ML20202D488
| ML20202D488 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 10/31/1997 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20202D390 | List: |
| References | |
| NUDOCS 9712050034 | |
| Download: ML20202D488 (89) | |
Text
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OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION PERFORMANCE INDICATORS OCTOBER 1997 SAFE OPERATIONS PERFORMANCE EXCELLENCE COST EFFECTIVENESS Eu" 288n 3nanes P
PDR m
OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION PERFORMANCE INDICATORS OCTOBER 1997 SAFE OPERATIONS PERFORMANCE EXCELLENCE COST EFFECTIVENESS HA* 288M Haa!!es P
Table of Contents / Summary Pace TABLE OF C ON TE NTS/SU M M ARY............................................... 1-lil MONTHLY OPERAT ING REPORT..............................
....... iv WANO. PERFORMANCE INDEX TREND..............................
.v i
WANO PERFORMANCE INDEX INDICATOR......,,..,.............,
...., vi
.WANO PERFORMANCE INDICATOR TREND $................
v ii FORT CALHOUN STATION REPORT SUMM ARY............................
....... viii NUCLEAR PROGRAM GOALS AND OBJECTIVES
........... ix.xli WANO PERFORMANCE INDICATURS Unit Capability Factor...
2 Unplanned Capability Loss Factor....
..... 3 Unplanned Automatic Reactor SCRAMS per 7000 Hours 4
High Pressure Safety injection System..........
5 Auxiliary Feedwater system.........................
...... 6 Emergency AC Power System...,,...............
7 Thermal Performance..
... 8 Fuel Reliability Indicator..........................,,............
............. 9 Secondary System Chemistry..........................................
10 Collective Radiation Exposure............
. 11 Industrial Safety Accident Rate
.... 12 Volume of Low Level Radioactive Waste
. 13 SAFE OPERATIONS Disabling injury /lliness Cases Frequency Rate.....
15 Recordable injury / Illness Cases Frequency Rate.
16 Clean Controlled Area Contaminations
>1,000 Disintegrations / Minute per Probe Area 17 i
i
Table of Contents / Summary Preventable / Personnel Error LERs........................................
18 Licensee Event Report (LER) Root Cause Breakdown.................................. 19 Violation Trend.......................
20 Maximum individual Radiation Exposure.............................................. 21 Significant Even ts.......................................................... 22 Missed Surveillanco Tests Resulting in LERs..............................
23 PERFORMANCE Station Net Generation.......................................................
25 Forced Outage Rate............................,............................ 26 Unit Capacity Factor...........................................
27 Equivalent Availability Factor............
28 Unplanned Safety System Actuations INPO Definition...............
....................................... 29 N RC D efinition...................................................... 30 Gross Heat Rate..........................................................
31 Daily Thermal Output 32 Equipment Forced Outages per 1,000 Critical Hours............................
33 Chemistry Action Levels Exceeded - Event Days.................................
34 Primary System Lithium % Hours Out of Limit 35 COST Cents Per Kilowatt Hour
..................................... 37 DIVISION AND DEPARTMENT PERFORMANCE INDICATORS Maintenance Workload Bacidogs (Corrective Non-Outage) 39 Ratio of Preventive 'o Total Maintenance 40 Percentage of Total MWDs Completed per month identified as Rework 41 3
Overtime......................
42 Procedural Nor. compliance Incidents............
43 In-Line Chemistry Instruments Cut-of-Service 44 ll
Table of Contents / Summary Hazardous Waste Produced......................................................... 4 5 i
Contaminated Radiation Controlled Area
................... 46 Radiological Work Practices Program..............................................
47 Document Review......................................,.................
..... 48 Loggable/ Reportable incidents (Security)..........................................,,, 49 i
Temporary Modifications.......................................................... 50 i
Outstanding Modifications...............
...................................... 51 Engineering Assistance Request (EAR) Breakdown...........,
,............. 52 Engineering Change Notices Status.................................................................53 Open..........................................................,
.... 54 Safety System Failures..................................................... 55 Licensed Operator Requalification Training 56 License Candidate Exams......................................................... 57 Cond ition Reports........................................................... 58 Cycle 18 Refueling Outage MWD Planning Status
..... 59 l
Overall Project Status.........................................
60 Outage Modification Planning............................................ 61 On-Line Modification Planning,............................
62 i
Progress of i997 On-Line Modification Pianning 63 ACTION PLANS. DEFINITIONS. SEP INDEX & DISTRIBUTION LIST Action Plans....
64 4
Performance indicator Definitions 66 i
Safety Enhancement Program index 74
?.
Report Distribution List 76 til
.d
FORT CALHOUN STATION OCTOBER 1997 Monthly Operating Report OPERATIONS
SUMMARY
The Fort Calhoun Station (FCS) operated at a nominal 100% power level during October 1997. On October 17,1997, as part of the Updated Safety Analysis Report (USAR) verification project, Design Engineering presented a preliminary determination that the station batteries may not meet the eight (8) hour loading requirement found in the Updated Safety Analysis Report. Procedural guidance was available to reduce DC loads during a station blackout event but was not available for other design basis accidents. At 17:55 hours, plant management conservatively declared the batteries inoperable and entered Technica! Specification (TS) 2.0.1, which required the plant to be in Hot Shutdown within six (6) hours. Operations Memorandum 97-11 was immediately issued to provide guidance to reduce DC electrical loads in accordance with existing emergency operating plan (EOP) procedures. This allowed TS 2.0.1 to be exited immediately after entry. Offsite notifications were completed as required by station procedures. See LER 97-15 for additional details.
3 iv
._m.
i Fort Calhoun index Value 10/97 OPPD Value was 88.95%
Industry Median index Value 3rd QRT. INPO Median is 86.4%
100 I
89 go '
85 82 g3 as 85 80 +
84 l
570.l i
l*
60.
50.L 40 96/2 96/3 96/4 97/1 97/2 97/3 Oct 2
j i
WANO PERFORMANCE INDEX TREND The Wano Ferformance Index Trend calculation is made up of eleven variables, each value is weighted to arrive at an overall index value. INPO calculates the Wano Performance Index value based on the industry reporting the information each quarter.
The variables are calculated over a defined period of time, as listed below.
PERFORMANCE INDICATOR WEIGHTED FACTOR TIME Unit Capability Factor 16 24 Months Unplanned Capability Loss Factor 12 24 Months High Pressure Safety injection 10 24 Months
- Auxiliary Feedwater 10 24 Months Emergency AC Power 10 24 Months Unplanned Auto Scrams /7000 Hours 8
24 Months Collective Rs1iation Exposure 8
24 Months Thermal Performance Indicator 6
12 Months Secondary Chemistry Indicator 7
12 Months Industrial Safety Accident Rate 5
12 Months Fuel Reliability Indicator 8
Quarterly V
b 16.00.
