ML20138G818

Performance Indicators for Nov 1996

ML20138G818
Person / Time
Site:	Fort Calhoun
Issue date:	12/20/1996
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20138G814	List: LIC-96-0201, Forwards Fort Calhoun Station Performance Indicators Rept for Nov 1996 ML20138G818
References
NUDOCS 9701020284
Download: ML20138G818 (113)

Text

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4 FORT CALHOUN STATION PERFORMANCE INDICATORS

• /

NOVEMBER 1996 SAFE OPERATIONS PERFORMANCE EXCELLENCE COSTEFFECTIVENESS FlR' 88!A 7es!!80s l

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FORT CALHOUN STATION November 1996 Monthly Operating Report i

OPERATIONS

SUMMARY

Fort Calhoun Station (FCS) was in a refueling outage until November 25 at 0644 hours0.00745 days <br />0.179 hours <br />0.00106 weeks <br />2.45042e-4 months <br /> when the reactor was made critical to start low power physics testing. The turbine l

generator was online at 0200 on November 27. The generator was maintained at a nominal 30% power level until November 28 at 0032 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> when the turbine over speed testing was conducted. The generator was retumed to service at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br /> on November 28 and maintained at a nominal 30% power level for secondary chemistry holds.

On November 30 at 0808 a slow power ramp-up was started to retum FCS to full power.

Major activities scheduled and completed during the refueling outage included.

complete core offload / reload; fuel sipping and reconstitution; polar crane feedrail replacement; Reactor Coolant Fump RC-3B motor replacement; Steam Generator tube inspection and plugging; manual DC transfer switch replacement; replacement of the final three (3) of four (4) channels of the reactor protective system nuclear instrumentation wide range power drawers; control element drive mechanism seal rebuilds; motor operator valve testing (MOVATS); containment local leak rate penetration tests; low pressure turbine inspection; circulating water system valve FCV-1904B repair; and AC supply bus maintenance and testing.

On November 11 at 1540 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.8597e-4 months <br /> it was determined that the containment air coolers would not function as required for certain Updated Safety Analysis Report, Chapter 14, design accidents. During a loss-of-cooling-accident (LOCA) or main steam line break event coincident with a loss of offsite power, the containment air coolers could generate an intemal steam bubble and upon restart of the component cooli,a water (CCW) pumps the steam bubble could collapse and generate water hammer inside the piping.

A safety analysis for operability evaluation had been completed to justify operability of the CCW system. Final resolution is expected by the end of the next refueling outage.

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--,, Industry tiedlanindex Value g_

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79 70.

Industry Median Projected 65 60.

1996 RFO Value forNovember 1998 is 80%

50.

40 95/1 95/2 95/3 95/4 96/1 96/2 96/3 Oct Nov Dec Jan Feb PERFORMANCE INDEX TREND j

l For the index calculation unit capability factor, unplanned capability loss factor, unplanned i

automatic scrams per 7000 hours0.081 days <br />1.944 hours <br />0.0116 weeks <br />0.00266 months <br /> critical, safety system performance, and collective radiation exposure. The indicators indicators are calculated for a two-year period instead of the normal three-year period to allow the index trend to be more responsive to changes in plant performance.

INPO no longer uses the volume of low-level radioactive waste as a plant indicator. The value will still be tracked, but the value will no longer be used in calculating the Stations Performance Index.

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UCF UCLF W S!

AFW EACP CRE uAs7 FRI CPI TPI isAR i

This graph shows the difference between the Maximum No. of points for each INPO indicator and the actual value achieved by Fort Ce!houn for the month of July.

I UCF Unit Capability Factor TPI Thermal Performance Indicator UCLF Unplanned Capability Loss Factor CPI Secondary Chemistry Indicator l

HPSI High Pressure Safety injection ISAR Industrial Safety Accident Rate AFW Auxiliary Feedwater l

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EACP Emergency AC Power UAS7 Unplanned Auto Scrams / 7000 Hours CRE Collective Radiation Exposure FRI Fuel Reliability Indicator Per INPO, the Performance Indicator for the Volume of Low Level Radioactive Waste buried, will no longer be used in calculating the Stations Performance index. All other parameters have been adjusted to reflect this change.

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Performance better than 1996 OPDD Goal l

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FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT j

October 1996-

SUMMARY

POSITIVE TREND REPORT POSITIVE TREND REPORT (cont.)

)

A performance Indicator with data representing three Contaminated Radiation' Controlled Area consecutive months ofimproving performance or three (Page 55) j consecutive months of performance that is superior to the stated goalis exhibiting a positive trend per Nuclear Temocrary Modifications j

Operations Division Quality Procedure 37 (NOD-QP-(Page 59) 37).

The following performance indicators exhibited positive End of Positive Trend Report.

trends for the reporting month:

Safetv Svstem Failures gp 9 19)

ADVERSE TEFND REPORT Hioh Pressure Safety Iniection System Safety System A performance indicator with data representing three l

Performance consecutive months of declining performance or three (Page 5) consecutive months of performance that is trending toward declining as determined by the Manage' -

Auxiliary Feedwater System Station Engineering. constitutes an adverse trend per (Page 6)

Nuclear Operations Division Quality Procedure 37 (NOD-QP-37). A supervisor whose performance j

I Emeraency A C Power System indicator exhibits an adverse trend by this definition (Page 7) may specify in written form (to be published in this report) why the trend as not adverse.

Secondary Chemistry (Page 10)

The following performance indicators exhibited adverse J

trends for the reporting month:

Emeraenev Diesef Generator Unit Reliabihty (Page 20)

Fuel Reliabihtv Indicator (Page 9)

Diesel Generator Reliability (25 Demands) l (Page 21)

Maintenance Workload Backloas (Page 47)

Emeroency Diesel Generator Unreliabilrty (Page 22)

Preventative Maintenance items Overdue (Page 48)

Missed Surveillance Tests Results in Licensee Event Reports End of Adverse Trend Report.

j (Page 28)

Unolanned Safety System Actuations (INPO)

(Page 34)

Secondary System Chemistry (Page 35) j Hazardous Waste Produced (Page 54) 4 Vi

3 INDICATORS NEEDING INCREASED 2

MANAGEMENT ATTENTION REPORT A performance indicator with data for the reporting period that is inadequate when compared to the OPPD goal is defined.as *Needing increased Management Attention

• per Nuclear Operations Division Qualdy Procedure 37 (NOD-QP-37).

Eauioment Forced Outaae Rate (Page 38)

Cents Der Kilowatt Hour (page 44)

Percentaae of Total MC Comoleted Der Month Identified as Rework, (Page 49)

PERFORMANCE INDICATOR REPORT IMPROVEMENTS / CHANGES End of Report improvements / Changes Report.

i vii

Table of Contents / Summary G OA LS........................................................

. xH WA NO PERFOR MA NCE IMDICATORS.................................................... 1 Unit Capability ~ Factor................................................................ 2 Unplanned Ca pability Loss Fa cte..................................................... 3 Unplanned Automatic Reactor SC TAMS per 7000 Hours.................................... 4 High Pressure Safety injection System.................................................... 5 AuxiDary Feedwater System............................................................ 6 Emergency AC Power System............................................................ 7 The rmal Pe rforma n ce.................................................................. 8 Fuel Reliability Indicator................................................................ 9 Second ary System Chemistry....................................................... 10 Collective Radiation Ex posure......................................................... 11 Volume of Low Level Radioactive Waste................................................. 12 Industrial Safety Accident Rate...................................

................13 SAFE OPERATIONS Disabling injury /lliness Cases Frequency Rate........................................... 15 Recordable injury / Illness Cases Frequency Rate 16 Clean Controlled Area Contaminations

>1,000 Disintegrations / Minute per Probe Area

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

.... i8 Safety System Failures 19 Emergency Diesel Generator Unit Reliability

.............20 Reliability (25 Demands) 21 Unreliability................

...................... 22 Control Room Equipment Deficiencies.....

..... 23 On-line and Outage Control Room Equipment Deficiencies 24 viii

Table of Contents / Summary Maximum individual Radiation Exposure................................................. 25 Vio lation Trend.................................................................... 26 l

Significa nt Ev ents................................................ ".................. 27 Missed Surveillance Tests Resulting in LERs

.............................................28 I

PERFORMANCE Station Net Generation........................................................... 30 Fo rced Outag e R ate................................................................ 31 U nit Ca pa city Fa ctor................................................................... 32 Equivalent Availability Fa ctor......................................................... 33 Unplanned Safety System Actuations I N PO Definition............................................................... 34 NRC Definition............................................................ 35 G ross Heat R ate...................................................................... 36 D aily Thermal Output............................................................... 37 Equipment Forced Outages per 1,000 Critical Hours

......................................38 Component Failure Analysis Report ;cFAR) Summary..................................... 39 Repeat Failures

......................................................................40 Chemistry Action Levels Exceeded - Event Days............................................ 41 1

Primary System Lithium % Hours Out of Limit

.................................42 993.I Cents Per Kilowatt Hour.......................................................

44 Spare Parts inventory Value.............

.....45 i

l l

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Table of Contents / Summary DIViblON AND DEPARTMENT PERFORMANCE INDICATORS Maintenance Workload Backlogs (Corrective Non-Outage).....................'................... 47 Ratio of Preventive to Total Maintenance......

...............................48 Percentage of Total MWOs Completed per month identified as Rework 49 Ov ertime.......................................

.............50 1

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

51 Daily Schedule Performance

- Percent of Completed Scheduled Activities................................ 52 l

In-Une Chemistry Instruments Out-of-Service

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

....................... 54 Contaminated Radiation Controlled Area............

55 Radiological Work Practices Program 56 Document Review

.................57 Loggable/ Reportable incidents (Security) 58 Temporary Modifications..............................

.............59 Outstanding Modifications...............

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

....................61 i

Engineering Change Notices Status

.......................................... 62 O pe n........................

........ 63 Ucensee Event Report (LER) Root Cause Breakdown

..... 64 Ucensed Operatcr Requalification Training............................................ 65 Ucense Candidate Exarns...................

66 Condition Reports 67 Cycle 17 Refueling Outage MWO Planning Status 68 Overall Project Status....

69

)

Outage Modification Planning 70 On-Une Modification Planning 71 Progress of 1996 On-Une Modification Planning......

.... 72 X

ACTION PLANS. DEFINmONS. SEP INDEX & DISTRIBUTION LIST Actio n Pla ns........................................,,,.........,,,,,,,,,,,,,,,,,,, 73 4

Performance Indicator Definitions..................................................... 78 I

Safety Enhancement Program Inder................................:................. 86 j

Report Distribution List....................................................,,,,,,,,,,,,, gg

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OPPD NUCLEAR ORGANIZATION GOALS 1996 Priorities i

MISSION The safe, reliable and cost effective generation of electricity for OPPD customers through i -

conservative decision making and the professional use of nuclear technology. We will conduct these operations to assure the health, safety;, and protection of our personnel, the general public, and the environment.

f GOALE i

Goal 'i:

SAFE OPERATIONS Supports: April 1995 Corporate Strategic Plan Goal 3, Obj: 3 & 4 j

A proactive, self-critical and safety conscious culture is exhibited throughout the nuclear l

organization. Individuals demonstrate professionalism through self-ownership and personal j

initiative and open communication.

1996 Priorities:

l Improve SALP ratings.

Improve INPO rating.

Reduce 1996 NRC violations with no violations more severe than level 4.

l No unplanned automatic reactor scrams or safety system actuations.

I Objectives to support SAFE OPERATIONS.

4 OBJECTIVE 1-1:

j No challenges to a nuclear safety system.

OBJECTIVE 1-2:

].

Comply with applicable policies, technical specs, procedures, standing orders and work instructions..

OBJECTIVE 1-3:

q identify conditions BEFORE they affect plant safety and reliability. Address every safety concem.

j OBJECTIVE 14:

Achieve all safety-related 1996 performance indicator goals in the Perfor; nance Indicator Report.

3 OBJECTIVE 1-5:

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

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OPPD NUCLEAR ORGANIZATION GOALS j

1996 Priorities Goal 2:

PERFORMANCE Supports: April 1994 Corporate Strategic Plan Goal 3, Obj: 2; G-4, Obj: 1, 2, & 3; G-6, Obj 3 Nuclear teamwork achieves high performance at Fort Calhoun Station as exhibited by safe, i

reliable and cost effective power production.

1996 PRIORGIES:

i Improve Quality, Professionalism and Teamwork.

i l

Maintain High Plant Reliability.

Pursue efficient, cost-effective work processes.

Meet or exceed INPO key parameters and outage performance goals.

1 Reduce the number of Human Performance errors.

Identify Programmatic performance problems through effective self assessment.

Maintain a high level of readiness in the ERO.

Objectives to support PERFORMANCE:

OBJECTIVE 2-1:

Achieve an annual plant capacity factor of 81.4% and a unit capability factor of 83.56%

OBJECTIVE 2-2:

Execute the 1996 refueling outage in 42 days or less; emphasize shutdown plant safety, i

OBJECTIVE 2-3:

Training meets the needs of the plant and the National Academy accreditation objectives.

Line managers use training to present, discuss & reinforce performance standards.

Line managers monitor and assess personnel performance to determine how well stan fards are met.

Line managers through personal involvement in training emphasize the importance of conducting activities within approved procedures / practices.

Executive Training Committee:

invites line supervisors to discuss the direction training is going for their specific area.

invites the line and training supervisors responsible for each accredited program to provide a status of intemal accreditation assessments.

ensures items such as training attendance, attentiveness, punctuality, etc. are uniformly emphasized.

OBJECTIVE 2-4:

Achieve all performance-related 1996 performance indicator goals in the Performance Indicator Report. Focus on performing basic skills well while pursuing efficient, cost-effective work processes.

Identify the barriers to excellence and resolve them.

xiii

OPPD NUCLEAR ORGANIZATION GOALS 1996 Priorities Goal 2:

PERFORMANCE (Continued) l OBJECVVE 2-5:

Teamwork is evide.nt by improved plant reliability, an effective emergency response organization, reduced number of human performance errors and effective self assessment.,

i OBJECRVE 24 This Jgh the Utilities Services Alliance (USA) attain operatin0 efficience and lower cost through l

a cooperative effort among several utilities. Initial focus is on sharing of personnel for outage support, combined purchasing and contracting, common dosimetry reading, sharing of equipment, including test equipment, standardization of plant access and general employee training.

Goal 3:

COSTS j

Supports: April 1995 Corporate Strategic Plan Goal 2, Obj: 1,2 and 3, and Goal 6, Obj: 1 Operate Fort Calhoun cost effectively to contribute to OPPD's " bottom line".

Cost consciousness is exhibited at all levels of the organization.

)

1996 Priorities:

i Maintain total O&M and Capital Expenditures within budget.

Streamline work process to improve cost effectiveness.

Implement Opportunity Review recommendations.

_ Objectives to support COSTS:

1 i

OBJECVVE 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 thee estimated cost savings.

Goals Source:

Lounsberry (Manager) xiv

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, Monthly Unit Capability Factor

...s... Year-to-Date Unit Capability Factor N

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36-Month Unit CapabilityFactor 1996 Fort Calhoun Goals GOOD 5

INPo industry Goals Year 2000 100%..

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, r7 Dec Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov 1996 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 d3 fined as the ratio of the cvailable energy generation over a given period of time to the reference energy generation (the energy that could be produced if the unit were operated continuously at full power under reference ambient conditions) over the same time period, expressed as a percentage (refu-cling periods excluded).

The UCF for November 1996 was reported as 0.7%. The year-to-date UCF was 72.9%, the UCF for the last 12 months was 74.5%, and the 36-month average UCF was reported as 83.9% at the end of the month.

Energy losses for May and August 1995 are explained on page 30.

Energy losses for March 1996 are due to a scheduled mini-outage and condenser tube re-pair.

Energy losses for May 1996 are due to a reduction in power to 95% for Moderator Coefficient Testing.

Energy losses for June 1996 are due to a forced outage when the Anti-Rotation Device on Reactor Coolant Pump RC-3B-M failed.

Energy losses for Sept., Oct.. & Nov.1996 due to the scheduled Refueling Outage.

The Year 2000 INPO industry goal is 87% and the industry current best quartile value (for the three-year period ending 12/94) is approximately 85%. The 1996 Fort Calhoun annual goal for this indicator is a minimum of 83.56%.

