors of omisserVcommesson committed by non-hcensed personnel involved in plant Operations Concern Equipment defconcies which hinder actMties etshon opershon.

j J

4) Mahilenance Problem The intent of this cause code it to Essential - Routme correctrve memtenance on essential 3

capture the full range of problems which can be attnbuted station systems and equipment.

I h any emyto propommehc deficencies in the maintenance functionsl orgenersten. ActMhes included in this category Non Essential Routme corrective memtenance on non-

]

ore momeenonce, testmg, surveillance, cohbration and essenhol elabon systems and equipment.

radehon protecten.

Plant Improvement. Nort. corrective maintenance and plant 5) ahrication Problem.

Improvements This cause code covers a fun range of programmatic detaences in the areas of design, constructen, instenshon, The indicator tracks memtenance performance for SEP #36.

l and lebnceton (Le, loss of control power due to underrated 1

fuse, equipment not quehRed for the ermronment, etc.).

MAXIMUM INDIVIDUAL RADIATION EXPOSURE

{

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6) Egulpment Failures (Electronic Piece Perts or The toget mammum amount of raememn received by en indMdual

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EnvironmentaWieteted Failures). This code is used for perscm working at FCS on a monthly, quarterly, and annual basis.

y spunous failures of electronc pece-ports and failures due to meteorolopcel condmons such as hghtning, ice, high MWO Pt.ANNING STATUS (CYCLE 14. REFUEUNG j

Generap, it includes spunous or one-tune OUTAGE) winds, etc.

y futures. Electric components included in tNs calogory are circuit cards. rocerers, betables, fuses, cepecitors, dedos, The total number of Memtenance Work Orders that have been reesstors, etc.

approved for inclusion in the Cycle 16 Refuehng Outage and the number that are ready to wortt (parts staged, planning complete, Lwaams F4tEPORTABLE INCIDENTS (SECURITY) and aR cther paperwork ready for Held use). Also included is the j

number of MWOs that have been engineerin0 holds (ECNs, The total number of securty incidents for the reportmg month procedures and other meceseneous engineering holds), parts depcted in two graphs. This indcator tracks securtly hold, (parts staged, not yet inspected, parts not yet arrtved) and

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performance for SEP #58.

pionning hold (job scope not yet completed) Memtenance Work Requests (MWRs) are eleo shown that have been identified for l

NAINTENANCE OVERTIME the Cycle 16 Refuehng Outage and have not yet been converted to MWOs.

The percent of overtime hours compared to normat hours for i

e montenance. This hebdes OPPD personnel as weH as contract personnel 1

MAINTENANCE WORKLOAD BACKLOGS e

i Thts indcator shows the bacidag of nortoutage Maintenance Work Orders remommg open at the end of the reportmg month.

Memtenance closelAcetens are denned as fotows:

Corrective Repair arg restorehon of equipr9ent or components that have failed or are malfuncienmg and are not t'

performmg their intended functon t

i 77 i

i PERFORMANCE INDICATOR DEFINITIONS NUMBER OF CONTROL ROOM EQUIPMENT DEFICENCIES 2) namen,.sh i Roguests Being Reviewed. This cologory includes A cordrol room equipment deficiency (CRD) is defined as any component which is operated or cortroned from the Control A) ModlAceton Requests that are not yet rowowed.

- Room, psouldes hdoslien or sierm to the Controi Room, provides

]

testmg e=fiam== from the Control Room, prendes automatic B) ModAcehon Requests being renewed ty the Nucteer i

actions from or to the Control Room, or prowdes a possive Projects Renew Commmee (NPRC).

i funct6on for the Control Room and has been identmed as 4

descient,i.e, does not perform under au condihons as designed C) hhdfication Requests bomg renewed by the Nucieer

.I The dehntion also apphes to the Atometo Shutdown Peneis Al-Profects Commmee (NPC).

I 179, Al-185, and Al-212.

