ML20212E724

Performance Indicators Rept, for Sept 1997

ML20212E724
Person / Time
Site:	Fort Calhoun
Issue date:	09/30/1997
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20212E710	List: LIC-97-0174, Forwards Fort Calhoun Station Performance Indicators, for Sept 1997 ML20212E724
References
NUDOCS 9711040038
Download: ML20212E724 (89)

Text

. _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

l OMAHA PUBLIC P'OWER DISTRICT FORT CALHOUN STATION PERFORMANCE INDICATORS .

SEPTEMBER 1997 SAFE OPERATIONS PERFORMANCE EXCELLENCE COST EFFECTIVENESS E$A* A08!! So85$es R PDR 1

. _ _ -- - . _ _ .~

. i . .

Table of Contents / Summary em TABLE OF CONTENTS /_EMM MAF.E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Wil MONTHLY. OPE RATIN G RE PORI . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iv WAN O PERFORMANC E IN DEX TREND . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v -

W AN O PE R FORMAN C E IN D EX IN DIC ATOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vi  ;

' WANO PERFORM ANCE INDICATOR TRENDS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vil FORT CALHOU N STATION RE PORT SU M M ARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . viii

• . NUCLEAR P.R.OGRAM GOALS AND OBJECTIVES , . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . ix-xil WANO PERFORMANCE INDICATORS U nit Ca p ability Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Unplanned Capability Loss Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Unplanned Automatic Reactor SCRAMS per 7000 Hours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 High Pressure Safety injection System . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . 5 Auxiliary Feedwater System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Emergency AC Power System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 Thermal P erformance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Fuel Reliability Indicator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 Secondary System Chemistry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Collective Radiation Exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 Industrial Safety Accident Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 Volume of Low Level Radioactive Waste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 S AFE OPERATIONS Disabling injury / Illness Cases Frequency Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 Recordable Injuryllliness Cases Frequency Rats . . . , . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . 16 Clean Controlled Area Contaminations 21,000 Disintegrations / Minute per Probe Area ......................................... 17 Preventable / Personnel Error LERs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 i

E r

Table of Contents / Summary:

Licensee Ev60t Report (LER) Root Cause Breakdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 Viol ation Trend . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

20 Maximum individual Radiation Exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 Significant Events . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ._ . . . . . . . . 22 Missed Survoillance Tests Resulting in LERs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23

, PERFORMANCE Station Net G eneration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 Forced Outage Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 6 U nit C apacity F actor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 7 Equivalent Availability Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28 Unplanned Safety System Actuations I N PO Definition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 9 N RC De finition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 30 G ros s He at Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , 31 Daily Thermal Output ........................................,..................,.. 32 Equipment Forced Outa,es per 1.000 Critical Hours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33

. Chemistry Acilon Levels Exceeded - Event Days . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . 34 Primary System Lithium % Hours Out of Limit .......,................................... 35 COST

, Cents Per Kik watt Hour . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 7 DIVISION AND DEPARTMENT PERFORMANCE INDICATORS Maintenance Workload Backlogs (Corrective Non-Outaga) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . 39 Ratio of Preventive to Total Maintenance .... ............................. .... 40 Percentage of Total MWDs Completed per month identified as Rework . . . . . . . . . . . . . . . . , . 41 Ov e rtime . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 2 Procedural Noncompliance incidents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 in-Line Chemistry Instruments Out-of-Service . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 44 li

. }

Table of Contents / Summary o Hazardous Waste Produced . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 5  ;

- Contaminated Radiation Controlled Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46

. - Radiological Work Practices Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 Document Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 8 Loggable/ Reportable ir.cidents (Security) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49 t

Temporary Modifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 .

Outstanding Modifications ' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 Engineering Assistance Request (EAR) Breakdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 Engineering Change Notices .

Status....................................................................53 Open.....................................................................54 Safety System F eilures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 5 Licensed Operator Requalification Training ....................... ...................... 56  ;

Ucense Candidate Exams . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 Condition Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 58 Cycle 18 Refueling Outage -

MWD Planning Status ........................................ ........... .. 59 Overall Project Status . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 Outage Modification Planning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , 61 On-Line Modification Planning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 62 Progress of 1997 On-Line Modification Planning ..............., ..,..................... 63 ACTION PLANS. DEFINITIONS. SEP INDEX & DISTRIBUTION LIST Ac tion Plan s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64 Performance Indicator Definitions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 66

- Safety Enhancement Program index ............................ ..................... 74 Report Distribution Ust ............................................................. 76 til

FORT CALHOON STATION SEPTEMBER 1997  ;

Monthly Operating Report OEERATIONSEUMMARY The Fort Calhoun Station operated at a nominal 100% power until September 8,1997, at 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br />. At this time, reactor power was reduced to less than 60% to repair a condenser E circulating water valve in the "B" Condenser. The power reduction was completed ou "

September 9,1997 at 0144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> with reactor power stabilized at 56%. On September 9,1997 at 2129 hours0.0246 days <br />0.591 hours <br />0.00352 weeks <br />8.100845e-4 months <br />, a reduction in power began due to indicated leakage in "B" Condenser. The reactor was taken to Hot Shutdown (Mode 3) and was subcritical on September 13,1997 at 0408 hours0.00472 days <br />0.113 hours <br />6.746032e-4 weeks <br />1.55244e-4 months <br />. Repairs to "A" and "B" condensers were completed and the reactor achieved criticality on September 13,1997 at 0408 hours0.00472 days <br />0.113 hours <br />6.746032e-4 weeks <br />1.55244e-4 months <br />. The reactor reached a nominal 100% power level on September 19,1997 at 0115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br /> and remained there throuph the end of the month.

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WANO PERFORMANCE INDEX TREHD The Wano Performance IndexTrend calculation is made up of eleven variables, each value is weighted to arrive at an overallindex value. INPO calculates the Wano Performance Index value based on the industry reporting the information each quarter.

The variables are calculated over a defined period of time, as listed below.

PERFORMANCE INDICATOR WElGHTED FACTOR TIME Unit Capability Factor 16 24 Months

- Unplanned Capability Loss Factor 12 24 Months High Pressure Safety injection 10 24 Months Auxiliary Feedwater 10 24 Months

' Emergency AC Power 10 24 Months Unplanned Auto Scrams /7000 Hours 8 24 Months Collective Radiation Exposure 8 24 Months Thermal Performance 1ndicator 6 12 Months Secondary Chemistry Indicator 7 12 Months Industrial Safety Accident Rate 5 12 Months Fuel Reliability indicator 8 Quarterly v

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0.00 UCF UCLF W S1 APW EACP CRE (JAS7 FRI CPI TR ISAR WANO PERFORMANCE INDEX INDICATORS This graph shows the difference between the Maximum No. of points for each WANO indicator and the actual value achieved by Fort Calhoun. r The cunent graph shows the difference between August '97 and September'97.

CALCULATED.OVERA1YEAREERIOD CALCULATED _OVER A_12. MONTH RERIOD UCF Unit Capability Factor TPI Thermal Perfomance Indicator UCLF Unplanned Capability Loss Factor CPI Secondary Chemistry Indicator HPSI High Pressure Safety injection ISAR Industrial Safety Accident Rate AFW Auxiliary Feedwater EACP Emergency AC Power CALCt8 LATED.OVER A QUARTERLLEERIOD UAS7 Unplanned Auto Scrams / 7000 Hours FRI Fuel Reliability indicator f CRE Co!!ective Radiation Exposure vi

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l WANO PERFORMANCE INDEX TRENDS l

- (As compared to previous month) -

4 Unit Capability Factor . Increased Unplanned Capability Loss Factor Decreased -

High Pressure Safety injection No Chatsge Aux. Feedwater System No Change

, Emergency AC Power Decreased Collective Radiation Exposure No Change Unplanned Automatic Reactor Scrams No Change  ;

• Fuel Reliability Decreasing Chemistry Indicator Decreasing Thermal Performance No Change industrial Safety Accident Rate No Change i

O Vii .

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FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT September 1997-

SUMMARY

POSITIVE TREND REPORT ~ The following performance indicators exhibited adverse treads for the reporting month.

A performance indicator with data reprosenting three consecutive months climproving EuelReliability_ Indicator performance or three consecutive months of (Page 9) performance that is superior to the stated goal is cxhibiting a positive trend per Nuclear Malatenance_ Workload _ Backlogs Operations DMslon Quality Procedure 37 (NOD- (Page 39)

ContaminatedRadiationfontrolledArea The following performance indicators exhibited (Page 46) positive trends for the reporting mondt INDICATORS NEEDING INCREASED UnplannedAutomaticReactor_ Scrams MANAGEMENT ATTENTION REPORT

_(P g 4)

A performance indicator with data for the IhermalEerformance reporting period that is inadequate when (Page 8) compared to the OPPD goal is defined as

• Needing increased Management Attention

• per IndustdaLSafetyAccidentRate (NOD-OP-37).

(P ge 12)

CollectivaRaolationExposure ljnplanned. Safety _SystemActuations (Page 11)

(P ge 30)

Recordable _lajuryAliness_Erequency_ Rate GrossileatRate (Page 16)

(Page 31)

Chemistryletbnievels_ Exceeded ADVERSE TREND REPORT (Page 34)

A performance indicator with data representing CentsReLKilowattBout three consecutive months of declining (Page 37) performance er three consecutive months of ,

performance that is trending toward declining as EroceduralNonComplianceJacidents determined by the Manager - Nuclear Licensing, (Page43)

• Maintenance only constitutes an adverse trend per Nuclear Operations Division Quality Procedure 37 BadiologicaLWorkEracticesRrogram

- (NOD-QP-37). A supervisor whose performance (Page 47) indicator exhibits an adverse trend by this d;finition may specify in written form (to be Outstanding _ Modifications published in this report) why the trend is not (Page 51) adverse, viii

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l NUCLEAR PROGRAM

-1997 GOALS AND OBJECTIVES EUIUREEQC U S_and. RELATIONSHIP _toIHANGE The nation's electric utility industry is passing through a period of significant organizational, financial and cultural changes. In this new era, change is inevitable, progress and success are not. Fort Calhoun -

. must react to these changes while improving capacity, SALP ratings and INPO ratings.

Wa must KNOW OUR COSTS to CONTROL COSTS. Understanding cost is essential to controlling it,

. cnd controlling ccst is essential to competing in today's market.

Wa are a learning organization. We must BUILD ON OUR HIGH PERFORMANCE CULTURE.

Individuals at all levels must take responsibility for their actions and must be committed to improve their own performance.

OUR CULTURE MUST SUPPORT THE NEW STRATEGIES. We must continue to develop and implement strategies that will allow us to effectively compete in the evolving market while still maintaining the highest levels of safety and reliability. Communicating is our key to improving. Follow up and feedback must be candid, forthright and timely.

W3 recognize that change causes disruption of work and work flow. That change requires increased management direction. We need IN-DEPTH, RELENTLESS ATTENTION to our NEW FOCUS / STRATEGIES.

VISION To be recognized as the best nuclear organization in the world and to preserve nuclear energy as a viable future energy source.

MISSION

Tha safe, reliable and cost effective genemtion of electricity for OPPD customers through conservative decision making and the professional use of nuclear technology. We will conduct these operations to cssure the health, safety, and protection of our personnel, the general public, and the environment.

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GOALS Goal 1: .' SAFE OPERATIONS Supports: April 1996 Corporate Strategic Plan Goal 3, Objective: 3 & 4 :

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

organization; Individuals demonstrate professionalism through self-ownership and personal initiative and open communication.

c..

1997 Prioritiesi

.-- Achieve an overall SALP Rating of "1" in 1997.'

. . Focus on Achieving an INPO Rating of "1" in 1998.

. Reduce 1997 NRC violations with no violations more severe than level 4.

. No unplanned automatic reactor scrams or safety system actuations.

Objectives to support SAFE OPERATIONS.

OBJECTIVE 11:

No challenges to a nuclear safety systems.

OBJECTIVE 1-2:

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

OBJECTIVE 13:-

Identify conditions BEFORE they affect plant safety and reliability. Address every safety concern.

OBJECTIVE 1-4:

Achieve all safety-related 1997 performance indicator goals in the Performance Indicator Report.

OBJECTIVE 15:

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

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

NUCLEAR PROGRAM -

1997 GOALS AND OBJECTIVES FUTURE FOCUS and RELATIONSHIP to CHANGE The nation's electric utility industry is passing through a period of sigr0ficant organizational, financial and cultural changes, in this new era, change is inevitable, progress and success are not. Fort Calhoun must react to these changes while improving capacity, SALP ratings and INPO ratings.

We must KNOW OUR COSTS to CONTROL COSTS. Understanding cost is essential to controlling it, and controlling cost is essential to competing in today's market.

We are a learning organization. We must BUILD ON OUR HIGH PERFORMANCE CULTURE.

Indiviauals at all levels must take responsibility for their actions and must be committed to improve their own performance.

OUR CULTURE MUST SUPPORT THE NEW STRATEGIES. We must continue to develop and implement strategies that will allow us to effectively compete in the evolving market while still maintaining the highest levels of safety and reliability. Communicating is our key to improving. Follow up and feedback must be candid, forthright and timely.

We recognize that change causes disruption of work and work flow. That change requires increased management direction. We need IN-DEPTH, RELENTLESS ATTENTION to our NEW FOCUS / STRATEGIES.

YlSION To be recognized as the best nuclear organization in the world and to preserve nuclear energy as a viable future energy source.

MISSION

. The safe, reliable and cost effective generation of electricity for OPPD customers through

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

. public, and the envuonment.

ix

OPPD. NUCLEAR ORGANIZATION GOALS 1997 Priorities Goal 2: . PERFORMANCE (Continued)

OBJECTIVE 2 3:

Achieve all performance-related 1997 performance indicator goals in the. Derformance Indicator Report. Focus on performing basic skills well, while pursuing efficient, cost-effective work processes. Identify the barriers to excellence and resolve them.

OBJECTIVE 2 4:

.. Plan for the completion of the 1998 refueling outage in 42 days or less.

OBJECTIVE 2 5:

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

Goal 3: COSTS Supports: April 199G Corporate Strategic Plan Goal 2, Objectivo: 1, 3, and Goal 5, Objective: 1 Operate Fort Calhoun cost effectively to contribute to OPPD's " bottom line". Cost consciousness is exhibited at alllevels of the organization.

1997 Priorities:

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

. Streamline work process to improve cost effectiveness.

. Implement Opportunity Review recommendations.

Objectives to support COSTS:

OBJECTIVE 3-1:

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

- OBJECTIVE 3 2:

Significantly reduce operating costs through full support of Utilities Service Alliance initiatives by

. maximizing sharing of resources, leveraging of buying power and elimination or reduction of redundcnt support services.

Goals Source: Lounsberry (Manager) xii

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UNIT CAPABILITY FACTOR UCF is defined as the ratio of the available energy generation over a given period of time to the r:ference energy generation over the same time period, expressed as a percontage. The UCF for September 1997 was reported as 74.5%. The year-to-date UCF was also reported as 86.9%, the UCF for the last 12 months (October 1996 through September 1997) was 73.7%,

and the 36-month average (October 1994 through September 1997) was reported as 80.5%

Energy Losses:

. Forced Outage - Condenser circulating valve repairs and leakage on Condenser "O,"

Event Period: September 10, thru 13,1997, e Forced Outage - Circumferential cracking of a weld down stream of a moisture separator due to high system stresses, Event Period: May 28, thru May 29,1997.