EMAXrAUMVALUE g Septenter 97 O ctober 97 O
Y 14.00 p
12.00 ggg ggg g
NNN NNk N
8 10.00 6
888 888 8
8.00 8
8 888 "d"
6.00 888 sss 4.00 2.00.
6 0.00 4_
+
+
+
i
-4_
+
+
UCF UCLF ff'St AFW EACP CRE UAS7 FRI O'l TH ISAR WANO PERFORMANCE INDEX INDICATORS This, aph shows the difference between the Maximum No. of points for each WANO indicator and the actual value achieved by Fort Calhoun.
The current graph shows the difference between September '97 and October '97.
CALCULATED OVER A 2 YEAR PERIOD GALCULATED OVER A 12 MONTH PERIOD UCF Unit Capability Factor TPI Thermal Performance Indicator UCLF Unplanned Capability Loss Factor C?l Secondary Chemistry Indicato HPSI High Pressure Safety injection ISA R Industrial Safety Accident Rate AFW Auxiliary Feedwater EACP Emergency AC Power CALCULATED OVER A QUARTERLY PERlQQ UAS7 Unplanned Auto Scrams / 7000 Hours FRI Fuel Reliability Indicator CRE Collective Radiation Exposure
. vi 1
WANO PERFORMANCE INDEX TRENDS (As compared to previous month)
Unit Capability Factor increased Unplanned Capability Loss Factor increased High Pressure Safety injection No Change Aux. Feedwater System No Change Emergency AC Power increased Collective Radiation Exposure No Change Unplanned Automatic Reactor Scrams No Change Fuel Reliability Deveasing Chemistry indicator increasing Thermal Performance No Change Industrial Safety Accident Rate No Change 3
3 vil
FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT OCTOBER 1997-
SUMMARY
POSITIVE TREND REPORT A performance indicator with data representing three INDICATORS NEEDING INCREASED consecutive months of improving performance or MANA 3EMENT ATTENTION REPORT three consecutive months of performance that is superior to the stated goalis exhibiting a positive A performance indi% tor with data for the reporting trend per Nuclear Operations Division Quality period that is inadequate when compared to the Procedure 37 (NOD-QP 37).
OPPD goal is defined at "Needing increased The following perforrnance indicators exhibited Management Attention" per (NOD-OP-37).
positive trends for the reporting month:
Collective Radiation Exoosure Unclanned Automatic Reactor Scrams (Page 11)
(Page 4)
Rect,rdable Iniurv/lfiness Frecuenev Rate Thermal Perfomiance (Page 16)
(Page 8)
Forced Outaae Rote Industrial Safety Accident Rate (Page 26)
(Page 12)
Chemistrv Action Levels Exceeded Unolanned Safety Svatem Actuations (Page 34)
(Pege 30)
Cents Per Kilowatt Hour Gross Heat Rate (Page 37)
(Page 31)
Procedural NonComoliance incidents ADVERSE TREND REPORT (Page43)
- Maintenance only A performance indicator with data representing three Radiolooical Work Practices Procram consecutive months of declining performance or three (Page 47) consecutive months o' performance that is trending toward declining as determined by the Manager.
Nuclear Licensing, constitutes an adverse trend per Nuclear Operations Division Quality Procedure 37 (NOD-CD-37). A supervisorwhose performance indicator exhibits an adverse trend by this definition may specify in written form (to be published in this j
report) why the trend is not adverse.The following performance Indicators exhibited adverse trends for the reporting month.
Fuel Reliability Indicator (Page 9)
Maintenance Workload Backloos (Page 39)
Contaminated Radiation Controlled Area (Page 46)
(
viii m
NUCLEAR PROGRAM 1997 GOALS AND OBJECTIVES FUTURE FOCUS and RELATIONSHIP to CHANGE The nation's ebetric 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 CONTROL COSTS Understanding cost is essential to controlling it, and controlling cost is essential to competing in today's market.
We are a teaming organization. We must BUILD ON OUR HIGH PERFORMANCE CULTURE.
Individuals at all leveh must take responsibility for their actions and must be committed to improve their own performance.
l OUR CULTURE MUST SUPPORT THE NEW STRATEGIES. We must continue to develop and implemont strategies that will allow us to effectively compete in the evolving market while still maintaining the highest levels of safety and reliability. Communicating is our key to imprcving. Follow up and feedback muet be candid, forthright and timely.
We recognize that change causes disruption of work and work flow. That change requires irecreased managernent direction. We need IN-DEPTH, RELENTLESS ATTENTION to our NEW FOCUS / STRATEGIES.
VISION To be recognized as the best nuclear organizLtion in the world and to preserve nuclear energy as a viable future energy source.
MIRSIOR The safe, reliable and cost effective generation of electricity for OPPD customers through conservative ciecision 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.
m 3
ix
OPPD. MUCI PAR ORGANIZATION GOALS Goal 1:
SAFE OPERATIONS Supports: April 1996 Corporate Strategic Plan Goal 3, Objective: 3 & 4 A pmactive, 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 Primitles:
Achieve an overall SALP Rating of "1" in 1997.
Focus on Achieving an INPO Rating of"1"in 1998.
Reduce 1997 NRC vlotations witn no violations more severe than level 4.
No unplanned automatic reactor scrams or safety system actuations.
Objectives to support SAFE OPERATIONS.
OBJECTIVE 1 1:
No challenges to a nuclear safety systems.
OBJECTIVE 1-2:
Comply with applicable policies, technical specs, procedures, standing orders and work instructions.
OBJECTIVE 1-3:
Identify conditions BEFORE they affect plant safety and reliability. Address every safety concern.
OBJECTIVE 1-4:
Achieve all safety-related 1997 performance indicator goals in the Performance Indicator Report.
OBJECTIVE 1-5:
Zero Lost Time Injuries and recordable injuries rate BELOW 1.5 percent X
I
OPPD NUCLEAR ORGANIZATION GOALS 1997 Priorities 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, reilable and cost effective power production.
1997 PRIORITIES:
Improve Quality, Professionalism and Teamwork.
Maintain High Plant Reliability.
Pursue efficient, cost-effective work processes.
Meet or exceed INPO key parameters.
Reduce the number of Human Performance errors.
Identify Programmatic performance problems through effective self assessment.
Maintain a high level of readiness in the ERO.
Objectives to support PERFORMANCE:
OBJECTIVE 21:
Achieve an annual plant capacity factor of 92.7% and a unit capability factor of 96.0%,
i OBJECTIVE 2 2:
l Training meets the needs of the plant and the National Academy accreditation objectives.
Line managers use training to present, discuss & reinforce performance standards.
Line managers monitor and assess personnel performance to determine how well standards are met.
Line managers through personal involvement a training emphasize the importance of conducting 4
activities within approved procedures / practices.
