Text

Performance Indicators Rept for Nov 1997
	ML20198A573
Person / Time
Site:	Fort Calhoun
Issue date:	12/22/1997
From:	; OMAHA PUBLIC POWER DISTRICT
To:	;
Shared Package
ML20198A565	List: LIC-97-0197, Forwards Fort Calhoun Station Performance Indicators Rept for Nov 1997; ML20198A573;
References
	NUDOCS 9801060023
	Download: ML20198A573 (88)
	v • d • e

. _ _ . _ _ _ , _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _

OMAHA PUBLIC POWER DISTRICT FORT CALHOU'N STATION PERFORMANCE INDICATORS a

k ====se wy -

NOVEMBER 1997 SAFE OPERATIONS PERFORMANCE EXCELLENCE ~

COST EFFECTIVENESS

$$0*I8852Ed$$$$es R PDR

Table of Contents / Summary '

East TAB LE OF C ONTE NTS/S U M M ARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 - 111 M ONTH LY OP E RATIN G R EPORT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV WANO PERFORM ANCE INDEX TREND . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v WANO PE R.FORMANC E IN DEX IN DIC ATOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vi JNANO PERFORMANCE INDICATOR TRENDS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vil EDRT C ALHOUN GTATION REPORT SUMM ARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Viil

_ NUCLEAR PROGRAM 30ALS AND QRJECTIVES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . lx.xil WANO PERFORMANCfJNDICATORS Unit Capability 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 Performance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .... .... ... 9 Fuel Reliability lndicator . . . . . . . . . . . . . . ...... ... , . ... .... , . . .. .. 9 Secondary System Chemistry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .... .. . . . 10 C*lective Radiation Exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .......... 11 Industrial Safety Accident Rate . ... . .. .. .. . .... ........... . ...... . 12 Volume of low level Radioactive Waste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 S AFE OPERATlQRS .

Disabling injury / Illness Cases Frequency Rate . . . . . . .. . . .... ... . . . ... 15 Recordable Injury /lliness Cases Frequency Rate . . . . . . . . . . , . , ,, .. .. . . 16 Clean Controlled Area Contaminations 11.000 Disintegrations / Minute per Probe Area .... .. . .......... .. . ... , . 17 .

i

Table of Contents / Summary Preventable / Personnel Error LERs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 Licensee Event Report (LER) Root Cause Breakdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19

. Viol ation Trend . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 Maximum individual Radiation Exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 Missed Surveillance Tests Resulting in LERs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 PERFORMANCE

' Station Net Generation . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 !

Forced Outage Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 5 l 1

Unit Capacity Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 6 Equivalent Availability Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 -

]

Unplanned Safety System Actuations I N PO De fin ition . . . . . . . . -. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28 N RC Definition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29 G ross He at Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 30 Daily Thermal Output ..................................... .............. ......... 31 Equipment Forced Outages per 1,000 Critical Hours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 Chemistry Action Levels Exceeded - Event Days . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33 Primary System Lithium % Hours Out of Limit ... . ......,..... ...... ... ......... 34 COST Cents Per Kilowatt Hour ................................................ ......... . 36 DIVISION Atw DEPARTMENT PERFORMANCE INDICATORS Maintenance Workload Backlogs (Corrective Non-Outage) .... ... ...................... ... . 38 Ratio of Preventive to Total Maintenance ...................................... . 39 Percentage of Total MWDs Completed per month identified as Rework . . . . . . . . . . . . . . . . . 40 O vertim e . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 Procedural Noncompliance incidents. . , . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . 42 in-Line Chemistry Instruments Out-of. Service ...... .............. ............ ........ 43 li l

I Table of Contents / Summary. .

Hazardous Waste Produced . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 44 . I 1

]

Contaminated Radiation Controlled Area . . . . . . . . . . . . . . . .............,,.......,....-45 !

l aadioiogicai work er.ctices program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4e :

Document Rev iew . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . 4 7 i Loggable/ Reportable incidents (Security) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 Temporary Modifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 9 !

' Outstanding Modifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , 50

Engineering Assistance Request (EAR) Breakdown . . . . . . . . . . . a . . . . . . . . . . . . . . . . . . . . . . . . . . 51 Engineering Change Notices Status................................................ ................, 52 Open . . . . . . . . . . . . .................................., ...... ......... 53 Safety System Failures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . 54 Licensed Operator Requalification Training ..,..................................,....... 55 License Candidate Exams . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 Condition Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 Cycle 18 Refueling Outage MWD Planning Status ................................ ...................... 58 Overall P.oject Status . . . . . . . . . . . . . . . . . . . . . . . . ................. .......... 59 Outage Modification Planning . . . . . . . . . . . , . . . . . . . . . . .... ..... . .. ...... 60 On-Line Modification Planning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 Progress of 1997 On-Line Modification Planning ............. ,,, , ........ ..... ....., 62 ACTION PLANS. DEFINITIONS. SEP INDEX & DISTRIBUTION LIST Ac tio n Pla n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64

. Perfctmance indic: tor Definitions . . . . . . . . . . . . . . .... ............................. 65-Safety Enhancement Program lndex ................... ..... ........................ 73 Report Distribution L!st . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . 75 le.

11

l FORT CALHOUN STATION NOVEMBER 1997 1

Monthly Operating Report !

OPERATIONS

SUMMARY

The Fort Calhoun Station (FCS) operated at a nominal 100% power level until November 14,1997 at 19:41 hours when power was reduced to 85% to allow testing and repair of the main generator stator cooling heat exchanger. Following testing and repair, the power level was increased reaching 100% on November 17,1997 at 18:16 )

hours where it remained through month end.

iv

e-9

. Fort Calhoun inde a Value 11/97 OPPD Value was 86.45% . l Industry Med6an Index Value - 3rd QRT. INPO Median is 86.4%

]

100 -

85 89 86 82 84 85 83 90 t

y . -

80 5-- i

>- 70' 60 SOA 40 96/3 96/4 97/1 97/2 97/3 Oct Nov L _._.

WANO PERFORMANCE INDEX TREND The Wano Performance Index Trend calculation is made up of eleven variables, each value is weighted to arrive at an overall index value. INPO calculates the Wano Performance Index value based on the ir.dustry reporting the information each quarter.

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

PERFORMANCE INDICATO_R . WEIGHTED 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 Indicator 6 12 Months Secondary Chemistry Indicator 7 12 Months industrial Safety Accident Rate- 5 12 Months Fuel Reliability Indicator 8 Quarterly v

i l

. - . -,,n-.--.

g-

~

16.00 . g KMXP.UA VAllE sqOctober 97 D Noventer97 Y

a 14 0o . .__

12.00 l t 888 888 8 10.00 $ 8

888 888 8 '

8.00 . 8 888 l 888 6.00 888 4.00 2_00 O.00 -

UCF i.

tJCLF

+

I~+_,...+1 FPS 1 AFW EACP CRE 7

+

UAS7

+

FM 8

CF1 i

TF1

+

g SAR

~

i l

i WANO PERFORMANCE INDEX INDICATORS 1 This graph shows the difference between the Maximum No. of points for each WANO indicator and the actual value achieved by Fort Calhoun. i The current graph shows the difference between October '97 and November '97.

CALCULATED OVER A 2 YEAR PERIOD CALCULATED OVER A 12 MONTH PEROQ UCF Unit Capability Factor TPI Thermal Performance Indicator UCLF Unplanned Capabi!ity Loss Factor CPI Secondary Chemistry Indicator ,.

HPSI High Pressure Safety injection ISAR Industrial Safety Accxient Rate AFW Auxiliary Feedwater '

EACP Emergency AC Power CALCULATED OVER A QUARTERLY PERIOD UAS7 Unplanned Auto Scrams / 7000 Hours FRI Fuel Reliability Indicator !

CRE- Co!!ective Radiation Exposure vi i

e.

l WANO PERFORMANCE INDEX TRENDS

. (As~ compared to previons month) -

Unit Capability Factor No Changs

Unplanned Capability Loss Factor No Change High Pressure Safety injection' No Change 3 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 No Change Thermal Performance No Change industrial Safety Accident Rate No Change

- vii

- =w'-

a FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT -

NOVEMBER 1997-

SUMMARY

POSITIVE TREND REPORT Fuel Reliability Indicator (Page g)

A perforrr.ance indicator with data representing three consecutive months of improving p Jrformance or Collective Radiation Exoosure three consecutive months of perforrrance that is (Page 11) superior to the stated goal is exhibiting a positive trend per Nuclear Operations Division Quality Mrintenance Workload Backlocs Procedure 37 (NOD-QP 37). (Page 38)

The following performance indicators exhibited positive trends for the reporting month: Contaminated Radiation Controlled Area (Page 45)

Unolanned Automatic Reactor Scrams (Page 4)

INDICATORS NEEDING INCREASED Aux. Feed Water System Safety System Performance MANAGEMENT ATTEhTION REPORT (Page 6)

A performance indicator with data for the reporting Thermal Performance period that is inadequate when compared to the (Page 8) OPPD goal is defined as "Needing increased Management Attention

per (NOD-OP 37). .

Industrial Safety Accident Ratti (Page 12) Recordable Iniurv/Ilhess Freauencv Rate (Page 16)

Disablina Inlurv / Illness Rrecuency Rate (Page 15) Forced Outaae Rate (Page 25)

Gross Heat Rate (Page 30) Chemistrv Action Levels Exceeded (Page 33)

Outstandina Modifications (Page 50) Cents Per Kilowatt Hour (Page 36)

ADVERSE TREND REPORT Procetlural NonComoliance Incidents A performance indicator with data representing three (Page42)

Maintenance only consecutive months of declining performance or three consecutive months of performance that is trending nadioloalcal Work Practices Procram toward declining as determined by the Menager . (Page 46)

Nuclear Licensing, constitutes an adverse trend per Nuclear Operations Division Quality Procedure 37 (NOD-OP-37). A supervisor whose performance indicator exhibits an adverse trend by this definition may specify in written form (to be published in this report) why the trend is not adverse.The following performance indicators exhibited adverse trends for the reporting month.

Vili

^

NUCLEAR PROGRAM 1997 GOALS AND OBJECTIVES FUTURE FOCUS and RELATIONSHIP to CHANGE 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.

We niust 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 leaming 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 highect 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.

YlSl0N 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 conservativo decision making and the professional use of nuclear technology. We will conduct these operations to assure the health, safety, and protection of our personnel, the general public, Lnd the environment.

ix

OPPD NUCLEAR ORGANIZATION 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 i

initiative and open cSmmunication, 1997 Priorities:

_ 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 12:

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

OBJECTIVE 13:

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

1 OBJECTIVE 1-4:

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

- OBJECTIVE 15:-

Zero Lost Time injuries and recordable injuries rate dELOW 1.5 percent X

i l

_ . . _ ~- . __ _.

QEEDJUrdJfAB QRGANIZAII0. fLGOALE 1997 Priorities Goal 2: PER70RMANCE

~

Supports: April 1996 Corporate Strater Plan Goal 3 Objective: 2; G 4, Objective: 1,2, & 3; G-5, Objective: 2 Nuclear teamwork achieves high performance at Fort Calhoun Station as exhibited t,y safe, reliable and cost effective power production.

1997 PRIORITIES:

. Improve Quality, Professionalism and Teamwork.'

. Maintain High Plant Reliability.

. Pursue efficient, cost-effective work processes.

. Meet or exceed INPO key parameters.

. Reduce the number of Human Performance errors.

. Ident@ Programmatic performance problems through effective self assessment.

. Maintain a high level of readiness in the ERO.

Objectives to support PERFORMANCE:

OBJECTIVE 21:

Achieve an annual plant capacity factor of 92.7% and a unit capability factor of 96.0%.

OEiJECTIVE 2 2:

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

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

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

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

. Executive Training Committee:

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

+ invites the line and training supervisors responsible for each accredited program to provide a status of intema! accreditation asse.;sments.

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

OPPD NUCLEAR ORGANIZATION GOALS 1997 Priorities :

1 Goal 2: PERFORMANCE (Continued)

+

OBJECTIVE 2 3.

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

Focus on performing basic skills well, while pursuing efficient, cost-effective work processes. Identify the barriers to excellence and resolve them.

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 e rors and effective self assessment.

Goal 3: COSTS Suppons: April 1990 Corporate Strategic Plan Goal 2, Objective: 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 eJectiveness.

. Implement Opportunity Review recommendations.

Objectives to support COSTS:

OBJECTIVE 31:

- 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 redundant support services.

Goals Source: Lounsberry (Manager)

Xii

4 0

s l

l 1 .

WANO

! PERFORMANCE l

INDICATORS l

l l

I l

l l

2 e

l i

l 1

e c Q 32thly U3tt Caps 24Hty Pagtte e It af onth Unit Capabihty Fetter 100f Fort Calhoun Goal (00%)

_ Ye er 2000 WANO Industry Goalltf %)

110% , 100.0% 100.0% 100.0% g g.5 % . 100.0% 100 M 06.4% 74.6% 100.0% 100,0 %

500% 1 0s.4% _ _ ,_._ _ _ _ _

A = != = = = = y a

- - f - -

= = - = = = =-

10s, ; -

_=

6 7 43.7%

40%I -

30% I 30v, I

. 0 v. 1 0% ' +

E k 8 i k l $ $ $ 5 8 E UNIT CAPA!LLITY FACTOR UCF is dermed as the ratio of the available energy generation over a given period of time to the

- reference energy generation over the same time period, expressed as a percentage. The UCF for November 1997 was reponed as 100%. The year-to-date UCF was also reported as 89.3%, the UCF for the last 12 months (December 1996 through November 1997) was 89.8%, and the 36-month average (December 1994 through November 1997) was reported as 80.6%.

