ML20084B431

Performance Indicators Apr 1995

ML20084B431
Person / Time
Site:	Fort Calhoun
Issue date:	04/30/1995
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20084B421	List: LIC-95-0113, Forwards Fort Calhoun Station Performance Indicators Apr 1995 ML20084B431
References
NUDOCS 9505310234
Download: ML20084B431 (99)

Text

4 FORT CALHOUN STATION PERFORMANCE INDICATORS em merdllidBam T W, Y.

APRIL 1995 SAFE OPERATIONS PERFORMANCE EXCELLENCE COST EFFECTIVENESS 78R5A8 SEA 3E885!ss R

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

Production Engineering Division System Engineering Test and Performance Group APRIL 1995

4 FORT CALHOUN STATION

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APRIL 1995 MONTHLY OPERATING REPORT OPERATIONS

SUMMARY

The Fort Calhoun Station (FCS) 1995 Refueling Outage was completed during the month of April. The plant performed the cold hydrostatic (hydro) pressure test on April 4,1995, and then continued with plant heatup and pressurization. The Reactor Coolant System (RCS) hot hydro was completed satisfactorily on April Sth, after a return to cold shutdown to repair a leak on HCV-151, one of the two Power Operated Relief Valves (PORV) block valves. Low Power Physics Testing was completed by April 13th and the generator was synchronized to the grid on Friday, April 14,1995, ending the 53-day refueling outage.

On April 21,1995, power ascension to a nominal 100% level was completed. Power was reduced to 95% on April 28th to complete Moderator Temperature Coefficient (MTC) testing, with power returning to 100% on May 1.

Work was completed on the modification to the Control Room air conditioners to address the design basis Component Cooling Water (CCW) temperature issue.

Inspection No. 95-04, the NRC Resident Monthly Inspection, was completed during this reporting period. Licensee Event Report (LER)95-001, " Time Delay Relays for Offsite Power Low Signal Found Out-of-Tolerance" was submitted during this reporting period.

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NRC PERFORMANCE INDICATORS l

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FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT APRIL 1995 -

SUMMARY

POSITIVE TREND REPORT ADVERSE TREND REPORT A performance indicator with data representing three A Performance Indicator with data representing 3 con-consecutive months of improving performance or three secutive months of declining performance; or four or consecutive months of performance that is superior to more consecutive months of performance that is trending the stated goalis exhibiting a positive trend per Nuclear towards declining as determined by the Manager - Sta-Operations Division Quality Procedure 37 (NOD-OP-37). tion Engineering, constitutes an adverse trend per NOD-OP 37. A supervisor whose performance indicator ex-The following performance indicators exhbited positive hibits an adverse trend by this definition may specify in trends for the reporting month:

written form (to be published in this report) why the trend is not adverse.

Hioh Pressure Safety Iniection System Safety System Performance The following performance indicator exhibited an ad-(Page 8) verse trend for the reporting month:

Emeroency Diesef Generator Unit Reliabihtv Industrial Safety Accident Rate (Page 11)

(Page 2)

Dal Generator Reliabihty (25 Demands)

(Page 12)

End of Adverse Trend Report.

Emeroenev Diesel Generator Unreliability (Page 13)

INDICATORS NEEDING INCREASED Number of Missed Surveillance Tests Resultino in Lic-MANAGEMENT ATTENTION REPORT ensee Event Reoorts (Page 20)

A performance indicator with data for the reporting period that is inadequate when compared to the OPPD goal is Forced Outaae Rate defined as *Needing increased Management Attention" (Page 23) per NOD-OP-37.

Unolanned Auto Scrams oer 7.000 Hours Cticial The following performance indicators are cited as need-(Page 28) ing increased management attention for the reporting Ur'olanned Safety System Actuations (INPO Definition)

(Page 29)

Disablino Iniurv/ Illness Frecuenev Rate (Lost-Time Acci-dent Rate Primarv System Chemistrv Percent of Hours out of Limit (Page 3)

(Page 38)

Secondary System Chemistry

1. 9*

(Page 39) j

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Cents Per Kilowatt Hour

1. 9' (Page 41 )

Temocrary Modifications in-Line Chemistrv Instruments Out-of-Service (Page 57)

(Page 51)

1. "*9*

P Hazardous Waste Produced (Page 52)

Contaminated Radiation Controlled Area (Page 53)

Ooen CARS and IRS

{Page 65)

End of Positive Trend Report.

l i

V

FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT APRIL 1995 -

SUMMARY

PERFORMANCE INDICATOR REPORT IMPROVEMENTS / CHANGES This section lists significant changes made to the report and to specific indicators within the report since the pre-vious month.

There are no improvements / changes to report for the month of April 1995.

End of Report improvements / Changes Report i

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I vi

.... -)

Table of Contents / Summary Enns GOALS......................................................................... x SAFE OPERATIONS Industrial Safety Accident Rate - INPO.................................................. 2 Disabling injury / Illness Cases Frequency Rate

................................................................. 3 Recordable injury / Illness Cases Frequency Rate.......................................... 4 Clean Controlled Area Contaminations.

>1,000 Disintegrations / Minute per Probe Area

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

................ 6 Safety System Failures

.......................... 7 Safety System Performance:

High Pressure Safety lnjection System...................................... 8 Auxiliary Feedwater System..................................................

9 Eme rg ency AC Power System............................................... 10 Emergency Diesel Generator Unit Reliability

............. 11 Reliability (25 Demands)

......... 12 Unreliability......

..............13 Fuel R elia bility lndicator..........................................

...............14 Control Room Equipment Deficiencies........

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

...........................16 Maximum individual Radiation Exposure.....

..........17 Violation Trend...............

........................................18 Significant Events

. 19 Number of Missed Surveillance Tests Resulting in LERs

........................20 i

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Table of Contents / Summary PERFORMANCE East Station Net G eneration............................................

.............. 22 Forced Outage Rate......

......................23 Unit Capacity Factor...........

.......................24 Equivalent Availability Factor

.........25 1

Unit Capability Factor

...................................................... 26 Unplanned Capability Loss Factor.......................................

27 i

1 Unplanned Automatic Reactor Scrams per 7,000 Hours critical................................................ 28 Unplanned Safety System Actuations INPO Definition

......................29 NRC Definition

...............................30 G ross H eat Rate...........................

......... 31 Thermal Performance...........

......................................... 32 Daily Th e rm al O utput........................................................ 33 Equipment Forced Outages per i,000 Critical Hours

........................ 34 Component Failure Analysis Report (CFAR) Summary 35 Repeat Failures

............................................................ 36 Volume of Low-Level Solid Radioactive Waste...

37 Primary System Chemistry Percent of Hours Out of Limit 38 Secondary System Chemistry.

.... 39 COST Cents Per Kilowatt Hour......................

..... 41 Staffing Level

. 42 Spare Parts inventory Value

.... 43 viii f

l i

Table of Contents / Summary

,v DIVISION AND DEPARTMENT PERFORMANCEINDICATORS Ege Maintenance Workload Backlogs (Corrective Non-Outage

..............................45 Ratio of Preventive to Total Maintenance & Preventive Maintenance items Overdue........ 46 Percentage of Total MWOs Completed per month identified as Rework................ 47 Overtime

..............................................48 Procedural Noncompliance incidents....

..........................49 Percent of Completed Scheduled Maintenance Activities

......... 50 t

in-Line Chemistry Instruments Out-of-Service

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

52 Contaminated Radiation Controlled Area...

53 Radiological Work Practices Program

....... 54 Document Review

..... 55 Loggable/ Reportable incidents (Security)................................

.. 56 Modifications Temporary............

57 Outstanding..

.........58 Engineenng Assistance Request (EAR) Breakdown

....................59 Engineering Change Notices Status

........60 Open.......

..... 61 Licensee Event Report (LER) Root Cause Breakdown..............

. 62 Licensed Operator Requalification Training

......63 License Candidate Exams.

............. 64 Open Corrective Action Reports and lncident Reports.......

..... 65 Cycle 16 Refueling Outage MWO Planning Status

..... 66 Outage Modification Planning

. 67 Progress of 1994 On-Line Modification Planning 68 ACTION PLANS. DEFINiilONS. SEP INDEX & DISTRIBUTION LIST Action Plans.

... 70 Performance indicator Definitions

......... 73 l

Safety Enhancement Program index 81 Report Distribution List

. 83 ix

OPPD NUCLEAR ORGANIZATION GOALS Vice President - 1995 Priorities MISSION

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The safe, reliable and cost effective generation of electricity for OPPD cusiomers 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:

No challenges to a nuclear safety system.

OBJECTIVE 1-2:

Conduct activities in accordance with applicable policies, technical specifications, procedures, standing 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.

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.

OPPD NUCLEAR ORGANIZATION GOALS Vice President - 1995 Priorities Goal 2_: PERFORMANCE Supports: April 1994 Corporate Strategic Plan Goal 3, Obj: 2 and Goal 4, Obj: 1 Achieve high standards of performance at Fort Calhoun Station resulting in safe, reliable and cost effective power production.

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.

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Identify Programmatic performance problems through effective self assessment.

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Objectives to support PERFORMANCE:

1 OBJECTIVE 2-1:

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

OBJECTIVE 2-2:

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

OBJECTIVE 2-3:

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

OBJECTIVE 2-4:

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

OBJECTIVE 2-5:

Team //ndividua/ ownership, accountability, performance and teamwork is evident by improved phnt reliability; improved ratings 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 completion of department goals & objectives and other specific measures.

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OPPD NUCLEAR ORGANIZATION GOALS Vice President - 1995 Priorities Goal 3: COSTS 1

Supports: April 1994 Corporate Strategic Plan Goal 2, Obj: 1,2 and 3 and Goal 6, Obj: 1 Operate Fort Calhoun Station 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.

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.

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Goals Source: Scofield (Manager) l

SAFE OPERATIONS Goal:.A proactive, self-critical and safety conscious culture i

is exhibited throughout the nuclear organization. Individu-als demonstrate professionalism through self-ownership and personal initiative and open communication.

0 1

1

""*-" Year to-Date FCS Industrial Safety Accident Rate (INPO Definition)

+ FCS Average Rate (Last 12 Months)

'-*** FC S Year-End Goal (<0.50) lGOODI

--85-" Industry Upper 10% (Data thru 6/94) p

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+ 1995 INPO Industry Goal (<0.50) 1.2 -

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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) Performance Indicators and Other Indicators for Use at U.S. Nuclear Power Plant': 'The purpose of 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 1.14 at the end of April 1995. The value for the 12 months from May 1,1994, through April 30,1995, was 0.67.

There was one lost-time accident and no restricted-time accidents in April 1995. There was one disabling injury / illness reported for the month. This disabling injury occurred as the result of when an employee attempted to plug in an instrument received an electrical shock and a cut on the hand. There has been no restricted and three 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 50.50.

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

Data Source:

Sorensen/Skaggs (Manager / Source)

Chase / Booth (Manager / Source)

Accountability:

Chase / Conner Adverse Trend 2

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+ 1995 Disabling injuryAliness Frequency

+ 1994 Disabling injury / Illness Frequency l"!

2-

+ Average Rate (Last 12 Months)

+ Fort Calhoun Goal y.

1.6 -

1.4 -

1.2 -

1-A 3

0.4 J 0.2 -

0-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 1.51 at the end of April 1995.

There was one disabling injury / illness reported for the month. This disabling injury re-sulted from a pulled muscle in the right shoulder. There have been four disabling injuries in 1995.

The disabling injury / illness frequency rate for the 12 months from April 1,1994, through April 30,1995, was 0.8.

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

Data Source:

Sorensen/Skaggs (Manager / Source)

Accountability:

Chase / Conner Adverse Trend:

None 3

2.5 -

-*-- 1995 Recordable injurynliness Frequency

-M-- 1994 Recordableinjuryllliness Frequency 2.25 -

-*- Average Rate (Last 12 Months)

GOOD

+ Fort Calhoun Goal l

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y 1.5 -

1.25 -

1 d

O.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 re-cordable 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 socordable injury illness cases frequency rate is computed on a year-to-date basis.

There have been four recordable injury / illness cases in 1995. The recordable injury /

illness cases frequency rate year to date was 1.51 at the end of April 1995. There was one recordable injury / illness case reported for the month of April when an employee attempted to plug in an instrument received an electrical shock and a cut on the hand.

The recordable injury / illness cases frequency rate for the 12 months from May 1,1994, through April 30,1995, was 1.46.

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 Adverse Trend:

None SEP 15, 25, 26 & 27 4

i I

60 -

Contamination Events (YTD) 55 -

50 -

lGoool 45 -

40 -

35 -

3I 30 -

25 -

20 -

15 -

10 -

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0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1995 CLEAN CONTROLLED AREA CONTAMINATIONS >1,000 DISINTEGRATIONS /

MINUTE PER PROBE AREA This indicator shows the Personnel Contamination Events in the Clean Controlled Area for contaminations >1,000 disintegrations /minuto per probe area for the reporting month.

There were 3 contamination events in April 1995. There has been a total of 31 con-tamination events in 1995 through the end of April. There have been 37 events as of May 10,1995.

Data Source:

Chase /Little (Manager / Source)

Accountability:

Chase /Lovett Adverse Trend:

None SEP 15 & 54 5

w Personnel Errors (Each Month)

-E-Preventable (18-Month Totals)

C Personnel Error (18-Month Totals) 16 _

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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 tetals for Personnel Error LERs and the Personnel Error totals for esch month. The LERs are trended based on the LER event data as opposed to the LER report date.