Executive Training Committee:
j
+
invites line supervisors to discuss the direction training is going for their specific area.
+
invites the line and training supervisors responsible for each accredited program to provide a status of intemal accreditation assessments.
+
ensures items such as training attendance, attentiveness, punctuality, etc. are uniformly emphasized 4
4 -
Xi
)
OPPD NUCLEAR ORGANIZATION GOALS 1997 Priorities Goal 2:
PERFORMANCE (Continued) i OBJECTIVE 2 3:
Achieve all performance-related 1997 performance indicator goals in the Performance Indicator Report.
1-Focus on performing basic skills well, while pursuing efficient, cost-effective work processes, Identify the j*
barriers to excellence and resolve them.
OBJECTIVE 2 4:
Plan for the completion of the 1998 refueling outage in 42 days or less, 1
OBJECTIVE 2-5:
j Teamwork is evident by improved plant reliability, an effective emergency response organization, reduced number of human performance errors and effective self assessment.
Goal 3:
COSTS Sup? orts:
April 1996 Corporate Strategic Plan Goa! 2, Objective: 1, 3, and Goal 5, Objective:1 4
Opera % Fort Calhoun cost offectively to contribute to OPPD's " bottom line". Cost consciousness is exhibited at alllevels of the organization.
4 i
i -
1997 Priorities:
Maintain total O&M and Capital Expenditures within budget.
4 Streamline work process to improve cost effectiveness.
Implement Opportunity Review recommendations, j
Objectives to support COSTS:
OBJECTIVE 31:
Conduct the nuclear programs, projects, and activities within the approved Capital and O&M budgets.
OBJECTIVE 3 2:
Significantly reduce operating costs through full',upport of Utilities Service Alliance initiatives by maximizing sharing of resources, leveraging o' buying power and elimination or reduction of redundant I
support services.
- Goals Source: Lounsberry (Manager)
I P
Xii i
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I
k WANO PERFORMANCE INDICATORS l
I
m,
_m i
C"l-) C enthly Unit Capability Factar
+ 12 M onth *.rnit C ap ability Factor 1997 For t Calhoun Goal 194%)
Year 2000 W ANO Industry Goal (87%)
4
+
120%.
100.0% 100.0% 100.0%
1 RW 100.0%
100.0 %
96.4%
95.4%
00%.
S C5 %
f_
_f 74.5%
M
=
. _ =
43.7%
40%
4
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0.7 %
0%
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8 UNIT CAPABILITY FACTOR 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 n percentage. The UCF for.
October 1997 was reported as 100%. The year-to-date UCF was also reported as 88.2%, the UCF for the last 12 months (November 1996 through October 1997) was 81.7%, and the 36-month average (November 1994 through October 1997) was reported as 80.6%.
Energy losses:
Forced Outage - Condenser circulating valve repairs and leakage on Condenser "B," Event a
Period: September 10, thru 13,1997.
Forced Outage - Circumferential cracking of a weld down stream of a moisture separator due to high system stresses, Event Period: May 28, thru May 29,1997.
Forced Outage - CircumferetJal cracking of a weld down stream of a moisture separator due to high system stresses, Event Period: May 28, thru May 29,1997.
4 Forced Outage - Steam leak in the fourth stage extraction steam system, Event Period: April through mid May 1997.
Forced Outage - Due to a steam leak in the fourth stage extraction steam sys9m, Everit Period: April 1997.
1996 Refueling Outage - Event Period: Sept, through Nov.1996 "ower Reduction - Faulty Manual Transfer switch on instrument inverter "A ", Event Period:
August 26, thru 28,1997.
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 96.0%. The maximum index point value for this indicator is 16. At the end of the October 1997, the FCS Value was 13.48. This compares to the previous month's value 12.56.
Data Source:
Generation Totals Report & Monthly Operating Report Accountability: Chase Trend:
None 2
Monthly Unplanned Capability Loss Factor
+ 12-Month Rolling Average Fort Calhoun Goal (1.58%)
er Year 2000 WANOIndustry Goal (4.5%)
80*/.
6*
50 %
.4 %
40%
30.50 %
[
1.57 % 0.00 % 0.00 %
0.00 %
N OM.
0.00 %
10% +
y w:
e 0%!
^-
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1-
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3 4
3 4
4 2
a; UNPLANNED CAPABILITY LOSS FACTOR This indicator shows the plant monthly Unplanned Capability Loss Factor (UCLF), a rolling l
12-month average, the OPPD goal, and the Year 2000 WANO goal. UCLF is defmed as the ratio of the unplanned energy losses during a given period of time, to the reference energy generation expressed as a percentage. Unphnned energy loss is defined as energy not produced as a result ofunscheduled 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 October 1997 was reported as 00.0%, the Year-To-Date UCLF was 11.80%, the UCLF for the last 12 months (November 1996 through October 1997) was 12.47%, and the 36-month average UCLF November 1994 through October 1997) was reported as 9.3% at the end of the month.
The Year 2000 WANO industry goal is 3.0% and the industry current best quartile value is approximately 3.2%. The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 1.58%.
The maximum index point value for this indicator is 12. At the end of October 1997 the FCS Value was 12.00. This compares to the previous month's value of 11.80.
Data Source:
Generation Totals Report & Monthly Operating Report Accountability: Chase Trend:
None 3
t
12 Month Rolling Average
+ FCS Reactor Srtam' Per 7,000 Hours Critical for last 36 months Fort Calhoun Gml(0.0)
Year 2000 WAM hdustry Goal (1) 3.
2..
~
N.
Oc!
'N:
o Nov Dec Jan Feb Mar.
Apr May June July Aug Sep oct 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 indicetor is defined as the number of unplanned automatic scrams that occur per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of critical operation.
There were no unplanned automatic reactor scrams dudng the month of October 1997. The 12-month rolling average (November 1996 through October 1997) was 0. The 36-month value (November 1994 through October 1997) was 0.310.
The 1997 Fort Calhoun Station goal for this indicator is 0. The Year 2000 WANO industry goal is a maximum of one unplanned automatic reactor scram per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical.
The maximum index point value for this indicator is 8. At the end of the October 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 l
Trend:
Positive 4
m MonthlyHPSISystm UnavallabilityValue
+ 12 Month Rolling Average Fort Calhoun Coal (0.003)
._,_ Year 2000 WANO Industry Goal (0.02) 0.02 --
e 0.01 C..
0.01..
0.005.
^2 0-Nov Dec Jan Feb Mar Apr May June July Aug Sep Oct HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the High Pressure Safety Injection (HPSI) System unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for October 1997.
The HPSI System unavailability value for the month of October 1997 was 0.0. There were 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of planned unavailability, and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned unavailat:lity, during the month.
The 12 month rolling average was (November 1996 through Octoba ! 797) was 5.37 X E-5, and the year-to-date HPSI unavailability value was 9.8 x E-4 at the end of the month. For the previous year there was a total of 1.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of planned unavailability and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned unavailability for the HPSI system.