. Forced Outage - Circumferential cracking of a weld down stream of a moisture separator due to high system etresses, Event Period: May 28, thru May 29,1997, e Forced Outage - Steam leak in the fourth stage extraction steam system, Event Period: April throu0h mid May 1997.

• Forced Outage - Due to a steam leak in the fourth stage extraction steam system, Event Period: April 1997.

• 1996 Refueling Outage - Event Period: Sept, through Nov.1996

• Forced Outage - MOV-CV leakage, Event Period: Dec.1996 Tha Year 2000 WANO industry goal is 87% and the industry current best quartile value is cpproximately 85% The 1997 Fort Calhoun annual goal for this indicator is a minimum of 96.0% The maximum index point value for this indicator is 16. At the end of the Septembcr 1997, the FCS Value was 12.56. This compares to the previous month's value 12.49.

D:ta Source: Generation Totals Report & Monthly Operating Report Accountability: Chace Trend: None 2

c Moni.ly Unplann:d C:p:bility Less F:: tor

= RO1"fn"b"!.Mia%

+ Year 2000 WANO inciustry Goal (4.5%)

80%

70% --

60% -- 56 H%

50% --

40% -- 30.42% 30.50 %

30% -- - -

0.00% 24 50%

1.57% 0.00 % 0.00 % 0.00 % 0.00 %

0.00% #

20%

10% -- .. ['  ;  ;  ;  ;  ; p' '0  ? 7~ -*

0% . - -

.= . - , . . . . . .

] z 8 j ,5  %

u a

2 } m

1. 8 a

,? <

?

d UNPLANNED CAPABILITY LOSS FACTOR

- This indicator shows the plant monthly Unplanned Capability Loss Factor (UCLF), a rolling 12-month average, the OPPD goal, and the Year 2000 WANO goal. UCLF is defined as the ratio of the unplanned energy losses during a given period of time, to the reference energy generation expressed as a percentage. Unplanned energy loss is defined as energy not produced as a result of unscheduled shutdowns, outege extensions, or load reductions due to causes under plant management control. Energy losses are considered to be unplanned if thay are not scheduled at least fot.r weeks in advance.

The UCLF for the month of September 1997 was reported as 24.5, the Year-To-Date UCLF was 13.14%, the UCLF for the last 12 months (October 1996 through September 1997) was 12.47%, and the 36-month average UCLF (October 1994 through September 1997) was reported as 9.3% at the end of the month.

The Year 2000 WANO industry goal is 3.0% and the industry current best quartile value is approximately 3.2%. The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 1.58%.

The maximum index point value for this indicator is 12. At the end of September 1997 the FCS Value was 11.80. This compares to the previous month's value of 11.96. .

Data Source: Generation Totals Report & Monthly Operating Report Accountability: Chase-Trend: None 3 l 1

-s- 12MrthRdengAmrage

• - res neamor swans ibr 7,000 Hass Ot6cd forlast 36 mrths

-*- FatodhanGad(a0)

Year 2000WNOlnistryGod(1) 3-2 --

. -N. "

N:  :  :  :  :  :  :

0: .0 0 0 0 0 0 0 0 0 0 0 Od Nw Dec Jan Feb ihr Apr May Jme JtJy Aug Sep UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7000 HOURS CRITICAL The upper graph shows the 12-month rolling average, the 36-month average, the OPPD goal for 1997 and the Year 2000 WANO goal. The lower graph shows the number of unplanned automatic reactor scrams that occurred during the last 12 months. This indicator is defined as the number of unplanned autom6 tic scrams that occur per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of critical operation.

There were no unplanned automatic reactor scrams during the month of September 1997. The 12-month rolling average (October 1996 through September 1997) was 0.

The 36-month value (October 1994 through September 1997) was 0.310.

The 1997 Fort Calhoun Station goal for this indicator is 0. The Year 2000 WANO 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 maximum index point value for this indicator is 8. At the end of the September 1997, the FCS Value was 8.0. This compares to the previous month's value of 8.0.

~

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

Accountability: Chase Trend: Positive 4

i .

l MMR MonthlyHPSISystemUnavailabilityValue

-e: 12 Month Rolling Average Fort calhoun Goal (0.003)

-*- Year 2000 WANo industry Goal (0.02) 0.02 - * = = = = = = = = = = =

0.015 -- ,

0.01 -

0.005 - , _ _ , , , , , , _ _ , , , , ,

T ' '

0 , , 7 , l oct Nov Dec Jan Feb Mar Apr May June July Aug sep HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCF This indicator shows the High Pressure Safety injection (HPS!) System unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for September 1997.

Toe HPSI System unavailability value for the month of September 1997 was 0.0. There were 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of planned unavailability, and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned unavailability, during the month. The 12 month rolling average was (October 1996 through September 1997) was 6.66 X E-5, and the year-to-date HPSI unavailability value was 9.8 x E-4 at the end of the month. For the previous year there was a total of 1.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 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.

The 1997 Fort Calhoun year-end goal for this indicator is a maximum value of 0.003. The Year 2000 WANO industry goal is 0.02.

TM maximum index point value for this indicator is 10. At the end of September 1997 the FCS Value was 10. This compares to the previous month's value of 10.

Data Source: Phelps/Schaffer(Manager / Source)

Accountability: Phelps/Schaffer Trend: -None 5

I l

l

~

l EEI M onthly Auxinary Feedwater System Unavailability j

-*-12 Month AFW Unavailabilit 1

-*- Fort Calhoun Goal (0.01) y ,

-*- Year 2000 WANO Industry Goal (0.025) 0.025 -

0.02 - 6 a  :. a a  :  :.  :  : a l 1 ,

0.015 1 l ooj - - - - - U - '

:  :  : 4

~'  !

0.005 - ng flr g

. 9 -

% = = ;gl V

M" ,

k g_@ ~ "

EEE I  ! '

L"E ,

1997 Oct Nov Dec Jan Feb Mar Apr May June July Aug Sep

)

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

S;ptember 1997.

The AFW System Unavailabi:'.y Value for September 1997 was 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. There were 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of planned and 12.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> of Unplanned Train Unavailability hours during the month.

The 12 month rolling average (October 1996 through September 1997) was 0.0049, and the y=r-to-date unavailability value was 0.0054 at the end of September 1997.

Tha 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 0.01.

Tho Year 2000 WANO industry goal is 0 025.

Tha maxin:Jm index point valuc for this indicator is 10. At the end of September 1997, the FCS Value was 10. This compares to the previous month's value of 10.

. D:ta Source: Phelps/Fritts (Manager / Source)

Accountebility: Phelps/Fritts Tr;;nd: None 6

l

l m Monthly Em ergency AC Power Unavaltability Value Year to Date Een etgency AC Power UnavaMability Value

- e.- Fort Calnoun Ooal(0.024)

--e-- Year 2000 W ANO lndustry coal (0.02 5) 0.04 .-

0.035 -- S 0.0: --

0.025 -- g 3 g g- g r .. g g g g 0.02 --

0.016 --

0.01 - -

0.005 --

, a M 8 m M ,

5 5 5 4 $ I I I j k I I EMERGENCY AC POWER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Emergency AC Power System unavailability value, as defined by WANO in the Safety System Peiformance Indicator Definitions, for the month of September 1997. The Emergency AC Power System unavailability value for September 1997 was 0.029. The Emergency AC Power System unavailability value year-to-date was 0.014 and the value for the last 12 months (October 1996 through September 1997) was 0.011.

Monthy Stati_stics Ebnned Unavailability: DG-1: 6.2 DG 2: 4.0 Total: 10.2 YTD: 150.5 Unclanned Unavailability: DOa: 8.0 DG-2: 23.5 Total: 31.5 YTD: 63.9 There were a total of 188.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-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 1997 Fort Calhoun year-end goal for this indicator is a maximum value of 0.024. The Year 2000 WANO industry goal is 0.025. The maximum index point value for this indicator ,

is 10. At the end of September 1997, the FCS Value was 5.25 This compares to the j previous month's value of 10.00.

Data Source: Phelps/Ronning (Manager / Source) l Accountability: Phelps/Ronning Trend: None 7

, :w

r- 1 MortMyThrmalPerformance

, ,12 Month Rolling Average Fort Calhoun Goal (99.8Y4

+ Year 2000 WANO Industry Goal (99.5%)

100%.. _

} - '

5 -

.  !? it e . .

O .

i.-  ?, .

99%.- 5  :

1996 RFO { l ,

+

, Y  ; , l

~

'l

] } i  !.

,9s  :  : , .

l

-3 8 z j E i

u a k &

< z z

$ i,t <

!P m

& j THERMAL PERFORMANCE This indicator shows the monthly Thermal Performance Value, the rolling 12-month average, the OPPD goal, and the Year 2000 WANO goal.

The thermal performance value for the month of September was 100%. The year to date value was reported as 99.9%. The 12 month rolling average (October 1996 through September 1997) was reported as 99.8%.

The 1997 Fort Calhoun year-end goal for this indicator is an index value which is > 99.7%.

The Year 2000 WANO industry goal is 99.5%.

The maximum index point value for this indicator is 6. At the end of September 1997, the

. FCS Value was 6.00 This compares to the previous month's value of 6.00.

Data Source: Piielps/Naser(Manager / Source)

Accountability: Phelps/Naser

. Trend:' Positive 8

Foi Rolla bility(E.4)

--*-- Yoct 2000 t7ANO Geal (6 x 10 4 Ulcrocurbs/3 rem) 1997 o on1147E.4 320 -

l280 -

E 240 +

-l 200 -

f.160- 1996 I [ RFO sti 28.7 as ei se 1 22.s 33

• = 40 -j _ _ d_8 t o.i c.,

is.s rm ri f""1 r- 1 11 C _ _

U $ i E 1  % 1 i E I E &

• O ;g o p u. I 4 I 4 > < m FUEL RELIABILITY INDICATOR Ccolant activity data through October 2,1997 had not reached an equilibrium level from the September shutdown, therefore the August 1997 evaluation of 15 leaking rods at core average power is still valid. If the leaking rods are at 70 % or 50% of core average power, the number of leaking rods will change to 26 or 43, respectively. The cesium data from the September 10th shutdown continues to indicate the leaking fuel to be in a mixture of second and third cycle bumed fuel (Batches S and T) which have the original grid design. The monthly FUEL RELIABILITY INDICATOR (FRI) for September 1997 was 66 X 10* microcuries/ gram which was an increase from the August 1997 FRI of 61 x 10d microcuries/ gram.

The Cycle 17 monthly FRI is trending lower than the Cycle 16 FRl at the same time in the fuel cycle due to the large contribution of the lodine-134 from the " recoil" Uranium. The lodine-134 activity is released to the coolant from the recoil activity thet is plated out on fuel assembly surfaces due to fuel failures in prior cycles. In the FRI equation, the lodine-134 activity is subtracted from the lodine-131 activity. This cycle, the recoil activity is trending two times higher than Cycle 16 while the lodine-131 is trending similar to the Cycle 16 values at the same point in the cycle. Consequently, the Cycle 17 calculated FRI value is trending lower.

The plant is currently in Action Level 3 per Standing Orde- S0-0-43, Fuel Reliability Action Plan, based on the September prediction of 15 core average power failures. The 1997 Fort Calhoun Station FRI Performance Indicator goalis to maintain FRI celow 147 E-4 microcuries/ gram. This goal is based upon previous cycles fuel performance, results of the most recent fuel inspection and reconstitution ,

campa'gns, and an improved fuel failure resistant grid design in the new assemblies (Batch U)in the Cycle 17 core.

The maximum index point value for this indicator is 8. At the end of the September 1997, the FCS Value was 1.11. This compares to the previous month's value of 2.13.

Data Gource: Guinn/Guliani(Manager / Source)

Accountability: Chase /Stafford Trend: Adverse .

9

m Monthly Chemistryindicator Fort Calhoun ooal(1 A) 3-2.7 5 - ,,,,

2.43 i 2.5 -

2.25 --

2--

1.75 -

1,32 1.31 1.27 1.14 1.32 1.5 + 1Me 1.2 5 -

1 . 1996 RFO o.es 0.5 .  :  ;  !

I

s D

O 2 o

n E S 6 3 I E 4

D 2

E $

E 4

I m

4 SECONDARY SYSTEM CHEMISTRY Criteria for calculating the Secondary System Chemistry Performan:e Iadex (CPI) are as follows:

1) the plant is at greater than 30% power.

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

The CPI for Septemt er 1997 is 2.43. The CPI value for the past 12 months (Octob;r 1996 through September 1997) was 1.20. The CPI value in the industry's upper quartil- is 1.17.

Six parameters are used in the CPI calculation. Four of the parameters were below the INPO mean value which are as follows: 1) steam generator chloride,2) sulfate,3) feedwater iron, and condensate pump discharge dissolved oxygen. Steam Generator sodium was above the mean value and has remained unchanged from the previous month. FH-6 copper remains above the INPO mean but is lower than the previous months value.

The maximum index point value for this indicator is 7. At the end of September 1997, the FCS Value was 3.34. This compares to the previous month's vales of 5.29.

Data Source: Hamilton /Ostien (Manager / Source Acce,untability: Harnilton Trend: None 10 l

m Monthly Personnel Radiation Exposure

--+-- Cumulative Personnel Radiation Exposure

- FCS Goal 38 person-REM 40 --

35 --

30 --

b 25 --

20 --

g 15 --

n.

.10 " 3.0 64 .375 5.753 7.099 .

~

3'3" 5- . 68 1.678 0' , , , ,  ;  ;  ;

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec COLLECTIVE RADIATION EXPOSURE ,

The 1997 Fort Calhoun goal for Collective Radiation Exposure is set at 38.0 person-REM.

The exposure for September 1997 was 7.099 Person-Rem (ALNOR).

The year-to4 ate exposure through the end of September 1997 was 32.630 Person-Rem (ALNOR).

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

The Year 2000 WANO industry goal for collective radiation exposure is 120 person-rem per year. For the three year period (October 1994 through September 1997), the total .

collective radiation exposure is 408.57 person-rem (ALNOR). The Fort Calhoun Station annual average over 3 years was 136.19 person-rem per year (ALNOR).

The maximum index point value for this indicator is 8. A' the end of September 1997 the FCS Value was 8.00 This compares to the previous month's value of 8.00 Data Source: Chase / Williams (Manager / Source)

Accountability: Chase /Gebers Trend: Needing increased Management Attention SEP54 11 l

--o-- Conthly induetrial Accident Rate

--e-- 12 Conth Rollig Average

--o-- FCSYear thd ooal(0.50)

Year 2000 WANOlndustry Goal (4AO) .

1.2 1-OJ 0.6 ; , _ , , _ _ , , , ,

5 g - . . . - - - -

0.2 - -

0 , -  :  ; Y I  ::

Oct Nov Dec Jan Fsb Mar Apr May June July Aug Sep INDUSTRIAL SAFETY ACCIDENT RATE The purpose of this indicator is to monitor rrogress in improving industrial safety performance for utility personnel permanently assigned to the station. Contractor work-hours are not included in the indicator. This indicator is defined as the number of accidents per ?00,000 work-hours workec' for all utility personnel permanently assigned to the station that result in any of following:

• one or more days of restricted work (excluding the day of the accident.)

. One or mom days away from work (excluding the day of the accident.)

Fatalities.

ISAR = (number of restricted-time 2ccidents + lont. time accidents + fatalities)2200.0a0 (number of station person-hours worked)

Tho Fort Calhoun Station industrial safety accident rate for the month of September 1997 was 0.00. The 12 month rolling average (October 1996 through September 1997) was 0.0794. The y;;r to date value was 0.00 at the end cf Saptember 1997.