Enerer Losses:

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

Event Period: September 10, thru 13,1997.

Power Reduction - Faulty Manual Transfer switch on instrument invener "A ",

Event Period: August 26, thru 28,1997.

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.

Force Outage Steam leak in the fourth stage extraction steam system, Event Period: April thrnugh mid May 1997 The Year 2000 WANO industry goalis 87% and the industry current best quartile value is approximately 85%. The 1997 Fort Calhoun annual goal for this indicator is r. minimum of 96.0%. The maximum index point value for this indicator is 16. At the end of the November 1997, the FCS Value was 13.48. This compares to the previous month's value 13.48.

Data Source: Generation Totals Report & Monthly Operating Report Accountability: Chase - ~

Trend: None 2

g--) C*s7th Unplanz0d Cap:bHNy Liss Fact r

i sfi.n""*n"s"oTe##

e Year 2000 WANO in ustry Goal (4.6%)

60% ,g j

l $0% -

40% _

30.50 %

30% - 2 $0%

,i -

20% i 0.00% 0.00 %

0.00 %

A 10% ,l.1.57 % 0.00% 0.00 % 0.00 % #

,, dOO% 0 00 % - : :

; _p 0% ri

g S W L k 8 ,I <

I I 6 E 8" , w a a 4 ,

UNPLANNED CAPABILITY LOSS FACTOR 1

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 t

of unscheduled shutdowns, outage extensions, or load reductions due to causes tmder plant management control. Energy losses are considered to be unplanned if they are not scheduled at least fe.ur weeks in advance.

The UCLF for the month of November 1997 was reported as 00.0%, the Year-To Date UCLF was 10.71%, the UCLF for the last 12 months (December 1996 through November 1997) was 9.93%, and the 36 month average UCLF (December 1994 through November 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 November 1997 the FCS Value was 12.00. This compares to the previous month's value of 12.00.

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

l 12 Month Rolling Average

FCS Re: tor Scr*ms P:t 7,000 Hours critic 1f;r tst 36 mtnth) ;

Fort Ca'houn ooal(0.0)

Yeat 2000 WANO Industry Goal (1) j 3

7 1

2 3 1' A 0

^N_ _ . . . . . . . .

Oc : : : : : : : : : : o Dec- Jan Feb Mar . Apr May' June July Aug Sep oct Nov I

FCS Reactor Scrams .1997 4

3.

2.

1

.0 0 0 0 o o o o o o o &

Dec Jan Fe b Mar Apr May June J uly Aug Sep Oct Nov 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 unplsnned automatic screms that occur per 7,000 hours0 days 0 hours 0 weeks 0 months of critical operation.

l- There were no unplanned automatic reactor scrams during the month of November 1997. The 12-month rolling average (December 1996 through November 1997) was

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

The 1997 Fort Calhoun Station goal for this indicator is 0. The Year 2000 WANO industry goalis a maximum of one unplanned automatic reactorenam per 7,000 hours0 days 0 hours 0 weeks 0 months critical.

The maximum index point value for this indicatoris 8. At the end of the November 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: oositive 4

gg MonthlyHPSISystom UnavallabilityValue

+ 12 Month Rolling Average Fort Cahoun Goal (0.003)

,_. Year 2000 WANO Industry Goal (0.02)

-. 0.02 . + : : : : : : : : : : :

0.015 -

0.01 .

0.005 -- _

0, : : - - 1 1 - :-

Dec Jan Feb Mar Apr May June July Aug Sep Oct Nov 3-1 -.

HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE Tnis indicator shows the High Pressure Safety Injection (HPSI) System unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for November 1997.

The HPSI System unavailability value for the month of November 1997 was 0.0. There were 0.0 hours0 days 0 hours 0 weeks 0 months of planned unavailability, and 0.0 hours0 days 0 hours 0 weeks 0 months of unplanned unavailability, during the month.

The 12 month rolling average was (December 1996 through November 1997) was 5.01 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of planned unavailability and 0.0 hours0 days 0 hours 0 weeks 0 months 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 goalis 0.02.

The maximum index point value for this indicator is 10. At the end of November 1997 the FCS Value was 10. This compares to the previous month's value of10.

Data Source: Phelps/Schaffer(Manager / Source)

Accountability: Phelps/Schaffer

- Trend: None 5

a.

%1 Fort CalhounA v la lity Goal (0.01)

+ Year 2000 WANO Industry Goal (0.025) 0.025 .

0 02 : : : : : : : : :. :

3 I ,

0.015 i ?

ry ,

l i

0.01 gl . ,

A O.005 4 y f ( _ _ , _ _ =

n :

/ g. 1 0.E d I i rm ,@ k l

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

AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Auxiliary Feedwater (AFW) System Unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for the month of November 1997.

The AFW System Unavailability Value for November 1997 was 0.0 hours0 days 0 hours 0 weeks 0 months . There were 0.0 hours0 days 0 hours 0 weeks 0 months of planned and 00.0 hours0 days 0 hours 0 weeks 0 months of Unplanned Train Unavailability hours during the month.

The 12 month rolling average (December 1996 through November 1997) was 0.0042, and the year-to-date unavailability value was 0.0043 at the end of November 1997.

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

The Year 2000 WANO industry goal is 0.025.

The maximum index point value for this indicator is 10. At the end of November 1997, the FCS Vvue was 10. This compares to the previor.s month's value of10.

Data Source: Phelps/Frius (Manager / Source)

Accountability: Phelps/Fritts Trend: Postive 6

MED Monthly Emerge ncy AC Powst Unavall*bility Value e Yest to.Date Em ergency AC Pow er Unsvallability Vt've Fett Calhoun Goal (0.024)

I -.c Year 2000 W ANO Industry Goal (0.02 6) 0.04 0,0 $ $ ,L 0.03 d

> 0.0 2 s .! , : -

0.02 . .( j;, -

A &

0.01s _

f 0.01 - .

, 0.0 0. .

0. _b _E _b -

E k 2 h k ! .l 7 i R 8 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 Performance Indicator Definitions, for the month of November 1997. The Emergency AC Power System unavailability value for November 1997 was 0.022.

The Emergency AC Power System unavailability value year-to-date was 0.015 and the value for the last 12 months (October 1996 through November 1997) was 0.014.

Monthly Statistics Planned Unavailability: DG-1: 27.9 DG-2: 3.2 Total: 31.1 YTD: 194.4 Hours Unplanned Unavailability: DG-1: 0,0 DG-2: 0.0 Total: 0.0 YTD: 84.7 Hours There were a total of 188.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of planned unavailability and 3.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months of unplanned unavailability for the emergency AC power sys'-m 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 November 1997, the FCS Value was 7.0. This compares to the previous month's value of 9.0.

Data Source: Phelps/Ronning (Manager /Soerce)

Accountability: PhelpvRonning Trend: None 7 :

e e MonthlyThermalPerformance

, ,12. Month Rolling Avetage Fort Calhoun Goal (99.6%)

+ Yeer 2000 WANO IndustryGoal(99.5%)

100% . 1996 , .

h h. g-x l

~

3l I

l* M I h

""^

o .

j h

y f7 \\

l l

l: ?

i. M i j lL U b;

! 9s% ! u -

w d l 8 .!! 8 i k l .l $ $ 5 8 E i

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 November was 100%. The year to date value was reported as 99.9%. The 12 month rolling average (December 1996 through November 1997) was reported as 99.9%.

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 Novembel 1997, the FCS Value was 6.00. This compares to the previous month's value of 6.00.

Data Source: Phelps/Naser(Manager / Source)

Accountability: Phelps/Naser Trend: Positive 8

m FuelRelP.bility (E-4 Microcuries/GrCm)- l

+ Year 2000 WANO Goal (5 E 4 Microcuries/ Gram) 1997 Goal (147 " 4 Microcuries/ Gram) 160 ..

~

~-

124 120 -

'100.. 83 80 -- 1996 d 66 45 60 - RFO 3M 29.7 y S E 40 ." 16.1 18.6 22.8

} 20 7 ^.5 4 . g ? ME h g

" 0- , , , , .

j li S N f ilE E $ E

$ y Z o

7

I E y , 4 FUEL RELIABILITY INDICATOR The monthly FUEL RELIABli.lTY INDICATOR (FRI) for November 1997 was 124 x E-04 microcures/ gram based on the steady state data at 100% power, November 1st thru the 14th and 23rd thru the 26 due to reduction in plant power for repairs and variations in the letdown flaw ( intermittent 2 charging pumps operation) Several days in November did not meet tne steady state cnteria for the FRI calculation.

Coolant activity data through November 30,1997 shows the presence of 21 leaking rods at core average power. If the leaking rods ue at 70% or 50% core power the number of leaking rods changes to 36 to 59, respectively. The cesium data indicates the leaking fuel is most likely to be in the second and third bumed viellegions (Batches S and T) which have the original grid design. These batches are planned to be permanently discharged from the reactor core during the 1998 refueling outage.

The Cycle 17 monthly FRI is trending slightly lower than the Cycle 16 FRI at the same time in the fuel cycle due to the large contribution of the lodine-134 from the ' recoil" Uranlem. The lodine-134 activity is released to the coolant from the recoil activity that is plated out on fuel assembly surfaces due to fuel failures in prior cycles. In the FRl 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 plan!'.s currently in Action Level 3 Standing Order SO-O-43, Fuel Reliability Action Plan, based on the November prediction of 21 core average power fuel failures.

The maxim'Jm index point value for this indicator is 8. At the end of the November 1997, the FCS Value was 0.0. This compares to the previous month's value of 0.05.

Data Source: Guinn/Roenigk (Manager / Source)

Accountability: Chase /Stafford Trend: Adverse _

9

e n'onthlyChemistryindicator Fort Calhoun Goal (1.4) -

I 3

[,

2.75 2.M g 2.54 2.25

2 7

1.75 2.

1 27 1.32 1.05 1.5 1.31 1.18 1.14 1.13 1.32 1.25 ) 3 1.1 0.75 0.5 - .

, , >E w .

, +

2 % k E i E $ E E U $

o ,5 w z < a , < m 0 z

; 4 i

SECONDARY SYSTEM CHEMISTRY Criteria for calculating the Secondary System Chemistry Performance Index (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 November 1997 is 1.10. The CPI value for the past 12 months (December 1996 through November 1997) was 1.39. The CPI value in the industry's upper quartile 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) su! fete, 3) feedwater iron, and condensaie 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 November 1997, the FCS Value was 7.00. This compares the previous month's value of 7.00.

Data Source: Hamilton /Ostien (Manager / Source)

A :ountability: Hamilton Trend: None 10

m M re h P m a m I R dadon e mostre

-,_ OmMhePersamelRde6mEkposure K s e d 3B r i,s W =

T . .

35 _

30 _

! 25.

j 204 y

[15.

Q. 10 - 7.099 30EM 579 6 008

5. m 1.67 8 1.803 0[E - b b nun S 2 im Jan Feb Mr Apr Wy Jm Jd Ag Sep 0:t few Dsc ;

COLLECTIVE RADIATION EXDOSURE The 1997 Fort Calhoun goal for Collective Radiation Exposure , set at 38.0 person REM.

The exposure for November 1997 was 1.803 Person-Rem (Al 'OR). The year-to-date exposure through the end of November 1997 was 41.951 Person-Rem (ALNOR).

This indicator is a " COLLECTIVE" indicator. WANO does not differentiate between on-line and outage exposure. The Year 2000 WANO industry goci for collective radiation exposure is 120 person-rem per year. For the three year period (December 1994 through November 1997),

the total collective radiation exposure is 412.82 person-rem (ALNOR). The Fort Calhoun Station annual average over 3 years was 137.60 person-rem per year (ALNOR).

The maximum index point value for this indicator is 8. At the end of November 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: Adverse SEP54 I1

y 0

_e Morthlyindustrid Aeddert Rde

-o 12MarchR$kahorage R:SYear.Ehd Gul(4.50) c_ Yes2000VWolndustryGoal(4AD) 1 0.6 .

l 0.5 _

GA i b :. :. :. :. :. :. :. :. :. :.

OA 0.21 !

0.14 N _ _ _

0 . : : : : [ [ $ _e a j Dec Jan Feb Mar Apr May Jim Jdy Aug Sep Oct itw liDUSTRIAL SAFETY ACCIDENT RATE The purpose of this indicator is to monitor progress 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 200,000 work-hours worked 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 more days away from work (excluding the day of the accident.)

Fatalities.

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

The Fort Calhoun Station industrial safety accident rate for the month of November 1997 was 0.00. The 12 month rolling average (December 1996 through November 1997) was 0. The year to date value was 0 at the end of November 1997.

There were no restricted-time and no lost. time accidents in November 1997. The 1997 Fort Calhoun year-er'd goal is 50.50. The Year 2000 WANO industry goal is 50.40. The maximum

-index point value for this indicator is 5. At the end of November 1997, the FCS maximum index point Value was 5.0. This compares to the previous month's maximum index point value of 5.0.

Data Source: Sorensen/Blumenthal (Manager / Source)

Chase / Booth (Manager / Source)

Accountability: Chase /Gebers Trend: Positive 12

e

, e e MonthlyVolume of LLRW (:u. ft.) .

Year to-Dete Cumulative Radioactive Waste Buried Fort Calhoun Goal (1200 cu.ft.)

1200 -

T-1100[

1000 i

! 900.l.

g ;

800 $

8 g 700

4 u.

600 o 500 7 400. g g i

300 . o v;

$e k ,. .

