Text

Performance Indicators Rept, for July 1997
	ML20216D037
Person / Time
Site:	Fort Calhoun
Issue date:	07/31/1997
From:	; OMAHA PUBLIC POWER DISTRICT
To:	;
Shared Package
ML20216D035	List: LIC-97-0144, Forwards Fort Calhoun Station Performance Indicators Rept, for July 1997; ML20216D037;
References
	NUDOCS 9709090195
	Download: ML20216D037 (90)
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FORT CALHOUN STATION PERFORMANCE INDICATORS JULY 1997 SAFE OPERATIONS PERFORMANCE EXCELLENCE COST EFFECTIVENESS U$0'$00No!0$$00s R PDR

8 6 e

OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT July 1997 1

Engineering and Operations Support Division Nuclear Licensing I

1 i

l Table of Contents / Summary ,

i e

TABLE OF CONTENTS /

SUMMARY

. . . . . . . . . . . . . . . . . . . . . . . . . . . . .1.lii. . . . . . . . . .

MONTH LY OPERATING RE PORT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iv WANO PERFORMANC E INDEX TREND . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . y WANO PERFORMANCE INDEX lNDICATOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vi

.WANO PERFORMANCE INDICATOR TRENDS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vil FORT CALHOUN STATION REPORT

SUMMARY

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , , . . vill NUCLEAR PROGRAM GOALS AND OBJECTIVES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , ix WAND PERFORMANCE INDICATORS U nit C a pa bility F actor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Unplanned Capability Loss Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Unplanned Automatic Reactor SCRAMS per 7000 Hours . . . . . . . . . . . . . . , . . . . . . . . . . . . . . , . . . . . . 4 High Pressure Safety injection System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 Auxiliary Feedwater System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Emergency AC Power System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 The rmal P e rforman ce . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Fuel R eliability indicator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 Second ary System C hemistry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Collective Radiation Exposure . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 Industrial Safety Accident Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 Volume of Low level Radioactive Waste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 SAFE. OPERATIONS Disabling injury / Illness Casas Frequency Rate . . . . . . . . . . , .. .................. ... 15 Recordable injury / Illness Cases Frequency Rate . . . . . . . .. ... .................... .. 16 Clean Controlled Area Contaminations

> 1.000 Disintegrations / Minute per Probe Area .....,.... .. ....... , ,.. ... .. .. . 17 Preventable / Personnel Error LERs . ..... ......., , .. ... . ....... ... ... . 18 i

Table of Contents / Summary Saf.ty sy si.m Faiiu res . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i g Maximum individual Radiation Exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 Violation Trend . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 i l

Sig nificant E ven ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 Missed Surveillance Tests Resulting in LERs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 PERFORMANCE Station Net Generation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 Forced Outage Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . 26 i

l U nit Capacity Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 7 Equivalent Avallability Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 8 Unplanned Safety System Actuations I N PO Definition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 9 N R C Defin ition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 30 G ros s Heat Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 Daily Thermal Output .............,................................................ 32 Equipment Forced Outages per 1,000 Critical Hours . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33 Chemistry Action tevels Exceeded Event Days . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 Primary System Lithium % Hours Out of Limit ... ........,,........ ................... 35 COST Cents Per Kilowatt Hour . . . . . , , , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 37 DlVislON AND DEPARTMENT PERFORMANCE INDICATORS Maintenance Workload Backlogs (Corrective Non-Outage) .............,, ,,...,,.............. 3g Ratio of Preventive to Total Maintenance ............ ..................... ,.... 40 Percentage of Total MWOs Completed per month identified as Rework . . . . , . . . , . . . . , . 41 Ov e rtime . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 2 Procedural Noncompliance incidents . . . . . . . . . . . . . . . . . , ................. ...... 43

!n-Line Chemistry Instruments Out-of Service .... ....,..................... ........... 44 il

Table of Contents / Summary Hazardous Weste Produced . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 5 Contaminated Radiation Controlled Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 Radiological Work Practices Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 7 Docu me nt R eview . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 8 Loggable/ Reportable incidents (Security) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49 l

Temporary Modifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 Outstanding Modifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 Engineering Assistance Request (EAR) Breakdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 Engineering Change Notices Status....................................................................53 Open . . . . . . . . . . . . . . . . . . . . . .

............................................ 54 Licensee Event Report (LER) Root cause Breakdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55 Licensed Operator Requalification Training ...........,................................. 56 License Candidate Exams . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . 57 Condition R eports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . 58 Cycle 18 Refueling Outage MWO Planning Status . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 59 Overall Project S tatus . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 Outage Modification Planning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 On-Line Modification Planning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 62 Progress of i997 0n-Line Modification Planning . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . , , , 63 ACTION PLANS. DEFINITIONS. REP INDEX & DISTRIBUTION LIST Action Plan s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64 Performance indicator Definitions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 66 Safety Enhancement Program index ........,...........................,............. 74 Report Distribution List ................ .............. . ............... ......... . 76 ill

FORT CALHOUN STATION JULY 1997 Monthly Operating Report i

t l

QPERATIONS

SUMMARY

The Fort Calhoun Station (FCS) produced 351.0 million kWh or 37% of the District's i

monthly net generation. The station operated at a nominal 100% power until July 10, when the reactor power was reduced to 95% to facilitate scheduled Screen Wash Pump repairs. Repairs were completed and reactor power reached 100% on July 12, and remained there through the end of the month.

iv

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WANO PERFORMANCE INDEX TREND The Wano Performance Index Trend calculation is made up of eleven variables each weighted to arrive at an overallindex 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, high pressures safety infection, auxiliary feedwater, emergency AC power, 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 HPsi AFW EACP CRE UAs7 FRf CPI TPI ISAR WANO PERFORMANCE INDEX INDICATORS This graph shows the difference between the Maximum No. of points for each WANO indicator and the actual value acheved by Fort Calhourt The current graph shows the diherence between June 17 and July '97.

UCF Unit Capability Factor TPI Thenna! Performance :ndicator UCLF Unplanned Capability Loss Factor CPI Secondary Chemrstry indicator HPSI High Pressure Safety injecbon ISAR IndustrialSafety AcodentRate AFW Auxiliary Feedwater EACP Emergency AC Power UAS7 Unplanned Auto Scrams /7000 Hours CRE Collective Radiation Expcsure FR1 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.

vi

l WANO PERFORMANCE INDEX TRENDS.

(As compared to previous month)

)

i Unit Capability Factor No Change Unplanned Capability Loss Factor Slight Decrease High Pressure Safety injection No Change Aux. Feedwater System No Change Emergency AC Power Decreased '

Collective Radiation Exposure Decreased "

Unplanned Automatic Reactor Scrams No Change Fuel Reliability Decreasing Chemistry Indicator Decreasing Thermal Performance Decreased Industrial Safety Accident Rate No Change vil

FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT July 1997-

SUMMARY

POSITIVE TREND REPORT The following performance indicators exhibited adverse trends for the reporting A performance indicator with data month, representing three consecutive months of Maintenance Workload Backloas improving performance or three consecutive (Page 39) months of performance that is superior to I

the stated goalls exhibiting a positive trend INDICATORS NEEDING INCREASED per Nuclear Operations Division Quality MANAGEMENT ATTENTION REPORT Procedure 37 (NOD-QP-37).

A performance indicator with data for the The following performance indicators reporting period that is inadequate when

exhibited positive trends for the reporting compared to the OPPD goalis defined as month: 'Needing increased Management Attention

per (NOD-QP-37).

Unolanned Automatic Reactor Scrams (Page 4) Fuel Reliability Indicator Industrial Safety Accident Rate (Page 12)

Recordable Inlurv/ Illness Freauency Rate Unolanned Safety System Actuations (Page 16)

E' Clean Controlled Area Contaminations In-l_Ine Chemistry Instruments Out-OF-Service (Page 17)

(Page 44) '

Cents Per Kilowatt Hour ADVERSE TREND REPORT (Page 37)

A performance indicator with data Maintenance overtime representing three consecutive months of (Page 42) declining performance or three consecutive months of performance that is trending Hazardous Waste Produced toward declining as determi w d by the (Page 45)

Manager - Nuclear Licensing, constitutes an adverse trend per Nuclear Operations Contaminated Radiation Controlled Area Division Quality Procedure 37 (NOD-QP- (Page 46) 37). A supervisor whose performance indicator exhibits an adverse trend by this Outstandina Modifications definition may specify in written form (to be (Page 51) published in this report) why the trend is not adverse.

viii l

l

~

NUCLEAR PROGRt.A 1 1997 GOALS AND 0" . sTIVES FUTURE FOCUS and RELATIOl THIP to CHANGE I

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

We must KNOW OUR COSTS to CON 1ROL COSTS Understanding cost is essential to controlling it, and controlling cost is essential to competing in today's market.

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

Individuals at alllevels 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 l still maintaining the highest levels of safety and reliability. Communicating is our key to l 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, ix

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.

OBJECTIVE 11:

No challenges to a nuclear safety systems.

03JECTIVE 12:

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

OBJECTIVE 13:

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

OBJECTIVE 14:

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

OBJECTIVE 15:

Zero Lost Time injuries and recordable injuries rate BELOW 1,5 percent.

x

OPPD NUCLEAR ORGANIZATION GOAL 8 ,

.1997 Prioritica Goal 2: PERFORMANCE Supports: April 1996 Corporate 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, reliable and coat effective power production.

1997 PRIORITIES: l

. Improve Quality, Professionalism and Teamwork.

j

. Maintain High Plant Reliability. '

Pursue efficient, cost-effective work processes.

. Meet or exceed INPO key parameters. l 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:

OBJECTIVE 2-1:

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

OBJECTIVE 2 2:

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

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

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

Line managers through pelunal involvement in training emphasize the importance of conducting activities within s 9 roved procedu s/ 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 prograrn to provide a status of intemal accreditation assessments.

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

xi

4 OPPD NUCLEAR ORGANIZATION GOAL')

1997 Prioritita Goal 2: PERFORMANCE (Continued)

OBJECTIVE 2 3:

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

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

i OBJECTIVE 24:

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

OBJECTIVE 2 6:

'femmwork 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, Ob}ective: 1, 3, and Goal 5, Objective: 1 Operate Fort Calhoun cost effectively to contribute to OPPD's bottom line". Cost consciousness is exhibited at alllevels of the organization.

1997 Priorities:

Maintain total O&M and Capital Expenditures within budget.

. Streamline work process to improve cost effectiveness.

. Implement Opportunity Review recommendations.

Objectives to support COSTS:

OBJECTIVE 3-1:

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

OBJECTIVE 3 2:

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

Goals Source: Lounsberry (Manager) .

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WANO PERFORMANCE INDICATORS 1

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0% m Aug Sep Oct Nov Dee Jon Feb Met Apr May June July UNIT CAPABILITY FACTOR This indicator shows the plant monthly Unit Capability Factor (UCF) value, a rolling 12-month avera08, 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, expressed as a percentage.

The UCF for July 1997 was reported as 100%. The year to-date UCF was also reported as 87.4%, the UCF for the last 12 months (August 1996 through July 1997) was 73.6%,

and the 36-month average (August 1994 through July 1997) was reported as 81.5%.

Enemy Losses:

Forced Outage -Circumferential cracking of a weld down stream of a moisture separator due to high system stresses, Event Period: May 28 thru Mav 291997.

. Forced Outage - Steam leak in the fourth stage extraction steam system, Evern Feriod: April through mid May 1997.

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

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

. Forced Outage - MOV-CV leakage, Event Period: Dec.1996 The Year 2000 WANO industry goal is 87% and the industry current best quartile value is approximately 85%. The 1997 Fort Calhoun annual goal for this indicator is a minimum of 90.0%.

The maximum index point value for this indicator is 16. At the end of the July 1997, the FCS Value was 12.48. This compares to the previous month's value 12.48.

Data Source: Generation Totals Report & Monthly Operating Report Accountability: Chase Trend: None 2

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Aug 88P Oct Nw Dec Jan Feb Mar Apr May Juno. July 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. Energy losses are considered to be unplanned if they are not scheduled at least four weeks in advance.

The UCLF for the month of July 1997 was reported as 00.0%. The year-to-date UCLF was 14.7%, the UCLF for the last 12 months (August 1996 through July 1997) was 9.92%,

and the 36 month average UCLF (August 1994 through July 1997) was reported as 8.5%

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 July 1997 the FCS Value was 11.99. This compares to the previous month's value of 12.00.

