Text

Performance Indicators Rept, Apr 1997
	ML20141M015
Person / Time
Site:	Fort Calhoun
Issue date:	04/30/1997
From:	; OMAHA PUBLIC POWER DISTRICT
To:	;
Shared Package
ML20141M012	List: LIC-97-0092, Forwards Fort Calhoun Station Performance Indicators Rept, for Apr 1997; ML20141M015;
References
	NUDOCS 9706040132
	Download: ML20141M015 (90)
	v • d • e

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FORT CALHOUN STATION PERFORMANCE INDICATORS

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APRIL 1997 SAFE OPERATIONS PERFORMANCE EXCELLENCE COST EFFECTIVENESS I

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OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION i

PERFORMANCE INDICATORS REPORT

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APR L 4

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1997 i

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Engineering and Operations Support Division i

NuclearLicensing i

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i FORT CALHOUN STATION APRIL 1997 Monthly Operating Report l

OPERATIONS

SUMMARY

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The Fort Calhoun Station (FCS) operated at a nominal 100% power level until April 21,1997 at 2023 hours0.0234 days 0.562 hours 0.00334 weeks 7.697515e-4 months when the reactor was manually tripped by the Control Room operators. The trip was prompted by a loud noise emanating from the Turbine Building and the sight of large amounts of steam in the turbine building. At 2045 hours0.0237 days 0.568 hours 0.00338 weeks 7.781225e-4 months a Notification of Unusual Event (NOUE) was declared and the Emergency 3

Response Organization (ERO) was activated. Notifications to Offsite agencies were completed per station procedures. A subsequent investigation revealed that an extraction steam line, which supplied the #5 Feedwater Heaters from the High 4

Pressure Turbine fourth stage, had ruptured. Damage occu, red to Motor Control Centers (MCC) in the area and piping insulation around the rupture.

The determination was made to proceed to Cold Shutdown to repair the damaged equipment and perform other previously identified maintenance. The NOUE was exited and ERO secured at 2345 hours0.0271 days 0.651 hours 0.00388 weeks 8.922725e-4 months on April 21.

The plant remains in Cold Shutdown at this time. Repairs to the Extraction Steam piping and other equipment continue.

On April 26,1997 at 1653 hours0.0191 days 0.459 hours 0.00273 weeks 6.289665e-4 months a NOUE was reported for heightened plant staff awareness due to a leak in the Component Cooling Water (CCW) System. The leak was attributed to a rubber seated isolation valve which leaked during maintenance

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work on a portion of the Waste Disposal System that was being abandoned. The leak was promptly secured.

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d Fort Calhoun Index Value

industry Median index Value 9614 Industry Median was 85%

97/1 OPPD Value was 85.24%

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1 Value for April 1997 was 87A%

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i 40 95/1 95/2 95/3 95/4 96/1 96/2 96/3 96/4 97/1 Apr May June e

PERFORMANCE INDEX TREND The performance index trend calculation is made up of eleven variables each weighted to arrive at an overall index value. The thermal performance, secondary system chemistry, and industrial safety accident rate values are calculated for a one-year period. Fuel reliability is calculated on a quarterly basis. The remaining values (unit capability factor, unplanned (unit) capability loss factor, unplanned automatic scrams per 7000 hours0.081 days 1.944 hours 0.0116 weeks 0.00266 months critical, safety system performance, and collective radiation exposure) are calculated for a two-year period. This method allows the index trend to be more responsive to changes in plant performance.

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

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UCF UCLF FPSI AFW EACP CRE uAS7 FRI CR TH ISAR 1

l This graph shows the difference between the Maximum No. of points for each WANO indicator and the actual value achieved by Fort Calhoun. The current graph shows the difference between March '97 and April '97.

t UCF Unit Capabiity Factor TPI Thermal Performance Indicator t

UCLF Unplanned Capability Loss Factor CPI Secondary Chemistry Indicator HPSI High Pressure Safety injection ISAR Industrial Safety Accident Rate AFW Auxiliary Feedwater I

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

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i FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT April 1997-

SUMMARY

1 POSITIVE TREND REPORT (Page 39)

End of Adverse Trend Report.

A performance indicator with data representing three consecutive months of improving performance or three INDICATORS NEEDING INCREASED l

consecutive months of performance that is superior to MANAGEMENT ATTENTION REPORT the stated goalis exhibiting a positive trend per Nuclear Operations Division Quality Procedure 37 (NOD-QP-A performance indicator with data for the reporting j

37).

penod that is inadequate when compared to the OPPD i

goal is defined as "Needing increased Management The following performance indicators exhibited positive Attention" per Nuclear Operations Division Quality J

trends for the reporting month:

Procedure 37 (NOD-QP-37).

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Hioh Pressure Safety iniection System Safety System Unit Canabilrty Factor Performance (Page 2)

(Page 5)

Unolanned Caesbility Lcas Factor i

Emeroency A.C Power System (Page 3)

(Page 7)

I Auxiliary Feedwater System j

Secondarv Chemistry (Page 6)

(Page 10)

Fuel Reliability in,dgg Safety System Failures (pag, g)

(Page ig) a Forced Outaae Rate Hazardous Waste Produced (Page 26)

(Page 45) i Capy;&g, Unit of Factor Contaminated Radiation Controlled Area 27) 1 i

(Page 46)

Eaulvalent Availability Factor End of Positive Trend Report.

(Page 28)

ADVERSE TREND REPORT Gross Heat Rate l

(Page 31)

A performance indicator with data representing three consecutive months of declining performance or three Eculoment Forced Outaoes e

consecutive months of performance that is trending (Page 33) toward declining as determined by the Manager -

1 Nuclear Licensing, constitutes an adverse trend per Ratio Of Preventive To Total Maintenance Nuclear Operations Division Quality Procedure 37 (Page 40)

(NOD-QP-37).

A supervisor whose performance indicator exhibits an adverse trend by this definition Document Review may specify in written form (to be published in this (Page 48) report) why the trend is not adverse.

i Temocrary Modifications 2

The following performance indicators exhibited adverse (Page 50) trends for the reporting month:

Maintenance Workload Backloos s

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WANO INDICATORS i

(As compared to previous month) j Unit Capability Factor increasing l

Unplanned Capability Loss Factor increasing i

High Pressure Safety injection No Change l

Aux. Feedwater System No Change Emergency AC Power Decreasing Collective Radiation Exposure increasing 4

Unplanned Automatic Reactor Scrams No Change l

Fuel Reliability Decreasing Chemistry indicator increasing l

Thermal Performance No Change l

Industrial Safety Accident Rate No Change i

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Table of Contents / Summary eaah GOALS..

............ xil WANO PERFORMANCE INDICATORS Unit Capability Factor.................

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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.....

8 Fuel Reliability indicator......

9 Secondary System Chemistry.

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

11 Volume of low level Radioactive Waste...

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industrial Safety Accident Rate.......

13 SAFE OPERATIONS l

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

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

16 Clean Controlled Area Contaminations 31,000 Disintegrations / Minute per Probe Area 17 Preventable / Personnel Error LERs 18 Safety System Failures...

19 Maximum Individual Radiation Exposure 20 Violation Trend 21 Significant Events

. 22 Missed Surveillance Tests Resulting in LERs 23 vi

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l Table of Contents / Summary C'F%it.'ANCE Station Net GeneraSon

... 25 Forced Outage Rate....................

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Unit Capacity Factor.

.................. 27 Equivalent Availability Factor........

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Unplanned Safety System Actuations INPO Definition....

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

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L Daily Thermal Output 32 1

Equipment Forced Outages per 1,000 Critical Hours........

33 Chemistry Action Levels Exceeded - Event Days...

34 Primary System Litnium % Hours Out of Limit.................................... 35 COST Cents Per Kilowatt Hour

. 37 DIVISION AND DEPARTMENT PERFORMANCE INDICATORS Maintenance Workload Backlogs (Corrective Non-Outage)

. 39 Ratio of Preventive to Total Maintenance 40 Percentage of Total MWOs Completed per month identified as Rework

.... 41 Overtime 42 Procedura! Noncompliance incidents.

.... 43 in-Line Chemistry instruments Out-of-Service 44 Hazardous Waste Produced 45 Contaminated Radiation Controlled Area

.. 46 Radiological Work Practices Program.

47 Document Review 48 vii

j Table of Contents / Summary 1

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Loggable/ Reportable incidents (Security) 49 Temporary Modifications..........

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Outstanding Modifications..

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Engineering Assistance Request (EAR) Breakdown..

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Engineering Change Notices I

Status 53 1

Open

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Licensee Event Report (LER) Root Cause Breakdown 55 Licensed Operator Requalification Training 56 I

License Candidate Exams 57 l

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Condition Reports.

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Cycle 18 Refueling Outage i

MWO Planning Status

..... 59 Overall Project Status

.................... 60 Outage Modification Planning.....

......... 61 On-Line Modification Planning..

62 Progress of i997 0n-Line Modification Planning

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

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Performance indicator Definitions 66 l

Safety Enhancement Program index

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4 NUCLEAR PROGRAM 1997 GOALS AND OBJECTIVES I

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 INP0 ratings.

We must KNOW OUR COSTS to CONTROL COSTS.

Understanding cost is essential to controlling it, and controlling cost is essential to competing in today's market.

We are a learning organization.

We must BUILD ON OUR HIGH PERFORMANCE CULTURE.

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

OUR CULTURE MUST SUPPORT THE NEW STRATEGIES.

We must continue to develop and implement strategies that will allow us to effectively compete in the evolving market while still maintaining the highest levels of safety and reliability.

Communicating is our key to improving.

Follow up and feedback must be candid, forthright and timely.

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.

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

MISSION The safe, reliable and cost effective generation of electricity for OPPD customers through conservative decision making and the professional use of nuclear technology.

We will conduct these operations to assure the health, safety, and protection of our personnel, the general public, and the environment.

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GOALS Goal 1:

SAFE OPERATIONS Supports: April 1996 Corporate Strategic Plan Goal 3, Objective: 3 & 4 A proactive, self critical and safety conscious culture is exhibited throughout the nuclear organization. Individuals demonstrate professionalism through self-ownership and personal initiative and open communication.

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.

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OBJECTIVE 1-1:

No challenges to a nuclear safety systems.

OBJECTIVE 1-2:

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

OBJECTIVE 1-3:

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

OBJECTIVE 1-4:

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

OBJECTIVE 1-5:

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

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l OPPD NUCLEAR ORGANIZATION GOALS 1997 Priorities Goal 2:

PERFORMANCE Supports:

April 1996 Coiporate Strategic 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 by safe, 7

reliable and cost effective power production.

1997 PRIORITIES.

1 Improve Quality, Professionalism and Teamwork.

I Maintain High Plant Reliability.

Pursue efficient, cost-effective work processes.

Meet er exceed INPO key parameters.

Reduce the number of Human Performance errors.

l Identify Programmatic performance problems through effective self assessment.

Maintain a high level of readiness in the ERO.

Objectives to support PERFORMANCE:

l OBJECTIVE 2-1:

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

l OBJECTIVE 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:

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

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

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

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OPPD NtICLEAR ORGANIZATION GOALS 1997 Priorities 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 j

processes. Identify the barriers to excellence and resolve them.

OBJECTIVE 2-4:

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

OBJECTIVE 2-5:

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

Goal 3:

COSTS Supports:

April 1996 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 effectiveness.

implement Opportunity Review recommendations.

e Objectives to support COSTS:

OBJECTIVE 3-1:

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

OBJECTIVE 3-2:

Significantly reduce operating costs through full support of Utilities Service Alliance initiatives by maximizing sharing of resources. leveraging of buying power and elimination or reduction of redundant support services.

Goals Source:

Lounsberry (Manager) xii

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PERFORMANCE 4

I IND CATORS i

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, Monthly thit Capability Factor

...x. 12 Month Unit Capability Factor 1997 Fort Calhoun Goal (96%)

Year 2000 WANoIndustry Goal (87%)

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

i UNIT CAPABILITY FACTOR This indicator shows the plant monthly Unit Capability Factor (UCF) value, a rolling 12-month average, the OPPD goal, and the WANO 2000 goal. UCF is defined as the ratio of the available energy generation over a given period of time to the reference energy generation over the same time period, cxpressed as a percentage.

The UCF for April 1997 was reported as 69.5%. The year-to-date UCF was also repcrted as 92.4%,

the UCF for the last 12 months (May 1996 through April 1997) was 73.7%, and the 36-month aver-cge (May 1994 through April 1997) was reported as 83.1%.

Energy losses for April 1997 are attributed to a steam leak in the forth stage extraction steam system.

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

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

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

Energy losses for Dec.1996 are due to MOV-CV leakage.

The Year 2000 WANO industry goal is 87% and the industry current best quartile value is cpproximately 85%. The 1997 Fort Calhoun annual goal for this indicator is a minimum of 96.0%.

The maximum index point value for this indicator is 16. At the end of the April 1997, the FCS Value was 14.13. This compares to the previous month's value 13.79.