200. g ;;

100.- g l 0 ;

man -

Jan Feb Mar Apr May J ur. Jul Aug Sep Oct Nov Dec l

1 VOLUME OF LOW-LEVEL RADIOACTIVE WASTE ;

This indicator chows the volume of the monthly Radioactive Waste buried, the cumulative l year-to-date radioactive waste buried, and the Fort Calhoun goal. J Ft ' .m*

Amount of solid radwaste shipped off-site for processing during current month : 00.0 00.0 Volume of solid radwaste buried during November 1997 : 162.2 4.5 Cumulative volume of solid radioactive waste buried ire 1997 : 733.3 20.5 Amount of solid radwaste in temporary storage : 00.0 0.0 The 1997 Fort Calhoun Station goal for the volume of solid radioactive waste (buried)is 120" wbic feet. The Year 2000 WANO industry goalis 45 cubic meters (1,589 cubic feet) per year, The industry upper ten percentile value is approximately 27.33 cubic meters (965.3 cubic fcet) per year, This indicator is no longer used by INPO, The indicator will still be tracked, but will no longer be used in coniputing the Station's ladex Number, Data Source: Chase /Breuer (Manager / Source)

Accountability: Chase /Gebers Trond: None SEP54 13

1 i

SAFE OPERATIONS Goal: A proactive, self-critical and safety conscious culture is exhibited throughout f r.e nuciear organization. Individuals demonstrate professionalism through self-ownership and personal initiative and open communication.

1 J

e 14 e

~v- ,,--n v ,, -.-e - , , , .-,-r o a - -

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

e

Monthly 06e6bhnginjuryalinese r$eqbency

% *2 Month Rolling Average 1997 F.C.S. Goal 0 *h .

l

~

0.6

, 0.4 .

t 0.3 y 0.2 ,

0,1 O

N : :

Dec Jan Feb Mar Apr May June July Aug sep oct Nov DISABLING INJURY /lLLNESS FREQUENCY RATE (LOST-TIME ACCIDENT RATE)

This indicator shows the November 1997 Disabling injury /lliness Frequency Rate and the disabling injury / illness rate for the past 12 months (rolling average).

For the month of November 1997 the disabling injury / illness frequency rate was 0.00. For the 12 month period (December 1996 through November 1997) the disabling injury / illness rate was 0.04 There were no disabling injury / illness cases reported for November 1997.

The 1997 Fori Calhoun Station year end goal for this indicator is a maximum value of 0.5.

Data Source: Sorensen/Blumenthal (Manager / Source)

Accountability: Chase /Gebers Trend: Postive SEP 25,26 & 27 15 l

~ ._ _.

M ontMy Recordable injurynlineaa Ffequenty Rate Roll 6ng 12 Womlh Average Fort Calhoun Goal (1,S) 4.S .

4.0 .

3.8 3.04 2.5

I 1.0 '

ri m- i Sep f

Dec Jan Feb Mar Apr May June July Aug oct Nov i i

I L

RECORDABLE INJURY /lLLNESS FREQUENCY RATE This indicator shows the monthly Recordable injury / Illness Frequency Rate, a rolling 12 month average, and the OPPD goal. A recordable injury / illness case is reported if perconnel from any of the Nuclear Divisions are injured on the job and require corrective medical treatment beyond first aid. The recordable injury / illness cases frequency rate is computed on a rolling 12 month average.

The recordable injury / illness frequency rate for the month of November 1997 was 1.41.

The recordable injury / illness frequency rate for the past 12 months (December 1996 through November 1997) was 1.46.

During the month of November 1997, there was 1 recordable injury an employee was moving a material cart and it rolled cver the foot resulting in a broken and cut great toe which required stitches and medication. There has been a total of 8 recordable injury / illness cases in 1997.

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

Data Source: Sorensen/Blumenthal (Manager / Source)

Accountability: Gebers Trend: Needing increased Management Attention MP 15,25,26 & 27 .

16

i a

M CantaminationEwres(MorWM !

-e ContaminationEntdsDTD) l l 100 .

90 ,

80 .

70 # es ",

63 60 57

, 50 40 41 f

1M. -

l 31 M- 34 20 j.

/

/ 16 8 11 7 Pd 10 a 5 5 6 ,

4 4 {

i 0 .. _. M S __S_E E I -

i Jan hb Mar Apr May Jun Jul Aug Sep Oct Nw Dec '

l-CLEAN CONTROLLED AREA CONTAMINATIONS >1,000 DISINTEGRATIONS / Mil;UTE PER PROBE AREA This indicator shows the Personnel Contamination Events in the Clean Controlled Area for contaminations 21,000 disintegrations / minute per probe area for November 1997.

There was no contamination event in Novmeber 1997. There have been 68 contamination events in 1997 through the end of November 1997.

Data Source: Case / Williams (Manager / Source)

Accountability : Chase /Gebers Trend: None SEP 15 & 54 17

3 . _

7-

_. Total EWrts 18NbrthTotds

[/y w .. Puertatie

o _s_ Pwend Far

= ss.

/ -*/.N-o

+

j3o, N

^

y #e',s ,

No-*-eg,,

s-s-a e/w- o

$! sN. k s

. _ . )_ V 0

8 8 8 s s s 8 8 " "

e 5 s aa e IM4I$$$$ $akI 4II8 PREVENTABLE / PERSONNEL ERROR Lens This hdicator 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 October 1997, there were two events which was subsequently reported as an LER. No LER's were categorized as Preventable and no LERs were categorized as Personnel Error for the month of October. The total LERs for the year 1997 is sixteen. 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 18

Msc 10*4 Ad-in i 3h l . 4.

I iS W ~

l .

l, ?

f I s, Design h 30 % :g l

l l

l l LO Dr.

'M- 13% !

' hint.

l 7% Oher &n 10 %

i j

UCENSEE EVENT REPORT (LER) ROOT CAUSE BREAKDOWN 1

This indicator shows the LERs by ovent date broken down by Root Cause Code for each of the past eighteen months from May 1,1996, through October 31,1997. To be consistent with the j Proventable/ Personnel Error LERs indicator, this indicator is reported by the LER event date, as 1 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.

l

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

i t

There were Two events in October 1997 that resulted in a LER.

j Data Source: Tills /Matzke (Manager / Source) 1 Accountability: Chase

Trend: None ,

j i

i 19

90 97 CURRDE e aoigws m CALP SALP a a w wnewstune*A

'gl ... n oiwvum-.tua eh ur )

newsm iumnewr.g Ca :ol e. hyan P' Died Wdeas (Ohneh wr.go kr W N top gaarth) gl I{

m; f ,

t- - - - t cL ,

C tz De ,

c, 4

s. _ .

e!

l 6[ s' _ ts .

I *

~ - =

i iw l '2L _,_ _

l

~

'h 2- . !"s } _# i- - - -

er Em E' > J l . Ilil s_

. E__.B1, o!. R - ok E - - o! a ,

k*

1h , }h b k $ 5 5 $ k $ $ b $

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 November 1997:

Violation Level LEfLNo. Title IV 97-18 Resident Monthly inspection NVC 97 16 Resident Monthly inspection To date, OPPD has received twelve violations for inspections completed in the current SALP cycle.

Levellli Violations 1 LevelIV Violations 5 Non-Cited Violations fi_,

Total 12 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 l

m. _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ . _____ _____ . _ _ _ - . _ . . . _ . . _ .

a r e ih5est 1.bnthly h:ludual Dposure nH f i , , F4 hest bdvdual Dposure Year.to-date na )

FCS Annual year end Goat 1000 nR'rdsdual 1000 l 900 .

800 700 i ,

000.

400-I 300.

200.

i 100 0 E -.-

reb f.br Apr f.by Jul Aug Sep 0:t th Doc l ._.

Jan Jun MAXIMUM INDIVIDUAL RADIATION EXPOSURE This indicator shows the highest exposure for an individual during the year 1997.

For the month of Novernher 1997, an individual accumulated 63 milllRem, which was the highest individual exposure for the month.

For the year to date, an individual has accumulated a total of 744 millirem TLD and ALNOR readings.

The 1997 Fort Calhoun Station Annual Administrative year end goalis a maximum of 1,000 millirem from all sources of occupational exposure at FCS. The OPPD limi' for the maximum yearly individual radiation exposure is 4,000 milllRem/ year from all sou af occupational exposure.

Data Source: Chase / Williams (Manager / Source)

Accountability: Chase /Gebers Trend: None 21

v Miased STs Resulting in LERs l 3 .. l t i l

i 24 j l '

1- i '

)

i l0 0 0 0 0 0 0 0 0 0 0 96 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec i

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 November 1997.

There were no missed surveillance tests resulting in LERs dunng November 1997.

The 1997 Fort Calhoun monthly goal for this indicator is 0.

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

Accountability: Chase /Phelps Trend : None SEP 60 & 61 22

l l

i PERFORMANCE I

l 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. '

23 ,

e i P

I Not Generation (10.000 MWh) l 88'i 34,8 38 14 34.48 35.1 [

34.43 33.3 4IIiiIIIilI i

$ k $ 5 5 $ k k $ $ E 5 STATION NET GENERATION During the month of November 1997, a net total of 348251.4 MWh were generated by the Fort Calhoun Station. Cumulative not generation for Cycle 17 was 3,809,106.30 MWh at the end of November 1997. Cumulative net generation for Cycle 16 was 5,418,326.6 MWh.

Data Source: Station Generation Report Accountability: Chase Trend: Nono l

24 J

l

" i.--- ...-,-.,,_m- . . , . _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _

y-0 a Monthly Forced outage Mate

,, Rolung 12 Month Average t 1997 Fort colhoun Goal (1.4%) ',

60% ,. ,

i 43 % 1 46%

~

40%l 7 j 36%.

31 %

30%. -

26% . ;

20%1 f 16% .

10%

'"T' sg , L . . _

/

/ Y. -

_7 IIe 0% 0% 0'% .

0% 0% 0% 0% 0%

0% 4_ -

96 Dec Jan Feb Mas Apr May June July Aug Sep oct Nov FORCED OUTAGE RATE The Forced Outage Rate (FOR) for the month of November 1997 was 0.00%. The forced outage rate for the previous 12 months (December 1996 through November 1997) was 7.05%. The 1997 year to-dato FOR was 7.6% at the end of November 1997. This indicator needs increased management attention since it exceeds the FCS goal.

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

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

Date Source: Monthly Operating Report -

Accountability: Chase Trend: None 25

O MonWyM capockyFector ;

i .. Year 4oode UnN capacky Factor j .. W capaceyrector for cWie 17 l 1M7 FCs Goal (M.00t9 110% ; Cyde 17 100% J yN wq _

90% .

j ~ '-*% ___ . .

-~ *

-a 80% , 6 ~, _m_-

, 70%;

jl f - i en } l i 50 % i ; a'

!40%l l 30%. !

20%. Il I 10%_

0%

l C 16 De Jan Feb Mr Apr May June July Aug Sep od Nov UNIT CAPACITY FACTOR This indicator shows the plant monthly Unit Capacity Factor, the Unit Capacity Factor for the current fuei cycle, the year-to-date, and the 1997 OPPD Station goal.

Unit Capacity Factor = NRLElfs.trical Enerav Ggngrated (MWH)

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

At the end of November 1997, the Cycle 17 Unit Capacity Factor was 100.00.The Unit Capacity Factor for the last 36 months (December 1994 through November 1997) was 83.05. The 1997 Fort Calhoun annual goal for this indicator is 96.00%

The year to-date value is 90.99%

Data Source: Monthly Operating Report Accountability: Chase

-Trend: None 26

__ = _ ._. - _ _ .

Y oeste Average Mortidy EAF <

-a- Rolling Average l >

99.2 99.1 % 97.5 % 97.5 % 98.7 % 98.3 %

100 % . 94.3 % 96.1 % T 92.8 %

90 % 4

_ 7T 'a

--- '*"* * *^

-e-g

'- - -*' * ' ' # i - -

70 %

60 % i:

50% .

45.7%

40 %

f 30% .

20% -

I 10%p 0% _. - - # 4 Dec Jan Feb Mar Apr May June July Aug Sep Oct Nov l

EQUIVALENT 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.

i The EAF for November 1997 was 98.03 %. The 12 month rolling average (December 1996 through November 1997) was 88.05%. The equivalent availability factor for the past three years (December 1994 through November 1997) is 82.16%.

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

Data Source: Dietz/Mikkelsen (Managers / Source)

Accountability: Chase Trend: None 27

. _ . . _ . . =. __

2 r_ _

m Safety System Actuations (INPo Definition)

FCS Goal (0)

+ Industry Upper 10 Pe::entil)(0) ,

i 2+

!14 I

I, 0 0 0 0 0 0 0 0 0 0 0 0 0 02 + : : : : : : : : : : : _; ,

i 96 Dec Jan- hb Mar Apr May June July Aug- Sep Oct Nov 1_

UNPLANNED SAFETY SYSTEM ACTUATIONS -(INPO DEFINITION) t There were no WANO unplannad safety system actuations during the month of November 1997.

There were no WANO unplanned safety system actuations during 1990.

The 1997 Fort Calhoun goal for this indicator is 0.

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

28 L-

l g Safety System Actuations (NRC Definition) e FCS Goal (0)

+ Critical Hours 10 __ 1996 RFo 800 8 .*~

00

~ $00 6_- {

4 400 f 4- __300

- 200 o 100 9

0a < . '0 0 J F M A M J J A S o N ,

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 Trend; None 29

i i

i m Gross Heat Rete

+ Year to Oste Gross Heat Aste Pwt Calhoun Gael l

l 10.75 8 ~

S S e e N

o n 8 o

g $

o ko 6 o

N o

~ ~

5

- o @

10.25 ei a -

\. -

, - F -

9.78 j t

9.26 . -- -

M nec Jan Feb Mar Apr May June July Aug Sep Oct Nov G7 TOSS HEAT RATE This indicator shows the Gross Heat R9te (GHR) for the reporting month, the year-to-date GHR, the goals, and the year-end GHR for the previous three years.