The maximum index point value for this indicator is 16. For the month of November the FCS Value was 12.00. This compares to the previous month's value of 13.32.

Data Source:

Generation Totals Report & Monthly Operating Report Accountability:

Chase Trend:

None 2

, Monthly Unplanned Capability Loss Factor l GOOD l

_,__ Year.To-Date Unplanned capability Loss Factor

+ 12-Month Average Unplanned Capability Loss Factor 1(

)

+ Fort Calhoun Goal (3.00%)

e_ Year 2000 INPO Industry Goal (4.5%)

l Industry Current Best Quartile 60%

50%..

40%..

30 %

20%

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Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec l1996l UNPLANNED CAPABILITY LOSS FACTOR This indicator shows the plant monthly Unplanned Capability Loss Factor (UCLF), the year-todate 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 s

produced if the unit were operated continuously at full power under reference ambient condi-tions), expressed as a percentage.

The UCLF for the month of November 1996 was reported as 30.42% Unplanned energy loss is defined as energy not produced as a result of unscheduled shutdowns, outage exten-sions, or load reductions due to causes under plant management control. Energy losses are considered to be unplanned if they are not scheduled at least four weeks in advance. There were 219 hours0.00253 days <br />0.0608 hours <br />3.621032e-4 weeks <br />8.33295e-5 months <br /> of unplanned energy losses due to the 9 day and 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> extension of the 1996 refueling outage. The year-to-date UCLF was 9.04%, the UCLF for the last 12 months was 8.28%, and the 36-month average UCLF was reported as 6.7% at the end of the month.

The Year 2000 INPO industry goal is 3.0% and the industry current best quartile value is approximately 3.2% or lower. The 1996 Fort Calhoun year-end goal for this indicator is a maximum value of 3.0%.

The maximum index point value for this indicator is 12. For the month of Novemberthe FCS Value was 4.83. This compares to the previous month's value of 5.82.

Data Source:

Generation Totals Report & Monthly Operating Report Accountability:

Chase Trend:

Needs increased Management Attention.

3

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

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

+ Fort Calhorm Goal (0,0)

+ Year 2000 INPo industry Goal (1) e industry Upper 10%(1 per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical)

)

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0 Ah>r May Jun Jul Aug Sep Oct P[ov Dec Jan Nb Mar FCS Reactor Scrams -1996 4..

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i 92 93 94 95 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7000 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 (cs defined in INPO's 12/93 publication " Detailed Descriptions of Intemational 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 November 1996. The value for the 12 months from December 1,1995, through November 30,1996 was 0.0. The value for the last 36 months was 0.913.

The 1996 Fort Calhoun goal for this indicator is 0. The Year 2000 INPO industry goal is a maximum of one unplanned automatic reactor scram per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical. The industry upper ten percentile v lue is approximately 0.48 scrams per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical.

The maximum index point value for this indicator is 8. For the month of November the FCS Va'ue was 8.0. This compares to the previous month's value of 8.0.

Data Source:

Monthly Operating Report & Plant Ucensee Event Reports (LERs)

Accountability:

Chase Trend:

Positive 4

gg Monthly High Pr;ecura s;fety injection system Unavailability V;iue Year-to-Date High Pressure safety injection systern Unavailability Value Good l

+ Fort Calhoun Goal (0.003)

+ Year 2000 INPo industry Goal (0.02)

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x 1994 1995 Jan Feb Mar Apr May Jun Jul Aug sep oct Nov Dec I*I HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the High Pressure Safety Injection (HPSI) System unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for the reporting month.

The HPSI System unavailability value for the month of November 1996 was 0.00. There were 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of planned unavailability, and 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unpianned unavailability, during the month. The 1996 year-to-date HPSI unavailability value was 0.00004 at the end of the month.

The unavailability value for the last 12 months was 0.000034126.

There has been a total of 0.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-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 HPSI system in 1996.

There was a total of 13.39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> of planned unavailability and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned un-availability for the HPSI injection system in 1995.

The 1996 Fort Calhoun year-end goal for this indicator is a maximum value of 0.003. The Year 2000 INPO industry goal is 0.02.

The maximum index point value for this indicator is 10. For the month of October the FCS Value was 10. This compares to the previous month's value of 10.

Data Source:

Phelps/Schaffer (Manager / Sour':e)

Accountability:

Phelps/Schaffer Trend:

Positive 5

Monthly Auxiliary Feedwater system unavailability i

Year.toeste AFW unavailability x

..... Fort calhoun Goal (0.01)

Year 2000 INPo industry Goal (0A25)

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AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Auxiliary Feedwater (AFW) System Unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for the reporting month.

)

1 The AFW System Unavailability Value for November 1996 was 0.0. There were 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of planned and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned unavailability during the month. The year-to-date un-cvailability value was 0.0017 and the value for the last 12 months was 0.00244 at the end of the month.

There has been a total of 14.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of planned unavailability and 6.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of unplanned unavailability for the AFW system in 1996. The unplanned unavailability on FW-10 was due to a failed relay on HCV-10458.

The 1996 Fort Calhoun year-end goal for this indicator is a maximum value of 0.01.

The Year 2000 INPO industry goal is 0.025.

The maximum index point value for this indicator is 10. For the month of November the FCS Value was 10. This compares to the previous month's value of 10.

Data Source:

Phelps/Fritts (Manager / Source)

Accountability:

Phelps/Fritts Trend:

Positive 6

m Monthly Ernergency AC Power Unavailability Value x

Year.to-Date Ernergency Ac Power UnavailabilityValue 1996 Fort Calhoun Goal (0.024)

[ G000 l Year 2000 lNPO lndustry Goal (0A25) y 0.14..

0.12..

0.1..

O A8..

Oh6..

0.04..

022 0

^

X x

x.

,x,

,x MX 0

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

The Emergency AC Power System unavailability value for November 1996 was 0.005. Dur-ing the month, there were 2.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of planned unavailability, and 3.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> of unplanned unavailability for testing and repairs. The Emergency AC Power System unavailability vslue year-to-date was 0.010 and the value for the last 12 months was 0.014 at the end of the month.

There has been a total of 157.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> of planned unavailability and 3.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> of unplanned unavailability for the emergency AC power system in 1996.

The 1996 Fort Calhoun year-end goal for this indicator is a maximum value of 0.024.

The Year 2000 INPO industry goal is 0.025.

The maximum index point value for this indicator is 10. For the month of November the FCS Value was 9.75. This compares to the previous month's value of 9. 75.

Data Source:

Phelps/Ronning (Manager / Source)

Accountability:

Phelps/Ronning Trend:

Positive 7

t i

n I

g MonthlyThermalPerformance g

i 12-Month Average w_

Year-toeste Average MonthlyThermalPerformance i

e Fort Calhoun Goal (99A%)

l Gooo l

+ Year 2000 INPO lndustry Goal (99.5%)

4 f

100%..

m R

54 E

E

{

E E

T m_ N m M M

M M

?

l b

l 99% --

1996 l

RFO 1

i 98 %

l l

l l

i j

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec l '"' I THERMAL PERFORMANCE i

i 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 1996 INPO j

industry goal and the approximate upper ten percentile value.

i l

The thermal performance value for November 1996 was N/A. The value was not recordable i

due to the 1996 refueling outage. The year-to-date average monthly thermal performance l

l value prior to the RFO was 99.7, at the end of the September. The average monthly value for i

i the 12 months from November 1,1995, through October 31,1996, was 91.41%.

i The 1996 Fort Calhoun year-end goal for this indicator is a minimum of 99.6%. The 1995 Fort Calhoun goal was a minimum of 99.5%. The Year 2000 INPO industry goal is 99.5%.

The maximum index point value for this indicator is 6. For the month of November the FCS Value was N/A. The value for September was 5.19.

Data Source:

Phelps/Naser(Manager / Source)

Accountability:

Phelps/Gorence Trend:

None 8

m FuelReliablilty(E-4)

Year 2000 INPO lndustry Fuel Defect Reference (5 x 10-4 Microcuries/ Gram)

_o._ 1996 Goal (9/1/96 through 12/31/96) 300..

i 280..

257.07 i

l 260 240..

217.6

$ 220..

)

169 159.9 B 160 --

1996 f $::

RFO 3 100..

75.52 73 4 78.42 80.. 55.38 60..

I Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov l1996l FUEL RELIABILITY INDICATOR The FUEL RELIABILITY INDICATOR (FRI) for November 1996 was Not Reportable due to the 1996 RFO. The purpose of the FRi is to monitor industry progress in achieving and maintaining a high level of fuelintegrity. An effective fuelintegrity and performance monitoring program provides a means to detect fuel failures and assess the fuel failure number, physical condition, exposure, mechanism, and location.

The INPO "WANO Performance Indicator Program Utility Data Coordinator Reference Notebook" (INPO No.94-009, Rev.1) states the Industry Goal for fuel reliability is: " units should strive to operate with zero fuel defects". The 1996 Fort Calhoun Station FRI Performance indicator goal is to maintain a monthly FRI below 5.0 x 104 microcuries/ gram. A value larger than 5.0 x 10d microcuries/ gram indicates a high probability of reactor core operation with one or more fuel defects. The 1996 year end goal can be met after the 1996 Refueling Outage See page iii.

The maximum index point value for this indicator is 8. For the month of November the FCS Value was 0. This compares to the previous month's value of 0.0.

Data Source:

Guinn/Guliani Accountability:

Chase /Stafford Trend:

Adverse 9

=. -..... _. _-.

. ~. - - -

l J

g SecondaryBystem CPI j~

+ Fort Calhoun Goal (1 A)

_.o._.12. Month Average lGoool 1.6..

V 1.5..

4

]j 1A--

1.3..

1.2..

^

1996 RFO I

I l

I I

I I

I I

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

SECONDARY SYSTEM CHEMISTRY Criteria for calculating the Secondary System Chemistry Performance Index (CPI) are:

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

1 The CPI for November was not calculated because the power and power rate change crite-j ria was not met during startup from the 1996 RFO. The 12-month average CPI value was l

1.19 at the end of the September.

j l

The Chemistry Performance Index (CPI) was above the goal in July due to slightly higher than average sodium and chloride values. The six chemistry parameters that are used in the CPI calculation have been evaluated against the best industry standards. As a result of this comparison, condensate dissolved oxygen, feedwater copper, and blowdown chloride con-l centrations have been targeted for reduction.

The maximum index point value for this indicator is 7. For the month of November the FCS Value was NIA. This compares to the last computed value (September) of 6.26.

i 3

l D:ta Source:

Spires /Reneaud (Manager / Source)

Accountability:

Spires Trend :

Positive due to performance better than goal 10 J

l m Muthly Persann 1 Radiation ExptsurJ Cumulative Personnel Radiation Exposure o FCS Goal 138 person. REM l 0000 g 1

j 230..

220.

210 4

20; j

t i' J..

j 180..

170..

~

160..

160..

t

=

=

=

=

=

=

=

-e-o 8F 120.

E 110..

E 100..

90..

80.

10..

60..

60..

A E___

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec j 1996 l COLLECTIVE RADIATION EXPOSURE

)

The 1996 Fort Calhoun goal for collective radiation exposure for the year is set at 138.0 person-REM.

The exposure for November 1996 was 81.133 person-Rem (ALNOR).

The year-to-date exposure through the end of November was 228.932 person-Rem (AL-NOR).

This indicator is a " COLLECTIVE" indicator. INPO does not differentiate between on-line and outage exposure.

The Year 2000 INPO industry goal for collective radiation exposure is 120 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 10/93 through 9/96 was 116.78 person-rem per year.

The maximum index point value for this indicator is 8. For the month of November the FCS Value was 5.75. This compares to the previous month's value of 6.8.

Data Source:

Chase /Cartwright (Manager / Source)

Accountability:

Chase /Gebers Trend:

None SEP 54 11

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

.-e-. Year to-Date Cumulative Radioactive Waste Buried l GOOD l

+ Fort Calhoun coal (1050 cu.tt.)

1100.

o

=

c c

c c

=

=

c o

900 800__

]

700__

600

$ 500__

8

)

0 8

6 400..

n ei l

300..

g 8

g 200..

Og 100.

8 R

8 o

o 0

-i

- - - i l - ;

j i

i Jan Feu Mar Apr May Jun Jul Aug sep Oct Nov Dec 1996 VOLUME OF LOW-LEVEL RADIOACTIVE WASTE This indicator shows the volume of the monthly radioactive waste buried, the cumulative year-to-date radioactive waste buried, the Fort Calhoun and INPO goals, and the approxi-mate industry upper 10%.

Cu.Ft.

Amount of solid radwaste shipped off-site for processing during current month 2080 Volume of solid radwaste buried during current month 200.0 Cumulative volume of solid radioac'.ive waste buried in 1996 489.50 Amount of solid radwaste in temporary storage 136.3 The 1996 Fort Calhoun goal for the volume of solid radioactive waste (buried) is 600 cubic f;et. The Year 2000 INPO industry goalis 45 cubic meters (1,589 cubic feet) per year. The industry upper ten percentile value is approximately 27.33 cubic meters (965.3 cubic feet) per year.

This indicator is no longer used by INPO. The indicator will still be tracked, but will no longer be used in computing the Stations Index Number.

Data Source:

Chase /Breuer (Manager / Source)

Accountability:

Chase /Gebers Trend:

None SEP 54 12

l

.,,_ Year-to-Date FCS Industrial Safety) Accident Rate (INPO Definition)

FCS Average Rate 1.ast 12 Months

+ FCS Year-End Goal <0.50) ile (.24) )

_s._ industryCurrent st Qvart ICDODl

,_ Year 2000 INPO Industry Goal(<0.40

,_1995 Industrial Safety Accident Rate (INPO Defination) l I 2..

1.5.-

1..

0.5 -

A -

Ex

=

/

=

=

0 5

7 I

I I

I I

I I

I Dec Jan Feb

'1ar Apr May June July Aug Sep Oct Nov INDUSTRIAL SAFETY ACCIDENT RATE As stated in INPO's December 1993 publication' Detailed Descriptions of World Association of Nuclear Operators (WANO) Performance Indicators and Other Indicators for Use at U.S. Nuclear Power Plants: "The purpose of this indicator is to monitor progress in improving industrial safety perfor-mance for utility personnel permanently assigned to the station."

The Fort Calhoun Station industrial safety accident rate value year-to-date was 0.31 at the end of November 1996. The value for the 12 months nom December 1,1995, through November 30, 1996, was 0.42.

There were no restricted-time and no lost-time accidents in November 1996.

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 1998 Fort Calhoun year-end goal is 50.50. Tne Year 2000 INPO industry goal is 50.40. The approximate industry upper ten percentile value (for the period from 7/93 through 6/94) is 0.12.

The maximum index point value for this indicator is 5. For the month of November the FCS Value was 4.64 This compares to the previous month's value of 4.60.

Data Source:

Sorensen/Skaggs (Manager / Source)

Chase / Booth (Manager / Source)

Accountability:

Chase / Bishop 13

Y l

l 1

1 i

! SAFE OPERATIONS j

Goal: A proactive, self-critical and safety conscious culture is l

exhibited throughout the nuclear organization. Individuals j

demonstrate professionalism through self-ownership and per-i sonalinitiative and open communication.

)

i i

)

i l

I j

14 l

4 l

l 1996 Dmabhng injuryfillness Frequency x._1995 Disabling injury / Illness Frequency

+ Average Rate (Last 12 Months) l GOOD l 1

+ 1996 Goal (0.50) j 2..

Y 1A..

1.6 1A..

1.2 x 1..

i 0J..

'[

1. 1

~

~

~

N I

7

~

04.

0.2.

l 0

Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov l1996l DISABLING INJURY /lLLNESS FREQUENCY RATE (LOST-TIME ACCIDENT RATE) l This indicator shows the 1996 disabling injury / illness frequency rate. The 1995 disabling injury /

illness freqt:ency rate is also shown.

The disabling injury / illness frequency rate year-to-date was 0.47 at the end of November 1996.

There were no disabling injury / illness cases reported for the month.

The disabling injury / illness frequency rate for the 12 months from December 1,1995, through November 30,1996, was 0.43.

The 1996 Fort Calhoun year-end goal for this indicator is a maximum value of 0.5.

Data Source:

Sorensen/Skaggs (Manager / Source)

Accountability:

Chase / Bishop Trend:

Meeting OPPDs Gaol SEP 25,26 & 27 15

i l

,_ 1996 Recordable injury / Illness Frequency

+ 1995 Recordable injuryAliness Frequency I 0000 1 Average Rate (Last 12 Months)

I i

...o...