Th;re were no restricted-time and no lost-time accidents in September 1997. The 1997 Fort C:lhoun year-end goal is 50.50. The Year 2000 WANO industry goal is 50.40. The maximum index point value for this indicator is S. At the end of September 1997, the FCS maximum index point Value was 5.0 This compares to the previous month's maximum index point value of 5.0.

' D:ta Source: Sorensen/Blumenthal (Manager / Source)

Chase / Booth (Manager / Source) l Accountability: Chase /Gebers Trend: Positive 1

i 12

m _ .

C SI's'ily V; lum e of LLR"1 (3% ft.)

Yest.to-Date C:m utth s Radioactive C ast) Brrr,d - '

F;tt CSh ea c :1 (1200 cm.tt.)-

12 0 0 -r -

1100 -

1000 --

goi .-

000 -

} 100 -

h (00 -

.3 500 -

400 g q 300 g h N f 200 -- g g s d I  : -4 100 - 8 $ 2 s

,  ; - -  % r, , - _

Jan Feb Mar . Apt May Jun Jul Aug Sep Oct. Nov Dec 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, and the Fort Calhoun goal.

Et* JD' L Ane!mt of solio radwaste shipped off-site for processing during current month : 00.0 00.0 Volume of solid radwaste buried during September 1997 ; 12.7 0.36 Cumulative volume of solid radioactive waste buried in 1997 : 205.0 5.74 Amount of solid radwaste in temporary storage : ,

251.2 7.03 The 1997 Fort Calhoun Station goal for the volume of solid radioactive waste (buried)is 1200 cubic feet. The Year 2000 WANO industry goal is 45 cubic meters (1,589 cubic feet) per year. The industry upper ten percentile value is approximately 27.33 cubic meteic (965.3 cubic l- 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 Station's Index Number. ,

Data Source: Chase /Breuer (Manager / Source)

Accountability: Chase /Gebers Trend: None SEP54 L .l I

l 13

. ~ . .

I

\l l

l

SAFE OPERATIONS l Goal

A proactive, self-critical and safety conscious cu!ture is exhibited throughout the nuclear organization. i Individuals demonstrate professionalism through self-ownership and personal initiative and open communication.

?. 1 l

1 l

l 14

--+-- Wonthly Dioebling injuryMinese rtoquency

-A- 12 Wonth Rolling Average

+1997 F.C.S. Goal g.

0.9 + ,

0.8 -l I

0.1 -

e 0.6 e 0.8 ,: -

.. i -; A

__ ~ ~ '

0.4 1 O.3 +

0.2 -

=  % L 3

0.1 -

0 -  :  :  :  ;  ;  ;  ;

Oct Nov uc Jan Feb Mar Apr May June July Aug Sep DISABLING INJURY /lLLNESS FREQUENCY RATE (LOST TIME ACCIDENT RATE)

Tlels indicator shows the September 1997 Disabling injury / Illness Frequency Rate and the disabling injury / illness rate for the past 12 months (rolling average).

For the month of September 1997 t'1e disabling injury / illness frequency . ate was 0.00. For the

• - 12 month period (October 1996 through September 1997) the disabling injury / illness rate was 0.12. There were no disabling injury / illness cases reported for September 1997.

The 1997 Fort Calhoun Station year-end goal for this indicator is a nlaximum value of 0.5.

t D:ta Source: Sorenson/Blumenthal (Manager / Source)

A:: countability: Chase /Gebers

_ Trend: Mone SEP 25,26 & 27 l

I 15

---*--- M onthly Re cordable injuryttllne ss Fre que ncy R ate

--*- R ollin g 13 M o n th Av e r a g e

.. *-... F ort C alho u n O ost 4.6 -

4.0 3.8 3.0 +

e 3.5 -

. N u . ... i...... .. . h%

t.0 Oct New Dec Jan Feb M et Apr May June J uly Aug Sep ,

RECORDABLE INJURY /lLLNESS FREQUENCY RATE This indicator shows the monthl/ Recordable Injury / Illness Frequency Rate, a rolling 12 month average, and the OPPD goal. A recordable injury / illness c.ase 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 injwy/ illness cases frequency rate is computed on a rolling 12 month average.

The recordable injury / illness frequency rate for the month of September 1997 was 1.53.

The recordable injury / illness frequency rate for the past 12 months (October 1996 through September 1997) was 1.40.

During the month of September 1997, there was no recordable injuries. There has been a total of 7 recordable injury / illness cases in 1997. -

The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum vnlue of 1.5.

Data Source: Sorensen/Blumenthal (Manager / Source)

Accountability: Gebers _ -

Trer.d: Needing increased Management Attention SEP 15,25,26 & 27 l l

16

L a ContaminationEvents(Monthly)

+ Contamination Ewnts (YTD) ,

100 90 t ,

, 80 .

. "t 43 60 .. 37 i

SO .,.

40 4 l

3, W i 31 30 J. g l

20 .

10 a j _

1, . _ _ .L -.

0 --

Y b - -

Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec CLEAN CONTROLLED AREA CONTAMINATIONS >1,000 DISlNTEGRATIONS/ MINUTE PER PROBE AREA This indicator shows the Persorinel Contamination Events in the Clean Controlled Area for

, contaminations >1,000 disintegrations / minute per probe area for September 1997.

There was 6 contamination event in September 1997. There have been 63 contamination evnnts in 1997 through the end of September 1997.

Data Source: Chase / Williams IManager/ Source)

- Accountability: Chase /Gebera ,

Trend

None SEP 15 & 54 17

w - _ .

"I E*" /.

$ 2s . 18 Month Totals #

g -.- pr.v.nu bi.

-*- p.r.on.i error 32o-E g 1s % p 8 to q

N-T T#-

/

g3 "-* % _,

-~_ .

O

~ a s s a a a a 9

$a $s y$kbE a s 4 m ,

$s$ $s kk $ e $$$ h $

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

The graph shows the 18-month totals for preventable LERs, the 18-month totals for Personnel Error -

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

NOTE: Due to the way LERs are tracked & reported, this indicator is one-month behind, in August 1997, there were four events which was subseq'Jently reported as an LER. No LER's were categorized as Preventable and no LERs were categorized as Personnel Error for the month of August. The total LERs for the year 1997 is fourteen. The total Personnel Error LERs for the year 1997 is five.

The 1997 goal for this indicator is that the year-end values for the 18-month totals not exceed 12 ,

Preventable and 5 Personnel Error LERs.

Data Source: Tills /Matzke (Manager / Source)

Accountability: Chase Trend: None SEP 15 10

l J

l use l 5% Adtm l

, # 9j%. l DesPJn ,

+ . J'g, 19% ,

['l [4 -M. ,

0, i 6

.3w-

$ other Err.

6%

J mt 48%

LICENSEE EVENT REPORT (LER) ROOT CAUSE BREAKDOWN This indicator shows the LER9 by event date broken down by Root Cause Code for each of the past eighteen months from March 1,1996, through August 31,1997. To be consistont with the i Proventable/ Personnel Error LERs indicator, this indicator is renorted by the LER event date, as opposed to the LER report date.

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

NOTE: Due to the way LERs are tracked & reported, this indicator is one-month behind.

There were Four events in August 1997 that resulted in a LER.

l l

Data Source: Tills /Matzko (Manager / Source)

Accountability: Chase Trend: None i 19

._._.___________ _ __l

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

C PCS Cleed weiselene late *IA C PCShuactedwetselene(teoeld

.e- PCS Caed Viennelsen (tH%nih Averege) 6< ~ *CsWwaimmas mwnshwreen

. ; hg $ _,

+ betoa N Ciud waimane Wen

• wrese We*n N top W I '*hib - 4 I 1.. , l3 -

l ln%

'4< h i

O!

4 ls:

e; g_ _

y_ _ _

I 2 .=, =b d I

~

t

3

;t n, o m , , ,_ o Idet hr 64ay June July Aug Sep gr,g segt ggg Oct Nov Dec Jan Feb VIOLATION TREND This indicator illustrates a 12 month trend for Fort Calhoun Station Cited Violations, Non-Cited Violations and Cited Violations for the Top Quartile plants in Region IV. 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 lags 2-3 months behind the Fort Calhoun Station trend. This lag is necessary to compile information on other Region IV plants.

The following Inspection reports noting violations were received during September 1997:

Violationlavel lER.No. Iltle None To date, OPPD has received zero violations for inspections completed in the current SALP cycla.

Levellli Violations 0 Lovel IV Violations 0 Non-Cited _VJolations 0 Total 0 The 1997 Fort Calhoun Station Goal for this performance indicator is to be at or below the cited violation trend for the top quartile plants in Region IV.

Data Source: Tills /Cavanaugh (Manager / Source) .

Accountability: Tills Trend: None -

20

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

C Hghest kbnthly bdkdual Exposure tra ,

r"""1Hghest bdNdualExposure Year to date tra FCs Annual year end Goat 1000 rrMndNkival ,

1000 m

800  ;

, 700- - -

600- -

- - - 1

, 600 -

400-200 100 ,

0 Jan Feb Lhr Apr May Jun Jul Aug sep oct Nov Dec MAXIMUM INDIVIDUAL RADIATION EXPOSURE This indicator shows the highest exposure for an individual during the year 1997.

For the month of September 1997, an individual accumulated 738 milllRem, which was the highest Individual exposuro for the month.

For the year to date, an individual has accumulated a total of 843 milllRem (TLD). Tho 843 milllRem came from ALNOR readings, and in general, are higher than TLD readings.

The 1997 Fort Calhoun Station Annual Administrative year-end goal is a maximum of

, 1,000 milllRem from all sources of occupational exposure at FCS. The OPPD limit for the maximum yearly individual radiation exposure is 4,000 milllRem/ year from all sources of occupational exposure.

Octa Source: Chase / Williams (Manager / Source)

Accountability: Chase /Gebers Trend: None

l. ,

l l

21

M NRC Signmcant Events

-e- Indust y Awerage Trend 1 1 1+ _

n 0.5-o _ _1 _r - _,_=_r..._ =__ e ,..__2 ,_= _.= m : ,

y 92 93 94 95 1 95 2 95-3 954 96 1 96 2 96 3 96 4

- Year . Quarter INPO Sigrdficant Events (SEs) 3 3-

• i 2- 1 1 Il ' b:1 0 0 0 0 [gg pgg ;

0 0 0 o , n ,

93 94 PS 1 95 2 95-3 964 96 1 96-2 96 3 964 97 1 Year-Quarter NRC SIGNIFICANT EVENTS The following SEs were identified between the 2nd Quar 1er of 1992 and the 1st quarter of 1995 (as reported in the NRC's ' Performance Indicators tot Operating Nuclear Power Rcactors' report dated June 30,1995):

3rd Quarter 1992: The failure of a Pressurizer Code Safety Valve to reseat initiated a LOCA with the potential to degrade the reactor coolant pressure boundary.

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 A.C. units.

INPO SIGNIFICANT EVENTS The following SEs have been identified since 2nd Quarter of 1991 by INPO:

2nd Quarter 1992: Intake of transuranics during letdown filter change-out.

l 3rd Quarter 1992: Safety Valve malfunction (RC 142).

1st Quarter 1993: Inopeiability of Power Range Nuclear Instrumentation Safety Channel D.

2nd Quarter 1993: Inadequate control of Switchyard act?vities.

3rd Quarter 1993: Loss of reactor coolant due to malfunction of Pressurizer Safety Valse.

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

, 2) Unplanned dilution of Boron concentration in the Reactor Coolant System.

ist 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.

i l

Data Source: Nuclear Regulatory Commission & INPO ~

Accountability: Chase Trend: None l

l

-22

Missed STs Resulting in LERs i 3 ..

t 5

2. -

1 1._ _

4..

0 0 0 0 0 0 0 0 0 l 0 - >

-l 96 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec NUMBER OF MISSED SURVEILLANCE TESTS RESULTING IN LICENSEE EVENT REPORTS This indicator shows the Number of Missed Surveillance Tests (STs) at FCS, that resulted in Licensee Event Reports (LER)s during September 1997.

There were no missed surveillance tests resulting in LERs during September 1997.

The 1997 Fort Calhoun monthly goal for this indicator is 0, Data Source: Monthly Operating Report & Plant Licensee Event Reports (LERs)

Accountability: Chase /Phelps Trend :- None SEP 60 & 61 23

f a

' ~

j .

PERFORMANCE .

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

l 2

4 l

l 24

Not Generation (10,000 MWh) 34.29 35.1 35.14 u,43 u.4g 33,, f fi;IIIIIiIIIi 5 h b k $ 5 5 $ kk $ $

i STATION NET GENERATION During the month of September 1997, a net total of 259,030.2 MWh were generated by the Fort Calhoun Station. Cumulative net generation for Cycle 17 was 3,099,738.90 MWh ,

at the end of September 1997. Cumulative net generation for Cycle 16 was 5,418,326,6 l MWh, ,

I Data Source: Station Generation Report Accountability: Chase Trend: None  :

, i e

i 25 .

l l

. . . . . _ - . , _ . _ _ _ . . ....,,._,__._.._.,-.a..._,,,._..__w___.

m Monthlyforcedo"tage Rate

--+- RollinD 12 Month Average

+-- 1997 Fort Calhoun Goal (1.4%)

50% -

45%. 43%

40% -

35% -

31%

30% - .

25% -

20% -

15% -

10% ,

5%- 0  : 0  ;

, 07 07._]. 0% Qi_ pg. _ 0y. Oft - _0%

96 Oct Nov Dec Jan reb Mar Apr May June July Aug Sep FORCED OUTAGE RATE The Forced Outage Rate (FOR)for the month of September 1997 was 10%. The forced outage rate for the previous 12 months (October 1996 through September 1997) was 8.26%. The 1997 year-to-date FOR was 9.4% at the end of September 1997. This indicator needs incrossed management attention since it exceeds the FSS goal.

Energy Lossos are described in the " Unit Capability Factor" indicator, page 2 of this report.

The 1997 Fort Calhoun Station year-er.d goal for this indicator is a maximum value of 1.4%.

Dato Source: Monthly Operating Report Accountability: Chase Trend: Nono 26

, 4 lElC"3 Monthly UnM Capscity Feetor

. . .O . . Ye:r40-De*3 0s::3 Capacity Factor  !

---+--- unM Cepacity Factor for Cycle 17 1997 FC4 Goal (96.00%Q 110% w 100% d *'

k "** , - -

90% h .#

1. '8- .

., g ...I 80% <

m p _

Q i' 10% -

• < 4

' / ~

-b Y  !

60%'

f Cycle 17 / g.j $ , E

. $[vI sh p h 4 } h 'g E $ );

20s.- 1 1 4 yng . If c .

11 4 ,;, ,

ty , .%. s; 10%- ,

bLf C.18 Sep oct Nov Dec Jan Feb Met Apr k ey June July Aug UNIT CAPACITY FACTOR This indicator shows the plant monthly Unit Capacity Factor, the Unit Capacity Factor for the current fuel cycle, the year-to date, and the 1997 OPPD Station goal.

Unit Capacity Factor = Het Electrical Energy. Generated (MWH)

Max. Dependable Capacity (MWe) X Gross Hours in the Reporting Period Cycle 16 Unit Capacity factor was 76.76%.