The gross heat rate for Fort Calhoun Station was 9,998 BTU /kWh for the month of November 1997. The 1997 year to-date Average GHR was 10,144 BTU /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 10.144 BTU /kWh.

Data Source: Guinn/Schawe (Manager / Source)

Accountability: Phelps/Naser ;

Trend:- Positive l f l l

l 30 l

l

Thermal Output a 1997

= Fort Calhoun 1495 MW ooal Tech Spec 1500 MW Limit :

r 1600 ,

1000 i 800 600 400 t i

200 O '

- " = n a : a e > c n n n n n t :

^

DAILY THERMAL OUTFUT The thermal output graph displays the daily operating power level during November 1997, the 1500 thermal megawatt average technical specification limit, and the 1498 thermal megawatt Fort Calhoun goal.

Fort Calhoun Station (FCS) operated at a nominal 100% power level until November 14,1997 at 19:41 hours when power was reduced to 85% to allow testing and repair of the main generator stator cooling heat exchanger. Following testing and repair, the power level was increased reaching 100% on November 17,1997 at 18:16 hours where it remained through month end, Data Source: Guinn/Schawe (Manager / Source)

Accountability: Chase /Short Trend: None b

9 31

l % Monthy Equipment POR e Equipment PORli,000 CrNical Hrs. (Rolling 12-Month interval)

Fort Calhoun Year End Goals (0.2) 2, 1 75 t ;

i 1.5 -

i 1.25 .

1 0.75 0.5 0.25 - a a N f g a

N _g 1: 4 0 - - - - -

Dec Jan Feb Mar Apr May June Juy Aug Se p oct Nov EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS The Equipment Forced Outage rate per 1,000 critical hours for the Rolling 12 months from December 1,1996 through November 30,1997, was 0.243. The year-To-date rate per 1,000 critical nours for the months from January 1,1997 through November 30,1997 was 0.266.

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 ,

~

Trond: Nono

v CHE'.*l8TRY ACTCN LEVELS EXCECED ,

cEvent Days + Averspo Event Days l 6 6 l

6. -

5-4 1 r

> d4 --

b h $1 O b5 1

$ d 8

)s ~. -m 0 0 f 0* I I ! ,

I9 f IE f k

E h

2 2

! Y 2 R

$~

k E

8 k

2 4 ! j i

CHEMISTRY ACTION LEVELS EXCEEDED EVENT OAYS The Chemistry Action Levels Exceeded indicator tracks the number of days in wnich (#e nbtiy parameters exceeded a corresponding action level for the reporting month, as well es a ,

12-month average of days an action levelis exceeded. The parameter action levels are delineated in Chemistry procedure CH AD-0003," Plant System Chemical Limits and Corrective Actions."

An action level is considered to have been exceeded for the purposa of tHs indicator, whenever the parameter exceeds the CH AD-0003 action lovel for the current sysiom mode, with the exception of the Steam Generators during Mode 1.

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

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

The 1997 Fort Calhoun goal for this indicator is the 12-month average of two event days per month. There is no goal est' tished for the number of event days per individual month.

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

There were 0 Event Days in November.

Data Source: Chasc/ Hamilton (Manager / Source)

Accountability: Hamilton Trend: Needs increased Management Attention -j 33 L

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

P

, i% Hours Out of Lh*

8.00 . OPIOGoat(5%)

5.00 +

4.00 +

i pci 3.00 .

2.M 1.48 1 01 1.21 1,og _

1.00 , -

o.oo 0.00 0.00 0.00 0.00 0.00 0.00 0.00 b k k k k $fkkh b h t

PRIMARY SYSTEM LITHlUM % HOURS OUT OF LIMIT The Primary System Lithium Percent Hours Out of Limit indicator tracks the hours per month that the primary system lithium is out of specification.

The Primary System Lithium Percent Hours Out of Limit was 0.00% for the month of November 1997.

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

r e

Data Source: Chase / Hamilton (Manager / Source)

Accountability: Hamilton Trend: None W

i 34

4 i

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

35

. _- . _ _ _ -.n _ ,-

t

_ Actu.i _._ 84.t _nn 3M ;

3M. [

3M. ~

I 3.20 .

3M_ M ~s am, , N --*--* % l am. N \ i 2.40 . \--e 2.20 -

3M c

asyaaa:;*****k 2 aaggggg kkkikkiiklki!Riik .

CENTS PER KILOWATT HOUR October 1997 The purpose of this indicator is to quantify the economical operation of Fort Calhoun Station.

The Cents Per Kilowatt Hour indicator represents the budget and actual cents per kilowatt hour on a 12 ,

month rolling average for the current year. The basis for the budget curve is the approved 1996 and 1997 revised budgets. The basis for the actual curve is the Financial and Operating Report.

The Decomber 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 is provided by Nuclear Fuels.

- The 12 month rolling average unit price (period of September,1996 through October,1997) svoraged 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 (9/96 through 10/97) is 3.12 cents per kilowatt hour.

The year to-date average is trending in a negative direction. This information normally legs by a month due to the short turn around required for processing.

Gents.3ter KWH Jan Feb Mar Anr May Jun Jul Aun Sep Oct Nov Dec r Budget Y.T D 2.83 2.66 2.58 2.55 ~ 2.44 2.46 2.48 2.46 2.42 2.43 2.42 2.41

. Actual Y T D 2.89' 2.60 2.54 2.75 2.99 -2.90 2.83' 2.79 2.79 2.73 0.00 0.00 Data Source: Lounsberry/ Dent (Manager / Source) -

Accountability: Lounsberry ,

Trend: Needing increased Management -

36 l +

1 l

l I

I r

i !

DIVISION AND :

i DEPARTMENT 1 i

PERFORMANCE ;

INDICATORS Goal: Achieve high standards at Fort Calhoun i

Station resulting in safe, reliable and cost '

l effective power production. i

!' I l

i l

I i

37 8

__.-_m. __ .._____._______..____m ---.,---,.______......,,_4 ww _ . . _ . _ , __, _ _ _ , . . . - . , , , _ ._,, _ - , , - _ . _ . , - m, ._-y,_ , . ~., ,,...-- . .

4 m Corrective Maintenance a Preventive Maintenance i i Non-Corteclive/ Plant improvements Fort Calhoun Goal (250) 0}N 729 682 624 625 630 763 674 636 644 592 300 ., -~~ -

@0 h - ]U 200 1 100 1 0 1.. -- - + - -.- -.- - - - - - +

u. h h ,<k b Non. outage Maintenance Work Document Backlog D Total MWDs Past Cor.ipletion 33 46%

300 j$$ "

N)}j h " M 0i-O 2

__ i - _. la:n-h-

64% Y * 'U ,M -

Ruty Rtrty Ruty Rtriy Rrrty 1 2 3 4 5 Not Com pleted e

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. The current backlog of corrective MWDs is 227 To ensure that the MWD backlog is worked in a timely manner, non-outage maintenance completion goa!s have been established as follows:

.Gral Priority 1 Immediate Action 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Priority 2 Urgent 5 days Priority 3 Operational Concerns 21 days Priority 4 Routine Corrective 90 days Priority 5 Non Essential 180 days The 1997 Maintenance workload backlog goal was revised from a maximum 350 to 250 in September 1997.

l Data Source: Chase / Johnson (Manager / Source) l Accountability: Chase /Faulhaber Trend: Adverse SEP 36 38

l Ratio of Pr:ventive t2 Total Maintenanc3 90% ! '

l90%, %

84 %

74 %

77 % 74g 76%

I 80 %

70%l m 65% .

G i 60% y I- . . .

., 52% % ge 'I

!50%1 ;' .

y gtj h

l40%i f 30% - p 4 >

20% a - ;. pf , [h ) l l 10% d s 'q n: b L[ ' .] ' O), 'i 0% ;_ IA- _ _ L _.-.- N _ -._ O _._ N _ ,_ _._ -

A-l 3 m i

ym -m e Preventive Maintenance items Overdue Fort Calhoun Goal

)6%.- S.50%

r,g 4.90% ;

j $% ~ 6 7 i f 4% . 2.00% 2.40%

j g 0.66% >I j 2% 4 0.63% 0.66% ~l 0.25% 0.56 Y ~: I 1% . g'a o oog 0.20% 0.30% <t ;

$2 o % ,_ c=i _._ Ed _lE % 12 c=n . _ t=3_._1. __

^" '. l i b N $ 5 5 $ k k $ $ b $

l RATIO OF PREVENTIVE TO TOTAL MAINTENANCE PREVENTIVE MAINTENANCE ITEMS OVERDUE The top graph shows the ratio of completed non-outage preventive maintenance to total completed non-outage maintenance. The ratio was 76% for the month of November 1997.

The lower graph shows the percentage of scheduled preventive maintenance items that are overdue. From the period of October 15th thru November 15th there were 24 PM's were completed late or not completed out of 490.

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)

Accountability: Chase /Faulnaber Trend: Needing increased Management Attention SEP 41 & 44 39

)

. . ~ . - - - - . . -

n . u.ini.ni.nc. ii.m. compi.i.a

% Id.ntifled .s Rep..t 600 6.0%

600

... ; N s

, I.60%

nr i u, K225 g no . ... c; no. "'

"8 in f e N .

.u,

~ " '

~ s ~ s.. ,..

~

u. , ~ , ,,

~

u.,' s . so,

~

a o,~~ .. , oi u..

i

"'" %,U'In'i'$'o"!."AUL*""

.0%

t.%

- m, g ,, , , , , , , , , ,

'g

' '~

o.. ~ ., ~ a ~ u., ~ 4,, ~ h ~ son.~ so,, ~

s to,

~

s., o.i

~

~.,~

PERCENTAGE OF TOTAL MWDs COMPLETED PER MONTH IDENTIFIED AS REWORK / REPEAT This graph indicates the percentage of total MWDs completed per month identified as rework. Rework activities are ider tified by maintenance planning and craft.

This indicator is calculated from the 15th of October through the 15th of November 1997, due to the delay in closing open MWDs at the end of each month. The Fort Calhoun monthly goal for this indicator is <3%. A detailed review is conducted of rework items each month to identify generic concerns.

Data Source: Faulhaber/ Johnson (Manager / Source)

Accountability: Chase /Faulhaber Trend: Needs increased Management Attention ,

40

V i

, ,MartNyomettu(Onuw) l l

_ _ YT0MortNyAnorage(Orh)

Fort Onihom"OnUne"(bal(10%

25.0%

7 21.4 %

20.0% .

1 16.1 %

15.0% .

' 11.5%

9.8%

10.0% _ __

EO% A -- #

45%

5.0%-_*N _ / 4[%

1.7%

0.0% --

U > l r : ,

Jan Feb Mar Apr May Jm Jd Aug Sep Oct Mw Dec

. + . .. . . .

MAINTENANCE 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 16.1% for the month of November 1997.

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

Data Source: Chase / Johnson (Manager / Source)

Accountability: Chase /Faulhaber Trend: Needs increased Management Attention

. i l

41 l

+ n s - . ., .,. . .. . - - . ,,- - - .w._u._=-- u_--

Human Performance CRs(MaintenancI)

"I 18 4 i

l t 16 3 l '

14 14 --

12 __ ,

a ^

s l h

g 8-- 7 !

6-- $

4 I 4

4. --

2..

I 0

May June July Aug Sep Oct Nov PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)

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

Data Source: Faulhaber/Burggraf (Manager / Source)

Accountability: Chase /Faulhaber Trend: None SEP 15,41 & 44 l 42

~

e _ % Pats'6dS -.% fbn-PAMi~66Sl

+ % Total oos Total % ooS Goal 14 % a T

12% .

10%

8% .

e% .

4%

NN. y

~

0% e i = 'N'.-k

= _ _ =

l 8 a B k B k u u u u 5 b k b b h h k b h h b $

i IN-LINE CHEMISTRY INSTRUMENTS OUT-OF-SERVICE This indicator shows the percentaga of hours the in-line chemistry system instruments are inoperable for the reporthg month. The chemistry systems involved in this indicator include the Secondary System and the Post Accident Sampling System (PASS). At the end of November 1997, the percentage of hours the in-line chemistry system instruments were inoperable was 1.42%. 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 SER'/lCE:

Feedwater Heater disolved oxygen inline analyzer B S/G conductivity inline analyzer Data Source: Chase /Ostien (Manager / Source)

Accountability: Chase /Skiles Trend: None 43 l

1

m W:sb Produced Ea:h Month (Kilograms)

Fort Calhoun Monthly Average Goal (150 kilograms)

+ Federal & State Meeithh 8.imit (Max.of 100 kg) 500 ,

4501 400 350 3001 250-200 g.

150 ' .

it)0 .

50 .

0 ,

$ l ! a k k f k < d E $

HAZARDOUS WASTE PRODUCED This indicator shows the total amount of Hazardous Waste Produced by the Fort Calhoun Station each month, the monthly average goal and the monthly average total for hazardous waste produced during the last 12 months. This hazardous waste consists of non-halogenated hazardous waste, halogenated hazardous waste, and other hazardous waste produced.

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

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

SPECIAL NOTE:

-FCS has recently revised it's classification with the State of Nebraska.

Due to our reduced waste generation over the past several years, we have revised our status from SMALL QUANTITY GENERATOR (</1000 kg/ month) to a CONDITIONALLY EXEMPT SMALL QUANTITY GENERATOR (<100 kg/ month).

Data Source: Chase /Shubert (Manager / Source)

Accountability: Chase / Hamilton Trend: None-

, i Contaminated Radiation CJntroNed Area Fort Calhoun Goal (59Q 10% .