These Mod Acetion Requests may be reviewed several times A piert component which is dehcent or inoperabie is considered belowtheyareapproedfor Diii iorconceled. Some l

en

• Operator Work Around (OWA) llem"if some other nhon is of these Modehoshon Requests are retumed to Engmeeting for

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required by an operator to componente for the condthm of the more informehen, some approved for evolushon, some approved j

component. Some examples of OWAs are:

for study, and some approved for pionning. Once planning is comp 6sted and the scope of the work is cieerly dehnod, these

1) The control room level indicator does not work bu a local MotAcetion Requests may be approved for accomphshment with I

sight glass een to read by an Operator out in the plwe, a year aseqpied for construchon or they may be canceled AR of j

these different phases require review.

j

2) A doncaent pump cannot be repaired because repiscement parts reques a long lead time for pc Cci, thus

3) Design Engineering Bacidog4n Progrees Nucteer reqLenng the redundant pump to be operated contmuously; Plannmg hos aseqined a year in which construction win be

3) Specal actions are required by an Operator haemima of equipment design problems These schone may be

4) Construction Bacidogan Progrees. The Construction I

described in Openshans Memorandums, Operator Notes, or Pechage has been leeued or construchon has begun but the may reques changes to Operahng Procedures, modrhostion has not been accepted by tte System

?

Acceptance Commmee (SAC).

4) DeAceert pimit equipment that is requesd to be used dunng l

Emergency Operehng Procedures or Abnormal Operstmg

5) DealpiEnginnedng Update Bacidogan Progrees PED Procedures, has recehed the Moeficehon Compiehon Report but the drawings have not been updeled

5) System indesten that prendes criticolinformehon dunng l

normal or abnormal opershons The ateve menhoned outetendng moshcohans do not include modificehone which are proposed for conceNehon NUtelpt OF MISSED SURVEILLANCE TESTS RESULTING IN LICENSEE EVENT REPORTS OVERALL PftOJECT STATUS (REFUEUNG OUTAGE) i The number of Survedlance Tests (STs) that resut in Liconoce The inecator shows the esclus of the projects which are in the Event Reports (LERs) during the reportmg month. TNs indicator scrios of the Refuelmg Outage.

l tracks missed STs for SEP #00 & 61.

Pt'RC'@fTAGE OF TOTAL MWOs COtrLETED PER MONTH I

OPEN CORRECTIVE ACTION REPORTS & INCIDENT ICENTIFIED AS REWORK REPORTS The percereage ofinesilWVOs compleesd per month identified as The inecc.* Joplays the total number of open Conectrue Act on remeA Rework acAMhos are idenhnod by maintenance pionning Reports (C 4Rs), the number of CARS that are older then six and craft Rework is: Any adebonel work requesd to correct morths and he number of signiflcent CARS. Also displayed are detaences decovered during a failed Post Mantenance Test to the numbe ' of open incedent Reports (irs), the number of irs ensure the component / system peamos andmatant Post i

that are g aster then six months old and the number of open Momtenance Test.

signrficent 'Rs.

+

?

PERCENT OF COMPLETED SCHEDutED MAINTENANCE OUTSTANL11NG MODIFICATIONS ACTIVITIES

]

The rusnbar t.' Maddicehon P=9==8= (MRs) in any state between The percent of the rnmber of completed memtenance actMtes the issuance v a Modificaten Number and the compiehon of the as compared to the rtmber of scheduled memtenance actMties drawing update, each month. This peromtege is shown for au maintenance I

crests. Aino shown are the number of emergent MWOs.

1) Form FC-1133 Bacidogan Progress. This number Maintenance actMhos include MWRs, MWOs, STs, PMOs, j

represents modrhcohon tsquests that have not been plant cabbrehens, and other tr6eceNaneous actMties. This inchcetor i

approved dunng the reportmo month.

tracks Memtenance performance for SEP #33.