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

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+ FCS C: actor 8:tems P:t 7.000 H :ts Criticalfor lati30 mo;the

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: 5 5 5 5 5 Aug Sep oct Nov Dec Jan Feb Mar Apr May June J .ly FCS Reactor scrams .1997 4..

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0 0 0 0 0 0 0 0 0 0 0 0 0 95 94 Aug Sep oct Nov Dec Jan Feb Mar Apr May June July UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7000 HOURS CRITICAL The upper graph shows the 12-month rolling average, the 36-month average, the OPPD goal for 1997 and the Year 2000 WANO goal. The lower graph shows the number of unplanned automatic reactor scrams that occurred during the last 12 months. This indicator is defined as the number of unplanned automatic 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 July 1997. The 12-month ' ' ling average (August 1996 through July 1997) was 0. The 36-month value (August t ' through July 1997) was 0.310.

The 1997 Fort Calhoun Station goal for this indicator is 0. The Year 2000 WANO industry goalis a maximum of one unplanned automatic 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 July 1997, the FCS Value was 8.0. This compares to the previous month's value of 8.0.

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

Accountability: Chase

-Trend: Positive 4

m Monthly HPSI System Ursvaliability Value

+ 12 Month Rolling Av; rap ,

.-e Fort Calhoun Goal (0.003)

+ Year 2000 WANO Industry Goal (0.025 -

0.02 ,. - ; ; ; ; ; ; ; ; ; ; ; ;

0.015 -

?

I

, 0.01 -

0.005 -

e : : : : : : : : : :

0 x ,, , x ,

1996 Aug sep Oct Nov Dec Jan Feb Mar Apr May June July HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE j' This indicator shows the High Pressure Safety injection (HPSI) System unavailability

) value, ar defined by INPO in the Safety System Performance Indicator Definitions, for July i 1997.

l The HPSI System unavailability value for the month of July 1997 was 0.0. There were 0.0 hours0 days 0 hours 0 weeks 0 months of planned unavailability, and 0.0 hours0 days 0 hours 0 weeks 0 months of unplanned unavailability, during the month. The 12 month rolling average was (August 1996 through July 1997) was 6.66E-5, and the year-to-date HPSI unavailability value was 7.0xE-4 at the end of the month.

For the previous year there was a total of 1.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of planned unavailability and 0.0 hours0 days 0 hours 0 weeks 0 months of unplanned unavailability for the HPSI system.

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

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

Data Source: Phelps/Schaffer (Manager / Source)

Accountability: Phelps/Schaffer Trend: None F

e Auxhary Feedwater System Unsvallability

-x- 12 AFW Unavailability i

-+- Year Fort2000 Cahoun WANOIndustry Goal (0.01) Goal (0.025) l a02s . naz:

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

am. . . .

o.oines 0.05ess O.05m4 o nodi 11 c.0022s 1 o amm

,bx ,

, ; k; 1997 Aug Sep Oct Nov Dec Jan Feb Mar Apr May June July AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Auxiliary Feedwater (AFW) System Unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for the month of July 1997.

~

The AFW System Unavailability Value for July 1997 was 0.00228 hours. There were 3.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of planned and 0.00 hours0 days 0 hours 0 weeks 0 months of unplanned unavailability during the month. The 12 I

month rolling average (August 1996 through July 1997) was 0.00449, and the year-to-date unavailability value was 0.00515 at the end of July 1997.

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

The Year 2000 WANO industry goal is 0.025.

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

t Data Source: Phelps/Fritts (Manager / Source)

Accountability: Phelps/Fritts Trend: None 6

i .

m Conthly Emergency AC P:wer Un;v:llability V:lu)

-x.- Yoct t3 Date Emer0:ncy AC Prwer Un;vtilabilityValue -

+ Fort Calhoun ooal(0.024)

+ Year 2000 WANO Industry ooal(0.025) 0.035 .

0.03 -

0.028 0.02 .

0.016 .

0.01 . x x --x x x--

x x E, ,E,m,E E, , ms E,m, ,

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

The Emergency AC Power System unavailability value for July 1997 was 0.038. During the month, there were 55.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of planned unavailability (15.1 for DG-1 and 40.7 for DG-2), and 0.0 hours0 days 0 hours 0 weeks 0 months of unplanned unavailability for testing and repairs. The Emergency AC Power System unavailability value year-to-date was 0.013 and the value for the last 12 months (August 1996 through July 1997) was 0.011.

There have been 132.8, hours year to date, (55.05 for DG-1 and 77.75 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 188.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of planned unavailability and 3.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months of unplanned unavailability for the emergency AC power 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 goalis 0.025.

The maximum index point value for this indicator is 10. At the end of July 1997, the FCS Value was 7.88 This compares to the previous month's value of10.

Data Source: Phelps/Ronning (Manager / Source)

Accountability: Phelps/Ronning Trend: None 7

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

. m MonthlyThermalPerf:rmancs j i

.12 Month Rolling Average 4

+ Fort Calhoun Goal (99.6%)

l + Year 2000 WANO Industry Goal (99.5%)

1

' 100% .

. .. 1~~

z ; - - -

99% .

1996 RFo j 98%

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

i l THERMAL PERFORMANCE

)

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

l The thermal performance value for the month of July 1997 was 100%.

l The year to date value was reported as 99.9%.

The 12 month rolling average (August 1996 through July 1997) was reported as 99.8%.

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

l The Year 2000 WANO industry goal is 99.5%.

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

Value was 5.55 This compares to the previous month's value of 6.00.

l

Data Source: Phelps/Naser(Manager / Source)

! Accountability: Phelps/Naser i Trend: None i

! 8 l

\

m F o o l Q c ila b ilit y(E .4 )

+ Yc er 2000 Q AN O O sel (8 a 10 4 d icrocurie st3 re m)

--.e-. 19 9 7 0 e s t 147 E -4 320 e s e.i e 2 8 0 ,,,T, , ,, ,

240 --

200 --

160 -- 1996 120 + RFO 80 --

22.s as '

2 40 -- 16.i i s .s ,5.3 ,,,,

g 4s

- - - - e m E I I 5 } $ 4 8 $ k I j k FUEL RELIABILITY INDICATOR The coolant activity data analysis through July 31,1997 shows the presence of 10 leaking rods at core average power of 27 leaking rods at lower core power levels. The Xe 133 activity increased in July 1997 indicating that additionalleakers have opened in the Cycle 17 core since the June 1997 data evaluation, The cesium data indicates that the leaking fuel is in a mixture of second and third cycle bumed fuel (Batches S and T) which have the original grid design. The monthly FUEL RELIABILITY INDICATOR (FRI) for July 1997 was 45 x E-04 microcuries/ gram based on the steady state data from July 1 through 31,1997. This is an increase from the June 1997 FRI of 35 x microcuries/ gram e-04 m!crocuries/ gram. The plant operated 9. an average of 100% power through the entire month of July.

The Cycle 17 monthly FRI is trending lower than the Cycle 16 FRI due to the large contribution of the lodine-134 from the " recoil" Uranium. The lodine-134 activity is released to the coolant from the recoil activity that is plated out on fuel assembly surfaces due to fuel failures, in prior cycles.

In the FRI equation, the lodine-134 activity is subtracted from the lodine-131 activity. This cycle, the recoil activity is trending two times higher than Cycle 16 while the lodine-131 is trending similar to the Cycle 16 values at the same point in the cycle. Consequently, the Cycle 17 calculated FRI value is trending lower.

Based on the number of predicted fue! failures at lower core power levels and the expectation that future fuel failures will be identified, this performance category is to be considered POOR for the second quarter of 1997.

The 1997 Fort Calhoun Station FRI Performance Indicator goalis to maintain FRI below 147 E-4 microcuries/ gram. This goal is based upon previous cycles fuel performance, results of the most recent fuel inspection 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 indicator is 8. At the end of the July 1997, the FCS Value was 2.13. This compares to the previous month's value of 2.80.

Data Source: Guinn/Guliani Accountability: Chase /Stafford Trend: Needing increased Management Attention 9

9 m Dexthly Chamttry tndl2at3r

--c Fort Calhoun Goal (1.4)

..$.. 2.64 .

i:: :-

i:1::

1:1:-

1: -

1.51 1.31 1.27 1.33 1.4 - a i m -L L -

IiUii1 ll lhl Aug Sep r

O ct Nov Dec Jan Feb Mar Apr May June July 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 July 1997 was 1.32. The CPI value for the past 12 months (August 1996 through July 1997) was 1.09. The CPI value in the industry's upper quartile is 1.17.

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

The maximum index point value for this indicator is 7. At the end of July 1997, the FCS Value was 5.39. This compares to the previous month's value of 6.77.

Data Source: Hamilton /Ostien(Manager / Source Accountability: Hamilton Trend : None 10 l

m MontNyPersontelParE=HariExposure

.-e- Camdative Personnel Radiation Exposure .

-o FCS Goal 38 personREM 40 r "

0 0 0 0 0 c 0 0 0 0 e o 3,

ao .

E 2s _

]ao.

$ .15 ,.

n.

10 - a375 3.064 5753 5-- 1.678 0' , , , :

j Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec COLLECTIVE RADIATION EXPOSURE The 1997 Fort Calhoun goal for Collective Radiation Exposure is set at 38.0 person-REM.

The exposure for July 1997 was 3.785 Person-Rem (ALNOR).

The year-to-date exposure through the end of July 1997 was 22.167 Person-Rem (ALNOR).

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

The Year 2000 WANO industry goal for collective radiation exposure is 120 person-rem per year. For the three year period (August 1994 through July 1997), the total collective radiation exposure was 401.377 person-rem (ALNOR). This gives a Fort Calhoun Station a three year average of 133.7923 person-rem per year (ALNOR).

The maximum index point value for this indicator is 8. At the end of July 1997 the FCS Value was 7.21 This compares to the previous month's value of 8.0.

Data Source: Chase / Williams (Manager / Source)

Accountability: Chase /Gebers Trend: None SEP54 11 1

l l

p Monthlyindustrial Accident Rate e 12 Month Molling Averogo )

,_ Fc8 Yeer4ind Goal (<0.00) - .

)

, + Year 2000 WANO Industry Goal (<0.40) 1.2..

1 0.8 --

Z A . . . . . . . _ _

0.4 lF : TN2 " "

I I I I I I 0.2 0 ,_

0 - : : : : 5 5 Aug Sep Oct Nov Dec Jan Feb Mar Apr May June July INDUSTRIAL SAFETY ACCIDENT RATE

- The purpose of this indicator is to monitor progress in improving industrial safety performance for utility personnel permanently assigned to the station. Contractor work-hours are not included in the indicator. This indicator is defined as the number of accidents per 200,000 work-hours worked for all utility personnel permanently assigned to the station that result in any of following:

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

+

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

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

The Fort Calhoun Station industrial safety accident rate for the month of July 1997 was 0.00. The -

12 month rolling average (August 1996 through July 1997) was 0.0793. The year to date value was 0.00 at the end of July 1997.

There were no restricted-time and no lost-time accidents in July 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 ofJuly 1997, the FCS Value was 5.0 This compares to the previous month's value of 5.0.

Data Source: Sorensen/Blumenthal (Manager / Source)

Chase / Booth (Manager / Source)

Accountability: Chase / Bishop Trend: Positive 12

m ConthlyVolume of LLRW( "J.ft.)

-x Y:st.to-Date Cumulativ3 Rad::activ3 Wash Biried ,

Fort Calhoun Goal (1200 cu.ft.)

1200 c' : : : : : : : : : : :

1100 .-

1000 -

900--

800 --

700.

600 .

500 .

400-300 f

200.- N I

8 100 g y r--* WD R 2

}/*#*

0 --x 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 year- ,

to-date radioactive waste buried, and the Fort Calhoun goal.

Cull Amount of solid radwaste shipped off-site for processing during current month 00.0 i Volume of solid radwaste buried during July 1997 40.8 Cumulative volume of solid radioactive waste buried in 1996 171.9 Amount of solid radwaste in temporary storage 251.2

Ihe 1997 Fort Calhoun Station goal for the volume of solid radioactive waste (buried) is 1200 cubic feet. The Year 2000 WANO industry goal is 45 cubic meters (1,589 cubic feet) per year. The industry upper ten percentile value is approximately 27.33 cubic meters (965.3 cubic feet) per year.