9%.

s% 9 r-- _ _ _ _ _ _ _ _ _

7% 4 i

6% 1 i \

~t t 4% I 3% T 2% .

1%

7

! l 0% I j

,E 1

u. a 2

} a z

8 ,i i

? A" ] ,

i 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 G.0% contaminated RCA in May 1997. This indicator has an Adverse Trend since it exceed the FCS goal.

At the end of November 1997, the percentage of the total square footage of the RCA that was contaminated was 6.8%.

Data Source: Chase / Williams (Manager / Source)

Accountability: Chase /Gebers Trend: Adverse SEP54 45

-- .~

_ Poor Raltion Worker Practices Fort Calhoun Goal (<10)

+ Total PRWP for 1997 ;

16 .

14 .

12 .

10 .

8-6 .

4$

o _

N Jan- Feb Wr Apr Wy June Ju!y Aug sep oct tbv Dec RADIOLOGICAL WORK PRAC'CES 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 accountability for their workers' radiological performance. 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 November, there was 1 PRWP identified.

There have been a total of 10 Poor Radiation Worker Practices in 1997.

The1997 Fort Calhoun Station year-end goal for PRWPs was revised by the Radiation Protection Department in October 1997 from a maximum value of <15 to <10.

Data Source: Chase / Williams (Manager / Source)

Accountability: Chase /Gebers Trend: Needing increased Management Attention SEP52

~

46 L

O. Drottments Schod:; led ist Reviec g Docum ent R9 view s com plete du,ing m onth -

g Documents Overdue 400-_. -

350.

I" -

200 .'. -

250.. , _

-200 +

l 150.-

100..

O _ k._ I _ E. E _ E. A_ . . ,_ ._

sa s n >

1997

s8 a DOCUMENT REVIEW The Document Review indicator shows the number of completed, scheduled, and overdue (greater than 6 months past the scheduled due date) blennial reviews for the reporting month. The documents reviews are performed in-house and include Special Procedures, the Site Security Plan, Maintenance Procedures, Preventive Maintenance Procedures. and the Operating Manual.

During November 1997, there were 237 document reviews scheduled, while 58 reviews were completed. At the end of the month, there were 83 document reviews more than 6 months overdue. There were 22 new documents initiated during November 1997.

Data Source: Chase /Plath (Manager / Source)

Accountability: Chase /Skiles Trend: None SEP 46 -

47

.. . . ~ -

. . . . ~

e o Syst:m F;llures a Non System Failures

! 27 25 .j 25 21 0

T 18

"' 13 13 12 12 0

I Dec Jan Feb Mar Apr May June July August Sep Oct Now i

LOGGABLE/ REPORTABLE INCIDENTS (SECURITY)

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

During the month of November 1997, there were 9 loggable/ reportable incidents identified. This is a 65% decrease in system and non-system failures from the previous reporting period and is the lowest number of loggable events during 1997.

System failures accounted for 67% of the total failures. One security force error and two unsecured vital area doors accounted for the non-systems failures during the reporting month. It should be noted that there were no lost / unattended security badging or access authorization incidents during the month. Security force errors continue to be the focus of management attention.

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 SEP 58 l

-48 1

, i Tcmporary M:difications >1-cy31e tid (RFO required f r r;mtv:l)

_ TCmporary Modifications >6 mtnths cid (Remtvable cn.lin:)

Fort Cath:un Goals f;r >1 cycle end >6 m:nths cid 1

3 3

7 2.54 21

1 1 1 18 1 1 1 1 1 1.51 fd '

1!

i 1i d 1 1 N E $ % E D E E E U o I' O 7 6 2 4 3 $, < m O z 4

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. MR-FC-97-011 is expected to be completed during the 1998 RFO TM 96-018, Equipment Drain Header Soft Rubber Patch was installed June 16,1996.

MWO 963468 is currently scheduled for the 1998 RFO.

At the end of November 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 close this TM. EAR 97-219 requires System Engineering review and approval. EAR 97-219 is expected to be completed by May 1,1998.

At the end of November 1997, there was a total of 13 TMs installed in the Fort Calhoun Station. Ten (10) of the 13 installed TMs require an outage for removal and 3 are removable on-line in 1997, a total of 17 TMs have been installed. At the end of November 1997, there were three (3) 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 49

i i TotallWbdficadanPackagesOpen

__- RrtC2amWer.End(bal(68) 80 . n n ,

~

n

~

n 75 _ M

~

- 70 4 3 65 .

00 . _

l

M I

4 . , i + - : :

96 Jan Feb hr Apr hy Jun Jti Aug Sep Oct ttu Dec OUTSTANDING MODIFICATIONS This indicator shows the total number of Outstanding Modifications (exc.luding outstandino modifications which are orocosed to be cancelled).

Reporting Category _ '94 'M '93

. '9Z '93 .'9.9 Month Form FC-1133 Backlog /in Progress 0 0 0 1 0 0 1 Mod. Requests Being Reviewed 0 0 0 0 0 7 7 Design Engr. Backlog /in Progress 0 0 0 0 4 5 9 Construction Backlog /In Progress 1 0 4 6 12 0 23 Design Engr. Update Backlog /In Progress J 6_ ._I ,2 _Q _Q ?Q Totals 6 6 11 9 16 12 60 (outage + OnLine) (2+4) (3+3) (9+2) (2+7) (14+2) (9+3)

At the end of November 1997,27 modification requests have been issued this year and 8 modification requests have been cancelled. The Nuclear Projects Review Committee (NPRC) has conducted 73 backlog modification request reviews this year. 1 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: Positive 50

6 60 E ARs Regoleing Enginee ring Clos sout . Not in Clos ecut ,

j 88 m SE D DEN 40 4 ~

33

~

24 28 30 + 27 21 21

~

1 T qg g4 34

! _ r 10 -

p 8

18 s N 7 7 e

8 2 2 i 2 1 k" k] I 1

.m _ rr i .E rm - P b, u 2_-

Sep oct Nov Sep oct Nov Sep Oct Nov Sep Oct Nov 0 3 M o n th s 3 6 Months 612 Months $12 Moriths O Engineering Response a Closeout (sE) 30 3, 20 .; 13 5 3 5 5 101 2 3 0 1 2 1 0 0

,. , m,, I , ,

Priortry 0 Priority 1 Priority 2 Priority 3 Priority 4 Priority 5 Priority 6 cio s e.oi

.7 e u , , , , , , ,

s . .'.". . l . a's,';;"

a 496%

h) _y h = = ~._m a

__. a- x,

' i;. f t

n.s . se u es o ,. r o .

C lo s . o v ts t 3.0 %

ENGINEERING ASSISTANCE REQUEST BREAKDOWN This 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. l The Total EAR breakdown is as follows: I EARS opened during the month 8 EARS closed during the month 31 Total EARS open at the end of the month 115 Data Source: Jaworski/Livingston (Manager / Source)

Accountability: Phelps/Jaworski .

Trend: None SEP 62 51

i 44 47 118 344 '

Clostout 86 months 6 3 LI&nthe DEN I4 M'"Ih8 10% P3g 14%

,4g s .t.

+

l $f - hges, u._ . . . .

+nx coNst. , ~ ' '

d'%

$%)%%h i d*

lECN STATUS - OERALL BACKLOG l 49 0 Backlo0ged O Received a Completed 45 0 3 Months 22 l

>6 Months 42%

2bu 39% _S, 3 6 M19% o n th s j 118 119 117 126 112 150 115 s

~ -

26

] 20 26 2625 ;]

1 s 745 25 241 6 23 14 23 50 1: E3 + 51. im _ 4:m. l I:3 1m_.

50 - June July Aug Sep Oct Nov EESIW N N 250 _ e i

75 200 1 3 4 u e nin.

.s .e u nin.

l 87.2%

150 2 ,

85 81 M 77 86 e.3 u n in .

100 ^ '

7 14 m12 - 10

~'

, 16 50 J l g

i 12 13 ;10 5 ,

1716 $3 0 L irma .1_n::s 1.=s:1 s. - IA L3:1-Juno July Aug Sep Oct Nov SNNN HW 300 8 250 ,206 211 217 213 220 ,,,,,n,,,

11 204 200 . - - - 7 4.1 % , ,, g 150 . 9 } , g3 100 . : 12 -13 5

'. 16 ,

50 . f 912 4 5 6 . 8 5 2 04 a ==== _ - =w I. _

288 June July Aug Sep Oct Nov , , ,, g PROCUREMENT /CONSTUCT10N 7

250 0 3 Months 3 6 Months 200 2 11.4 %

15.9%

i 150 .i 100 gg 46 June 42 44 46

" diLd'n fe nan 64 &g J uly Aug 4926 Sep 492 Oct 441 Nov f,

h.

j lD R AFTING/CLO SEO U rl ENGINEERING CHANGE NOTICE STATUS _

Data Source: Jaworski/Livingston (Mansger/ Source)

Accountability: Jaworski/Phelps Trend: None SEP62 52 l

~

% M l Pdorkytut Pdadeyles 93 DC TYPE IM IM M 25%

8"'"'"

v

_/

s Total Open ECNs = 462 k2 Pd*'kF 3"(8- y 51% sa Total ChenENs= Et

,o

= .,

14. ., 12 7 g ig ig

'N

'** a 32 gg g4 tes 2' 25 to g

46 50 34 10 44 37 33 pg ygg2

' 2 2 4 Priority 586 1 0 4 22.8%

88%

2. ? .

55 :: si .. 52 46 8 '" '*% ,'I.f'." e eCA;'oP.n 255 Pr onty p 253 249 251

{ 11 9 15%

3,a 2 14 7 8 200 ,1 EO B5 5 16 7 E2

-150} 17 5 42 ,3 Pr or ,y Jun47 Jul-97 Aug-97 Se N 7 Oct 97 Nw47 SubstRute Replacemers kom ECNs Open 64 %

48 4 4t Priority 844 Priority 1&2 Priority 3&4 51.4 % 4.3% 44.1 %

100 . to ts

s u

i, t

a a g-40 :

j w

g ,,

1 G A,y

.m June July Au. Sep Oct Nov Decument Change ECNs Open

~

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

Accountability: Phelps/Jaworski Trend: None SEP 62 53

a

(. O l i i Startup m Shutdown m Operations

...o. Industry Average Trend 2-1.5 .

g 1.

0.5 . o ...o ....o.... ....a ...o......o..... ....o......e......a......o 0 m i 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 i

Year-Quarter j

! +

SAFETY SYSTEM FAILURES This indicator illustrates the number of NRC Safety System Failures as reported by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data in the 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 greater 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 resuhed in a failure of the system to meet design requirements during a seismic event.

4th Quarter 1993: 1) During surveillance testing, both PORVs for the LTOP system failed to open during multiple attempts. The fai!ures were a result of differential expansion caused by a loop seal, excessive venting line back pressure, and cracked valve disks; 2) Calibration errors of the offsite power low signal relays could have prevented offsite power from inpping and the EDGs from starting in the required amount of time during a degraded voltage condition; 3) Both AFW pumps were inoperable when one was removed from service for testing and the control switch for the other pump's steam supply valve was out of the auto position.4) Only one train of control rovin ventilation was placed in recirc when both toxic gas monhors became Inoperable. Later during surveillance testing, the other train auto. started and brought outside air into the control room for a six-minute period.

1st Quarter 1994: A design basis traview 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, CC'N temperature could rise causing compressor rupture

- disc failure and a release of freon.

There were no safety system failures since the 4th qua:ter of 1995. -

Data Source: Nuclear Regulatory Commiss6n Accountability: Chase Trond: Nono 54

O Total Requalific" tion Training Hours g Simulator Training Hours g Non Requalification Training Hours s O Number of Exam Failures 35 . 33 g$

31 31 30 +

25 i .

22 20 .

gg 4 4 14 15 2 !

i 10 g g 8

, g, l 6

I* 3

~

0_ .

_ Su .

Cycle Cycle Cycle Cycle Cycle Cycle Cycle. Cycle Cycle 96 5 96 7 97 1 97 2 97 3 97 4 97 5 97 6 97 7 LICENSED OPERATOR REQUALIFICATION TRAINING This indicator provides information on the total number of hours of training given to each crew during each cycle. The simulator training hours shown on the graph are a subset of the total training hours. Non-Requalification Training Hours are used for AOP/EOP verification & validation, INPO commitments, GET, Fire Brigade, Safety Meetings, and Division Manager lunches.

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

Note: Rotation 97-6 was the Annual Licensed Operator Requalification Examination rotation for 1997. There were Three (3) individual and one (1) crew simulator exam failures during rotation 97-6. All remediations were completed prior to the end of the exam week.

Conceming Reactor Operator and Senior Reactor Operator Candidate exams:

Currently, there is no initial Licensed Operator training class in session.

Data Source: Conner /Guliani(Manager / Source)

Accountability: Conner /Guliani Trend: None SEP 68 l

1 l

55

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

t i

O SRO Exims Administred a SRO Exams Passed )

I l o RO Exams Administered '

I D RO Exams Passed I

10 i

l l

l 77 77 77 77

)

i 5

l 1

1 4 :

0000 00 00 00 00 0000 0000 0000 0000 0000 0000 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec ,

i LICENSE CANDIDATE EXAMS - 1997 This indicator shows the number of Senior Reactor Operator (SRO) and Reactor Operator (RO) quizzes and exams taken and passed each month. These internally administered quizzes and exams are used to plot the SRO and RO candidates' monthly progress.

During the month of November 1997, there were no (SRO) or (RO) training classes in session.