Data Source:

Generation Totals Report & Monthly Operating Report Accountability:

Chase Trend:

Needs increased Management Attention 2

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. Monthly unplannod Capability Loss Factor

+ 12 Month Rolling Average

,_. Fort Calhoun Goal (1.58%)

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+ Year 2000 WANo industry Goal (4.5%)

60%..

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40%..

30%..

20%..

10%.-

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May Jun Jul Aug Sep oct Nov Dec Jan Feb Mar Apr UNPLANNED CAPABILITY LOSS FACTOR This indicator shows the plant monthly Unplanned Capability Loss Factor (UCLF), a rolling 12-month average, the OPPD goal, and the Year 2000 WANO goal. UCLF is defined as the ratio of the unplanned energy losses during a given period of time, to the reference energy generation expressed as a percentage. Unplanned energy loss is defined as energy not produced as a result of unscheduled shutdowns, outage extensions, or load reductions due to causes under plant management control. Energylosses are considered to be unplanned if they are not scheduled at least four weeks in advance.

The UCLF for the month of April 1997 was reported as 30.50%. The year-to-date UCLF 4

was 7.63%, the UCLF for the last 12 months (May 1996 through April 1997) was 9.7%, and the 36-month average UCLF (May 1994 through April 1997) was reported as 6.9% 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 April 1997 the FCS Value was 7.47. This compares to the previous month's value of 7.0, i

Data Source:

Generation Totals Report & Monthly Operating Report Accountability:

Chase Trend:

Needs increased Management Attention 3

12-Month Rolling Average

+ PCS Reactor Scrams Per 7,000 Hours Critical for last 36 months Fort Calhoun Goal (0.0)

._ Year 2000 WANOlndustry Goal (1) l 3.-

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

FCS Reactor Scrams 1997 4..

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95 96 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 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 c.nd the Year 2000 WANO goal. The lower graph shows the number of unplanned automatic reactor scrams that occurred during the last 12 months. This indicator is defined as the number of unplanned cutomatic scrams that occur per 7,000 hours0 days 0 hours 0 weeks 0 months of critical operation.

There were no unplanned automatic reactor scrams during the month of April 1997. The 12-month rolling average (May 1996 through April 1997) was 0. The 36-month value (May 1994 through April 1997) was 0.301.

The 1997 Fort Calhoun Station goal for this indicator is 0. The Year 2000 WANO industry goal is a 1

maximum of one unplanned automatic reactor scram per 7,000 hours0 days 0 hours 0 weeks 0 months critical.

The maximum index point value for this indicator is 8. At the end of the April 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:

None 4

I m Monthly HPSI System Unavailability Value

+ 12 Month Rolling Average

+ FortCalhounGoal(0.003)

+ Year 2000 WANo industry Goal (0.02) 0 02 --

0.015..

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0.005..

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x 1996 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the High Pressure Safety injection (HPSI) System unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for April 1997.

The HPSI System unavailability value for the month of April 1997 was 0.00. There was 0.0 hours0 days 0 hours 0 weeks 0 months of planned unavailability, and 0 hours0 days 0 hours 0 weeks 0 months of unplanned unavailability, during the month.

The 12 month rolling average was (May 1996 through April 1997) was 6.0E-5, and the year-to-date HPSI unavailability value was 0.00006 at the end of the month.

4 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 goal is 0.02.

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

4 Data Source:

Phelps/Schaffer(Manager / Source)

Accountability:

Phelps/Schaffer Trend:

Positive 5

I m Monthly Auxiliary Feedwater System unavailability

-x-12 Month AFW Unavailability i

Fort Calhoun Goel(0.01)

Year 2000 WANo industry Goal (0.025) 0.025..

0.022 0.02 __

O 1996 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE j

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 April 1997.

The AFW System Unavailability Value for April 1997 was.022. There were 4.0 hours0 days 0 hours 0 weeks 0 months of planned and 18.00 hours0 days 0 hours 0 weeks 0 months of unplanned unavailability during the month. The 12 month rolling cverage (May 1996 through April 1997) was 0.00435, and the year-to-date unavailability value was 0.00766 at the end of April 1997.

At the end of April 1997, there has been a total of 4.00 hours0 days 0 hours 0 weeks 0 months of planned unavailability and 36.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of unplanned unavailability for the AFW system.

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 April 1997, the FCS Value was 10. This compares to the previous month's value of 10.

Data Source:

Phelps/Fritts (Manager / Source)

Accountability:

Phelps/Fritts Trend:

Needs increased Management Attention 6

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m Monthly Emergency AC Power UnavaBability Value Year-to-Date Ernergency Ac Power unavailabirdy Value Fort Calhoun Goal (0.024)

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I May Jun Jul Aug sep Oct Nov Dec Jan Feb Mar Apr 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 April 1997.

i The Emergency AC Power System unavailability value for April 1997 was 0.003 During the month, there was 4.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months of planned unavailability, and 0.0 hours0 days 0 hours 0 weeks 0 months of unplanned unavail-ability for testing and repairs. The Emergency AC Power System unavailability value year-to-date was 0.011 and the value for the last 12 months (May 1996 through April 1997) was 0.011.

There has been 62.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months (33.1 for DG-1 and 29.2 for DG-2) of planned unavailability and 0.0 hours0 days 0 hours 0 weeks 0 months of unplanned unavailability for the emergency AC power system in 1997.

There were a total of 163.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-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 system in 1996.

The 1997 Fort Calhoun year-end goal for this indicator is a maximum value of 0.024.

The Year 2000 WANO industry goal is 0.025.

The maximum index point value for this indicator is 10. At the end of April 1997, the FCS Value was 9.75. This compares to the previous month's value of 10.00.

Data Source:

Phelps/Ronning (Manager / Source)

Accountability:

Phelps/Ronning Trend:

Positive 7

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

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i 12-Month Rolling Average Fort Calhoun Goal (99.6%)

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+ Year 2000 WANo industry Goal (99.5%)

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1996 RFO i

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

l THERMAL PERFORMANCE This indicator shows the monthly Thermal Performance Value, the rolling 12-month average,

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j the OPPD goal, and the Year 2000 WANO goal.

j The thermal performance value for the month of April 1997 was 99.74%.

The year to date value was reported as 99.8%.

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The 12 month rolling average (May 1996 through April 1997) was reported as 99.78%.

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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%.

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

Value was 5.34 This compares to the previous month's value of 5.34.

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Data Source:

Phelps/Naser(Manager / Source)

Accountability:

Phelps/Naser

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Trend:

None i

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i e FuelReliability(E4)

, Year 2000 WANO Goal (5 x 10-4 Microcuries/ Gram)

-- _1997 Goal 14754 320.

299.16 l280__

257.07 g 240..

217.6 j200- - 189

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,,_ m._._ _ _

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

FUEL RELIABILITY INDICATOR The FUEL RELIABILITY INDICATOR (FRI) for April 1997 was 31.1E 4 microcuries/ gram. This is an increase from the March 1997 of FRI of 22.8 E-4 microcuries/ gram. The April 1997 FRI v,alue is based on data through April 21 at 100% steady-state power and an average letdown flow of 33.38 gpm. The plant was manually tripped at approximately 8:23 p.m. on April 21 due to a pipe rupture in a 12 inch turbine extraction steam line to number 5 heater. The plant did not restart in April. The Cycle 17 FRI in the first five months of operation is trending similar to the Cycle 16 FRI values.

Based on the coolant chemistry data through the end of April, there is no change to the previous Westinghouse fuel failure prediction of 8 to 14 leaking rods at icwer core power levels (i.e,<50%) or 3 to 5 leaking rods at core average power. During April, there was little change in the corrected and normalized iodine 131 level and the equilibrium Xenon 133 level which are both used to predict the number of fuel failures.

Cesium data from the April 21 manual trip indicated that the leaking fuel rods have a bumup of ap-proximately 36,000 MWD /MTU which corresponds to Batch S or T assemblies (Westinghouse original grid design).

The purpose of the FRI is to monitor industry progress in achieving and maintaining a high level of fuel integrity. An effective fuelintegrity and performance monitoring program provides a means to detect fuel failures and assess the fuel failure number, physical condition, exposure, mechanism, and loca-tion.

The 1997 Fort Calhoun Station FRI Performance Indicator goal is to maintain FRI below 147 x 10-4 microcuries / gram. This goal is based upon previous cycles fuel performance, results of the most recent fuelinspection and reconstitution campaigns, and an improved fuel failure resistant grid design in the new assemblies (Batch U) in the Cycle 17 core.

The maximum index point value for this indicatoris 8. At the end of the April 1997, the FCS Value was 3.79. This compares to the previous month's value of 3.94.

Data Source:

Guinn/Guliani Accountability:

Chase /Stafford Trend:

Needs Management Attention 9

m._

m Monthly Chemistry Indicator

+ 12-Month Rolling Average j

+ Fort Calhoun Goal (1.17)

]

2.6.

2.5..

2.4..

2.3..

1 4

2.2..

2.1..

I 2..

1.9..

j 1.s..

1.7..

1.6.

1.5..

1.4..

1.3..

E j

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

'Apr 0

i l

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 April 1997 was 1.14. The CPI value for the past 12 months (May 1996 through April 1997) was 1.31. In order to place the FCS in the industry's upper quartile, the 1997 goal has been changed from a CPI value < 1.4 to the CPI va!ue < 1.17.

~

l l

Reactor Plant forced outage occurred from 4/21 through 4/30. Of the six parameters used in the CPI calculation, four are below the INPO mean value. These are steam generator chlo-ride, sulfate, feedwater iron, and condensate pump discharge dissolved oxygen. Steam Gen-i crator 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 I

value.

1 The maximum index point value for this indicator is 7. At the end of April 1997, the FCS Value was 6.68. This compares to the previous month's value of 6.37.

]

Data Source:

Spires /Reneaud (Manager / Source)

Accountability:

Spires i

Trend :

Positive 10

.~

i i

e Monthly Personnel Radiation Exposure Cumulative Personnel Radiation Exposure

_e FCS Goal 38 person-REM 40..

C o

35.

30.

25..

b 20.

I 15.

10.

t

~

5.

0 E

i i _

l t

i i

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

COLLECTIVE RADIATION EXPOSURE The 1997 Fort Calhoun goal for collective radiation exposure is set at 38.0 person-REM.

The exposure for April 1997 was 6.375 Person-Rem (ALNOR).

The year-to-date exposure through the end of April 1997 was 12.468 Person-Rem (AL-NOR).

This indicator h a "COI.LECTIVE" indicator. WANO does not differentiate between on-line and outage exposure.

The Year 2000 WANO industry goal for collective radiation exposure is 120 person-rem per year. For the three year period (May 1994 through April 1997), the collective radiation exposure was 398.794 person-rem (ALNOR). This gives a Fort Calhoun Station a three year average of 133.9313 person-rem per year (ALNOR).

The maximum index point value for this indicator is 8. At the end of April 1997 the FCS Value was 7.2. This compares to the previous month's value of 6.8.

Data Source:

Chase /Cartwright (Manager / Source)

Accountability:

Chase /Gebers Trend:

None SEP54 11

' Monthly Volume of LLRW (cu.ft.)

-x Year to Date Cumdative Radioacthe Waste auried i

+ Fort Calhoun Goal (1200 cu.ft.)

1200 -- :

1100..

l 1000..

i 900..

1 i

1 800..

i 700..

i 600..

500..

'Cu

-400..

(

300..

200..

8 8

8

.g g

E d

100.

I O

x# C*T Jan Feb Mar Apr May-Jun Jul Aug sep oct Nov Dec VOLUME OF LOW-LEVEL RADIOACTIVE WASTE This indicator shows the volume of the monthly radioactive waste buried, the cumulative yrar-to-date radioactive waste buried, and the Fort Calhoun goal.

Cu.Ft.

- Amountofsolidradwasteshippedoff-siteforprocessingduringcurrentmonth 0.0 Volumeof solid radwasteburied during April 1997 17.4 Cumulative volume of solid radioactive waste buried in 1996 16.0

~ Amount of solid radwaste in temporary storage 136.3

~ The '1997 Fort Calhoun Station goal for the volume of solid radioactive waste (buried) is 1200 cubic feet. The Year 2000 WANO industry goal is_45 cubic meters (1,589 cubic feet) per

.l year. The industry upper ten percentile value is approximately 27.33 cubic meters (965.3 l

cubic feet). per year.

l L

This indicator is no longer used by INPO. The indicator will still be tracked, but will no longer

.l l

be used in computing the Station's Index Number.

j t

}

Data Source:

Chase /Breuer(Manager / Source) i Accountability:

Chase /Gebers Trend:

None SEP54 I

12 i

i

.-~.

,_. Monthlyinduetrial Accident Rate

~

-e-12 Month Rolling Average

,_. FCS Year-End Goal (<0.50)

+ Year 2000 WANo industry Goal (<0.40) 1.2..