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i 78 l

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E PERFORMANCE INDICATOR DEFINITIONS

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PREVENTABLE /PERS00SEL ERROR LERs paruru nGICAL WORK PRACTICES PROGRAM This indicator is a treakdown of LERs. For purposes of LER The number of identified poor redmiogscal work prochces I

. event clemencehon, a "Proventehle LER" is defined as:

(PRWPs) for the reporting month. This indcator tracks e

redmiopical work performance for SEP #52.

j An event for which the root cause is personnel error (i.e.,

inappropnote action by one or more individuals), erwengn=

RADIO OF PREVENTIVE TO TOTAL MAINTENANCE &

)

admrustrative controls, e design constructen, instenshon, PREVENTIVE MAINTENANCE ITEMS OVERDUE motellehan, fatricehon problem (invoMng work completed by l

or swervloed by OPPD personnel) or a maintenance problem The rato of prownhve maintenance (mcludmg sunedionoe lostmg l

(ettnbuted to inaram,pata or improper '-f

, L, of plant and celitrabon procedures) to the sum of non-outage corrective equipmert). Also, the cause of the event must have occurred maintenance and preventive memtenance completed over the withri appreidmdely two years of the

• Event Date" epoceed in reporting period. The ratio, expressed as a percentage, is j

the LER (e g., en event for whch the cause is attributed to a eaad beood on man-hours. Also deployed are the percent problem with the enginet design of the plant would not be of preventive maintenance items in the month that were not l

considered preventable).

corgisted or.b J r; closed by the scheduled dele plus a grace ponod equal to 25% of the scheduled interval This For purposes of LER ownt cleosifeshon, a " Personnel Error" indcator tracks preventive mantenance actrvities for SEP #41.

LER is defined as foNows:

RECORDABLE INJURYALLIESS CASES FREQUENCY i

An ownt for which the root cause is inappropnete acten on the RATE

'l part of one or more individuals (as eff==ad to beme attributed l

to e deportment or a general group). Also, the inappropnete The number of ir$ures requmng more then normes first aid per l

action must have occurred within opprommately two years of 200,000 man-hours worked The indcolor trends personnel 1

the " Event Date" specified in the LER.

performance for SEP #15,25 and 26.

j Aadlemnally, each event cleesefied as e " Personnel Error" should REPEAT FAILURES also be cleosifed as "Proventable* The indcator trends i

personnel performance for SEP ltem #15.

The number of Nucieer Plant Rehotukty Data Syelem (NPRDS)

{

components with more then one feiture and the number of a

PRIMARY SYSTEM CHEMISTRY % OF HOURS OUT OF NPRDS componerts wth more then two feHures for the eighteen.

.l LIMIT month CFAR pared.

')

p The percent of hours out of hmit are for six pnmary chemetry SAFETY SYSTEM FAILURES parameters divided by the total number of hours possible for the i

month. The key parameters used are: Lithium, Chionde, Safety system failures are any events or conditions that could l

Hydrogen, Desolved Oxygen Fluonde and Suspended Solids.

prevent the fulfillment of the safety funchons of structures or EPRI hrruts are used.

systems. If a eyelem coneeste of mulhpie redundant subsystems l

or trains, failure of en trams conohtutes a safety system failure.

]

PROCEDURAL NONCOMPLlANCE INCIDENTS Failure of one of two or more trains is not counted as a safety (MAINTENANCE) system failure. The deflnihon for the indcator pereReis NRC i

reportry recNiremeras in 10 CFR 50.72 and 10 CFR 50.73. The The number of 6dentified incidents concommg maintenance fotowng is a het of the mejor safety systems, sut>eystems, and procedural problems, the number of closed irs reisted to the use components monitored for this indmetor of procedures (meludes the number of closed irs couesd by procedural noncompience), and the number of closed procedural Accident Monitoring instrumentetson, Aumliery (and noncomptance irs. The inckstor trends personnel performance Emergency) Feedwater System, Combustible Gas Control, for SEP #15,41 and 44 Component Coohng Water System, Containment and Cortenmort leoishon, Containment Cooient Systems, Control PROGRESS OF CYCLE 14 OUTAGE MODIFICATION Room Emergency Ventilshon System, Emergency Core PLANNING (FROZEN SCOPE OF 15 MODIFICATIONS)

Coolrig Sm Engineered Saisty Features instrumentebon, Essental Compressed Air Systems, Essental or Emergency e

This indcator shows the status of modifestens approved for Service Water, Fire Detecten or Suppreseen Systems, complehon dunng the Refuehng Outoge.