Data Source: Conner /Guliani(Manager / Source)

Accountability: Conner /Guliani Trend: None SEP 68 l

56 l.__-_..

l Oosed

+ Total 04

-e- % to oose i

35001 3000.

i l 2000E A 1500a 1000 l _

A; :--

55 _ _ _

-: -w ____r= - -r -

}

g : : :

' 3 I

8 I8 8

E 5 5 E dgk 5

+

E 5 l k8 5 4 CONDITION REPORTS BY LEVEL This indicator shows the total number of Condition Reports which are Closed, Ready to Close, Open and the Total Number of Condition Reports to date.

Level 1 Level 2 Level 3 Level 4 Level 5 Level 6 Total Open 25 16 111 770 21 237 1180 Closed 17 14 145 1449 539 381 2545 380 condition Reports are classified as READY to CLOSE, Data Source: Tesar/Burggraf (Manager / Source)

Accountability: - Andrews/Gambhir Trend: None 57

= \

D** M W D HOLDS l e M ** M System Pam j

Engineering 6%

3i -

Planner 5% )

I E "g 7

= = -

- ts .

g m m g =

g = - =

EEW MWD PLANNING STATUS (CYCLE 18 REFUELING OUTAGE)

This indicator shows the total number of Molntenance Work Requests (MWRs) and Maintenance Work Documents (MWDs) that have been approved for inclusion in the

- Cycle 1r '*efueling Outage. This graph indicates:

- Parts Holds - Planning Complete, Awaiting Parts

- System Engineering Holds - Awaiting System Engineering Input to Planning

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

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

- In Review - Planning Complete awating SE, ISI and OC review.

Data Source: Chase / Johnson (Manager / Source)

Accountability: Chase / Herman Trend: None SEP 31 58

V gLAST OTHIS gg FOR SCHEDULE so .

= E .1

,,i 3 8 i

E E E $

60 I

~

E Lso ! [ t) ,

,0; ( 1 ll i _

!h!..i190e I nil v i COMPONENT TESTING DEPARTMENT AND SPECIAL SERVICES ENGINEERING DEPARTMENT 1998 OUTAGE PROJECTS STATUS REPORT e

l

1=

11/2747, k.ls-s " s 5

10/2857 < ; , ,

=

, , , ; ; , . . . . . "e -

7/3097. 5 ,,, s s

N $'$-

5 h EI , ActualEDato 4/197.

. Tag E We 3297.

1/3147.

1/1S7 L

111111111ll 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).

The goal for this indicator is to have all modification packages which were identified prior to March 20,1997, PRC approved by September 15,1997.

November 1997 Modifications added: 0 Deleted = 0 Data Source: Jaworski/ Walling (Manager / Source)

Accountability: Gambhir/Jaworski Trend: None SEP 31 60 L

v ;

. Actual PRC Date .Taget PRC Date 1 2/596. .s 12/17S7 ... e s ;

10.7&97 . *

.a,7 .

sg-="

7/20/97 .

f/31S7 .

I 4/11/97 . j 2/20/97 -

1/1/97 .. -

L I!fk

$$oE w w I

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.

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

Accountability: Gambhir/Jaworski Trend: None SEP 33

- i 61 1

No 1997 On Line Modifications Currently Approved PROGESS OF 1997 ON LINE MODIFICATION PLANNING This indicator shows the status of modifications approved or in review for approval for on line in tallation during 1997.

The goal for this indicator is to have all modification packages PRC approved by their scheduled date, November 1997 Modifications Added: 0 Deleted: 0 Data Source: Jaworski/ Walling (Manager / Source)

Accountability: Gambhir/Jaworski Trend: None SEP 31 62

a-3fd .uee--4 m+4 marg.w..a.m-- raaa.-e,-oe,a na.4, 4.5AE,.a a e a yam,.mm--rm u m m _ s,sa ma 4 m su a aA_4,a e4 -..me m.m,s.m.saiag.i.ya,#4.i.w_.a s.w. . _ _ _ _A.4,._.a. 4.u -.

l l :

l-s

(

I I

i ACTION PLAXS I

I i

l l

\

i

)

I 63 i i

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

In accordance with Revision 5 of NOD-QP-37, the following performance indicator: would require action plans based on three (3) consecutive months of performance 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 4th 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 November prediction of 21 core average power failures.

Maintenance Workload Backlogs (page 39)

A Work Management System improvement project is currently 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 by July 1997.

64

PERFORMANCE INDICATOR DEFINITIONS 1 i

I AUXILLARY FEEDWATER SYSTEM SAFETY SYSTEM twdget. The basis for the actual curve is the Financial and j PERFORMANCE Operahng Report The sum of the known (planned and unplanned) unavailable CLEAN CONTROLLED AREA CONTAMINATIONS E 1,000 hours0 days 0 hours 0 weeks 0 months and the eshmated unavailable hours for the au'dhary DISINTEGRATIONS / MINUTE PER PROSE AREA feedwater system for the reporting period dtvided by tre critcal hours for the reporbng period mutbphed by the The personnel contaminabon events in Ps cM-) controlled number of trains in the auxihary feedwater system. area. This indicator tracks personnel performance for SEP -

158 54, COLLECTIVE RADIATION EXPOSURE CONTAMINATED RADIATION CONTROLLED AREA Collecbve radiation exposure is the total extemal whole-body dose received by all orbsite personnel (including The percentage of the Radiahon Controlled Area, which contractors and visitors) dunng a time penod, as measured includes the auxiliary building, the radwaste building, and by the thermoluminescent dosimeter (TLD). Collective areas of the C/RP building, that is contaminated based on radiaton exposure is reported in units of person-rem. Thh the total square footage. This indicator tracks performa ice indecator tracks radiological work performance for SEP C t. for SEP #54.

COMPONENT FAILURE ANALYSIS REPORT (CFAR) DAILY THERMAL OUTPUT

SUMMARY

This indicator shows the daily Core thermal output as The summary of INPO categories for Fori Calhoun Stat on measured from computer point XC105 (in thermal with significantly higher (1,645 standard deviations) failure megawatts). The 1500 MW Tech Spec limit, and the unmet rates than the rest of the industry for an eighteerwmonth portion of the 1495 MW FCS daily goal for the reportng time penod. Failures are reported as component (Le., month are also shown.

pumps, motors, main steam stop valves, control element motors, etc.) categones. DIESEL GENERATOR REllABILITY (25 Demands)

Failure Cause Catepones are:

This indicator shows the number cf failures occumng for Age / Normal Use thought to be the consequence of each emergency diesel generator dunng the last 25 start expected wear, aging. endef hfe, or normal use , demands and the tast 25 load run demands, Manufacturing Defect a failure attributable to DISABLING INJURYllLLNESS FREQUENCY RATE inadequate assembly or intbal quality of the responsible (LOSS TIME ACCIDEN" RATE) component or system.

This indicator is defined as the number of accidents for all Engineering / Design . a failure attributable to the utihty personnel permanently assigned to the station, inadequate design of the responsible component or involving days away from work per 200.000 man-hours system. worked (100 man-years). This does not include contractor personnel. This indicator tracks personnel performance for Other Devices . a failure attnbutable to a failure or SEP #25,26 & 27.

misoperation of another mmponent or system, including associated devices. DOCUMENT REVidW(BIENNIAL)

Maintenance / Action . resulting from improper The Document Review Indicator shows the number of maintenance, lack of maintenance, or personnel errors documents reviewed, the number of documents scheduled that Occur during maintenance activibeson the for review, and the number of document reviews that are cor .ponent., overdue for the reporting month. A document review is Testing Action . resulting from improper testing or considered overdue d the review is not complete within six personnel errors that occur during testr , ectivities. months of the assigned due date. This indicator tracks initial Installation Error . caused by improper inibal performance for SEP #46.

Insta!!abon of equipment EMERGENCY AC POWER SYSTEM SAFETY SYSTEM CENTS PER KILOWATT HOUR PERFORMANCE The purpose of this indicator is to quantfy the economical The sum of the known (planned and unplanned) unavailable operation of Fort Calhoun Station. The cents per kilowatt and the estimated unavailable hoursfer the emergency AC ,

hour indicator represents the budget and actual cents per power system for the reporbng penod divided by the number kilowatt hour on a twelve-month average for the current of hours in the reporting penod multiplied by the number of year. The basis for the budget curve is the approved yearty trains % the emergency AC power system.

65

[ PERFORMANCE INDICATOR DEFINITION EMERGENCY DIESEL GENERATOR UNIT RELIABILITY ' E) A faRure to start because a portion of the starting system was disabled for test purpose, if followed by a The indicator shows the turnber of fehures that were reported dunng successful start with the startng system in its normal the lost 20, So, and 100 errorgency desel generator dernenos at the alignment.

Fort Calhoun Station. Also stown are ingger values whch corretate Each emergency generator failure that results in the to a high loved of confidence that a units desel generators hen generator being dedared inoperable should be counted as '

obtened a redet>tity of yester than or aquel to 95% when ee dernand one demand and one failure. Exploratory tests during taaures are less than the trigger values. Corrective maintenance and the successful tesi that follows repair to verify operabihty should not be counted as

1) Number of Start Demands: AH valid and inadvertent demands or failures when the EDG has not been dedared -

start demandt., including au start +nly demands and all operab6e agairL start demands that are followed by lea &run demands, whether by outomabC or manualinitiabon. A start only EMERGENCY DIESEL GENERATOR UNRELIABILITY demand is a dsmand in which the emergency Generator is started, but no attempt is made to load the TNs indicator measures the total unreliability of emergency generator, diesel generators. In general, unrelialliity is the rabo of unsuccessful operabons (starts or loaGruns) to the number

2) Number of Start Failures:Any failure within the of valid demands. Total unreliability is a combination of start emergency generator system that prevents the unrehabihty and loa &run unreliability, generator from acNeving specified frequency and voltage is classified as a valid start failure. TNs ENGINEERING ASSISTANCE REQUEST (EAR) indudes any condibon identified in the course of BREAKDOWN maintenance inspections (with the emergency Generator in standby mode) that definitely would have This indicator shows a breakdown, by age and priority of the resulted in a start failure if a demand had occurred. EAR, of the number of EARS assigned to Design Engineering Nudear ar"i System Engineering. TNs Indicator tracks performance for SEP #62.

3) Number of Load-Run Demands: For a vahd loa &run demand to be counted, the load 4un attempt must meet one or more of the following criteria: ENGINEERING CHANGE NOTICE (ECN) STATUS A) A loaGrun of any durabon that results from a real The number of ECNs that were opened. ECNs that were automabc or manualinibabon. completed, and open bacidog ECNs awaiting completion by DEN for the reportng month. This indicator tracks D) A load-run test to sabsfy the plant's load and perfomiance for SEP #62, durabon as s;ated in each test's specifications.

ENGINEERING CHANGE NOTICES OPEN C) Other spedal tests in wNch the emergency generator is expected to be operated for at least This indicator breaks down the number of Engineering one hour while loaded with at least 50% of its Change Notices (ECNs) that are assigned to Design design load. Engineering Nudear (DEN), System Er'gineering, and Maintenance The graphs provide data on ECN Facihty Changes open, ECN Subst tute Replacement items open,

4) Number of Load Run Failures: A loa &run failure should be counted for any reason in which the and ECN Document Changes open. This indicator tracks emergency generator does not pick up load and run es performance for SEP #62.

predicted, Failures are counted during any valid load-run demands. EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS

5) Exceptions: Unsuccessful attempts to start or loa $

run should not be counted as vahd demands or failures Equipment forced outages per 1,000 critical hours is the when they can be attributed to any of the following: inverse of the mean time between forced outages caused by equipment failures. The mean bme is equal to the number A) - Spunous tnps that would be bypassed in the event of hours the reactor is enbcal in a penod (1,000 hours0 days 0 hours 0 weeks 0 months ) of an emergency. divided by the number of forced outages caused by equipment fa;:ures in that period.

8) Malfunction of equipment that is not required during an emergency. EQUIVALENT AVAILABILITY Ft.CTOR C) Intentional termination of a test because of This ludicator is defined as the ratio of gross available abnormal condibons that would not have resulted generation to gross maximum generation, expressed as a in major diesel generator damage or repair, percentage. Available generation is the energy that can be produced if the unit is operated at the maximum power level D) Malfuncbons or operating errors which would not per nitted by equipment and reputatory limitations, -

have prevented the eme gency generator from Maximum generation is the energy that can be produced by being restarted and brought to load within a few a unit in a given pened if operated conhnuously at maximum I minutes. capadty.

66 ,

e PERFORMANCE INDICATOR DEFINITIONS FORCED OUTAGE RATE 2) One or more days away from work (excluding the day of the ar.cident); and This indicator is defined as the percentage of time that the 3) Fatallbes.

unit was unavallatne due to forced events compared to the time planned for electrical generaton. Forced everta are Contractor personnel are not included for this indicator, failures or other unplanned conditions that require remeving the unit from service tefore the end of the next weekend. IN LINE CHEMISTRY INSTRUMENTS OUT OF SERVICE Forced events include start up failures and events initiated while the unit is in reserve shutdown (i.e., the unit is Total number of in-line semistry instruments that are out of-service in the Secondary System and the Post Accident avaltable but not in service).

Samphng System (PASS).

FUEL RELIABILITY INDICATOR LICENSE CANDIDATE EXAMS This indicator is defined as the steady state pnmary coolant 1-131 acbvity, corrected for the tramp uranium contnbut on This indicator shows the number of SRO and/or RO quizzes and normaltzed to a common punAcabon rate. Tramp and exams that are administered and passed each month.

uranium is fuel which has been deposited on reactor core This indicator tracks training performance for SEP #68.

intamals from previous defechve fuel or is present on the surface ni fuel elements from the manufactunng process. LICENSED OPERATOR REQUALIFICATION TRAINING Steady state (5 defined as continuous opers,bm for at least three days at a power level that does not vary more than + The total nurnber of hours of training given to each crew or -5%, Plants should collect data for this indicator at a during each cycle. Also prcmded are the simulator training power level above 85%, when possible. Plants that did not hours (which are a subset of the total trainmg hou's), the number of non-REQUALIFICATION training hours and the operate at steady-state power above 85% should collect data for this indicator at the highest steady. state power 6al number of exam failures. This indicator tracks training attamed during the month, performance for SEP # 68.