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

Data Source: Chase /Breuer (Manager / Source)

Accountability: Chase /Gebers Trend: None SEP 54 13

SAFE OPERATIONS l

Goal: A proactive, self-critical and safety conscious culture is exhibited throughout the nuclear organization. Individuals demonstrate professionalism through self-ownership and personalinitiative and open communication.

1 14

- +-. Monthly Disabling injurynliness Frequency

'+ 12 Month Rolling Average

+ 1997 F.C.S. Goal 2..

1.8 .

1.6--

1.4 .-

1.2..

1 .

0.8 ..

0.6 ,

0.4 . I 5 0.2.. , , ,

0 -

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

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

For the month ofJuly 1997 the disabling injury / illness frequency rate was 0.00. For the 12 month period (August 1996 through July 1997) the disabling injury / illness rate was 0.16. There were no disabling injury / illness cases reported for July 1997.

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

Data Source: Sorensen/Blumenthal (Manager / Source)

Accountability: Chase / Bishop Trend: None SEP 25,26 & 27 15

- Monthly Recordable injurynlineos Frequency Rate

% Rolling 12 Month Average

... ... Fort Calhoun Goal 4.5.

4.0-3.5 -

3.0-2.5-

-5 I 4.5 ........... .. ....... ........ . ........ ........... .......... ...... .

5

/

. : . . . . . . . g. . . . . . . . .

i.o ,

Aug sep Oct Nov Dec Jan Feb Mar Apr May June July RECORDABLE INJURY /lLLNESS FREQUENCY RATE This indicator shows the monthly Recordable injury / Illness Frequency Rate, a rolling 12 month average, and the OPPD goal. A recordable injury / illness case is reported if 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 July 1997 was 2.0.

The recordable injury / illness frequency rate for the past 12 months (August 1996 through July 1997) was 1.7.

During the month of July 1997, there was 2 recordable injuries in which one employee had to have stitches in the forehead and another employee twisted the left knee. There have been a total of 7 recordable injury / illness cases in 1997.

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

Data Source: Sorensen/Blumenthal (Manager / Source)

Accountability: Bishop Trend: Needing increased Management Attention SEP 15,25,26 & 27 16 1

i . . . . . . , . . . . .

e m Cntamin: tion Ev: Kin ("ssithly)

+ Contamination Events (YTD) 100. ,

90 .

80 .

70 .

60 .

60 ..

4e el 40 .- -

0 31 30 . g 20 .

108+ g l 0 E -

Mar Ea Apr May Jun Jul Aug Sep Oct Nov Dec l Jan Feb CLEAN CONTROLLED AREA CONTAMINATIONS

>1,000 DISINTEGRATIONSIMINUTE 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 July 1997.

There was O contamination event in July 1997. There have been 41 contamination events in 1997 through the end of July 1997.

The 1997 monthly personnel contamination was revised from 20 mrem per person skin dose to 100 mrem per person skin dose.

Data Source: ChaseMlilliams (Manager / Source)

Accountability: Chase /Gebers Trend- Needing increased Management Attention SEP 15 & 54 17 i

m Personnet Erfo.4 (Esch Month)

+ Preventable (15. Month Totals) e Personnel Error (15 MoreiTotais) 30 -

15 -

10 .

5 : : .

O o ,

aEaa a Jan Feb Mar Apr May Jun Jul Aug sep oct Nov Dec Jan Feb Mar Apr May June PREVENTABLE / PERSONNEL ERROR LERs This indicator depicts 18-month totals for numbers of " Preventable" and " Personnel Error" LERs.

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

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

in June 1997, there were four events which were subsequently reported as an LER. Two LER's were categorized as Preventable and one LER was categorized as Personnel Error for the month of June. The total LERs for the year 1997 is nine. The total Personnel Error LERs for the year 1997 is two.

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)

Accountabirrty: Chase Trend: None' SEP 15 18

4

, i Startup m Shutdown

. m Cperations

...o. . Industry Average Trend 2-l1.5.

E u.

1 1- -

0.5 . '""

""D"". .

. . . .t " " G" ""D"* " -G" " O " " " D - -O 9 -l

+ i I i t i :

l I l 93 1 83-2 93 3 93 4 94 1 94 2 94-3 94 4 95 1 95 2 95 3 95 4 Year-Quarter SAFETY SYSTEM FAILURES This indicator illustrates the number of NRC Safety System Failures as reported by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data in the annual" Performance Indicators for Operating Commercial Nuclear Power Reactors" report.

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

1st Quarter 1993: The SG low pressure scram signal block reset values, for all 4 channels of both SGs, were greater than the allowed limits. This rendered the scram input inoperable at certain operating conditions.

2nd Quarter 1993: A section of the piping configuration for the borated water source of the safety injection system was not seismically qualified. This could have 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 vatve disks; 2) Calibration errors of the offsite power low signal relays could have prevented offsite power from tripping and the EDGs from starting in the required amount of time during a degraded voltage condition; 3) Both AFW pumps were inoperable when one was removed from service for testing and the control switch for the other pump's steam supply valve was out of the auto position.4) Only one train of control roort. 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 Accountability: Chase rrend: None 19

m Highest Monthly hNdual Exposure mR l aMghest hNdual Expostre Year-to4st) mR

+ FCS Annual yeared ooal 1000 mRfudddual 1000 : : : : : : : : : : :

900, 800 700.

600 400.

300 200 100.

0 =

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec MAXIMUM INDIVIDUAL RADIATION EXPOSURE This indicator shows the highest exposure for an individual during the year 1997.

For the month of July 1997, an individual accumulated 686 millirem, which was the highest individual exposure for the month.

For the year to date, an individual has accumulated a total of 705 millirem (TLD). The 705 millirem came from ALNOR readings, and in general, are higher than TLD readings.

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

Data Source: Chase / Williams (Manager / Source)

Accountability: Chase /Gebers Trend: None 20

asuun FCS Oted Wla6one(Monthly) a FCS Nonated Viola 6ons(Monthly)

, o._ FCS Oted Violatione(124onth Average) e FCS Nonated Wlations(12&onth Average) m Reglon IV Cited Viole6ons (124onth Average for Reglon IV top quartile) -

12 10 . : : :

8, 6.- - E C C C C C C 4-- C 0 0 0 0 0 0 0 0 ^ ^

- s, s ;

m, . .

m . m E E: .-

Aug Sep Oct Nov Dec Jan Feb Mar Apr May June July VIOLATION TREND This indicator illustrates a 12-month trend for Fort Calhoun Station Cited Violations, Non-Cited Violations and Oited Violations for the Top Quartile plants in Region IV. Additionally, the Fort Calhoun Station Cited and Non-Cited Violations for the past 12 months will be illustrated monthly. The 12-month trend for the Region IV top quartile lags 2-3 months behind the Fort Calhoun Station trend. This lag is necessary to compile information on other Region IV plants.

The following inspections were completed during July 1997:

i IER No. Title 97-05 Enviromiental / RP Inspection 97-13 Corrective Action Inspection To date, OPPD has received fifteen violations for inspections reports received in 1997.

Levellli Violations 1 LevelIV Violations 10 Non-Cited Violations 4.

Total 15 The 1997 Fort Calhoun Station Goal for this performance indicator is to be at or below the cited violation trend for the top quartile plants in Region IV.

Data Source: Tills /Cavanaugh (Manager / Source)

Accountability: Tills Trend: None 21

]

m NRC Sig*tfic:nt Evotts IIdu;try Aver:g) Trand a

i 1 0.5 0 1, r r r r r 92 93 94 95 1 95 2 95 3 95-4 66 1 96 2 96-3 96-4 Ye ar . Q uarte r INPO Significant Events (SEs) 3 3-2- 2 q q 1- 0 0 0 0 0 0 0 0

93 94 95 1 96 2 95 3 95 4 H1 96 2 H-3 H-4 97 1 Ye ar-Quarte r NRC SIGNIFICANT EVENTS The fonowing SEs were identified between the 2nd Quarter of 1992 and the 1st quarter of 1995 (as reported in the NRC's

' Performance Indmators 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 invoMng a large break LOCA or a main steam line break inside containment could result in the inoperability of both control room A.C. units.

INPO SIGNIFICANT EVENTS The following SEs have been identified since 2nd Quarter of 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 ist Quarter 1994).

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

1st Quarter 1996: During pressurizer solid plant operation, the Low Temperature Overpressurization (LTOP) protechon 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

u d sTa maaing in Les ;

3-2 -

1 1

O o o o o o o O ; ; ;

1 i

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

There were rio missed sunteillance tests resulting in LERs during July 1997.

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

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

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

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

l 24 !

l l

Nat Gsneradon (10,000 MWh) s l

34.81 3114 35.1 -

34.43 34.43 32.82 30 .-

9g 24.37 8 RFO l 20 .~ 18.06 a

g 9.746 Aug Sep Oct l

Nov Dec Jan Feb Mar Apr May June July STATION NET GENERATION During the month of July 1997, a net total of 351027.4 MWh were generated by the Fort Calhoun Station. Cumulative net generation for Cycle 17 was 2853322.9 MWh at the end of July 1997. Cumulative net generation for Cycle 16 was 5418326.6 MWh.

Data Source: Station Generation Report Accountability: Chase Trend: None 25

. i Monthly Forced Outage Rate

+ Rolling 12 Month Av; rage .

. + 1997 Fort Calhoun Goal (1 A%) ,

80% .

48% .

40% .

l 36 % 4 30% . -

26% '--

20% .-

15%..

s. sos #

5% - -

: : : : : --[

ng ,

: x : : : : : : :

96 Aug sep' Oct Nov Dec Jan. Feb Mar Apr May June- July FORCED OUTAGE RATE The Forced Outage Rate (FOR) for the month of July 1997 was 0.0 %. The forced outage rate for the previous 12 months (August 1996 through July 1997) was 7.31%. The 1997 year-to-date FOR was 10.7% at the end of July 1997.

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

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

Date Source: Monthly Operating Report Accountability: Chase Trend: Needing increased Management Attention 26 J

. c:r ate Uni Ity Factor

, Unit C.pacity Factor for Cycle 17

1M7 FCS Goal (M.00%)

110% .

100 % . .. -

90% -. gg =- =

a...a.,, ,,

80% - - -

70% .

4- Cycle 17 60% -

40% .

30% --

20% .

10%.-

0% i i i i . . .

i

, : i C-16 Aug Sep Oct Nov Dec Jan Feb Mar Apr May June July 3

UNIT CAPACITY FACTOR This indicator shows the plant monthly Unit Capacity Factor, the Unit Capacity Factor for the current fuel cycle, the year-to-date, and the 1997 OPPD Station goal.

Unit Capacity Factor = Net Electrical Enerav Generated (MWH)

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

At the end of July 1997, the Cycle 17 Unit Capacity Factor was 79.90%. The Unit Capacity Factor for the last 36 months (August 1994 through July 1997) was 83.38. The 1997 Fort Calhoun annual goal for this indicator is 96.00%.

The year-to-date value is 88.33%.

Data Source: Monthly Operating Report Accountability: Chase Trend: None 27 l

i i MonthyEAF

.-e Year-to Date herage Monthly EAF *

+ 12 Month Rolling herege w OPPD Goal . .

100% ..

l

' 5.J %

K T

- 90% - $ n'-)%

i ~

- X E k 2 80% .- ,.

w

/

3 A

/ A '

70% - _

j 80% -

50% -

40% ..

30%-

1096 RFO 10% .

4.9%

P4 -

Aug Sep oct Nov Dec Jan Feb Mar Apr May June July EQUIVALENT AVAILABILITY FACTOR This indicator shows the plant monthly Equivalent Availability Factor (EAF), the year-to-date average monthly EAF, the 12 month rolling average, and the OPPD goal.

The EAF for July 1997 was 97.45 %. The 12 month rolling average (August 1996 through July 1997) was 73.09%. The equivalent availability factor for the past three years (August 1994 through July 1997) was 82.58%.