In March 1995, there was one event which was subsequently reported as an LER. No LERs were categorized as Preventable or as a Personnel Error.

The total preventable / personnel error LERs for the year 1995 (through March 31,1995) is one. The total Personnel Error LERs for the year 1995 is zero. The total Prevent-able LERs for the year is zero.

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

Data Source:

Trausch/Cavanaugh (Manager / Source)

Accountability:

Chase Adverse Trend:

None SEP 15 6

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3-

- Industry Average Trend

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k 91 2 91-3 91-4 92-1 92-2 92-3 92-4 93-1 93-2 93-3 93-4 94-1 Year-Ouarter 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.

1 The following NRC safety system failures occurred between the first quarter of 1993 and the first quarter of 1994:

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 certain operating conditions.

Second Quarter 1993: A section of the piping configuration for the borated water source of the safety injection system was not seismically qualified. This could have i

resulted in a failure of the system to meet design requirements during a seismic event.

i Founh 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 expan-sion caused by a loop seal, inappropriate 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 I

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 recirc 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 4

loss of safety injection and spray flow, due to premature actuation of recirculation flow.

Data Source: Nuclear Regulatory Commission j

Accountability: Chase Adverse Trend: None 7

--+-- 1995 Monthly High Pressure safety lejection system Unavailability Value

-M-- 1995 Year-to-Date High Pressure safety injection System Unavailability Value

+ 1995 Fort Calhoun Goal (0.004)

+ 1995 INPo industry Goal (0.02)

O Industry Upper 10% (0.0011) 0.03 '

l Good l O.025 -

p 0.02 --

1 1

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A A

A A

A 0.015 -

0.01 -

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C C

C C

C C

C C

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Jan Feb Mar Apr May Jun Jul Aug sep oct Nov Dec 1995 Unavanabmty vmue 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 reporting month.

The High Pressure Safety System unavailability value for the month of April 1995 was 0.0. There were no hours of planned unavailability for surveillance tests, and no hours of unplanned unavailability, during the month. The 1995 year-to-date HPSI unavavailability vrlue was 0.0002 at the end of the month. The unavailability value for the last 12 months was 0.0026.

There has been a total of 1.03 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-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 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 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 approximate 1y 0.001.

Data Source:

Jaworski/Schaffer Accountability:

Jaworski/Schaffer Positive Trend 8

i C" 3 Monthly Auxiliary Feedwater System Unavailability

-M-- Year-toaste Ernergency AC Power Unavailability l

l

-*- Fort calhoun Goal (0.01)

-*- 1995 INPO Industry Goal (0.025)

Y

--G-Industry Upper 10% (0.00211 0.03 -

(

0.025 -

0.02 --

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0.015 -

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0 0

0 0

0 0

0 0

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j 0.005 -

N C

S C

C C

C 0

3 1994 0

Unavailability Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec Value 1995 1

AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE l

This indicator shows the Auxiliary Feedwater System Unavailability value, as defined by j

INPO in the Safety System Performance Indicator Definitions, for the reporting month.

The Auxiliary Feedwater System Unavailability Value for April 1995 was 0.0298. There i

were 25.98 hours0.00113 days <br />0.0272 hours <br />1.62037e-4 weeks <br />3.7289e-5 months <br /> of planned and no hours of unplanned unavailability during the month.

i The year-to-date unavailability value was 0.0084 and the value for the last 12 months was 0.0056 at the end of the month.

j' 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-

!e planned unavailability for the auxiliary feedwater system in 1995.

J The 1995 Fort Calhoun year-end goal for this indicator is a maximum value of 0.01.

4 The 1995 INPO industry goal is 0.025 and the industry upper ten percentile value is ap-proximately 0.002.

i l

Data Source:

Jaworski/Nay Accountability:

Jaworski/Nay Adverse Trend:

None 9

C""El Monthly Emergency AC Power Unavailability Value

+ Year-to-Date Emergency AC Power Unavailability Value 0.06 -

+ Fort Calhoun Goal (0.024)

-e-1995 INPO industry Goal (0.025)

V 0.05 -

-G-- Industry Upper 10% (0.0035)

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i

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0.04 "

0.03 -

3 3

3 3

3 3

3 3

3 3

3 3

0.02 -

0.01 -

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C C

C C

C C

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1995 EMERGENCY AC POWER SYSTEM SAFETY SYSTEM PERFORMANCE 3

This indicator shows the Emergency AC hwer 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 April 1995 was 0.0022. During the month, there were 3.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of planned unavailability for testing, and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned unavailability. The Emergency AC Power System unavailability value year-to-date was 0.0028 and the value for the last 12 months was 0.008 at the end of the month.

There has been a total of 15.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> of planned unavailat'ility 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-proximately 0.0035.

r Data Source:

Jaworski/Ronning Accountability:

Jaworski/Ronning Positive Trend based on Performance better than Goal 10 l

Failures /20 Demands Failures /50 Demands GOOD M Failures /100 Demands

-#-Trigger Values /20 Der.unds f

-*-Trigger Values /50 Demands

-*-Trigger Values-100 Domands g-7-

6" S-o a

a a

a a

a a

a a

4

.A 4-3-

2 2--

1 1

1 1

1 1

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

0 0

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

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 ;oaded with at lea! t 50% of design load (see exceptions and other demand criteria in the Definition Sectici of this report).

Data Source:

Jaworski/Ronning t, Manager / Source)

Accountability:

Jaworski/Ronning Positive Trend 11

O DG-1 Failures /25 Demands EEEl DG-2 Failures /25 Demands l coop l 5

+ Failure Trigger Value for 25 Demands / Fort Calhoun Goal f

4-C 0

0 0

0 0

0 0

0 0

0 3

3-2-

1 1

1 1

1 3

0 0 0 0 0 0 0 0 0 0 00 0 0 0

0 0

0 0

0 May Jun Jul Aug Sep Oct Nov Dec Jan Fet>

Mar Apr 1994 1995 DIESEL GENERATOR RELIABILITY (25 DEMANDS)

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

it must be emphasized that, in accordance with NUMARC criteria, certain actions will take place in the event that any one emergency diesel generator experiences 4 or more fail-ures within the last 25 demands on the unit. These actions are described in the Defini-tions Section of this report. A System Engineering Instruction has been approved for the Fort Calhoun Station to institutionalize and formally approve / adopt the required NUMARC actions.

Diesel Generator DG-1 has experienced one failure during the last 25 demands on the unit. On December 8,1994, DG-1 failed its monthly surveillance test because sl the inlet air damper would not open. The cause of the failure was found to be ice buildup on the damper louvers from a previous snowstorm.

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

Data Source:

Jaworski/Ronning (Manager / Source)

Accountability:

Jaworski/Ronning Positive Trend due to performance better than goal 12

M DG 1 Unreliability Value IIIHERI DG.2 Unreliability Value l GOOD l

M Station Unreliability Value M Industry Upper 10% (0.002 for a 3 Year Average) r 0.08 -

-e-1995 Goal 0.07 -

0.06 --

0.05 0.05 -

C

=

=

3 0.04 -

9.03 -

0.02 -

00 00 00 00 00 00 00 0

00 00 00 00 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 1994 1995 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 April 1995 was 0.0. The 1995 goal for this indicator is a maximum value of 0.05.

For DG-1:

There were 3 start demands for the reporting month without a failure.

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

For DG-2:

There were 3 start demands for the reporting month without a failure.

!n 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 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 1

n.

Fuel Reliminlity l

l

-*-- 1995 INPO Industry Fuel Defect Reference (5 x 10-4 Microcuries/ Gram) i 1995 Goal Y

,l g..

$l 15 --

h cycle ts

,E a

v 4

W

+

15 C

[

f n

0"I'O' l 10 --

gy ji y

{?

g N

f

?

4 i

a g

g g

q t

i5-c

@W M

M

'g W

m May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar.

Apr -

l 1994 1995

[

FUEL RELIABILITY INDICATOR The FUEL RELIABILITY INDICATOR (FRI) for April 1995 was 0.9556 X 10-4 microcuries/ gram.

The purpose of the FRI is to monitor industry progress in achieving and maintaining a high level of fuel integrity. The April FRI value, is less than the zero defect threshold value, however this does not necessarily confirm a defect free core, as discussed below, i

Cycle 16 plant operation started on April 13 and attained 100% power on April 23. The plant f

operated above 95% from April 20 through the 22, at 100% power from April 23 through the 28th, j

and at 95% April 29th and 30th. The April FRI was calculated based on fission product activities present in the reactor coolant during steady state full power operation, April 23 through 30. The Xenon activity has shown a gradualincrase, without iodine spiking. However, based on the results from last cycle it is strongly suspected that the core contains one or more failed fuel pins.

The April FRI value of 0.9556 X 10-4 microcures/ gram is very similar to the initial chemistry data l

taken during the first month of operation following the 1993 refueling outage. The April FRI of O.9556 X 10-4 microcuries/ gram FRI value is far below the 1995 operational goal. The value may show small monthly changes due to chemistry variability.

The INPO September 1992 report, " Performance 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 10-4 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 sophisticated analysis by utility reactor engineers." The value of 5.0 x 10-4 microcuries/ gram is defined as a " Fuel Defect Reference" number of a "Zero Leaker Threshold." Each utility will evaluate whether the core is defect free cr not. The 1995 Fort Calhoun Station FRI Performance Indicator goal is to maintain a monthly FRI below 5.0 x 10-4 microcuries/

i gram.

Data Source:

Holthaus/ Weber Accountability:

Chase /Spijker Adverse Trend:

None 14

O Control Room Deficiences Repairable On-Line l GOOD l C Total Number of Control Room Deficiencies 80 -

-O-FCs Goal for Total Control Room Deficiencies (CRD's) (45) 70 -

60 -

F F

50 -

c 3_

30 -

20 -

10 -

{ j

~

p 0

May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 1994 1995 C Operator Work Aro::nd CRD's Repairable On-Line l GOOD l C Total Number of Operator Work Around CRD's i

Y 12 -

+ FCS Goal for Total O_perator Work Around CRD's (51 10 -

8-C 0

0 0

0 0

3

^

4 2-0 May Jun Jul Aug sep Oct Nov Dec Jan Feb Mar Apr 1994 1995 NUMBER OF CONTROL ROOM EQUIPMENT DEFICIENCIES This indicator shows the number of Control Room Deficiencies that are repairable during plant operations (on-line), the number of outstanding Control Room Deficiencies, the number of Operator Work Around (OWA) CRD's repairable on-line, the number of outstanding Operator Work Around CRD's and the Fort Calhoun goals.

There was a total of 42 Control Room Deficiencies at the end of April 1995. 21 of these deficiencies are repairable on-line and 21 require a plant outage to repair.

There were 4 OWA CRD's identified at the end of the month on equipment tags: RC-3C and RC-3D On C/R Panel CB-1/2/3; FW-54 and MOV-D1 On C/R Panel CB-10/11. 3 OWA CRD's require an outage to repair.

The 1995 Fort Calhoun monthly goal for this indicator is a maximum of 45 CRD's and 5 OWA CRD's.

Data Source:

Chase / Tills (Manager / Source)

Accountability:

Chase /Faulhaber Adverse Trend:

None 15

M Monthly Personnel Radiation Exposure

+ Personnel Cumulative Radiation Exposure l GOOD l

+ FCS Goal (143.1 Person-Rem) y.

160 T 160 C 140-130 -

120 -

110 -

l 100 -

4 90 1 60 -

70 -

c. 60 -

50 -

40 30 -

0 --

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1995 COLLECTIVE RADIATION EXPOSURE The 1995 Fort Calhoun goal for collective radiation exposure is less than 143.1 person-Rem.

The exposure for April 1995 was 96.198 person-Rem (by ALNOR).

The year-to-date exposure through the end of April was 124.735*

person-Rem (TLD & ALNOR).

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 5/92 through 4/95 was 112.965 person-rem per year.

• Following reading of outage TLDs.

Data Source:

Chase /Little (Manager / Source)

Accountability:

Chase /Lovett Adverse Trend:

None SEP54 16

l O Highest Exposure (April) 5000 --

O Highest Exposure (1995) l OPPD 4500 mRemfyr. Limit 4000 '

3000 -

2000 -

1286 976 FCS Goal 1000-m.e

^ bh"3Q.

O Highest Highest Exposure Exposure (April)

(1995)

MAXIMUM INDIVIDUAL RADIATION EXPOSURE During April 1995, an individual accumulated 976 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 1,286 mrem. (875 mrem of this was received during orifice plate repairin a steam generator.) However, the OPPD 4500 Mrem /yr limit is not expected to be exceeded.

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

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

Data Source:

Chase /Little (Manager / Source)

Accountability:

Chase /Lovett Adverse Trend:

None 17

G:32g FCs Cited Molations (Monthly)

FCs Non. Cited Molations (Monthly) i i

l GOOD l c

FCs Cited Molations (12-Month Average) e-FCs Non-Cited Monations (12-Month herage)

_.m._

Region IV Cited Molations (12-Month Aerage for Region IV top quartile) 14,

. ~

8

- C a

j' j

e o

4-2--%

~

~

~

0 O

W Apr May Jun Jul Aug sep oct Nov Dec Jan Feb Mar 1994 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 will be illustrated monthly for the past 12 moriths. 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 March 1995:

JER No.