The 1997 Fort Calhoun year-end goal for this indicator is a maximum value of 0.003. The Year 2000 WANO industry goalis 0.02.
The maxirnum index point value for this indicator is 10. At the end of October 1997 the FCS Value was 10. This compares to the previous month's value of10, Data Source:
Phelps/Schaffer (Manager / Source)
Accountability: Phelps/Schaffer I
Trend:
None l
5
Monthly.Auxiitary Feechvater Sptem UnavailabHity m,__12 Month AFW Unavailability Fort Calhoun Goal (0.01) e Year 2000 WANO Industry Goal (0.025) 0.025 0.02.
E C
0.015.
0.01..
O.005
~.
g
--;;' g o-1997 Nov Dec
.'a n Feb Mar Apr May Juna July Aug Sep Oct 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 October 1997.
The AFW System Unavailability Value for October 1997 was 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. There were 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of planned and 00.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of Unplanned Train Unavailability hours during the month. The 12 month rolling average (November 1996 through October 1997) was 0.0045, and the year-to-date unavailability value was 0.0048 at the end of October 1997.
The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of u.01.
The Year 2000 WANO industry goal is 0.025.
The maximum index point value for this indicator is 10. At the end of October 1997, the FCS Value was 10. This compares to the previous month's value of10.
Data Source:
Phelps/Fritts (Manager / Source)
Accountability: Phelps/Fritts Trend:
None 6
i T
l m Monthly Emettency AC Power Unavailability Value
.. Yeat.to Date Emergency AC Power Unavailability Value Fort f.ethorn 0o 110.024)
+. Year 2000 W ANo ladratty Goal (0.028) 0.H.
0.036.
0.03.
0.026 0.02 O.e t t.
S 0.01.
[EJ.
,E,
, K., E,[m_._m3 I
2 4
I I
I J
T I
I 8
EMERGENCY AC POWER SYSTEM l
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 October 1997.
The Emergency AC Power System unavailability value for October 1997 was 0.014. The Emergency AC Pov er Systera unavailability value year-to-date was 0.014 and the value for the last 12 months (November 1996 through October 1997) was 0.012.
Monthly Statistics Planned Unaval! ability:
DG-1: 4.2 DG-2: 8.6 Total: 12.8 YTD: 163.3 Hours Unplanned Unavailability: DG-1: 8.0 DG-2: 0.0 Total: 8.0 YTD: 84,7 Ilours There were a total of 188.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of planned unavailability and 3.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> of unplanned unavailability for the emergency AC power system in 1996.
The 1997 Fort Calhoun year-end goal for this indicator is a maximum value of 0.024. The Year W0 WANO industry goal is 0.025. The maximum index point value for this indicator is 10. At the end of October 1997, the FCS Value was 9. This compares to the previous month's value of 5.25.
Data Source:
Phelps/Ronning (Manager /Sn'itce)
Accountability:
Phelp Ronning y
Trend:
None 7
m Month yThermalPerformance
,12 Month Romng Average
._ Fort Calhoun Goal (99.6%)
Yeer 2000 W ANO Industry Goal (99.5%)
.r-7
[
~
k b
5 N
k 8
i THERMAL PERFORMANCE This indicator shows the monthly Thermal Performance Value, the rolling 12-month average, the OPPD goal, and the Year 2000 WANO goal.
The thermal performance value for the month of October was 100%. The year to date value was reported as 99.9%. The 12 month rolling average (November 1996 through October 1997) was reported as 99.8%.
The 1997 Fort Calhoun year-end goal for this indicator is an index value which is >
99.7%. The Year 2000 WANO industry goal is 99.5%.
The maximum index point value for this indicator is 6. At the end of October 1997, the FCS Value was 6.00. This compares to the previous month's value of 6.00.
~
Data Source:
Phelps/Naser(Manager / Source)
Accountability:
Phelps/Naser Trend:
Positive 8
m FuelReliability(E 4)
._,-. Year 2000 WANO Goal (5 x 10-4 Microcuries/ Gram) 1997 Goal 147E 4 100--
83 80 7 66 61 60 1 s
45 8
40 1996 31.1 21s.7
.D T RFO 22.8 16'1 18.6 E
20 --
4.5 y
0 0 ; a ;-
i a
$ j
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$" fI E
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y z
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4 FUEL RELIABILITY INDICATOR The monthly FUEL RELIABILITY INDICATOR (FRI) for October 1997 was 83 x E-04 microcures/ gram based on steady state data at 100% power during the entire month.
Coolant activity data through October 31,1997 shows the presence of 16 leaking rods at core average power. If the leaking rods are at 70% or 50% core power the number of leaking rods changes to 28 to 46, respectively. The cesium data indicates the leaking fuel is most likely to be in the second and third bumed fuel regions (Batches S and T) which havc the original grid design. These batches are planned to be permanently discharged from the reactor core during the 1998 refueling outage.
The Cycle 17 monthly FRI is trending slightly lower than the Cycle 16 FRI at the same time in the fuel cycle due to the large contribution of the lodine-134 from the " recoil" 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 lodioe-131 is trending similar to the Cycle 16 values et the same point in the cycle. Consequently, the Cycle 17 calculated FRI value is trending lower.
The plant is currr -tly in Action Level 3 Standing Order SO-O-13, Fuel Reliability Action Plan, based on the October prediction of 16 core average power fuel failures.
The maximum index point value for this indicator is 8. At the end of the October 1997, the FCS Value was 0.5. This compares to the previous month's value of 1.11.
Data Source:
Guinn/Guliani(Managcr/ Source)
Accountability:
Chase /Staf'ord Trend Adverse 9
m MonthlyChemistryIndK:stor Fort Calhoun Goal (1.4)
- T 2.75 -
2.54 2.43 2.5.
2.25 2
1.7 5 +
o 1.5 1.27 1.32 1.31 1.18 1.14 1.25.
gggg 1
1.13 e:
Illittil t
g o
M E
f k
1 8
{
F 4"
t z
6 u.
E m
4 o
t SECONDARY SYSTEM CHEMISTRY Criteria for calculating the Secondary System Chemistry Performance Index (CPI) are as follows:
- 1) the plant is at greate.- than 30% power.
- 2) the power is changing st less than 5% per day.
The CPI for October 1997 is 1.05. The CPI value for the past 12 months (November 1996 through October 1997) was 1.29. 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 from the previous month, FH-6 copper remains above the INPO mean but is lower than the previous months value.
The maximum index point value for this indicator is 7. At the end of October 1997, the FCS Value was 7.00. This compares to the previous month's value of 3.34.