Isolabon Condeneer, Low Temperature Overpressure Protechon, Main Steam Line isolshon Velves, Onsite i

e PROGRESS OF 1996 ON-LINE MODIFICATION PLANNING Emergency AC & DC Power w/ Distribution, Redehon j

(FROZEN SCOPE OF 12 MODIFICATIONS)

Montormg instrumentshon, Reactor Cocient System, Reactor Core leoinhon Cooling System. Reactor Tnp System and This indcator shows the status of modifcotens approved for instrumentshon, Recirculebon Pump Trip Actuaten completon dunng 1995.

Instrumentaten, Residual Heat Removat Systems, Safety Velves, Spent Fuel Systems, Standby Liquid Control System and Uthmete Host Sink.

79 i

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PERFORMANCE INDICATOR DEFINITIONS SECONDARY SYSTEM CHEMISTRY PERFORMANCE STAFFING LEVEL I

INDEK The octual staffing level and the authortrod staffmg invol for the

.I The Chemory erformenos index (CPI) is a e=Mahan bened on Nuclear Opershons DMeson, The Produchon Engmeonng p

the concentrabon of key impunhos in the secondary side of the Dunen, and me Nucieer Sernces Deveen This indicator tracks 6

plant. These issy impurthes are the most Ilhely cause of performance for SEP #24.

E desertorston of the steem generators. Creerte for ceiculehng the CPI are:

STATION liET GENERATION

1) The plant is at greater then 30 percent power; and The not genersten (sum) produced by the FCS during the l

reportmg month.

2) the power is changmg less then 5% per day.

TEMPORARY MODIFICATIONS t

The CPI is calculated using the fotowing equehon.

l The number of temporary mechancel and electrical

[

CPI = (sociumm.90) + (Chionde/1.70) + (Sulfale/1.90) +

configurohons to the plants systems (iron /4AO) + (Copper /0 30)/5.

1) Temporary configuratens are defmed as electrealjumpers, Where: Sodium, sulfate and chkmde are the monthly everage electrical blocks, machenical jumpers, or machencal blocks i

blowdown concentrahons in ppb, iron and copper are monthly whch are instaged in the plant operating systems and are not l

time weighted average feedwater concentrebans in ppb. The shown on the istost reveen of the P&lD, schemehc, denominator for each of the five factors is the INPO meden connochon, wmng. or flow diagrams value. If the mordNy enrage for a specife parameter is less then the INPO meden value, the medan value is used in the

2) Jumpers and blocks which are instened for Sunminence calcunsten.

Tests, Maintenance Procedures, Cahbrahon Procedures, j

Special Procedures or Operahng Procedures are not i

SiONIFICANT EVENTS conodored as temporary modificehons unises the jumper or block ramens m piece stor he test or procedure is complete l

Segnilkant events are the events identtfled by NRC staff through Jumpers and blocks instound in test or lab instruments are deteeled screenng and ev=b=han of operstmg eigenence. The not considered as temporary modificatens i

l screenmg process includes the daily review and hdan of eH reported operstmg reactor events, as well as other opershonal

3) Scoffold is not concedered a temporary modificehon data such as epocalloots or constructen actMhes An event Jumpers and blocks which are insteNed and for which MRs identifed from the screenng process as a significant event have been submitted wil be considered as temporary

(

condedste is further evolusted to determme if any actual or modrflcehons unts final resoluhon of the MR and the jumper j

polonim threat to the hoseh and esfoty of the pubic was invched or block is removed or is permanently recorded on the i

Specife examples of the type of critene are summenzod as drowngs This indcator tracks temporary modifications for follows:

SEP 862 and 71.

j

1) Degradaten of important safety equipment, THERMAL PERFORMANCE

2) Unexpected plant response to a transent.

The ruto of he desqpi groes host rate (corrected) to the adjustad actusi groes heet rate, expressed as a percentage

3) Degradaten of fuel integnty, pnmary cooient pressure boundary, important sesocated features; UNIT CAPABILITY FACTOR

4) Scramwitncomplicaten; The ratio of the evellable energy genersten over a yven time penod to the reference energy generation (the energy that could

5) Unplanned reisese of redcoctMty;

% produced if the unit were operated contmuously at full power

.z Ar reference embent condihons) over the same time period,

6) Opersten outside the hm#s of the Techncal Specifcatens; expressed as a percentage

7) Other.