1..

0.8 K-0.4 I M

f I

TN 5

L T

T T

)

May June July Aug Sep Oct Nov Dec Jan Feb Mar Apr INDUSTRIAL SAFETY ACCIDENT RATE This indicator is defined as the number of accidents per 20,000 man-hours worked for all utility personnel permanently assigned to the station that result in any of the 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.

The purpose of this indicator is to monitor progress in improving industrial safety performance for utility personnel permanently assigned to the station. Contractor man-hours are not included in the indicator.

The values for this indicator are determined as follows:

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

The Fort Calhoun Station industrial safety accident rate for the month of April 1997 was 0.00. The 12 month rolling average (May 1996 through April 1997) was 0.1502. The year to date value was 0.00 at the end of April 1997.

There were no restricted-time and no lost-time accidents in April 1997.

The 1997 Fort Calhoun year-end 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 April 1997, the FCS yalue was 5.0 This compares to the previous month's value of 5.0.

Data Source:

Sorensen (Manager)

Chase / Booth (Manager / Source)

Accountability:

Chase / Bishop Trend:

Positive 13

~

1 i

i i

1 i

l l

i i

l SAFE OPERAT ONS 1

l

)

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

exhibited throughout the nuclear organization. Individuals j

demonstrate professionalism through self-ownership and l

personalinitiative and open communication.

i 1

i i

l 14 i

I.

,__ Monthly Disabling injury / Illness Fraquency

]

12 Month Rolling Average

,_.1997 OPPD Goal i

i 2.

1.8..

j 1.6..

1A.-

l 1.2.

1.

0.8..

0.5 l

N-M-

0.41

'M I

~i

?

I I

0.2

\\

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

DISABLING INJURY /lLLNESS FREQUENCY RATE (LOST-TIME ACCIDENT RATE)

This indicator shows the April 1997 disabling injury / illness frequency rate and the disabling injury /

j illness rate for the past 12 months (rolling average).

For the month of April 1997 the disabling injury / illness frequency rate was 0.00. For the 12 month period (May 1996 through April 1997) the disabling injury / illness rate was 0.15. There were no disabling injury / illness cases reported for April 1997.

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

Data Source:

Sorensen/Blumenthal (M anager/ Source)

Accountsbility:

Chase / Bishop Trend:

Meeting OPPD's Goal SEP 25,26 & 27 15 a

i l

,_ Monthly Recordable injury / Illness Frequency Rate l

Rolling 12 Month Average l

..... Fort Calhoun Goal 4.5..

4.0..

3.5..

3.0 --

2.5..

2.0 e

1.5,............................................................................

l 1.0 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 1

RECORDABLE INJURY /lLLNESS FREQUENCY RATE This indicator shows the monthly recordable injuryfillness frequency rate, a rolling 12 month average, and the OPPD goal.

I A recordable injuy/ illness case is reported if personnel from any of the Nuclear Divisions are injured on the job and require corrective medical treatment beyond first aid. The recordable injury / illness cases frequency rate is computed on a rolling 12 month average.

The recordable injury / illness frequency rate for the month of April 1997 was 1.47.

l The recordable injury / illness frequency rate for the past 12 months (May 1996 through April 1997) was 1.66.

During the month of April 1997, there was 1 recordable injury in which an employee I

reported the development of wrist strain due to extensive keyboard work over the coarse of several years.

l r

l There have been a total of 3 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 Accountability:

Bishop l

Trend:

None SEP 15,25,26 & 2-7 16 l

y m Contaminatkm Events (Monthly)

_ Contamk.ation Events (YrD) 100..

90.

80 70..

60..

50 __

40..

30..

20..

10..

s 0

Og i

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec CLEAN CONTROLLED AREA CONTAMINATIONS 21,000 DISINTEGRATIONS / MINUTE PER PROBE AREA This indicator shows the Personnel Contamination Events in the Clean Controlled Area for contaminations 21,000 disintegrations / minute per probe area for April 1997.

There was 1 contamination events in April 1997. There have been nine contamination events in 1997 through the end of April 1997.

Data Source:

Chase /Cartwright (Manager / Source)

Accountability:

Chase /Gebers Trend:

None SEP 15 & 54 17

a m Personnel Errors (Each Month)

+ Preventable (18-Wonth Totals)

C PersonnelError(18 Mors Totals) 20..

15..

10..

5-C C

C

[

~

N C

C 0

'E

,E:

E,Ei

~

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

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

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

Due to the manner in which documentation is closed out, data for this Performance Indicatoris one month behind.

In April 1997, there were no events which were subsequently reported as an LER. No LERs were categorized as Preventable and no LERs were categorized as Personnel Er-ror for the month of April. The total LERs for thr, year 1997 is one. The total Personnel Error LERs for the year 1997 is zero.

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 /Cavanaugh (Manager / Source)

Accountability:

Chase Trend:

None SEP 15 18

, Startup e Shutdown m Operations

...o...

Industry Average Trend I=

1 o

92-2 92-3 92 4 93-1 93 2 93-3 93 4 94-1 94-2 94-3 94-4 95-1 Year-Quarter SAFETY SYSTEM FAILURES This indicator illustrates the number of NRC Safety System Failures as reported by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data in the biannual" Performance Indica-tors 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 condi-tions.

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

4th Quarter 1993: 1) During surveillance testing, both PORVs for the LTOP system failed to open during multiple attempts. The failures were a result of differential expansion caused by a loop seal, excessive venting line back pressure, and cracked valve disks; 2) Calibraton errors of the offsite power low signal relays could have prevented offsite power from tripping and the EDGs from starting in the required amount of time during a degraded voltage condition; 3) Both AFW pumps were inoperable when one was removed from service for testing and the control switch for the other pump's steam supply valve was out of the auto posi-tion.4) Only one train of control room ventilation was placed in recirc when both toxic gas monitors 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 review determined that an ESF relay could result in loss of safety injection and spray flow, due to premature actuation of recirculation flow.

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

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

Data Source:

Nuclear Regulatory Commission 19 Accountability:

Chase Trend:

Positive

m Hghest Wnthly hdividual Eposure trR g--- Year-tcxlate

+ Fort Cahoun Goal 1000 rrR 1000 900.

800.

700.

600.

500.

400.

300.

200.

100..

O E

[

Jan Feb Mar Apr May Jun Jul Aug Sep Oct tbv Dec 4

l MAXIMUM INDIVIDUAL RADIATION EXPOSURE 2

This indicator shows the highest exposure for an individual during January 1997.

For the month of April 1997, an individual accumulated 211 millirem, which was the highest individual exposure for the month.

For the year to date, an individual has accumulated a total of 465 millirem (TLD). The 465 mR is down from the previous reading of 556 mR due to TLDs being read. The 556 mR came from ALNOR readings, and in general, are higher than TLD readings.

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

year. The 1997 Fort Calhoun Station year-end goal is a maximum of 1,000 mrem.

1 Data Source: Chase / Cartwright (Manager / Source)

Accountability:

Chase /Gebers Trend:

None 20

r 4

l NO DATA AVAILABLE l

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 inforrna-l tion on other Region IV plants.

The following inspections were completed during February 1997:

IER No.

TJun 97-03 Resident Monthly

- To date, OPPD has received no violations for inspections conducted in 1997.

Level 111 Violations 0

)

LevelIV Violations 0

Non-Cited Violations

_Q Total 0

The 1997 Fort Calhoun Station Goal for this performance indicator is to be at or below the cited violation trend for the top quartile plant in Region IV.

Data Source:

Tills /Cavanaugh (Manager / Source) 4 Accountability:

Tills Trend:

None 21

~

NRC Significant Ewnts e-Industry Average Trend 1

1 1 -.

0.5..

l 0l

_ M e m L p=.e r

r r

r 92 93

^4 frM 95-2 95-3 95-4 96-1 96-2 96-3 96-4 l

Year-Quarter INPO Significant!!wems (sea) 3 3 -.

2..

2 9

9 0

0 0

1 I-c 93 94 95 1 95-2 95-3 95 4 96-1 96-2 96-3 96 4 97 1 Year-Quarter SIGNIFICANT EVENTS NRC SIGNIFICANT EVENTS The following SEs were identified between the 2nd Quarter of 1992 and the 1st quarter of 1995 (as reported in the NRC's

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

3rd Quarter 1992:

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

4th Quarter 1994:

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

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

2nd Quarter 1992:

Intake of transuranics during letdown filter change-out.

3rd Quarter 1992:

Safety Valve malfunction (RC-142).

1st Quarter 1993:

Inoperability of Power Range Nuclear Instrumentation Safety Channel D.

2nd Quarter 1993:

Inadequate control of Switchyard activities.

3rd Quarter 1993:

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

1st Quarter 1994:

1)

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

2)

Unplanned dilution of Boron concentration in the Reactor Coolant Gystem.

1st Quarter 1996:

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

2nd Quarter 1996:

RC Pump Anti-Reverse Rotation Device (ARD) failure.

No SE reports have been received from INPO on the 1996 SEs as of August 1, 1996.

Data Source:

Nuclear Regulatory Commission & INPO Accountability:

Chase Trend:

None 22

Missed STs Resulting in LERs 3._

2._

1__

0 0

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

t NUMBER OF MISSED SURVEILLANCE TESTS RESULTING IN LICENSEE EVENT REPORTS This indicator shows the number of missed Surveillance Tests (STs) that resu;ted in

]

Licensee Event Reports (LERs) during April 1997.

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

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

i i

Data Source:

Monthly Operating Report & Plant Licensee Event Reports (LERs)

Accountability:

Chase /Phelps Trend :

None SEP 60 & 61 23 l

!~

!l-i i

i 1

a PERFORMANCE i

I i

i l

i i

l Goal:

To strive for Excellence in Ope. rations utilizing the l

highest standards of performance at Fort Calhoun Station that l

result in safe, reliable plant operation in power production.

i i

i l

1 l

1 1

i 1

i, l

24 l

1

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

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

t l

l f

Net Generation (10,000 MWh) 40 I

30 __

j 1996 I

E RFO 20 outage 1

10, l

10.-

l n

j i

i i

i May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr STATION NET GENERATION During the month of April 1997, a net total of 243745.9 MWh were generated by the Fort Calhoun Station. Cumulative net generation for Cycle 16 was 5,418,326.6 MWh. Cumu-lative net generation for Cycle 17 was 1,640,444.50 MWh at the end of April 1997.

Energy losses for April 1997, were attributed to a forth stage extraction steam pipe rup-ture.

4 Energy losses for June 1996 were attributed to a failure of the Anti-Rotation Device (ARD) associated with Reactor Coolant Pump Motor RC-3B.

Energy losses for December were attributed to a steam leak on the turbine control valves (MOV-CV).

Data Source:

Station Generation Report Accountability:

Chase Trend:

None 25

, Monthly Forced Outage Rate

+ Rolling 12 Month Average

+ 1997 Fort Calhoun Goal (1 A%)

50%.

45%..

40%..

35%..

30%..

25%.

20%.

15%.

10%..

5%..T

/

4 0%

0 0

0 A,

0 0

96 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr FORCED OUTAGE RATE 4

The forced outage rate (FOR) for the month of April 1997 was 30.6 % The forced outage rate for the previous 12 months (May 1996 through April 1997) was 7.71%. The 1997 year-to-date FOR was 7.6% at the end of April 1997.

Energy Losses are explained on Page 25.

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

i e

i Date Source:

Monthly Operating Report Accountability:

Chase Trend:

Needs Management Attention 26

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

1 l

Monthly Unit Capacity Factor

..e... Year-toCate UnitCapacityFactor i

UnitCapacstyFactorforCycle 17 l

_e - 1997 FCS Goal {96.00%)

l 110 % -

l 100 % -.

l 90%. 85X4 80%..

'.a.-

Cycle 17 j

50%..

l 40% -.

30*4..

l m..

10%..

P4 l

i i

i l

C.16 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr UNIT CAPACITY FACTOR i

1 i

j This indicator shows the plant monthly Unit Capacity Factor, the Unit Capacity Factor for the 1

current fuel cycle, the year-to-date, and the 1997 OPPD Station goal.

)

The Unit Capacity Factor is computed as follows:

I Net Electrical Enerav Generated (MWH)

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

~

l t

I k

i Cycle 16 Unit Capacity factor was 85.23%.

f At the end of April 1997, the Cycle 17 Unit Capacity Factor was 70.82%. The Unit Capacity Factor for the last 36 months (May 1994 through April 1997) was 84 AS%. The 1997 Fort Cal-houn annual goal for this indicator is 96.00%.

The year-to-date value is 93.44%.

Data Source:

Monthly Opersting Report Accountability:

Chase Trend:

Needs Management Attention 27

, Monthly EAF l

._e_. Year-to-Dete Average Monthly EAF

+ 12 Month Rolling Average l

+ OPPD Goal 100%

,s.es v s.o

L.

i

. N g

7 m,

80%..