Data Source:
Hamilton /Ostien (Manager / Source)
Accountability:
Hamilton Trend:
None 10
m
- T l
gg M:rtNyNw.umiRdsknikpaare
_,_ OmidhePerscnnelRddknEkpante FCSGal38perscnRM 40,
35 )
)
30.
! 25.
x 6 20 _
Io B15
/e 7
' 10 1 78 amt 375 5753 1.734 175 3 334 5-t 1.678 50 0%I E
mm e
Jm Feb Wr Wy Jm Jd Ag Sep Cd b
- Dic, 1
COLLECTIVE itADIATION EXPOSURE The 1997 Fort Calhoun goal for Collective Radiation Exposure is set at 38.0 person REM.
The exposure for October 1997 was 6.008 Person-Rem (ALNOR). The year-to-date exposure through the end of October 107 was 38.635 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-rom per year. For the three year period (November 1994 through October 1997), the total collective radiation exposure is 137.81 person-rem (ALNOR). The Fort Calhoun Station annual average over 3 years was 130.19 person rem per year (ALNOR).
The maximum index point value for this indicator is 8. At the end of October 1997 the FCS Value was 8.00. This compares to the previous month's value of 8.00.
Data Source:
Chase / Williams (Manager / Source)
Accountability:
Chase /Gebers Trend:
Needs increased Management Attentions SEP54 11
MarthlyindustrW Aoddent Ree e 12MorthFtenghorage FCSYear4xl Goal (4.80) o-Year 2000WhN0lndustryGosi(440) 0.6.
0.5 OA i 5
5' I
03 e -
O.2.
~
~
0.1 N,
h 0
few Dec Jan Feb Mar Apr May June Jtdy As Sep Oct I
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 personne' 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 October 1997 was 0.00.
The 12 month rolling average (Novermber 1996 through October 1997) was 0. The year to date value was 0 at the end of October 1997.
There were no restricted time and no lost time accidents in October 1997. The 1997 Fort Calhoun year-end goal is 50.50. The Year 2000 WANO industry goalis 50.40. The maximum index point value for this indicator is 5. At the end of October 1097, the FCS maximum index point Value was 5.0. This compares to the previous month's maximum index point value of 5.0.
Data Source:
Sorensen/Blumenthal (Manager / Source)
Chase / Booth (Manager / Source)
Accountability: Chase /Gebers Trend:
Positive 12
1 m MonthlyVolume of LLRW(cu.ft.)
)
Year-to Date Cumulative Radioactu Waste Buried l
Fort Calhoun Goal (1200 cu.ft.)
1200.
1100-1000 900 800 +
8 g 700.
g I 600 4 f
I o 500 1 400 g
300 +
h k
o 200 ;i g
y 100.
0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec l
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.
Ft 8 8
.m,
Amount of solid radwaste shipped off-site for processing during current month : 1040 29.1 Volume of solid radwaste buried during October 1997 :
366.1 10.3 Cumulative volume of solid radioactive waste buried in 1997 :
571.1 16.0 Amount of solid radwaste in temporary storage :
00.0 0.0 The 1997 Fort Calhoun Station goal for the volume of solid radioactive waste (buried) is 1200 cubic feet. The Year 2000 WANO industry goal is 45 cubic meters (1,589 cubic feet) per year, The industry upper ten percenti'e 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, bJt will no longer be used in computing the Station's index Number.
Data Source:
Chase /Breuer (Manager / Source)
Accountability: Chase /Gebers Trend:
None SEP54 13
i l
i l
i l
i 1
SAFE OPERATIONS i
i l
Goal: A proactive, self-critical and safety conscious l
culture is exhibited throughout the nuclear l
organization. Individuals demonstrate professionalism j
through self-ownership and personal initiative and l
open communication.
i l
I l
f I
l l.
l i
I i
14
-+- W%WRe@erry e 12MathItuingAnerage 1997 F.CE (bd 0A.
0.5 i
OA 03.
0.2.
0.1.
0 1
Mw Dec Jan Ibb Mar Apr W
Jme Jdy Aug Sep Od DISABLING INJURY /lLLNESS FREQUENCY RATE (LOST-TIME ACCIDENT RATE)
This indicator shows the October 1997 Disabling injury / Illness Frequency Rate and the disabling injury / illness rate for the past 12 months (rolling average).
For the month of October 1997 the disabling injury / illness frequency rate was 0.00. For the 12 month period (November 1996 through Octot er 1997) the disabling injury / illness rate was 0.08. There were no disabling injury / illness cases reported for October 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 /Gebers Trend:
None SEP 25,26 & 27 15
--+-. NbrtHyMWRegency%
_eItlling12 NkrthAerage
._ RrtOnhastChal 4.5.
4.0 +
.3.5 3.0..
2.5.-
N 1.5 3
7 N'N 1.0
_a Ptw Dec Jan Feb Nhr Apr Why Jirie Jtdy Aug Sep Oct RECORDABLE INJURYllLLNESS FREQUENCY RATE This indicator shows the monthly Recordable injury / Illness Frequency Rate, a rolling 12 month averat,e, 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 October 1997 was 1.39.
The recordable injury / illness frequency rate for the past 12 months (Noverber 1996 through October 1997) was 1.28.
During the month of October 1997, there was no recordable injuries. There has been a total of 7 recordable injury / illness cases in 1997.
The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 1.5.
Data Source: Sorensen/Blumenthal (Manager / Source)
Accountability: Gobers Trend:
Needing increased Management Attention SEP 15,25,26 & 27 16
m Contamins6anBents(W
,_ ContaminstkriBents(YT4 100.
90 -
80.
70 +
ca 60 -
8T 50 -
l 40 41 40.
31 M.
y 1'
20 -
16 0
E E
Jan Feb Mar Apr May Jun Jd Aug Sep Oct Nw Dec CLEAN CONTROLLED AREA CONTAMINATIONS >1,000 DISINTEGRATIONS / MINUTE PER PROBE AREA This indicator shows the Personnel Contamination Events in the Clean Controlled Area for contaminations >1,000 disintegrations / minute per probe area for October 1997.
There was 2 contamination event in October 1997. There have been 68 contamination events in 1997 through the end of October 1997.
Data Source:
Case / Williams (Manager / Source)
Accountability : Chase /Gebers Trend:
None SEP 15 & 54 17 o
m f 23
-+_ Toki Ewnh 18 Month Totals Prenntable 4
g 20.
_e Personel Error
%l
/aN
- 16 6,,
MA s ---.
d
?. ; [
l
$C
'aQ -.
O11Ii11111!!!11iiil PREVENTABLE / PERSONNEL ERROR LERs This indicator depicts 18-month totals for numbers of " Preventable" and " Personnel Error" LERs.
The gra.nh 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 September 1997, there were no events which was subsequently reported as an LER. No LER's were categorized as Prevenfable and no LERs were categorized as Persc,nnel Error for the month of September. The total L'dRs for the year 1997 is fourteen. The total Personnel Error LERs for the year 1997 is five.