Fort Calhoun Goal 1.75..

1.5 :

s

.............o.........................................o 1.25..

1 1..

j 0.75..

0.5..

0.25.

0 Dec Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov l1996l RECORDABLE INJURY / ILLNESS FREQUENCY RATE This indicator shows the 1996 recordable injury / illness frequency rate. The 1995 record-able injury / illness cases frequency rate is also shown.

A recordable injury / illness case is reported if personnel from any of the Nuclear Divisions are injured on the job and require corrective medical treatment beyond first aid. The recordable injury / illness cases frequency rate is computed on a year-to-date basis.

There have been 13 recordable injury /illnese cases in 1996. The recordable injury / illness cases frequency rate year-to-date was 2.03 at the end of November 1996. There was 1 recordable injury / illness case reported for the month of November. This injury occured when a worker injured his/her left elbaw while opening the PAL Door..

The recordable injury / illness cases frequency rate for the 12 months from October 1, 1995, through November 31,1996, was 1.85.

The 1996 Fort Calhoun year-end goal for this indicator is a maximum value of 1.5.

Data Source:

Sorensen/Skaggs (Manager / Source)

Accountability:

Bishop Trend:

Needs Management Attention SEP 15,25,26 & 27 16

m Contamination Events (Monthly)

J

._,_ Contamination Events (YrD) 100..

90 __

80 __

70 __

60 _.

50 _.

s2 40..

30 _.

20

~

20 _.

g ts 10..

O M

M E

EM i

i Jan Feb Mar Apr May Jua Jul Aug sep Oct Nov Dec j1996l 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 / minute per probe area for the reporting month.

There were 28 contamination events in November 1996. There has been a total of 80 contamination events in 1996 through the end of November.

Data Source:

Chase /Cartwright (Manager / Source)

Accountability:

Chase /Gebers Trend:

Needs Management Attention SEP 15 & 34 17

\\

j i

e PersonnelErrors (Each Month)

+ Preventable (18-Month Totals) s PersonnelError(18-MonthTotals) 20 15..

10 __

'~W

?=N

E;

'E; 0

i i

l y

May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct l1996l PREVENTABLE / PERSONNEL ERROR LERs This indicator depicts 18-month totals for numbers of " Preventable" and " Personnel Error" LERs.

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

In October 1996, there were six events which were subsequently reported as LERs.

Four LERs were categorized as Preventable or Personnel Error for the month of Octo-ber. The total LERs for the year 1996 (through October 31,1996) is seven. The total Personnel Error LERs for the year 1996 is six. The total Preventable LERs for the year is seven.

Due to the manner in which documentation is closed out, data for this Performance Indi-cator is always one month behind.

The 1996 goal for this indicator is that the year-end values for the 18-month totals be no more than 12 Preventable and 5 Personnel Error LERs.

Data Source:

Tills /Cavanaugh (Manager / Source)

Accountability:

Chase Trend:

None SEP 15 18

l 1

Startup i

Shutdown iGOOD8

)

m Operations l

l

...g...

Industry Average Trend 2..

V

!ii I

1 E

.g

.....a......a......n

...n ;.......

...............n

...e zo j

l l

l c

92 2 92-3 92-4 93-1 93-2 93 3 93-4 94-1 94-2 94-3 94-4 95-1 Year-Quarter i

l i

SAFETY SYSTEM FAILURES This indicator illustrates the number of NRC Safety System Fanures as reported by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data in the biannual" Performance Indica-tors for Operating Commercial Nuclear Power Reactors" reort.

The following safety system failures occurred between the 2nd quarter of 1992 and the 1st quarter of 1995:

1st 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 condi-tions.

2nd Quarter 1993: A section of the piping configuration for the borated water source of the safety injection system was not seismically qualified. This could have resulted in a failure of the system to meet design requirements during a seismic event.

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

1st Quarter 1994: A design basis review determined that an ESF relay could result in loss of safety injection and spray flow, due to premature actuation of recirculation flow.

4th Quarter 1994: An accident scenario was identified that could result in the inoperability of both control room air conditioning units. Following certain accident conditions, CCW temperature could rise causing compressor rupture disc failure and a release of freon.

There were no safety system failures in the 1st quarter of 1995.

Data Source:

Nuclear Regulatory Commission Accountability:

Chase Trend:

Positive 19

m Failures 120 Demands a Failuresl50 Demands e Failures /100 Demands

- -... - Trigger Valuest20 Demands Trigger Valuesl50 Demands E Trigger Values.100 Demands 1I 8 --

7__

6.

5_.

4__

m

.. r.,

2 _ $

3 3

g9 39 3

3 y

o Dec Jan Feb Mar Apr May Jun Jul Aug sep oct Nov l1996l 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 1996 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 manual initiation. Load-run demands must follow successful starts and meet at least one of the following criteria: a load-run that is a result of a real load signal, a load-run test expected to carry the plant's load and duration as stated in the test specifications, and a special test in which a diesel generator was expected to be operated for a minimum of one hour and to be loaded with at least 50% of design load (see exceptions and other demand criteria in the Definitions Section of this report).

Data Source:

Phelps/Ronning (Manager / Source)

Accountability:

Phelps/Ronning Trend:

Positive due to performance better than goal.

20

l l

l DG1 Failures /25 Demands 1

i e DG-2 Failures /25 Demands l Good l l

+ 1996 Goal 5~

V 4-c 3

3.

2.

1 1

1 1

1 1

1 1

1

~

O Dec Jan Feb Mar Apr May Jun Jul Aug sep oct Nov 1996 l

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 1996.

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 zero failures during the last year, and zero failures during the last 25 demands on the unit. Diesel Generator DG-2 has experienced zero failures during the last 25 demands on the unit.

Data Source:

Phelps/Ronning (Manager / Source)

Accountability:

Phelps/Ronning Trend:

Positive due to performance better than goal.

I l

l 21

DG 1 UnreliabilityValue DG-2 UnreliabilityValue

+ Station UnrellabilityValue lMl O A7..

Y OD6 04S.

c

~

OD4..

0.03.

0.0:e 0.02..

0.01.. 0 0

0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

0 8

Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov l1996l EMERGENCY DIESEL GENERATOR UNRELIABILITY The purpose of this indicator is to monitor the likelihood that emergency AC power generators will respond to off-normal events or accidents. It also provides an indication of the effectiveness of maintenance, op s.

tion and test practices in controlling generator unreliability. The last event occured on September 1,1995 i

when the Field Flash Relay on DG-2 failed.

The year-to-date station EDG unreliability at the end of November 1996 was 0.0. The 1996 goal for this i

indicator is a maximum value of 0.05.

For DG-1:

There were 5 start demands for the reporting month with 0 failures.

in addition, there were 3 load-run demands without a failure.

]

For DG-2:

There were 11 start demands for the reporting month with 0 failures.

)

In addition, there were 4 load-run demand without a failure.

Emergency diesel generator unreliability is calculated as follows:

value per DG = SU + LU -(SU x LU) where SU e Start Unreliability

= number of unsuccessful starts number of valid start demands LU = Load-run Unreliability = number of unsuccessfulload-runs number of valid load-run demands Station Value = average of DG-1 and DG-2 values Data Sotree:

Phelps/Ronning (Manager / Source)

Accountability:

Phelps/Ronning Trend:

Positive due to performance better than goal.

22

I j

m control Room Deficiencies Added

, Controf Room Derciencies Completed e Completed within Target Completion Date Compietion Rate t

90..

. 100.0%

a Goal.Corrplate80%of C R.Dermances byTarget CorrpletionDate 88 80..

A

] 70 _

80.0% y

....s o

5 60.. a n.s

.. 60 ')% y l

8.7 y

> s4.o 6 o 40..

]

y 4

4.. 40.0% }

$ 30..

27 88.0%

E 24 Apr May Jun Jul Aug Sep Oct Nov ControlRoorn Derciencies j

l i

NUMBER OF CONTROL ROOM EQUIPMENT DEFICIENCIES 1

This indicator measures the timeliness of closing Control Room Deficiencies.

Target Completion Dates are established by the Emergent Work Committee. The goalis to close at least 80% of all CRDs within the Target Due Date.

There were 86 Control Room Deficiencies completed during November 1996, and 34 were completed within the target completion date.

1 i

A Scheduling Coordinator has been assigned to track performance on a weekly basis and identify problem areas. Revisions have oeen made to the scheduling process to allow for i

more timely completion of CRDs.

Due to a new tracking system initiated in July / August, data for August 1996 was not avail-able.

i i

Data Source:

Chase /Kermoade (Manager / Source)

Accountability:

Short/Faulhaber Trend:

None 23

No Data Provided NUMBER OF ON-LINE AND OUTAGE CONTROL ROOM DEFICIENCIES This indicator shows the total number of On-Line and Outage Control Room Deficiencies, and the number of overdue Control Room Deficiencies.

No data was available for the month of November.

The 1996 Fort Calhoun goal for these indicators are less than 8 overdue on-line and no overdue outago Control Room Deficiencies.

Data for August was not available.

Data Source:

Chase /Kermoade (Manager / Source)

Accountabil:ty:

Short/F aulhaber/ Herman Trend:

None i

24

g Hghest Manthly hdivdual E:xposure rnR(1995) a Year-to-date

+ Fort Calhoun Goal 1'AknR 1500 1400.

1300.

1200.

1100.

1000.

900.

800.

700.

600.

500.

400.

300.

200.

100.. E O

Jan Feb Mar Apr Wy Jun Jul Aug Sep Oct tbv Dec j

MAXIMUM INDIVIDUAL RADIATION EXPOSURE For the month of November 1996, an individual accumulated 1.415 Rem, which was the i

highest individual exposure for the month.

From January 1996, through November 1996, an individual has accumulated a total of 1.475 Rem.

l l

The OPPD limit for the maximum yearly individual radiation exposure is 4,000 mrem /

year. The 1996 Fort Calhoun year-end goalis a maximum of 1,500 mrem.

Data Source:

Chase /Cartwright (Manager / Source)

Accountability:

Chase /Gebers Trend:

None 4

25 I

a m FC5 cited Violations (Monthly) a FCS Non41ted Violations (Monthly) c FCS Cited Violations (12-Month Average) l GOOD l e

FCS Non Cited Violations (12-Month Average)

+ Region IV Cited Violations (12-Month Average for Region IV top quartile) lI 10..

8..

N E

C c

c a

W

• N 6..

4..

c c

c c

o 2"

o num

, sus U, uns

,E:

E1, e

e

=

t e

s e

e z

i;

)

5 m

z s

4 m

o z

1996 VIOLATION TREND This indicater il!ustrates a 12-month trend for Fort Calhoun Station Cited Violations, Non-Cited Violations and Cited Violations for the Top Quartile plants in Region IV. Additionally, the Fort Calhoun Station cited and non-cited violations for the past 12 months will be illustrated monthly. The 12-month trend for the Region IV top quartile iags 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 November 1996:

IER No.

Title 96-12 ISI/ Maintenance 96-14 Resident Monthly inspection 96-15 L/O Requalification & C.R. Observation l

To date, OPPD has received fifteen violations for inspections conducted in 1996.

Levellli Violations 1

LevelIV Violations 9

Non-Cited Violations

_5 Total 15 The 1996 Fort Calhoun Station Goal for this performance indicator is to be at or below the cited violation trend for the top quartile plant in Region IV.

Data Source:

Tills /Cavanaug. sianager/ Source)

Accountability:

Tills Trend:

None 26

NRC 5ignificant Events I

,__ industry Average Trend l

l GOOD [

1 i

1 -.

3 r 0.5 --

0 0

0 m

r l

l 92 93 94 95-1 95-2 95 3 95-4 96-1 96-2 96-3 96-4 l Year -Quarter [

INPO Significant Events (SEs) lG000g 3

- 2 2

1 1

y 5

5, 0

i i

92 93 94 95-1 95-2 95-3 95-4 96 1 96-2 96 3 96-4 l Year-Quarter l SIGNIFICANT EVENTS NRC SIGNIFICANT EVENTS The following SEs were identified between the 2nd Quarter of 1992 and the 1st quarter of 1995 (as reported in the NRC's

• Performance Indicators for Operating Nuclear Power Reactors' report dated June 30,1995):

3rd Quarter 1992:

The failure of a Pressurizer Code Safety Valve to resent initiated a LOCA with the potential to degrade the reactor coolant pressure boundary.

4th Quarter 1994:

A potential accident scenario involving a large break LOCA or a main steam line break inside containment could result in the inoperability of both control room AC. units.

INPO SIGNIFICANT EVENTS The following SEs have been identified since 2nd Quarter of 1992 by INPO:

2nd Quarter 1992:

Intake of transuranics during letdown filter change-out.

3rd Quarter 1992:

Safety Valve malfunction (RC-142).

1st Quarter 1993:

Inoperability of Power Range Nuclear Instrumentation Safety Channel D.

2nd Quarter 1993:

Inadequate control of Switchyard activities.

3rd Quarter 1993:

Loss of reactor coolant due to malfunction of Pressurizer Safety Valve.

1st Quarter 1994:

1)

Unexpected CEA withdrawal. (Event occurred November 13,1993 but was not identified as an SE until 1st Quarter 1994).

2)

Unplanned dilution of Boron concentration in the Reactor Coolant System.

1st Quarter 1996:

During pressurizer solid plant operation, the Low Temperature Overpressurization (LTOP) protection for the RCS was inadvertently disabled.

2nd Quarter 1996:

RC Pump Anti-Reverse Rotation Device (ARD) failure No SE reports have been received from INPO on the 1996 SEs as of August 1, 1996.

Data Source:

Nuclear Regulatory Commission & INPO Accountability:

Chase Trend:

Positive 27

l Missed sTs Resuking in LERs iy 2..

1 1..

0 0

0 0

0 0

0 0

0 0

0 0

0 0

93 94 95 Jan Feb Mar Apr May Jun Jul Aug sep oct Nov Dec 4

1996 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.

There were no missed surveillance tests resulting in LERs during November 1996.

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

j The 1996 Fort Calhoun monthly goal for this indicator is 0.

Data Source:

Monthly Operating Report & Plant Licensee Event Reports (LERs)

Accountability:

Chase /Phelps Trend :

Positive SEP 60 & 61 28

i i

8 i

i i

PERFORMANCE i

l i

l Goal: To strive for Excellence in Operations utilizing the high-j est standards of performance at Fort Calhoun Station that l

result in safe, reliable plant operation in power production.

4 l

\\

4 4

i 29 i

i I

1

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

~

.-~.-.--~-~---.=.-~.-a-l l

Net GerHration (10,000 MWh) l 40 1

36.27 35.23 35.85 l

34.55 34.84 34.81 33.85 i

i So.0s 30..

l M lal.

i e

o uta ge

~

1996 20.1s RFo p

l20 "

Ou t*9

• 18.s4 i

5

]

9.74s 10..

j 0

j j

i i

i i

j l

[

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

)

1996 j

i i

i STATION NET GENERATION During the month of November 1996, a net total of 9746.3 MWh was generated by the l

Fort Calhoun Station. Cumulative net generation for Cycle 16 was 5,418,326.6 MWh.

Cumulative ne generation for Cycle 17 was 9746.3 MWh at the end of the month.

I Energy losses for June 1996 were attributed to a failure of the Anti-Rotation Device (ARD) associated with Reactor Coolant Pump Motor RC-38.

l Energy losses for March 1996 were attributed to (1) a planned mini-outage, and (2) con-j denser tube leakage repair.

j.

Energy losses for August 1995 were attributed to a plant trip during testing of a backup automatic shutdown system, which began on August 24th. The generator was brought j

back on-line at 3:43 p.m. on Saturday, August 26th, after a two-day outage.

i Data Source:

Station Generation Report i

Accountability:

Chase

[

Trend:

None 30 4

b i

, Forced Outage Rate (Monthly)

+ Forced Outage Rate (12 Months) l Good l

_e._1996 Fort calhoun Goal (1.4%)

50%..

y 45%..

40%..

I 35%..

30%..

25%..

20%..

15%..

10%..

5%..

3.sts

,\\, /

1.s ss... yg e

)

0%

f""1

",~; -

~

93 94 95 Dec Jan Feb Mar Apr May Jun Jul Aug sep oct Nov 1996 FORCED OUTAGE RATE The forced outage rate (FOR) was reported as 5.0% for the twelve months from October 1,1995, through November 30,1996. The 1996 year-to-date FOR was 5.90% at the end of the month.