' 21"

./

y N

+

60%

I 43.2%

~

40%..

20%..

RFO 0%

,U r7.

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

EQUlVALENT AVAILABILITY FACTOR This indicator shows the plant monthly Equivalent Availability Factor (EAF), the year-to-date average monthly EAF, the 12 month rolling average, and the OPPD goal.

The EAF for April 1997 was 68.66%. The 12 month rolling average (May 1996 through April 1997) was 73.56%. The equivalent availability factor for the past three years (May 1994 through April 1997) was 84.47%.

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

Data Source:

DietzNandervort (Manager / Source)

Accountability:

Chase Trend:

Needs increased Management Attention 28

4 m Safety System Actuations (INPO Definition)

._,_. R:S Goal (0)

+ Industry Upper 10 Percentile (0) 3,.

2..

1..

0 0

l 96 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Ma'r Apr UNPLANNED SAFETY SYSTEM ACTUATIONS -(INPO DEFINITION)

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

There were no WANO unplanned safety system actuations during 1996.

The 1997 Fort Calhoun goal for this indicator is 0.

i Data Source:

Monthly Operating Report & Plant Licensee Event Reports Accountability:

Phelps/Foley/Ronning Trend:

None 29

m SafetySystem Actuations(NRCDefinition)

, FCsGoal(0)

Critical Hours 10 1MI6 ff0

_.800

..700 8..

.600 g

i E

..500

$8"t t

8 E

..400 x

=

b

_.300 0

f 200 2.

f

__100 0 (

0 0 0

.;'i O

FMAM J JASONDJ FMAMJ JAsONDJ FMA UNPLANNED SAFETY SYSTEM ACTUATIONS -(NRC DEFINITION)

~

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

There 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/Foley/Ronning Trend:

None 30

m Gross Heat Rate Year-to-Date Gross Heat Rate

+ Fort Calixmn Goal a

14.75 __

j 1

14.25._

l 13.75.

i 13.25 g 12.75._

j g 12.25.-

l

$ 11.75..

8 i

, 11.25 10.75._

10.25..,ow 9.75..

i i

i 96 May Jun Jul Aug Sep oct Nov Dec Jan Feb Mar Apr GROSS HEAT RATE This indicator shows the Gross Heat Rate (GHR) for the reporting month, the year-to-date GHR, the goals, and the year-end GHR for the previous three years.

The gross heat rate for Fort Calhoun Station was 10,038 BTUlkWh for the month of April

~

1997. The 1997 year-to-date GHR was 10,025 BTU /kWh at the end of the month.

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

The 1997 Fort Calhoun year-end goal for this indicator is 10,166 BTUlkWh.

Data Source:

Guinn/Willett (Manager / Source)

Accountability:

Chase /Skiles Trend:

Increased Management Attention 31

J l

Thermal Output

._e Fort Calhoun 1498 MW Goal

^

+ Tech Spec 1500 MW LimK 1600.

<m -c---=

=

=-

=====-

. m 1400.

1 1200.

1 l

1000.

. h^

s00.

l i

400.

0

1. 2 3 4 5 6 7 8 9 101112131415161718192021222324252627282930 DAILY THERMAL OUTPUT i

The thermal output graph displays the daily operating power level during April 1997, the 1500 thermal megawatt average technical specification limit, and the 1498 thermal mega-watt Fort Calhoun goal.

Data Source:

Guinn/Willett (Manager / Source)

Accountability:

Chase /Short Trend:

None 32

i

+ Monthly Equipment FOR

+ Equipment FORii,000 Critical Hrs. (Rolling 12-Month interval)

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

j i

1.

EN - d

=

5 E

E

=

0 May Jun

[ul Aug Sep oct Nov Dec Jan Feb Mar Apr EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS The equipment forced outage rate per 1,000 critical hours for the 12 months from May 1,1996, through April 30,1997, was 0.289. The year-to-date rate per 1,000 critical hours for the months from January 1,1997 through April 30,1997 was 0.376.

t An equipment forced outage occured during the month of June 1996, due to the failure of the Anti-Rotation Device associated with RC-3B-M.

The equipment forced outage that occured at the end of April 1997, was attributed to the rupture of a fouth stage extraction steam pipe.

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)

Accontability:

Chase /Phelps Trend:

Increased Management Attention 33

l l

l CHEMISTRY ACTION LEVELS EXCEEDED Sent Days + Average bent Days + oFPD L'riit r

3.

i 2.5.

2.

g 1.5.

h 1.

0.5.

O E

k k

}

W o

E F

k

?

E

{.

V 9

5 9

7 7

7 5

?

T 8

8 S

8 8

8 2

MONTH CHEMISTRY ACTION LEVELS EXCEEDED - EVENT DAYS l

The Chemistry Action Levels Exceeded indicator tracks the number of days in which chemistry parameters exceeded a corresponding action level for the reporting month, as well as a 12-month average of days an action level is 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 purpose of this indicator, whenever the parameter exceeds the CH-AD-0003 action level for the current system 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.

T% 1997 Fort Calhoun goal for this indicator is the 12-month average of two event days per month. There is no goal established for the number of event days per individual month.

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

There were no event days in April.

Data Source:

Chase / Spires Accountability:

Spires Trend:

None 34

1

% Hours outof Umit 12.00.

+NMN 10m.

l l

am.

6.00.

)

2.00.

0.00 r,

R E

E I

I 5

E E

4 E

a i

PRIMARY SYSTEM LITHlUM % HOURS OUT OF LIMIT l

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 April 1997.

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

i l

l l

l Data Source:

Chase / Spires (Manager / Source)

Accountability:

Spires Trend:

Postive 35

i-a 1

i i

4 i

I i

i i

l i

)

l COST i

.i

!e i

Goal: Operate Fort Calhoun Station in a manner that cost i

offectively maintains nuclear generation as an i

cconomically viable contribution to OPPD's bottom line.

l Cost consciousness is exhibited at all levels of the l

organization.

I l

r f

l

{

4

)

i s

36 l

w-v

--* Actual e

Budget Ran l

3.80 3.60.

3.40.

3.20.

3.00.

2J0.

~

2.60.

2.4n.

2.20.

2.00 li ' ' * * ' ' " " * * " E i i E i CENTS PER Kil.OWATT HOUR March 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 December 31 amounts are also shown for the prior years 1992 through 1996. In addi-tion, 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 ro!!ing average unit price (period of February,1996 through March,1997) averaged above the budget due to 12-month rolling expenses exceeding the budget expecta-tions. The 12 month rolling average (2/96 through 3/97) is 3.24 cents per kilowatt hour.

The year-to-date average is trending positively.

Cents per KWH Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Budget Y-T-D 2.83 2.66 2.58 2.60 2.55 2.53 2.54 2.51 2.50 2.50 2.48 2.47 Actual Y-T-D 2.89 2.60 2.54 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Data Source:

Lounsberry/ Dent (Manager / Source)

Accountability:

Lounsberry Trend:

None 37 1

r i

4 I

1 i

DIVISION AND 3

l DEPARTMENT 4

l PERFORMANCE INDICATORS Goal: Achieve high standards at Fort Calhoun Station resulting in safe, reliable and cost effective power production.

38

. - ~ -

M Corrective Maintenance Preventive Maintenance l

i Non-Corrective /Plantinprovements Fort Calhoun Goal i

1000 -

sm 1

780 720 l @800-ttimiti i

637 729 682 624 1

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

Non Outage Maintenance Ybrk Order Backlog i

i Past Completion Completed

}

m TotalMWos 62 %

l MWO PRIORfrY BREAKDOWN i

600 411.

38 %

h~Q

Y<f'~4f 400 A

u

, ~.

A7 200 - )2l' i8b I

4 I

M w

Not Cornpleted o-i

- r t

t j

Rbrty Riorky R orty Rbrty Riorty

}

1 2

3 4

5 i

MAINTENANCE WORKLOAD BACKLOG 4

This indicator s' nows the backlog of non-outage Maintenance Work Orders remaining open at the end of the reporting month. It also includes a breakdown by maintenance classification and prior-j ity. The 1997 goal for this indicator is 350 non-outage corrective maintenance MWOs. The cur-i rent backlog of corrective MWOs is 312. To ensure that the MWO backlog is worked in a timely manner, non-outage maintenance completion goals have been established as follows:

1 Goal Priority 1 Immediate Action 2 days 1

Priotity 2 Urgent 5 days Priority 3 OperationalConcems 30 days i

Priority 4 Routine Corrective 90 days Priority 5 Non-Essential 180 days 1

l Data Source:

Chase / Johnson (Manager / Source)

Accountability:

Chase /Faulhaber Trend:

None SEP 36 i

39 i

~ - -

Ratio of Preventive to Total Maintenance 90%.

80%..

70%..

60%

~

Data N/A 40 %

30%

20%

10%

0*4 1

1 1

1 I

i l

l

.l i

May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr e Preventive Maintenance items Overdue e Fort Calhoun Goal 3% "

2.60 %

2%..

1%..

0.75%

0.63%

0.56 %

0.40 %

0.39 % 0.39%

E E;

E, 0.00%

n=4 i

i i

i May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr RATIO OF PREVENTIVE TO TOTAL MAINTENANCE PREVENTIVE MAINTENANCE ITEMS OVERDUE The top graph shows the ratio of completed non-outage preventive maintenance to total com-pleted non-outage maintenance. The ratio was 83.6% for the month of April 1997.

The lower graph shows the percentage of scheduled preventive maintenance items that are over-1 due. During April 1997,356 PM items were completed.

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

Data Source:

Chase / Johnson (Manager / Sources)

Accountability:

Chase /Faulhaber Trend:

Increased Management Attention SEP 41 & 44 40

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

i e

m No. Maintentance tems conpleted

+ % k$entified as Repeat 4

i f

700.

. 6.0%

526

. 5.0%

500.

l

. 4.0%

l 400.

l 300.

252 238 248 214 207 19 i

i i

...i

_. 0.0%

{

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

m ReworkasidentifiedbyCraft

,_ Fort Calhoun Goal (<3%)

] 5%..

4.s %

I5 4%..

S 8d' 3%

3o

~~

l.6 %

4.5 %

1.5 %

1.4 %

S 1%..

e.s%

6.s %

835

'd"

" *4 I

l l

1 I

I i

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

This indicator is calculated from the 15th of March to the 15th of April, due to the delay in closing open MWOs 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 41 Trend:

None

, Monthly Overtime (On-Une) l l

Y T-D Monthly Average (On-Une)

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

10.0% --

s-3

=

9.0 % _

8.0%..

7.0%.

6.0%..%

5.0%

p 4.0%..

1 3.0%..

2.0%..

l 1.0%..

i 0.0%

i Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec MAINTENANCE OVERTIME 1

1 The Maintenance Overtime Indicator monitors the ability to perform the desired rnainte-nance activities with the allotted resources.

The percent of overtime hours with respect to normal hours was reported as 9.8% for the month of April 1997. The 9.8% overtime does not include the forced outage overtime hours.

The 1997 Fort Calhoun monthly "on-line" goal for this indicator is a maximum value of 8%.

Data Source:

Chase / Johnson (Manager / Source)

Acccuntability:

Chase /Faulhaber Trend:

Needs Management Attention 42

l' l

Human Performance CRs(Maintenance) i 20.

18..

l j

16..

l l

14..

3 12..

k E

I a

g 10..

U j

8 IO~-

7 j

Oct Nov Dec Jan Feb Mar Apr PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)

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

4 1

l l

Data Source:

Faulhaber Accountability:

Chase /Faulhaber i

Trend:

None SEP 15,41 & 44 1:

I l

l 43 i

5u.

._e

% PAssoos

-x

% tunPAss oos a_ % Tota!OoS

+ Total % oos Goal 50%.

i 45%.

4o%.

35%.

30%.

25%.

20%.

15 %

I

,t h

10%

I N-5/

'E~ N::- x 1

f%g_,N N

5% x a

mW o%

=

4 8

8 8

m a

a i

I 4

4 I

I

}

$'ai lN-LINE CHEMISTRY INSTRUMENTS OUT-OF-SERVICE This indicator shows the percentage of hours the in-line chemistry system instruments are inoperable for the reporting month. The chemistry systems involved in this indicator in-ciude the Secondary System and the Post Accident Sampling System (PASS). At the end of April 1997, the percentage of hours the in-line chemistry system inrk iments were inoperable was 1.03%. The following instrument was out of service for the current month:

1.

% PASS HOURS OUT OF SERVICE - NONE 2.

% NON-PASS HOURS OUT OF SERVICE Al-110 Hydrogen was out of service from 4/12 thru 4 /24 1997.

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

Data Source:

Chase /Ostien (Manager / Source)

Accountability:

Chase /Skiles Trend:

Positive 44

i 0

m Waste Produced Each Month (Kilograms)

,_. Fort Calhoun Monthly Average Goal (150 kilograms)

+ Federal & State MonthlyLimit(Max.of 1,000 kg)

'000 -

a 900.

800 i

700..