At the end of September 1997, the Cycle 17 Unit Capacity Factor was 80.9%. The Unit C:pacity Factor for the last 36 months (October 1994 through September 1997) was 82.64.

Tha 1997 Fort Calhoun annual goal for this indicator is 96.00%.

Tho year-to-date value is 87.67%.

D:ta Source: Monthly Operating Report Accountability: Chase Tr nd: None L

27-

fe AverCoe MontNy EAF

-+-- ont Rolling Average 96.1 % 99.2 % 99.1 % 97.5% 97.5%

100%

• 94.3% T - - -

92.8 %

.g --

90% - 4

• - 4 3

e. -

80%. - 68.7 % 73.6 %

/

• %  :.  : 1 70%- P' } .

60% - ,

45.7%

50%-

40% - 1,9, R50 30% -

20% --

3.1%

-~

0% -

Oct Nov Dec Jan Feb Mar Apr May June July Aug sep EQUlVALENT AVAILABILITY FACTOR This indicator shows the plant monthly Equivalent Availability Factor (EAF), the year to- -

date average monthly EAF, the 12 month rolling average, and the OPPD goal.

The EAF for September 1997 was 73.59 %. The 12 month rolling average (October 1996 through September 1997) was 73.07%. The equivalent availability factor for the

, past three years (October 1994 through September 1997) is 82.45%.

The Fort Calhoun Station goal for this indicator is an EAF of 93.00%.

Data Source: Dietz/Mikkelsen (Managers / Source)

Accountability: Chase Trend: None 28'

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

y Safety System Actuations (INPO Definition)

,_. FCSGoal(0)

+ Industry Upper 10 Percentile (0) ,

3

< 2 1

4 0 0 0 0 0 0 0 0 0 0 0 0 0 ,

0 ,  :  :  :  :  : ,  :  :  :  :  :  :  :

96 Oct Nw Dec Jan l'ob Mar Apr May June July Aug Sep l l

UNPLANNED SAFETY SYSTEM ACTUATIONS -(INPO DEFINITION)

There were no WANO unplanned safety system actuations during the month of September 1997.

There were no WANO unplanned safety system actuations during 1996.

The 1997 Fort Calhoun goal for this indicator is 0.

Data Source: Monthly Operating Report & Plant Licensee Event Reports Accountability: Phelps Trend: None 29

(------) Saf;ty System Actuati:ns (NRC D0finiti:n) ,

i FCS C al(0) j C ritic al Hours j I

10 _. 1996 RFo . 800 t ,. . N -l1600 7" 6..

500 C ,

1400 $l 4" 300 )

• 200 b .

100 D -

'O l ,

o N D J F M A M J J A s ,

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

There have been no unplanned safety system actuations in the last 12 months. The 1997 Fort Calhoun goal for this Indicator is 0.

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

• Accountability: Phelps Trond: Positive 30 i

1

,w -- -

M Gross Heat Rate

-# - Year to.Date Gross Heat Rate Fort Calhoun Goal 14,75 -

1425 - a 6

13.75 -

13.25 -

12.75 -

• $ 12.25 -

g g 11.75 -

{

" 11.25 - '! .

m q s

~

h h h h IIE 10.25 - o D 9 EE EE "m 4 9.75 - ; } .[! j Q h 2 '+

_l .i l'. L ir ( ik ^%

96 Od Nov Dec Jan Feb Mar Apr May June Ady Aug Sep I

GROSS HEAT RATE This indicator shows the Gross Heat Rate (GHR) for the reporting month, the year to-date GHR, tha goals, and the year-end GHR for the previous three years.

Tho gross heat rate for Fort Calhoun Station was 10,350 BTUlkWh for the month of September 1997. The 1997 year to-date Average GHR was 10,172 Bid /kWh at the end of the month.

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

The 1997 Fort Calhoun year-end goal for the Average GHR indicator is 10.166 BTUlkWh.

. D:ta Source: Guinn/Schawe (Manager / Source)

Accountability: Phelps/Naser Trend: Positive Y

a 31

t----)1997 --m-Thermal Output Fort Calhoun 1495 MW Goal -o-Tech Spec 1500 MW LimTl 1600 e-e-e-e-e-a  : : : : : : :-e-: : = e-e-e-e-e-e-e-e-e-a 1400 1200 1000-800 000 ,

400 200 -

- " * *

• 5"O W D E & N N  % R DAILY THERMAL OUTPUT The thermal output graph displays the daily operating power level during September 1997, the 1500 thermal megawatt average technical specification limit, and the 1498 thermal megawatt Fort Calhoun goal.

FCS operated at a nominal 100% power until September 8,1997, when the reactor power was reduced to 60% to repair a condonser circulating water valve in the "B" Condenser. The reactor was placed in Hot Shutdown (Mode 3) and taken subcritical on September 10,1997 at 0408 hours0.00472 days <br />0.113 hours <br />6.746032e-4 weeks <br />1.55244e-4 months <br /> due to an indicated leakage in "B" Condent,er. Repairs to the "A" and "B" Condensers were completed and reactor criticality was achieved on September 13,1997 at 0408 hours0.00472 days <br />0.113 hours <br />6.746032e-4 weeks <br />1.55244e-4 months <br />.

The reactor reached a nominal 100% power level on September 19,1997 at 0115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br /> and remained there through the end of the month.

Data Source: Guinn/Schawe (Manager / Source)

Accountability: Chase /Short  ;

Trend: None j l

32

-+ - Morithey Equipment FoR

-e-- Equipment FoR/1,000 Critical Hrs. (Rolling 12. Month IntervQ Fort Calhoun Year 4nd Goals (0.2) i g..

1.75 --

15--

1.25 --

1-0.75 --

0,5 --

0.24 - A 4 i A N / \ \ /

^ ^ ^ ^ ^ ^

0

^ -

Oct Nby Dec Jhn Feb br Apr May June ly Aug Sep EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS The Equipment Forced Outage rate per 1,000 critical hours for the Rolling 12 month's from October 1,1996 through September 30,1997, was 0.286. TheYear-To Date rate per 1,000 critical hours for the months from January 1,1997 through September 30,1997 was 0.333.

The equipment forced outage that occurred on September 8.1997 was attributed to a faulty Condenser Circulating Valve in Condenser "B" Reactor rwer was reduced to 56%

to perform repairs on the valve. During the power reduction the plant also experienced a Loss of Vacuum due to leakage in the "B" Condenser. It was decided to place the plant into Hot Shutdown to complete the repairs. The reactor was returned to criticality on September 13,1997 and reached a nominal 100% reactor power on September 19,1997.

The 1997 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)

Accountability: Chase /Phelps Trend: None 33 e

3 c wv -

CHEUISTRY ACTIQU LEVELS EXCEEDED N 3 l - 'E 1

i e

~

E i &gM i i j j I  ! l $ l I i { I  ! $ $

1 CHEMISTRY ACTION LEVELS EXCEEDED - EVENT DAYS The Chemistry Action levels Exceeded indicator tracks the number of days in which themistry paramoteis exceeded a corresponding action Icvel for the reporting month, as web as a 12-month everage of days an action levelis exceeded. The parameter c:: tion it.vpfa cm delinoated in Chemistry procedure CH-AD 0003, " Plant System Chemica! Umtis End (nrrective Actions". j l

An action level is considerad to have been exceeded for the purpose of this indicator, I i

whenever the parameter exceeds the CH AD-0003 acllon level for the current system mode, with the exception of the Steam Generators during Mode 1. j The ?, team Generators are considered to have exceeded an action level in Mode 1 when the plant power is greater than 30% and the power is ch nging 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 1997 Fort Calhoun goal for this indicator is the 12-month average of two event days per month. There is no goal established for the number of event days per t Individu I month. .

H4torical 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 months were reached.

There were 6 Event Days in September.

Data Source: Chase / Hamilton (Manager / Source)

Accountability: Hamilton Trend: Necding increased Management Attention 34

llg333% Hours out of Umit ,

13.00 ' PPD Goal (5%)

11.00 -  !

9.00 <

7.00 -

5.00 <

2.93

. 3.00 - ,

1.21 1.08 I'" ~ 0.00 0.00 0.00 0.00 0.00

] 0.00 0.00

[ ,

1.00 - D 5 $ $ 5 E D E $ E o z o ,5 u, 3 < g , < 4" 4

PRIMARY SYSTEM LITHlUM % HOURS OUT OF LIMIT

' The Primary System Lithium Percent Hours Out of Limit Indicator tracks the hours per month th:t the primary system lithium is out of specification.

The Primary System Lithium Percent Hours Out of Limit was 1.48% for the month of ,

September 1997.

The 1997 Fort Calhoun Station monthly goal for this indicator is a maximum of 5% hours out of limit.

. D:ta Source: Chase /Humilton (Manager / Source)

Accountability: Hamilton Trend: None 35

1 l

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

t e

36

l

+ Actual + BudO*l + Han t

3,80 3.60 .

'j'; r - -

N  :

3.00 . N 2.60 .

2.40 .

':' ~

00 .

42 45 i b i -l { k 8kbiilkkh44***'N8bi?gigig k 4 CENTS PER KILOWATT HOUR August 1997 The purpose of this indicator is to quantify the econornical 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 1996 and 1997 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 1992 through 1996. In addition, the report shows the plan amounts for the years 1998 through 2002 for reference. The basis for the dollars are the Nuclear Long Range Financial Plan and the 1997 Corporate Planning and Budget Review. The basis for the generation la provided by Nuclear Fuels.

The 12 month rolling average unit price (pericd of July 1996 through August,1997) anraged above the budget due to 12-month rolling expenses exceeding the budget and the 12 month budgeted generation falling

. below budget. The 12 month rolling average (7/96 through 8/95 is 3.34 cents per kilowatt hour.

The year-to dato average is trending in a negative direction. This information normally lags by month due to

, the short tum around required for processing.

Cents ner KWH Jan Feb Mar Anr Mav Jun Jul Aua Sen Ost Nov Dec Budget Y T-D 2.83 2.66 2.58 2.55 2.44 2,46 2.48 2.46 2.45 2.46 2.45 2.43 Actual Y T-D 2.89 2.60 2.54 2,75 2.99 2.90 - 2.83 2.79 0.00 0.00 0.00 0.00 Data Source: Lounsberry/ Dent (Manager / Source)

Accountability: Lounsberry_

' Trend: - Needing increased Management 37 I

l l

1 l

I i

i i

DIVISION AND  !

l .

DEPARTMENT PERFORMANCE '

INDICATORS  :

l Goal: Achieve high standards at Fort Calhoun Station -

resulting in safe, reliable and cost effective power  ;

i production.

l 38 I

lume Corrective Maintenance CD Preventive Maintenance i i Non-Corrective / Plant irrprovernents -- Fort Calhoun Goal

1. 1 '" 887 f42 72e

' 718 788 87*

sat s24 c,oo j ,

400- _ _ _

200-0 +- + "-- -+- + --- + + -- --- --

u. 2 2 4

- Non-outage Maintenance Work Docurnent Backlog a

O TM NM4]r, Past Completion MAD PRioRmf 46%

mb 4 21 D 400 163 k_ j 0 8

_ ,_gg_n .

$4%

Row IWW huW how Ro#

1 2 3 4 5 Not Corrpleted MAINTENANCE WORKLOAD BACKLOG This indicator shows the backlog of non-outage Maintenance Work Documents remaining open at the end of the reporting month. It also includes a breakdown by maintenance classification and priority. The 1997 goal for this indicator is 250 non-outage corrective maintenance MWDs.

Tho current backlog of corrective MWDs is 352. To ensure that the MWD backlog is worked in a timely manner, non-outage maintenance completion goals have been established as follows:

Goal Priority 1 Immediate Action 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Priority 2 Urgent 5 days Priority 3 Operational Concems 21 days Priority 4 Routine Corrective 90 days Priority 5 Non Essential 180 days D:ta Sourco: Chase / Johnson (Manager / Source)

Accountability: Chase /Faulhaber Tr:nd: Adverse SEP 36 39

Ratio of Proventive O Total Caintenance ,,g 90"4 7 erg 84 %

77% V II%

g, 74 %

70g '

60 %

fS%

% J

[ 61 %

@ ,- m 60% - r, *l.

E2% g 7' h w

60% - .

L. M. L 40% - .1 H l'

O N 1.

30 % N 4

~

20% - ..

q .

a j ,y

,0v. .  : y u c~

y, [ ~ ,

4 Oct Nov Dec Jan Tab Mar Mr May June July Aug sep ,

CEFJ Preventive Maintenance iterns Overdue ,

Fort Calhoun Goal 3% -

2.50%

, 2.40 %

L

~

~

!q '

g 2% - ix l u A

'% ~ 8%

h i o, jog 0.25%

E83%

. . ,.,g3 0.56 % E56% 0.20v. 0 30%

- o ,

og - ( N 09 , R k b Oct Nov Dec Jan Feb Mar Apr May June July Aug sep PATIO OF PRF.VENTIVE TO TOTAL MAINTENANCE PREVENTIVE MAINTENANCE ITEMS OVERDUE l

The top graph shows the ratio of completed non-outage preventive maintenance to total completed non-outage maintenance. The ratio was 77% for the month of September 1997.

The lower graph shows the percentage of scheduled preventive maintenance items that are -

overdue. During September 1997,423 PM's out of 11 wera completed.

i The 1997 Fort Calhoun monthly goal for the percentage of preventive maintenance items overdue is a maximum of 0.5%.

Data Source: Chase / Johnson (Manager / Source) i Accountability: Chase /Faulhaber l Trend: Needing Increased Management Attention SEP 41 & 44 l

I I

1 40

-.l

1

\

e ILEIENo, Mainteatnco cme tempted

-+-- % Id e n tifie d a s R e L e s t too 8 , e es 600 -

les , , ,

$a - .'...,

g? ,

I 400 -

y' gig

,,.. to ,,,

7 A. .,

l

,._ A oes Nov oes sen

.a ree

. g u se i

Apr A"

uer 1

Juae F+

9 Jv'r F

..e 8

't see

'4. ,

,_og C"3 Rework as identified by Craft

+ Fort Calhoun Goal (<3%)

ss , :  :  :  :

e -

y 2.4%

0 1 . 2.0% Ol I I% " i "w , .7 % 1.8 % F 0.6%

y P f.' % t.5 % lyk k 3 ,,

5 T n P: 9g 3 ^

~ w g n .,.

f '# '3n; kkk o

3 ,.

S I

h a

kw N m

k x

e a, a w y e e a g g g ~

b g$$

5 g L0 ,

,_ h .

01 '

oei ne, oes  ;.. re, u s,

• e, us, s. soi, ... s e, PERCENTAGE OF TOTAL MWDs COMPLETED PER MONTH IDENTIFIED AS REWORK! REPEAT This graph indicates the percer.tage of total MWDs completed per month identified as rework.

Rework activi'ies are identified by maintenance planning and craft.

This indicator is calculated from the 15th of Octobw ' hough the 15th of September 1997, du] to the delay in closing open MWDs at the end of ea .h month. The Fort Calhoun monthly goal for this indicator is <3% A detailed review is conti .cted of rework items each month to id:ntify generic concerns.

Data Source: Faulhaber/ Johnson (Manager / Source) l Accountability: Chase /Faulhaber Trend: None 41

. . _ . _ _ __ - ~

C""3 L*.onthly Overtime (2n-Une)

-e- Y.T4 Monthly Average (on-Une)

Fort Calhoun "On-Une" Goal (10%)

21.4 %

20.0% -

15.0% +  !