The 1997 goal for th4s indicator is that the year-end values for the 18 month totals not exceed 12 Preventable and S Personnel Error LERs.
Data Source: Tills /Matzke (Manager / Source)
Accountability: Chase Trend:
None SEP 15 18 l
hhc 11 %
Adtnn 32 %
Desbn 25 %
'A
.n s
N' y l
f Wnt.
LO Err.
f 7%
14 %
Other Err.
11 %
i f
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 eighteen months from Apr!l 1,1996, through September 31,1997. 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.
l NOTE: Due to the way LERs are tracked & reported, this indicator is one-month behind.
l There were No events in September 1997 that resulted in a LER.
Data Source:
Tills /Matzke (Manager / Source) f Accountability:
Chase Trend:
None 1
l 19 i
l
56 97 Q.RRENT gas ntonewsex, (arve Sf4P SALP a Msunowd*** starve 3'
. Ksthedwhears(mAersed 2)]
- RsNnomdwssure(nureAnery) c 2
.. >Nowdwears(omseAarsu kr%krwtcpeare) c-y e...
yI ct.
v\\
d 6
6b 6
15,
d 4-to.
~
d 70 :
LL.
- O m*
i m,
jja j j a
i x4 aaa14tiaa VIOLATION TREND This indicator il!ustrates a 12-month trend for Fort Calhoun Station Cited Violations, Non Cited Violations and Cited Violations for the Top Quartile plants in Region IV. Additionally, the Fort Calhnun Station Cited and Non Cited Violations for the past 12 months will be illustrated monthly. The 12-month trend for the Region IV top quartile lags 2-3 months behind the Fort Calhoun Station trend. This lag is necessary to compile information on other Region IV plants.
The following inspection reports noting vio!ctions were received during October 1997:
Violation. Level IER No.
Title IV 97-13 Resident Monthly inspection Ill 97-17 Spec. Inspection-Disabling Containment Spray To date, OPPD has received three violations for inspections completed in the current SALP cycle.
Levelill Violations 1
Level IV Violations 2
Non-Cited Violations 0
Total 3
The 1997 Fort Calhoun Station Goal for this performance indicator is to be at or below the cited violation trer,d for the top quartile plants in Region IV.
4 Data Source:
Tills /Cavanaugh (Manager / Source)
']
Accountability: Tills Trend:
None 20
m HJ est WntNy hdNdual Exposura trH h
> Hghest idNdual Exposure Year to-date nH FCS Annualyear-end Goal 1000 nR'rdNdel i 1000 000.
800,
i 700.
l
- 0.
500
~
~
400.
300.
i 200-l l
l 1
100.
O.
E
{
l Jan Feb Wr Apr Wy Jun Jul Aug Sep Oct tbv Dec MAXIMUM INDIVIDUAL RADIATION EXPOSURE This indicator shows the highest exposure for an individual during the year 1997.
For the month of October 1997, an individual accumulated 405 millirem, which was the highest individual exposure for the month.
For the year to date, an individual has accumulated a total of 843 m!illRem (TLD). The 843 millirem came from ALNOR readings, and in general, are higher than TLD readings.
The 1997 Fort Calhoun Station Annual Administrative year-end goal is a maximum of 1,000 millirem frem 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 21
W W rond 1
1,.
0.5 0
0 0__s-.
-a __, _ : _. #_. = %_ :._.._.. : _. _. _ _ _ =
_4 93 94 95 1 95-2 95 3 954 E1 52 E3 964 Year Charter IN"O Seyil6carit Ever1ts(SEs) 3 SI-2 1
1 1-0 0
0 0
0 0
0 0
93 94 951 95 2 53 954 51 52 96 3 964 97 1 Yea-Quarter NRC SIGNIFICANT EVENTS The following Significant Events were identified in the NRC report, ' Performance Indicators for Operating Nuclear Power Reactors dated June 30,1995."
4th Quarter 1994:
A potential accident scenario involving a large break LOCA or a main steam line break inside containment could result in the inoperability of both control room A.C. units.
INPO SIGNIFICANT EVENTS The following Significant Events have been identified since 1993 by INPO:
1st Quarter 1993:
Inoperability of Power Range Nuclear instrumentation Safety Channel D.
2nd Quarter 1993:
Inadequate control of Switchyard activitics.
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.3E 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) protection for the RCS was inadvertently disabled.
2nd Quarter 1996:
RC Pump Anti-Reverse Rotation Device (ARD) failure.
No SE reports have been received from INPO on the 1996 SEs as of August 1, 1996.
Data Source:
Nuclear Regulatory Commission & INPO Accountability:
Chase Trend:
None 22
Miesed STs Resulting in LERs 3.,.
2 -
1 1
i l
o o
o o
o o
o o
o o
0 96 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec l
NUMBER OF MISSEC 3URVEILLANCE 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 October 1997.
There were no missed surveillance tests resulting in LERs during October 1997.
The 1997 Fort Calhoun monthly goal for this indicator is 0.
Data Source:
Monthly Operating Report & Plant Licenseo Event Reports (LERs)
Accountability: Chase /Phelps Trend :
None SEP 60 & 61 23
i r
i j.
i i
i PERFORMANCE i
i i
Goal: To strive for Excellence in Operations utilizing the j
highest standards of performance at Fort Calhoun Station j
that result in safe, reliable plant operation in power l
production.
i l
l.
i i
24 l;
f
me-+w- <e4 c.es 4-a..J2 4 Md., Ashm A h + 4 mAm."** Amw, A_ d M ----
'" h he d 4 f ma.h aa ah4mm A+,.4 M d* did-
".4.iEJ-Aap. " - - Ampe.k+.;s _a h hw w hJ_.'-
mM 4h4h44 k
I e
1 h
P
?
I
.)
h i
f t
\\
I v
e A
e e
L L
4 I
i
~ h w
L i
a 6
4 Ip 9 i
)
i eum.--4-.gg yg qqry.ew g
-yog
....ysy-,,,
,yy q
,_g
,sy,,,
,gg,_,,
,m.g mg,,,, _
p,,
~m_ p wrm _g
,y
,y 9
..,,g6,g
...p..w
,,.p,%,
Not Generation H 0,000 MWh) 4o 0
e-k
?
5 5
k k
8 STATION NET GENERATION During the month of October 1997, a net total of 361116.6 MWh were generated by the Fort Calhoun Station. Cumulative net generation for Cycle 17 was 3,460,854.90 MWh at the end of October 1997. Cumulative net generation for Cycle 16 was 5,418,326.6 MWh.
Data Source:
Station Generation Report Accountability:
Chase Trend:
None 4
25
, Monthly raced Outage Rete
%_ RoIInng 12 Month Average 1997 Fort Calhoun Goal (1.4Y4 50%.
43%
45%.