The density correcbon factor is the ratio of the specific LICENSEE EVENT REPORT (LER) ROOT CAUSE volume of coolant at the RCS operating temperature (540 BREAKDOWN degrees F.,Vf = 0.0217) divided by the specAc volume of coolant at normal letdown temperature (120' F at outlet of This indicator shows the number and root cause code for the letdown coohng heat exchanger, Vf = 0.0163), which Licensee Event Reports. The rcot cause codes are as results in a density correction factor for FCS equal to 1.33. follows:

GROSS HEAT RATE 1) Administrative Control Problem . Management and supervisory deficiencies that affect plant programs or Gross heat rate is denned as the rabo of total thermal activities (i.e., poor planning, breakdown or lack of snergy in British Thermal Units (BTU) produced by the adequate management or supervisory control, incorrect reactor to the total gross electrical energy praduced by the procedures, etc).

generator in kilowatt-hours (KWH).

2) Licensed Operator Error This cause code captures HAZARDOUS WASTE PRODUCED errors of omission / commission by licensed reactor operators during plant activities.

The total amount (in Kilograms) of non-halogenated ha ardous maste, halogenated hazarcous waste, and other 3) OtherPersonnelError Errorsof hazardou waste produced by FCS each month. omission / commission committed by non-licensed personnel involved in plant activities.

HIGH PRESSURE SAFETY INJECTION SYSTEM *.VaTY SY3 TEM PERFORMANCE 4) Maintenance Problem The intent of this cause code is to capture the full range of problems which can be The sum of the known (planned and unplanned) unavailable attributed in any way to programmatic deficiencies in hours and the estimated unavailable hours for the higti- the rnaintenance functional orgenl2ation. Activities pressure safety injechon system *or the reporting penoi included in this category are maintenance, tesbng, divided by the enticol hours for the reporbng period surveillance, calibrabon and radiaton protection.

muttphed by the number of trains in the high pressort safety injection system. 5) Design / Construction / installation / Fabrication Problem This cause code covers a full range of INDUSTRIAL SAFETY ACCIDENT RATE -INPO programmatic I

This indicator is defined as the number of accidents per 200.000 man hours worked for all utility personnel (

permarently assigned to the station that result in any of the following.

1) One or more days of restr'cted work (excluding the day of the 3th nt);

67

4

PERFORMANCE INDICATOR DEFINITIONS deficiencies in the areas of design, constructon, This ind cator tracks maintenance performance for SEP installshon. and fabricabon (i.e., loss of control power due to #30.MA)lMUM INDIVIDUAL RADIATION EXPOSURE underrated fuse, equipment not quahfied for the ..

environment. etc,). The total 'naximum amount of radiaton received by an Indnidua' person -

6) Equipment Failures (Electronic Piece-Parts or ENironmental Related Failures) . This code is used working al FCS on a monthly, quart?y, and annual basis, for spurious failures of electronic piece-parts and failures due to meteorological conditions such as MWD PLANNING STATUS (CYCLE 17 REFUELING lightning, loe, high winds, etc. GeneraDy, it includes OUTAGE) spurious or one bme tailures. Electric components induded in this category are circuit cards, rectifiers, The total number of Maintenance Work Documents that bistables, fuses, capadtors, diodes, resistors, etc. have been approved for inclusion in the Cycle 17 Refuehng Outage and tne number that are ready to wark (parts LOGG ABLEntEPORTABLE INCIDENTS (SECURITY) staged, planning complete, and all other paperwork ready for field use). Also included is the number of MWDs that The total number of security inddents for the reporbng have been engineering holds (ECNs, procedures and other month depicted in two graphs. This indicator tracks security miseenaneous engineenng holds). parts hold, (parts staged, performance for SEP #58, not yet inspected, parts not yet arrived) and planning hold (Job scope not yet completed). Maintenance Work Requests MANTENANCE OVERTIME iMWRs) are also shown that have been idenbfied for the wule 17 Refueling Outage and have nt4 yet been converted The percent of overbme hours compared to normal hours for to MWOs.

maintenance. This includes OPPD personnel as well as contract personnel. NUMBER OF CONTROL ROOM EQ'llPMENT DEFICIENCIES MAINTENANCE WORKLOAD BACKLOGS A control roorn equipment deficiency (CRD)is defined as This indicator shows the backlog of non-outage any component which is operated or controlled from the Maintenance Work Orders remaining open at the end of the Control Room, provides indication or alarm to the Control reporung rnonth. Maintenance classifications are defined as Room, provides testing capabilibes from the Control Room, follows: provides automatic acbons from or to the Control Room, or provides a passive funcbon for the Control Room and has Cocrective - Repair and restorauon of equipment or been identfied as deficient,1 e., does not perform under all components that have failed or are malfunctioning and condibons as desigr# This definiton also applies to the are not performing their intended function. Altemate Shutdown Panels Al-179, Al.185, and Al-212.

Preventive Acbons taken to maintain a piece of A plant component which is de6cient or inoperable is equipment within design operating conditions, prevent considered an " Operator Work Around (OWA) ltem* If some equipment failure, and extend its life and are performed other acbon is required by an operator to compensate for the pnor tc, equipment failure. condibon of the component. Some examples of OWAs are:

Non-Corrective / Plant improvements . Maintenance 1) The control room levelindicator does not work but a activities performed to implement station improvements or local sight glass can be read by an Operator out in the to repair non-plant equipment. - plant; Maintenance Work Priorities are defined as: 2) A deficient pump cannot be repaired because replacement parts require a long leM Ume for Emergency Conditons which significantly degrade purchase / delivery, thus requinng the redundant pump stabon safety or availabihty. to be operated continuously; immediate Action Equipment deficiencies which 3) Special actons are required by an Operator becauso of sigruficantly degrade station reliability, Potential for unit equipment design protams. These actions may be shutdown or power reduchon. described in Operations Memorandums, Opeiator Notes, or may require changes to Operating l Operations Concern . Equipment deficiencies which Procedures; hinden stabon operaton.

4) Deficient plant equipment that is required to be used Essential . Routine correchve ma'r* ens ce on essential dunng Emergency Operatng Procedures or Abnormal station systems and equipment. Operabng Procedures; e

Non-Essential Roubne corrective maintenance on non- 5) System indication that provides enbcal information -

essenbal stabon systems and equipment. during normal or abnormal operations Plant improvamont - NorH:orrecbve maintenance and plant improvements.

68

PERFORMANCE INDICATOR DEFINITIONS NUMBER OF MISSED SURVEILLANCE TESTS PERCENTAGE OF TOTAL MWDs COMPLETED PER RESULTlNG IN LICENSEE EVENT REPOR? S MONTH IDENTIFIED AS REWORK The number of Surveillance Tests (STs) that result in The percentage of 10tal MWDs completed per month Licensee Event Reports (LERs) during the reportng month, identified as rework. Rework actWibes are identif:ed by maintenance planning and craft Rework is: Any additional This mdicator tracks missed STs for SEP #60 & 61.

OPEN INCIDENT REPORTS work required to correct deficiencies discovered during a failed Post Mainten.,W Test to ensure the TNs indicatrv displays the total number of open incuent component / system passes sutnequent Post Maintenance Reports (IR$), the number of irs that are greater than six Test.

months old and the Dumber of open significant irs.

PERCENT OF COMPLETED SCHEDULED OUTSTANDING MOOlFICATIONS MAINTENANCE ACTIVITIES The number of ModMcahon Requests (MRs)in any state The percent of the number of completed maintenance acbvities as compared to the number of scheduled between the issuance of a ModMcation Number and the complebon of the drawing update, maintenance actvibes each month. This percentage is shown for all maintenance crafts. Also shown are the

1) Form FC 1133 Backlog /In Progress. This number number of emergent MWDs Maintenance activibes include represents modification requests that have not been MWRs, MWDs, STs, PMOs, calibrabons, and other plant approved during the reporting rnonth, miscellaneous activibes. This indicator tracks Maintenance performance for SEP #33.

2) Modif 'ation Requests Being Reviewed. This category includes: PERFORMANCE INDICATOR INDEX A) Modificabon Requests that are not yet reviewed. This indicator index is calculated from a wethted combMahon of eleven performance indicator values, which B) Modification Requests being reviewed by the indude the following: Unit Capability Factor, Unit Capabihty Loss Factor, HPSI, AFW, Emergency AC Power System, Nuclear Protects Review Committee (NPRC).

Unplanned Automatic Scrams, Collective Radiation C) Modification Regi .ats being reviewe't by the Exposure, Fuel Reliability, Thermal Performance, Secondary Nudear Projects Committee (NPC). System Chemistry, and industrial Safety Accident Rate.

These Modificabon Requests may be reviewed several PREVENTABLE / PERSONNEL ERROR LERs times before they are approved for acwidement or canceled. Some of these Modification Requests are This indicator is a breakdown of LERs. For purposes of reumed to Engineering for more informahon, some LER event classification, a

Preventable LER* Is defined as:

approved for evaluabon, some approved for study, and some approved for planning. Once planning is completed An event for which the root cause is personnel error (i.e.,

and the scope of the work is dearly defined, these inappropriate action by one or more individuals).

Modification Requests may be approved for accomplishment inadequate administrabve controls, a design construchon, with a year assigned for construebon or they may be insta!!abon, it'stattation, fabricaton problem (involving canceled. All of these different phases require review. work completed by or supervised by OPPD personnel) or a maintenance problem (attributed to inadequate or

3) Design Engineering Backlog /in Prog ess. Nudear improper upkeep / repair of plant equipment). Also, the Planning has assigned a year in which construchon will cause of the event must have occurred within be completed and design work may be in progress, approximately two years of the " Event Date" specified in the LER (e.g., an event for which the cause is attributed

4) Construction Backlog /In Progreat The Construction to a problem with the oriwinal design of the plant would Package has been issued or constructon has begun not be considered preventable).

but the modi 5 cation has not been accepted by the System Acceptance Committee (SAC). For purposes of LER event classification, a

Personnel Error

LER is defined as follows:

5) Design Engineering Update Backlog /in Progress.

PED has recebed the Modificabon Complebon Report An evet,t for which the root cause is inappropriate acton but tne drawings have not been updated.The above on the part of one or more individuals (as opposed to mentioned outstanding modifications do not indude being attnbuted to a department or a general group).

modificabons which are proposed for canceliabon. A!so, the inappropriate achon must have occurred within approximately two years of the " Event Date" specified in OVERALL PROJECT STATUS (REFUELINO OUTAGE) the LER. .

This indicator shows the Status of the projects which are in the scope of the Refueling Outage. )

I L 69 ;

1

~

. PERFORMANCE INDICATOR DEFINITIONS Additionally, each event dassified as a ' Personnel Error" SAFETY SYSTEM FAILURES should also be dassified as " Preventable.' This indicator trends personnel performance for SEP ltem #15. Safety system failur .s are any events or conditions that could prevent the fulfillment of the safety functicas of PRIMARY SYSTEM LITHlUM % OF HOURS OUT OF structures or systems, if a system cons:sts of multiple LIMIT redundant subsystems or trains, failure of all trains const~tutes a safety system failure. Failure of one of two or The percent of hours out of hmit are for lithium divided by more

rains is not counted as a safety system failure. The the total number of hours posChie for the month. definition for the indicator parallsz NRC reporting requirements in 10 CFR 60.72 and 10 CFR 50.73. The PROCEDURAL NONCOMPLLANCE INCIDENTS following is a list of the major safety systems, sub-systems, (MAINTENANCE) and components monitored for this indicator:

The nurnber of idenbfied incidents conceming maintenance Acddect Monitonng Irctrumentation, Auxlhary (and procedural problems, the number of dosed irs related to Dnergency) Feedwater System, Combustible Gas the use of procedures (indudes the number of dosed irs Control, Component Coohng Water System, Containtnent caused by procedural noncomnliance), and the number of and Containment isolabon, Containment Coolant closed procedural noncompliance ds. This indicator trends Systems, Contrei Room Emergency Ventilation System, personnel performance for $dP #15,41 and 44 Emergency Core Cooling Systems. Engineered Safety Features instrumentabon, Essenbat Compressed Air PROGRESS OF CYCLE 17 OUTAGE MODIFICATION Systems, Essenbal or Emergency St vice Water, Fire PLANNING Detection or Suppression System., Isolation Condenser, Low Torrperature Overpressure Protechon, Main Steam This indicator shows the status of modifications approved for Line Isolation Valves Onsite Emergency AC & DC Power complebon dunng the Refueling Outage. w/ Distribution, Radiaton Monitoring instrumentation, Reactcr Coolant System, Reactor Core isolabon Coohng PROGRESS OF 1995 ON LINE MODIFICAh0N System, Reactor Trip Eystem and instrumentation, PLANNING Recirculation Pump Trip Actuation Instrumentabon, Residua! Heat Removal Systems, Safety Valves, Spent This indicator shows the status of modifications app t ved for Fuel Systems, Standby Liquid Control System and complebon during 1995. Ultimate Heat Sink.

RADIOLOGICAL WORK PRACTICES PROGRAM SECONDARY SYSTEM CHEMISTRY PERFORMANCE INDEX The number of identfied poor radiological work practices (PRWPs) for the reporbng month. T' is indicator tracks The Chemistry Performance Index (CPI) is a calculabon radiological work performance for StiP #52. based on the concentration of key impurities in the secondary side of the plant. These key impuribes are the RATIO OF PREVENTIVE TO TOTAL MAINTENANCE & most hkely cause of detenorabon of the steam generators.