11.6%

98% -

10.0% - _

d %

• 5.0% - ./ -

1.7%

] I ' ' '

0.0% ,

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

MAINT5 NANCE OVERTIME The Maintenance Overtime Indicator monitors the ability to perform the desired maintenance activities with the allotted resources.

The percent of overtime hours with respect to normal hours was reported as 11.6% for the month of September 1997.

The 1997 Fort Calhoun monthly "on-line" goal for this indicator is a maximum value of 10%.

Data Source: Chase /Johncon (Manager / Source)

Accountability: Chase /Faulhaber Trend: None -

l l

l l 42

Human P;rformance CRs(Maintnance) 20 --

18 ,

18 J-14 14 --

{ 12 .--

10 --

b 8  ::

x l

n.  ;

Mar Apr May June July Aug Sep PROCEDURAL NONCOMPLIANCE INCIDENTS '

(MAINTENANCE)

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

D:ta Source: Faulhaber/Burggraf (Manager / Source)

. Accountability: Chase /Faulhaber Tr:nd: None SEP 15,41 & 44 1

43 l l

--m-% PASS DOS -+- % Non# ASS OOS

--*-- % fotal OOS Total % 003 Go{

14% -

' 12% -

1o%

8%

e

,, p i

o% = = = = _ = _

s s 4  :  : :  :  :

b $ $ $ $ $ $ $

$ b E $

IN-LINE CHEMISTRY INSTRUMENTS OUT-OF-SERVICE This in fcator 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 September 1997, the percentage of hours the in-line chemistry system instruments were inoperable was 0.87%. The following instrument (s) were out of service for the current month:

1.  % PASS HOURS OUT OF SERVICE:

None -

2.  % NON-PASS HOURS OUT OF SERVICE:

CPD DO2 and SG cat conductivities.

Data Source: Chase /Ostien (Manager / Source)

Accountability: Chase /Skilos Trend: None 44 1

1

a

, i Was'.3 Produced Each Month (Kilograms)

+ Fort Calhcon Monthly Average Goal (150 kilograms) l

Federal & State Monthly Limit (Max of 1,000 kg) -

E 1000 :.  :. - - - . - -  :.  :. a 900..

800.

700 600.. .

500..

y

, 400.

300.

200..

100..

0 ,

8 o j ,5 4 >

a $ k 8  %  ?

z a a z ,

i HAZARDOUS ' WASTE PRODUCED

- This indicator shows the total amount of Hazardous Waste Produced by the Fort Calhoun Station each month, the monthly average goal arid the monthly average total for hazardous waste produced during the last 12 months. This hazardous waste consists of non-halogenated hazardous v.aste, halogensted hazardous waste, and othor hazardous waste

< produced.

During the month of September 1997,0.0 kilograms of non-halogenated,0.0 ki., grams of halogenated and 0.0 kilograms of other hazardous waste were produced.

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

The 1997 Fort Calhoun monthly average goal for hazardous waste produced is a maximum

. of 150 kilognims.

Data Source: Chase /Shubert (Manager / Source)

R Accountability: Chase / Hamilton Trend: " None 3,

i 45 4

I'.-

l

i l Era Contaninated Radiation Controlied Area Fort Calhoun Goal ($%)

10%

T 9% -

r k k '? h 7% - p j n' f# fY a

..,.. g -

0y

4 p ,

~

,.,.. 4 lr [~ L .i '

$ L 2  !

! d  ; -

l , s. l ) 9 Isf 3 4% -- ' l g i h y

I '

I  : i

' t a

(

.:) a;:

3% -- ,

$N [

t i

ii f '

, .h hN l l Mg e. 0 h .,

f j k , .J .

j

, r _

Nov Dec Jan Feb Mar Apr May June July July Aug sep CONTAMINATED RADIATION CONTROLLED AREA This indicator shows the percentage of the Radiologically Controlled Area that is contaminated based on the total square footage. The 1997 monthly non-outage goal was revised from a maximum 10% to 5.0% contaminated RCA in May 1997. This indicator has an Adverse Trend since it exceed the FCS goal. .

At the end of September 1997, the percentage of the total square footage of the RCA that was contaminated was 7.9% .

Data Source: Chase / Williams (Manager / Source)

Accountability: Chase /Gebers Trend: Adverse SEP54 46

Poor Radiation Worker Practices l

-o--Fort Calhoun Goal (<15) i

--*-- Total PRWP for 1997 ,

16 T

12 . ,

10 .

6.  ;.

. 6 ,

l

~

2 2 1 0  :

Jan Feb Mar Apr May June July Aug Sep Oct Nov Dec RADIOLOGICAL WORK PRACTICES PROGRAM The Radiological Work Practices Program Indicator shows the number of Poor Radiological Work Practices (PRWPs) which were identified during the reporting month.

The number of PRWPs which are identified each month should indirectly provide a means to qualitatively assess supervisor accountabliity for their workers' radiolog! cal pt. armance.

This indicator needs increased management attention due to a 3 month increasing trend of poor radiation worker practices based on YTD.

During the month of September, there was 0 PRWP identified.

There have been a total of 8 Poor Radiation Worker Practices in 1997.

The Fort Calhoun Station year-end goal for PRWPs is a maximum of 15.

Data Source: Chase / Hamilton (Manager / Source)

Accountability: Chase /Gebers Trend: Needing increased Management Attention SEP 52 l

47

a D:cuments Sch:dul:d f:r R view 0 Documents Rsvbwed during month O Documents Overdue 400 - -

~ ~

350 -- -

300- _

250 --

200_.

150.

100- _ ,

50 __ _

^

0 l b; *

• 5 8 8 ,8 1 h a 2 e  ?,  ? & I o z o w 2 < 2 < m j 4

1997 j DOCUMENT REVIEW The Document Review indicator shows the number of completed, scheduled, and overdue (greater than 6 months past the scheduled due date) biennial reviews for the reporting month. The documents reviews are performed in-house and include Special Procedures, the Site Se arity Plen. Maintenance Procedures, Preventive Maintenance Procedures, and tne Operath.a . 'anusl.

During September 1907, there were 240 document reviews scheduled, while 67 reviews were completed. At the end of the month, there we*e 67 document reviews more than 6 months overdue. There were 3 new documents initiated during September 1997.

Data Source: Chase /Psath (Manager / Source)

Accountability: Chase /Skiles Trend: None SEP 46 48

i O System Failur:s -

0 Non System Failur;e 27 l 25

i. 4 25 _  :

i 20 - 1919

-18 16.

15 .

13 13 12 12

10

.10 .. 9 -

+ ] 6 5 _5 5 t 5.. 4 --

~ ~" ' 3 ~

3 2 , _ ,

2 2 0 7 7 Oct Nov Dec Jan Feb Mar Apr May June July August Sep LOGGABLE/ REPORTABLE INCIDENTS (SECURITY)

The Loggable/ Reportable incidents (Security) Indicator is depicted in the above graphics display. The graph depicts the total number ofloggable/ reportable non-system failures and rystem failures which occurred during the reporting month.

During the month of September 1997, there were 17 loggable/ reportable incidents identified. System failures accounted for 71% of the total failures. 54% of the system failures were environmental. Three lost / unattended security badges, one security force error, and unsecured vital area door, were the non-systems failures during the reporting month. Non-system failures continue to rhow a negative trend when compared to the three year average.

This indicator provides information on security performance for Safety Enhancement Program'(SEP) Item No. 58.

Data Source: Sefick/Woemer (Manager / Source)

Accountability: Sefick ,

Trend: None SEP58 49

s 1 i T:nporaryCodifications >1 c)cle old (RFo required for removal) r-, Temporary Modifications >6 months old (Removable on-line)

Fort Calhoun Goals for >1 cycle and >6 months o!d l

3T 2.5 -

2- y j i i i 12, 1 i 1 1.5 -

1$ 1 1- h 0.5 - 5 i 0

t 8 8 ,E S h k # R i,  ? E o z o w a < m a < m  ;

J TEMPORARY MODIFICATIONS This indicator provides information on the number of Temporary Modifications (TMs) greater than one fuel cycle old requiring a refueling outage (RFO) for removal and the number of temporary modifications removable on-line that are greater than six months old. The 1997 Fort Calhoun monthly goals for this indicator are zero.

There are currently two (2) temporary modifications that are greater than one-fuel cycle old requiring an outage for removal. TM 96-014, Reactor Coolant Gas Vent Line Pressure High Alarm, was installed April 22,1996. Repairs for this TM were completed during the 1996 RFO, but the reactor coolant gas vent line pressure is still high. MR-FC-97-011 was initiated to solve this problem and currently DEN is planning the modification. TM 96-018, Equipment Drain Header Soft Rubber Patch, was installed June 16,1996. MWO 963468 was written to remove the patch and is currently scheduled for the 1998 RFO.

At the end of September 1997, there was one (1) TM installed that was greater than six months old that could be removed on-line. TM 96-039 Railroad Siding / Corridor 26 Door, was installed November 1,1996. EAR 97-219 will be used to close this TM. EAR 97-219 requires System Engineering review and approval.

At the end of September 1997, there was a total of 12 TMs installed in the Fort Calhoun Station. Ten (10) of the 12 installed TMs require an outage for removal and 2 are removable on-line. In 1997, a total of 16 TMs have been installed. At the end of September 1997, there -

were two (2) procedural or maintenance configuration alterations (PMCAs) (a special classification of TM) installed in the Fort Calhoun Station using PRC approved procedures which are controlled by Standing Order O-25.

Data Source: Phelps/ Frank (Manager / Source)

Accountability: Phelps/ Core Trend: None SEP 62&71 50

i- L._J Total Modification Packages Open -

- Fort Calhoun Y;ar End Goal (68) 80 -- o

". n.

S n

n_

70 - -

65  ; , , ,  ;  : ,

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

. OUTSTANDING MOUlFICATIONS This indicator shows the total number of Outstanding Modifications (excluding outstanding modificallonsphich are proposed.to_be. cancelled).

Reporting Category _

94 '95 '96 '9Z '9B _99 Month Form FC-1133 Backlog /In Progress 0 0 0 2 0 0 2 Mod. Requests Being Reviewed 0 0 0 0 0 7 7 Design Engr. Backlog /In Progress 0 0 0 0 14 3 17 Construction Backlog /In Progress 3 1 5 7 3 0 4

-19 Design Engr. Update Backlog /In Progress _4 _12 _.S _1 _0 ._0 ... 2 6 Totals 7 13 16 9 17 10 71 (outage + Onl.ine) (3+4) (5+8) (11+3) (2+7) (15+2) (7+3)

At the end of September 1997,26 modification requests have been issued this year and 7 modification requests have been cancelled. The Nuclear Projects Review Committee (NPRC) has conducted 67 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) has completed 22 backlog modification request reviews this year. ,

The 1997 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: Lounsberry/Jaworski Trend: Needing increased Management Attention 51 i

be - ' E Am e Q c es er82 s 8 80 t9 e e r8%e C lo s e *38

• N el 13 C 13es et t g

~

B SE O DEN 40 t si

'l SS 30 - if is 87 17 8'

2 20 is 13 * -

E

, . . . . . . t c g 4 l l E .i 1 . [a 1 1 1 $ 5

- J u ly Aug Sep J u ly Aug Sep J u ly Aug Sep J u ly Aug Sep 0 3 M eethe 8 4 M onths s.13 M er,ths s t* M onths l

O Ergineering Response D Closecut(sE) ,

20 - 15 3j 10 10 - 3 g i 3

,1 0 0 0

1 1

[0 ,

Priority 0 Priority 1 Priority 2 Priority 3 Priority 4 Priority 5 Priority 6 43 Overdue Closeout Reponsee 9 et EAR's on Schedule 60.9 % [

Y ~

b sponse

< J g e overdue (24 Closecuts 6.8%

ENGINEERING ASSISTANCE REQUEST BREAKDOWN '

lhls indicator shows a breakdown of the number of EARS assigned to Design Engineering and System Engineering. The 1997 year-end goal for this indicator is a maximum of 140 outstanding EARS. -

The Total EAR breakdown is as follows:

EARS opened during the month 11 EARS closed during the month 26 Total EARS open at the end of the month 133 Data Source: Jaworski/Livingston (Manager / Source)

Accountability: Phelps/Jaworski Trend: None SEP 62 32

l ae sus n 1 CL0889UT 117 >4 Months 0 3 84anths

~

diD [f 3 c!" r. k-us q <

'h-M p ;/ -

s'1 us

" 7MMP*

~

'nCNSTATOS d/ERMfBACKL'OG-60 c) Dacklogged O Received O Completed 0$,

250

'I f50._115.

110 115 118 119 117 ,, 7 g h0 0 25 6 kM 23 36 Ljg im d-n 1 *N b Months ISO .L Apr May June July Aug Sep

~

!De~SidH ENGifiEE}HRD~ ~ '

250 ,. 33 8"*"'"'

2')01 ts%

150h ,,': u ,,in, ,, ,',',,,,

9 100iyg 87 85 81 84 2.4 %

~

50 I 13 4g 12 12 1013 10 l Wa-- -

- "$. N N 0b -N * "m *e m Apr May June July Aug Sep D pigt.gggh

~

iSVSTEM ENGINEERING ~ ~

300 . '

250 1 221 225 211 217 tr 20s 204 e.: u.nih.

4d% *"'"'

200h __ ' s".3 %

'$1 i

So 00 10 12 5 6 8 ,, jrs , ,

0 s y,3 g Apr May June July Aug Sep

-PROClFEfENT/CONSTUCTICN [] _

250 , y 4 200 Mo hs 1O gg{42 I 39 44 42 44 46 48 gg

• N' p 00 -

M onths 0

Apr May June July Aug Sep i

l DRAFTING / CLOSEOUT _______.-a ENGINEERING CHANGE NOTICE STATUS Data Source: Jaworski/Livingston (Manager / Source)

Accountability: Jaworski/Phelps Trend: None SEP62 53

93 Priorier 'I 5ed P'II'Y 8"I 66- If% 2M DC TTel  %

"Q ,M,c Npg 4 -

w A & ,/

250 Prl ey

$RITYPt M sss Total Open ECNs = 454 se% Tctal Open ECNs = 454 o.............e.............. ,

e:...:::.:::.:: ...:::=:<~~ -

~~

T *' -

ne ... '" '" ...

,g,.3

n. ,. .. . . ,,

jup, , -

ses - ..

( 9n ee - ,, .. .. . ..

.+ . '.' a m iu "

., 4 .. sus Paa"'y ue n1*~

nr.

'"'" " " 7. . ..a ;'.'.'. . . W:e's . . ' " ' " '"'"

"* T n > n> n* n> n, n. .

. ~,;... , . . . . ;.:', ,,,

,, .4 -,1 = i.

n. 7

"'  ? I I ,,, I 5

i4, I.- N n',, ,t ,,

m.

_ d ,, [ ,, ,, -

i ,e ...

j 44 45 49 44 43 F 48 , ' "-l'. ga . .

Apr47 May4F Jun47 Jul47 Aug47 See47 Substitute Replacement item ECNs Open

.. ,, 3 "T ,.

eaan'v iu se t " n '

- 44 14%

.. M

n a y a -

k b

w/;- j

':t

. [! .. b.. 3 ., 7 ..

ll -

x]8 -  %< > .

Apr May June July Aug 83 Document Change ECNs Open

/

ENGINEERING CHANGE NOTICES OPEN Data Source: Jaworski/Livingston (Manager Source)

Acr.ountability: Phelps/Jaworski Trend: None SEP 62 l

54 l

. ~

i i Startup m Shutdown -

Operations o- Industry Aworage Trond -

2-1.5 -

u.