Title 95-04 Monthly Resident inspection To date, OPPD has received three violations for inspections conducted in 1995.

Level Ill Violations 0

Level IV Violations 1

Level V Violations 0

Non-Cited Violations 2

Total 3

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

Data Source:

Trausch/Cavanaugh (Manager / Source)

Accountacility:

Trausch Adverse Trend:

None 18

O NRC Significant Events IGOODI Industry Average Trend y

1 Nsiff o.5 -

0 i

i i

i i

i i

i i

i i

i 91-3 91-4 92-1 92-2 92-3 92-4 93-1 93-2 93-3 93-4 94-1 94 2 Year - Quarter E INPO Significant Events (SERs)

IGOODI V

2 2-3 3

3 3

3

,M,

,M,M,

,M,M, 91-3 91-4 92 1 92 2 92-3 92-4 93-1 93-2 93-3 93-4 94-1 94-2 Year - Quarter SIGNIFICANT EVENTS This indicator illustrates the number of NRC and INPO Significant Events for Fort Calhoun Station as reported by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data in the biannual " Performance Indicators for Operating Commercial Nuclear Power Reactors" report and INPO's Nuclear Network.

The following NBQ significant events occurred between the second quarter of 1991 and the First quarter of 1994:

Second Quarter 1991: Safety related electrical equipment was not adequately protected from a high energy line break.

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

The following INPO significant events, as reported in Significant Event Reports (SERs), oc.

curred between the fourth quarter of 1991 and the first quarter of 1994:

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

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

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

Second Quarter 1993: SBFU Breaker Relay (Switchyard) Plant Trip l

Fourth Quarter 1993: Unexpected CEA Withdrawal.

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

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

t

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

0 0

0 0

- - - ;O r-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 April 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 20 i

l l

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

1 i

4 21

50 -

3 Net Generation (10,000 Mw hours) 40 -

36.66 34.36 34.88 M.31 34,94 33,,,

h30 -

e 21.19 3

15.29 Cycle 15 Refueling 10 '

outage 0

1 I

I i

l i

I I

I I

1 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 1994 1995 STATION NET GENERATION During the mor.th of April 1995, a net total of 152,917 MWH was generated by the Fort Calhoun Station. Cumulative net generation for Cycle 16 was 152,917 MWH at the end of the month. Planned energy losses for the month were attributable to the 1995 refueling outage which began on February 20 and ended on April 14,1995.

f i

1 Data Source:

Station Generation Report Accountability:

Chase Adverse Trend:

None 22

I gg

-+- Forced Outage Rate

+ Fort Calhoun Goal (2.4%)

10% -

Y 8%-

6%-

Cycle is R*Aaling 4%-

outage 1JB e

O O

O O

O O

O O

,0%

92 93 94 May Jun Jul Aug Sep oct Nov Dec Jan Feb Mar Apr 1994 1995 FOP,CED OUTAGE RATE The forced outage rate (FOR) was reported as 0.0% for the twelve months from May 1, 1994, through April 30,1995. The 1995 year-to-date FOR was 0.0% at the end of the month.

The 1995 Fort Calhoun year-end goal for this indicator is a maximum value of 2.4%.

Data Source:

Monthly Operations Report Accountability:

Chase Positive Trend 23

Monthly Unit Capacity Factor

+ Unit Capacity Factor for Cycles 15 & 16 120.0 % -

-* 36-Month Average Unit capacity Factor

--M-" FCS Goal 100.0 % -

e 3

5 h

E b

b 80.0% -

60.0% -

40.0% -

cyde 15 20.0% -

Refueling Outage 0.0%

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

The Unit Capacity Factor for April 1995 was 44.49% due to the 1995 refueling outage, which was completed on April 14,1995.

At the end of the month, the Cycle 16 Unit Capacity factor was 44.49%, and the Unit Capacity Factor for the last 36 months was 81.03%.

The Unit Capacity Factor is computed as follows:

4 Net Electrial Energy Generated (MWH)

Maximum Dependable Capacity (Mwe) X Gross Hours in the Reporting Period Data Source:

Monthly Operating Report Accountability:

Chase Adverse Trend:

None 24

c'" 3 Monthly EAF j

-G-Year-to Date Average Monthly EAF

-*- 12-Month Average EAF l GOOD l

--M-Industry Median Value (76.7% for a 3-Year Avermoe)

$2 100 % - y_.g.

.g.

0 F'T

^

b M

N y

x 3

3 3

y y_

a0% -

x x

x x

x 60% -

~

40% -

Cycle is

~

Refuelirq outage 20% -

0%

E 8 "

May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 1994 1995 EQUIVALENT AVAILABILITY FACTOR This indicator shows the plant monthly Equivalent Availability Factor (EAF), the year-to-date average monthly EAF, and the year-end average monthly EAF for the previous three years.

The EAF for April 1995 was reported as 43.7% due to the refueling outage. The year-to-date monthly average EAF was 51.8% at the end of the month.

The Fort Calhoun average monthly EAF for the three years prior to this report was 80.3%.

The industry median EAF value for the three-year period from 7/90 through 6/93 was 76.7%.

Data Source:

Dietz/Parra (Manager / Source)

Accountability:

Chase Adverse Trend:

None 25 i

M Monthly Unit Capability Factor

-M-- Year-to-Date Unit Capability Factor

-+-- 36-Month Unit Capability Factor l Good l 1994 and 1995 Fort Calhoun Goals

""" 1994 and 1995 INPO Industry Goals (80%)

0%

I May Jun Jul Aug sep oct Nov Dec Jan Feb Mar Apr 1994 1995 UNIT CAPABILITY FACTOR 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 l

percentage (refueling periods excluded).

The UCF for April 1995 was reported as 42.5%. The year-to-date UCF was 42.4%, the UCF for the last 12 months was 80.7%, and the 36-month average UCF was reported as 81.6% at the end of the month.

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 79.65%.

Data Source:

Generation Totals Report & Monthly Operating Report Accountability:

Chase Adverse Trend:

None 26 l

l

40% --

C-I Monthly Unplanned Capability Loss Factor Year.To-Date Unplanned capability Loss Factor l Good l

-*-- 12-Month Average Unplanned capability Loss Factor 35% -

-M-Fort Calhoun Goal (3.97%)

y

-e-1995INPoindustry Goal (4.5%)

Y

-+- Indust _ry Current Best Quartile 30% -

r

~

25% -

A 20% -

15% -

l 10% -

r 5% ~

k 2 2

2 2

2 2

2.

2 2

2 2

=

a 2

0%

--I May Jun Jul Aug sep oct Nov Dec Jan Feb Mar Apr 1994 1995 UNPLANNED CAPABILITY LOSS FACTOR This indicator shows the plant monthly Unplanned Capability Loss Factor (UCLF), the l

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.

The UCLF for the month of April 1995 was reported as 0.0%. Unplanned energy loss is defined as the energy that was not produced during the period of unscheduled shut-downs, outage extensions, or load reductions due to causes under plant management control. Energy losses are considered to be unplanned if they are not scheduled at least four weeks in advance. The year-to-date UCLF was 17.09%, the UCLF for the last 12 months was 8.47%, and the 36-month average UCLF was reported as 7.31% at the end of the month.

The 1995 INPO industry goal is 4.5% and the industry current best quartile value is ap-proximately 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 i

Adverse Trend:

None l

\\

27 i

5-

""" FCs Reactor scrams Per 7,000 Hours Critcal Year to Date

-+-- FCS Reactor scrams Per 7,000 Hours critical for last 36 months 4-

+ 1995 & 1994 Fort Calhoun Goals (0.0)

-*- 1995 INPo Industry Goal C

Industry Upper 1084 (0.48 per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical over a 3C-month time period) 3 2;

O 0

0 0

0 0

0 0

0 0

1-A i

4 4

A A

a a

E

=

=

=

=

=

=

N a

0 0

0 0

0 0

0 0

May Jun Jul Aug sep Oct Nov Dec Jan Feb Mar Apr 1994 1995 3

4' E FCs Reactor scrams

~

3' 2

2-

-]:o1} 0 0

0 0

0 0

0 0

0 0

0 0

0 91 s2 83 94 May Jun Jul Aug sep oct Nov Dec Jan Feb Mar Apr 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 April 1995. The value for the 12 months from May 1,1994, through April 30,1995, was 0.0. The value for the last 36 months was 1.97.

The 1995 Fort Calhoun goal for this indicator is 0. The 1995 INPO industry goal is a rnaximum 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.

Data Source:

Monthly Operations Report & Plant Licensee Event Reports (LERs)

Accountability:

Chase Positive Trend 28

3-C""~3 Safety System Actuations (INPO Definition)

+ FcS Goal (0)

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

q.

0 0

0 0

0 0

0 0

0 0

0 0

0

o 22 93 M May Jun Jul Aug Sep oct Nov Dec Jan Feb Mar Apr 1994 1995 UNPLANNED SAFETY SYSTEM ACTUATIONS -(INPO DEFINITION)

There weis no INPO unplanned safety system actuations during the month of April 1995.

Thero was one INPO unplanned safety system actuation during the month of February 1994. It occurred on February 11,1994, when supervisory relay 86B/CPHSS failed, which resulted in tripping relay 86B/CPHS. The CPHS relay trip actuated the Safety injection Actuation Signal, Containment Isolation Actuation Signal, Ver.lilation 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.

Data Source:

Monthly Operations Report & Plant Licensee Event Reports (LERs)

Accountability:

Jaworski/Foley/Ronning Positive Trend 29

C Safety Systein Actuations (NRC Definition)

["""'3 1995 FcS Goal 12-Month Running Tctal SSAs (NRC Definition)

-+- critical Hours cyde is 10 Cyde 14

" "8 Outage ' 800 ng outase 700 s00 4

y i

2 2 3 200 o 100 "s

e'x i

a s

e a

,3 UNPLANNED SAFETY SYSTEM ACTUATIONS -(NRC DEFINITION)

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

There was one NRC unplanned Safety system actuation during the month of February 1994. It occurred on February 11 when supervisory relay 86B/CPHSS failed, which re-suited 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.

Data Source:

Monthly Operations Report & Plant Licensee Event Reports (LERs)

Accountability:

Jaworski/Foley/Ronning Adverse Trend:

None 30

O Monthly Gross Heat Rate qq..

--M-Year.toaste Gross Hed Rate l0000l

+ 1994 & 1995 Fort Calhoun Goals e

10.75 -

10.5 -

"~

3

~~

t22 10.25 -

a as ms g

$A

=

s

^

V s

10 -

LE Cycle 15

~

9.75 -

.0 w

4 Outage i.

9.5 E

E E

2 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 10,266 for the month of April 1995. The 1995 year-to-date GHR was 10,098 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 degrad:s 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 <10,167.

I i

Data Source:

Holthaus/Willett (Manager / Source)

Accountability:

Chase /Jaworski Adverse Trend:

None 31

C-'"'3 Monthly Thermal Performance C"~3 12-Month Average k

-M Year-to-Dete Average MonthlyThermal Performance l

1995 Fort Calhoun Goal (99.6%)

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

GOOD C Industry Upper 10% (99.9%)

100 % -

ll ll l"

ll ll l

'i 90% -

Cycle 15 Refueling 80% -

outage 70 % -

60% -

50%

40 %

May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 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 April 1995 is not available since 100% power was not achieved until very late in the month.

Initia1 results from testing to verify FW flow requirements indicate biased results from plant instruments is causing the thermal performance indicator to be under-reported. Correc-tions to the indicator will be made upon completion of the FW Flow Nozzle Fouling Study.

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/Gorence Accountability:

Jaworski/Gorence Adverse Trend:

None 32

f

+ Thermal Output

+ Fort Calhoun 1495 MW Goal

--*- Tech Spec 1500 MW Limit 1600-1400 -

l MTc 1200_

Test 1000 -

.c j 800 -

600-400 -

200 -

0 0 0-0 0:0 0 0 0:0:0:0 0-1 3

5 7

9 11 13 15 17 19 21 23 25 27 29 DAILY THERMAL OUTPUT The thermal output graph displays the daily operating power level during April 1995, the 1500 thermal megawat average technical specification limit, and the 1495 thermal mega-watt Fort Calhoun goal.

Data Source:

Holthaus/Willett (Manager / Source)

Accountability:

Chasefrills Adverse Trend:

None 33 i

l

+ Equipment Forced outage Rateli,000 Critical Hours for a 1244onth interval

+ 1994 & 1995 Fort Calhoun Year-End Goals (0.2) 0.8-0.6-0.4 -

0.11 0.2 E E

E E

E R

0

?

?

?

2 E

o p

g g

g May Jun Jul Aug sep oct Nov Dec Jan Feb Mar Apr 1994 1995 2

Number of Equipment Forced outages Per Month 1-0 May Jun Jul Aug Sep oct Nov Dec Jan Feb Mar Apr 199 199 EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS The equipment forced outage rate per 1,000 critical hours for the 12 months from May 1, 1994, through April 30,1995, was 0.13. The rate per 1,000 critical hours for the months from January through April 1995 was 0,60 An equipment forced outage occurred on February 20,1995, when the plant experienced a problem with a control ement assembly motor drive and a related small leak of reactor coolant.