600.

E

$ 500..

a* 400.

1 300.

4 200.

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

During the month of April 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.

The 1997 Fort Calhoun. monthly average goal for hazardous waste produced is a maxi-mum of 150 kilograms.

Data Source:

Chase /Shubert (Manager / Source)

Accountability:

Chase / Spires Trend:

Positive 45

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

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

l!

m Contaminated Radiation ControNed Area

{

+ FortCalhounGoal(10%)

I i

i 10%..

9%..

8%..

1i. t I 7%

i

.i l

i i

i May Jun Jul Aug sep Oct Nov Dec Jan Feb Mar Apr CONTAMINATED RADIATION CONTROLLED AREA This indicator shows the percentage of the Radiologically Controlled Area that is contami-nated based on the total square footage. The 1997 monthly non-outage goalis a maxi-mum of 10.0% contaminated RCA.

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

i Data Source:

Chase / Williams (Manager / Source)

Accountability:

Chase /Get,ers Trend:

Postive SEP 54 46

~

Poor Radiation Worker Practices

+ Fort Calhoun Goal (<15) 16 14.

12.

10.

8.

6.

4.

2 2.

0 o

0

~

0:

Jan Feb hr Apr May June July Aug sep Oct Nov Dec I

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

The number of PRWPs which are identified each month should indirectly provide a means to qualitatively assess supervisor accountability for their workers' radiological performance.

During the month of April 1997, there were 2 PRWP identified.

There have been a total of 2 Poor Radiation Worker Practices in 1997.

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

Data Source:

Chase /Cartwright (Manager / Source)

Accountabilitv:

Chase /Gebers Trend:

None SEP52 47

-. ~ -

l O Doc,uments scheduled for Review 3 Documents Reviewed g Documents Overdue 450..

400..

350.

~

300..

250..

200..-

150..

j 100..

Il 50..

l 0.__ (_ k i

+j

+_

q May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 1996 DOCUMENT REVIEW The Document Review indicator shows the number of completea, scheduled, and over-due (greater than 6 months past the scheduled due date) biennial reviews for the report-ing month. The documents reviews are performed in-house and include Special Proce-l dures, the Site Security Plan, Maintenance Procedures, Preventive Maintenance Proce-dures, and the Operating Manual.

During April 1997, there were 363 document reviews scheduled, while 91 reviews were completed. At the end of the month, there were 33 document reviews more than 6 months overdue. There was 5 new documents initiated during April 1997.

Data Source:

Chase /Plath Accountability:

Chase /Skiles Trend:

Needs Management Attention SEP 46 l

48 l

l

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

~ -

i*

i i

g System Failures

[

O Non. System Failures 27 j

j 25.-

28 22 22 i

20 _

i 15 D

n 10.

O 1

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

i 4

l LOGGABLE/ REPORTABLE INCIDENTS (SECURITY)

I The Loggable/Reporteble incidents (Security) Indicator is depicted in the following charts.

The charts depict the total number of loggable/ reportable non-system failures and system i

failures which occurred during the reporting month. Further, charts illustrating the three i

year average, a managment tool for measuring performance, for total loggables/reportables i

and non-system / system failures are attached.

l l

During the month of April 1997, there were 15 loggable/ reportable incidents identified.

l System failures accounted for 87% of the total failures. Four (4) of the six (6) non-environ-i mental system failures involved the x-ray machine. I&C technicians are currently trouble-4 shooting the problem with resolution expected during the first week of May 97. Environ-l mental failures accounted for 54% of the system failures. The two non-system failures consisted of one security force error, and one error involving access authorization.

i j

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

I l

Data Source:

Sefick/Woerner (Manager / Source)

]

Accountability:

Sefick

{

Trend:

None SEP 58 49 i

l

~

=

i TemporaryMoctrications>1 cycleold(fforsqtiredforremoel) i m Temporarylextficabans>6monthsold(fbmombiecrHine)

+ RrthMfw>1@W)6tecid 8

3..

2.5..

2 E

3 1.5.-

e i

1 3

0.5.

00 0 0 00 C

o0 00 0

0 E

3 E

S o

o g

i k

E o

I y

m O

Z m

E 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 requir-ing a refueling outage to be removed. TM 96-014, Reactor Coolant Gas Vent Line Pressure High Alarm, was scheduled and repairs were made during the 1996 Refueling Outage, but function testing of the repairs not be performed because the reactor coolant gas vent line pressure is currently too high to test the equipment. TM 96-018, Equipment Drain Header Soft Rubber Patch, was supposed to be removed by MWO 963468 during the 1996 Refueling Outage. MWO 963468 is currently scheduled for the 1998 Refueling Outage. At the end of April 1997, there was 1 temporary rnodification installed that was greater than six months old that could have been re-moved on-line. TM 96-022, Containment Low Flow Purge was installed 06/14/96. ECN 96-450 will make this TM permanent.

At the end of April 1997, there was a total of 13 TMs installed in the Fort Calhoun Station. Eight (8) of the 13 installed TMs require an outage for removal and 5 are removable on-line. In 1997, a total of 8 temporary modifications have been installed. At the end of April 1997, there were nine (9) procedural or maintenance configuration alterations (temporary modifications) installed using PRC approved procedures. These procedural or maintenance configuration alterations are con-trolled by Standing Order O-25.

Data Source:

Phelps/ Frank (Manager / Source)

Accountability:

Phelps/ Core Trend:

Increased Management Attention SEP 62 & 71 50

TdallWdlicationRackapsChen i

i

_,_ RrtQinm%eredQal(08) 80.

7, 77 76 75 74 70 70.

E l

l l

i l

l l

H 96 Jan Rib Nhr Nhy Jm Jd Ag Sep Q:t ftu Duc OUTSTANDING MODIFICATIONS This indicator shows the total number of outstanding modifications (excluding outstanding modifications which are orooosed to be cancelled).

Reporting 1

Cateoorv

'M

'95

'fifi

'OZ E

E Month Form FC-1133 Backlog /In Progress 0

0 0

7 0

0 0

Mod. Requests Being Reviewed 0

0 0

1 0

0 0

Design Engr. Backlog /In Progress 0

0 0

20 20 Construction Backlog /In Progress 1

6 15 2

1 21 21 Design Engr. Update Backlog /in Progress _1

_I

__11

_Q

_Q 2R

_._2R Totals 2

13 26 10 21 2

79 (Outage + OnUne)

(0+2)

(5+8) (17+9) (1 +9) (20+1) (50+29)

At the end of April 1997,21 modification requests have been issued this year and 2 modification requests have been cancelled. The Nuclear Projects Review Committee (NPRC) has conducted 41 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) has completed 0 backlog modification request reviews this i

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:

None 51

40..

EARS Requiring Engineering Closeout - Not in Ooseout 27 28 27 30 --

24 g SE O DEN 20.. 16 15 1

'o 12 3

3

~

n 10.

4 5

4-5 3

2-1

E-E E

0

>E Feb Mar Apr Feb Mar Apr Feb Mar Apr Feb Mar Apr 0-3 Months 3-6 Months 612 Months

>12 Months O W*@W' W NWW 30..

20..

11 14 8

0 0

1 0 0 10..

1 3

o 1

1 I

I I

0 Priority 0 Priority 1 Priority 2 Priority 3 Priority 4 Priority 5 Priority 6 a==ut 10 %

..p.....

48 4#

I s k e. u te

Response

3 14.2 %

ENGINEERING ASSISTANCE REQUEST BREA.KDOWN 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.

The Total EAR breakdown is as follows:

EARS opened during the month N/A EARS closed during the month N/A Total EARS open at the end of the month 119 l

Data Source:

Jaworski/Livingston (Manager / Source)

Accountability:

Phelps/Jaworski Trend:

None SEP 62 52

.t 42 Ill 6s ctostout osa

,,3 g, _,

r s' co 1.

ECN Status - Overall Backlog

.4 1

n....

g Backlogged O Received g Completed um 250.

150.

m.

ma u2 18

. mi

,3 N"

" 3' s.sn$...

08 j Nov Dec Jan Feb Mar Apr j

u n,,.,

j 445 Design Engineering i

250.

3-6 d

E nths 200.

03 I ~

Watk.

100..u

=

2 O

'Systo Engineering m.>"

=>

0.......

es

,s 250.

I I... l...

... b,l,, :l:: @

~

0

.E

- "l"**

Oct Nov Dec Jan Feb Mar Procurement / Construction 250.

,,,j,,

8

,,3 200.

Month.

0%

10%

150.

100

2 rs g_'

g'm a d

o IM EC. R E A E E N' '

M,,,,,

Nov Dec Jan Feb Mar Apr s0'.

Drafting / Closeout ENGINEERING CHANGE NOTICE STATUS Data Source:

Jaworski/Livingston (Manager / Source)

Accountability:

Jaworski/Phelps Trend:

None SEP 62 53

i

~

l 1

1 78 il6 90 96 j

DC 7YPE 7C TYPE P 'to rity P rie rity 17m as sa6 sar

,m

==r 2,,m 2s3 I

sRITYPE 271 Total Open ECNs = 457

,,io e7 Total Open ECNs = 457 l

ss*

344 j

5 1

0 DEN. Closeester Drafting Net C omplete j

E n.a.t.

.c e/C...tr.c ts..fr,e c.,eme t. w.cn N o t C o mpiete j

E system Engemeering. Response. Confirmation Net Complete gog E DEN. E ngineering Not C o mplete i

150-ese i44 its i:1

,3,

j 3

9 1

7 3

7 4

3 l

9 i

a

,.s y

2 7 W.

3 s

3 3

s 2

prorny 142 4

9 57 3

i 8

17%

O i

t 3

i i

N e w-96 D ec.96 n-F ar 97 Apr 97 l

l 350' 37 72 1

296 194 303 199 P rio rity I 'I' 'I'I 142 la 13 14 247 sA6 2ss 250.

4, it is,

to it to 100.

i k

J Nov46 Dec46 Jan47 Feb47 Mar 47 Apr47 a

]

s7m Substitute Replacernent item ECNs open dr

,1.',,

,e i.

se uov one

.se.

P. =

uer Apr r a a's Document Change ECNs Open ENGINEERING CHANGE NOTICES OPEN Data Source:

Jaworski/Livingston (Manager Source)

Accountability:

Phelps/Jaworski Trend:

None SEP 62 54 i

O Administrative Control Problem g Ucensed Operator Error 3 Other Personnel Error 3 Maintenance Problem O Design / Construction / Installation / Fabrication Problem 3,.

3 Misc.

3.-

J n

4 2..

2..

l 1..

1.-.

c u

0 "

4 k

(

q r

i

M 0

May Jun Jul Aug Sep oct Nov Dec Jan Feb Mar Apr LICENSEE EVENT REPORT (LER) ROOT CAUSE BREAKDOWN This indicator shows the LERs by event date broken down by Root Cause Code for each of the past twelve months from May 1,1996, through April 30,1997. To be consistent with the Preventable / Personnel Error LERs indicator, this indicator is reported by the LER event date, as opposed to the LER report date.

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

this report.

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

l There were two events in April 1997 that resulted in a LER.

l l

Data Source:

Tills /Cavanaugh (Manager / Source)

Accountability:

Chase Trend:

None 55

1 O Total Requalification Training Hours g SimulatorTrainingHours I

s Non-Requalification Training Hours O Number of Exam Failures 35 35 __

M 32.5 32 i

1 30..

i I

4 25 _.

j 22

]

i 20 __

16 5.5 i

15..

14 4

4 2

2 2

10 "

.5 8

8 8

7 7

6 6

5 5._

4 1

1 1

0 0._

+

i l

i

+-

I

~

cycle cycle cycle cycle cycie cyck cycle cycle cycie 95-5 954 96-1 96-2 96-3 96-5 96 7 97-1 97 2 LICEN5ED OPERATOR REQlIALIFICATION 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 Managerlunches.

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

Data Source:

Conner /Guliani(Manager / Source)

Accountability:

Conner /Guliani Trend:

None SEP 68 56

s t

g SROExams Administered O SRO Exams Passed a Ro Exams Administered g ROExams Passed 10..

d i

77 77 77 l

t i

5..

i l

i 1

4 0000 00 00 00 0

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

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 intemally administered quizzes and exams are used to plot the SRO and RO candidates' monthly progress.

During the month of April 1997, there were 7 individuals who passed SRO comprehen-sive wntten exams.

Data Source:

Conner /Guliani(Manager / Source)

Accountability:

Conner /Guliani Trend:

None SEP 68 57

mM'* * "

+ Total CRs 3000 2s00.

j' 2000.

1500.

1000 e A.

g

^

s00.

O P

W r

2 s

s a

s s

s a

a a

a R

E E

5 6

s s

4 4

s i

e e

n n

M Z

O 7

E 2

CONDITION REPORTS BY LEVEL I

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 24 12 103 836 21 73 1079 Closed 11 3

86 909 393 110 1518 176 Condition Roports are classified as READY to CLOSE.