'ti 1- - m p m }-

7 E e U ""U *'"D" b -G " U""' 'D- -O h ~ ~ G- ~ D - - -D " C

.g"0.5- =

3 g 7

+ i

.s  ? E =j g = =

93-1 93 2 93-3 93-4 94-1 94-2 94-3 94-4 95-1 95-2 95-3 95-4

• Year-Quarter SAFETY SYSTEM FAILURES Thb indicator illustrates the number of NRC Safety System Failures as reported by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data in the annual" Performance Indicators for Operating Commercial Nuclear Power Reactors

• report.

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 gre;ter than the allowed limits. This rendered the scram input inoperable at certain operating conditions.

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 te meet design requirements during a seismic event.

4th Quarter 1993: 1) During survelilance testing, both PORVs for the LTOP system failed to open during multiple attempts. The failures were a result of differential expansion caused by a loop seal, excessive venting line back pressure, and cacked 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 de2 graded 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 testing, tin 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 couU rise causing compressor rupture disc failure and a release of freon.

~

There were no safety system failures since the 4th gaarter of 1995.

Data Source: Nuclear Regulatory Commission Accountebility; Chase-Trend: None o

155 L

L- j

O Total Requalification Training Hours i

a simulator Training Hours O Non Re 1ualification Training Hours l O Number of Exam Failures 34 35 . g n 31 31 31 _

~ ~ ~

30 .

25 22

< 20 .

14 '

14 14 14 15 12 8 8 8 10

• 8 8 8 _ _ _

8 y

7 0 _

~

5. .

2

' l' -

0[

Cycle Cyc',e Cycle Cycle Cycle Cycle Cycle Cycle Cycle 96 3 96-5 96 7 97 1 97 2 97 3 97-4 97 5 97 6 LICENSED OPERATOR REQUALIFICATION TRAINING This indicator provides information on the total number of hours of training given to each crew during each cycle. The simulator training hours shown on the graph are a subset of the total training hours. Non-Requalification Training Hours are used for AOP/EOP verification &

validation, NPO committnents, GET, Fire Prigade, Safety Meetings, and Division Manager ,

lunches.

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

(JPMs) segmentr. of the Licensed Operator Requalification Training.

Data Source: Conner /Guliani(Manager / Source)

Accountability: Conner /Guliani Trend: None SEP 68 56

1 0 SCO Ex::ms Administ:r:d i' D SRO Exams Passed O RO Exams Administered B RO Exams Passed 10 --

t 77 77 77 77

,. i 5--

0000- 00 00 00 00 0000 0000 0000 0000 0

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec LICENSE CANDIDATE EXAMS - 1997

. This indict. tor shows the number of Senior Reactor Operator (SRO) and Reactor Operater (RO) quizzes and exams taken and passed each month. These intemally administered quizzes and exams are used to plot the SRO and hO candidates' monthly progress.

, During the month of September 1997, there were no (S TO) or (RO) training classes in session.

Data Source: Conner /Gullani(Manager / Source)

Accountability: Conner /Gullani Trend: None SEP 68 i

)

y 57

C""""} Ready to Close C""3 Closed

-dr--Total LRs

+ Open

'3500 3000 -

2500-2000- l 1500- i

, , - gl ^ _

f >

1000 - ,

, .. f ' ~

500 -

f/

0 j >

!A 4 8

8 8

8 E

8 b

4 N

4 4

E 4

k 4

4 k

4 E

4 8

l 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.

Leve!1 Level 2 Level 3 Level 4 Level 5 Level 6 Total Open 25 20 132 842 56 260 1341 Closed 1'i 7 115 1235 478 237 2087 377 condition Reports are classified as READY to CLOSE. ,

Data Source: Tesar/Burggraf (Manager / Source)

Accountability: ~ Andrews/Gambhir Trend: None 58 l

l

o Toet omoe MWos MWD HOLDS

, , , - a WWon ne.* w work - System

- EngruarinD MS 1% F/* m

~

yr vi.

m J m - <W iQ-Y j

=4 g ...

c m m ,w

,l c

,,, 2 3 *_g a ,& b N REWW

, wr ,.7 , m,  %., s.r., #%

. MWD PLANNING STATUS (CYCLE iS REFUELING OUTAGE)

. This indicator shows the total number of Maintenance Work Requests (MWRs) and Maintenance Work Documents (MWDs) that have been approved for inclusion in the Cyc'e 18 Refueling Outage. This graph indicates:

Parts holds - Planning Complete, Awaiting Parts

- System Engineering Holds - Aviaiting System Engineering Input to Planning

. - Planner Holds - Maintenance Planner has not completed planning the work package.

- ECN Hotd - Awaiting Substitute Replaceinent items ECN from DEN.

- In Review - Maintenance Planners ana currently not reviewing work package.

Data Source: Chase / Johnson (Manager / Source)

Accountability: Chase / Herman Trend: Nor;e SEP 31 e

59

EB Last Month E This Month D Next Month 120 -

110 100f M

• l 80

$ 70 - 8 g -

o .

8 3 3

$ }mha a a

. m , a m ,aa s l

5  ! I I i I.  ! If i  != 5 1 3 se i Et i Si i } H 13 i fi j j j "

0 SPECIAL SERVICES ENGINEERING DEPARTMENT 1998 OUTAGE PROJECTS STATUS REPORT l

I Data Source: Phelps/Swearngin (Manager /Scurce)

Accountability: Phelps/Boughter .

Trend: None SEP 31 l

60

a " - . . . . . . . . . . . -

8/29/97 - , f 4 7/30/97 - fg 6/30/97.-

h 6/31/97 -

$11/97 -

+ Actual PRC Date

., 4f 3f,7 ,

3 arget T PRC Date S'2/97 -

. 1/31/97 -

. . , ,, ,. . . , ,, . ~ .

5 4 $ $

!. . $. $. !. 8  !. $. . $. . $.

PROGRESS OF 1998 REFUELING OUTAGE MODIFICATIONS CYCLE 18 This indicator shows the status of Modifications approved for installation during the Cycle 18 Refueling Outage (March 1998).

Th3 goal for this indicator is to have all modificc on packages which were identified prior to M:rch 20,1997 PRC approved by September 15,1997.

September 1997 Modifications added: 0 Deleted = 0

. D*ta Source: Jaworsk!/ Walling (Manager / Source)

Accountability: Gambhir/Jaworski Trend: None SEP 31 61

I

+ Aid PFCDNe a TargdFfCDde I

12/17/97 k s somw - 3E ia S g 9'aw'~ -

e "

mow 8 uas7; 4'1tw ; .

zmi L ,I ' '

V1/97 ,,

-e o 2 ;I 2 8EE "SS ..

s PROGRESS OF CYCLE 18 OUTAGE MODS AND ECN'S ADDED TO '98 REFUELING OUTAGE AFTER FREEZE DATE This indicator will show the status of Modifications and ECN's approved for installation during the Cycle 18 Refueling Outage. The goal for this indicator is to have all modification packages PRC approved by their target date.

September 1997 Modifications /ECN's Added = 0 Deleted = 0 Data Source: Jaworski/ Walling (Manager / Source)

Accountability: Gambhir/Jaworski .

Trend: None SEP 33 62

No 1997 On Lina Modifications Currcntly Apprsvcd P

PROGRESS OF 1597 ON-L!NE MODIFICATION PLANNING

' ' ' This indicator shows the status of modifications approved or in review for approval for on-line installation during 1997.

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

September 1997 Modifications Added: 0 Deleted: 0 Data Source: Jaworski/ Walling (Manager / Source)

, Accountability: Gambhir/Jaworski Trend: None SEP 31 e

i 63

i 1

9 e

e ACTION PLANS 3

e s

64

. ACTION PLANS This section lists action plans that have been developed for the performance indicators cited as Adverse Trends during the month preceding this report. Also included are Action Plans for indicators that have been cited in the preceding month's report as Needing increased

- M:nagement Attention for three (3) consecutive months.

In accordance with Revision 5 of NOD-QP-37, the following performance indicators would require action plans based on three (3) consecutive months of pedormance cited as "Needing increased Management Attention":

• Fuel Reliability Indicator (page 9)

Based on the large number of predicted fuel failures and the expectation that future fuel failures will be identified, the Fuel Performance functional area performance is considered to be POOR for the 3rd quarter of 1997. The plant is currently in " Action Level 3"in accordance with Standing Order 0 43," Fuel Reliability Action Plan,"

based on the August prediction of 15 core average power failures,

• Maintenance Workload Backlogs (page 39)

A Work Management System improvement project is curremiy in progress. The purpose of this project is to stream line the maintenance process at Fort Calhoun Station. This will significantly improve our " WRENCH TIME" by removing inefficiencies and related hurdles that prevent work from being accomplished in a timely manner. In addition, it is

- expected that schedule compliance will also increase and our maintenance backlog will decrease. This project is scheduled to be fully implemented 'ay July 1997.

9 65

PERFORMANCE INDICATOR DEFINITIONS AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM CLEAN CONTROLLED AREA CONTAMINATIONS 21,000 PERFORMANCE DISlNTEGRATIONS/ MINUTE PER PROBE AREA The sum of the known (planned and unplanned) unawitable hours The personnel contaminabon events in the dean mntrolled area.

and the estimated unavaltable hours for the auxihary feedwater This indicator tradts personnel performance for SEP #15 & 54.

system for the reporting period divided by the critical hours for the reporting period multiphed by the number of trains in the audiary CONTAMINATED RADIATION CONTROLLED AREA feedwater system.

The percentage of the Radiation Co , rolled Area, whidi indudes COLLECTIVE RADIATION EXPOSURE the auxiliary building, the radwaste building, and areas of the C/RP building, that is contaminated based o.1 the total square footage.

Couechve radiabon exposure is he total extemal whole-body dose This indicator tracks performance for SEP #54.

teceived by all orbsite personnel (induding contractors and visitors) during a hme period. as rneasured by the DAILY THERMAL OUTPUT thermoluminescent dosimeter (TLD). Conecbve radtabon exposure is reported in units of person-rem. This indicator tracks This indicator shows the daily core thermal output as measured ,

radiological work performance for SEP #54. from computer point XC105 (in thermal megawatts). The 1500 MW Tedi Spec limit, and the unmet porbon of the 1495 MW FCS COMPONENT FAILURE ANALYSIS REPORT (CFAR) daily goal for the reporbng rnonth are also shown.

SUMMARY

DlFSEL GENERATOR RELIABILITY (25 Demands)

The summary of INPO categories for Fort Calhoun Stabon with significantly higher (1.645 standard deviations) faDure rates than This indicator shows the number of failures occurring for each the rest of the industry for an eighteen-month bme period. Failures emergency diesel generator during the last 25 start demands and are ,eported as component (i.e., pumps, motors, rnain steam stop the last 25 load.run demands.

valves, control element motors, etc.) categories.

DISABLING INJURY /lLLNESS FREQUENCY RATE Failure Cause Categories are: (LOSS TIME ACCIDENT RATE)

Age / Normal Use -though; to be the consequenco of expected This indicator is defined as the number of accidents for all utility wear, aging end4f.bfe, or normal use . personnel permanently assigned to the station, involving days away from work per 200.000 man-hours worked (100 man-years).

Manufacturing Defect a failure attnbutable to inadequate This does not indude contractor personnel. This indicator tracks assembly or inibal quahty of the responsible component or personnel performance for SEP #25,26 & 27.

system.

DOCUMENT REVIEW (BIENNI AL)

Engineering / Design a failure attributable to the inadequate design of the responsible component or system. The Document Review Ir dicator shows the number of documents reviewed, the number of documents scheduled for review, and 'he Other Devices . a failure attributable to a failure or number of document reviewe that are overdue for the report ng misoperabon of another component ce system,induding month. A document review is considered overdue if the review is associated devices. not complete within six months of the assigned due date. .This indicator tracks performance for SEP #46.

Maintenance / Action . resutbng from improper maintenance, lack of maintenance, or personnel err;,rs that occur during EMERGENCY AC POWER SYSTEM SAFETY SYSTEM maintenance activsbeson the component., PERFORMANCE Testing Action . resulting from improper testing or personnel The sum of the known (planned and unplanned) unavailable and ,

errors that occur during teshng achvities. the eshmated unavailable hoursfor the emergency AC power system for the reportng pened divided by the number Initial Installation Error caused by improper initiat installabon of hours in the reportng period multiphed by the number of trains of equipment in the emergency AC power system.

CENTS PER KILOWATT HOUR The purpose of this indicator is to quantfy the economical operation of Fort Calhoun Stabon. The mnts per k!!cwatt hour 6dicator represents the budget and actual cents per kilowatt hour on a twelve-month average inr the current year. The basis for the budget curve is the approved year 1y budget The basis for the actual curve is the Finandal and Operating Report.

66

PERFORMANCE INDICATOR DEFINITION EMERGENCY DIESEL GF,NERATOR UNIT RELIABILITY E) A fahre to start because a portion of the starting system was disatAed for test purpose, if fof5wed by a successful start with TNe indicator shows the number or failures that were reponed during the last the starting systern in its normal alignment.

20,60. and 100 emerg6ncy desel generator demands at the Fort Camoun Statiert Moo shown are Ingger values wtch cortWate to a Ngh level et Each emergency generator failure that resulta in the generator contseace that a urers desel gene'etors have obtaened a rellat, sty or greater being dedared inoperable should be munted as one demand and than or equal to 95% when the demand fattu'es as less than the trtD9er one failure. Exploratory tests during correct,ve maintenance and values. the successful test that follows repair to verify operability should not be counted as demands or failures when the EDG has not

1) - Number of Start Demands: A!I valid and inadvertent start been dedared operable again.

demands, Induding all start-only demands and all start

- demands that are followed by load-run demands, wheher by EMERGENCY DIESEL GENERATOR UNRELIABILITY

• automa5c or manualinibahon. A starlonly demand is a demand in whidt the emergency ponerator is statted, but ro This indicator measures the total unreliability of emergency diesel attempt is made to load the generator, gmerators, in general, unrehability is the ratio of unsuccessful operations (starts or load-runs) to the number of valid demands.

2) Number of Start Failures: Any failure within the emergency Total unreliabihty is a combination of start unreliability and load.run generator system that prevents the generator from achieving unreliabihty, specified frequency and voltage is dassified as a valid start failure. This indudes any condition identified in the murse of ENGINEERING ASSISTANCE REQUEST (2AR) maintenance inspechons (with the emr rgency generator in BREAKDOWN standby mode) that definnely would have resulted in a start failure if a demand had occurred. This indicator shows a breakdown, by age and priority of the EAR.

of the number of EARS assigned to Design Engineering Nudear

3) Number of Load-Run Demands: For a vahd load-run and System Engineering. This indicator tracks performance for demand to t's counted, the load-run attempt must meet one SEP #62.

cr more of 'ne following criteria:

GNGINEERING CHANGE NOTICE (ECN) STATUS A) A loa &run of any duration that results from a real autortvtic or manuat initation. Tl e number of ECNs that were opened. ECNs that were co npleted, and open backlog ECNs awaiting r:empletion by DEN

8) A load-run test to satisfy the plant's load and durabon as for the reporting month. This indicator tracks performance for SEP stated in each tests specifications. 1 2-C) - Other spedal tests in which the emerg .ncy generator is ENGINEERING CH;.NGE NOT:CES OPEN expected to be operated for at least one hour while loaded wMh at least 50% of its design load. This indicator breaks down the number of Engineering Change Notices (ECNs) that are assigned to Cesign Engineering Nudear

4) Number of Lnad4 tun Failures: A load-run failure should be (DEN), System Engineenng, and Maintenance, The graphs counted for any reason in which the emergency generalor provide data on ECN Facility Changes open, ECN Substitute does not pick up load ami run as predicted, Failures are Replacement items open, and ECN Document Changes open.

counted dunng any vahd load-run demands. This indicator tracks performance for SEP #62.