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

Data Source: Dietz/Mikkelsen (Managers / Source)

- Accountability: Chase Trend: None 28

~ m Safety System Actuations (INPO Definition)

, .-e- FCS Goal (0)

-+ Industry Upper 10 Percentile (0)-

3.

2.

1.

0 0 0 0 0 0 0 0 0 0 0 0 0 0 96 Aug sep Oct Nov Dec Jan Feb Mar Apr May June July l

l UNPLANNED SAFETY SYSTEM ACTUATIONS -(INPO DEFINITION)-

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

There were no WANO unplanned safety system actuations during 1996.

The 1997 Fort Calhoun goal for this indicator is 0.

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

m Saf3ty Sy0 tom Astuatlans (NRC Dofinitlan) i i FcS Gocl(0) .

+ Critical Hours 10 .- 1888 RF0 - 800 700 j

1.00

" 6-_ 500 j - 400-4--

f

^

300 g 2--

- 200 0

- 100 0 '

0 A s O N D J F M A M J J UNPLANNED SAFETY SYSTEM ACTUATIONS -(NRC DEFINITION)

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

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

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

Accountability: Phelps Trend: Positive 30

I m Cross He-2 Rate

+ Year-to-Date Grose Heat Rate

) .+ Fort Calhoun Goal 14.76 -

14.25 --

13.75 -

4 13.25 .

, 12.75 12.25 11.75

11.25 .

, 10.75 10.25 m, 9.75 -

, , am ,

9.25 96 Aug Sep Oct Nov Dec Jan Feb Mar Apr May June July i

GROSS HEAT RATE l

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 10,329 BTUlkWh for the month of July 1997. The 1997 year-to-date Average GHR was 10,129 BTU /kWh at the end of the month.

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

The 1997 Fort Calhoun year-end goal for the Average GHR indicator is 10,166 BTU /kWh.

4 Data Source: Guinn/Schawe (Manager / Source)

Accountability: Chase /Skiles Trend: None-31 4

4

+1hermet Output

+ Fort Calhoun 1494 MW Goal a .. Tech Srwe 9500 MW Limit is00 1_1_ . _ ._1_1_m._-. _ 2- r, , , ,_ ,_

r v 1490 ,

1440.

1470 1460.

. 0.

1440.

1430.

1420 1 2 3 4 5 6 7 8 9 10 11 12 13 14 16 16 17 18 19 20 21 22 23 24 25 26 27 20 29 30 31 DAILY THERMAL OUTPUT The thermal output graph displays the daily operating power level during July 1997, the 1500 thermal megawatt average technical specification limit, and the 1498 thermal megawatt Fort Calhoun goal. The station operated at a nominal 100% power until July 10, when the reactor power was reduced to 95% to facilitate scheduled Screen Wash Pump repairs. Repairs were completed and reactor power reached 100% on July 12, and remained there through the end of the month.

Data Source: Guinn/Schawe (Manager / Source)

Accountability: Chase /Short

- Trend: None 32

+ Monthly Equipment FoR

+ Equiprwnt FoR/1,000 Creal Hrs. Colling 12-Month interval)

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

1. .

! Ei ! ! $ b '

b\ , - \

0 - - - - - - -

Aug Shp oct dv DIt JEn Feb Nr Apr Ny June July l

EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS i

The Equipment Forced Outage rate per 1,000 critical hours for the 12 months from August 1,1996, through July 30,1997, was 0.142. The year to-date rate per 1,000 critical hours for the months from May 1,1997 through July 30,1997 was 0.217.

The equipment forced outage that occurred April 21,1997 was attributed to the rupture of a fourth stage extraction steam pipe. A second outage occurred on May 24 due to a weld crack which caused reactor power to be reduced to 10% while repairs were made on-line.

The 1997 Fort Calhoun year-end goal for this indicator is a maximum value of 0.20.

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

Accountability: Chase /Phelps Trend: None 33

CHEMmTRY ACTION LEVELS EXCEEDED emme Ewnt Days +.Awrage Ewnt D8yt +oPPD L6mht ,

3.

2.. .

p .

E __

~ ~

!i o

%y. --.

Ie I

I s { E s ( E s

E~ l~ { Y e

I

~ e CHEMISTRY ACTION LEVELS EXCEEDED - EVENT DAYS 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 levelis exceeded. The parameter action levels are delineated in Chemistry procedure CH AD-0003, " Plant System Chemical Limits and Corrective Actions".

An action levelis 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.

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

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

There were no event days in July.

Data Source: Chase / Hamilton (Manager / Source)

Accountability: Hamilton Trend: None 34 i

w% Hours out of Umit 13.00 . + OPPD Goat (5%) '

11.00 .

9.00 .

7.00 .

5.00 . e : e ; ; ; ; ; ; ; ;

3.00 . _

j 1.00 - -

I I 5 $ $ 4 3 I I I j $

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

The Primary System Lithium Percent Hours Out of Limit was 0.0% for the month of July 1997.

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

hours out of limit.

- Data Source: Chase / Hamilton (Manager /Soume)

Accountability: Hamilton Trend: None 35 1

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

36

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

T e

T h

i 4

i i

e

]

u

'1 I

s P

I

-I i

c !

P F

k i

'h 1

I i

P

.?,

I 1

+

h t

?

i 3

f.

t

-k 1

s I

?

4 5

L t

- f.

i .

)

i -

4 l :

)

I' ,

l_.

i l )k

"- f s_ _ _ _

?

.v.,-,..-,- . _ , , - ~, ,mme .#-. . . . . , ,,--~ . . . . . , . _ , - -me. 4 -J ,. ..---._,---.,_,,,,,,..c. ~, .-, . . . - . . . ,. . . , , - ..,.-.,.-,~,m,

, + Actual e. Budget Plan 3.00 , '

3.60 3.40 3.30 3.00 e

t. N=% i tto .

2.40 < w 3.30 2.00

$?E E N k k $$k k $k k $k k g g g g' g

&ibb$k$iklk3$$8kk ;

CENTS PER KILOWATT HOUR June 1997 The purpose of this indicator is to quant'ry the economical operation of Fort Calhoun Station.

The Cents Per Kilowatt Hour indicator represents the budent and actual cents p6r 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 Finandal and Operating Report.

The December 31 amounts are also shown for the prior years 1992 through 1996. In addition, the report shows the plan amounts for the years 1998 through 2002 for reference. The basis for the dollars are the Nuclear Long Range Financial Plan and the A7 Corporate Planning and Budget Review. The basis for the generation is provided by Nuclear Fuels.

The 12-rnonth rolling average unit price (period of May1996 through June,1997) averaged above the budget due to 12-month rolling expenses exceeding the budget and the 12 month budgeted generation falling below budget. The 12 month rolling average (5/96 through 6/97)is 3 34 cents per kilowatt hour.

The year-to-date average is trending in a negative direction.

NOTE: This information nom 1 ally lags by month due to the short tum around required forprocessing.

Cents per KWH Jan Feb Mar Anr May Jun Jul Ana San Oct Nov Dag Dudget Y.T-D 2.83 2.66 2.58 2.55. 2.44 2,48 2.48 2.46 2.45 2.46 2.44 2.43 Actual Y T-D 2.89 2.60 2.54 2.75 2.99 2.90 0.00 0.00 0.00 0.00 0.00 0.00 >

Data Source: Lounsberry/ Dent (Manager / Source)

Accountability: Lounsberry Trend: Needing increased Management Attention 37

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

38

m Correctiv3 M:intenance gage Preventive t'aintenance N on-Corrective / Plant irrproveme nts Fort Calhoun Goal D 664 g37 r29 682 824 713 $

674

$25 630 600-0.-1 200

+ + - -- _ ~ + s

$ b h b Non Outage Maintenance Work Document Backlog g TddlMDB Past Completion gggcgyy Completed ED . .

4 48%

$0-- 0 4 Mau 3

M-.,_

6 j

Rn4 Roty Roty Ron noty 1 2 3 4 6 u%

Not Conpleted MAINTENANCE WORKLOAD BACKLOG This indicator shows the backlog of non-outage hiaintenance Work Documents remaining open at the end of the reponing month. It also includes a breakdown by maintenance classification and priority. The 1997 goal for this indicator is 350 non-outage corrective maintenance hiWDs. The current backlog of corrective h1WDs is 322. To ensure that the htWD backlog is worked in a timely manner, non outage maintenance completion goals have been established as follows:

Ocal Priority 1 immediate Action 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Priority 2 Urgent 5 days Priority 3 Operational Concerns 21 days Priority 4 Routine Corrective 90 days Priority 5 Non-Essential 180 days Data Source: Chase / Johnson (Manager / Source)

Accountability: Chase /Faulhaber Trend: Adverse SEP 36 39

) .

! R: tic of Prov:ntivo ts Total M:intenance 90Y. -

82 % M%

77 %

80% -

7,3 j 70% '

00% 61 %

l H%- R%

j 60% -

40% -

) 30%

20 %

10%

OY. - - ,---- , + -+- i i --a Aug Sep oct Nov Dec Jan Feb Mar Apr May June July i

gust Preventive Maintenance items overdue i 2.60% + Fod Calhoun Goal

]

3% -

i 2% -

0.63 %

1% ._ 0.39% 0.25%

0.66 %

o---o---- ----o c --

0% - i .

i i mma ,E i i - ! i i EwSq Aug Sep oct Nov Dec Jan Feb Mar Apr May June July RATIO OF PREVENTIVE TO TOTAL MAINTENANCE i PREVENTIVE MAINTENANCE ITEMS OVERDUE The top graph shows the ratio of completed non-outage preventive maintenance to total completed non-outage maintenance. The ratio was 61% for the month of July 1997.

The lower graph shows the percentage o' cheduled preventive maintenance items that are overdue. During July 1997,348 PM s put of 349 were completed.

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

Data Source: Chase / Johnson (Manager / Sources)

Accountability: Chase /Faulhaber Trend: None SEP 41 & 44 40

l sun tb. Maintentarco itenu completed

.+.% Identified as Repeat too . s7e

, , og 000 '

626 60%

.40%

~

319 30%

S00 ' 179 234 343 5 207 III 1' 17g 20%

.t0*

~

~ ^ ' "

Aug Sep Od b Dec Jan F2 Mar Apr May his My ott C alh Un 08 4

- - ., _ a g ,, ....

$g .. .., .. .....

. i .

4., .., ... ... ... s.. ... u., ,,, u., s... s. ,

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

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

Data Source: Faulhaber/ Johnson (Manager / Source)

Accountability: Chase /Faulhaber Trend: N >r 4 41

i ihonthly Overtime (On Une)

.-w. Y.T D Monthy Av:rego (On-Une) ,

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

21A%

20.0% ..

15.0% -

10.0% . , ; ; e g g ,_._ _ , e : ., ; e 60%

6.0% -

1.7%

Y[*

0.0% :

1 - >

, y Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec MAINTENANCE OVERTIME The Maintenance Overtime Indicator monitors the ability to perform the desired maintenance activities with the allotted resources.

The percent of overtime hours with respect to normal hours was reported as 4.4% for the month of July 1997.

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

Data Source: Chase / Johnson (Manager /Scurce)

Accountability: Chase /Faulhaber Trend: Needing increased Management Attention-42

Hum:n Porfsrmanco CRs (Maintsnonco)

. 20 ..

18 ._ '

16 .-

14 12 .

I 10 -

$ 8- 7 7

0. , , ,.. ., 1 Dec Jan Feb Mar Apr May June July PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)

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

Data Source: Faulhaber Accountability: Chase /Faulhaber Trend: None SEP 15,41 & 44 43

% PASS OoS x % NorWASS OoS

+ % Total ooS + Total % oos Goat

14% . '

12% .

in : : : : : : : : : : : :

8% .

0%

4% . / j N_

_ . = = . = =

E s s 8. s k k 4 4 k k ~

I A 8 } $ 4 e # # I 4 k IN-LINE CHEMISTRY INSTRUMENTS OUT-OF-SERVICE This indicator shows the percentage of hours the in-line chemistry system instruments are inoperable for the reporting month. The chemistry systems involved in tc% Indicator include the Secondary System and the Post Accident Sampling System (PASS). At the end of July 1997, the percentage of hours the in-line chemistry system instruments were Inoperable was 5.22%. The following instrument (s) were out of service for the current month:

1. % PASS HOURS OUT OF SERVICE:

SL-18 was nonfunctional in the Accident Mode to obtain an RCS Grab Sample.