Energy Losses are explained on Page 30.

The 1996 Fort Calhoun year-end goal for this indicator is a maximum value of 1.4%.

Date Source:

Monthly Operating Report Accountability:

Chase Trend:

None 31

~

, Monthly Unit Capacity Factor i

...s...

YearMate Unit Capacity Factor g

e Unit Capacity Factor for Cycles 15 & 16 f,

36-Month Average Unit Capacity Factor

( Good l 110%..

1996 FCs Goal (81.49%)

100 % _.-

,-e-

.....a....,,,,,,,,,

• A

+

l rN, 70%_.

60%..

50%..

40%.

30%._

20%.-

10%..

0%

l rm Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov 1996 UNIT CAPACITY FACTOR This indicator shows the plant monthly Unit Capacity Factor, the Unit Capacity Factor for the current fuel cycle, year-to-date and the 36-month average Unit Capacity Factor.

At the end of the month, the Cycle 18 Unit Capacity factor was 85.23%, and the Unit Capacity i

Factor for the last 36 months was 85.17%. The 1996 Fort Calhoun annual goal for this indicator is 82.00%.

The year-to-date value is 74.84%.

Energy losses are explained on Page 2.

The Unit Capacity Factor is computed as follows:

l Net Electrical Enerov Generated (MWH)

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

Monthly Operating Report Accountability:

Chase Trend:

None 32

.~

. _ - = - - - _ -

. MonthlyEAF e__ Year-tocate Average Monthly EAF

+ 12-Month Average EAF

1. industry Median Value (76.7% for a 3-Year Average) 100%..

s r.as r

n e s.s s A

\\

d-*

r 80%

i x

x x

x x

x r

=

60% [

i 40%..

20%..

1996 RFO 0%

j n

92 93 94 95 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Ncre 1996 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 November 1996 was reported as 3.07%. The year-to-date monthly average EAF was 70.6% at the end of the month.

The Fort Calhoun average monthly EAF for the past three years is 85.08%. The industry median EAF value for the three-year period from 7/90 through 6/93 was 76.7%.

Data Source:

DietzNandervort (Manager / Source)

Accountability:

Chase Trend:

None 33

j Sefety System Actuations (INPo Definition)

--o FCS Goal (0) l

+ Industryupper10 Percentile (0) 3 _.

2_.

1 1

1 1_.

t 0

0 0

0 0

0 0

0 0

0 0

0 0

i e

e e

92 93 94 95 Jan Feb Mar Apr May Jun Jul Aug Sep oct Nov 1

96 UNPLANNED SAFETY SYSTEM ACTUATIONS -(INPO DEFINITION)

{

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

There was one unplanned safety system actuation during the month of August 1995. It occurred on August 24,1995, when the plant was tripped during a test of a backup auto-matic shutdown system. The generator was brought back on-line at 3:43 p.m. on August 26th, after a two-day outage.

In February 1994, a reactor trip occurred as a result of an inadvertent ESF actuation. A short in the 86B/CHPS associated supervisory relay energized the 86B/CPHS lockout which initiated a SGIS Safeguards signal. As a result, the MSIVs closed which caused a simultaneous turbine and reactor trip.

The 1^9G Fui Calnoun goal for this indicator is 0.

Data Source:

Monthly Operating Report & Plant Licensee Event Reports Accountability:

Phelps/Foley/Ronning Trend:

Positive 34

m Safety System Actuations (NRC Definltion)

, FcS Goal (0) i

+ CriticalHours 12 Month Running Total sSAs (NRc Definition) 10..

. 800 cym unamme 8..

ouisse

..600 E

500 6..

4 s

E

.400 :E 4

1

~

_ 300 3

i*

2.

..200 100 0

l

,_:=l

=

0 92 93 94 95 O N D J FMAMJJASONDJFMAMJJASON l

l1994l l1995l "T W 6-I 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 rnajor equipment is operated and when the logic systems for these safety systems are challenged.

An unplanned safety system actuation occurred in December 1993 when the main turbine and reactor tripped during Electro-Hydraulic Control pump start testing. Also, there was an unplanned SSA during the month of February 1994 when supervisory relay 86B/CPHSS failed, which resulted in a concurrent turbine and reactor trip.

There have been no u panned safety system actuations in the last 12 months. The 1996 Fort Calhoun goal for this indicator is 0.

Data Source:

Monthly Operating Report & Plant Licensee Event Reports (LERs)

Accountability:

Phelps/Foley/Ronning Trend:

None 35

4 m Gross Heat Rate

• + Year.to-Date Gross Heat Rate l GOOD l Fort Calhoun Goal 14.75..

I I 14.25..

j 13.75.

I 13.25..

j 12.75..

11 5

)

g 12.25..

i m

11.75..

I

" 11.25..

10.75..

10.25.. " ' "

• 2' MN mm 9.75..

j 9.25 I

92 93 94 95 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov 1996 i

i j

l GROSS HEAT RATE This indicator shows the Gross Heat Rate (GHR) for the reporting month, the year-to-date j

GHR, the goals and the year-end GHR for the previous three years.

The gross heat rate for Fort Calhoun Station was 16,549 for the month of November 1996. The 1996 year-to-date GHR was 10,225 at the end of the month.

1 l

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

Fahrenheit.

j The 1996 Fort Calhoun year-end goal for this indicator is 10,166.

Data Source:

Guinn/Willett (Manager / Source) i Accountability:

Chase /Skiles Trend:

None 36 i

4

e

+ Thermaloutput

+ Fort Calhoun 1495 MW Goal

+ Tech Spec 1500 MW Limit 1600..

1400..

1200..

1000..

f800" 1996 RFO 4

600..

i 400..

200..

.. m Os 1 234 5678 9 101112131415161718192021222324252627282930 DAILY THERMAL OUTPUT The thermal output graph displays the daily operating power level during November 1996, the 1500 thermal megawatt average technical specification limit, and the 1495 thermal megawatt Fort Calhoun goal.

Data Source:

Guinn/Willett (Manager / Source)

Accountability:

Chase /Short Trend:

None 37

+ Numbar sf Equipmm.t Faraud Outtga (Mas.thly) l GOOD l

+ Equipment Forced Outage Rate /1,000 Critical Hrs.(12 Month Interval)

Fort Calhoun Year-End Goals (0.2) 37 2.

1..

C

^

0 0

0 0

5 b

b e

0 93 94 95 Jan Feb M ar Apr May Jun J'u l Aug Sep Oct NEv Dec EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS The equipment forced outage rate per 1,000 critical hours for the 12 months from Decem-ber 1,1995, through November 30,1996, was 0.286. The year-to-date rate per 1,000 critical hours for the months from January 1996 through November 1996 was 0.320.

An equipment forced outage occured during the month of June due to the failure of the Anti-Rotation Device associated with RC-3B-M.

An oquipment forced outage occured at the end of the March due to condenser tube leakage.

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

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

The 1996 Fort Calhoun year-end goal for this indicator is a maximum value of 0.20.

Data Source:

Monthly Operating Report & Plant Licensee Event Reports (LERs)

Accontability:

Chase /Phelps Trend:

Needs increased Management Attention 38 l

l l

l

=+== WW=$ W y

+

18.

~~

16.

E l

/

W 10

~

g..

j6 5

[

[

~

~

y j

4.

2.

o J

A 5

0 N

D J-96 F

M A

M J

J A

S O

N A ge/N o rma10s e 80.7 %

P rocedure Error 16%

initial las tallatio n I

18%

Testing Action 4.9%

Maintenance Def et A ction 18%

18.4 %

Engineering /D esign 16%

COMPONENT FAILURE ANALYSIS REPORT (CFAR)

SUMMARY

The top chart illustrates the number of component categories, application categories and total categories in which the Fort Calhoun Station has significantly higher (1.645 standard deviations) failure rates than the industry failure rates during the past 18-month Component Failure Analysis Report (CFAR) reporting period (from February 1995 through July 1996). Fort Calhoun Station reported a higher failure rate in 6 of the 83 component categories (valves, pumps, motors, etc.)

during the past 18-month CFAR period. The station reported a higher failure rate in 9 of the 174 application categories (main steam stop valves, auxiliary / emergency feedwater pumps, control element drive motors, etc.) during the past 18-month CFAR period.

The p e chart depicts the breakdown by INPO cause categories (see the " Definitions" section of this report for descriptions of these categories) for the 61 failure reports (failure discovery dates within the 18-month CFAR period) with known failure causes that were submitted to INPO by Fort Calhoun Station. A total of 89 failure reports were submitted to INPO with discovery dates within the 18-month CFAR period.

Data Source:

Phelps/ Frank (Manager / Source)

Accountability:

Phelps/ Dowdy Trend:

None 39

e CImpo;;cnts with more than One Failure

-w_

Components with more than Two Failures l

l 15..

)

10 -.

10 M

j i

l 7

7 5

f f/

3 3

3 3

?

?

b, b.

1 7

Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov REPEAT FAILURES The Repeat Failures indicator (formerfy called the " Maintenance Effectiveness Performance Indicator") was dIveloped in response to guidelines set forth by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (NRC/AEOD). The NRC requirement for a Maintenance Effectiveness Performance Indicator has been discontinued, 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 reportable components with more than one failure during the 18-month Component Failure Analysis Report (CFAR) period (failure discovery dates from Fcbruary 1995 through July 1996) and the number of NPRDS reportable components with more than two failures during the 18-month CFAR period.

Durir g the last 18-month CFAR period, there were 10 NPRDS components with more than one failure.

Three out of these 10 NPRDS reportable components had more than two failures. Recommendations and cctions to correct these repeat failures are listed in the Biannual CFAR. The description and tag numbers of the NPRDS reportable components with more than one failure are listed below:

IA-HCV-2987-BP Air Intensifier for HPSI Pump SI-2C Discharge Isolation Valve

(> 2 Failures)

IA-HCV-2918-BP Air Intensifier for HPSI Altemate Header IsolationValve.

RC-10-08 Contro! Element Drive Mechanism RC-3D-M Reactor Coolant Pump Motor a

V/P-402C Valve Positioner for Cont. Cooling Coil VA-8A CCW Outlet Valve a

V/P-403C (> Two Failures)

Valve Positioner for Cont. Cooling Coil VA-8B CCW Outlet Valve a

FW-56 (> Two Failures)

Auxiliary Feedwater Pump FW-56 Diesel Engine a

HCV-1106-0 Valve Operator for SG RC-2B Feed Regulation Bypass Valve YE-116A QSPDS Heated Junction Thermocouple Probe for Reactor Vessel RC-1 it$3B-4 AC-3A Circuit Breaker 4

Data Source:

Phelps/ Frank (Manager / Source)

Accountability:

Chase Trend:

None 40

CHEMISTRY ACTION LEVELS EXCEEDED man, bent Days + Average bent Deys + Lsnt l 6.

5.

s 4.

8 g

3.

$2.

g p

L e

y rer i ris :

e r

fs a

s k

k s

a a

a s

MowrH j

CHEMISTRY ACTION LEVELS EXCEEDED - EVENT DAYS The Chemistry Action Levels E::ceeded indicator tracks the number of days in which chemistry parameters exceeded a corresponding action level for the reporting month, as well as a 12-month average of days an actiors levelis exceeded. Tue parameter action levels are delineated in Chem-istry procedure CH-AD-0003, Plant System Chemical Limits and Corrective Actions.

An action level is considered to have been exceeded for the purpose of this indicator, whenever the parameter exceeds the CH-AD-0003 action level for the current system mode, with the excep-tion of the Steam Generators during Mode 1.

The Steam Generators are considered to have exceeded an action levelin Mode 1 when the plant power is greater than 30% and the power is changing less than 5% per day.

The number of event days can exceed the number of days in a month since each event is counted separately and there can be multiple events per day.

The 1996 Fort Calhoun goal for this indicator is the 12-month average of two event days per mohth. There is no goal established for the number of event days per individual month.

Historical data is used to calculate the monthly average event days. The 12-month average was calculated by dividing the number of event days by the number of preceding months, until twelve monihs were reached.

The ECN to the chemical feed system has been completed. There have been no action levels exceeded due to the chemical feed system since the ECN has been completed.

Data Source:

Chase / Spires Accountability:

Spires Trend:

None

I 12.00 11.00 E

10 2 uoai 9.00 E

8.00 E

g 7.00 E

E 6.00 E

E h

5.00 M

M 4.00 M

M M

3.00 S

S S

S S

S 2.00 1.00 S

U M

0.00 S

U

=

M E

Jan Feb Mar Apr May Jun Jd Aug Sep oct tbv 1996 PRIMARY SYSTEM LITHlUM % HOURS OUT OF LIMIT The Primary System Lithium Percent Hours Out of Limit indicator tracks the hours per month that the primary system lithium is out of specification.

The Primary System Lithium Percent Hours Out of Limit was 12.00% for the month of November 1996. Lithium exceeded its limits for 89.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> during the month.

Lithium was out of specification due to boron concentration changes during plant startup l

followint the 1996 RFO.

The 1996 Fort Calhoun monthly goal for this indicator is a maximum of 5% hours out of limit Data Source:

Chase / Spires (Manager / Source)

Accountability:

Spires Trend:

None 42

i I

,1 i

I i

i I

i I

t i

COST i

4 i

j l

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

4 d

2 43

?

l

-.+- Actual Revised Budget l

Original Budget Plan 4.0 0..

3.75..

3.50..

3.25.

2 3.00 j.

l 5

u 2.75..

2JO..

2.25..

2.00 D91 D92 D93 D94 D95 J96 F O.

A M J

J A

8 O

N D D96 D97 D98 D99 Months CENTS PER KILOWATT HOUR The purpose of this indicator is to quantify the economical operation of Fort Calhoun Station.

The cents per kilowatt hour indicator represents the budget and actual cents per kilowatt hour on a 12-month rolling average for the current year. The basis for the budget curve is the approved 1995 and 1996 revised budgets. The basis for the actual curve is the Financial and Operating Report.

The December 31 amounts are also shown for the prior years 1991 through 1995. In addition, the report shows the plan amounts for the years 1997 through 2000 for refer-ence. The basis for the dollars are the Nuclear Long Range Financial Plan and the 1996 Corporate Planning and Budget Review. The basis for the generation is provided by Nuclear Fuels.

The 12-month rolling average unit price (period of September,1995 through October, 1996) averaged over budget due to 12-month rolling expenses meeting the budget ex-pectations, but the 12-month rolling generation not meeting the budget expectations. The 12-month rolling average (08/95 through 09/96) is 2.79 cents per kilowatt hour.

The year-to-date average is trending negatively.

Cents per KWH Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Budget Y-T-D 2.79 2.84 2.85 2.81 2.82 2.76 2.73 2.75 2.80 2.97 3.12 3.12 Actual Y-T-D 2.91 2.77 2.96 2.94 2.83 2.98 2.91 2.85 2.84 2.98 l

Data Source:

Lounsberry/ Dent (Manager / Source)

Accountability:

Lounsberry Trend:

Needs Management Attention 44

l i

1

,_. Spare Parts inventoryValue ($ M!tlico) 16.30..

16.10..

15.90 i

15.70..

5

% 15.50..

O o

E 8 15.30..

i 15.10..

i 14.90..

14.70..

14.50 1

Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov 1996 SPARE PARTS INVENTORY The spare parts inventory value at the Fort Calhoun Station at the end of November 1996 was reported as $14,956,618.

Data Source:

Steele/Huliska (Manager / Source)

Accountability:

Willrett/McCormick Trend:

None 45

I i

4 l

l l

l l

i DIVISION AND l

DEPARTMENT a

l PERFORMANCE i

l INDICATORS i

Goal: Achieve high standards at Fort Calhoun Station resulting in safe, reliable and cost effective power pro-duction.

i k

i l

i i

i l'

i 46 1

4 4

Gorrective Maintenance Preventive Maintenance 1

m Non-Corrective /Plantimprovements e

FortCalheunGoal i

1000 "

782 830 870 730 l

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

l1995l l mge Maintenance Work Order Backlog l l1996l MWOs Past co p uon g Total MWos l III I

I o

Priorty Priorty Priorty Priarty Priorty 1

2 3

4 5

MAINTENANCE WORKLOAD BACKLOG 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 1996 goal for this indicator is 400 non-outage corrective maintenance MWOs. The current backlog of corrective MWOs is 440. To ensure that the MWO backlog is worked in a timely manner, non-outage maintenance completion goals have been established as follows:

Goal Priority 1 Immediate Action 2 days Priority 2 Urgent 5 days Priority 3 Operational Concems 21 days Priority 4 Routine Corrective 90 days Priority 5 Non-Essential 180 days Data Source:

Chase /Schmitz (Manager / Source)

Accountability:

Chase /Faulhaber Trend:

Adverse SEP 36 47

r Ratio of Preventive to Total Maintenance 90%..