5) Exceptions: Unsuccessful attempts to start or load-run EQUIPMENT FORCED OW AGES PER 1,000 CRITICAL HOURS should not be munted as vahd demands or failures wten they can be attnbuted to any of the following: Equipment forced outages per 1,000 critical hours is the inverse of

, the mean bmg between forced outages caused by equipment A) - Spurious trips that would be bypassed in the event of an . failures. The mean time is equal to the number of hours the emergency, reactor is critical in a period (1,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />) divided by the number of j forced outages caused by equipment failures in that period.

i *- D) Malfunchon of equipment that is not required during an emergency. EQUIVALENT AVAILABILITY FACTOR C) Iraenbonal termination of a test because of abnormal This indicator is defined as the ratio of gross available generaton condibons that would not have resutted in major diesel - to gross maximum genen, tion, expressed as a percentage.

i. generator damage or repair. Available generation is the enerDy that can be produced if the unit j is operated at the maximum power lesel permitted by *outpment l D) Malfunchons or operating errors which would not have end regulatory limitations. Maximum generabon is the mergy that L prevented enWmergency generator from being restarted can be produced by e unit in a given period if operated and brought to load within a few tranutes. conhnuously at maximum capacity.

67

PERFORMANCE INDICATOR DEFINITIONS

- FORCED OUTAJE RATE INDUSTRIAL SAFETY ACCIDENT RATE INPO This indicator is defined as the percentage of bme that the unit TNs indicator is defined as the number of accidents per 200.000 was unavailable due to forced events compared to tt a bme man-hours worked for all utility personnel permanenty assigned to

planned for electrical genersbon. Forced events are failures or - the station that result in any of the following

other unpfanned conditions that require removing the unit from

. service before the end of the next wo:,kend. Forced events 1) One or more days of restricted work (exduding the day of the indude etart up faitures and events initated while the unit is in acddent);

reserve shutdown (i.e., the unit is available but not in service). 2) One or more days away from work (exduding the day of the acodent); and FUEL RELIABILITY INDICATOR 3) Fatalities.

This indicator is defined as the sMady-state primary coolant 1-131 Contractor personnel are not induded for this indicator. j

+

activity, corrected for th tramp urpruum contribution and ,

normalized to a common purtfication rate. Tramp uranium is fuel IN LINE CHEMISTRY INSTRUMENTS OUT OF SERVICE wNch has been deposited on ret ctor core intemals from previous defective fuel or is present on ihe cudace of fuel elements from tt e Total number of in-line chemistry instruments that are out-of-mcnufacturing process. Steady state is defined as conbnuous service in the Secondary System and the Post Accident Sampling cperation for at least three days at a power level that does nohary System (PASSL more than + or -5% Plants should collect data for tNs indicator at a power lavel above 85%, when possible. Plants that did not LICENSE CANDIDATE EXAMS operate at steady-stato power above 85% should collect data for

' this indicator at the highest steady-state power level attained This indicator shows the number of SRO and/or RO quizzes and dunng the month. exams that are administeJed and passed eacti month. This indicator tracks training performance for SEP a68.

The density correchea factor is the rabo of the spedfic volume of contant at the RCS operatng temperature (540 degrees F., Vf = LICENSED OPERATOR REQUALIFICATION TRAINING 0.02146) divided by the specific volume of coolant at normal let$own temperature (120' F at cutlet c'f the letdown cooling heat The total number of hours of training given to each crew dunng exchanr.Vf = 0.016204), wtuch re4utts in a density correction each cyde. Also provided are the simulator training hours (which factor foi ruS equal to 1.32. are a subset of the total training hours), the number of non.

REQUALIFICATION training hours and the number of exam GROSS HEAT RATE failures. This indicator tracks training performance for SEP

1. 68.

Gross heat rate is defined as the ratio of total thermal energy in Dntish Thermal Ur.its (BTU) produced by the r3 actor to the total LICENSEE EVENT REPORT (LER; ROOT C .!

gross electncal energy produced by the generator in kilowatt-hours BREAKDOWN (KWH).

This indicator shows the number and root cause code for Licensee HAZARDOUS WASTE PRODUCED Event Reports. The root cause codes are as follows:

The total amount (in Kilograms) of nor;-halogenated hazardous 1) Administrative Control Problem Management and waste, halogenated hazardous waste, ar.d other hazardous waste supervisory deficiences that affect plant programs or produced by FCS each month, activities (i.e., poor planning, breakdown or lack of adequate management or supervisory control, incorrect pro *edures, HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY etc).

SYSTEM PERFOf1MANCE

2) Licensed Operator Error This cause code captures errors ,

The sum of the known (planned and unplanned) unavailable hours of omission / commission by licensed reactor operators during and the estimated unavailable hours for the Ngh pressure safety plant activities.

. injection system for the reporting penod divided by the entical hours for the reporting period muttplied by the number of trains M 3) Other Personnel Error - Errors of omission / commission ,

the N0h pressure safety injechon system. committed by non-licensed personnel irwolved in plant activities.

4) Maintenance Problem The intent of this cause code is to capture the full range of problems which can be attributed in any way to programmatic deficiencies in the maintenance functior'al organization. Actvities induded in this category are maintenance, tesbng, surveillance, cahbrabon and radiation protection.

5) Design /Constructionfinstallation/ Fabrication Problem -

TNs CIuse code covers a full range of programmabr 68

PERFORMANCE INDICATOR DEFINITIONS defidendes in the areas of design, construction, installation, ard MAXIMUM INDIVIDUA! P.ADIATION EXPOSURE fabrication (La., loss of control power due to underrated fuse, equipment not quahfied for the environment, etc.). The total rnaximum amount of radiation received by an individual person

6) Equipment Failures (Elect.Dnic Piece-Paris or Enviror mental 4telated Faltures) . TNs cooe ls used for working at FCS on a monthly,7;arterly, and annual basis, spurious failures of electronic piece parts and failures due to meteorological conditions sudi as lightning, ice, Ngh winds, MWD PLANNING STATUS (CYCLE 17 REFUELING OUTAGE) -

etc. Oenerally,it indudes spuruts or one-time failures.

Electric components induded in this category are drcuit The total number of Maintenance Work Documents that have been cards, rectifiers, bistables, fuses, capadtors, diodes, approved for indusion in the Cyde 17 Refueling Outage and the resistors, etc. number that are ready to work (,aarts stage 1, planning mmplete, and all other paperwork ready for field use). Alao meluded is the

• LOGGASLE/ REPORTABLE INCIDENTS (SECUR"Y) number of MWDs that have oeen engineering holds (ECNs, procedures and other miscellaneous engineering holds), parts T'te total number of security incidents for the reporting rnonth hold, (parts staged, not yet inspected, parts rd yet arrived) and cepicted 1,6 two graphs. This indicator tracks security performance planning hold Gob scope not yet completed). Maintenance work for SEP #58, Requests (MWRs) are also shown that have been identified for the Cycle 17 Refuehng Outage and have not yet been mnverted to MAINTENANCE OVERTIME MWOs.

The percent of overt:rne hours compared to normal hours for NUMBER OF CONTROL ROOM EQUIPMENT DEFICIENCIES maintenance, Thrs indudes OPPD personnel as wel as contract personnel. A control room equipment deficiency (CRD)is de5r ed as any component which is operated or controlled !Tm the Control Room, MAINTENANCE WORKLOAD BACKLOGS provides indication or alarm to the Control Room, provides teshng capabilities from the Control Room, provides automatic actions This indicator shows the backlog of norwoutage Maintenance Work from ur to the Control Room, or provides a passive function for the Orders remaining open at the end of the repor ting month. Control Room and has been identified as deficient, l.e., does ret Maintenance dassificatons are defined as follows perfor9 under all conditions as designed. This definition also applies to the Altemate Shutdown Panels Al-179, Al-185, and Al-Corrective - Repair and restoration of equipment or 212, components that have failed or are malfunctioning and are not performing their intended function, A plant component which is deficient or inoperable is considered an ' Operator Work Around (OWA) Item"if some other acten is Preventive - Achons taken to maintain a pece of equipment required by an operator to compensate for the condition of the within design operating conditions, prevent equipment lailure, cornponent. Some examples of OWAs are:

and extend its hfe and are performed prior to equipment failure.

1) The control rosn level Indicator does riot work but a local Non-Corrective / Plant improvements . Maintenance activities sight glass can be read by an Operator out in tne plant; performed to implement stahon improvements or to repair non-plant equipment. 2) A deficient pump cannot be repaired because replacement prts require a long Itad time for purchase / delivery, thus Maintenance Work Priorities are defined as; requiring the redundant pump to be operated contnuously; Emergency . Condibons which significantly degrade station 3) Spedal actions are required by an Operator because of salsty or availability, equipinent design problems. These actions may be

., desenbed in Operations Memorandums, Operator Notes, or immediate Action . Equipment deficiencies which significantly may require changes to Operating Procedures; degrade station reliability, Potential for unit shutdown or power reduchon, 4) Deficient plant equipment that is required to be used during 4 Emergency Operating Procedures or Abnormat Operating Operations Concern . Equipment deliciencies which hinder Procedures; stabon coeration.

5) System indication that provides critical information dur ng Essential Routine wrrective maintenance on esscritial station normal or abnormal operatons systems and equipment.

NorwEssential . Routino corrective maintenance on nord essenbal stabon systems and equipment.

Plant improvement Non-correcbve maintenance and plant improverrents.

This indicator tracks maintenance periormance for SEP #36.

69

PERFORMANCE INDICATOR DEFINITIONS NUMBER OF MISSED SURVEILLANCE TE3TS RESULTING IN The above mentioned outstanding modifications do not indude LICENSEE EVENT HEPORTS modificebons wtth are proposed for cancellabon.

The number of Survelliance Tests (STs) that resuh in Licensee OVERALL PROJECT $ FA1US (REFUELING OUTAGE)

Event Reports (LERs)during the reporting rnonth. Ynis indx:ator r tracks missed STs for SEP EO & 61. This indicator shows the status of the projects which are in the OPEN INCIDENT REPORTS scope of the Refueling Outage.

This indicator displays the total number of open inddent P.eporta PERCENTAGE OF TOTAL MWDs COMPLETED FER MONTH (irs), the number of irs that are greater than six months old and IDENTIFIED AS REY.'MK the number of upon significant irs.

The percentage of total MWDs completed per rnonth identified as rework. Rework achvities are identified by maintenance planning +

OUTSTANDING MODIFICATIONS and craft. Rework is: Any addibonal work required to correct The number of Modifk:abon Requests (MRs)in any state between deficiences disevered during a failed Post Maintenance Test to the issuance of a Modification Number and the completion of the - ensure the component / system passes subsequent Post

~

drawing update. Maintenance Test.

1) Form FC 1133 Backlog /in Progress This number PERCENT OF COMPLETED SCHEDULED MAlhTENANCE represents modification requests that have not been plant ACTIVITIES approved dunng the reporting month.

The percent of the number of mmpleted maintenance activities as

2) Modification Requests Being Reviewed. This category compared to the number of scheduled maintenance achvibes each includes: rnonth. This percentage is shown for all maintenance crafts. Also sbyn are the number of emergent MWDs. Maintenance activibes A) Mndification Requests that are not yet reviewed. Indude MNRs, MWDs, STs, PMOu, calibrations, and other mmcellaneous achvities. This indicator tracks Maintenance B) - Modification Requasts being reviewed by the Nudear performance for SEP #33.

Projects Review Committee (NPRC).

PERFORMANCE INDICATOR INDEX C) Modification Requests being reviewed by the Nudear Pryects Committee (NPC). This indicator index is calculated from a weighted combination of eleven perfornance indicator values, which inoude the following:

These Medficabon Requests may be reviewed several bmes Unit Capability Factor, Unit Capabihty Loss Factor, HPSt, AFW, before they are approved for accomplishment or canceled Some Emergency AC Power System. Unplanned Automabc Scrams, of these MMficabon Requests are retumed to Engineenng for Collective Radiabon Exposure, Fuel Reliabihty, Thermal more informabon, some approved for evaluation some appwved Performance, Se,:ondary System Chemistry, and industna Safety for study, and some approved for planning. Once plant'ing is Acddent Rate.

completed and the scope of the work is dearly defined, these Modification Requests may be approved fo; accomplishment with PREVENTABLE / PERSONNEL ERROR LERs a year assigned for construchon or they may be canceled. All of these different phases require review. This indicator is a breakdown of LERs. For purposes of LER event dassification, a " Preventable LER'is defined as:

3) Design Eng!neering Backlogin Progress. Nuclear Plannmg has assigned a year in t.ich construct.on will be An event for which the root cause is personnel error (i.e.,

completed and design work may be P progress. Inap;yopnate achon by one or more individuals), inadequate administranve controls, a design tonstruchon, installation, ,

4) Construction 8tcklogin Progress. The Construebon installation, fabrication problem (involving work completed by or Package has been issued or construebon has begun but the supervised by OPPD personnel) or a maintenance problem modification has not been accepted by the System (attributed to inadequate or improper upkeep / repair of plant Acceptance Comtruttee (SAC). equiprnent). Also, the cause of the event must have occurred

• witnin approximately two years of the " Event Date'spedfed in B) Design Engineering Update Backlog!!n Progress. PED the LER (e.g., an event for which the cause is attributed to a has received the Modificattun Complebon Report but the problem with the original design of the plant wr>uld not be drawings have not been updated, considered pre ventable).

For purposes of LER event classification, a " Personnel Error

• LER is defined as follows:

An event for which the root cause is inappropriate action on the part of one or more individuals (as oppoaed to being attnbuted to a department or a general group) Also, the inapvopriate acbon must have occurred within approximately two years of the

" Event Date" sceofied in the LER.

70

PERFORMANCE INDICATOR DEFINITIONS Add 4bonally, endi overit classtf.ed as a

• Personnel Error" should SAFETY SYSTEM FAILURES stao be dassified as

• Preventable? This indicator trends personnel perf:nnance for SEP thm #15. Safety system feilures are any events or mnditions that could prevent the fulfIlment of ti e safety functions of structures or FRIMARY SYS7M LITHlUM % OF HOURS OUT OF LIMIT systems. If a system consists cd rnuthple redundant subsystems or trains, falture of all trains constitutes a safety system fatture.