2. % NON-PASS HOURS OUT OF SERVICE:

Various Secondary In-Line Instruments on Al-110 were out of service from May 27,1997 thru June 13,1997.

Data Source: Chase /Ostien (Manager / Source Accountability: Chase /Skiles Trend: Positive 44

gag Wate Produmd Ea* knth (Kilograms)

-, Fort Calhoun WrWh Average Goal (180 ldograns) .

Federal & Stde Rudh unit (Mm. of 1,000 kW 1000 3 , a , ; ; ; _a ; ; a 900.

800 .

700 800 .

800 --

t g 400.-

300.-

200.-

g e : : : : : : : e -

0 -

as Aug Sep Oct Nw Dec Jan Feb hr Apr May June My HAZARDOUS WASTE PRODUCED This indicator shows the total amount of Hazardous Waste Produced by the Fort Calhoun Station each month, the mor;thly average goal and the monthly average total for hazardous waste produced during the last 12 months. This hazardous waste consists of non-halogenated hazardous waste, halogenated hazardous waste, and other hazardous waste produced.

During the month of July 1997,0.0 kilograms of non-halogenated,172.1 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 maximum ;

of 150 kilograms. '

Data Source: Chase /Shubert (Manager / Source)

Accountability: Chase / Hamilton Trend: Needing Increased Management Attention 45

m Cont:rdnatad Ratistion Controlled Area

% Fort Calhoun Goal (6%)

10% - e : : : : : : : -

9% -

8% .

7% -

6% .-

8% - _ _

4% .

3% .

2% .

1% .

0% .- i i , +

Aug Sep oct Nov Dec Jan Feb Mar Apr May June July CONTAMINATED RADIATION CONTROLLED AREA This indicator shows the percentage of the Radiologically Controlled Area that is contaminated based on the total square footage. The 1997 monthly non-outage Doal was revised from a maximum 10% to 5.0% contaminated RCA in May 1997.

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

Data Source: Chase / Williams (Manager / Source)

Accountability: Chase /Gebers Trend: Needing increased Management Attention SEP54 46 l

-.+--Poor Radiation Worker Practices

+ Fort Calhoun Goal (<15)

+ Total PRWP for 1997 16 12 .

10 -

8.

6.

I 3

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

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

During the month of July 1997, there was 2 PRWP identified.

There have been a total of 7 Poor Radiation Worker Practices in 1997.

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

Data Source: Chase / Hamilton (Manager / Source)

Accountability: Chase /Gebers Trend: None SEP 52 47

O Documents Sch;duled for R:vlew ,

5 Documents Reviewed during month a Documents Overdue 400-- _

350 . _- -

300 -- -

~

250 -

200_.

150--

100--

l E+_ E+_ E+_E+_ +_ +_ +_ +_ + + _

m a - > u e m ' x x g

e 8 8 i 8 A e & E' Q ,= 4 1997 DOCUMENT REVIEW

\

The Document Review indicator shows the number of completed, scheduled, and overdue (greater than 0 months past the scheduled due date) biennial reviews for the reporting month. The documents reviews are performed in-house and include Special Procedures, the Site Security Plan, Maintenance Procedures, Preventive Maintenance Prccedures, and the Operating Manual.

During July 1997, there were 306 document reviews scheduled, while 62 reviews were completed. At the end of the month, there were 65 document reviews more than 6 months overdue. There was 7 new documents initiated during July 1997.

Data Source: Chase /Plath Accountability: Chase /Skiles Trend: None SEP 46 48

. O Systsm Fallutse o Non System Failuree 27 as 22 to .. 1919 16 0

Aug Sep Oct Nov Dee Jon Feb Mer Apt M ay June J uly I

LOGGABLEIREPORTABLE INCIDENTS (SECURITY)

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

During the month of July 1997, there were 17 loggable/ reportable incidents identified.

System failures accounted for 71% of the total failures. Three (3) of the twelve (12) failures were environmental. Two Security Force error events, one access authorization event, and two unsecured vital area doors, were the non-systems failures that increased during the reporting month.

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

Data Source: Sefick/Woerner (Manager / Source)

Accountability: Sefick Trend: None SEP58 49 I

a Temp rary Ccdifications >1. cycle cid (RFO r qstr:d f;r r;moval) m Temp;rary Ccdificatlo:s D6 m:cths cid Glom 2Wable ca.line)

Fcrt Calhoza Occle f:t #1. cycle c:d D6 m:nths aid 3 -- 3 : s a a 0 o. *

=

. =lH...Ea sx.

1 s 8 > i a a a > s TEMPORARY MODIFICATIONS This indicator provides information on the number of Temporary Modifications (TMs) greater than one fuel cycle old requiring a refueling outage (RFO) for removal and the number of temporary modifications removable on line that are greater than six months old.

The 1997 Fort Calhoun monthly goals for this indicator are zero.

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

At the end of July 1997, there was one (1) TM installed that was greater than six months old that could be removed on4ne. TM 96-039, Railroad Siding / Corridor 26 Door, was installed November 1,1996. ECN 97-247 wrs written to close out this TM ECN 97-247 is scheduled to be reviewed by the NPRC during the month of August 1997.

At the end of July 1997, there was a total of 12 Tms installed in the Fort Calhoun Station.

Eight (8) of the 12 installed TMs require an outage for removal and 4 are removable on.

line. In 1997, a total of 15 TMs have been installed. At the end of July 1997, there were two (2) procedural or maintenance configuration alterations (PMCAs) (a special classification of TM) installed in the Fort Calhoun Station using PRC approved procedures.

These PMCAs are controlled by Standing Order O-25.

Data Source: Phelps/ Frank (Manager / Source)

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

r-- 1 Total hoodnostion Packages open

--.- Fort Calhoun Year End Goal (es) no - n

E u E E 7s . n E 70 E

. + -

4 + + e : : : 4 ----

50 ; -4 '

96 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec OUTSTANDING MODIFICATIONS This indicator shows the total number of Outstanding Modifications (excluding outstandina q modifications which are orocomed to be cancelled),

Reporting Cateaorv W ,M '96 '91 Month

'ES .'99 Form FC-1133 Backlog /in Progress 0 0 0 1 0 0 1 Mod. Requests Being Reviewed 0 0 0 1 0 9 10 Design Engr. Backlog /In Progress 0 0 0 0 18 0 18 Construction Backlog /in Progress 3 1 6 7 1 0 18 Design Engr. Update Backlog /In Progress A .12 .it ._t ,_A A ,___2R Totals 7 13 17 10 19 9 75 (outage + onune) (3+4) (6+s) (13+4) (2+s) (17+2) (e+3)

At the end of July 1997,24 modification requests have been issued this year and 5 modification requests have been cancelled. The Nuclear Projects Review Committee (NPRC) has conducted 61 backlog modification request reviews this year The Nuclear Projects Committee (NPC) has completed 22 backlog modification request reviews this

_ year, .

The 1997 year-end Fort Calhoun goal for this indicator is a maximum of 68 outstanding modifications.

Data Source: Jaworski/ Walling (Manager / Source)

Lounsberry/Beiek (Manager / Source)

Accountability: Lounsberry/Jaworski Trend: Needing increased Management Attention 51

_ _ = _

a a

.. . ,, ........ ,...........c ......... i.. ......

<a. .

m SE o DEN So 34 as g, 20 - U 17 1 1 it it

~ ~

it - ? ? , ',

, [ {

1 ' ' '

Way Jun. J uly May June J uly May June J u ly M.y June J u ly e.: u ..th, s.s u .ein. 4 1* u ..th. .t u enin.

D Engineering Response a closeout (sE)

II 20 . 3, 13 10 . q 3 0 1 p1 1

,',1 0 0 Priority 0 Priority 1 Priority 2 Priority 3 Priority 4 Priority 5 Priority 6 47 Overdue Clos.out 75 FARs ori R* PO'*'8

,2y, so.ue n1%

es.Os Respo 12 3 12 Overdue Oo outs 90%

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

The Total EAR breakdown is as follows:

EARS opened during the month 12 EARS closed during the month 18 Total EARS open at the end of the month 134 Data Source: Jaworski/Livingston (Manager / Source)

- Accountability: Phelps/Jaworski Trend: None SEP 62 52

e 43 310 41 CL0850WT ii4 50M8"#8 04 t*,onihe s n- ws ,,s a k b

[ECK$T4105-~CMWEMBECG ,

o Backlogged a Received gg Completed 260

o-s uoniws 160 -102 113 118 110 til 118 ***

44 l-

60 .. Feb Mar Apr May June July 23

. M,onthe

~

l DESIGN ENGIREERING j 260

,,,T is

...Me....

'5a1 "*

100 78 78 79 'I 88

. .'. M e . . .

7%

$0

,, 21 13 14 9 E 2 12 O T k814 . ktil Exam .h .guenin.

Feb Mar Apr May June July

[8V5TGKEffGINEENNG l 211 221 225 '4 ""'

206 211

2. ,,

150 . 8%

2 100 . 63 "'

$0 . 4 310 912 6 00 23 4g O- -.- -,_ ~+ -

Feb Mar Apr May June July

[ itbORtKCRUCDN570btidN t 2so .

2o0 .

J, e u . . iii . , ,';' ,, ,

in ..

1s. 82 ,,

n ,,

'" C 3' C 50 - '4 "'"'

0 2.

s Feb Mar Agt May Asw July

{RAFilNG/ CLOSEOUT l ENGINEERING CHANGE NOTICE STATUS Data Source: Jaworski/Livingston (Manager / Source)

Accountability: Jaworski/Phelps Trend: None SEP 6 53

\ .

ye tr7 Prior ist DC TYPt FC TYPE fr% 274 ,

IN 8%

< J _ < J 2ss -

p,{M,, y#

Total Open ECNs = 456 8 "'sN" $ Total Open ECNs a 456 0 DEN. Osseaus er Drabe k Compleer g7 e MinesmaeceCas ewede@rotweenmat . Wert k Caspleet Priority 3M e 5 ys een E menneerlas . Haspans e. Cannrsuaden b Cenpleer 71.1 %

e DEN. Instneeeing Na Casplom 150 _ ** t:4 as I

--+-- Priort 1

, g ' gt ,

-~ Priority 646 Febf7 Me- J ul-p 16.3%

Jun-77 12.8%

I'# '

gy 253 als 254 als Pr er il;ttttt 80 Fe b-97 Mar-97 Apr-97 May-97 substitute Replacernent itsm ECNs Open 77 78 88 Jun-97 78 Jul47 74 c + Priorley te!

70

' 7 *

:: 7 res.rf sus Priori 3a4 60 - 81 44.9 % 48.7%

h ,,

7

" /

20 . %

10 . ,, at to Q. .

.. g .

Feb Mar Apr May June July Document Change EONS Open ENGINEERING CHANGE NOTICES OPEN Data Source: Jaworski/Livingston (Manager Source)

Accountability: Phelps/Jaworski Trend: None SEP 62 54

. . ______O

O Administrativo Centr:I Pr:bl:m 3 Licensed Operator Error 3 Other Personnel Error M Maintenance Problem o DesigniconstructiontinstallationIFabrication Problem a Misc.

3- .

l 2.

l 1-- . . . . .

0 E $ $ b Illl+ b

.l I.11 k

_3

$ b $ $ $ h 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 July 1,1996, through June 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 detailed descriptions of these codes, see the " Performance Indicator Definitions" section of this report.

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

There were four events in June 1997 that resulted in a LER.

Data Source: Tills /Cavanaugh (Manager / Source)

Accountability: Chase Trend: None 55

O Total Requalification Training Hours a Stmulator Train 8ng Hours .

g Non4tequalificationTraining Hours O Numberof ExamFailures

_ - gg g 33 33

- 82 21 31

~

30 -

25 -

22 20 .

$.5 15 - 4 4 4 12 12 10 - '

a

,g ,e ,

g 6 5.

1 1 1 0 0 0 0 0 0v_ ,_ -+ -

7 i i +- i -.4- - .

cyci. cycle cycle cych cycie cyci, cycle cycle cyci.

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

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

Data Source: Conner /Guliani(Manager / Source)

Accountability: Conner /Guliani Trend: Nono SEP 68 56 i

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

, O SRO Exame Adminletered O SRO Exac Passed ;

a RO Exams Mministered l 3 Ro Exams Passed 10 .