UNIT CAPACITY FACTOR INPO significant events reported in the indcator are SERs The not electrical energy generated (MWH) dMded by the (S6grufcont Event Reports) which inform utgitos of signifcant product of medmum dependable capocay (not MWe) times the events and lessons learned idenhfied through the SEE-IN groeshours in the reportmg period expressed as a percent. Not screening process electrical energy generated is the gross electncel output of the unit measured at the output terminals of the turtune generator SPARE PARTS INVENTORY VALUE rnmus the normat etshon service loeds during the groes hours of the reporting penod, expressed in megewett hours.

The doller value of the spare parts inventory for FCS during the reportng penod.

80 m..

i PERFORMANCE INDICATOR DEFINITIONS UNPLANNED AUTOMATIC MEACTOR SCRABAS PER T,000 UNPUWSdED SAFETY SYSTEM ACTIONS.980C CRmCAL HOURS DEFINmON) j TNs indicator is esened as the number of unplanned automate Tiai number of safety system actuohone whch inckale (GDb) the seems (reeckar protecten system logic actuohone) that occur por High Pressure Soloty injechen System, the Law Pressure Safety 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of crit 6cel operation tr$ection Syalam, the Selely Irischon Tanks, and the Emergency i

Diesel Generators The NRC closelficehon of selety eyetem The value for this indmetor is r*mirad by mulhplying the total actuohonsindudes actuonons when mejor equipment is operated number of unplanned automehc reactor acroms in a specshc tone gIgl when the logic systems for the above oefety systems are -

]

period by 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, then devkhng that number by the total chenenged number of hours crtkal in the same tone period. The indmetor is further denned as fotows:

VIOLATION TREle -

i t) Unplanned meanstrad the scram was not en ontmipated part TNsindcolor is defined as Fort Calhoun Station CNed Vrmns i

of a planned test.

and Non-Clied Vicistens trended over 12 months Addihonelly, I

Caed Violabons for the top quartte Regen IV plant is trended mer i

2) Scram means the automehc shutdown of the reactor by a 12 months (legging the Fort Calhoun Station trend by 2-3

)

rapid insertion of negatrve reactivity (e g., by control rods, months). Itis the Fort Calhoun Station goel to be et or below the liquid kischon system, etc.) that is caused by actuohon of the cited vioinhon trend for the top quartile Region IV plant.

1 reactor p otechon system. The scram signal may have -

]

resuned from =% a set pomt or may have been VOLUME OF LOW LEVEL SOUD parurucTNE WASTE spurious.

This indcator is deRned as the volume of low-level solid redlooctsve weste actueHy sNpped for bunal. This indcolor also H

3) Automate means that the indtml signal that caused actuation shows the volume of low level radmechve weste which is in of the reactor protection system logc was provided from one temporary storage, the amount of redmectrue oil that has been of the sensor's monstoring plant paramelers and concNhons, shipped off-site for procesemg, and the volume of eclid dry rather tien tie menuel scram swRches or, menuel turbine inp redoecheweste which has been sNpped off elle for processing i

edches (or push bunons) provided in the mein control room.

Low-leved solid redmactive weste conents of dry active weste, i

sludges, resins, and steparator botoms generated as a result of j

4) Critcal means that during the steady-etste condihon of the nuclear power plant operadion and maintenance Dry radioactive reactor pnor to the screm, the effective mie hhan (k,,)

weetsincludes cortaminated rags, cimenmg motorials, deposable

,l r

was essentally aquelto one, proteceve cialNng, pleetc cor teners, and any other meterial to be z

cReposed of at a low-level radioective weste disposal elle, enoopt i

UNPLANNED CAPABIUTY LOSS FACTOR resin, sludge, or evaporator bc2 toms Low-level refers to as radmactive weste that is not spent fuel or a by-product of opent The rate of the unplanned energy losses during a given period of fuel proceoong This indcator tracks radiological work.

time, to the reference energy genershon (the energy that could be performance for SEP #54.

produced if the unit were operated conhnuously at full power under reference embent conditions) over the same bme period, expressed as a percentage UNPLANNED SAFETY SYSTEM ACTUATIONS (INPO DEFINITION)

This indcolor is deRned as the sum of the following safety system actuations:

1) The number of unplanned Emergency Core Coolmg System

)

(ECCS) ectuatens that result from reaching an ECCS actuation set point or from a spunous/ inadvertent ECCS signol.