40%
35%.
30%.
25%.
20%.
15% +
'o*-l 10%
4
/
V
~r 4
5%.
^
/
0%
1%
0%
0%
0I4 0%
C%
0%
0%
0%,
96 Nov Dec Jan Feb Mar Apr May June July Aug Sep Oct FORCED OUTAGE RATE The Forced Outage Rate (FOR) for the month of October 1997 was 0.00%. The forced outage rate for the previous 12 months (Nevember 1996 through October 1997) was 7.60%. The 1997 year to-date FOR was 8.4% at the end of October 1997. This indicator needs increased management attention sinco it exceeds the FCS goal.
Energy Losses are described in the " Unit Capability Factor" indicator, page 2 of this report.
The 1997 Fort Calhoun Station year end goal for this indicator is a maximum value of 1.4%.
Date Source:
Monthly Operating Report Accountability:
Chase
- Trend:
None 3
26
, MonthlythitcepeelryFactor 4 Year 4oDatethWtCapacityFactor that capacityrector fra cycle 17 1997 FCS Otel (96.00tS 110 % -
Cycle 17
{
100 %.
A' - q 90%.
60%.
j a
+
70%.
/
W 60% +
/
$0%
40%.
30%.
l 20%.
10%.
0% !
--, ' 1 C 16 ftw Dec Jan Feb Mar Apr May June My Aug Sep Od l
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 Eneray Genersted (MWH)
Max. Dependable Capacity (MWe) X Gross Hours in the Reporting Period Cycle 16 Unit Capacity factor was 76.76%.
At the end of October 1997, the Cycle 17 Unit Capacity Factor was 100.00.The Unit Capacity Factor for the last 36 months (Nowmber 1994 through October 1997) was 83.05. The 1997 Fort Calhoun annual goal for this indicator is 96.00%.
- The year-to-date value is 89.97%.
D..9 Source:
Monthly Operating Report Accountability:
Chase Trend:
None 27 m
hY n
I
_e_. Year to-Date Amage Montidy EAF
_6_
h Rolling Average 99.2 % 99.1 %
97.5 % 97.5%
98.7 %
g,4 T
'4}%
7 __. T T
92.8 %
=*-
y
=
80%.
68.7 %
73.6 %
/
N-a 1
y, T p
.0% 4 45.7%
50% _
40%.
RFO 30%.
20%.
3.1%
10%.
0%
r1 1
Nov Dec Jan Feb Mar Apr May June July Aug Sep Oct 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 October 1997 was 98.07 %. The 12 month rolling average (November 1996 through October 1997) was 73.07%. The equivalent availability factor for the past three years (November 1994 through October 1997) is 82.20%.
The Fort Calhoun Station goal for this indicator is an EAF of 93.00%.
Data Soarce:
Dietz/Mikkelsen (Managers / Source)
Accountability:
Chase Trend:
None 28
m Safety System Actuations (INPo Definnion) fCS GoaI(0)
+ Industry Upper 10 Percentile (0) 3.
I 3
2-1_
0 0
0 0
0 0
0 0
0 0
0 0
0 j
i 0 96 Nov Dec Jan Feb Mar Apr May June July Aug sep Oct I
UNPLANNED SAFETY SYSTEM ACTUATIONS -(INPO DEFINITION)
There were no WANO unplanned safety system actuations during the month of October 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 s
)
29
l m Safety System Actuations (NRC Definition) m FCS Goal (0)
_, Critical Hours 10 -
1996 RFo 800
^
__700 600 Y
T f6 500 400 T
g j
4--
y300 f g
i 200 0 E
1100
^
U>
l0 0
N D
J F
M A
M J
J A
S O
UNPLANNED SAFETY SYSTEM ACTUATIONS -(NRC DEFINITION)
This indicator shows the number of Unplanned Safety System Actuations (SSAs), which includes the High and Low Pressure Safety injection Systems, the Safety injection Tanks, and the Emergency Diesel Generators. The NRC classification of SSAs includes actuations when major equipment is operated and when the logic systems for these safety systems are challenged.
There have been no unplanned safety system actuations in the last 12 months. The 1997 Fort Calhoun goal for this indicator is 0.
Data Source:
Monthly Operating Report & Plant Licensee Event Reports (LERs)
Accountability:
Phelps Trend:
Positive 30
, Gross Heat Rate Yearn.)ste Gross Heat Rate Fort Cautoun Goal 14.75 14.25 13.75.
Q
~
13.25.
12.75 -
g 12.25.
" 11.75.
11.25.
h 8
10.75.
g o
l 1025.
o
=
o 2
=
=
=
9.25 96 Nov Dec Jan Feb Mar Apr May June July Aug Sep Oct i
GROSS HEAT RATE This indicator shows the Gross Heat Rate (GHR) for the reporting month, the year-to-date GHR, the goals, and the year-ered GHR for the previous three years.
The gross heat rate for Fort Calhoun Station was 10,065 BTUlkWh for the month of October 1997. The 1997 year-to-date Average GHR was 10,160 BTUlkWn at the end of the month.
The GHR varies with fluctuations in river water temparature, in general, the GHR improves during the winter months and degrades during the. ammer. This is because the gross heat rate is not normalized to the design river water temperature of 60 degrees Fahrenheit.
The 1997 Fort Calhoun year-end goal for the Average GHR indicator is 10.166 BTUlkWh.
Data Source:
Guinn/Schawe (Manager / Source)
Accountability:
Phelps/Naser Trend:
Positive 31
1500 a: : : : : : :-
1498
^r: ?
N M
0 #
0 00 0-O' O O
- 1496 1494 Therm al Ouiput g,y 1449.
Fort Calhoun 1496 MW Goal 1488 a_. Tech Spec 1500 MW 1486.
Limit 1484 1482 1480 1
3 5
7 9
11 13 15 17 19 21 23 25 27 29 31 I
I DAILY THERMAL OUTPUT The thermal output graph displays the daily operating power level during October 1997, the 1500 thermal megawatt average technical specification limit, and the 1498 thurmal megawatt Fort Calhoun goal.
FCS operated at a nominal 100% power until September 8,1997, when the reactor power was reduced to 60% to repair a condenser circulating water valve in the "B" Condenser. The reactor was placed in Hot Shutdcwn (Mode 3) and taken subcritical on Seotember 10,1997 at 04:08 hours due to an indicated leakage in "B" Condenser.
Repairs to the "A" and "B" Condensers were completed and reactor enticality was achieved on September 13,1997 at 04:08 hours. The reactor reached a nominal 100%
power level on September 19,1997 at 01:15 hours and remained there through the end of the mon',h.
Data Source:
Guinn/Schawe (Manager / Source)
Accountability:
Chase /Short Trend:
None 32
e C onthly Equipment FOR
+ Equipment FoR/1,000 Critical Hrs. (Rolling 12. Month interval)
Fort Cal;,oun Year.End Goals (0.2) 2 1.75.