80%

I 70%..

i 60%..

50%..

40%~..

j nu

[

j i

i i

i i _.

i.

i i

i

{

{

Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov l1996l l

g Preventive Maintenance items Overdue

+ Fort Calhoun Goal 3%.

V 2%..

1%..

0%

E E

i i

i

.i i

... t -

-- f ---

1 i

i l

"'P l

Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov l1996l RATIO OF PREVENTIVE TO TOTAL MAINTENANCE PREVENTIVE MAINTENANCE ITEMS OVERDUE The top graph shows the ratio of completed non-outage preventive maintenance to total com-pleted non-outage maintenance. The ratio was 70.67% for the month of November 1996.

The lower graph shows the percentage of scheduled preventive maintenance items that are overdue. During November 1996,1638 PM items were ccmplet'.ed.

The 1996 Fort Calhoun monthly goal for the percentage of preventive ma5tonance items over-due is a maximum of 0.5%.

Data Source:

Chase /Schmitz/Meistad (Manager / Sources)

Accountability:

Chase /Faulhaber Trend:

Adverse SEP 41 & 44 48

. _ _.. - ~. -

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

e m Rewerk as idsstifud by Craft

+ Port Calhoun Ocel(+ 3%)

?'

5 %..

.sg 4%..

s.e s y

s.f s 1

3%.

8-S 5,

2%.-

1.s s g.s g t.a s 1%..

3,o g 3,g g 8.8 s as Des Jan Fe b Mar Apr May Jun J ul Aug Sep Oct New m No. Maintenance items Competed

+% identfied as Repeat 700 0

8.0%

600.

~

526 500.

. 6.0 %

400.

355

~

ggg

. 4.0%

\\217.

220 214 207 3.0 %

200 Dec Jan Feb Mar A pr May Jun Jul A ug Sep Oct Nov PERCENTAGE OF TOTAL MWOs COMPLETED PER MONTH IDENTIFIED AS REWORK / REPEAT This graph indicates the percentage of total MWOs completed per month identified as rework. Rework activities are identified by maintenance planning and craft.

This indicator is calculated from the 15th of July to the 15th af August, due to the delay in closing open MWOs at the end of each month.

The Fort Calhoun monthly goal for this indicatoris <3%. A detailed review is conducted of rework items each month to identify generic concerns.

Data Source:

Faulhaber/Schmitz (Manager / Source)

Accountability:

Chase /Faulhaber Trend:

None 49

_ _ _ _.. _ _ _ _ ~ _ _ _.. _. _.... _ ~

..__._________.____________.._____..___m.

g Maintenance overtune

1. 12-Mcnnh Average Maintenance Overtime lG0001 j

+ Fort Calhoun "On-l.ine" Goal (10Y4 L___

l I

45%.

i V

1 40%.

35%._

O MINI-OUTAGE j

30%..

1 ARD OUTAGE l

20%._

15%.

j 10%.-

o i

I i

I i

i I

i i

I l

l I

Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov l1996l 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 43% for the month of November 1996. The 12-month average percentage of overtime hours with respect to normal hours was reported as 16.0 % at the end of the month.

High overtime due to the 1996 RFO.

The 1996 Fort Calhoun monthly "on-line" goal for this indicator is a maximum value of 10%.

Data Source:

Chase /Schmitz (Manager / Source)

Accountability:

Chase /Faulhaber Trend:

None 50 a

....... ~.. -....

j l

l l

Human Performance CRs(Maintenance) 20..

i i

18..

i e

l 16..

i 14..

h g 12..

I i

ag 10..

o o

j 8

6 6..

5 n

i i

i i

i l

May Jun Jul Aug Sep Oct Nov PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)

This indicator shows the number of Condition Reports related to procedural noncompli-ance incidents assigned to the Maintenance Department.

1 Data Source:

Faulhaber Accountability:

Chase /Faulhaber Trend:

None SEP 15,41 & 44 51

i DATA IS AVAILABLE ON-LINE VIA NUCLEAR NEWS NETWORK DAILY SCHEDULE PERFORMANCE PERCENT OF SCHEDULED ACTIVITIES COMPLETED This indicator shows the percent of Integrated Plant Schedule activities completed on schedule. All work groups and activities are included.

The percent of emergent work is calculated as a percentage of the total number of sched-uled and emergent activities.

The 1996 Fort Calhoun monthly goal for completed scheduled maintenance activities is 85%.

NOTE:

Statistics from the June RC-3B Outage were not included in these numbers.

Statistics from the weeks of June 10 and June 17 were not kept.

I Data Source:

Chase /Schmitz (Manager / Source)

Accountability:

Chase /Faulhaber Trend:

None SEP 33 52

__m l

ggg % of Hours the in-Line Chemistry instruments are Inoperable GOOD

+ 1996 Fort Calhoun Goal (10%)

iV 11%..

9%

I,ji 6%..

i i

j i

i j

i Dec Jan Feb Mar Apr May Jun Jul Aug sep oct Nov l1996l IN-LINE CHEMISTRY INSTRUMENTS OUT-OF-SERVICE This indicator shows the percentage of hours the in-line chemistry system instruments are inoperable for the reporting month. The chemistry systems involved in this indicator include the Secondary System and the Post Accident Sampling System (PASS).

At the end of November 1996, the percentage of hours the in-line chemistry system instruments were inoperable was 3.45%. The following instruments were out of service for the entire month of November 1996:

PHE-6775 CPD pH YE-6776 CPD Dissolved Oxygen The entire instrument channel is considered inoperative if: 1) the instrument is inopera-tive, 2) the chart recorder associated with the instrument is inoperative, or 3) the alarm function associated with the instrument is inoperative. If any of the functions listed above are not operational, then the instrument is not performing its intended function.

Data Source:

Chase /Reneaud (Managely3ource)

Accountability:

Chase /Skiles Trend:

Positive - Better than OPPD Goal 33

a m Waste Produced Each Month (Kilograms)

, e Monthly Average Waste Produced During the last12 Months (Kilograms)

Fort Calhoun Monthly Average Goal (150 kilograms)

+ Federal & State MonthlyLimit(Max.of1,000 kg) 1000 :

=

x x

x x

x y

y 7,

800 600 l

e E

1 400.

J 200..

e r

o 07

?

?

2

?

?

?

Dec Jan Feb Mar

_ Apr May Jun Jul Aug Sep Oct Nov l1995 l HAZARDOUS WASTE PRODUCED This indicator shows the total amount of hazardous waste produced by the Fort Calhoun Station each month, the monthly average goal and the monthly average total for hazard-ous waste produced during the last 12 months. This hazardous waste consists of non-halogenated hazardous waste, halogenated hazardous waste, and other hazardous waste produced.

During the month of November 1996,0.0 kilograms of non-halogenated,0.0 kilograms of halogenated and 0.0 kilograms of other hazardous waste was produced. The total haz-crdous waste produced during the last 12 rionths is 191.1 kilograms.

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

The 1996 Fort Calhoun monthly average goal for hazardous waste produced is a maxi-mum of 150 kilograms.

Data Source:

Chase /Shubert (Manager / Source)

Accountability:

Chase / Spires Trend:

Positive

!e

__m.__,

m Contaminated Radittion Controlled Area l000Dl o__ Fort Calhoun Goal (10%)

l I 10%..

e 3

^

I 9%..

i 85

...g....

y

_.g p

..g..

,9

_.y._

._j _

q_

.,, g _,

., g Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov N

CONTAMINATED RADIATION CONTROLLED AREA This indicator shows the percentage of the Radiologically Controlled Area that is contami-j nated based on the total square footage. The 1996 monthly non-outage goal is a maxi-mum of 10.0% contaminated RCA.

3 At the end of November 96, the percentage of the total square footage of the RCA that was contaminated was 8.4%.

Data Source:

Chase /Gundal(Manager / Source)

Accountability:

Chase /Gebers Trend:

None SEP54 55 j

+

IdentNied PRWPs(YTD)

Fort Calhoun Goal (<15) 16 14.

12 12 12.

10.

8.

6 6.

3 4

4.

2.

l o:

Jan Feb hr Apr hy June July Aug Sep oct ibv Dec i

4 RADIOLOGICAL WORK PRACTICES PROGRAM The Radiological Work Practices Program Indicator shows the number of Poor Radiologi-cal Work Practices (PRWPs) which were identified during the reporting month.

The number of PRWPs which are identified each month should indirectly provide a mains to qualitatively assess supervisor accountability for theirworkers' radiological perfon w ice.

During the month of November 1996, there were O PRWP identified.

There have been 12 PRWPs in 1996.

l The 1996 year-end goal for PRWPs is a maximum of 15.

D.ata Source:

Chase /Cartwright (Manager / Source)

Accountability:

Chase /Gebers Trend:

None SEP52 56

~ -

O Documents Scheduled for Review g Documents Reviewed g Documents Overdue 400..

350 300..

250..

200..

150..

100.

50..

0.__ E+_

K+. _

E+_ E+_ E+_ E+_

+_

+

l_

+_

+_

y Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov 1996 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 November 1996, there were 380 document reviews scheduled, while 33 reviews were completed. At the end of the month, there were 33 document reviews more than 6 months overdue. There were 9 new documents initiated during November 1996. Begin-ning in September 1995, these figures include PED and NOD procedures.

Data Source:

Chase /Plath Accountability:

Chase /Skiles Trend:

None SEP 46 57

.. ___.~

e e

i g System Failures l GOOD l 0 Non-System Failures 30 Y

26..

22 22 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov LOGGABLEIREPORTABLE INCIDENTS (SECURITY)

This graph shows the Loggable/ Reportable incidents (Security) Indicator and depicts (1) the total number of loggable/ reportable incidents conceming system failures which oc-curred during the reporting month, and (2) the total number of loggable/ reportable inci-dents non-system failures conceming Security Badges, Access Control and Authoriza-tion, Security Force Error, and Unsecured Doors.

During the month of November 1996, there were 20 loggable/ reportable incidents iden-tified. This resulted in a 47% decrease on the overall incidents reported during the previous period. System failures accounted for 80% of the loggable/ reportable incidents, cight (50%) of which were environmental failures. Non-system failures consisted of two security force errors and two unsecured vital area doors, both of which were related to air pressure problems. Due to the increased emphasis by security personnel, there were no security badging and/or access authorization incidents during the reporting period.

This indicator provides information on security performance for Safety Enhancement Pro-gram (SEP) Item No. 58.

l Data Source:

Sefick/W6emer (Manager / Source)

Accountability:

Sefick Trend:

None SEP 58 58

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

1 l

Temporary Mosicatons >1 cycle old triru required for remowal) i i

i Temporary Modificatons >6 months oki(Removable on ime)

]

g FortCatmunGoalsfor>1 cycleand>6moethsold 7..

1 6..

]

5..

4..

l 3..

a 2..

1 1

t s

0 0

0 0 0 0 0 0 0 0 0

00 00

]_

O 0

x y

x x

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

l I,

TEMPORARY MODIFICATIONS t

i This indicator provides information on the number of temporary modifications (TMs) greater than j

one fuel cycle old requiring a refueling outage (RFO) for removal and the number of temporary modifications removable on-line that are greater than six months old. The 1996 Fort Calhoun i

monthly goals for this indicator are zero.

l There is currently one t morary modification that is greater than one-fuel cycle old requiring a i

refueling outage to rems TM 96-014, Reactor Coolant Gas Vent Line Pressure High Alarm, 3

was scheduled and repair.

' re made dudng the 1996 Refueling Outage, but function testing of the repairs cannot be perfor...ed because the reactor coolant gas vent line pressure is currently too high to test the equipment. At the end of November 1996, there were O temporary modifi-cations installed that were greater than six months old that could have been removed on-line.

At the end of November 1996, there was a total of 12 TMs installed in the Fort Calhoun Station.

i four (4) of the 12 installed TMs require an outage for removal and 8 are removable on-line. In 1996, a total of 34 temporary modifications have been installed.

Data Source:

Skiles/ Frank (Manager / Source)

Accountability:

Skiles/Gorence Trend:

Positive SEP 62 & 71 1

59

, Total Modification Packages opeT

+ Fort Calhoun Year-End Goal (68) 100 90 80 ya rs is 7s is is 7:

IO --

=

=

=

=

c T

77

"=

a 60..

50..

40..

30..

20..

10..

O l

l 93 94 95 Jan Feb Mar Apr May Jun Jul Aug sep oct Nov Dec 96 OUTSTANDING MODIFICATIONS This indicator shows the total number of outstanding modifications (excludino outstandino modifications which are proposed to be cancelled).

Reporting Cateoorv

'93

'94

'95

'9Q

'9Z

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

0 0

0 1

2 2

Mod. Requests Being Reviewed 0

0 0

0 0

0 0

Dedan Engr. Backlog /In Progress 0

0 0

0 4

14 29 Construction Backlog /In Progress 4

0 8

10 1

0 34 Design Engr. Update Backlog /In Progress _1 2

6 18 0

0 11 Totals 5

2 14 28 6

17 72 (outage + online)

(3+2)

(0+2) (6+8) (19+9) (0+6) (16+1)

(45+30)

At the end of November 1996,13 modification requests have been issued this year and 3 modification requests have been cancelled. The Nuclear Projects Review Committee (NPRC) has conducted 44 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) has completed 7 backlog modification request reviews this year.

The 1996 year-end Fort Calhoun goal for this indicator is a maximum of 68 outstanding modifications.

Data Source:

Jaworski/ Walling (Manager / Source)

Lounsberry/Belek (Manager / Source)

Accountability:

Scofield/Jaworski Trend:

None 60

a 80..

EARS Requiring Engineering Closeout - Not in Closeout 60 --

5 SE O DEN 40.

20 0;

,C,n,

E

E, 0

m Sep Oct Nov Sep Oct Nov Sep Oct Nov Sep Oct Nov 0-3 Months 3 6 Months 612 Months -

>12 Months O Engineering Response g Closeout (sE) 30 _

20..

I I

Priority 0 Priority 1 Priority 2 Priority 3 Priority 4 Priority 5 Priority 6 s7 EAR.

4ssansen 4i ov rau.

R. quiring is EAR.

Sch.dul.

R.p.nses R..,.....

R...iv.a 44.ts

.... s s

is o r...

ci..

w.

15.5%

l ENGINEERING ASSISTANCE REQUEST BREAKDOWN This indicator shows a breakdown of the number of EARS assigned to Design Engineering and System Engineering. The 1996 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 5

EARS closed during the month 5

Total EARS open at the end of the month 103 Data Source:

Jaworski/Livingston (Manager / Source)

Accountability:

Skiles/Jaworski Trend:

None SEP 62 61 l

)

i a

l 1

i N

Dh 43 Moe CLO EOUT S E.

3-8 Month l.

ECN Status-Overall Backlog l

}

30 g Bacidogged O Received g Completed e-s m e=h.

{

22 _

1 vs l

150.

12 m

a a

~

! Jun Jul Aug Sep Oct Nov 8

89%

l Design Engineering

(

250.

g 200.

0-3 150.

g

- :D-3.s l

100.

p er Months B"{ G 8 R R E"C. '

de

)

Jun Jul Aug Sep Oct Nov es Montht j

System Engineering 84%

g",,,

um zu l

L L L L L L w..u....,,,,,,,,

~

l 0

j May Jun Jul Aug Sep Oct j

Procurement / Construction 250.

j

>6 0-3 Wnths Wnths 150 _tas as 78% [

22%

W hs o

Jun Jul Aug Sep Oct Nov Drafting / Closeout ENGINEERING CHANGE NOTICE STATUS J

Data Source:

Jaworski/Livingston (Manager / Source) 1 Accountability:

Jaworski/Skiles i

Trend:

None SEP 62 J-I 1

62

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

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

e e

137 e5 59 PC TYP E P rio rity

{ fJf *

Y 12 s%

J-

.' a ; ; m y. &

J

'"*" *%nyt:#Dib SRI TYP E Total Open ECNs = 492 Total Open ECNs = 492 60%

20 25 O DEN.Closeeut or Drafting Nof Complete P riority P rio rity 5 Maintenance /ConstructionfProcuremord -Wrk Not Complete 5&S 1&2 5 system Engineering. Response, CorWirrration Not Complete 16 %

13 %

5 DEN Engineering Not Cornplete 200 --

m

$ss we 8

2 P riority 344 Jun98 Jul-es ug et-as Nov-96 37%

M-se 40 so so, 300.