The percent of hours out of hmit are for hthium divided by the total Failure of one of two or rnore trains is not counted as a safety number of hours possible for the rnonth, system faiture. The definition for the indicator paraitels NRC reportng requirements in 10 CFR 50.72 and 10 CFR 60.73. The PROCEDURAL NONCOMPLtANCE INCIDENTS following is a hst of the major safety systems, sub-systems, and (MAINTENANCE) components monitored for this hdicator:

The number of identified inodents conceming mair'tenance Accident Monitoring instrumentabon, AuxJliary (and Emergency)

' procedural probtems, the number of dosed irs related to the use Feedwater System, Combust ble Gas Control, Component of procedures (includes the nurrter of dosed irs caused ty Coohng Water System, Containment and Cantainm-t Isolabon, procedural noncompliance), and the numbe' of closed procedural Containment Coolant Systems, Control Room Emergney nonmmphance irs. This indicator trends personnel performance Ventiabon System Emergency Core Coohng Systems, for SEP #15,41 and 44. Engineered Safety Features instrumentaton, Essential Compressed Air Systems, Essential or Emergency Service

, PROGRESS OF CYCLE if OUTAGE MODIFICATION Water, Fire Detecbon or Suppression Systems, isolation PLANNING Condenser, Low Temperature Overpressure Protect 6on, Main Steam Line isolabon Va;ves, Onsite Emergency AC & DC This hdtcator shcme the status of rnodifications approved for Power w/Distnbubor., Radiat on Monitoring instrumentat on, comFebon during the Refuehng Outage. Reactor Coolant System, Reactor Core isolabon Coohng System, Reactor Trip System and instrumentation, Recirculabon PROGRF 3S OF 1996 ON LINE MODIFICATION PLANNING Pump Trip Actuation instrumentation. Residual Heat Removal Systems, Safety Valves, Spent Fuel Systems, Standby Liquid This indicator shows the status of modificabons approved for Control System and Ultimate Heat Sink, mmplebon during 1995.

SECONDARY SYSTEM CHEMISTRY PERFORMANCE INDEX RADIOLOGICAL WORK ?RACTICES PROGRAM The Chemistry Performance index (CPI)is a calculation based on The number of identsfied poor radiological work practices (PRWPs) the concentration of key impunties in the secondary side of the for the reporting month. This indg.ator tracks radiological woris plant These key impunt es are the most likely cause of performance for SEP #52. deteriorabon of the steam generators. Criterta for calculating the CPI are:

RATIO OF PREVENTIVE TO 10TAL MAINTENANCE &

PREVENTIVE MAINTENANCE ITEMS OVERDUE 1) The plant is at greater than 30 percent power, and The rabo of preventive maintenance (induding surveillance test ng 2) the power is changinD less than 5% per day, and cahbrabon proceduces) to the sum of non outage correcbve maintenance and preventive maintenance completed over the The CPI is calcutated csing ine following equabon:

reportrsg period The rabo, expressed as a percentage, is calculated based on man-hours. Also displayed are the percent of CPI = ((sodiurrVO.79) + (ChlorNir/1.52) + (Sulfate /1.44) +

prevenhve maintenance items in the month that were not (Iron /3.30) + (Cwer/0.30)+(Coadensate 02/2.90)y6 completed or administratively closed by the scheduled date plus a grace period equal to 25% of the adieduled interval. This indicator Where: Sodium, sulfate, chloride and condensate dissolved

, , tracks preventive maintenance achvibes for SEP #41. oxygen are the monthly averege blowdown concentrabons in ppb, iron and copper are monthly 'Jrae weighted average feedwater

, RECORDADLE INJURY /lLLNESS CASES FREQUENCY RATE concentrations in ppb. The denominator fg s ich of ,he five factors is the INPQ median value. If the monthly average for a 4 The number of injuries requiring more than normal first aid per specific parameter is less than the INPO median value, the median 200.000 man-hours worised This indicator trends personnel value is used in the calculation.

performance for SEP #t5,25 and 26.

REPEAT FAILURES The number of Nuclear Plant Reliabihty Data System (NPRDS) components with more than one failure and the r' umber of NPRDS components with more than two failures for the eighteen-month CFAR period.

71

PERFORMANCE INDICATOR DEFINITIONS SiONIFICANT EVENTS 2) Jumpers and blods wh62 are instaliet, for Surveillance Tests, Maintenance Procedures Calibrat on Pro:sdures, Speaal Sgnificant events are the events 6dentified by NRC staff through Procedures or Ope abng Procedures are not considered as detailed sneenmg and evaluaban of operabng expenence. The temporary rnodifications Lntet a the jumper or block remains in sersening process includes the dalty teAew and discutsion of all place after the test or pocedu,e 6s complete. Jumpers and reported operabng reactor emnts, as well as other opersbonal blocks installed in test or lab Instruments are not consdered as data such as speual tests or wnstruct.on activibes. An event temporary mod ficabons.

Identified from the soreening process as a sgnificant event candidate is further evaluated to determine H any actual or 3) Scaffold is not considered a temporary modificabon. , lumpers potent at threat to the health and safety of the public was involved. and blocks which are 6nstalled and for wh:2 MRs have been Specfr examples of the type of uiteria are summanted as submitted will be considered as ternporary mod-ficabons unbi follows final resolubon of the MR and the jumper or block is removed

1) Degradabon of im;ortant safety equipment, or is permanently recorded on the drawings This indicalor tracks temporary mWications for SEP #62 and 71. *

2) Unexpected plant t;sponse to a transient; THERMAL PERFORMANCE

3) Degradabon of fuel hlegnty, pnmary coolant pressure

• boundary,important assodated features; The ratio of the design gross heat rate (corrected) to the adjusted actual gross heat rate, expressed as a percentage.

4) Scram with complicabon; UNIT CAPABILITY FACTOR

$) Unptanned release of radmchvity; The rabo of the available energy generation over a given time

6) Operauon outsde the hmits of the Technical Spedficabons. penod to the referenos energy generat on (the energy that could be produced if the unit were operated continuously at full power

7) Other. under reference ambient conditions) over the same time per6od, expresssd as a percentage, INPO sgnificant events reported in this indicator are SERs

($gnificant Event Reports) which inform utilibes of significant UNIT CAPACITY FACTOR events and Iassons loamed 6dentified through the SELIN sueening protess. The net electncal energy generated (MWH) dMded by the product of maximum dependable capacity (net MWe) times the gross SPARE PARTS INVENTORY VALUE hours in the reporting penod expressed as a percent Net electncal energy generated is the gross elecincal output of the unit The dollar value of the spare parts inventory fur FCS dunng the rnessured at the output terminals of the turtune generator minus reporting period. the normal stabon service loads dunng the Dross hours of the reporbng pe lod, expressed in megawatt hours.

STAFFING LEVEL UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7,000 The actual staffing level and the authortred staffing level for the CRITICAL HOURS Nudear Operat ons DMaici The Produchon Engineenno Division, and the Nuclear Services C, vision. This indicator tracks This indicator is defined as the number of unplanned automabc performance for SEP #24. scrams (RPS logic actuabons) that occur per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of cr tical operauun.

8TATION NET GENERATION The value for this indicator is calculated by multiplying the total The not generation (sum) produced by the FCS during the number of unplanned automatic reactor scrams in a spe3fic time reporbng month, penod by T,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, then dMding that number by the total ,

number of hours uiticalin the same time penod. The indicator is TEMPORARY MODIFICATIONS further defined as follows:

Tha number of tempou,ry mechanical and electncal configurations 1) Unplanned rneans that the scram was not an ant <cipated part '

to the plant's systems. of a planned test.

1) Temporary configurabons are defined as electricaljumpers, 2) Soam means the automatic shutdown of the reactor by a electrical blocks, mechanical jumpers, or mechanical blocks rapid insertion of negative reactrvity (e.g , by control rods, whim are 6nstatted in the plant operating systems and are not liquid injechon system, etc.) that is caused by actuation of the shown on the latest revision of the P&lD, schematic, reactor protechon system. The sgnal may have resulted from connecbon, winng, or flow degrams, exceeding a set point or spunous.

72

PERFORMANCE INDICATOR DEFINITIONS

3) Automabc mans that the inibal signal that caused actuate of VIOLATION TREND the reactor protechon system logic was prov6ded from one of the sensor's 1orotonng plant parameters and condibons, This indicator is defined as Fort Calhoun Stabon C4ted V6olations tatho' than the rnanval scram swit&es or, rnanual turbine tnp and Ncn Cated VKalabons trended over 12 months. Additionally, swit:hes (or push 4uttons) provided in the main Control room. Cated Violabons for the top quarble Region IV plant is trended over 12 rnonths (lagging the Fort Calhoun Station trend by 2 3 months).

4) Cribcal f.wans that furlng the stet tfy-state cond: bon of the it is the Fort Calhoun Stabon goal to be at or below the oted reador prior to the scram, the effective try altipikahon (k ,, ) was v6otsbon trend for the top quartile Region IV plant essenbalty equal to ca,e.

UNPLANNED CAPABILITY LOSil FACTOR VOLUME OF LOW LEVEL SOLID RADIOACTIVE WASTE The rabo of the unplanned energy losses during a given penod of This indicator is defined as the volume of low 4evel solid e tro, to the reference energy genersbon (the energy that could be radioachvo waste actually shipped for burial This indicator also produced if the unit were operated cont nuously at full power under shows the volvme of low-level re$0 active waste whkh is in reference ambient conditions) over the same time period, temporary storage, the amount of radioactive oil that has been crpressed as a pe",4r tape. shipped off-site for processing, and the volume of solid dry radioactive waste wh6ch has been shipped off-stte for processing.

UNPLANNED SAFETY SYSTEM ACTUATIONS e(INPO Low-level solid radioactive weste conalsts of dry active waste,

+ DEFINITION) studges, resins, and evaporator bottoms generated as a result of nudear power plant operabon and maintenance. Dry radioactrve TC lndicator is defined as Me sum of the following safety syst6m waste indudes contaminated rags, deaning materials, disposable actus'Ros: yctechvo dothing, plastic containers, and any other material to be Jisposed of at a low level radioachve waste disposal site, except

1) The number of unplanned Emergeocy Core Cochng System resin, studge, or evaporator bottoms. Low-level refers to alt (ECCS) actuations that result from reaching an ECCS radioachve waste that is not spent fuel or a by-product of spent actuat on set point or from a spurious / inadvertent ECCS signal. fuel processing. This indicator tracks radiological work

- l

2) The number of unt anned emergency AC power system actuabons that result from a loss of power to a safeguards bus.

An unplanned safety system actuation ocoars when an actuation tot point for a safety system is reached or when a spurlous or inadvertent signal is generated (ECCS on% and major equipment in the system is actuated. Unplanned means that the system actuabon was not part of a planned test or evolution. The ECCS actuabons to be counted are actuabons of the h6gh pressure injechon system, the low pressure irnechon system, or the safety irvection tanks.

UNPLANNED SAFETY SYSTEM ACTUATIONS .(NRC DEFINITION)

The number of safety system actuatnins which indude (only) tro High Pressure Safety trVochon System, the Low Pressure Safety Irvechon System, the Safety trtechon Tanks, and the Emergency Diesel Generators. The NRC dassification of safety system actumbons indudes actuabons when major equipment is operated

, and when the logic systems for the ebove safety systems are chattenged.

e 73

SAFETY ENHANCEMENT PROGRAM INDEX i

The purpose of the Safety Enhancement Program (SEP) Performance Indicators index is to list performance indicators related to SEP ltems with parameters that can be trended.

SEP. Reference Number _15 Page e increase HPES and IR Accountability through use of Performance Indicators Procedural Noncompliance incidents (Maintenance) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 Recordablo injury / Illness Cases Frequency Rate . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 Clean Controlled Area Contaminations 21.000 Disintegrations / Minute Per Probe Area . . . . . . ..... .... 17 Proventable/ Personnel Error LERs ........................................... .............. 18 SEP_Referonce Numbers 25.2.6 & 27 ,

• Training Program for Managers and Supervisors implemented

. Evaluate and implement Station Standards for Safe Work Practice Requirements e implement Supervisory Enforcement of Industrial Safety Standards Disabling injury / Illness Frequency Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 Recordable injury / Illness Cases Frequency Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 SEP_Referencellumber.31

• Develop Outage and Maintenance Planning Manual and Conduct Project Management Training MWO Planning Status (Cycle 17 Refueling Outage) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 59 SSED's Overall Project Status . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . ........................ 60 Overall Project Status (Cycle 17 Refueling Outage) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ......... . . 61 Progress of Cycle 17 0utage Modification Planning . . . . . . . . . . . . . . . . . . . . . . . ...... .. ... . . . . S3 SEP_ Reference Numbet33

. Develop On Line Maintenance and Modification Schedule 1996 0n-line Modification Planning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 62 SEP_ Reference. Number _36

• Reduce Corrective Non Outage Backlog Maintenance Workload Backlogs (Corrective Non-Outage) ............. ... ................. .. 39 SEP_Referenca Numbers _414 A4

• Develop and implement a Preventive Maintenance Schedule

• Compliance With and Use of Procedures Ratio of Preventive to Total Maintenance & Preventive Maintenance items Overdue ...........,....... 40 Procedural Noncompliance incidents (Maintenance) . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . ,. 43 SEP_ Reference NumbetA6

+ Design a Procedures Control and Administrative Program Document Review ....................... ........... ........... . . ......... ..... . 48 i 74

SAFETY ENHANCEMENT PROGRAM lNDEX SEPJteforence. Number 32 Page

e. Establish Supervisory Accountability for Workers Radiological Practices -

Radiological Work Practices Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..............,47 SEP_ReferenceRumber34

+ Complete implementation of Radlological Enhancement Program o

Clean Controlled Area Disintegrations L>1,000 Counts / Minute Per Probe Area . . . . . . . . . . . . . . . . . . . . . . . . . 17 Collect!ve Radiation Exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . 11 Votume of Low. Level Solid Radioactive Waste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 Contaminated Radiation Controtted Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 SEP_ Reference Nurther.58

• Revise Physical Security Training and Procedure Program Loggable/ Reportable incidents (Security) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49 SEP. Reference _ Numbers.60161

+ improve Controls Over Surveillance Test Program

. Modify Computer Program to Correctly Schedule Surveillance Tests Number of Missed Surveillance Tests resulting in Licensee Event Reports . . . . . . . . . . . . . . . . , , . . . . . . . . 23 SEP_ReferenceRumber 62 e Establish interim System Engineers Temporary Modifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 Engineering Assistance Request (EAR) Breakoown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . 52 Engineering Change Notice Status .......................................................... 53 Engineering Change Notices Open . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54

, SEP_ReferenceRumber 68 e Assess Root Cause of Poor Operator Training and establish means to monitor Operator Training 3 License OperLtor Requalification Training . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 t.icense C andidate Exams . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57

. SEP,_ReferenceNumberli

. . lmprove Controls over Temporary Modifications Temporary Modifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 75

REPORT DISTRIBUTION LIST i

R. L. Andrews J. B. Kuhr (9 Copies)

K. L. Bolek L. T.Kusek G.C. Bishop C. J. Linden (10 Copies)

C. E. Boughter S. A. Lindquist C. J. Brunnert B. R. Livingston .

J. W. Chase E. R. Lounsberry R. G. Conner T. J. Mcivor M.R. Core K. A. Miller .

T. R. Dukarski P. A. Mruz M. L. Ellis R. J. Mueller H. J. Faulhaber R. L. Plott S. K. Gambhir W.J.Ponec J. K. Gasper D. G. Rled W. G. Gates M. J. Sandhoefner S. W. Gebers F. C. Scofield M. J. Guinn H. J. Sofiuk R. H. Guy R. W. Short A. L. Hale J. L. Skiles B. R. Hansher R. D. Spies (2 Copies)

K. R. Henry K. E. Steele J. B. Herman D. E. Spires R. P. Hodgson M. A. Tesar C.K. Huang J. J. Tesarek J. K. Kollams J. W. Tills R. L. Jaworski D. R. Trausch J. W. Johnson L. P. Walling D.D. Kloock G. R. Williams 9

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