PREVENTIVE MAINTENANCE ITEMS OVERDUE Criteria for calculahng the CPI are:

The tr.tio of prevenhve maintenance (induding surveillance 1) The plant is at greater than 30 percent power; and tesbng and cahbration procedures) to tne sum of non outage correctrve maintenance and preventive maintenance 2) the power is changing less than 5% per day.

completed over the reporbng period. The rabo, expressed as a percentage,is calculated based on man-hours. Also The CPI is calculated using the following equation:

displayed are the perc3nt of prevenhve maintenance items in the month that were not completed or administratively CPI = ((sodium /0.79) + (Chloride /1.52) + (Sulfate!1.44) +

closed by the scheduled date plus a grace pennd equal to (Iron /3.30) + (Copper /0.30)+(Condensate 02/2.90))/6 25% uf the scheduled interval. This indicator tracks preventive maintenance acovities for SEP #41. Where: Sodium, sulfats, chlonde and condensate dissolved oxygen are the monthly average blowdown concentrations ItECORDABLE INJURYllLLNESS CASES FREQUENCY in ppbjren and cooper are monthly time weighted average RATE feedwater concentrabons in ppb. The denominator for each of the five factors is the INPO median value, if the monthly The number of injunes requiring rnore than normal first aid average for a specific parameter is less than the INPO per 200,000 man-hours worked. This indicator trends median value, the median value is used in the calculation.

personnet performance for SEP #15,25 and 26.

REPEAT FAILURES -

The number of Nudear Plant Reliability Data Syster e (NPRDS) components with more than one failure and the .

number of NPRDS components with more than two failures for the -

eighteen month CFAR penod.

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PERFORMANCE INDICATOR DEFINITIONS .

SDNIFsCANT EVENTS 2) Jumpers and tdods whim are instahed for Surveillance Tests, Maintenance Procedures, Cabbrabon P.ocedures, Signehcent events see the events 6dentifed by NRC staff Special Procedures or Operahng Procedures are not through deta6 led screening and evaluabon of operahng considered as temporay modtftcabons unless the experenos. The screening process induces the daity jumper (a idock remains in place after the test of review and discussion of all reported operabng reactor procedure is complete. Jt.mpers sad bb,13 instabed in events, as well as other opersbonal data sus as spedal test or lab instruments are not considerrsd at temporary tests or construction actwites. An event ident:fied from the modifications.

$creerung process as a significant event candidate is further evaluated to determine if any actual or potential threat to the 3) Scaffold is not considered a temporary modif cabon.

health and safety of the public was involved. Specific Jumpers and blods Wch are installed and for which examples of the type of criteria are summartzed as follows: MRs have been submitted wdl be considered as

1) Degradabon of important safety equipment; temporary modificabons until final resolution of the MR and the jumper or tdock is removed or is permanently

2) Unexpected plant respon6e to a transient, recorded on the drawings This indicalv trscks temporary moefications for SEP #62 and 71.

3) Degradabon of fact integy, pnmary otr. dant pressure boundary,important ssociated features: THERMAL PERFORMANCE

4) Summ with complicabon, The rabo of the design gross heat rate (corrected) to the adl usted actual gross heat rate, expressed as a percentage.

6) Unplanned reteese of radioactMty:

UNIT CAPASILITY FACTOR

6) Operabon outside the lirrdts of the Te&n6cet Specificebons; The ratio of the avaltable energy genersbon over a given time penod to the reference energy genersbon (the energy

7) Other, that could be produced if the unit were operated ,

conhnuously at full power under reference ambient INPO significant events reported in this indecator are SERs condibor s) over the same time penod, expressed as a (Significant Event Reports) which inform utikbes of percentage.

sigrubcant events and lessons leamed identified through the SEE tN screensng process. UNIT CAPACITY F ACTOR SPARE PARTS INVENTORY VALUE The net electrical energy generated (MWH) divided by the product of maximum dependable capacity (net MWe) bmes The dollar value of the spare parts inventory for FCS during the gross hours in the reporting penod wpressed as a the reporting penod. percent. Net electrical energy generated is the gross electncal output of the unit enessured at the output terminals STAFFING LEVEL of the turtaine generator minus the normal station serv 6ce loads dunng the gross hours of the fupotting penod, The actual st-ffing level and the authortred staff ng level for expressed in megawatt hours.

the Nuclear C , era'.,ons Division, The Production Eagineenng Divis6on, and the Nuclear Servkes Dwision. UNPLANNED AUTOMATIC REACTOR SCRAMS PER This indecator tracks performance for SEP #24. 7,000 CRfTICAL HOURS STATICH NET GENERATION This indicator is defined as the number of unplanned automabc scrams (RPS log'c actuations) that occur per The net genersbon (sum) produced by the FCS during the 7,000 hours0 days 0 hours 0 weeks 0 months of cnbcal operation.

reporting rnonth.

The value for this indicator is calculated by mult plying the TEMPORARY HN)lFICATIONS total number of unplanned automatic reactor scrams in a specific time period by 7,000 hours0 days 0 hours 0 weeks 0 months , then dividing that The numttr of temporary mechanical and electncal number by the total number of hours criticalin the same conhgurabons to the plaits systems, bme penod. The Indicator is further defincJ as follows:

1) Temporary confeptsbons are dehned as electncal 1) Unplanned means that the scram was not an anticipated jnper), electrical blocks, mechancal jumpers, or part of a planned test.

mechanical blocks which are installed in the plant operating systems and are not shown on the latest 2) Scram means the automatic shutdown of the reactor by I revtsbon of the P&lD, seemabc, connection, winng, or - a rapid insertion of negatwo reactivity (e g., by control flow diagrams. rods, hquid 6ryechon system, etc ) that is caused by 4:tuabon of the reactor protechon system. The signal .

may have resutted from exceeding a set point or spunous.

I-I l

71

?

e PERFORMANCE INDICATOR DEFINITIONS

3) Aut9rnate rneans tnai the erubal signal that caused VIOLATION TREND actuabon of the reactor protection system kryc was provided from trie of the sensor's monikring plant This indicator as defined as Fort Cat wn Stabon Cited pararreters and cond6 bons, rather than the manual Violatas and Non-Cited %otabons trended over 12 months scram swild1s or, rnanual turtune inp switches (or Ad$bonally, Cited Violations for the top Quartde Region IV push buttons)(vovided in he main control room, plant la trended over 12 months (lagging the Fort Calhoun Station trend by 2 3 months) 1:is the Fort Calhoun Station

4) Cnbcal means that dunng the steady-state con $tm of goal to be at or tetow the cited violabon trend for the top the reactor pnor to the scram, the effecbve rnuttiphcabon guartde Region IV plant (k ) was essenbalay equal to one.

UNPLANNED CAPABILITY LOSS FACTOR VOLUME OF LOW LEVEL SOLID RADIOACTIVE WASTE The rabo of the unplanned ericrgy losses dunng a given TNs in$cator is defir+d as the volume of low-level solid perxrj of time, to the reference energy generabon (the radioactive waste actually shipped for bunal. This in$cator energy that could be twoduced if the unit were operaled also t. hows the volume of low level ra$oactive waste wtuch conbnuousiy at full power under reference amtnent is in temporary storage, the amount of ra$oactNe Ml that con $tions) over the same time per6od, expressed as a has been shipped off site for processing, and the volume of percentage. sohd dry raWoachve waste wNch has been shipped o% site for processing Low-level sohd ra$oactive warste consists of UNPLANNED SAFETY SYSTEM ACTUATIONS.(INPO dry active weste, sludges, resins, and evaporator bottoms

DEFINITION) generated as a resuP of nuclear power plant opersbon and maintenance. Dry ra$oactive waste includes contaminated Tties indicator is defined as the sum of the following safety rags, cleaning matenals, disposable protectsve cloth 6ng, system actuabons: plasbc containers, and any ot5er material to be disposed of at a lowdevel fa$oactive este disposal site, eacept resin,

1) The number of unplanned Emergency Core Cooling sludge. or evaporator bottoms Low 4evel refers to all System (ECCS) actualms that result from reaching an radioactise waste that is not spent fuel or a by product of ECCS actuation set point or from a spunout' inadvertent spent fuel processing This indicator tracts radiological ECCS signal. work performance for SEP e54.

2) The number of unplanned emergency AC power system actuateons that resutt from a loss of power to a safeguards bus An unplanned safety system actualon occurs when an actuation set point for a safety system is reached or when a spunous or inadvertent signalis generated (ECCS only), and major equiptrent in the system as actuated Unplanned treans that the system actuabon was not part of a planned test or evolubon.

The CCCS actuabons to t e counted are actuabons of the high pressure injection system, the low pressure injecta system, or the safety injechon tanks.

UNPLANNED SAF ETY SYSTEM ACTUATIONS .(NRC DEFINITION)

The number of safety :ystem actuabons which 6nclude (on!y) the High Pressure Safety Iryecton System, the Low Pressure Safety trgect.on System, the Safety injecton Tanks, and the Emergency Diesel Generators. The NRC classificahon of safety syster.i actuabons incledes nctuations when major eautpment is operated ILrid when the logic systems for thJ above safety systems are challenged.

72

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SAFETY ENHANCEMENT PROERAM INDEX The purpose of the Safety Enhancement Program (SEP) Performance Indicators index is to list performance indicators related to SEP .4ems with parameters that can be trended.

P_ age SEE.Reittence Numbit.15 e increase HPES and IR Accountability through use of Performance Indicators .

Procedural Noncomphance incidents (Maintenance) ...... .................... ..... . 43 Recordable injury / Illness Cases Frequency Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 Clean Controlled Area Contaminations 11,000 Disintegrations / Minute Per Probe Area . . . . . . . . . 17 Preventable / Personnel Error LERs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........... . 18 SEP_IMittence3nmhmial5Jtfd21

. 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_ReitianctEumheL3.1

Develop Outage and Malntenance Planning Manual and Conduct Project Management Training MWO Planning Status (Cycle 17 Refueling Outage) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 SSED's Overall Project Status . . . . . . . . . . . . . . . . . . . . . . .............................. 60 Overall Project Status (Cycle 17 Refueling Outage) ..................... .............. 61 Progress of Cycle 17 Outage Modification Planning . . . . . . . . . . . . . . . . . . ........... .. 63 SEP_Befrience NumbgL33

Develop On Line Maintenance and Modification Schedule 1996 On-line Modification Planning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....... . 62 EEP_RefstencnEumhar_3S

. Reduce Corrective Non Outage Backlog Maintenance Workload Backlogs (Corrective Non Outage) ............... . ... ..... 39 SEP BeierenceEumbers 41 & 44

. Develop and implement a Preventive Maintenance Schedule

. Compliance With and Use of Procedures Ratio of Preventive to Total Maintenance & Preventive Maintenance items Overdue . . . . . . . . . . . . 40 Procedural Noncompliance incidents (Maintenance) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , 43 EEP_BtitirnanEumber 46 Design a Procedures Control and Administrative Program

Document Review . . . , , . . . . . . . . . . . . . . . . . . . . . ...... . . .

. ............ ., ,, . 48 73 i

SAFETY ENHANCEMENT PROGRAM INDEX BEP_Belaffnct_Nufnktfl2 EAgt

Establish Supervisory Accountability for Workers Radiological Practices Radiological Work Practices Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 BEP Raffrance Number 54

+ Complete implementation of Radiological Enhancement Program Clean Controlled Area Disintegrations 21.000 Counts / Minute Per Probe Area . . . . . . . . . . . . . . . . . 17 Collective R ediation Exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 Volume of Low-Level Solid Radioactive Weste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 Contaminated Radiation Controlled Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 SEP Refstence_Numbsta6 e Revise Physical Security Training and Procedure Program Loggable/ Reportable incidents (Security) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49 BEP_ Reference Nurnbata_60 a 61 e improve Controls Over Surveillance Test Program

. Modify Computer Program to Correctly Schedule Surveillance Tests Number of Missed Surveillance Tests tesulting in Licensee Event Reports .................. 23 SEP_Referance _Numbet$2

. Establish Interim System Engineers Tempor ary Modifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 Engineering Assistanco Request (EAR) Breakdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 Er gineering Change Notice Status ............ ...... ..... ..... . ......... ..... 53 Engineering Change Notices Open . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54 EEP Refersnce MumbtL6A

+ Assess Root Cause of Poor Operator Training and establish means to monitor Operator Training License Operator Requalification Training ........ ............ ...... . .............. 56 Licens e C andidate Exams . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 SEP ReferenGt.Numberli e improve Controls over Temporary Modifications Temporary Modifications . . . . . . . . . . . . . . . . . . . . . . .................................. 50 74

REPORT DISTRIBUTION LIST R. L. Andrews J. B. Kuhr (9 Copies)

K. L. Belek L. T.Kusek G.C. Bbhop C. J. Linden (10 Coples)

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. Phelps S. K. Gambhir R. L. Plott J. K. Gasper W. J. Ponec W. G. Gates D. G. Ried S. W. Gebers M. J. Sandhoefner M. J. Guinn F. C. Scofield R. H. Guy H. J. Sefick A. L. Hale R. W. Short B. R. Hansher J. L. Skiles K. R. Henry R. D. Spies (2 Coples)

J. B. Herman K. E. Steele R. P. Hodgson D. E. Spires C.K. Huang M. A. Tesar J. K, Kellams J. J. Tesarek R. L. Jaworski J. W. Tills J. W. Johnson D. R. Trausch D.D. Kloock L. P. Walling G. R. Williams 75 I

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ML20198A573

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SUMMARY

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