2s4 2ss P riority P rio rity I

JurW6 M M 8ep46 Ott 06 M

P riority anda W RomEENs Cpen

,,'(

100.

80 -

74 se 112 To ss 3%

0

. I7.

s, as 60.

is s

U N.

i 41 2

y

'8 3

Jun Jul Aug Sep Oct Nov

""*[

Document Change ECNs Open ses ENGINEERING CHANGE NOTICES OPEN Data Source:

Jaworski/Livingston (Manager Source)

Accountability:

Skiles/Jaworski Trend:

None SEP 62 63

i g Administrative controlProblem g Licensed Operator Error l

g OtherPersonnelError g Maintenance Problem O Design / construction / Installation / Fabrication Problem g Equipment Failures 3..

\\

2..

1..

O i

Nov Dec Jan 1%b Mar Apr May Jun Jul Aug Sep Oct f*l I""I LICENSEE EVENT REPORT (LER) ROOT CAUSE BRIAKDOWN This indicator shows the LERs by event date broken down by Root Cause Code for each of the past twelve months from November 1,1995, through October 31,1996. 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-triled descriptions of these codes, see the " Performance Indicator Definitions" section of this report.

There were six events in October 1996 that resulted in LERs.

Data Source:

Tills /Cavanaugh (Manager / Source)

Accountability:

Chase Tcend:

None 64

1 g Total Requalification Training Hours a simulator Training Hours a Non.RequanficationTraining Hours g Number of Exam Failures y

3, 35.

32 32.5 32 30..

25..

20..

7 16 5.5

)

4 I4 4

15..

2 12 10..

j 7.5 8

8 6

5 3

5 5..

3 1

1 0

0 1

i 0._

i l

l l

l l

cycle cycle cycle cycle cycle cycle cycle cycle 954 95-4 954 95 6 96-1 96 2 96 3 96 4

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

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

LICENSED OPERATOR REQUALIFICATION TRAINING This indicator provides information on the total number of hours of training given to each crew during each cycle. The simulator training hours shown on the graph are a subset of the total training hours. Non-Requalification Training Hours are used for AOP/EOP verification & validation, INPO commitments, GET, Fire Brigade, Safety Meetings, and Division Manager lunches.

Exam failures are defined as failures in the written, simulator, and Job Performance Measures (JPMs) segments of the Licensed Operator Requalification Training.

Data Source:

Conner /Guliani(Manager / Source)

Accountability:

Conner /Guliani Trend:

None SEP 68 65

1 g SRO F.xams Administered O SRO Exams Passed O ROExams Administered 3

g ROExams Passed 30..

25..

20..

4 15..

10.

S..

4 0

m M.

Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov l1995l l1996l LICENSE CANDIDATE EXAMS This indicator shows the number of Senior Reactor Operator (SRO) and Reactor Opera-tor (RO) quizzes and exams taken and passed each month. These intemally adminis-tered quizzes and exams are used to plot the SRO and RO candidates' monthly progress.

During the month of November 1996, there were O RO and 0 SRO exams given.

Data Source:

Conner /Guliani(Manager / Source)

Accountability:

Conner /Guliani Trend:

None SEP 68 66

i e Ready to Close m dosed l

+ Total CRs j

+ open 2000 1800..

1600..

1400.

1200 0

1000.

800 ---

0 400 200 n

29-Mar 12-Apr 26-Apr 10-May 24-May Jun-96 Aug-96 oct-96 CONDITION REPORTS BY LEVEL This indicator shows the total number of Condition Reports which are Closed, Ready to Close, Open and the Total Number of Condition Reports to date.

Level 1 Level 2 Level 3 Level 4 Level 5 Level 6 Total Open 23 10 82 731 23 19 892 Closed 8

2 69 606 319 88 1092 213 Condition Reports are " READY" to "CLOSE".

At the end of November,1996 there were 102 "OPEN" incident Reports, of which, 27 were Significant.

As of September 21,1995, incident Reports were no longer issued.

Data Source:

Tesar/Burggraf(Manager / Source)

Accountability:

Andrews/Gambhir/Patterson Trend :

None 67

i o WN8PN 1200..

i 1000.

MWo HOLDS i

sy m m aoo.

numer NREMEW 18%

3

{

12%

l 2m..

m 87 %

J l

0 l

l l

j Aees sapes octes m

i MWO PLANNING STATUS (CYCLE 17 REFUELING OUTAGE)

This indicator shows the total number of Maintenance Work Requests (MWRs) and Main-l tenance Work Orders (MWOs) that have been approved for inclusion in the Cycle 17 Refueling Outage. This graph indicates:

i l

- Parts Holds - Planning Complete, Awaiting Parts i

- System Engineering Holds - Awaiting System Engineering input to Planning j

- Planner Holds - Maintenance Planner has not completed planning the work j

package.

- ECN Hold - Awaiting Substitute Replacement Items ECN from DEN.

i i

Data Source:

Chase /Schmitz (Manager / Source) l Accountability:

Chase /Faulhaber

{

Trend:

None SEP 31 l

68 1

J y

No Data Available SPECIAL SERVICES ENGINEERING DEPARTMENT OVERALL PROJECT STATUS (Cycle 17 Refueling Outage)

This performance indicator shows the status of projects which are in the scope of the Cycle 17 Refueling Outage. SSED's goalis to have all projects ::ompleted by August 23, 1996, 30 days prior to the Refueling Outage start date.

Data Source:

Phelps/Sweamgin (Manager / Source)

Accountability:

Phelps/Boughter Trend:

None SEP 31 69 l

--$=- Baseline Schedum for PRC Approval

--G-Projected /ActualScheduleforPRC Approval

-Final Desgn Pkg lssued (2 FD DCP ksued Pror to 05/0795)

To tal M odif cate n Packages (22) (11 Added After 05/0795) 9

/

e 8.

-m 37.

v.j6.

,/

5.

h $ 4.

e

- E 3.

m xy2_.

21 c.

0:

$ f$$$f$

5 S

N 5

E M

E M

5 W

S S

PROGRESS OF CYCLE 17 OUTAGE (1996 MODIFICATION PLANNING)

(FROZEN SCOPE OF 9 OUTAGE MODIFICATIONS)

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

The goal for this indicator is to have all modification packages which were identified prior to May 1,1995, PRC approved by March 22,1996. 11 Modifications added after May 1, 1995, not included.

November 1996 Modifications added: 0 Deleted = 0 Graph corrected to represent the baseline schedule.

Data Source:

Jaworski/ Walling (Manager / Source)

Accountability:

Gambhir/Jaworski Trend:

None SEP 31 70

l MODS ADDED TO 96 REFUELING OUTAGE AFTER FREEZE DATE (05/01/96) 16-ag o

(

9E.

A b*

g am o

~$ 7/14/96..g.i

.g.g

.g

.g.i U

! E S"- !!.s s

s s

s 3

s g < CM96.

g s/1ss6.

E 4r25ss N

4 S 96 95 96 95-95-96-95-95 E

95-95-025 001 023 011 002 013 022 008 007 020 MODIFlCATION NUMBER

\\ewaneu nu awwnemm l PROGRESS OF CYCLE 17 OUTAGE (1996 MODIFICATION PLANNING)

(1996 MODIFICATION PLANNING)

This indicator shows the status of modifications approved for installation during the Cycle 17 Refueling Outage. These modifications were added to the outage list after May 1, 1995. The data is represented with respect to the baseline schedule (established May 1, 1996).

The goal for this indicator is to have all modification packages PRC approved by their target date.

November 1996 Modifications Added: 0 Deleted = 0 Modifications Pre-Approved: 6 Data Source:

Jaworski/ Walling (Manager / Source)

Accountability:

Gambhir/Jaworski Trend:

None SEP 31 71

,__ Baseline Schedule for PRC Approval Total Modification Package' (10)(4 Added After 052145) s 6

x 7

5..

)

]d--

2

/

3..

i n.

{ 2..

i 5

1 m: : : ::::.

o i

8 i

! lI l

E 8

8 E

g 5

g s

s a

s s

s i

s a

s

=

PROGRESS OF 1996 ON-LINE MODIF" CATION PLANNING (FROZEN SCOPE OF 6 MODIFICATIONS)

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

The goal for this indicator is to have all modification packages which were identified prior to May 1,1995, PRC approved by March 25,1996.1 Modification added after May 1, 1995, not included.

November 1996 Modifications Added: 0 Deleted = 0 Graph corrected to represent the baseline schedule.

Data Source:

Jeworski/ Walling (Manager / Source)

Accountability:

C.nbhir/Jaworski Trend:

None SEP 33 72

ACTION PLANS e

73

ACTION PLANS i

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-QP-37, the following performance' indicators wou

require action plans based on three (3) consecutive months of perfomiance cited as "Needing increased Management Attention":

. Fuel Reliability Indicator (page 9)

. Maintenance Workload Backlogs (page 47)

FAILED FUEL ACTION PLAN Problem Statement:

Fuel failures in Cycle 16 have caused elevated reactor coolant system activities subsequently resulting in higher radiological dose rates ( and exposures with access problems) as well as a fuel reliabi'.ty indicator (FRI) which does not meet the performance indicator goal. The ele'tated FRI has resulted in lowering the plant performance indicator index to an undesirable value.

.GQstl Reduce the reactor coolant activity levels for Cycle 16 operations and take measure to achieve zero defect fuel performance for Cycle 17 and beyond.

Eliul The plan below is compromised of both short term corrective actions to address the Cycle 16 operations goals identified above and long term corrective actions for Cycle 17 and beyond.

I 74

Fuel Reliability SHORT TERM (CYCLE 16 OPERATIONS)

~

1 l

LIf,M ACTION RESP DATE DUE STATUS 1.

Evaluate replacement of two-mecron filter in CVCS with one-Holthaus Completed Complete.1/4/96. Filter replacement win micmn filter, result in improved particulate removal 01/04/96 and consequently lower dose rates.

1 a.

InstaN one-micron Alters in CVCS 01/31/96 Ceiis d 03/13/96 2.

Evaluate benetts ofincreasing letdown flow.

Holthaus/Spilker Co.,.: ". J Previously evaluated in Radiological 01/19/96 Analysis95-005, which supports increased letdown flow.

3.

Evaluate need for and effectiveness of more frequent of Holthaus Completed Complete. 01/04/96. Resin bed effective puri#caton and cation ion beds.

01/04/96 in minimizing RCS acthnty Resin beds replaced in November 1995.

IIEM ACTION RESP.

Date Due STATUS 3a.

Replace si. sin beds dering Spring 1996 outage.

Spires 03/22/96 Canceled 4.

Prepare and issue Nuclear Network request for industry Completed Complete. 01/12/98. Transmitted experiencein reducing FRI.

01/12/96 proposedinquiry to Licensing for Nuclear Network entry.

5.

Evaluate instsNation of silver mordenite titration system Holthaus/ Spires CO.,@;,,J Received general (unclassited) forincreased lodine removal.

01/26/96 information on systeniused at Savannah River Project.

6.

Identify number of old design assembles to be placed Completed Previously iden68ed eight assembles to in penpheral locations for second cycle and consider Holthaus/Guinn 01/12/96 be placed on core periphery for second replacement with new design assembly.

cycle.

75 p

-Fuel Reliability 7.

Evaluate whether these assembles could be used for Holthaus/Guinn C uiv k i J v

more than one cycle to reduce cost.

01/19/96 8.

Determine if Westinghouse can supply the above fuel Cuii,.L:ed Complete. 01/12/96. Westinghouse has assemblies for Cycle 17. Also, can Fuels Dvision Holthaus/ Hanger 01/12/96 indicated that they can fabricate the provide necessary uranium assemb5es Cost estimates by Fuels Division is approx.12M. Discount from Westinghouse also requested.

9.

Eboluate Cycle 18 pretminary pattem same as S & 6 Holthaus/Guinn Completec Cycle 18 pretminary pattem indicates 01/17/96 four additional assemb5es would be required. Cost $i.0M 10.

Evaluate Cycle 19 preRminary pattem same as S& 6 Holthaus/Guinn Co..,.L;, 3 Cycle 19 prelmmary pattomindicates 01/17/96 eight additional assemblies would be required. Cost $2.0M 11.

Ans!yze additional assemblies to be procured Holthaus/ Hanger Co,,,.L: J Total costis $5.0M for 20 additional 01/17/96 assembles 12.

Evaluated cost /benett with assumphon of Holthaus/ Hanger Co.v,L:ed

$10,000/ person exposure.

01/25/96 i

76

The action plan for Maintenance Workload Backlog (page 47) is as follows:

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

Planning Scheduled Maintenance Bulk Work 1

77

PERFORMANCE INDICATOR DEFINITIONS AUXILIARY FEEDWATFR SYS1EM SAFETY SYSTEM CLEAN CONTROLLED AREA CONTAWNATIONS > 1,000 PERFORMANCE DISINTEGRATIONS /WNUTE PER PROBE AREA The sum of the known (planned and unplanned) unavaMable The personnel cortarrunabon events in the clean controlled area.

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

feedwater system for the reporting penod divided by the cribcal hours for the reporting penod multiplied by the number of trains CONTAWNATED RADIATION CONTROLL ED AREA in the auxisery feedwater system.

The percertage of the Radiation Controlled Area, which includes COLLECTNE RADIATION EXPOSURE the auxHiary buildeng, the radweste bulkhng, and areas of the C/RP building, that is contaminated based on the total square CollectNe radiation exposure is the total extemal whole-body footage. This indcator tracks performance for SEP #54.

done receked by al orveite personnel (includog contractors and visitors) during a time period, as measured by the DAILY THERMAL OUTPUT thermoluminescent dosimeter (TLD). Collective radiation expsure is reported in units of persordrem. This indcator This hdicator shows the daHy core thermal output as measured tracks radiological work performance for SEP #54.

Itom computer point XC105 (in thermal megawatts). The 1500 MW Tech Spec limit, and the unmet portion of the 1495 MW COMPONENT FAILURE ANALYSIS REPORT (CFAR)

FCS daily goal for the reporting month are also shown.

SUMMARY

DIESEL GENERATOR RELIABILITY (26 Demands)

The atsnmary of INPO categories for Fort Calhoun Station with angnicangy higher (1.645 standard deviations) ImHure rates than This indicator shows the number of failures occumng for each the rest of the industry for an seghteerHnonth time period.

emergency diesel generator during the last 25 start demands Fauures are reported as component (i.e., pumps, motors, main and the last 25 load-run dernands.

steam stop valves, control element motors, etc.) categones.

DISABLING INJURYALLNESS FREQUENCY RATE FaRure Cause Categories are:

(LOSS TIE ACCIDENTRATE)

Age / Normal Use -thought to be the consequence of This hdicator is defined as the number of accidents for ad utility expected wear, aging, eno of-life, or normal use.

personnel permanently assigned to the station, involving days away from work per 200,000 man-hours worked (100 man.

Manufacturing Defect. a failure attributable to lnadequate years). This does not include contractor personnel. This assembly or inibal quahty of the responsible component or indcator tracks personnel performance for SEP #25,26 & 27.

system.

DOCUENT REVIEW (BIENNIAL)

Engmeenng/Dessgn a faBure attributable to the inadequate design of the responsible component or system.

The Document Review Indicator shows the number of documents reviewed, the number of documents scheduled for Other Devices. a failure attributable to a failure or review, and the number of document reviews that are overdue misoperaten of another component or system, including for the reportmg month. A document review is considered associated devices.

overdue if the review is not complete within six months of the assigned due date. This indcator tracks performance for SEP Mamtenance/ Action. resulbng from improper maintenarr e,

1. 46.

lack of maintenance, or personnel errors that occur during maintenance actrvibeson the component..

EMERGENCY AC POWER SYSTEM SAFETY SYSTEM PERFORMANCE Testing Action -resuting from improper testng or personnel errors that occur during testing activibes.