2) The number of unplanned emergency AC power system actuatens that result from a loss of power to e oefeguards j

e bus. An unplanned eefety system actuation occurs when en

)

actuohon set point for a safety system is reached or when a opurious or Wiedvertent signal is generated (ECCS only), and

- mejor equipment in the system is actuated Unplanned means that the system actuaten was not part of a planned test or evolution. The ECCS actuatens to be counted are

- actuohone of the high pressure injection system, the low i

pressure trisction system, or the safety infection tanks.

]

81

.I J

' SAFETY ENHANCEMENT PROGRAM INDEX The purpose of the Safety Enhancement Program (SEP) Performance Indicators inder is t0 list i

performance indmetors related to SEP ltems with parameters that can be trended.

SEP Refemnce Number 15 East

.. Increase HPES and IR Accountability through use of Performance Indicators

' Procedural Noncompliance incidents (Maintenance).................................... 50 Clean Controlled Area Contaminatens11.000 Disintegratiors/ Minute Per Probe Area............ 5 Recordable injuryAliness Cases Frequency Rate........................................ 4 Preventable /Personnet Error LERs...............................

.6 SEP Refemnce Number 24

. Complete Staff Studies Staffing Level..............................

.................................43 SEP Refemnce Numbers 28. 26. & 27 Training Program for Managers and Supervisors implemented

. Evaluate and ;.. A-

^ Station Standards for Safe Work Practice Requirements

. 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)

......................................67 Overall Project Status (Cycle 16 Refueling Outage)....................................... 66 l

Progress of Cycle 16 Outage Modification Planning......................................

6g SEP Reference Number 33

. Develop On4.ine Maintenance and Modification Schedule Percent of Completed Scheduled Maintenance Actness (All Mamtenance Crafts)............... 51 L

SEP Reference Number 36 Reduce Corrective Non-Outage Backlog Maintenance Workload Backlogs (Corrective Non-Outage).................................. 46 SEP Refemnce Numbers 41 & 44

. Develop and " ;_; E xx:' a Preventive Maintenance Schedule

. Compliance With and Use of Procedures Ratio of Preventive to Total Maintenance & Preventive Maintenance items Overdue

............,.47 Procedural Noncompliance incidents (Maintenance)...................................... 50 SEP Reference Number 44

. Design a Procedures Control and Administrative Program Document Revew............................................................... 56 82

1 l

1 i

4 1

SEP Reference Number 52 Egga

)

. Estatdish Supervisory Accountability for Workers Radiological Practices Radioicgical Work Practices Program................................................. 55 SEP Reference Number 54

. Complete implementation of Radiological Enhancement Program i

Collective Radiation Exposure.......................................

............. 17 -

Volume of Low-Level Solid Radioactive Weste..................................... 38 Clean Controlled Area Disintegrations 11,000 Counts / Minute Per Probe Area.................. 5 Contaminated Radiation Controlled Ares............................................. 54 SEP Reference Number 58

. Revise Physical Security Training and Procedure Program Loggable/ Reportable incidents (Security)

....... 57 SEP Reference Numbers 60 & 61

. Improve Controls Over Surveillance Test Program

. Modify Computer Program to Correctly Schedule Surveillance Tests l

Number of Mosed Surveillance Tests resulting in Licensee Event Reports.

21 SEP Reference Number 62

. Establish interim System Engineers 1

Temporary Modifications........................................................, 58 j

Engineering Assatance Request (EAR) Breakdown............................

.... 60 Engineering Change Notice Status

.............. 61 Engineering Change Notices Open....................

.. 62 SEP Reference Number 68

. Assess Root Cause of Poor Operator Training and establish means to monitor Operator Training License Operator Requalification Training............................................