4 77 77 77 77

= =

1 6.

\

1 1

1 i

b 0000 00 00 00 00 0000 0000 0 + =--+ ,

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec LICENSE CANDIDATE EXAMS - 1997 This indicator shows the number of Senior Reactor Operator (SRO) and Reactor Operator (RO) quizzes and exams taken and passed each month. These internally administered quizzes and exams are used to plot the SRO and RO candidates' monthly progress.

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

Data Source: Conner /Gullani(Manager / Source)

Accountability: Conner /Guliani Trend: None SEP 68 57 J

. l n to Oone m aady ;

aow . 1 I

+ Total 01s

, -+ 4=

m. ,

2500<

2000 .

1500<

0 0 0 1000! % _r v

s00 0 -

8 8 s s 8 y ~

t k ;{; k b 8

$hb 8

hbgb5 ,

h 4 5 E E B

k b CONDITION REPORTS BY LEVEL This indicator shows the total number of Condition Reports which are Closed, Ready to Close, Open and the Total Number of Condition Reports to date.

Level 1 Level 2 Level 3 Level 4 Level 5 Level 6 Total Open 22 19 123 826 20 85 1138 Closed 13 5 105 1126 454 183 1886 211 Condition Reports are classified as READY to CLOSE.

Data Source: Tesar/Burggraf (Manager / Source)

Accountability: Andrews/Gambhir Trend : None 58

'I

, , - . - , , . - ,, - . , .-. e , ,,v

O Totaloutage hBWDs

, , a hMfDs Ready to Work System soo . W9 Parts 9%

600 -

I d

amww soo . #%

0 i i e i -

Mar 97 Apr 97 May-07 Juri-97 J497 MWD PLANNING STATUS (CYCLE 18 REFUELING OUTAGE)

Thb indicator shows the total number of Maintenance Work Requests (MWRs) and Maintenance Work Documents (MWDs) that have been approved for inclusion in the Cycle 18 Refueling Outage. This grcph 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

c tastMarth a TNsMonth O For M ,

120-110 .

N. ' %1.

90 .

80 ..

j 70 --

$ Q.-

50 _. g

_i i : , _; , y S 3 1 $ E Na ! 3[

i S $E l! E

$ 3 E

as 5

in o!

g5 $' 5 E E 55 j j E, 45 SPECI AL SERVICES ENGINEERING DEPARTMENT 1998 OUTAGE PROJECTS STATUS REPORT 1-August-97 Data Source: Phelps/Sweamgin (Manager / Source)

Accountability: Phelps/Boughter Trend: None SEP 31 60

- m.

m - ~.

Gr29W m - e .. ae a

4 a e a a e a a e amw N

i saow was Sw.

ww.

ym.

va m vm ,

i aff s k. k' .

k. k k.

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

The goci for this indicator is to have all modification packages which were identified prior to March 20,1997 PRC approved by. September 15,1997, July 1997 Modifications added: 1 Deleted = 0 Data Source: -Jaworski/ Walling (Manager / Source)

Accountability: Gambhir/Jaworski Trend: None- SEP31 61

~

. Adud FTCDde a Target PIC Dde -

12/17/97 . E 1&29 97 waw.ia 7/2097.

U3V97.

mver!

22m vv97.. .

2 E; E RE2 EE$

w w PROGRESS OF CYCLE 18 OUTAGE MODS AND ECN'S ADDED TO '98 REFUELING OUTAGE AFTER FREEZE DATE This indicator will show the status of Modifications and ECN's approved for installat!2a during the Cycle 18 Refueling Outege. The goal for this indicator is to have all moemcation packages PRC approved by their target date.

July 1997

- Modifications /ECN's Added = 2 Deleted = 0 Data Source: Jaworski/ Walling (Manager / Source)

Accountability: Gambhir/Jaworski Trend: None SEP31 62

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

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

l July 1997 Modifications Added: 0 Deleted: 0 i

Data Source: Jaworski/ Walling (Manager / Source)

Accountability: Gambhir/Jaworski Trend: None SEP33 63

w4m av muuu- M&2i- m,aw G-a 4 Anwe&Me'id M 4-me-* me - W e me**A-esM4e-4m m e A--+eauA*M-a,4 *b w AmAm ur as .o Me n e- A 4lleum-44de

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f T

s 5

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i J l 5

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1 l e

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l ACT ON PLANS 3

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)

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

In accordance with Revision 3 of NOD-QP-37, the following performance indicators 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. hs addition, it is expected that schedule compliance'will also increase and our maintenance backlog will decrease. This project is scheduled to be fully implemented by July 1997, o

65

PERFORMANCE INDICATOR DEFINITIONS AUXILLARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE CLEAN CONTROLLED AREA CONTAMINATIONS g1,000 DISINTEGRATIONS / MINUTE PER PROBE AREA The sum of the known (planned and unplanned) unavailable hours and the estemsud unavailable hours for the auxiliary Tu personnel contamination events in the c!ean controlled feedwater system for 0 reporbng period devided by the critical area. This indcator tracks personnel performance for SEP hours for the reporbng period multipbed by the number of trains #15 & 61.

In the auxiliary feedwater system.

CONTAMINATED RADIATION CONTROLLED AREA COLLECTIVE RADtATION EXPOSURE The percentage of t~e Radiation Controlled Area, which Collective rediation exposure ls the total extemal whole-body includes the auxiliary building, the radweste building, and dose received by all on-site personnel (including contractors areas of the C/RP building, that is contaminated based on the and visitors) durir,g a time period, as measured by the total square footage. This indicator tracks performance for thermoluminescent dosimeter (TLD). Collective rad 6ation SEP #54.

exposure is reported in units of person-rem. Tnis indcator tracks radiological work performance for SEP #54. DAILY THERMAL OUTPUT COMPONENT FAILURE ANALYSIS REPORT (CFAR) This indicator shows the dai'y core thermal output as

SUMMARY

. measured from computer point XC105 (in thermal megawatts).

The 1500 MW Tech Spec Emit, and the unmet portion of the The summary of INPO categories for Fort Catioun Station with 14g5 MW FCS daily goal for the reporting month are also significantly higher (1.645 standard deviations) failure rates shown.

than the rest of the industry for an eighteerwnonth time period.

Failures are reported as component (i.e., pumps, motors, main DIESEL OENERATOR RELIABILITY (26 Demands) steam stop valves, control element motors, etc.) categories.

Tnes indicator shows the number of failures occurring for each Failure Cause Categories are: emergency diesel generator during the last 25 start demands and the last 25 load-run demands.

Age / Normal Use -thought to be the consequence of expected wear, aging, and<f-hfe, or normal use . DISABLING INJURY /lLLNESS FREQUENCY RATE (LOSS TIME ACCIDENT RATE)

Manufacturing Defect. a failure attributable to inadequate assembly or initial quahty of the responsible component or This indcator is defined as the number of accidents for all system. utikty personnel permanently assigned to the station, involving days away from work per 200,000 man-hours worked (100 Engineering / Design a failure attributable to the man-years), This does not include contractor personnel. This inadequate design of the responsbie component or system. Indcator tracks personnel performance for SEP #25,26 & 27.

Other Devices a failure attnbutable to a failure or DOC 8 MENT REVIEW (BIENNIAL) misoperation of another c:omponent or sptem, including

. associated devices. The Document Review Indicator shows the number of documents reviewed, the number of documents scheduled for Maintenance / Action - resulting from improper review, and the number of document reviews that are overdue maintenance, lack of maintenance, or personnel errors that for the reporting month. A document review is considered occur during maintenance 4ctivitieson the component.. Overdue if the review is not complete within stx months of the assigned due date. This indicator tracks performance for SEP Testing Action . resulting from improper testing or #46.

personnel errors that occur dunng testing activitses.

' EMERGENCY AC POWER SYSTEM SAFETY SYSTEM initial Installation Error . caused by impruper initial PERFORMANCE insallation of equiprnent The sum of the known (planned and unp?anned) unavailable CENTS PER KILOWATT HOUR and the estimated unavailable hours for the emergency AC power system for the reporting period divided by the number The purpose of this indicator is to quantrfy the economical of hours in the reporting period multiplied by the number of operation of Fort Calhoun Station. The cents per kilowatt trains in the emergency AC power system.

hour indicator represents the budget and actual cents per kilowatt hour on a twelve-rnonth average for the current ysar. The basis for the budget curve is the approved yearty budget. The basis for the actual curve is the Financial and Operating Report.

66

4 e

PERFORMANCE INDICATOR DEFINITIONS EMERGENCY DIESEL GENERATOR UNIT RELIABILITY minutes.

E) A failure to start because a portion of the starting system This indcaW shows the number of fadures that were reported dunng the- was drsabled for test purpose, if followed by a successful last 20. 50. and 100 emergency 6;esel Denerator demands at the For start with the starting system in its normal abgnment.

Cahouri Statiort Also shown are trigoer values who correlate to a high level of conndence that a units desel generators have obtained a

" 'h' ""#* *** Each emergency generator failure that results in the generator n , being declared inoperable should be counted as one demand and one failure Exploratory tests during corrective

1) Number of Start Demands: All vahd and inadvertent maintenance and the successful test that follows repair to start demands, including all start-only demands and all verWy operabihty should not be counted as demands or failures start demands that are followed by lood-run demands, when the EDG has not been declared operable again.

whether by automatic or manual initiation A start-only deman( is a demand in which the emergency generator EMERGENCY DIESEL GENERATOR UNRELIABILITY is started, but no attempt is made to load the generator.

This indicator measures the total unreliability of e>nergency

2) Number of Start Failures: Any failure within the diesel generators. In general, unreliability is the ratio of emergency generator system that prevents the generator unsuccessful operations (starts or load-runs) to the number of from achieving specified frequency and voltage is vahd demands. Total unreliabihty is a combination of start classified as a vahd start failure. This includes any unreliability and load-run unreliabihty.

condition identified in the course of maintenance inspections (with the emergency generator in standby ENGINEER!NG ASSISTANCE REQUEST (EAR) rnode) that definitely would have resulted in a start failure BREAKDOWN If a demand had occurret This indicator shows a breakdown, by age and priority of the

3) Number of Load-Run Demands: For a vahd load-run EAR, of the number of EARS assigned to Design Engineenng demand to be counted, the load-run attempt must meet Nuclear and System Eng:neering. This indicator tracks one or more of the following critena: performance for SEP M2.

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

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 sta: a in each test's specifications. DEN for the reporting month. This indicator tracks performance for SEP M2.

C) Other special tests in which the emergency generator is expected to be operated for at least one ENGINEERING CHANGE NOTICES OPEN hour wtule 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 Engineering

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 Substituta Replacement items open, and ECN Document predicted. Failures are counted during any valid load-run Changes open This indicator tracks performance for SEP demands. M2.

5) Exceptions: Unsuccessful attempts to start or load-run EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL should not be counted as valid demands or failures when HOURS 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 time is equal to the number of hours the reactor is entical in a period (1,000 hours0 days 0 hours 0 weeks 0 months ) divided by B) Malfunction of equipment that is not required during the numt:er of forced outages caused by equipment failures in an emergency, that period.

EQUIVALENT AVAILABILITY FACTOR C) Intentiona! termination of a test because of abnormal conditions that would not have resulted in major tltesel generator damage or repair. This indicator is defined as the ratio of gross available generation to gross maximum generation, exp.essed as a D) Malfunctions or operating errors which would not percentage. Available generation is the energy that can be have prevented the emergency generator from produced if the unit is operated at the maximum power level being restarted and brought to load within a few permitted try equipment and regulatory limitations. Maximum generation is the energy that can be produced by a unit in a

(

67

PERFORMANCE INDICATOR DEFINITIONS :

f given period if operated contmuously at maximum cepoolly. This indiostor is deflned as the number of ecoldents por 200.000 men-hours worked for aA utibly personnel pomienently assigned to the stabon that result in any of the follow,ng:

FORCED OUTAGE RATE 1) One or more days of restricted work (excluding the day of -

the accident);

. This biduator is denned as the percentage of time that the unit 2) One or more days away from work (excludeg the day of was unevailable due to forced events compared to the time the socident); and

. pionned for electrical generation. Forced events are fouures '3) Fatalities or other unplanned conditions that require removing the unit from service before the end of the next weekend - Forced Contractor personnel s's not included for this indicator, events include start up failures and events initiated while the unit is in reserve shutdown (i.e., the unit is avenable but not in IN UNE CHERAISTRY INSTRUGAENTS OUT OF SERVICE service).