The sum of the known (planned and unplanned) unavailable and the estimated unavailable hours for the emergency AC power initial Installation Error. caused by improper initial system for the reporting period drvided by the number of hours instabaton of equipment in the reportng period multiplied by the number of trains in the emergency AC power system.

CENTS PER KILOWATT HOUR EDERGENCY DIESEL GENERATOR UNIT RELIABILITY The purpose of this indcator is to quanbfy the economcal operaten of Fort Calhoun Staten. The cents per kilowatt ThB eldcator ahons the nunter of failures that were reported during the hour indcator represents the budget and actual cents per last 20, R and 100 ewgency diesel generator dernands at the Fort idlowatt hour on a twelve-month everage for the current year.

h h Ano show are tnggenalues which correlate to a high The bass for the budget curve is the approved yearty budget.

level of c n den e that a unirs dassel generators have obtamed a The bases for the actual curve is the Financial and Operabng han t

r Report.

78

PERFORMANCE INDICATOR DEFINITIONS j

and ihe su<messu iesnhet fo.ows,epet io ve,1,y o,.,-y

1) Nisviher of etert Demands: AR valid and inadvertent start should not be courted as demands or inHures when the EDG demands, includmg al start-only demands and al start has not been deciered operable again.

/

demands that are fotowed by load run demands, whether by automobc or manuelinilinhon. A start only demand is ERERGENCY DESEL GENERATOR UNRELIABN.ITY a demand in wheh tio emergency generator is started, bLA no attempt is made to load the generator This indicator measures the total unreliebiNty of emergency diesel generators In general, unreliabiluy is the ratio of

2) Number of Start Failures Any failure within the unsuccessful operations (starts or lood-r'.ms) to the menber of emergency generator system that prevents the generator valid demands. Total unrelii;5ility 4, a comtunebon of start tom actiieweig spodsed tospaancy and voltage is classited unreliabluty and lood-run unrekebaty.

as a valid start teilure. This includes any condition

!dentiged in the course of maintenance inspections (with ENGINEERSiG ASSISTANCE REQUEST (EAR) the emergency generator in stanstay mode) that doenholy BREAKDOWN won'id have resumed in a start failure if a demand had occi.'ved.

This indmetor shows a breakdown, by age and priority of the EAR, of the number of EARS assigned to Design Engineenng

3) Numbe of LoosJtun Demands: For a valid lood run Nuclear and System Engmeenng. This indsator tracks demeru to be counted, the lood-run enempt must meet performance for SEP 862.

one or ;nore of the fonowing crtlerte:

ENGBIEERING CHANGE NOTICE (ECN) STATUS A) A load-run of any duraton that resuRs tom a reel automebc or monuelinibebon.

The number of ECNs that were opened, ECNs that were completed, and open bacidog ECNs awaiting compiehon by B) A loed4un test to saliefy the plant's load and durobon DEN br the reportmg month. This indcator tracks performance as stated in each tears spacencetons for SEP 862.

C) Otter special tests in which the emergency generator ENGINEERNG CHANGE NOTICES OPEN is expecned to be operated for at leest orm hour while loaded with at least 50% of as design load.

This indsator brooks down the number of Engmeenne Change Nobces (ECNs) that are assigned to Design Engmwenng

4) Nuredser of Land Run Failures: A load-run failure should Nuclear (DEN), System Engineering, and Memtenance The be counted for any reason in which the emergency graphs provide data on ECN Facihty Changes open, ECN generator does not pidt up load and run as predeted.

Subettute Repiscement items open, and ECN Document Fanures are counted dunng any valid lood run demands.

Changes oport This indestor tracks performance for SEP #62.

5) Exceptions: Unsuccessful attempts to stort er lood-run EQUrtiENT FORCED OUTAGES PER 1,000 CRITICAL should not be counted as valid demands or Isilures when HOURS they can be attributed to any of the fonounng Equpmerd kreed culeges per 1,000 critical hours is the inverse A) Spunous trips that would be bypassed in the event of of tie mean bme between forced outages caused by equipment an emergency failures. The mean time is equel to the number of hours the reactor is cuticalin a penod (t,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />) divided by the number

8) Malfunchon of equipment that is not required during of forood outages caused by equipmert failures in that penod.

en emergency.

EQUlVALENT AVAILABILITY FACTO't C) Irdertional terminobon of a test because of abnonnel condibons that would not have resulted in major This indicator is defined as the ratio of gross available dieselgenerator demoge or repeir.

genershon to gross rneximum generation, expressed as a percentage. Available genersten is the ent.rgy that con be D) Melhmetens or operahng errors which would not produced if the unit is operated at the maximum power level have prevented the emergency generator from being permitted by equipment and regulatory hmitsbons Maximum restarted and brought to load within a few menutes generation is the energy that can be produced by a unit in a given period if operated conhnuously at maximum cepecty E) A feiture to start because a porten of the starting system was M=1 for test purpose, if fotowed by FORCED OUTAGE RATE a successful start with the starbng system in Rs normal alignment This indmetor is deAned as the percentage of time that the unit was unavailable due to forced events compared to the bme Each emergency generator failure that results in the generator planned for electncel generation. Forced events are foHures or being dociered inoperable should be counted as one demand other unplanned concNhons that require removing the unt from and one taikse. Exploratory tests dunng corrocuve maintenance service before the end of the next weekend. Forced events 79

a PERFORMANCE lNDICATOR DEFINITIONS include start-up failures and events initiateJ while the unit is in Contractor personnel are not included for this indmetor recorve shutdown (i.e., the unit is available but not in serves).

IN4.INE CHEMISTRY INSTRUAE!NTS OUT OF SERVICE FUEL ftELIABEJTYINDICATOR Total number of kWine chernistry instruments that are out of-This indmetor is desnod as the steady etate pnmary coolant l-service in the Secondary System and the Post Accedent 131 activity, corrected for the trarnp uratuum contributen and Sempilng System (PASS).

normatead to a common purecolon rate. Tramp uraruum is fuel which has been deposited on reactor core intemets from LICENSE CANDIDATE EXAMS previous defectnre fuel or is present on the surInce of fuel elements troen the menuinctunng process. Steady state is This buscolor shows Die number of SRO and/or RO quizzes and defined as conhnuous operaten for at least three days at a exams that are admeustered and poseed each month. This power level that does not very more then + or -55 Plants indmotor tracks trairung performance for SEP #88.

' should cated date for tiis indmetor at a power level ateve 85%,

when poselde. Plants tiet dd not operate at steedy-etate power LICENSED OPERATOR REQUALFICATION TRAgdpfG above 85% should coRect data h this indicator at the highest olesdy-elete power level attained during the month.

The total number of hours of training given to each crew during each cycle. Also provided are the simulator training hours The donelly correcnon factor is the rate of the specac volume (which are a subset of the total training hours), the number of of contarit et the RCS operahng temperature (540 degrees F., Vf norWtEQUAUFICATION tainmg hours and the number of exam

= 0.02146) divided by the epocMc volume of cooient at normal failures. This indicator tracks traeung performance for istdown tempershoe (120* F st onset of the letdown cooHng host SEP #88.

exchanger,VI= 0.018204), whis roeuns in a density corremon factor for FCS equel to 1.32.

LICENSEE EVENT REPORT (LER) ROOT CAUSE BftEAMDOWN oftOSS HEAT RATE This indmetor shows the number and root cause code for Gross heet role is defined as the ratio of total thermal energy in Uconese Event Reports. The root cause codes are as follows Brash Thermal Units (BTU) produced by the reactor to the total groes electrical energy produced by the generator in idiowett-

1) Administralfwe Control Problem - Management and hours (KWH).

supervisory deAconcies. hot affect plant programs or activibes (Ls., poor planning, breakdown or inck of HAZARDOUS WASTE PRODUCED adequate management or supavisory cordrol, incorrect procedures, etc).

The total amount (in Kilograms) of rurWielogenotec; hazardous waste, hologenoted hazardous waste, and other hazardous

2) Licensed Operator Error - This cause code captures weste produced by FCS each month.

errors of onussen/commmemn by toensed roedor operators during pient souvibes HIGH PftESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PEftFORMANCE

3) Other Personnel Error Errors of omiseen/commlosen committed by norWeensed personnel Irwolved in plert The sum of the known (planned and unplanned) unevaikble acteribes hours and tie esbmeted unevailable hou. for the high press <ee safety injechon system for the reportmg period divided by the

4) Maintenance Proldom.The intent of this cause code is to atical hours for the reportmg period mulbphed by the number of capture the fug range of problems which can be attributed trains in the high pressure safety injechon system.

in any way to programmete deAconces in the moeilenance furictonal orgerutaten. Acevibes included in INDUSTftlAL SAFETY ACCDENT RATE INPO this category are maintenance, teshng, survedience, cabbration and redeten protechon.

This insularis doened as the number of acadents per 200,000 marWiours worked for al utsty personnel permanently assigned 5) abrication Problem-to the station that result in any of the fotowing This cause code covers a fug range of programmehc defknencies in the areas of design, construchon,

1) One or more days of restricted work (excluding the day of rutouston, and fabricaten (i.e., loss of control power due the occident);

to underreled fuse, equipment not quehned for the environment, etc.).

2) One or more days away from work (excluding the day of the accedent); and

6) Equipment Failures Electronic P oce# arts or Environmental 4telated Failures) This code is used for

3) Fatehties.

spunous failures of electronc pece-ports and failures due to meteorologmal conditens such as hghtnmg, ice, high 80

I e

PERFORMANCE INDICATOR DEFINITIONS a

winds, etc. Generapy, R includes spunous or one-time MAXIMUM INDIVDUAL RADIATION EXPOSURE failures. Electne components included in this category are circuit cards, rechfiers, tuotables, fuses, capacitors, diodes, The totai rnaarnum amourt of radiabon received by an individual resistors, etc.

person worldng at FCS on a monthly, quarterty, and annual beeis.

LOGGASLEstEPORTABLE INCIDENTS (SECURfTY)

MWO PLANNmiG STATUS (CYCLE 17 REFUELING The total number of securty incidents for the reporting month OUTAGE) depicted in two graphs. This indicator tracks security performance for SEP #58.

The total numb of Maantenance Work Orders that have been approved for km.bn in the Cycle 17 Refueling Outage and the MAINTENANCE OVERTIRE rusnhor th.t are ready to work (parts staged, planning complete, and al orier papensork ready for fleid use). Also included is the The percent of overtime hours compared to normal hours for number of MWOs that have been enginsonng holds (ECNs, maintenance This includes OPPD personnel as wet as procedures and other miscotoneous engineering holds), parts contract personnel.

hold, (pe'is slaged, not yet inspected, ports not yet crrived) and plannrg hold Gab scope not yet completed). Maintenance Work MAINTENANCE WORKLOAD BACKLOGS Requests (MWRs) are also shown that have been identmed for the Cyde 17 Rebeing Ottage and have not yet been converted This Indicator shows the bacidog of non-outage Maintenance to MWOs.

Work Orders remaining open at the end of the reporting month.

Meantononce cissemcohons are defined as fonows:

NURSER OF CONTROL ROOM EQUrtENT DEFICIENCES Corrective. Repair and restorabon of equipment or A control room equipment deficiency (CRD) is denned as any components that have fated or are malfunctiorung and are not component which is operated or controlled from the Control performing their intended funchon.

Room, provides indication or alarm to the Control Room, provides testing enf= mas from the Control Room, provides Preventive. Achons taken to maintain a piece of equipment automatic actions tom or to the Control Room, or provides a wthin design operahng condlhons, prevent equipment failure, passive funeon for tie Conhol Room and has been identmed as and extend its ble and are performed prior to equipment dolcant, l.a., does not perform under aN eondbons es designed.

failure.

This delnihon also applies to the Allemate Shutdown Panels Al-179, Al-185, and Al-212.

Non4ctractiverlant Maintenance adiviles performed to implement station improvements or to A plant cargonent which is deficeent or inoperable is considered repair run-plant equipmert an

• Operator Wbrk Around (OWA) ltem"if some other action is required by an operator to (~,i.,,--

_ for the condition of the Maintenance Work Priorities are deened as:

componert Some examples of OWAs are:

L_.

y. Condiboo which sgnmosntly degrade station

1) The control room level indicator does not work but a local anfety or avagabdRy.

sight glass con be road by an Operator out in the plant; immediate Action. Equipment deficiencies which

2) A detaart pump cannot be repaired tucause replacement asgnmcently degrade station relehdity. Potential for unit parts require a long lead hme for purchsee/ delivery, thus shutdown or power reduchon.

requring the rodmdant pump to be operated continuously, Operations Concern. Equipment de6ciencies wWh hinder

3) Special actions are required by an Operator because of station opershon equipment design problems. These actions may be described in Operations Memorandums, Operator Notes, Essential Routine corrective maintenance on essential or may require changes to Operating Procedures, stehon systems and equipmert

4) Dolciert piert eqtapmert that is required to be used during Nondseential-Rouhne correctrve maintenance on non-Emergency Operating Procedures or Abnormal Operating esseghel stahon systems and equipment..

Procedures, Plant b _ _ :. Norwcorrective maintenance and plant

5) System indication that provides criticat informaten during improvements, normal or abnormaloperations.

This indicator tracks maintenance performance for SEP #36.

81

e PERFORMANCE INDICATOR DEFINITIONS NURSER OF RSSSED SURVEILLANCE TESTS RESULTING This indicator shows the status of the projects which are n the IN LICENSEE EVENT REPORTS scope of the Refueling Outage.

The number of Survetence Tests (STs) that result in Licensee PERCENTAGE OF TOTAL MINOs COMPLETED PER Event Reports (LERs) dunng me reportmg month. This indicator MONTH IDENTFIED AS REWORK tracks mesed STs for SEP 900 & 61.

The percentage of total MWOs completed per anonth identifled OPEN INCDENT REPORTS as rework. Rework actMties are identrRed by maintenance planning and craft. Rework is: Any addihonal work required to This indcolor deploys the total number of open incident Reports correct detaences decovered during a failed Post Maintenance (irs), me number of irs that are greater then six months old and Test to enetse the component / system posses subsequent Post 3

the number of open sagndcant irs.

Maintenance Test.

OUTSTANDING MOOlFICATIONS PERCENT OF ColWPLETED SCHEDULED MAINTENANCE ACTMTES The number of Moddcetion Requests (MRs) in any state between the issuance of a Modecabon Number and the The percent of the number of completed maintenance activities completon of the drawing update, as compared to the number of scheduled maintenance actMbes each month. This percentage is shown for au maintenance

1) Form FC.1133 Bacidogan Progress. This number crafts. Also shown are the number of emergent MWOs represents modscehon requests that have not been plant Maireenance actwities include MWRs, MWOs, STs, PMOs, approved during the reportmg month, calibrations, and other miscetoneous activihes. This indcator tracks Maintenance performance for SEP #33.

2) % Requests Being Reviewed. This category includes PERFORMANCE DIDICATOR NdDEX A) Modscobon Requests that are not yet reviewed.

This indmetor index is calculated from a weighted combmehon of twelve performance indicator values, which include the B) Mme6% Requests being reviewed by the Nucieer foHowing: Unit Capabiky Factor, Unit Capebility Loss Factor, Projects Review Committee (NPRC).

HPSI, AFW, Emergency AC Power System, Unplern /

Automatic Scrams, Collectue Radiation Exposure, Fuel C) nhear% Requests being reviewed by the Nuclear RetabRy,Thermel Performance, Secondary System Chemistry, Projects Committee (NPC).

Radabon Weste, and industrial Safety Accident Rate.

These Modincetion Requests may be reviewed several times PREVENTABLE / PERSONNEL ERROR LERs before they are approved for accompbehment or conceled.

Some of these ModiAcaten Requests are retumed to This indcator is a breakdown of LERs. For purposes of LER Enginsonng for more informehon, some approved for evolustion, event closescaten, a " Preventable LER"is defined as:

some approved for study, and some approved for pionning.