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 34

1. o ent Ca% odes 40-35-

-+-- # of Application Categories 30-Total # of Categories 8

y 25-g 20-O g 15-10-A A

i 1

5-Y 0

N D J94 F M

A M

J J

A S

O N 094 J F

M A95 E WearOut/ Aging Q Other Devices

@ Manufacturing Defect O Maintenance / Action 48.6%

M-4.3%

O Engineering / Design

@ Error / Operating Action

^

4.3%

[

4.3%

)

Percent of Total Failures During p/

the Past 18 Months

g '-

p

/

7.1%

BA 11.4%N W COMPONENT FAILURE ANALYSIS REPORT (CFAR)

SUMMARY

The top chart illustrates the number of component categories, application categories and total categories in which the Fort Calhoun Station has significantly higher (1.645 standard deviations) failure rates than the industry failure rates during the past 18 months (from July 1993 through December 1994). Fort Calhoun Station reported a higher failure rate in 4 of the 87 component categories (valves, pumps, motors, etc.) during the past 18 months. The station reported a higher failure rate in 4 of the 173 application categories (main steam stop valves, auxiliary /

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

The pie chart depicts the breakdown by INPO cause categories (see the " Definitions" section of this report for descriptions of these categories) for the 83 failure reports that were submitted to INPO by Fort Calhoun Station during the past 18 months. Of these, the failure cause was known for 70. The pie chart reflects known failure causes.

4 Data Source: Jaworski/ Frank (Manager / Source)

Accountability: Jaworski/ Frank Adverse Trend: None 35

Components With More Than One Failure l GOOD l Y

25 -

-M--

Cornponents With More Than Two Failures 20 -

15-io-9W?

8 8

5-4 4N

~

1 1

1 1

1 1

.1 1

1

%o,

.o.

.o.

m m

m m

m 9

i i

i i

i i

i i

m i - i m

i May94 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr95 REPEAT FAILURES i

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

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

This indicator shows the number of NPRDS components with more than 1 failure during the eighteen month CFAR period and the number of NPRDS components with more than 2 failures during the eighteen month CFAR period.

During the last 18 reporting months there were 3 NPRDS components with more than 1 failure. None of these 43 had more than 2 failures. The tag numbers of the compo-nents with more than 1 failure are: AC-100, NT-001 and RC-374. Recommendations and actions to correct these repeat component failures are listed in the quarterly Com-ponent Failure Analysis Report.

Data Source: Jaworski/ Frank (Manager / Source)

Accountability: Chase Adverse Trend: None 36

C Radioactive Waste Buried This Month (in cublic feet)

^

=

0 0

1. ~

Cumulative Radioactive Waste Buried

+ 1995 Fort Calhoun GoaMM lo000l 800 -

i 700 -

600-500 -

C O

O O

O O

O E

~

j 300 -

{

100 -

0 l

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

GEEL Amount of solid radwaste shipped off site for processing during current month 2.080 Volumo 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.

t Data Source:

Chase /Breuer(Manager / Source) f Accountability:

Chase /Lovett Adverse Trend:

None SEP54 i

37

Primary System Chemistry Percent of Hours Out of Limit i

i GOOD 0

Fort Calhoun Goal (0.02)

IY 2% -- c 0

0 0

0 0

0 0

0 0

0 o

1% --

Cycle 16 Refueling outage IE 0%

l May Jun Jul Aug sep Oct Nov Dec Jan Feb Mar Apr 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 Limit was 0.0% for the month of April 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 38

I 1.6 --

0 12-Month Average GOOD l

-dr-Fort Calhoun Goal (1.4) 4 1.5--

1 1.4 --

t.

i o

e o

o o

o o

o o

o a s-1.3 --

1.2 -

4,

_M 1.1 --

1 l

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; snd 2) the power is changing at less than 5% per i

day.

The CPI for April 1995 was 1.24. The 12-month average CPI value was 1.05 at the end of the month.

l

(

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

Data Sr;urce:

Smith / Spires (Manager / Source)

(

Accountability:

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

39

~

COST Goal: Operate Fort Calhoun Station in a manner that cost effectively maintains nuclear generation as an economically viable contribution to OPPD's bottom line. Cost conscious-ness is exhibited at all levels of the organization.

4 40

i 4-

+ Actuals

+ Budget

+ Plan 3.75 -

3.5 -

i i

x 3.25 -

3-jy 2.75 -

2.5 -

2.25 -

2 g g

g g

g 2

E m'

O z

g g

g g

g Q

C Q

Q C

O O

O O

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 Decem'oer 31 amounts are also shown for the prior years 1992,1993 and 1994. In addition, the report 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 (2.95 cents per kilowatt hour for April 1995) averaged lower than budget due to generation exceeding the budget.

Data Source:

Scofield/Jamieson (Manager / Source)

Accountability:

Scofield Positive Trend 41

@ Nuclear Services Division Staffing O Production Engineering Division Staffing 2 Nuclear Operations Division Staffing C Total Nuclear Staffing 8

7 7

9 0

7 7

7 8

?

700-i 600-4 4

+

2 5

b 4 j 4

4 4

Q 4

4 f

5 5

4 4

3 3

500-5 400-

[

p 7

c 8

300-O h

9 :

9 9

8 200-1 l

1

[

1$

11 1

8,,,

8 8

8

+

3 l

q,5, 12 1

1 1

1 1

i 1

?

1

(

3 5

5 4

7 6

6 4

3

[

4 O

4 g

Jan91 Jan92 Jan93 Jan94 Apr94 Jul94 Oct94 Dec94 Mar 95 ACTUAL STAFFING LEVEL (UPDATED QUARTERLY)

STAFFING LEVEL 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 1825 1996 440 432 Nuclear Operations Division 181 175 Production Engr. Division 114 113 Nuclear Services Division Data Source: Ponec (Manager & Source)

Accountability: Ponec Adverse Trend: None SEP 24 42

i s

+ Spare Parts inventory Value ($ Million) 16.8 _.

16.6..

16.4 -

_!, 16.2 _,

2 Ti 16 -

g i$ 15.8..

s 15.6 +

6 15.4 --

15.2 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 1M 1995 Spare Parts inventory Value The spare parts inventory value at the Fort Calhoun Station at the end of April 1995 was reported as $15,689,841.

The drop in inventory this month reflects the continuing investment recovery efforts'to date.

s l

Data Source:

Steele/Huliska (Manager / Source)

Accountabilitv:

Willrett/McCormick Adverse Trend:

None 43

i l

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

O r

g

O Corrective Maintenance Q

Non-Corrective / Plant trnprovements O

Preventive Maintenance

--O--

Fort Calhoun Goal 800-752 720 N

693 M

gg 700-6_2,6 581

=

60 y

T P

565 7

600 -

g; m'

d

==

m$

==

U Q

1.

jf W

y n

500-

~

400-

'Q Q,

C

,Q.

,C Q

y,

~

/

/

2=-

/,.

/,

//

/,

/.

//

./,

. /,

//

//

/,

//.

100-

4.

'4 ff

';4

4 4'. g

'4 f4 g;

4 f4 0

MAY94 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr95 Non-Outage Maintenance Work Order Backlog O Total MWos 8 MWOs Which Exceed Maintenance Cornpletion Goals 500 -

400-209 300-

>9

>3 d"Y" 149

>180 200-82 days 58 days

~f. ff,j-

{'f/

. days 1'

l

~

O ps Priority 1 Priority 2 Priorrty 3 Priority 4 Priority 5 Priority 6 Non-Outage Maintenance Work Order Aging MAINTENANCE WORKLOAD BACKLOGS This indicator shows the backlog of non-outage Maintenance Work Orders remaining open at the end of the reporting month. It also includes a breakdown by maintenance classification and priority. The 1995 goal for this indicator is 400 non-outage corrective MWOs. To ensure that the MWO backlog is worked in a timely manner, non-outage maintenance completion goals have been established as:

Goal Priority 1 Emergency N/A Priority 2 Immediate Action 3 days Priority 3 Operations 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 responses to maintenance work requests. Implementation is scheduled for 6/1/

95.

Data Source: Chase /Schmitz (Manager / Source)

Accountability: Chase /Faulhaber Adverse Trend: None SEP 36 45

s 10' Ratio of Preventive to Total Maintenance 90% -

80% -

70% -

~

60% -

~

50% -

40% -

30% ~

20% -

10%-

0%

May Jun Jul Aug Sep oct Nov Dec Jan Feb Mar Apr 1994 1995 2%

C' 3 Preventive Maintenance items Overdue

- Fort Calhoun Goal 1%

C O

O O

O O

O O

O O

o O

0%

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

PREVENTIVE MAINTENANCE ITEMS OVERDUE The top graph shows the ratio of completed non-outage preventive maintenance to total completed non-outage maintenance. The ratio was 88.8% for the month of April 1995.

The lower graph shows the percentage of scheduled preventive maintenance items for April that are overdue. During April 1995,441 PM items were completed. FOur (4) of these PM items (0.9% of the total) were not completed within the allowable grace period or 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 46

1 l

O 6% -

Rework as identified by Craft 5.9%

+ Fort Calhoun Goal (<3%)

5% -

4.7%

4% -

O m

3.2%

6 3% -

(c 1

f 2h

[

2.5%

s o

2% -

i p

2

" ~

i'5' E

N 1% -

0%

sep-94 Oct Nov Dec Jan Feb Mar Apr 95 PERCENTAGE OF TOTAL MWOs COMPLETED PER MONTH IDENTIFIED AS REWORK This graph indicates the percentage of total MWOs completed per month identified as rework. Rework activities are identified by maintenance planning and craft.

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

36% (16)

Required Addition Work Discovered During PMT 55% (24)

Required Work to be Reperformed 9% ( 4)

Required Additional Work Beyond the scope of the original MWO's The Fort Calhoun monthly goal for this indicator is <3%.

Data Source:

Faulhaber/Schmitz (Manager / Source)

Accountability:

Chase /Faulhaber Adverse Trend:

None 1

47

0.45 C"3 Maintenance OverthTm Good

--M--

12-Month Average Maintenance Overtirre 0.4 -

g

--o-- Fort Calhoun "on-Line" Goal (10%)