At the end of February 1997, all "OPEN" incident Reports are closed.

Data Source:

Tesar/Burggraf(Manager / Source)

Accountability:

Andrews/Gambhir Trend :

None 58

._.m._-____

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

i 1

j a Totaloutn9eunos j-a MND* MioWo*

l 350 -

i j

300.

MWO HOLDS sy.wn j

250.

Engneemg FWts j

4%

int 200..

150 -

265 15 i

100' NFe/BV 138 Romer 16 %

63%

50.

i j

0-i i

i 1

JarWrt Fet>97 nhr97 Apr.87 i

MWO PLANNING STATUS (CYCLE 18 REFUELING OUTAGE) l This indicator shows the total number of Maintenance Work Requests (MWRs) and Main-i tenance Work Orders (MWOs) that have been approved for inclusion in the Cycle 18 Refueling 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.

Data Source:

Chase / Johnson (Manager / Source)

Accountability:

Chase / Herman Trend:

None SEP 31 59

\\

l j

l i

NO DATA AVAILABLE i

l i

SPECIAL SERVICES ENGINEERING DEPARTMENT OVERALL PROJECT STATUS (Cycle 18 Refueling Outage)

Data Source:

Phelps/Swearngin (Manager / Source)

Accountability:

Phelps/Boughter l

Trend:

None SEP 31 60

i

, ActualMCDate a Tar 9et PRc Date 9/28S7.

e a

a ar29s7 7/30S 7.

6/30S7.

5/31S 7.

5/1/97.

l 4/1/97.

a/2s7.

j 1/31/97.

1/1/97 i

e s

e e

m s

s m

s h !

I.

k.~$

h h i

~

s k..kk

.s

\\

]

PROGRESS OF 1998 REFUELING OUTAGE MODIFICATIONS I

CYCLE 18 1

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 l

to March 20,1997, PRC approved by September 15,1997.

April 1997 Modifications added: 0 Deleted = 0 l

Data Source:

Jaworski/ Walling (Manager / Source)

Accountability:

Gambhir/Jaworski Trend:

None SEP 31 61 i

i

~

\\

)

i No data available for Indicator until a baseline is established.

I i

4 f

s l

PROGRESS OF CYCLE 18 OUTAGE MODS ADDED TO '98 REFUELING OUTAGE AFTER FREEZE DATE This indicator will show the status of modifications approved for installation during the Cycle 18 Refueling Outage. Since the baseline schedule has yet to be established, there is no information available at this time. The goal for this indicator is to have all modifica-l tion packages PRC approved by their target date.

i April 1997 Modifications Added: 0 Deleted = 0 Modifications Pre-Approved: 0 l

Data Source:

Jaworski/ Walling (Manager / Source)

Accountability:

Gambhir/Jaworski Trend:

None SEP 31 l

62

t I

NO DATA AVAILABLE i

PROGRESS OF 1997 ON-LINE MODIFICATION PLANNING This indicator shows the status of modifications approved or in review for approval for on-line installation during 1997. Modifications added to the on-line list after March 20,1997 are not part of this indicator.

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

April 1997 Modifications Added: 0 Deleted = 0 l

)

i Data Source Jaworski/ Walling (Manager / Source)

Accountability:

Gambhir/Jaworski Trend:

None SEP 33 63

lb*

s l

e e

f i

s 1

i t

I 1

l l

l n.

i i

I j

i 1

i ACTION PLANS I

d i

1 i

1 L

n i

64

~

1 ACTION PLANS i

This section lists action plans that have been developed for the performance indicators cited as Adverse Trends during the month preceding this report. Also included are Action l

Plans for indicators that have been cited in the preceding month's report as Needing increased Management Attention for three (3) consecutive months.

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

. 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 Fadnion, it is expected that schedule compliance will also increase and our mrintenance backlog will decrease. This project is scheduled to be fully implemented by July 1997.

i 65

i 4

PERFORMANCE INDICATOR DEFINITIONS AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM CLEAN CONTROLLED AREA CONTAMINATIONS t,1,000 PERFORMANCE DISINTEGRATIONS / MINUTE PER PROBE AREA j

4 1

The sum of the known (planned and unplanned) unavailable The personnel contamination events in the clean controlled I

hours and the estimated unavallable hours for the auxiliary area. This indicator tracks personnel performance for SEP feedwater system for the reporbng period divided by the critical

15 & 54.

hours for the reporung period mulbplied by the number of trains in the auxiliary feedwater system.

CONTAMINATED RADIATION CONTROLLED AREA COLLECTIVE RADIATION EXPOSURE The percentage of the Radiation Controlled Area, which includes the auxlhary building, the radweste building, and i

Collochve radiat.on exposure is the total extemal whole-body areas of the C/RP building, that is contaminated based on the

)

dose received by all oresite personnel (including contractors total square footage. This indicator tracks performance for and visitors) during a time period, as measured by the SEP #54.

thermoluminescent desirneter (TLD). Collechve radiation exposure is reported in units of person-rem. This indcator DAILY THERMAL OUTPUT tracks radiological work performance for SEP #54.

This indicator shows the daily core themtal output as COMPONENT FAILURE ANALYSIS REPORT (CFAR) rneasured from computer point XC105 (in thermal rnegwatts).

SUMMARY

The 1500 MW Tech Spec limit, and the unmet portion of the 1495 MW FCS daily goal for the reporting month are also The summary of INPO categories for Fort Calhoun Station with shown.

~

significantly higher (1.645 standard deviations) failure rates than the rest of the industry for an eighteen-month trne period.

DIESEL GENERATOR RELIABILITY (25 Demands)

Failures are reported as component (i.e., pumps, motors, main steam stop valves, control element motors, etc.) categories.

This indicator shows the number of failures occurring for each emergency desel generator during the last 25 start demands Failure Cause Categories are:

and the last 25 load 4un demands.

Age / Normal Use -thought to be the consequence of DISABLING INJURY /lLLNESS FREQUENCY RATE expected wear, aging, end-of-life, or normal use.

(LOSS TIME ACCIDENT RATE)

Manufacturing Defect - a failure attributable to inadequate This indicator is defined as the number of accidents for all assembly or initial quahty of the responsible component or utility persor.nel permanently assigned to the station, involving system.

days away from work per 200,000 mar @ours worked (100 marwyears). 'Ihis does not include contrador personnel This Engineering / Design - a failure attributable to the indicator tracks personnel performance for SEP #25,26 & 27, inadequate design of the responsible component or system.

I DOCUMENT REVIEW (BIENNIAL)

Other Devices - a failure attributable to a failure or misoperation of another component or system, including The Document Review indicator shows the number of associated devices.

documents reviewed, the number of documents scheduled for review, and the number of document reviews that are overdue MaintenanceIAction resulting from improper for the reporting month. A document revew is considered maintenance, lack of maintenance, or personnel errors that overdue if the revew is not complete within six months of the occur during maintenance activitieson the component.,

assigned due date. This indicator tracks performance for SEP

46.

Testing Action - resulting from improper testing or personnel triors that occur during testing activities.

EMERGENCY AC POWER SYSTEM SAFETY SYSTEM PERFORMANCE Initial Installation Error - caused by improper initiat installatiort of equipment The sum of tne known (planned and unplanned) unavailable and the estimated unavailable hours for the emergency AC CENTS PER KILOWATT HOUR power system for the reporting period divided by the number of hours in the reporting period multiplied by the riumber of The purpose of this indicator is to quantify the economical trains in the emergency AC power system.

operation of Fort Calhoun Station. The cents per kilowatt hour indicator represents the budget and actust cera.s per EMERGENCY DIESEL GENERATOR UNIT RELIABILITY kilowatt hour on a twelve-month average for the current year. The bases for the budget curve is the approved yearly Ttus indcator shows the number or fanu'es that were reported during the budget. The basis for the actual curve is the Financial and last 20, 50, and 100 emergency diesel generator demands at the Fort Operating Report.

Calhoun Station. Also shown are tngger values whch correlate to a high levet or confidence that a unit's diesel generators have obtained a 66

PERFORMANCE INDICATOR DEFINITIONS rehapaty at grenier than or equal to 95% when the dernand failures are Each emergency generator failure that resuks in the generator less than the tnoger values-being declared inoperable should be counted as one demand and one failure.

Exploratory tests during corredive

1) Number of Start Demands: All valid and inadvertent start demands, including all start-only demands and all maintenance and the successful test that follows repair to start demands that are followed by load-run demands, verify operability should not be counted as demands or failures whether by automatic or manual initiation. A start-only when the EDG has not been declared operable again.

J demand is a demand in which the e norgency generator EMERGENCY DIESEL GENERATOR UNRELIABluTY is started, but no attempt is made to load the generator.

This indicator measures the total unreliability of ernergency

2) Number of Start Failures: Any failure within the diesel generators. In general, unreliability is the ratio of 4

emergency generator system that prevents the generator unsuccessful operations (starts or load-runs) to the number of from achieving specified frequency and voltage is valid demands. Total unreliability is a cornbination of start classified as a valid start failure. This includes any unreliability and load <un unreliabihty.

2 condition identified in the course of maintenance inspections (with the emergency 9enerator in standby ENGINEERING ASSISTANCE REQUEST (EAR) mode) that definitely would have resulted in a start failure BREAKDOWN if a demand had occurred.

l This indicator shows a breakdown, by age and priority of the

3) Humber of Lond4un Demands: For a valid load-run EAR, of the rmmber of EARS assigned to Design Engineering demand to be counted, the load-run attempt must meet Nuclear and System Engineering. This indicator tracks one or more of the following criteria:

performance for SEP #62.

A) A load-run of any duration that results from a real ENGINEERING CHANGE NOTICE (ECN) STATUS automatic or manualinitlation.

The number of ECNs that were opened, ECNs that were B) A load-run test to satisfy the plant's load and completed, and open backlog ECNs awaiting completion by duration as stated in each test's specifications.

DEN for the reporting month.

This indicator tracks C) Other special tests in which the emergency generator is expected to be operated for at least one ENGINEERING CHANGE NOTICES OPEN hour while loaded with at least 50% of its design load.

This indicator breaks down the number of Engineering Change Notices (ECNs) that are assigned to Design Er.gineering

4) Number of Load-Run Failures: A load-run failure Nuclear (DEN), System Engineering, and Maintenance. The should be counted for any reason in which the graphs provide data on ECN Facility Changes open, ECN emergency generator does not pick up load and run as Substitute Replacement items open, and ECN Document predicted. Failures are counted during any valid load-run Changes open. This indicator tracks performance for SEP demands.

62.

5) Exceptions: Unsuc.cessful attempts to start or load-run EQUIPMENT FORCED OUTAGES PER 1,000 CRIT 3 CAL should not be counted as valid demands or failures when HOURS i

they can be attributed to any of the following:

Equipment forced outages per 1,000 critical hours is the A) Spurious trips that would be bypassed in the event inverse of the mean time between forced outages caused by of an emergency.

equipment failures. The mean tirne is equal to the number of hours the teactor is critical in a period (1,000 hours0 days 0 hours 0 weeks 0 months ) divided by B) Malfunction of equipment that is not reqv% oring the number of forced outages caused by equipment failures in an emergency.

that period.

C) Intentional termination of a ten because of EQUIVALENT AVAILABiUTY FACTOR abnormal conditions that vNuld not have resulted in major diesel generator ^ amage or repair.

This indicator is defined as the ratio of gross available a

generation to gross maximum generation, expressed as a D) Malfunctions or ryerating errors which would not percentage. Available generation is the energy that can be have preventN the emergency generator from produced if the unit is operated at the maximum power level being restar.ed and brought to load within a few permitted by equipment and regulatory limitations. Maximum minutes.

generation is the energy that can be produced by a unit in a E). A f6ure to start because a portion of the starting system was disabled for test purpose, if followed by a successful start with the starting system in its normal alignment.

67 i

/

._.m.______

_m__

1 J-i j~

b i

1 PERrORMANCE INDICATOR DEFINITIONS i

i FORCED OUTAGE RATE

1) One or more days of sestnched work (excluding the day of

)

i.

the accident);

This indicator ik defined as the percentage of time that the unit

2) One or more days away from work (excludeg the day of

)

was unavailable due to forced events compared to the time the occident); and planned for eledncel generation. Forced events are failures '

3) Fatauties

or other unplanned conditions that require removing the unit from service before the end of the next weekend Forced Contractor personnel are not included for this indicator.

i events include start-up failures and events initiebed while the unit is in reserve shutdown (i.e., the unit is available but not in IN-LINE CHERIBSTRY INSTRURRENTS OUT OF SERVICE i-service).

l 1

Total number of in-line chemistry instruments that are out-of-4 l-FUEL RELIABILITY INDICATOR service in the Secondary System and the Post Accident 6

Samphng System (PASS).