Total number of in-line w mistry instruments that are out-ot.

FUEL P88 im ITY INDICATOR - service in the Secondary System and the Post Accident Samphng System (PASS),

- This indicator le defined as the steady etete pnmary coolant 1 131 acdMty, conected for the tramp uteruum contribution and LICENSE CANDIDATE EXAIAS

normalized to a common purificebon rate. Tramp uranium is fuel which has been deposlied on reactor core intemals from - This indicator shows the number of SR 3 and/or RO quianos previous defective fuel or is present on the surface of fuel and exams that are administered and passed each month.

elements from the manufacturing process. Steady state is , This inchcolor tracks training performance for SEP 868; deflned as contmucus operation for at loest three days at a power level that does not very more than + or 5% Plants LICENSED OPERATOR REQUALIFICATION TRAINING should collect dets for this indicator at a power level above -

~ 86%, when possible Plents that did not operate at steady. The total number of hours of training given to each crew during state power above 86% ehould colod date for this indicator at each cycle. Also provided are the simulator training hours -

the highest steady state power level elleined during the month. (which are a subset of the total training hours), the number of ,

~

non-REQUALIFICATION trairung hours and the number of The density conecton fador is the ratio of the specific volume exam fegures. This indicator tracks traming performance for of cocient et the RCS operahng temperature (540 degrees F., SEP #68. j Vf = 0,02146) dnnded by the specille volume of coolant at "

normel lendown temperature (120' F et outlet of the letdown _ LICENSEE EVENT REPORT (LER) ROOT CAUSE i cooling heet exchanger, Vf = 0.016204), which results in a BREAKDOINN density conochon factor for FCS equal to 1.32.

This indicator shows the number and root cause code for-GROSS HEAT HATE Uconese Event Reports. The root cause codes are as fotows.

Orces heat rate is defined as the retic of total thermal energy 1) -- Administrothre Control Problem . Management and

- in British Thermal Units (BTU) produced by the reactor to the . ' supervisory deficiencies that aflect plant pmgrams or total groes electrical energy produced by the generator in activities (i.e., poor planning, breakdown or lack of kliowatt-hours (10NH).

adequale management or supenneory control, inconect procedures, etc).

. HAZARDOUS WASTE PRODUCED

2) Licensed Operator Error . This'cause code captures :

The total amount (in Kilog.ame) of non-heiogensted hazardous errors of. omesion/ commission by heensed reactor

> weste, halogensted hazardous weste, and other hazardous . operators during plant activities.

weste produced by FCS each month.

3) Other Personnel Error. Errors of omission / commission

- HIGH PftESSURE SAFETY INJECTION SYSTERI SAFETY commer J by non-licensed personnel involved in plant

= SYSTERA PERFORIAANCE - activitiss.

The sum of the known (planned and unplanned) unavailable 4) Ideintenance Problem .The bilent of this cause code is .

hours and the estimated unavailable hours for the high . to capture the fut range of problems which can be pressure safety ugection system for the reportmg period attrtiuted in any wey to programmebe deficiencies in the .

divided by the critical hours for the reporting period mulbplied rneintenancefunctionalorgenstation. Actrvibesincluded by the number of trains in the high pressure safety injecuan in this category are maintenance, testing, surveillence,

.systern. - cahbration and radiation protechon INDUSTRIAL SAFETY ACCIDENT RATE -lNPO - 5) DesigrN=8-WFabrication Problem

. This cause code covers a fun range of programmatic 68:

a PERFORMANCE INDICATOR DEFINITIONS deficsoncies in the areas of design, construction, instakition, Plant improvement Non corrective maintenance and and fabricaten (i.e., loss of mntrol power due to underrated plant improvements.

fuse, equipment not qualifed for the environment, etc.).

This indicator tracks maintenance performance for SEP #36.

6) Equipment Failures (Electronic Piece-Parts or Environmental-Related Failures) Thra code is used for MAXIMUM INDIVIDUAL RADIATION EXPOSURE spurious failures of electronic piece-parts and failures due in meteorological conditions such es i ghtning, Ice, high The total maximum amount of radiation received by an winds, etc. Generally, it includes spurious or one-time indtvidual person working at FCS on a monthly, quarterty, and failures. Electric components included in this category annual basis, are circuit cards, rectifiers, bestables, fuses, capacitors, diodes, resistors, etc.

MWO PLANNING STATUS (CYCLE 17 REFUELING OUTAGE)

LOGGABLE/ REPORTABLE INCIDENTS (SECURITY)

The total number of Maintenance Work Orders that have bes:1 The total number of security incidents for the reporting month approved for inclusion in the Cycle 17 Refueling Outage and depicted 6n two graphs. This indicator tracks secunty the number that are ready to work (parts staged, planning performance for SEP #58. complete, and all other paperwork ready for field use). Also includeJ is the number of MWOs that have been engineering MAINTENANCE OVERTIME holds (ECNs, promdures and other miscellaneous engineering holds), parts hold, (parts staged, not yet inspected, parts not The percent of overtime hours compared to normal hours for yet amved) and planning hold (job scope not yet completed).

ma itenance. This includes OPPD personnel as well as Maintenance Work Requests (MWRs) are also shown that comract personnot. have been identified for the Cycle 17 Refueling Outage and have not yet been converted to MWOs.

MAINTENANCE WORKLOAD BACKLOGS NUMBER OF CONTROL ROOM EQUIPMENT This indicator shows the backlog of non-outage Maintenance DEFICIENCIES Work Orders remaining open at the end of the reporting month.

Maintenance classifications are defined as follows: A control room equipment deficiency (CRD) is defined as any component which is operated or controlled from the Control l Corrective Repair and restoration of equipment or Room, ;.ovides indication or alarm to the Cor, trol Room, components that have failed or are matfunctioning and are provides testing capabilities from the Control Room, provides not performing their intended function, automatic actions from of to the Control Room, or provides a passive function for the Control Room and has been identified i hh Actions takea to rnaintain a pece of equipment as deficient, i.e., does not p' dorm under all conditions as l within design operating conditions, prevent equipment desiDned. This definition also applies to the Altemate t failure, and extend its hfe and are performed prior to Shutdown Panels Al-179, Al-185, and Al-212.

equiptrent feilure.

A plant component which is deficient or inoperable is Non-Corrective / Plant improvements - Maintenance considored an ' Operator Work Around (OWA) Item" if some activites performed to implement station improvements or other action is required by an operator to compensate for the to repair non-plant equipment. condition of the component. Some examples of OWAs are:

Maintenance Work Priorities are defined as: 1) The mntrol room levelindicator does not work but a local sight glass can be read by an Operator out in the plant; Emergency Conditions which significantly degrade station safety or availability. 2) A deficient pump cannot be repaired because replacement parts require a long lead time for immediate Action Equipment deficiencies which purchase /dehvery, thus requinng the redundant pump to significantly degrade station rehabihty. Potential for unit be operated continuousty; shutdown or power reduction.

3) Special actions are required by an Operator because of Operations Concern Equipment deficiencies which hinder equipment design problems. These actions may be station operation. desenbed in Operations Memorandums, Operator Notes, or may require changes to Operating Procedures; Essential - Routine corrective maintenance on essential station systems and equiprnent. 4) Deficient plant equipment taat is required to be used dunng Emergency Operating Procedures or Abnormal Non-Essential Routine corrective maintenance on non- Operating Procedures; essential station systems and equipment.

5) System indcation that provides entical information dunng 69 l

l l

PERFORMANCE INDICATOR DEFINITIONS normal or abnormal operations The above menboned outstanding modscalons do not indude

, modencatens wteh are proposed for cancellation.

OVERALL PROJECT STATUS (REFUELING OUTAGE)

This indcator shows the status of the protects which are in the NUMBER OF MISSED SURVEILLANCE TESTS RESULTING scope of the Refuehng Outage.

IN LICENSEE EVENT REPORTS PERCENTAOF OF TOTAL MWOs COMPLETED PER The number of Surveillance Tests (STs) that result in Licensee MONTH IDEN1sFIED AS REWORK Event Reports (LERs) during the reporting month. This indicator tracks missed STs for SEP #60 & 61.

The percentage of total MWOs completed per month identried OPEN INCIDENT REPORTS as reworlt Rework activibes are identmed by maintenance planning and craft Rework is: Any addebonal work required This indicator displays the total number of open incident to correct deficiencies discovered during a failed Post Reports (irs), the number of irs that are greater than six Maintenance Test to ensure the component / system passes month: old and the number of open signif' cant irs. subsequent Post Maintenance Test.

PERCENT OF COMPLETED SCHEDULED MAINTENANCE OUTSTANDING MODIFICATIONS ACTIVITIES The number of Modification Requests (MRs) in any state The percent of the number of completed maintenance between the issuance of a Modr$ cation Number and the activites as compared to the nunter of scheduled completion of the drawing update, maintenance actrvibes each month. This percentage is shown for all maintenanca crafts. Also shown are the number of

1) Form FC-1133 Backlogtln Proareas. This number emergent MWOs Maintenance activities include MWRs, represents moddcauon requests that have not been plant MWOs, STs, PMOs, calibrahons, and other miscellaneous approved during the reporting month. actMties. This indicator tracks Maintenance performance for SEP #33,

2) Modification Requests Being Reviewed. This category includes: PERFORMANCE INDICATOR INDEX A) Modification Requests that are not yet reviewed. This indicator index is calculated from a weighted combination of eleven performance indicator values, which include the B) Modification Requests being reviewed by the following: Unit Capability Factor, Unit Capability Loss Factor, Nuclear Projects Review Committee (NPRC). HPSI, AFW, Ernergency AC Power System, Unplanned Automate Scrams, Collective Radiaton Exposure, Fuel

. C) Modification Requests being reviewed by the Reliability, Thermal Performance, Secondary System Nuclear Projects Committee (NPC), Chemistry, and Industrial Safety Accident Rate.

These Modification Requests may be reviewed several tunes PREVENTABLE / PERSONNEL ERROR LERs before they are approved for accomplishment or canceled.

Some of these Modrncation Requests are returned to This indicator is a breakdown of LERs. For purposes of LER Engineering for more information, some approved for event classification, a " Preventable LER* is defined as:

evaluaton, some approved for study, and some approved for planning. Once planning is completed and the scope of the An event for which the root cause is personnel error (Le.,

work is clearty defined, these Modification Requests may be inappropriate action by one or more individuais), inadequate approved for acce6-4MEent with a year assigned for administrative controls, a design construebon, installaten, canstruction or they may be canceled. All of these different installaton, fabrication problem (involving work completed phases require review. by or supervised by OPPD personnel) or a maintenance problem (attnbuted to inadequate or improper upkeep / repair

3) Design Engineering Backlog!!n Progrees. Nuclear of plant equipment). Also,the cause of the event must have Planning has assigned a year in which construction will occurred within approximately two years of the " Event Date*

be completed and design work may be in progress. specified in the LER (e.g., an event for which the cause is attributed to a problem with the onginal design of the plant

4) Construction Backlog /In Progrees The Construction would not be considered preventable).

Pad (age has been issued or construction has begun but the modification has not been accepted by the System For purposes of LER event classification, a *%w.ra Error" Acceptance Committee (SAC). LER is defined as follows:

5) Design Engineering Update Backlogtln Progress An event for which the root cause is inappropriate action on PED has received the Modificaten Compiehon Report but the part of one or more individuals (as opposed to being {

the drawings have not been updated. attributed to a department or a general group). Also, the }

70 1

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.o-

- PERFORMANCE INDICATOR DEFINITIONS Inappropnote action must have occurred within approximately The number of Nucisar Plant Rehabday Data System (NPRDS) two years of the ' Event Date" specified in the LER, components with more than one failure and the number of Addlhona8y, each event classified as a " Personnel Error" NPRDS co.aponents with more than two failures for the should also be classified as " Preventable? This indicator eighteerwmonth CFAR period.

trends personnel performance f or SEP ltem #15.