0.35 -

0.3 -

0.25 -

0.2 -

0.15 -

f i

0.1 -

c f

~~~~

/

O.05 -

n R

,n,n 0

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

The percent of overtime hours with respect to normal hours was reported as 35% for the month of April 1995. This was due to the 1995 refueling outage and is within acceptable limits. The 12-month average percentage of overtime hours with respect to normal hours was reported as 10.5% at the end of the month.

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

i Data Source:

Chase /Schmitz (Manager / Source)

Accountability:

Chase /Faulhaber Adverse Trend:

None l

l 48

3-O open irs Related to the Use of Procedures (Maintenance)

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

O Procedural Noncompliance irs (Maintenance) 2 2-1 1 111 1

1-000 000 000 000 0

000 000 000 0 0 00 000 0

l May Jun Jul Aug Sep oct Nov Dec Jan Feb Mar Apr 1994 1995 PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)

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

There were no procedural noncompliance incidents for maintenance reported for the month of April 1995.

Data Source:

Chase (Manager)

Accountability:

Chase / Conner Adverse Trend:

None 49

Completed Scheduled Activities (AllCrafts)

E""""3 Number of Emergent MWos completed 100% -

-- 120

--e-Fort Calhoun Goal (80%)

f 90% -

102

>. o.

-- 100

GiQ

'I

=

,"N 70% -

1 0

-- 80 $

$4 60% -

NIk s.3.;.

h cgm N@

-- 60 3 se 50% -

53 W~S n

g

]

, %f l

+-

kD [,

%[ih!M.-g 4s

.. ' q" '.

' [p +

Vyy w

+

, gj

& 30% -

n 3.

{

RUQ

^79%

D' M

)

-- 20 I q

^

[

' ig$2; Nh[

M-

.g: '

M 0%

0 January'95 February'95 March '95 April'95

(*% Completed scheduled Activities Not Available)

PERCENT OF COMPLETED MAINTENANCE ACTIVITIES (ALL MAINTENANCE CRAFTS)

This indicator shows the percent of the number of completed scheduled maintenance activities as compared to the number of scheduled maintenance activities concerning al!

Maintenance Crafts. Maintenance activities include MWRs, MWOs, STs, PMOs, calibra-tions, and miscellaneous maintenance activities. The number of emergent MWOs com-pleted for the month is also shown.

The data for this indicator will not be available until 6/1/95 due to software changes re.

i quired for implementation of the Integrated Plant Schedule.

The 1995 Fort Calhoun monthly goal for completed scheduled mainterrero.v.dvhie4 o 80%.

I Data Source:

Chase /Schmitz(Manager / Source)

Accountability:

Chase /Faulhaber Adverse Trend:

None SEP 33 l

l' i

50 i

1

_ ~

C-~3 % of Hours the in-Line Chemistry Instruments are Inoperable

--e-- 1998 Fort Calhoun Goal (10%)

10% -

C 0

0 0

0 0

0 0

0 0

0 o

9% --

9% --

7% --

8% -

s l

3 2% -

~

5 1% -

s 0%

M ay Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 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 indicator include the Second-ary System and the Post Accident Sampling System (PASS).

At the end of April 1995, the percentage of hours the in-line chemistry system instruments were inoperable was 5.78%. The following instruments were out of service for various durations during the month of April 1995:

• Primary Water Storage Tank Dissolved Oxygen YE-1535; 17 days

• A Steam Generator Sodidum Analyzer Yi-6767A; 3 days

• B Steam Generator Sodium Analyzer Ul-6767B; 3 days

• Waste Gas Oxygen Analyzer YlA-627; 4 days

• Waste Gas Hydrogen Analyzer YlA-628; 4 days

• Condensate Pump DracharDe Drssolved Oxygen Analyzer YE-6776; 13 days

• Feedheater #6 Dssolved Oxygen Analyzer YE-6783; 13 days 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.

i 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 51

Waste Produced Each Month (Kilograms)

+ Monthly Average Waste Produced During the last 12 Months (Kilograms)

+ Fort Calhoun Monthly Average Goal (150 kilograms)

--M-~ Federal & State Monthly Limit (Max. of 1,000 kg) 1MO X X

X X

X X

X X

X X

X X

800 -

E 600 -

2 52 400 -

i 200 -C O

O O

O O

O O

O O

O O

I

=

=

=

=

=

OT T

~

T i

May Jun Jul Aug sep oct Nov Dec Jan Feb Mar Apr 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 nnn-halogenated hazardous waste, halogenated hazardous waste, and other hazardous waste produced.

During the month of April 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 54.51 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-j mum of 150 kilograms.

Data Source:

Chase /Carlson (Manager / Source)

Accountability:

Chase / Smith Positive Trend l

52 l

l l

' Contaminated Radiation Controlled Area 15%

I

+ Fort Calhoun Goal (non-outage months)

I Y

12%--

9% --

6%.-

1 3% 1 t.

0%

May Jun Jul Aug Sep oct Nov Dec Jan Feb Mar Apr 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 goalis a maximum of 9.5% contaminated RCA.

At the end of April 1995, the percentage of the total square footage of the RCA that was contaminated was 9.4%.

i Data Source:

Chase /Gundal(Manager / Source)

Accountability:

Chase /Lovett i

Positive Trend SEP 54 53

I

+ Identified PRWPs (Year to Dato) l GOOD l

+ 1995 Fort Calhoun Goal (<20)

T 20 ;

18 -

16 ~

13 n.14 -

g12 -

jiO -

8'

~

4 g 4-

"2-d 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.

j The number of PRWPs which are identified each month should indirectly provide a means i

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

During the month of April 1995, there was 1 PRWP identified.

There have have 13 PRWPs in 1995.

~

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

Data Source:

Chase /Little (Manager /Cource)

Accountability:

Chase /Lovett Adverse Trend:

None 54

l 1

360 -

O Documents Scheduled for Review E Documents Reviewed O Documentsoverdue 250-200 -

150 -

l, May Jun Jul Aug sep oct Nov Dec Jan Feb Mar Apr 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.

During April 1995, there were 137 document reviews scheduled, while 88 reviews were completed. At the end of the month, there were 7 document reviews more than 6 months overdue. There were 14 new documents initiated during April.

Data Source:

Chase /Plath Accountability:

Chase /Jaworski l

Adverse Trend:

None 55 l

60 "

System Failures l GOOD 50 -

j 4g 30 --

26 gg 22 21 20 20 --

16 17 17

~

11 i

10 10 -

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

Non-S ". tem Failures l GOOD l 3

14 -

IY 12 -

10 10 -

8-6-

5 5

5 4

4 4

4-3 3

2 2

2-0 l

May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 1*

LOGGABLE/ REPORTABLE 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 April 1995, there were 26 loggable/ reportable incidents identified compared to 52 for the previous month. System failures accounted for 21 (81%) of the loggable/ reportable incidents. There were five (5) non-system failures during the report-ing period. Lost / Unattended security badge incidents decreased significantly during April 1995 from 11 to two (2). Six (6) of the nine (9) microwave environmental failures are attributed to one microwave zone. An ECN, scheduled for installation in September 1995, will repair this problem.

Data Source:

Sefick/Woerner(Manager / Source)

Accountability:

Sefick Adverse Trend:

None se

i temporary Modifications >1-cycle old (RFO required for removal) i C:":l Temporary Modifications >6 months old (Removable on-line)

--o-- Fort Calhoun Goal for Temporary Modifications > 1-cycle old 6 -

w Fort Calhoun Goal for Temporary Modifications > 6 months old 4

4 4'-

S '

f Nhhy

$ :/

Q<'.

1E m

2-ggy g~g

'*k.c i

g 1

/->

1 l

Gay L

['y M

a c January '95 Fe bruary '95 March '95 April '95 TEMPORARY MODIFICATIONS This indicator provides information on the number of temporary modifications greater than one fuel cycle old requiring a refueling outage (RFO) for removal and the number of 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-tion (BAST level ir.dication) has been approved by management to exceed these goals due to cost effectiveness considerations (reference PED-STE-94-042).

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 completion of MWO 941450, which is scheduled for a future refueling outage whenever cover gaskets are replaced. In addition, at the end of April 1995 there were 4 temporary l

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

These were: 1) Local indication for BAST CH-11 A and CH-11B, in which Operations is reviewing a draft FLC. After review, Licensing is to issue an FLC, and the NRC is to approve; 2) Control system for intensifier on HCV-2987, which is awaiting completion of ECN 94-280, scheduled for completion as 1995 on-line 9/95; 3) brace to IA header 'T' to water plant, which is awaiting completion of ECN 94-482, scheduled for issue from DEN-Mechanical 6/01/95 and Construction Management actions complete 11/30/95; and 4)

DW-8A/B suction piping alignment changes, which is awaiting completion of ECN 94-505, scheduled for completion 11/95. All of these overdue dates have been reviewed and approved by the NPRC and approved based upon need and resource priorities.

At the end of April 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 14 are removable on-line, in 1995, a total of 15 temporary modifications have been installed.

Data Source:

Jaworski/Tumer(Manager / Source)

Accountability:

Jaworski/Gorence Trend:

Needs Increased Management Attention SEP 62 & 71 9

57

> TotalModification Packages Open 140 --

+ Fort Calhoun Year-End Goal 127 120 -

1]

100 -

80 60 -

50

.T 40 -

20 -

M ay Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr OUTSTANDING MODIFICATIONS This indicator shows the total number of outstanding modifications (excludina outstandina modifications which are proposed to be cancelled).

Cateaory Reportina Month Form FC-1133 Backlog /In Progress 2

Mod. Requests Being Reviewed 1

Design Engr. Backlog /In Progress 32 Construction Backlog /In Progress 40 Design Engr. Update Backlog /in Progress 3

Total =

78 At the end of April 1995, 5 additional modification requests had been issued this year and one modification request had been cancelled. The Nuclear Projects Review Committee (NPRC) had completed 11 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) had completed 2 backlog modification request reviews this year.

• A review of the reports used to determine the total number of outstanding modifications

^

and their various stages of accomplishment was undertaken at the request of the Nuclear Planning Department. 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 50 outstanding modifications.

Data Source:

Skiles/Ronne (Manager / Source)

Scofield/Lounsberry (Manager / Source)

Accountability:

Scofield/Phelps Adverse Trend *-

None 58

l I

l J ;,

EARS Requiring Engineering Closeout - Not in Closecut

-E:.

O SE O DEN 5:._

1[

,O,O,n:

,0 C,O.

Feb Mar Apr Feb Mar Apr Feb Mar Apr Feb Mar Apr 0-3 Months 34 Months 6-12 Months

>12 Months April 1995 Overdue EARS 100-.

O Engineering Response O Closeout (SE) 30 60 -

40 20 -

i i

0 Priority 0 Priority 1 Priority 2 Priority 3 Priority 4 Priority 5 Priority 6 i Priority 1 & 2 i Priority 3 Total open EARS i

i 150 --

100 -- ]

]

[

[

[

[

[

[

[

[

50 -

0 M ay Jun Jul Aug sep oct Nov Dec Jan Feb Mar Apr 1994 5 EARS on Schedule 108 EARS 72 EARS 3%

103 Re-- " '. ;

8aasolved 72 Overdue Overdue

[

M s7 camout s

""M i

ENGINEERING ASSISTANT REQUEST BREAKDOWN 1

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.

l Total EAR breakdown is as follows:

EARS opened during the month 24 EARS closed during the month 11 Total EARS open at the end of the month 180 Data Source:

Skiles/Mikkelsen (Manager / Source)

Accountability:

Jaworski/Skiles Adverse Trend:

None SEP 62 l

59

E in DEN = 137 E 0-3 Months = 249 5.6

.7%

O in System Engineering = 98 37.

l O 3-6 Months - 97 h

k7.6% -

O in Procurement /Constr. - 178 7.5 O d u s=2m V

O in Closeout = 142 ECN STATUS - OVERALL BACKLOG E ECNs Backlogged O ECNs Received During the Month

@ ECNs Completed During the Month E 0-3 Months - 64 250 g

s 200 -

=

S m

C 39.4 %

Nc

.7%I O 3-6 Months = 19 150 -

13M O >6 Months - 54 i

i i

i i

i Nov94 Dec Jan Feb Mar Apr95 (Year-to Date rnonthly average of ECNs received was 41)

ECN STATUS DEN 250 -

200-E 0-3 Months = 34 8

8 g

1 50.0%

1 0 3-6 Months = 15

~

O >6 Months = 49 0

i e

i i

i i

,15.3%

Nov94 Dec Jan Feb Mar Apr95 ECN STATUS SE 250-200 -

y j

D D

E 0-3 Months = 83 40.5 1

.6 O 3-6 Months = 23 g

gg iya 2:

}

ER 50-O >6 Months = 72 12.9%

Nov94 Dec Jan Feb Mar Apr95 ECN STATUS PROC /CONSTR 250 g

l E O-3 Months - 68 2

3 g23.9%

100 -

l k

,8 O 3-6 Months = 40 h

R 28.2 %

50-gg a2 ge ag t-r' tr O >6 Months = 34 0

i i

i i

i

[

Nov94 Dec Jan Feb Mar Apr95 i

ECN STATUS-DRAFTING / CLOSEOUT

{

ENGINEERING CHANGE NOTICE STATUS Data Source: Skiles/Mikkelsen (Manager / Source)

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

Prionty 6 &

Priority 1 &

DC Type a s = 133 2 = 111 81 FC Type ""

20 %

m SRI pe =

9 Total Open ECNs by Type (555 Total)

Total Open ECNs by Priority (555 Total)

C DEN. Closecut or Drafting Not Con 1plete EEE MaintenanaWConstrudion/ Procurement. Work Not Complete Priorides Priorities C Syst;m Engineering Response, Conermation Not Complete 6&4 1&2 EEE DEN Engineering NotComplete 15%

23%

__+ Total FC ECNg Open 200 -

y sas sa'

?

12a s22 4

48 51 48 37 33 150 100-B5 83 81 2

80 g4 g-6 4

2 5

5 3

9 51 52 3 ^

4 54 m 42 Prioribes 1

0 3&4 Nov44 Dec Jan Feb Mar Apr-95 82%

Facility Change ECNs Open 3j2 208 Pfioriti'8 Priorities 266 266 28g 280 5&s 1&2 86 250 -

37 15%

27%

t E ss 4s s

5 Nov44 Dec Jan Feb Mar Apr-95 4

Substitute Replacement item ECNs Open seg 160-Priorities i

140 -

1&2 Priorities 120-112 113 118 1

X 4%

3&4 38%

46 51 48 E

20 -

==

g 3a 30 Priorities 0

S&S Sn Nov44 Dec Jan Feb Mar Apr45 Document Chance ECNs Open ENGINEERING CHANGE NOTICES OPEN Data Source:

Skiles/Mikkelsen (Manager / Source)

Accountability:

SI:iles/Jaworski Adverse Trend:

None SEP 62 61

O Administrative Control Problem 3"

E Licensed Operator Error E Other Personnel Error E Maintenance Problem O Design / construction / installation /Fabriation Problem E Equipnent Failures j

.l 2--

l 1-ll ll 0

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

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 April 1,1994, through March 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.

There was one event in March 1995 that resulted in an LER.

Data Source:

Trausch/Cavanaugh (Manager / Source)

Accountability:

Chase Adverse Trend:

None 62

i O Total Requalification Training Hours E Sirnulator Training Hours O Non-Requalification Training Hours E Nunter of ExarnFailures 37 37 37 37 33,g 35 - 32.5 30 M-3 25 --

20 --

7 5

4 15 --

gi 12a 11.5 10 -

7.5 3

3 33 3

2.5 5--

2 E'

0 c ie cycle cycle cycle cyene cycle c rie cycle r

94-2 94-3 94 4 94-5 94-6*

94-7 95 1 95-2

• Note 1:The sirnulator was out-of-service during Cych 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 Ermloyee Trainlag.

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.

Rotation 95-2 was shortened to support the 1995 Refueling Outage. Also, the Simulator was out of service during this rotation for scheduled maintenance. There were no written examination failures during Rotation 95-2.

Data Source:

Gasper /Guliani(Manager / Source) e Accountability:

Gasper /Guliani l

Adverse Trend:

None SEP 68 l

63

E SRO Exams Mministered O SRO Exams Passed O RO Exams Mministered E RO Exams Passed 20 -

15 -

17 10 -

' N'l E,

l l

0 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 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 April, no RO or SRO examinations were administered, with the exception of one remedial examination. The examinee passed his remedial examination.

Data Source:

Gasper /Guliani(Manager / Source)

Accountability:

Gasper /Guliani Adverse Trend:

None SEP 68 64

C-"3 Open Cars > 6 Months Old C open Significant CARS l GOOD l

-+- Total Open Cars

-G-1995 Goal 70 -

60 -

'~^

0 50 -

40 -

30 -

C 0

0 0

l 20 16 18 18 15 17 15 15 14 18 13 11 12

{[ ~7

-8 8

8 7

-8 7

7

~7

~

7

-7

~7 l

]

]

]

"~l

- 7

-]

]

q

-]

-]

"]

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

1994 1975 l

C Open irs >6 Months old l

C-I open significantIRs 450 -

400 -

l 350 -

e 300 -

250 -

200 1g3 3

200 -

162 171 150- )

~

129 127 100 -

2

- 78 81 79 72 73 74 75

~

70 l 65 56 56 50 -

l 0

May Jun Jul Aug sep Oct Nov Dec Jan Feb Mar Apr 1994 1995 OPEN CORRECTIVE ACTION REPORTS AND INCIDENT REPORTS This indicator shows the total number of open Corrective Action Reports (CARS), CARS

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

At the end of April 1995, there were 55 open CARS,16 of these CARS were greater than 6 months old. There were 7 Open Significant CARS at the end of the month.

Also, at the end of April 1995, there were 203 open irs.127 of these IRS were greater than 6 months old. There were 56 Open Significant irs at the end of the month.

The 1995 monthly goal for the number of CARS greater than 6 months old is less than 30.

As of April 21,1995, CARS are no longer being issued. All future corrective actions will be

)

documented on irs.

Data Source:

Orr/Gurtis (Manager / Source) & CHAMPS Accountability:

Andrews/Phelps/Patterson Positive Trend 65 l

l l

l

~

i

~,

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

l t

i J

l i

MWO PLANNING STATUS (CYCLE 16 REFUELING OUTAGE) l 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 thejob from being ready to work are parts or engineering support)

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

Data Source:

Chase /Schmitz Accountability:

Chase /Faulhaber Adverse Trer.d:

None se

e Data for Progress of Cycle 17 Outage Modification Planning will not be available until July 1,1995.

PROGRESS OF CYCLE 17 OUTAGE MODIFICATION PLANNING The data is represented with respect to the baseline schedule and the current schedule.

This information is taken from the Modification Variation Report provided by the Design Engineering group.

l l

l l

Data Source:

Skiles/Ronne(Manager / Source)

Accountability:

Phelps/Skites Adverse Trend:

None SEP 31

(

67 l

l I

i Baseline schedule for PRC Approval

--o-. Projected / Actual schedule for PRC Approal Total Modification Packages (12) (1 le Close out only) 12 h-.

3 10 --

[

Bgl I$y s.-

.I a

6 g

SW 8

o o.

4-E

• X 2

n.

e.

o hffE$$$$$$E Eh!

sasssssi s-s sas ss; 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 packages identified prior to 1/13/95 PRC approved by October 30,1995.

April 1995 Modifcations Added: 0 Deleted = 3 The 3 modifications were added to the 1995 outage work.

Data Source:

Skiles/Ronne (Manager / Source)

Accountability:

Phelps/Skiles Adverse Trend:

None SEP 31

]

68

e e

O 9

ACTION PLANS l

l a

69

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)

. Thermal Performance (page 32)

. Temporary Modifications (page 57)

. Outstanding Modifications (page 58)

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

. The Plant Manager has requested an INPO Staff Assistant visit because of the accident frequency rate increase.

The action plan for Thermal Performance (page 32) is as follows:

. Initial results trom testing to verify FW flow requirements indicate biased results from plant instruments is causing the thermal performance indicator to be under-reported. Corrections to the indicator will be made before October 1,1995.

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 July 1,

- l 1995.

70

ACTION PLANS (continued)

Review of the Outstanding Modifications (page 58) has developed the following results:

. A review of the reports used to determine the total number of outstanding rnodifications and their various stages of accomplishment was undertaken. 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 data.

e 5

71

=

This page has been left blank intentionally.

l 72

PERFORMANCE INDICATOR DEFINITIONS AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM CLEAN CONTROLLED AREA CONTAMINATIONS ?,1,000 PERFORMANCE DISINTEGRATIONS / MINUTE PER PROBE AREA The sum of the known (planned and unplanned) unavailable The personnel contamination events in the ciesn controlled area.

hours and the estimated unavailable hours for the aumliary This indcator tracks personnel performance for SEP #15 & 54.

feedwater system for the reporting penod dmded by the critcal hours for the reporting penod multiplied by the number of trains CONTAMINATED RADIATION CONTROLLED AREA

~*

In the auxsisery feedwater system.

The peroertage of the Radiation Controlled Area, which includes COLLECTIVE RADIATION EXPOSURE the aumliary builden0, the radweste building, and areas of the C/RP buildeng, that is contamensted bened on the total square Cotedwe rar*n exposure is the total extemal whoie-body dose footage. This irdcator tracks performance for SEP #54.

received by all on-site personnel (including contractors and viestors) dunng a time penod, as measured by the DAILY THERMAL OUTPUT thermoluminescent dosimeter (TLD). Collective radiation exposure is reported in units of person-rem. This indcator tracks This indicator shows the daily core thermal output as measured redological work performance for SEP #54.

from computer point XC105 (in thermal rnegawatts). The 1500 MW Tech Spec hmit, and the unmet portion of the 1495 MW FCS COMPONENT FAILURE ANALYSIS REPORT (CFAR) daily goal for the reporting month are also shown.

SUMMARY

DIESEL OENERATOR RELIABILITY (28 Demands)

The summary of INPO categories for Fort Calhoun Station with sagnificantly higher (1.645 standard deviations) failure rates than This indcator shows the number of failures occumng for each the rest of the industry for an eighteen-rnonth time penod.

emergency diesel generator dunng the last 25 start demands and Failures are reported as component (i e., pumps, motors, main the last 25 load-run demands, steam stop valves, control element motors, etc.) categones.

DISABLING INJURY / ILLNESS FREQUENCY RATE Failure Cause Categories are:

(LOSS TIME ACCIDENT RATE)

Wear Out/ Aging. a failure thought to be to be the This indicator is defined as the number of accidents for all utility consequence of expected wart or aging.

personnel permanently assigned to the stabon, involving days away from work per 200,000 markhours worked (100 marbyears).

Manufacturing Defect a failure attributable to inadequate This does not helude contractor personnel. This indcator tracks assemble or initial quality of the respunsible component or personnel performance for SEP #25,26 & 27, system.

DOCUMENT REVIEW (BIENNIAL)

Engineering / Design - a failure attributable to the inadequate design of the responsible component or system.

The Document Review Indcator shows the number of documents remed, the number of documerts scheduled for review, and the Other Devices - a failure attributable to a fakre or number of document reviews that are overdue for the reporting misoperation of another component or system, including mnnth. A documert review is considered overdue if the review !s associated devices, not complete within six months of the assigned due date. This indcator tracks performance for SEP #46.

Maintenance / Testing a failure that is a result a improper maintenance or testing, lack of maintenance, or personnel errors that occur dunng maintenance or testing actMties EMEROENCY AC POWER SYSTEM SAFETY SYSTEM performed on the responsible component or system, includang PERFORMANCE failure to follow procedures.

The sum of the known (pianned and unplanned) unavailable and Errors. failures attributable to incorrect procedures that were the estirnated unavailable hours for the emergency AC power followed as written, improper installation of equipment, and system for the reporting penod divlded by the number of hours in personnel errors (including failure to follow procedures the reporting penod multiplied by the number of trains in the property). Also included in this category are failures for which emergency AC power system.

cause is unknown or cannot be assigned to any of the i

preceding categories.

CENTS PER KILOWATT HOUR The purpose of tnis indcator is to quantify the economcal operation of Fort Calhoun Staten. The cents per kilowatt hour indicator represorts the budget and actual cents per kilowatt hour on a tweh+morth awrage for the current year The bas,s for the budget curve is the approved yearty budget. The basis for the actual curve is the Financial and Operating Report.

73

i

\\

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 with the starting system in its normal abgnment.

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 I

values whch correlate to a high level of confidence that a unit's being declared hoperable should be counted as one demand and diesel generators have obtained a reliabshty of greater than or one fadure. Exploratory tests during corrective maintenance and equal to 95% when the demand failures are less than the tngger the successful test that follows repair to venfy operabihty should values.

not be counted as demands or failures when the EDG has not been declared operable again.

1) Number of Start Dernands: All vahd and inadvertent start demands, including all start <nly demands and all start EMERGENCY DIESEL GENERATOR UNRELIABILITY demands that are foked by load-run demands, whether by automate or manual initiaton. A start-only demand is a This indcator measures the total unrehabikty of emergency diesel demand in whch the emergency generator is started, but no generators. In general, unrehabihty is the ratio of unsuccessful attempt is made to load the generator, operatens (starts or load-runs) to the number of vahd demands.

Total unrehabihty is a combination of start unreliability and load-

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

emergency generator system that prevents the generator frorn achieving specified frequency and voltage es classified ENGINEERING ASSISTANCE REQUEST (EAR) as a vahd start failure This includes any condition identifed BREAKDOWN in the course of maintenance inspections (with the emergency generator in standby mode) that definitely would This indicator shova a breakdown, by age and pnority 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) Nurnber of Load-Run Demands: For a vahd load-run performance for SEP #62.

demand to be counted the load-run attempt must meet orm or more of the following entena ENGINEERING CHANGE NOTICE (ECN) STATUS A) A load run of any duraton that results from a real The number of ECNs that were opened, ECNs that were automate or manualinitiat:on.

completed, and cpen tacklog ECNs awaiting completion by DEN for the reporting month. This indcator tracks performance for B) A load-run test to satisfy the plant's load and duraton SEP #62.

as stated in each test's specifcations.

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 Nobces (ECNs) thd are assigned to Design Engineenng Nuclear (DEN), System Engineenng, and Maintenance. The graphs

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

generator does not pck up load and run as predcted This indicator tracks performance for SEP #62.

Failures are counted dunng any vahd 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 attnbuted to any of the following-Equipmert forced outages per 1,000 entcal 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 rnean time is equal to the number of hours the an emergency.

reactor is crtical in a penod (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 penod.

B) Malfmeten of equipment that is not required dunng an emergency.

EQUIVALENT AVAILABILITY FACTOR C) Intentional terminaten cf a test because of abnormal This indcator is defined as the rate of gross available generation conditions that would not have resulted in major desel to gross maximum generation, expressed as a percentage.

generator damage or repair.

Available generaten is the energy that can be produced if the units is operated at the maximum power level permitted by D) Malfunctens or operating errors whch woukt have not equipment and reguidory hmitations. Maximum generation is the prevented the emergency generator from being energy thd can be produced by a uivt in a given pered if operateo restarted and brought to load within a few minutes.

continuously at maximum capacity.

74 l

~

PERFORMANCE INDICATOR DEFINITIONS FORCED OUTAGE RATE INDUSTRIAL SAFETY ACCIDENT RATE -lNPO This indcator is deflned as the percentage of time that the unit The indcator a defined as the number of accidents per 200,000 was unavailable due to forced events compared to the time mar @ours worked for all utility personnel permanently assigned planned for electncal generat>on. Forced events are failures or to the station that result ln any of the following:

other unplanned conddions that require removing the und fran I*

service before the end of the next weekend. Forced events

1) One or more days of restncted work (exckxting the day of include start-up failures and events initiated while the unit is in the acciden:);

reserve shutdown (I e., the unit is available but not in service).

2) One or mom days away from work (excluding the day of the FUEL REL1 ABILITY INDICATOR accident); and The indcator is defined as the steady-state pnmary coolant 1-13t

3) Fataisties actmty, corrected for the tramp uranium contribution and normakzed to a common punfcation rate. Tramp uranium is fuel Contractor personnel are not included for th:s indicator, whch has been deposted on reactor core intemals from previous defective fuel or is present on the surface of fuel elements from IN-LINE CHEMISTRY INSTRUMENTS OUT OF SERVICE the manufacturing process. Steady state is defined as continuous operation for at least three days at a power level that Total number of in-line chemistry instruments that are out<>f-does not vary more than + or -5%. Plants should collect data for seryce in the Secondary System and the Post Accicent Sampling the indcator at a power level above 85%, when possible. Plants System (PASS).

that did not operated at steady-state power above 85% should collect data for this indicator at the highest steady-state power LICENSE CANDIDATE EXAMS level attained dunng the month.

The indcator shes the number of SRO and/or RO quizzes and The density correction factor is the ratio of the specrfic volume of exams that are administered and passed each month. This codant at the RCS operating temperature (540 degrees F., Vf =