[

l This indscador is defined as the steady-state primary coolant l-131 adulty, conected for the tramp uranium contribution and LICENSE CANDIDATE EXARIS normanzed to a common purtlication rate. Tramp uranium is 1

i fuelwhich has beenef-won reactor core intomals from This indicator shows the number of SRO and/or RO quizzes j

previous defectwo fuel or is present on the surface of fuel and exams that are administered and passed each month.

{

elements from the manufacturing procoes Steady state is This indicator tracks training performance for SEP 868.

j defined as contmuous operation for at least three days at a a

power level that does not very more than + or.5%. Plants LICENSED OPERATOR REQUALIFICATION TRAINING i

i should collect data for this indicator at a power level above

~

85%, when possible. Plants that did not operate at steady.

The total number of hours of training given to end) crew during state power above 85% should coIsct data for this indicator at each cycle. Also provided are the simulator tramme hours j

the highest ";

power level attained during the month.

(which are a subset of the total training hours), the number of '

]

- non-REQUALIFICATION trainmg hours and the number of 1

The density conodion todor is the ratio of the specific volume exam failures. This indicator tracks training performance for ~

l' of coolant at the RCS operating temperature (640 degrees F.,

SEP # 68.

2 Vf = 0.02146) devided by the specille volume of coolant at normal letdown temperature (120' F st outlet of the letdown LICENSEE EVENT REPORT (LER) ROOT CAUSE coolmg heat exchanger, Vf = 0.016204), which results in a BREAKDOWN a

densky conocbon fador for FCS equal to 1.32.

This indicator shows the number and root cause code for GROSS HEAT RATE Liconese Event Reports. The root cause codes are as follows:

j Gross heat rate is defined as the ratio of total thermal energy

1) Administrative Control Problem "... 4 and j

in British Thermal Units (BTU) produced by the reactor to the supervisory deficiencess that affect plant programs or total gross electrical energy produced by the generator in adwities (i.e., poor planning, breakdown or lack of kilowatt-hours (KWH).

adequate management or supervisory control, iriconcet procedures, etc).

HAZARDOUS WASTE PRODUCED

{

2) Licensed Operator Error-This cause code captures The total amount (in Kilograms) of non-halogenated hazardous errors of omesion/comrmssion by licensed reador waste, halogenated hazardous waste, and other hazardous operators during plant activities.

j waste produced by FCS each rnonth.

i

3) Other Personnel Enor Errors of omission / commission l

HIGH PRESSURE SAFETY INJECTION SYSTEIA SAFETY committed by non-licensed personnel involved in plant I

[

SYSTEM PERFORMANCE activities The sum of the known (planned and unplanned) untrailable

4) RAsintenance Problem -The intent of this cause code is hours and the estimated unavailable hours for the high to capture the full range of problems which can be pressure safety injection system for the reporting period attributed in any way to programmatic deficiencies in the divided by the critical hours for the reporting period multiplied maintenance functional organization. Activities included i

by the number of trains in the high pressure safety injection in this category are maintenance, testing, surveillance, j

system.

calibration and radiation protection.

INDUSTRIAL SAFETY ACCIDEN' RATE lNPO

5) Design /ConstructionfinsemilaticWFabrication Problem

(

. This cause code covers a full range of programmatic This indicator is defined as tie number of accidents per deficiencies in the areas of design, construction, 4

200.000 man-hours worked for G utility personnel permanently instaRation, and fabncahon (i.e., loss of control power due j

assigned to the station that result in any of the following:

to undwrrated fuse, equipment not quahfied for the environment, etc.).

i-68 4

b

o PERFORMANCE INDICATOR DEFINITIONS J

6) Equipment Failures (Electronic Piece-Parts or MAXIMUM INDMDUAL RADIATION EXPOSURE Environmental-Related Failurse)-This code is used for spurious failures of electronic piece-parts and failures due The total maximum amount of radiation received by an to meteorological conditions such as lightning, ice, high individual person working at FCS on a monthly, quarterty, and winds, etc. Generally, It includes spurious or one-time annual basis.

failures. Electric components included in this category are circuit cards, rectifiers, bistables, fuses, capacitors, MWO PLANNING STATUS (CYCLE 17 REFUELING oiodes, resistors, etc.

OUTAGE)

LOGGABLE/ REPORTABLE INCIDENTS (SECURITY)

The total number of Maintenance Work Orders that have been approved for inclusion in the Cycle 17 Refueling Outage and The tctal number of security incidents for the reporting month the number that are ready to work (parts staged, planning depicted in two graphs. This indicator tracks security complete, and all other paperwork ready for field use). Also performance for SEP #58.

included is the number of MWOs that have been engineering holds (ECNs, promdures and other mascellaneous engineering MAINTENANCE OVERTIME holds), parts hold, (parts staged, not yet inspected, parts not yet arrived) and planning hold Oob scope not yet completed).

The percent of overtime hours cornpared to normal hours for Maintenance Work Requests (MWRs) are also shown that maintenance. This includes OPPD personnel as well as have been identified for the Cycle 17 Refueling Outage and contract personnel.

have not yet been converted to MWOs MAINTENANCE WORKLOAD BACKLOGS NUMBER OF CONTROL ROOM EQUIPMENT DEFICIENCIES This indicator shows the backlog of non-outage Maintenance Work Orders remaining open at the end of the reporting month.

A control room equipment deficiency (CRD) is defined as any Maintenance classifications are denned as follows:

component which is operated or controlled from the Control Room, provides indication or alarm to the Control Room, Corrective Repair and restoration of equiprnent or provides testing capabihties from the Control Room, provides components that have failed or are malfunchoning and are automatic actions from or to the Control Room, or provides a not performing their intended function.

passive function for the Control Room and has been identified as deficient, i.e., does not perform under all conditions as Proventive - Achons taken to maintain a piece of equipment designed. This definition also applies to the Altemate within design operating conditions, prevent equipment Shutdown Panels Al-179, Al-185, and Al-212.

failure, and extend its life and are performed prior to equipment failure.

A plant componer;t which is deficient or inoperable is considered an " Operator Work Around (OWA) ltem" If some Non-Corroclive/ Plant improvements - Maintenance other action is required by an operator to compensate for the activities performed to implement station improvements or condition of the component. Some examples of OWAs are:

to repair non-plant equipment.

1) The control room levelindicator does not work but a local Maintenance Work Priorities are defined as:

sight glass can be read by an Operator out in the plant; Emergency - Conditions which significantly degrade station

2) A deficient pump cannot be repaired because j

safety or availabihty.

replacement parts require a long !aad time for l

purchase / delivery, thus requiring the redundant pump to immediate Action Equipment deficiencies which be operated continuously; significantly degrade station reliabihty. Potential for unit shutdown or power reduction.

3) Special actions are required by an Operator because of equipment design problems. These actions may be Operations Concern Equipment deficiencies which hinder described in Operations Memorandums, Operator Notes, station operation.

or may require changes to Operating Procedures; Essential-Poutine corrective maintenance on essential

4) Deficient plant equipment that is required to be used station systems and equipment.

during Emergency Operating Procedures or Abnormal Operating Procedures; Non-Essential-Routine corrective maintenance on non-essential station systems and equipment.

5) System indication that provides critical information during normal or abnormal operations.

Plant improvement - Non-corrective maintenance and plant improvements.

This indicator tracks maintenance performance for SEP #36.

69

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

. -. _ ~. ~. - -.

I PERFORMANCE INDICATOR DEriwirious NURSER OF RSSSED SURVEILLANCE TESTS RESULTING This indicator shows the status of the projects which are in the IN LICENSEE EVENT REPORTS scope of the Refueling Outage

{,

The number of SuneeHance Tests (STS) that result in Lkanese PERCENTAGE OF TOTAL MWOs CORIPLETED PER Event Repot (LERs) during the reporting month. This 100 NTH IDENTIFIED AS REWORK indicator tracks missed STs for SEP 860 & 61.

The percentage of total MWOs completed por month identitled Of GINCIDENTREPORTS as rework. Rework actubes are identilled by mantenance planning and crafL Rework is: Any additional work required

- mor displays the total number of open incident to conect deficiencies discovered during a failed Post j

hopv.L i.Hs), the number of irs that are greater than six Maintenance Test to ensure the component / system passes months old and the number of open significant irs.

subsequent Post Maintenance Tool OUTSTANDING 800DIFICATIONS PERCENT OF COtp%ETED SCHEDULED BRAINTENANCE ACTWITIES The number of Modification Requests (MRs) in any state between the lesuance of a Wodificebon Number and the The percent of the number of completed memtenance complebon of the drawing update.

actMties as compared to the number of scheduled mantenance actMbes each month. This percentage is shown

1) Fo:m TC-1133 3ecidogan Progrees. This number for au maintenance crafts. Also shown are the number of represents modilicebon requests that have not been plant emergent MWOs Maintenance actMbos include MWRs, approved during the reporting month.

MWOs, STs, PMOs, cabbrations, and other stuscellaneous actMeios. This indicator tracks Maintenance performance for

2) Modification Requests Being Reviewed. This category SEP #33.

lach"8**

PERFORMANCE INDICATOR INDEX A) Modificebon Requests that are not yet reviewed.

This indicator inder is <=leni=wi from a weighted combinabon

8) Modification Requests being reviewed by tne of eleven performance indicator values, which include the Nuclear Projects Revow Committee (NPRC).

following: Unit Capabihty Factor, Unit Capability Loss Fado",

HPSI, AFW, Emergency AC Power System, Unplanned C) Modificebon Requests being reviewed by the Automabc Scrams, Collective Radiation Exposure, Fuel Nuclear Projects Committee (NPC).

Reliabihty, Thermal Performance, Secondary System Chemistry, and Industria: Safety Accedent Rate.

These Modification Requests may be reviewed several times before they are approved for accomphshment or cancaled PREVENTABLE /PERSONN0, ERROR LERs Some of these Modificebon Requests are retumed to Engineering for more information, some approved for This indicator is a breakdown of LERs. For purposes of LER ovaluation, some approved for study, and some approved for event classsficebon, a *Proventable LER* is defined as:

planning. Once planning is completed and the scope of the work is clearly defined, these Modificebon Requests may be An event for which the root cause is personnel error (i.e.,

approved for accomplishment with a year assigned for mappropnets adion by one or more indmduais), inadequate construchon or they may be canceled. All of these different admmestrative controls, a design construchon, installation, phases require review installation, fatmcation problem (invoMng work completed by or supervised by OPPD personnel) or a maintenance

3) Design Engineering Backlog 4n Progrees. Nuclear problem (attributed to inadequate or improper upkeep / repair j

Planning has assigned a year in which construchon will of plant equpment). Also, the cause of the event must have i

be swC M and design work may be in progress.

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

4) Construction Backlog 4n Progrees. The Constniction attnbuted to a problem with the original design of the plant Package has been issued or construction has begun but would not be considered preventable).

the modificatiot, 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 4n Progress.

PED has received the Modifustion Completon Report but An event for whidt the root cause is inapptcpriate action on the drawings have not been updated the part of one or more indrviduals (as opposed to being attributed to a department or a general group). Also, the The above menboned outstandmg mochlicebons do not include inappropriate action must have occurred within modificatior.e which are proposed for cancellation.

approximately two years of the " Event Date" specsfied in the LER.

OVERALL PROJECT STATUS (REFUELING OUTAGE) l 70

~

l*

1 PERFORMANCE INDICATOR DEFINITIONS Additionally, each event classifed as a " Personnel Error" NPRDS components with more than two failures for the 1

should also be classified as " Preventable." This indicator eighteen-month CFAR period.

trends personnel performance for SEP ltem #15.

SAFETY SYSTEM FAILURES PRIMARY SYSTEM LITHlUM % OF HOURS OUT OF LIMIT Safety system failures are any events or conditions that 5,ould The percent of hours out of limit are for lithium divided by the prevent the fulfillment of the safety functions of structuies or total number of hours possible for the month.

systerns, if a system consists of multiple re%ndant subsystems or trains, failure of all trains constitutes a safety PROCEDURAL NONCOMPLIANCE INCIDENTS system failure. Failure of one of two or more trains is not (MAINTENANCE) counted as a safety system failure. The definition for the 1

Mdicator parallels NRC reporting requirements in 10 CFR The number of identified incidents concoming maintenance 50.72 and 10 CFR 50.73. The following is a list of the major procedural problems, the number of closed irs related to the safety systems, sub-systems, and components monitored for use of procedures (includes the number of closed irs caused this indicator by procedural noncompliance), and the number of closed

]

procedural noncomphance irs.

This indicator trends Accident Monitoring instrumentaten, Auxiliary (and personnel performance for SEP #15,41 and 44.

Emergency) Feedwater System, Combustible Gas Control, Component Cooling Water System, Containment and i

PROGRESS OF CYCLE 17 OUTAGE MODIFICATION Containment isolation, Containment Coolant Systems, PLANNING Control Room Emergency Ventilation System, Emergency Core Cooling Systems, Engineered Safety Features This indicator shows the status of modifications approved for Instrumentation, Essential Compressed Air Systems, completion during the Refueling Outage.