64 License Candidate Exams........................................................ 65 SEP Reference Number 71

= 1mprove Controls otar Temporary Modifications Temporary Modifications

.................................... 58

'0 4

83-

I REPORT DISTRIBUTION LIST R. L Andrews J. D. Keppler K. L Belek D. D. Kloock B. H. Biome L.T.Kusek C. E. Boughter M. P. Lazar C. J. Brunnert B. R. LMngston M. W. Butt D. L. Lovett C. A. Carlson

~ J. H. MacKinnon G. R. Cavanaugh J. W. Marcil i

J. W. Chase N. L. Marfice A. G. Christensen R. D. Martin O. J. Clayton T. J. Mcivor R. P. Clemens K. G. Melstad R. G. Conner K. A. Miller J. L. Connolley P. A. Mruz G. M. Cook Nuclear Licensing i

S. R. Cntes

& Industry Affairs D. W. Dale J. T. O'Connor D.C.Dietz W. W. Orr M. L. Ellis T. L Patterson H. J. Faulhaber R. T. Pearce M. T. Frans R. J. Phelps -

D. P. Galle W. J. Ponec S. K. Gambhir C. R. Rice J. K. Gasper A. W. Richard W. G. Gates D. G. Ried S. W. Gebers G. K. Samide L. V. Goldberg M. J. Sandhoefner D. J. Golden F. C. Scofield D. C. Gorence H. J. Sefick R. H. Guy J.W.Shannon A. L. Hale C. F. Simmons K. R. Henry E.L.Skaggs J. B. Herman J. L. Skiles T. L. Herman F. K. Smith K. C. Holthaus R. D. Spies L. P. Hopkins D. E. Spires C. K. Huang R. L. Sorenson T. W. Jamieson K. E. Steele R. L. Jaworski M. A.Tesar R. A.Johansen J. J. Tesarek J. W. Johnson J. W. Tills R. Jones D. R. Trausch W. C. Jones J. M. Waszak G. R. Williams S. J. Willrett 84 I

FORT CALHOUN STATION OPERATING CYCLES AND REFUELING OUTAGE DATES EVENT DATE RANGE PRODUCTION (MWH)

CUMULATIVE (MWH)

Cycle 1 09/26/73 - 02/08/75 3,299,639 3,299,639 1st Refueling 02/08/75 -05/11/75 Cycle 2 05/11/75 -10/01/76 3,853,322 7,152,961 2nd Refueling 10/01/76 -12/13/76 Cycle 3 12/13/76 - 09/30/77 2,805,927 9,958,888 3rd Refueling 09/30/77 -12/09/77 Cycle 4 12/09/77-10/13/78 3,026,832 12,985,720 4th Refueling 10/13/78-12/24/78 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 -12/03/82 3,561,866 24,330,034 7th Refueling 12/03/82 - 04/06/83 Cycle 8 04/06/83- 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 12th Refueling 02/17/90 - 05/29/90 Cycle 13 05/29/90 - 02/01/92 5,451,069 51,040,528 13th Refueling 02/01/92 - 05/03/92 Cycle 14 05/03/92- 09/25/93 4,981,485 56,022,013 14th Refueling 09/25/93 -11/26/93 Cycle 15 11/26/93- 02/20/95 5,043,887 61,065,900 15th Refueling 02/20/95- 04/14/95 Cycie 16 04/14/95- 09/21/96 16th Refueling 09/21/96 -11/02/96 (Planned Dates)

FORT CALHOUN STATION CURRENT PRODUCTION AND OPERATIONS " RECORDS" First Sustained Reacton August 5,1973 (5.47 p m.)

First Electncity Supplied to the System August 25,1973 Commercial Operabon (180,000 KWH)

September 26,1973 Achieved Full Power (100%)

May 4,1974 Longest Run (477 Days)

June 8,1987-Sept. 27,1988 Highest Monthly Net Generaton (364,468.800 KWH)

October 1987 Most Productve Fuel Cycle (5,451,069 MWH - Cycle 13)

May 29,1990-Feb.1,1992 Shortest Refueling Outage (52 days)

Feb 20,1995-Aptd 14,1995 Highest Calendar Year Generston (4,118,368.7 MWH) 1994