indcator tracks training performance for SEP#68.

0.02146) dmded by the specirc volume of coolant at normal letdan temperature (120' F at outlet of the letdown cooling heat LICENSED OPERATOR REQUALIFICATION TRAINING exchanger, Vf = 0.0162C4), which results in a density correcton factur for FCS equal to 1.32.

The total number of hours of training given to each crew during each cyde. Also pnMded are the simulator training hours (which GROSS HEAT RATE are a subset of the total training hours), the number of non-REQUALIFICATION training hours and the number of exam Gross heat rate is defined as the ratio of tntal thermal energy in falures. Thisindcator tracks training performance for SEP #68.

Bntish Thermal Units (BTU) produced by the reactor to the total gross electncal energy produced by the generator in kilowatt-hours (KWH).

HAZARDOUS WASTE PRODUCED The total amount (in Kilograms) of non-halogenated hazardous waste, halogenated hazardous waste, and other hazardous wast produced by FCS each month.

HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE The sum of the known (planned and unplanned) unavailable hours and the estimated unavailable hours for the high pressure safety injection system for the reporting pered divided by the crital hours for the reporting pened multiplied by the number of trains in the hTh pressure safety injection system.

75 J

PERFORMANCE INDICATOR DEFINITIONS LICENSEE EVENT REPORT (LER) ROOT CAUSE Preventive Actions taken to maintain a piece of equipment BREAKDOWN within design operating conditons, prevent equipment failure, and entend its life and are performed prior to equipment failure.

This indcator shows the number and root cause code for Ucensee Event Reports. The root cause codes are as follows:

Non4ctructiveMant improvements Maintenance actmhos performed to implemert station improvements or to repair non-

1) Administrative Control Problem Management and piant equipment

• 4 supervisory defciencies that affect plant programs or actrdties (i.e., poor planning, breakdown or lack of adequate Maintenance Work Priortties are defined as:

management or supervisory control, incorrect procedures, etc.

Emergency - Condstons which signifcantly degrade staten safety or availabihty.

2) Licensed Operator Error - This cause code captures errors of omason/w n en by licensed reactor operators immediate Action Equipment defciencies which during plant actmties, signifcantly degrade station reliabdity. Potential for unit shutdown or power reduction.

3) Other Personnel Error - Errors of omission / commission I

committed by non-Icensed personnel involved in plant Operations Concern Equipment derciencies which hinder actmtses.

station operation.

4) Mamtenance Probium. The intent of this cause code is to Essential Routine correctrve maintenance on essential capture the full range of problems whch can be attributed station systems and equipment.

in any way to programmate deficiencies in the maintenance functional organization. Activttes included in this category Non-Essential - Roubne correctrve maintenance on non-are maintenance, testing, survedlance, calibration and essenhal station systems and equipment.

radiation protecton.

Plant improvement Non correctrve maintenance and plant i

)

5) DesigrVConstructioMnstallation/ Fabrication Problem.

improvements.

l l

This cause code covers a full range of programmate l

deficiencies in the areas of design, construction, installation, This indcator tracks maintenance performance for SEP #36.

(

and fabncaten (i.e., loss of control power due to underrated I

fuse, equipment not qualified for the environrnent, etc.).

MAXIMUM INDIVIDUAL RADIATION EXPOSURE

6) Equipment Failures (Electronic Piece-Parts or The total maximum amount of radiation received by an individual Environmental-Related Failures) This code is used for person working at FCS on a monthly, quarterly, and annual basis.

spunous failures of electronic piece-parts and failures due to meteorologeal conditions such as lightning, ice, high MWO PLANNING STATUS (CYCLE is REFUELING winds, etc. Generally, it includes spunous or one-time OUTAGE) falures. Electne components included in this category are crcut cards, rectifiers, txstables, fuses, capacitors, dodes.

The total number of Maintenarce Work Orders that have been resistors, etc.

apgrmed for inclusion in the Cycle 16 Refuehng Outage and the nurrber that are ready to work (parts staged, planning complete, LOGOABLE/ REPORTABLE INCIDENTS (SECURITY) and all other paperwork ready for feld use). Also included is the number of MWOs that have been engineering holds (ECNs, The total number of secunty incidents for the reporting month procedures and other truscellaneous engineenng holds), parts depicted in two graphs. This indicator tracks secunty hold, (parts staged, not yet inspected, parts not yet arrtved) and performance for SEP #58.

planning hold (job scope not yet completed). Maintenance Work Requests (MWRs) are also shown that have been identified for MAINTENANCE OVERTIME the Cycle 16 Refueling Outage and have not yet been converted to MWOs.

The % of overtime hours compared to normal hours for rnartenance. This includes OPPD personnel as well as contract personnel.

1 MAINTENANCE WORKLOAD BACKLOGS l

This indcator shows the back}og of noncutage Maintenance Work Orders remaining open at the end of the reporting month.

Maintenance classifcatons are defined as follows:

Corrective - Repair and restoration of equipment or sovna a that have faded or are malfunctioning and are not performing their intended functon.

76

PERFORMANCE INDICATOR DEFINITIONS

]

NUMBER OF CONTROL ROOM EQUIPMENT DEFICIENCIES

2) Modfication Requests Being Reviewed. This category includes:

A control room equipment derciency (CRD) is defined as any component which is operated or controlled from the Control A) Modifcation Requents that are not yet reviewed.

Room, provides indcahon or alarm to the Control Room, provides testing capabilities from the Control Room, provides automate B) Modfcahon Requests being reviewed by the Nuclear actions from or to the Control Room, or provides a passive Projects Review Committee (NPRC).

function for the Control Room and has been identified as deficsont, Le., does not perform under all condihons as designed C) Modfcation Requests being reviewed by the Nuclear This defirsten also apphes to the Attemate Shutdown Panels Al-Projects Committee (NPC).

179, Al-185, and Al-212.

These Modifcation Requests may be reviewed several times A pivt component which is defcient or inoperable is considered before they are appnWed for accomplishment or canceled. Some an "Opeldtor Work Around (OWA) Item" If some other schon is of these Modifcation Requests are retumed to Engmeenng for required by an operator to compensate for the conditen of the rnore a h, 4,m, some approved for evaluation, some approved component. Some examples of OWAs are:

for study, and some approved for planning. Once planning is completed and the scope of the work is clearty defined, these

)

1) The control room level indcator does not work but a local Modfication Requests may be approved for accomplishment with sight glass can be read by an Operator out in the plant; a year asagned for construction or they may be canceled All of these diffeient phases require review.

2) A dercient pump cannot be repaired because replacement parts require a long lead time for purchase / delivery, thus

3) Design Engineering Backlogan Progress. Nuclear requinng the redundant pump to be operated contmuously; Planning has assigned a year in which construction will be completed and design work may be in progress.

3) Special actions are required by an Operator because of equipment design problems. These actons may be

4) Construction BacklogSn Progress. The Construction desenbed in Operabons Memorandums, Operator Notes, or Package has been issued or construction has begun but the may require changes to Operating Procedures; modification has not been accepted by the System Acceptance Committee (SAC).

4) Ceficiert plant equipment that is required to be used during Emergency Operating Procedures or Abnormal Operating

5) Design Engmeeting Update Backlogan Progress. PED Procedures; has received the Modifcahon Complebon Report but the drawings have not been updated.

5) System indcabon that provides critcal information dunng normal or abnormal operabons.

The above mentioned outstanding modifications do not include modifcations whch are proposed for cancellation.

NUMBER OF MISSED SURVEIL 8.ANCE TESTS RESULTING IN LICENSEE EVENT REPORTS OVERALL PROJECT STATUS (REFUELING OUTAGE)

The number of Surveillance Tests (STs) that result in Licensee This indcator shows the status of the projects which are in the Event Reports (LERs) during the reporting month. This indicator scope of the Refueling Outage.

tracks missed STs for SEP #60 & 61.

PERCENTAGE OF TOTAL MWOs COMPLETED PER MONTH OPEN CORRECTIVE ACTION REPORTS & INCIDENT IDENTIFIED AS REWORK REPORTS The percertage of total MWOs completed per month identifed as This indcator displays the total number of open Corrective Action rework. Rework actMbes are identifed by maintenance planning Reports (CARS), the number of CARS that are older than six and craft. Rework is: Any additional work required to correct months and the number of signifcant CARS. Also displayed are deficences discovered dunng a failed Post Maintenance Test to the number of open incident Reports (irs), the number of irs ensure the component / system passes subsequent Post that are greater than six months old and the number of open Maintenance Test.

signifcant irs.

PERCENT OF COMPLETED SCHEDULED MAINTENANCE OUTSTANDING MOOiFICATIONS ACTIVITIES l

The rurnber of Moddication Requests (MRs) in any state between The % of the number of completed maintenance activites as the issuance of a Modifcatson Number and the wiAi of the compared to the number of scheduled maintenance activities drawing update.

each month. This % is shown for all maintenance crafts. Also shown are the number of emergent MWOs. Maintenance

1) Form FC-1133 Backlog /in Progress. Thrs number actMtes include MWRs, MWOs, STs, PMOs, calibratens, and represents modifcation requests that have not been plant other miscellaneous actMtes. This indicator tracks Maintenance approved dunng the reporting month.

performance for SEP #33.

77

PERFORMANP INDICATOR DEFINITIONS PREVENTABLE / PERSONNEL ERROR LERs RADIOLOGICAL WORK PRACTICES PROGRAM This indcator is a breakdown of LERs. For purposes of LER The number of identified poor radclogical work practces event classifcation, a

• Preventable LER" is defined as:

(PRWPs) for the reporting month. This indicator tracks radological work performance for SEP #52.

An event for which the root cause is personnel error (ie.,

inappropnate action by one or more individuals), inadequate RADIO OF PREVENTIVE TO TOTAL MAINTENANCE &

administrative controls, a design constructen, installation, PREVENT 1VE MAINTENANCE ITEMS OVERDUE installat on, fabncaton problem (involving work completed by or supervised by OPPD personnel) or a maintenance problem The ratio of preventNe maritenance (including surveillance testing (attnbuted to inadequate or Improper upkeep / repair of plant and calibration procedures) to the sum of non-outage correctrve equipment). Also, the cause of the event must have occurred maintenance and preventive rnaintenance completed over the vathin approximatety two years of the " Event Date" specified in reporting pered The rate, expressed as a percentage, is the LER (e g., en event for which the cause is attnbuted to a calculated based on man-hours. Also displayed are the percent problem with the onginal design of the plant would not be of preventive maintenance items in the month that were not consdered preventable).

completed or administratively closed by the scheduled date plus a grace pered equal to 25% of the scheduled interval. This For purposes of LER event classifcation, a " Personnel Error" indicator tracks preventive maintenance actrvities for SEP #41.

LER is defined as follows:

RECORDABLE INJURYALLNESS CASES FREQUENCY An event for whch the root cause is inappropnate acton on the RATE part of one or more indviduals (as opposed to being attnbuted to a department or a general group) Also, the inappropnate The number of injunes requinng more than normal first and per acton must have occurred within approximately two years of 200,000 man-hours worked. This indicator trends personnel the " Event Date" specified in the LER.

performance for SEP #15,25 and 26 Additionalty, each event classifed as a " Personnel Error" should REPEAT FAILURES also be classified as " Preventable" This indicator trends personnel performance for SEP ltem #15 The number of Nuclear Plant Rehability Data System (NPRDS) components with more than one fadure and the number of PR! MARY SYSTEM CHEMISTRY % OF HOURS OUT OF NPRDS components with more than two failures for the eighteen-LIMIT month CFAR penod.

The percent of hours out of limit are for six pnmary chemistry SAFETY SYSTEM FAILURES parameters divided by the total number of hours possible for the month The key parameters used are: Lithium, Chlorde, Safety system failures are any events or conditions that could Hydrogen. Dissolved Oxygen, Fluonde and Suspended Sohds prevent the fulfillment of the safety functions of structures or EPRI hmits are used.

systems. If a system consists of multiple redundant subsystems or trains, failure of all trains constdutes a safety system failure.

PROCEDURAL NONCOMPLtANCE INCIDENTS Failure of one of two or more trains is not counted as a safety (MAINTENANCE) system failure The definiten for the indcator parallels NRC repyting requiremerts in 10 CFR 60 72 and 10 CFR 50.73 The The number of dentified inedents conceming maintenance foBowing is a hst of the major safety systems, sub-systems, and procedural problems. the number of closed irs related to the use components monitored for this indicator:

of procedures (includes the number of closed irs caused by nrocedural noncomphanm), and the number of closed procedural Accdent Monitonng instrumentaten, Auxihary (and noncompliance irs. This indcator trends personnel performance Emergency) Feedwater System, Combustible Gas Control, for SEP #15,41 and 44 Component Coohng Water System, Containment and Contarnmert isolaten, Containment Coolant Systems, Control PROGRESS OF CYCLE 16 OUTAGE MODIFICATION Room Emergency Ventilation System, Emergency Core PLANNING (FROZEN SCOPE OF 15 MODIFICATIONS)

Cochng Systems, Engneered Safety Features instrumentaten, Essential Compressed Air Systems, Essential or Emergency This indcator shows the status of modifications approved for Service Water, Fire Detection or Suppressen Systems, completon dunng the Refuehng Outage.

Isolat>on Condenser, Low Temperature Overpressure Protection, Main Steam Line isolation Valves, Onsite PROGRESS OF 1995 ON-LINE MODIFICATION PLANNING Emergency AC & DC Power w/Distnbution, Radiaton (FROZEN SCOPE OF 12 MODIFICATIONS)