Essential or Emergency Service Water, Fire Detection or

{

Suppression Systems, Isolation Condenser, Low PROGRESS OF 1995 ON4.INE MODIFICATION PLANNING Temperature Overpressure Protection, Main Stearn Line Isolation Valves, Onsite Emergency AC & DC Power This indicator shows the status of modrfications approved for w/ Distribution, Radiation Monitoring instrumentation, completion during 1995.

Reactor Coolant System, Reactor Core isolation Cooling System, Reactor Trip System and instrumentation, RADIOLOGICAL WORK PRACTICES PROGRAM Recirculation Pump Trip Actuation instrumentation, Residual Heat Removal Systems, Safety Valves, Spent The number of identifed poor radiological work prachces Fuel Systems, Standby Uquid Control System and Ultimate (PRWPs) for the reporting month. This indicator tracks Heat Sink.

radiological work performance for SEP #52.

SECONDARY SYSTEM CHEMISTRY PERFORMANCE RATIO OF PREVENTIVE TO TOTAL MAINTENANCE &

INDEX PREVENTIVE MAINTENANCE ITEMS OVERDUE The Chemistry Performance Index (CPI) is a calculation based The ratio of preventive maintenance (including surveillance on the concentration of key impunties in the secondary side of testing and calibration procedures) to the sum of non-outage the plant. These key impuribes are the most likely cause of corrective maintenance and preventive maintenance deterioration of the steam generators. Criteria for calculating mLJ over the reporting penod. The ratio, expressed as the CPI are:

a percentage, is calculated based on man-hours. Also displayed are the percent of preventive maintenance items in

1) The plant is at greater than 30 percent power, and the month that were not completed or administratively closed by the scheduled date plus a grace period equal to 25% of the

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

scheduled interval.

This indicator tracks preventive maintenance activities for SEP 841.

The CPI is calculated using the following equation:

RECORDABLE INJURY /lLLNESS CASES FREQUENCY CPI = ((sodium /0.79) + (Chloride /1.52) + (Sulfate /1.44) +

RATE (tron /3.30) + (Copper /0.30)+(Condensate 02/2.90))/6 i

The number of injuries requiring more than normal first aid per Where: Sodium, sulfate, chloride and condensate dissolved 200,000 man-hours worked. This indicator trends personnel oxygen are the monthly average blowdown concentrations in performance for SEP #15,25 and 26.

ppb, iron and copper are monthly time weighted average feedwater concentrations in ppb. The denominator for each of REPEAT FAILURES the five factors is the INPO medan value. If the monthly average for a specific parameter is less than the INPO median The number of Nuclear Plant Reliability Data System (NPRDS) value, the median value is used in the calculation.

components with more than one failure and the number of SIGNIFICANT EVENTS 71

1 1

o PERFORMANCE INDICATOR DEriniTiONs Significant events are the events identified by NRC staff Tests, Maintenance Procedures Calibration Proce(ures, through detailed screening and evaluation of operating Special Procedures or Operating Procedures are not exponence. The screening process includes the daily review consdered as temporary modifications unless the jumper and discussion of all reported operating reactor events, as well or block remains in place after the test or procedure is as other operatonal data such as special tests or construction complete. Jumpers and blocks instahed in test or lab activibes. An event identified from the screening process as inst'uments are not considered as temporary a significant event canddate is further evaluated to determine modifications.

If any actual or potential threat to the health and safety of the public was involved. Specific examples of the type of cnteria

3) Scaffold is not considered a temporary modification.

l are summarized as follows:

Jumpers and blocks which are installed and for which MRs have been submitted will be considered as temporary j

1) Degradation of important safety equipment; modifications until final resolution of the MR and the I

jumper or block is removed or is permanentry recortled on i

2) Unexpected plant response to a transient; the drawings.

This indicator tracks temporary modificatens for SEP $62 and 71.

3) Degradation of fuel integrity, pnmary coolant pressure boundary, important associated features; THERMAL PERFORMANCE

4) Scram with complicaten; The ratio of the design gross heat rate (corrected) to the adjusted actual gross heat rate, expressed as a percentage.

5) Unplanned release of radioactivity; UNIT CAPABILITY FACTOR

6) Operation outside the limits of the Technical Specrficatione; The rato of the available energy generation over a given time period to the reference energy generation (the energy that

7) Other.

Could be produced if the unit were operated continuously at full power under reference amtssnt conditions) over the same 5me (NPO significant events reported in this indicator are SERs period, expressed as a percentage.

(Significant Event Reports) which inform utilities of significant events and lessons lemmed identified through the SEE-IN UNIT CAPACITY FACTOR screening process.

The net eledncal energy generated (MWH) divided by the SPARE PARTS INVENTORY VALUE product of maxrnum dependable capacity (net MWe) times the gross hours in the reporting period expressed as a percent.

The dollar value of the spare parts inventory for FCS during Net electrical energy generated is the gross electrical output the reporting penod.

of the unit measured at the output terminals of the turbine generator minus the normal station service loads du'ing the STAFFING LEVEL gross hours of the reporting period, expressed in megawatt

hours, The actual staffing level and the authorized staffing level for the Nudear Operations Division, The Produchon Engineering UNPLANNED AUTOMAT:0 REACTOR SCRAMS PER 7,000 Division, and the Nuclear Services Division. This indicator CRITICAL HOURS tracks performance for SEP #24.

This indicator is defined as the number of unpianned automatic STATION NET GENERATION scrams (RPS logic actuations) that occur per 7,000 hours0 days 0 hours 0 weeks 0 months of critical operation.

The net generation (sum) produced by the FCS during the reporting month.

The value for this indicator is calculated by multiplying the total number of unplanned automatic reactor scrams in a specific TEMPORARY MODIFICATIONS time period by 7,000 hours0 days 0 hours 0 weeks 0 months , then di.'iding that number by the total number of hours entical in the same ikne period. The The number of temporary mechanical and electrical indicator is further defined as follows:

configurations to the plant's systems.

1) Unplanned means that the teram was not an anticipated

1) Temporary configurabons are defined as electrical part of a planned test.

jumpers, electrical blocks, mechanical jumpers, or mechanical blocks which are installed in the plant

2) Scram means the automatic shutdown of the reactor by a operating systems and are not shown on the latest revision rapid inserton of negative reactivity (e.g., by control rods, i

of the P&lD, schematic, connection, wiring, or flow liquid injection system, etc.) that is caused by actuation of l

diagrams, the reactor protection system. The signal may have i

resulted from exceeding a set point or spurious.

2) Jumpers and blocks which are installed for Surveillance 1

72 l

E

l PERFORMANCE INDICATOR DEFINITIONS

3) Automatic means that the initial signal that caused VOLUME OF LOW-LEVEL SOLID RADIOACTIVE WASTE actuation of the reactor protection system logic was provided from one of the sensors irana,..,g plant This indicator is defined as the volume of low-level solid parameters and condebons, rather than the manual scrcm radioactive waste actualty shipped for burial. This indicator swildas or, manual turbine trip switdes (or push-buttons) al:;o shows the volume of low-level radioactive waste which is J

provided in the main control room.

in temporary storage, the amount of radioec6ve oil that has been shipped off-site for processeng, and the volume of solid

4) Critical means that during the steady-state condition of the dry radioactive waste which has been shipped off-site for reactor prior to the scram, the effective multplication (k,

processing. Love-level solid radioec6ve waste consists of dry

) was essentially equal to one, ac6ve waste, sludges, resins, and evaporator bottoms generated as a read of nuclear power plant operanon ard UNPLANNED CAPABILITY LOSS FACTOR maintenance. Dry radioactive waste indudes contaminated rags, cleaning matermis, reara==M= protec8ve c6athing, plas6c The ratio of the mplanned energy hanaa during a given period containers, and any other material to be disposed of at a low-of 1.me, to the reference energy generation (the energv that level radioac6ve waste disposal site, except resin, sludge, or could be produmd if the unit were operated continuously at full evaporator bottoms. Low-level refers to all radioective waste power under reference ambient exandibons) over the same #me that is not spent fuel or a by-product of spent fuel processing.

period, expressed as a percentage.

This indicator tracks radiological work performance for SEP es4.

)

UNPLANNED SAFETY SYSTEM ACTUATIONS. (INPO

+ DEFINITION) j This indicator is defined as the sum of the followingl Safety

)

system actuations.

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

4 1

2) The number of unplanned emergency AC power system actuabons that result from a loss of power to a safeguards bus. An unplanned safety system actuation occurs when an actuation set point for a safety system is reached or when a spurious or inadvertent signal is generated (ECCS only), and major equipment in the system is actuated.

Unplanned means that the system actuation was not part of a planned test or evolubon. The ECCS actuations to be counted are actuations of the high pressure injection system, the low pressure injection system, or the safety injed>on tanks.

j UNPLANNED SAFETY SYSTEM ACTUATIONS -(NRC DEFINITION)

The number of safety system actuations which indude (QD.X)

I the High Pressure Safety injection System, the Low Pressure Safety injection System, the Safety injection Tanks, and the Emergency Diesel Generators. The NRC dass4fication of safety system actuations indudes actuations when major equipment is operated 30g when the logic systems for the above safety systems are challenged.

V.OLATION TREND This indicator is defined as Fort Calhoun Station Cited Violabons and Non-Cited Violations trended over 12 months.

Additionally, Cited Violations for the top quartile Region IV plant is trended over 12 months (lagging the Fort Calhoun Station trend by 2-3 months). It is the Fort Calhoun Station goal to be at or below the dted violation trend for the top quartile Region IV plant.

73

1

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

SEP Reference Number 15 Eaga e ir. crease HPES and IR Accountability through use of Performance Indicators Procedural Noncompliance 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 Reference Numbers 25. 26. & 27

. Training Program for Managers and Supervisors implemented

. Evaluate and implement Station Standards for Safe Work Practice Requirements

= implement Supervisory Enforcement of industrial Safety Standards Disabhng injury / illness Frequency Rate....................................... !.... 15 Recordable injury / Illness Cases Frequency Rate.....................................

16 SEP Refemnce Number 31

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

............. 59 SSED's Overall Project Status................................................. 60 Overall Project Status (Cycle 17 Refueling Outage)

.............. 61 Progress of Cycle 17 Outage Modification Planning

.......... 63 SEP Reference Number 33

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

........ 62 SEP Reference Number 36

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

......... 39 SEP Reference Numbers 41 & 44

. Develop and implement a Preventive Maintenance Schedule

. Compliance With and Use of Procedures Ratio of Preventive to Total Maintenance & Preventive Maintenance items Overdue 40 Procedural Noncompliance incidents (Maintenance)..

... 43 SEP Reference Number 46

. Design a Procedures Control and Administrative Program Document Review.

... 48 74 l

~

l.

r I

SEP Reference Number 52 ERSR i

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

.. 47 l

SEP Reference Number 54

. Complete implementation of Radiological Enhancement Program Clean Controlled Area Disintegrations >1,000 Counts / Minute Per Probe Area

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

............. 11 i

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

12 l

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

........ 46 4

SEP Reference Number 58 I

. Revise Physical Security Training and Procedure Program Loggable/ Reportable incidents (Security) 49 SEP Reference Numbers 60 & 61

. Improve Controls Over Surveillance Test Program

. Modify Computer Program to Correctly Schedule Surveillance Tests Number of Missed Surve;:!ance Tests resulting in Licensee Event Reports..

23 SEP Reference Number 62 Establish interim System Engineers

)

Temporary Modifications......

50

)

Engineering Assistance Request (EAR) Breakdown

........... 52 4

Engineering Change Notice Status.

.... 53 Engineering Change Notices Open.....

...... 54 j

SEP Reference Number 68

. Assess Root Cause of Poor Operator Training and establish means to monitor Operator Trsining 2

I License Operator Requalification Training....

.. 56 4

t License Candidate Exams 57 SEP Reference Number 71 Improve Controls over Temporary Modifications l

Temporary Modifications..

.... 50 75

e REPORT DISTRIBUTION l lST R. L. Andrews T. J. Mcivor G. C. Bishop K. A. Miller C. E. Boughter P. A. Mruz C. J. Brunnert R. J. Mueller J. W. Chase R. L. Plott R. G. Conner W.J.Ponec M.R. Core D. G. Ried T. R. Dukarski M. J. Sandhoefner M. L. Ellis F. C. Scofield i

H. J. Faulhaber H. J. Sefick S. K. Gambhir R. W. Short J. K. Gasper J. L. Skiles W. G. Gates R. D. Spies (2)

S. W. Gebers D. E. Spires R. H. Guy M. A.Tesar A. L. Hale J. J. Tesarek W. R. Hansher J. W. THis K. R. Henry D. R. Trausch J. B. Herman L. P. Walling R. L. Jaworski G. R. Williams J. W. Johnson D. D. Kloock M. Edwards (7)

L.T.Kusek C. J. Linden B. R. Livingston l

76

ML20141M015

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