Once plannmg is completed and the scope of the work is cieerty An event for which the root cause is personnel error (i.e.,

defined, these Modecoten Requests may be approved for inappropriate acten by one or more indwiduals), inadequate accomplishment with a year seeagned for constructen or they administratrve controis, a design construchon, instagstion, rney be canceled. AE of these diflerent phases require review.

reistehon, fabriceton problem (involving work -.? J by or sLponneed by OPPD persormal) or a maintenance probism

3) Design Engineering Backlog 4n Progress. Nuclear (attributed to inadequate or improper upkeep / repair of plant Plannng has assagned a year in which constructen wiu be equpment). Also,the cause of the event must have occurred completed and design work may be in progress.

within approximately two years of the " Event Date" specined in the LER (e.g., an event for which the cause is attnbuted to

4) Construction Backlog 4n Progress. The Construebon a problem with the onginal design of the plant would not be Package has been issued or constructen has begun but considered preventable).

the modecoten has not been accepted by the System Acceptance Committee (SAC).

For purposes of LER event cisandcaten, a

• Personnel Error" LER is deflned as fogows:

5) Design Engineering Update Bacidogan Progress PED has recewed the Modscoton Completon Report but the An event for which the root cause is inappropriate action on drawings heve not been updated.

the part of one or more indwiduals (as opposed to being attributed to a department or a general group). Also, the The above mentened outstandmg modecahons do not include neppropnote acton must have occurred within approximately moddcatens which are proposed for cancelletson.

two years of the " Event Date" specded in the LER.

OVERALL PROJECT STATUS (REFUELING OUTAGE) 82

o l

PERFORMANCE INDICATOR DEFINITIONS Addtionaly, each event etassified as a " Personnel Error" should SAFETY SYSTEM FAILURES also be classified as " Preventable." This indicator trends personnel performance for SEP ltem #15.

Safety system failures are any events or condibons that could prevent the fulfillment of the safety funcbons of structures or PRIMARY SYSTEM LITHlUM % OF HOURS OUT OF LlHT systems. If a systern consats of multiple redundant subsystems or trains, failure of at trains constitutes a safety system failure.

The percent of hours out of hmit are for lithium divided by the Failure of one of two or more trains is not counted as a safety total number of hours possible for the month.

system failure. The definition for the indicator parallels NRC reporting regurements in 10 CFR 50.72 and 10 CFR 50.73. The PROCEDURAL NONCOMPLIANCE INCIDENTS baowing is a ist of the major safety systems, sut> systems, and (MAINTENANCE) components monitored for this indicator:

The number of identified incidents conceming maintenance Accident Monitoring instrumentation, Auxiliary (and procedural problems, the number of closed irs related to the Emergency) Feedwater System, Combustible Gas Control, use of procedures (includes the number of closed irs caused by Component Cooling Water System, Containment and procedural noncomphance), and the number of closed Contaanmert isolation, Containment Coolant Systems, Control pnxedural noncomplance irs. This indicator trends personnel Room Emergency Venblation System, Ernergency Core performance for SEP #15,41 and 44.

Cooling

Systems, Engineered Safety Features instrumentation, Essential Compressed Air Systems, PROGRESS OF CYCLE 17 OUTAGE MODIFICATION Essenbal or Emergency Service Water, Fire Detection or PLANNING Suppression Systems, Isolation Condenser, Low Temperature Overpressure Protection, Main Steam Line Thie indicator shows the status of rnodtfications approved for Isolation Valves, Onsite Emergency AC & DC Power compl6 tion darinj the Refuehng Outage.

w/Datribubon, Radiation Monitoring instrurnentation, Reactor Coolant System, Reactor Core isolation Coohng System, PROGRESS OF 1995 ON-LINE MODIFICATION PLANNING Reactor Trip System and instrumertation, Recirculation Pump Trip Actuation instrumentation, Residual Heat Removal This indicator shows the status of modifications approved for Systems, Safety Valves, Spent Fuel Systems, Standby Liquid completion dunng 1995.

Control System and Ulbmate Heat Sink.

RADIOLOGICAL WORK PRACTICES PROGRAM SECONDARY SYSTEM CHEMSTRY PERFORMANCE INDEX The number of identified poor radiological work practices (PRWPs) for Me reporting rnonth. This indicator tracks The Chemistry Performance index (CPI)is a calculation based radiological work performance for SEP #52.

on the concentration of key impurities in the secondary side of the plant. These key impurities are the most likely cause of RADIO OF PREVENTIVE TO TOTAL MAINTENANCE &

detenorabon of the steam generators. Criteria for calculating the PREVENTIVE MAINTENANCE ITEMS OVERDUE cpl are:

The ratio of preventive maintenance (including surveillance

1) The plant is at greater than 30 percent power; and testing and calibration procedures) to the sum of non-outage corrective rnaintenance and preventive maritenance completed

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

over the reporting peried The ratio, expressed as a percentage, is calculated based on man-hours. Also displayed are the The CPIis calculated using the following equation:

percent of preventive maintenance items in the month that were not cornpleted or administratively closed by the scheduled date CPI = ((sodium /0.79) + (Chloride /1.52) + (Sulfate /1.44) +

plus a grace pened equalto 25% of the scheduled interval. This (Iron /3.30) + (Copper /0.30)+(Condensate 02/2.90))/6 indicator tracks preventive maintenance activibes for SEP #41.

Where: Sodium, sulfate, chloride and condensate dissotved RECORDABLE INJURY /lLLNESS CASES FREQUENCY oxygen are tne monthly average blowdown concentrations in RATE ppb, iron and copper are monthly time weighted average feedwater concentratiorn in ppb. The denominator for each of The number of injunes requiring rnore than normal first aid per the five factors is the INPO median value. If the monthly 200,000 man-hours worked. This indicator trends personnel average for a specific parameter is less than the INPO median performance for SEP #15,25 and 26.

value, the median value is used in the calculatsen.

REPEAT FAILURES SIGNIFICANT EVENTS The number of Nuclear Plant Reliability Data System (NPRDS) componer'ts with inore than one failure and the number of Sgnificart events are the eventsidsntified by NRC staff through NPRDS components with more than two failures for the detated screening and evaluation of operating experience. The eighteen-month CFAR penod.

screening process includes the daily teview and discussion of 83

s PERFORMANCE INDICATOR DEFINITIONS all reported operating reactor events, as well as other instruments are not considered as temporary rnodifications.

operational data such as special tests or construction activities.

An event identified from the screening process as a significant

3) Scaffold is not considered a temporary modification.

overt candidate is further evaluated to determine if any actual or Jumpers and blocks which are installed and for which MRs potential threat to the health and safety of the public was have been submitted will be considered s temporary involved. Specific examples of the type of criteria are modecations until final resolution of the MR and the jumper summarized as follows:

or block is removed at is permanent!y recorded on the drawings. This indicator tracks temporary modifications for

1) Degradation ofimportant safety equipment; SEP #62 and 71,

2) Unexpected plant response to a transient; THERMAL PERFORMANCE

3) Degradaten of fuel integrity, primary coolant pressure The ratio of the design gross heat rate (corrected) to the boundary, important associated features; adjusted actual gross heat rate, expressed as a percentage.

4) Scramwithcomplication; UNIT CAPABILITY FACTOR

5) Unplanned release of radioactivity; The ratio of the available energy generation over a given time penod to the reference energy generation (the energy that could

6) Operaton outside the limits of the Technical Specifications; be producedif the unit were operated continuously at full power under reference ambient conditions) over the same time period,

7) Other.

expressed as a percentage.

INPO significant events reported in this indicator are SERs UNIT CAPACITY FACTOR (Significant Event Reports) which inform utilities of significant events and lessons learned identsfied through the SEE-IN The net electrical energy generated (MWH) divided by the avreening process, product of maximum dependable capacity (net MWe) times the gross hours inthe reporting period expressed as a percent. Net SPARE PARTS INVENTORY VALUE electrical energy generated is the gross electrical output of the unit measured at the output terminals of the turbine generator The dollarvalue of the spare parts inventory for FCS during the minus the normal station service loads during the gross hours of reportsng period.

the reporting period, expressed in megawatt hours.

STAFilNG LEVEL UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7,000 CRITICAL HOURS The actual staffing level and the authorized staffing level for the Nuclear Operations Division, The Production Engheering This indicator is defined as the number of unplanned automatic Division, and the Nuclear Services Division. This edicator scrams (reactor protection system logic actuations) that occur tracks performance for SEP #24.

per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of critical operation.

STATION NET GENERATION The value for this indicator is calculated by multiplying the total number of unplanned automatic reactor scrams in a specific time The net generation (sum) produced by the FCS during the period by 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, then dividing that number by the total reporting month.

number of hours crtticalin the same time penod. The indicator is further defined as fellows:

TEWORARY MODIFICATIONS

1) Unplanned means that the scram was not an anticipated The number of temporary mechanical and electrical part of a planned test.

configurations to the plant's systems.

2) Scram means the automatic shutdown of the reactor by a

1) Temporary cx>nfigurations are defined as electricaljumpers, rapid insertion of negative reactivity (e g., by control rods, electncal blocks, mechanical jumpers, or mechanical blocks liquid injection system, etc.) that is caused by actuation of which are installed in the plant operating systems and are the reactor protection system. The scram signal may have not shown on the latest revision of the P&lD, schematic, resulted from exceeding a set point or may have been connection, winng or flow diagrams.

spurious.

2) Jumpers and blocks which are installed for Surveillance

3) Automatic rneans that the initial signal that caused actuation Tests, Maintenance Procedures, Calibration Procedures, of the reactor protechon system log c was provided from one Special Procedures or Operating Procedures are not of the sensor's monitonng plant parameters and conditions, consedered as temporary modificatens unless the jumper or rather than the manual scram switches or, manual turbine block remains in place after the test or procedure is tnp switches (or push-buttons) provided in the main control complete. Jumpers and blocks installed in test or lab roorn.

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PERFORMANCE INDICATOR DEFINITIONS

4) Cntical means that during the steady state condibon of the processing. Low-level solid radioactive waste consists of dry reactor prior to the scram, the effective mulbphcotion (k,)

actwo waale, sludges, resans, and evaporator bottoms generated was essenhagy equal to one.

as a resuR of nuclear power plant operation and maintenance.

Dry radmactive weste includes contaminated rags, cleaning UNPLANNED CAPAttuTY LOSS FACTOR rnatonais, d=f-hi* Protective Clothing, plastic Containers, and any other material to be disposed of at a low-level radioactive The ratio of the unplanned energy losses during a given period wede disposal site, except resin, sludge, or evaporator bottoms.

of time, to the reference energy generation (the energy that Low 4evel refers to al radmactive weste that is not spent fuel or could be produced if the unit were operated continuously at fui a by-product of spent fuel processing This indicator tracks power under reference ambient conditions) over the same time radiological work performance for SEP #54.

pered, expressed as a percentage.

UNPLANNED SAFETY SYSTEM ACTUATIONS. (INPO

+ DEFINITION)

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

1) The numberof unpionned Emeyoney Core Cooling System (ECCS) actuations that result from reaching an ECCS actuation 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 unplanned safety system actuaten occurs when an edusbon set point for a safety system is reached or when a spurious or inadvertent signal is generated (ECCS only),

and mapr equipment in the system is actuated. Unplanned means that the system actuation was not part of a planned test or evolution. The ECCS actuations to be counted are actuations of the high pressure injection system, the low pressure injection system, or the safety injection tanks.

UNPLANNED SAFETY SYSTEM ACTIONS. (NRC DEFWITION)

The number of safety system actuatens which include (gnly,) the High Proseure Safety injedian System, the Low Pressure Safety tryoden System, the Safety Irisction Tanks, and the Erne gency Diesel Generators. The NRC classification of safety system actuations includes actuatens when major equipment is operated gg[ when the logic systems for the rbove safety systerns are challenged.

VIOLATION TREND This indicator is doened as Fort Calhoun Station CRed Volations and Nor> Cited Violations trended over 12 months. Additionapy, Cited Velations for the top quartile Region IV plant is trended over 12 months (lagging the Fort Calhoun Staten trend by 2-3 morths). R is the Fort Calhoun Station goal to be at or below the cRed violaten trend for the top quartile Region IV plant.

VOLUhE OF LOW 4.EVEL SOUD RADIOACTWE WASTE This indicater is defined as the volume of low-level solid radoectwo weste actually shipped for burial This indcator also shows the volume of low-level radioactive waste which is in ternporary storage, the amount of radsoactive oilthat has been shipped off-site for processing, and the volume of solid dry radioactive waste which has been shipped off-site for 85 1

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SAFETY FAHANCEMENT PROGRAM INDEX The purpose of the Safety Enhar.:ement Program (SEP) Performance Indicators Index is to list performance indicators related.o SEP items with parameters that can be trended.

SEP Reference Number it'.

Engg

. Increase HPES and IR Accountability through use of Performance Indicators Procedural Noncompliance incidents (Maintenance)..................................... 51 Recordable injury / Illness Cases Frequency Rate........................................

16 Clean Controlled Area Contaminations.>,,1,000 Disintegrations / Minute Per Probe Area

..........17 Preventable / Personnel Error LERs.................................................... 18 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

...............15 Recordable injury / Illness Cases Frequency Rate........................................ 16 SEP Reference Number 31

. Develop Outage and Maintenance Planning Manual and Conduct Project Management Training MWO Planning Status (Cycle 17 Refueling Outage)

.........................68 SSED's Overal! Project Status.................................................. 69 Overall Project Status (Cycle 17 Refueling Outage).........

. 70 Progress of Cycle 17 Outage Modification Planning..................................... 71 SEP Reference Number 33

. Develop On-Line Maintenance and Modification Schedule Percent of Completed Scheduled Maintenance Activities (All Maintenance Crafts)............. 52 1996 On-Ene Modification Planning.........................

72 SEP Reference Number 36

. Reduce Corrective Non. outage Backlog Maintenance Workload Backlogs (Corrective Non-Outage)

............................47 SEP Reference Numbers 41 & 44

. Develop and implement a Preventive Maintenance 3chedule

. Compliance With and Use of Procedures Ratio of Preventive to Total Maintenance & Preventive Maintenance items Overdue........... 48 Procedural Noncompliance incidents (Maintenance)................................... 51 86

t SAFETY ENHANCEMENT PROGRAM INDEX SEP Reference Number 46

. Design a Procedures Control and Administrative Program Document Review................................................................... 57 SEP Reference Number 52 Engg

. Establish Supervisory Accountability for Workers Radiological Practices Radiological Work Practices Program................................................ 56 SEP Reference Number 54

. Complete implementation of Radiological Enhancement 8'rogram Clean Controlled Area Disintegrations >1,000 CountsMinute Per Probe Area

..................17 Collective Radie$on Exposure....................................................... 11 Volume of Low-Level Solid Radioactive Waste........................................... 12 Contaminated Radiation Controlled Area............................................... 55 SEP Reference Number 58

. Revise Physical Security Training and Procedure Program Loggable/ Reportable incidents (Security)................................................ 58 SEP Reference Numbers 60 & 61

. Improve Controls OverSurveillance Test Program

. Modify Computer Program to Correctly Schedule Surveillance Tests Number of Missed Surveillance Tests resulting in Licensee Event Reports.................... 28 BEP Reference Number 62

. Establish interim System Engineers Temporary Modi 6 cations............................................................. 59 Engineering Assistance Request (EAR) Breakdown..................................... 61 Engineering Change Notice Status.................................................... 62 Engineering Change Notices Open.................................................... 63 SEP Reference Number 68

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

..............................................65 Ucense Candidate Ex ams......................................................... 66 SEP Reference Number 71

. Improve Controls over Temporary Modifications Temporary Modi 6 cations

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bPORT DisTaisurion List R. L Andrews C. A. Marasco G. C. Bishop T. J. Mcivor C. E. Boughter K. A. Miller C. J. Brunnert P. A.Mruz J. W. Chase R. J. Mueller R. G. Conner Nuclear Ucensing (7)

G. M. Cook T. L Patterson M.R. Core R. L Plott T. R. Dukarski W.J.Ponec H. J. Faulhaber D. G. Ried S. K. Garnbhir M. J. Sandhoefner J. K. Gasper F. C. Sco6 eld W. G. Gates H.J.Se8ck S. W. Gebers R. W. Short D. C. Gorence J. L Skiles R. H. Guy R. D. Spies (2)

A. L. Hale D. E. Spires K. R. Henry M. A. Tesar J. B. Herrnan J. J. Tesarek R. L. Jaworski J. W. Tills J. W. Johnson D. R. Trausch W. C. Jones B. J. Van Sant D. D. Kloock L P. ' alEng W

M. Edwards (7)

G. R. Wiliams L T. Kusek S. J. Wilrett B. R. Livingston t

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