Monitonng Instrumentation, Reactor Coolant System, Reactor Core isolation Coohng System, Reactor Tnp System and This indcator shows the status of modifications approved for Instrumentaten, Recirculabon Pump Tnp Actuaton completon dunng 1995 Instrumentation, Residual Heat Removal Systems, Safety Valves, Spent Fuel Systems, Standby Liquid Control System and Ultimate Heat Sink 78

PERFORMANCE INDICATOR DEFINITIONS SECONDARY SYSTEM CHEMISTRY PERFORMANCE STAFFING LEVEL INDEX The actual staffing level and the authonzed staffing level for the The Cherrutry Performance Index (CPI) is a calculaton based on Nuclear Operatens Division, The Production Engineenng the concentration of key impunties in the secondary side of the DMson, and the Nuclear Services Division. This indcator tracks plant. These key impuntes are the most likely cause of performance for SEP #24.

detenorabon of the steam generators. Critena for calculating the CPI are:

STATION NET GENERATION

1) The plant is at greater than 30 percent power; and The net generation (sum) produced by the FCS dunng the reporting month.

2) the power is changing less than 5% per day.

TEMPORARY MODIFICATIONS The CPI is calculated using the following equation:

The number of temporary mechanical and electrical CPI = (sodium /0.90) + (Chloride /1.70) + (Sulfate /1.90) +

configurabons to the plant's systems.

(Iron /4 40) + (Copper /0.30)/5.

1) Temporary configurabons are defined as electncaljumpers, Where: Sodium, sulfate and chlonde are the monthly average electrical blocks, mechanical jumpers, or mechanical blocks blowdown concentrations in ppb, iron and copper are monthly whch are installed in the plant operating systems and are not time weighted average feedwater concentrations in ppb. The shown on the latest revision of the P&lD, schemate, denominator for each of the five factors is the INPO median connecten, winng, or flow diagrams.

value. If the monthly average for a specific parameter is less than the INPO median value, the median value is used in the

2) Jumpers and blocks which are installed for Surveillance calculation.

Tests, Maintenance Procedures, Calibrabon Procedures, Special Procedures or Operahng Procedures are not SIGNIFICANT EVENTS considered as temporary modifcations unless the jumper or block ternans t1 place after the test or procedure is complete.

Significart events are the events identified by NRC staff through Jumpers and blocks installed in test or lab instruments are r'ataded screening and evaluation of operating expenence. The not considered as temporary modifcations.

screening process includes the dady review and discussion of all reported operating reactor events, as well as other operatonal

3) Scaffold is not considered a temporary modifcation.

data such as special tests or construction actMties. An event Jumpers and blocks which are installed and for which MRs identified from the screening process as a signifcant event have been submitted will be considered as temporary candidate is further evaluated to determine if any actual or modificatens until final resolution of the MR and the jumper potedial threat to the heath and safety of the public was involved.

or block is removed or is permanently recorded on the Specific examples of the type of cntena are summanzed as drawings. This indcator tracks temporary modifcahons for follows:

SEP #62 and 71.

1) Degradation of important safety equipment; THERMAL PERFORMANCE

2) Unexpected plant response to a transient; The ratio of the design gross heat rate (corrected) to the adjusted actual gross heat rate, expressed as a percentage.

3) Degradation of fuel integnty, pnmary coolant pressure boundary, important associated features; UNIT CAPABILITY FACTOR

4) Scram with compication; The rado of the availabie energy generaten over a given time pened to the refererce energy generation (the energy that could

5) Unplanned release of radcactMty; be produced if the unit were operated conbnuously at full power under reference ambient conditions) over the same time period,

6) Operation outside the limits of the Technical Specifcatens; expressed as a percentage.

7) Other.

UNIT CAPACITY FACTOR INPO significant events reported in this indicator are SERs The net electncal energy generated (MWH) divided by the (Signitcant Event Reports) whch inform utilities of signtfcant product of maximum dependable capacity (net MWe) times the events and lessons leamed identified through the SEE-IN gross hours in the reporting period expressed as a percent. Net screening process.

electrical energy generated is the gross electncal output of the unit measured at the output terminals of the turbine generator SPARE PARTS INVENTORY VALUE minus the normal staten servce loads dunng the gross hours of the reporting penod, expressed in megawatt hours.

The dollar value of the spare parts inventory value for FCS dunng the reporting penod.

79

PERFORMANCE INDICATOR DEFINITIONS UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7,000 UNPLANNED SAFETY SYSTEM ACTIONS (NRC CRITICAL HOURS DEFINITION) i This indcator is defined as the number of unplanned automatic The number of safety system actuatons whch include (gn!y) the

'l scrams (reactor protection system logc actuatons) that occur per High Pressure Safety injection System, the Low Pressure Safety 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of entcal operation inledon System, the Safety injection Tanks, and the Emergency Diesel Generators. The NRC classifcation of safety system

• j The value for this indcator is calculated by multiplying the total actuahons includes actuabons when major equipment is operated number of unph nned automate reactor scrams in a specifc time BDQ when the loge systems for the above safety systems are i

penod by 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, then dividing that number by the total challenged.

nurnber of hours enticalin the same time penod. The indcator es further defined as follows:

VIOLATIONS TREND

1) Unpanned rneans that the scram was not an anticipated part This inde #or is defined as Fort Calhoun Staten Cited Violatons of a planned test.

and Non-Cited Violations trended over 12 months. Additonally, Cited Violations for the top quartie Regon IV plant is trended over

2) Scram means the automate shutdown of the reactor by a 12 months (lagging the Fort Calhoun Station trend by 2-3 rapid insertion of negative reactivity (e g, by control rods, months) It ts the Fort Calhoun Staten goal to be at or below the liquid injection system, etc.) that is caused by actuation of the cited volaton trend for the top quartile Region IV plant, reactor protection system. The scram signal may have resulted from exceeding a set point or may have been VOLUME OF LOW. LEVEL SOLID RADIOACTIVE WASTE spunous.

This indicator is defined as the volume of low-level solid radioactive waste actually shipped for bunal This andcator also

3) Automate means that the initial signal that caused actuation shows the volume of low-level radioactive waste which rs in of the reactor protection system logc was provided from one temporary storage, the amount of radcactrve oil that has been of the sensor monitonng plant parameters and condstons, shipped off-site for processing, and the volume of solid dry rather than the manual scram switches or, in manual turbine radcactre waste which has been shipped off site for processing.

tnp switches (or push-buttons) provided in the main control Low-level solid radcoctrve waste consists of dry active waste, room sludges, resins, and evaporator bottoms generated as a result of nuclear power plant operaton and rnaintenance. Dry radcactive

4) Cntical means that dunng the steadyAate condition of the waste inchdes contamrided rags, cleaning matenals, disposable reactor pnor to the scram, the effective multipication (k,,, )

prdective cidhing, plashc containers, and any other matenal to be was essentially equal to one.

dcsposed of at a low-level radioactive waste disposal site, except resin, sludge, or evaporator bottoms. Low-level refers to all UNPLANNED CAPAB1LITY LOSS FACTOR radcactrve waste that is not spent fuel or a by-product of spent fuel processing. This indcator tracks radiologcal work The rato of the mplanned energy losses dunng a given period of performance for SEP #54 time, to the reference energy generaton (the energy that could be produced if the unit were operated continuously at full power under reference ambient conditions) over the same time penod, expressed as a percentage.

UNPLANNED SAFETY SYSTEM ACTUATIONS - (INPO DEFINITION)

The indicator a defined as the sum of the following safety system actuatons:

1) The number of unplanned Emergency Core Cooling System (ECCS) actuations that result from reaching an ECCS actuaton set point or from a spunous/ inadvertent ECCS signal.

2) The number of unplanned emergency AC power system actuations that result from a loss of power to a safeguards bus An mplanned safety system actuaton occurs when an actuaten set point for a safety system is reached or when a spunous or riadvertent signal rs generated (ECCS only), and major 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 actuations of the high pressure injecton system, the low pressure rijection system, or the safety injection tanks.

80

I I

1 SAFETY ENHANCEMENT PROGRAM INDEX The purpose of the Safety Enhancement Program (SEP) Performance Indicators Index is to list performance indicators related to SEP items with parameters that can be trended.

a SEP Reference Number 15 East

. Increase HPES and IR Accountability through use of Performance indicators Procedural Noncompliance incidents (Maintenance)...................................... 4g Clean Controlled Area Contaminations >1,000 Disintegrations / Minute Per Probe Area

.......... 5 Recordable injury /lliness Cases Frequency Rate..................................... 4 Preventable / Personnel Error LERs...........................................

.....6 SEP Reference Number 24

. Complete Staff Studies Sta ffing Level.................................................................. 42 SEP Reference Numbers 25. 26. & 27

. Training Program for Managers and Supervisors implemented

. Evaluate and implement 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)

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

Progress of Cycle 16 Outage Modification Planning........................................ 68 SEP Reference Number 33

. Develop On-Line Maintenance and Modification Schedule Percent of Completed Scheduled Maintenance Activities (All Maintenance Crafts).............. 50 SEP Reference Number 36

. Reduce Corrective Non-Outage Backlog Maintenance Workload Backlogs (Corrective Non-Outage)............................... 45 SEP Reference Numbers 41 & 44

. Develop and implement a Preventive Maintenance Schedule

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

..........46 Procedural Noncompliance incidents (Maintenance)......................

.......49 SEP Reference Number 46 i

. Design a Procedures Control and Administrative Program l

Document Review 55 81

SEP Reference Number 52 EAnt

. Establish Supervisory Accountability for Workers Radiological Practices Radiological Work Practices Program.............

........... 54 SEP Reference Number 54

. Complete implementation of Radiological Enhancement Program Collective Radiation Exposure....................................................... 16 Volume of Low-Level Solid Radioactive Waste........................................... 37 Clean Controlled Area Disintegrations >1,000 Counts / Minute Per Probe Area................... 5 Contaminated Radiation Controlled Area................................,.............. 53 SEP Reference Number 58

. Revise Physical Security Training and Procedure Program Loggable/ Reportable incidents (Security)............................................. 56 SEP Reference Numbers 60 & 61

. Improve Controls Over Surveillance Test Program

. Modify Computer Program to Correctly Schedule Surveillance Tests Number of Missed Surveillance Tests resulting in Licensee Event Reports

.....................20 SEP Reference Number 62

. Establish Interim System Engineers Temporary Modifications........................................................... 57 Engineering Assistance Request (EAR) Breakdown.....................,................. 59 Engineering Change Notice Status..................................................... 60 Engin eering Ch a nge Notices Ope n................................................... 61 SEP Reference Number 68

)

. Assess Root cause of Poor Operator Training and establish means to monitor Operator Training Ucense Operator Requalification Training...........

.............................63 License Candidate Exams

.......................... 64 SEP Reference Number 71

. Improve Controls over Temporary Modifications Temporary Modifications

............................... 57 4

l l

i 82

REPORT DISTRIBUTION LIST R. L. Andrewc J. D. Keppler K. L. Belek D. D. Klocck B. H. Blome L.T.Kusek C. E. Boughter M. P. Lazar C. J. Brunnert B. R. Livingston M. W. Butt D. L. Lovett G. R. Cavanaugh J. H. MacKinnon

' J. W. Chase J. W. Marcil A. G. Christensen N. L. Marfice O. J. Clayton R. D. Martin R. P. Clemens T. J. Mcivor R. G. Conner K. G. Melstad J. L. Connolley K. A. Miller G. M. Cook P. A. Mruz S. R. Crites Nuclear Licensing D. W. Dale

& Industry Affairs D. C. Dietz J. T. O'Connor M. L. Ellis W. W. Orr H. J. Faulhaber T. L. Patterson M. T. Frans R. T. Pearce D. P. Galle R. J. Phelps S. K. Gambhir W.J.Ponec J. K. Gasper C. R. Rice W. G. Gates A. W. Richard S. W. Gebers D. G. Ried L. V. Goldberg G. K. Samide D. J. Golden M. J. Sandhoefner D. C. Gorence F. C. Scofield R. H. Guy H. J. Sefick A. L. Hale J. W. Shannon K. R. Henry C. F. Simmons J. B. Herman E.L.Skaggs T. L. Herman J. L. Skiles K. C. Holthaus F. K. Smith L. P. Hopkins R. L. Sorenson C.K. Huang K. E. Steele T. W. Jamieson M. A.Tesar R. L. Jaworski J. J. Tesarek R. A.Johansen J. W. Tills J. W. Johnson D. R. Trausch R. Jones J. M. Waszak W. C. Jones G. R. Williams S. J. Willrett l

83

FORT CALHOUN STATION OPERATING CYCLES AND REFUELING OUTAGE DATES EVENT DATE RANGE PRODUC' ION (MWH)

CUMULATIVE (MWH) i Cycle 1 09/26/73 -02/08/75 3,299,639 3,299,639 l

f'.

1st Refueling 02/08/75 -05/11/75 Cycle 2 05/11/75-10/01/76 3,853,322 7,152,961 l

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 l

Sth Refueling 01/18/80 -06/11/80 Cycle 6 06/11/80 -09/18181 3,899,714 20,768,168 6th Refueling 09/18181 - 12/21!81 Cycle 7 12/21I81 -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 -09/28/86 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 j

Cycle 15 11/26/93 -02/20/95 5,043,887 61,065,900 15th Refueling 02/20/95-04/14/95 FORT CALHOUN STATION CURRENT PRODUCTION AND OPERATIONS " RECORDS"

)

First Sustained Reaction August 5,1973 (5:47 p.m.)

First Electricity Supplied to the System August 25,1973 Commercial Operation (180,000 KWH)

September 26,1973 Achieved Full Power (100%)

May 4,1974 Longest Run (477 Days)

June 8,1987-Sept. 27,1988 Highest Monthly Net Generation (364,468,800 KWH)

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

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

Feb. 20,1995-April 14,1995

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