SAFETY SYSTEM FAILURES PRIMARY SYSTEM LITHlUM % OF HOURS OUT OF LIMIT Safety system fatu1 s are any events or conditions that could -

The percent of hours out of limit are for lithium divided by the prevent the fulflNms it of the safety functions of structures or total number of hours possible for the month, systems. If a sIstem consists of rnultiple redundant subsystems or tra.r s, failure of aR trains consttutes 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 indicator parauels NRC reportmg 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 nurnber of cloeod irs related to the safety systems, sut> systems, and su,,,Gr, ia. monitored for use of procedu'es (includes the number of closed irs caused this indicator, by procedural noncomphancs), and the number of closed procedural noncompliance irs. This indicator trends Accident Monitonng instrumentation, Auxiliary (and personnel performance for SEP #15,41 and 44. O,e,v.s.c.i) Feedwater System, Combustible Gas Control, Component Coohng Water System, Containment and PROGRESS OF CYCLE 17 OUTAGE MODIFICATION Containment Isolaten, Containment Coolant Systems, PLANNING Control Room Emergency Ventdation System, Emergency Core Cooling Systems, Engineered Safety Features l This indicator shows the status of modifications approved for Instrumentaten, Essential Compressed Air- Systems, I

completon dunng the Refueling Outage. Essential or Emergency Service Water Fire Detection or

Suppression Systems, Isolation Condsneer, Low -

PROGRESS OF 1996 ON-LINE MODIFICAT10N PLANNING Temperature Overpressure Protection, Main Steam Line isolation Valves, Onsite Emergency AC & DC Power This ind6cator shows the status of modifications approved for w/ Distribution, Radiation Monitoring Instrumentation, wiip W,ii 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 Identified poor radiological work prachoes Fuel Systems, Standby Liquid Control System and Uthmate (FRWPs) for the reporting month.- . This indicator tracks Heat Sink.

radiologbal work performance for SEP #52.

SECONDARY SYSTEM CHEMISTRY PERFORMANCE RATIO OF PREVENTIVE TO TOTAL MAINTENANCE & INDEX PREVENTIVE MAINTENANCE ITEMS OVERDUE The Chometry Performance Index (CPI) is a calculaton based The rate of preventive maintenance (including surveillance on the concentrabon of key impurities in the secondary side of testing and cahbration procedures) to the sum of non-outage the plant. These key imputties are the most likely cause of conective mamtenance and preventive maintenance deterioration of the steam generators. Crtteria for calculating compisted over the reporting penod. The ratio, expressed as the CPI are:

a percentage, is calculated based on markhours. Also deployed 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 #41. The CPI is calculated using the foHowing equaten:

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

RATE (tron /3.30) + (Copper 10.30)+(Condensate 02/2.90))/B The number of injuries requiring more than normat 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 concentrabons in ppb. The denominato* for each of REPEAT FAILURES the five factors is the INPO rnedian value. If the monthly average for a specific parameter is less than the INPO median 71 i

PERFORMANCE INDICATOR DEFINITIONS value, the median value is used in the calculation. 2) Jumpers and blocks which are installed for Surveillance Tests, Maintenance Procedures, Calibraten Procedures, SIGNIFICANT EVENTS Special Procedures or Operating Procedures are not considered as temporary mod ficates unless the jumper Significant events are the events identrhed by NRC staff or block remains in place after the test or procedure is through detailed screening and evaluaten of operating complete. Jumpers and blodts installed in test or lab experience. The screening process indudes the daily review instnarnents are not considered as temporary and discussion of al reported operahng reactor events, as well - modifcations.

as other operatonal data such as spedal tests or construction activities. An event identsfied from the screening process as 3) Scaffold is not cont,idered a temporary rnodifcahon.

a significent event candidate is further evaluated to determine Jumpers and blods whidi are installed and Nr which MRs if any actual or potential threat to the health and safety of the have been submitted will be considered as temporary pubic was involved. Specific examples of the type of cnteria modifications until final resolution of the MR and the are sumrnartzed as follows: jumper or blod is rernoved or is permanently recorded on

1) Degradation of important safety equipment- the drawings. This indicator tracks temporary modificahons for SEP 862 and 71,

2) Unexpected plant response to a transient; THERMAL PERFORMANCE

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

4) Scram with corrplicaton; UNIT CS

ABILITY FACTOR

5) Unplanned release of radioactivity; The rate of the avaliable energy generation over a given time

6) Operation outside the Imts of the Technical period to the reference energy generation (the energy tnat Spedficahons; could be produced if the cut were operated conhnuously at full power under reference ambeent condibons) over the same trne

7) Other. period, expressed as a percentage.

INPO signifcant events reported in this indsator are SERs .

(Significant Event Reports) which inform utilities of signifcant events and lessens teamed identified through the SEE-IN UNIT CAPACITY FACTOR screening process.

The not electrical energy generated (MWH) divided by the SPARE PARTS INVENTORY VALUE product of maxrnum dependabio capacity (net MNo) hmes the gross hours in ' aporting period expressed as a percent.

The dollar value of tne spare parts inventory for FCS during Net electrical erergy generated is the gross electreal output the reporting period. of the unit measured at the output terminals of the turbine generator minus the normal station service loads during the STAFFING LEVEL gross hours of the reporting period, expressed in megawatt hours.

The actual stamng level and the authorned stamng level for the Nudear Operations Drvision. The Production Engineering UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7,000 Division, and the Nudear Services Division. Thrs indicator CRITICAL HOURS tracks performance for SEP #24.

This indicator is defined as the number of unplanned automatic

' STATION NET GENERATION scrams (RPS logic actuatens) that occur per 7,000 hours0 days 0 hours 0 weeks 0 months of critical operabon.

The net generaten (sum) produced by the FCS dunng the reporting month. The value for this indicator is calculated by mulbplying *he 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 dividing that number by the total number of hours criticalin the same time penod. The The number of temporary mechanical and electrical indicator is further defined as folloves:

configurations to the plant's systems.

1) Unplanned means that the scram was not an anticipated

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

Jumpers, electrical bincks, mechanical jumpers, or . _

mechanical blocks MDb are installed in the plant 2) Scram means the automatic sh stdown of the reactor by a operating systems and av not shown on the latest revision rapid insertion of negative reactivity (e.g., by control rods, of the P&lD, schematic, connechon, wiring, or flow liquid infecten system, etc.) that is caused by actuation of diagrams. the reactor protection system. The signal may have 72

O PERFORMANCE INDICATOR DEFINITIONS resulted from exceeding a set point or spurious. quartile Region IV plant.

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 sensor's monitoring k.nt This indecator is defined as the volume of low level solid parameters and condtons, rather than the manual scram radioactive waste actualty shipped for buttal This indicator swtches or, manual turtaine tnp swiches (or push-buttons) also shows the volume of low-level radioactive waste which is provided in the main control room. In temporary storage, the amount of radioactive oil that has becn shipped o%stte for processing, and the volume of solid

4) Critical means that during the steady-state condition of the dry radioactive waste which has been shipped off-sito for reactor prior to the scram, the effective multiplicahon (k ,,, processing. Low-level solid radioactive waste consists of dry

) was essentialty equal to one. active waste, sludges, resins, and evaporator bottoms generated as a result of nuclear power plant operatio and UNPLANNED CAPABILITY LOSS FACTOR maintenance. Dry radcactive waste includes contane,ated rags, cleaning materials, disposable protecuve clothing, plastic The ratio of the unplanned energy losses du ing a given period containers, and any other material to be drsposed of at a low-of time, to the reference energy generation (the energy that level radioactive waste disposal site, except resin, sludge, or could be produced if the unit were operated continuousPy at full evaporator bottoms. Low-level refers to all radioadive waste power under reference ambient condibons) over the same trne 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

54.

UNPLANNED SAFETY SYSTEM ACTUATIONS - (INPO

+ DEFINITION)

This indicator is defined as the sum of the fo!!owing safety system actuations:

1) The number of unplanned Emergency Core Cooling System (ECCS) actuations that result from reaching an ECCS actuation set point or from a spurious /madvertent ECCS signal

2) The number of unplanned ernergency AC power system actuatons that result imm 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 spunous orinadvertent signalis generated (ECCS l only), and major equipment in the system is actuated.

I Unolanned means that the system actuaton was not part l of a planned test or evoluten. The ECCS actuations to be l counted are actuations of the high pressure injection l system, the low pressure injechon system, or the safety injection tanks.

UNPLANNED SAFETY SYSTEM ACTUATIONS .(NRC DEFINITION)

The number of safety system actuations which include (strh) the High Pressure Safety injection System, the Low Pressure Safety injection System, the Safety injection Tanks, and the Emergency Diesel Generators. The NRC classification of ssfety system actuations includes actuations when major equipment is operated RDA when the logic systems for the above safety systems are challenged.

VIOLATION TREND This indicator is defined as Fort Calhoun Station Cited Velatons and Non-Cited Violatens trended over 12 months.

Additionalty, 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 cited violaton trend for the top 73

$AFETY ENHANCEMENT PROGRAM INDEX t

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 _

Eggg

. Increase HPES and IR Accountability through use of Performance Indicators ,

Procedural Noncompliance incidents (Maintenance) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 Recordable injury / Illness Cases Fiequency Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . 16 Ck.an 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

. Disabling injury /lllness Frequency Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , , . . . . , . 15 -

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

. Develop Outage and Maintenance Planning Manual and Conduct Project Management Training -

MWO Planning Status (Cycle 17 Refueling Outage) . . . . . . . . . . . ...........,...,....... 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 On4.ine Maintenance and Modification Schedule

- 1996 0n-line Modification' Planning . . . . . . . . . . . . . . ..... ..... .... ................ 62 SEP Reference Number 36

. Reduce Corrective Non-Outage Backlog Maintenance Workload Backlogs (Corrective Non-Outage) ... .... ..................... 39 SEP Reference Numbers 41 & 44 i

. 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

=

e-SAFE 7Y ENHANCEMENT PROGRAM INDEX SEP Reference Number 52 Eagg

. Establish Supervisory Accountability for Workers Radiological Practices Radiological Work Practices Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 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 Volume of low-Level Solid Radioactive Waste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . 12 Contaminated Radiation Controlled Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 SEP Reference Number 58

. 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 Surveillance Tests resulting in Licensee Event Reports . . . . . . , . . . . . . . . . . 23 SEP Reference Number 62

. Establish Interim System E.1gineers Temporary Modifications . . . . . . . . . . ..... ..................... ....... ......... 50 Engineering Assistance Request (EAR) Breakdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 Engineering Change Notice Status . . . . . . . . . . . . ....... ..... .................... 53 Engineering Change Notices Open . . . . . . . . . . . . . . . . . . . . . . . . . . .............. ...., 54 SEP Reference Number 68

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

License Operator Requalification Training ........ . . .. .......... ........ .. ... 56 License Candidate Exams . . . . . . . . . . . . . ... ....... . .. ............ ... .. 57 SEP Reference Number 71

. Improve Controls over Temporary Modifications Temporary Modifications ........... .... ... ... . . . .... ..... .. ..... 50 75

L REPORT DISTRIBUTION LIST R.- L. Andrews L. T. Kusek G.C. Bishop C. J. Linden (7 Copies)

C. E. Boughter S. A. Lindquist C.- J. Brunnert B. R. LMngston J. W. Chase E. R. Lounsberry R. G. Conner T. J. Mcivor M.R. Core - K. A. Miller T. R. Dukarski P. A. Mruz M. L. Ellis R. J. Mueller .

H. J. Faulhaber R. L. Plott S. K. Gambhlr W.J.Ponec J. K. Gasper D. G. Ried W. G. Gates M. J. Sandhoefner S. W. Gebers F. C. Scofield M. J. Guinn H. J. Sefick R. H. Guy R. W. Short A. L. Hale J. L. Skiles

' B. R. Hansher R. D. Spies (2 Copies)

K. R. Henry K. E. Steele J. B. Herman D. E. Spires R.P.Hodgson M. A. Tesar C. K. Huang J. J. Tesarek J. K. Kellams J. W. Tills

. R. L. Jaworski D. R. Trausch J. W. Johnson L. P. Walling D.D. Kloock G. R. Williams J.B. Kuhr (9 Copies) 76 s

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ML20216D037

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