3 1.54 1.25 _
14 0.75 0.5 0.25.
=
Q
]
\\
x
]
p
^
0 Nov Dec
[an Feb Mar Apr May June July Aug Sep Oct EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS The Equipment Forced Outage rate per 1,000 critical hours for the Rolling 12 months from November 1,1996 through October 30,1997, was 0.262. TheYear-To-Date rate per 1,000 critical hours for the months from January 1,1997 through October 31, 1997 was 0.297.
Fort CWhoun Station operated at a nominal 100% power level during October 1997.
On October 17,1997, Design Engineering presented a preliminary determination that the station batteries may not meet the eight (8) hour loading requirement found in the Updated Safety Analysis Report. Plant management conservatively declared the batteries inoperable and entered Technical Specification (TS) 2.0.1, which required the plant to be in Hot Shutdown within six (6) hours. Operations Memorandum 97-11 was issued to provide guidance to reduce DC electricalloads and TS 2.0.1 was entered and exited at 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br /> on October 17,1997. Offsite notifications were completed, as required by station procedures.
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 (LER s)
Accountability:
Chase /Phelps Trend:
None 33
CHEMISTRY ACTION LEVELS EXCEEDED Event Days + Average Event Days 6
6 6,
5-g4 3
2-O NT 8
d 0
O k
k k
k Y
N k
b k
k E
E E
8 8
E E
E E
'A 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 Ldaits and Corrective Actions."
An action level is considered to have been exceeded for the purpose of this indicator, whenever s
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 lt 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 cvent 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 O Event Days in October.
Data Source:
Chase / Hamilton (Manager / Source)
Accountability: Hamilton Trend:
Needs increas.d Management Attention 34 i
l
,% Hours Out of Linit 13.00 -
12.00 I
)
11.00.
9.00.
7.00.
5.00 3.00 1 233 1A8 W
1.21 1.08 1.00 -
0.00 0.00 0.00 0.00 0.00 0.00 q
-1. = -- :
,y
,s s
a 8.
t e
A g
=
z w
a a
z 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 1.61% for the month of October 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 / Source)
Accountability: Hamilton Trend:
None s
35
4 i
l Cost Goal: Operate Fort Calhoun Station in a manner that cost effectively maintains nuclear generation as an economically viable contribution to OPPD's bottom line. Cost consciousness is exhibited at all levels of the organization.
f i
a
.O 36 l
+ Actual
-e Budget
+ Ran 3.80.
3.60 -
3.40.
3.20.
~_,
~
' ' " +
2.80 -
2.60 2.40.
2.20.
2.00 !
4???????944%52 455 I$$$$42Ii!l3II3i3[8 [5j CENTS PER KILOWATT HOUR September 1997 The purpose of this indicator is to quantify the economical operation of Fort Calhoun Station.
The Cents Per Kilowatt Hour indicator represents the budget and actual cents per kilowatt hour on a 12-month rolling average for the current year. The basis for the budget curve is the approved 1996 and 1997 revised budgets. The basis for the actual curve is the Financial and Operating Report.
The December 31 amounts are also shown for the prior years 1992 through 1996. In addition, the report shows the plan amounts for the years 1998 through 2002 for reference. The basis for the dollars are the Nuclear Long Range Financial Plan and the 1997 Corporate Planning and Budget Review. The basis for the generation is provided by Nuclear Fuels.
The 12-month rolling average unit price (period of August,1996 through September,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 (8/96 through 9/97) is 3.34 cents per kilowatt hour.
The year-to-date average is trending in a negative direction. This information normally lags by a month due to the short tum around required for processing.
C.gnts per KWH Jan Feb Ma-Apr May Jun Jul Auo Seo Oct Nov Dec Budget Y T-D 2.83 2.66 2.58 2.55 2.44 2.46 2.48 2.46 2.49 2.49 2.48 2.46 Actual Y-T D 2.89 2.60 2.54 2.75 2.99 2.90 2.83 2.79 2.79 0.00 0.00 0.00 s
Data Source:
Lounsberry/ Dent (Manager / Source)
Accountability:
Lounsberry l
Trend:
Needing increased Management l
l 1
37
DIVISION AND DEPARTMENT PERFORMANCE INDICATORS Goal: Achieve high standards at Fort Calhoun Station resulting in safe, reliable and cost effective power production.
S 38
m Corrective Maintenance e Preventive Maintenance
, Non-Correclive/ Plant improvements Fort Calhoun Goal (250) 81 9, 742 729 682 624 625 636 592 630 60* 1 v
500 4 400 1 300 1 200{
1000b
+
t e
s t
=
a e
t e
t 2
o 7
6 2
4 E
4 4
m O
Non-outage Maintenance Work Document Backlog D Total MWDs Past Comptetion MWDPRORTY 46 %
Ralty Ruty Ruty R uty R uty 1
2 3
4 5
Not Com pleted MAINTENANCE WORKLOAD BACKLOG This indicator shows the backlog of non-outage Maintenance Work Documents remaining open at the end of the reporting month. It also includes a breakdown by maintenance classification and priority. The 1997 goal for this indicator is 250 non-outage corrective maintenance MWDs. The current backlog of corrective MWDs is 227 To ensure that the MWD backlog is worked in a timely manner, non-outage maintenance completion goals have been established as follows:
GDal Priority 1 Immediate Action 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Priority 2 Urgent 5 days Priority 3 Operational Concems 21 days Priority 4 Routine Corrective 90 days Priority 5 Non-Essential 180 days The 1997 Maintenance workload backlog goal was revised from a maximum 350 to 250 in September 1997.
Data Source:
Chase / Johnson (Manager / Source)
Accountability:
Chase /Faulhaber Trend:
Adverse SEP 36 39
_-- J
Ratioof Pr ventive13 Tot;lM:intenanc3 90%
90%,.
84 %
77 %
74 %
80 %
74 %
70%
70%
70%
65%
T 60%
60 % 1 52 %
50 % 1 40%1 30%1 20% 1 10%1 o% !
1 o
e a
x e
ta a
3 4
I f'
2' i
j i
4 5
5 sus earmemensmenmaanie n
_ ratoennckd eA{
- A +l i
2gs 3%[
NA ne4 NA
~
2%" Q10%
ner4 ay4 QN WA 1%
w4 NA 7
eAi sea uma num sus a-mum men m
uom Nu Dec Jun Feb W
Apr Mef he Jh Ag Sep Ch RATIO OF PREVENTIVE TO TOTAL MAINTENANCE PREVENTIVE MAINTENANCE ITEMS OVERDUE The top graph shows the ratio of completed non-outage preventive maintenance to total completed non-outage maintenance. The ratio was 74% for the month of Or ':ober 1997.
The lower graph shows the percentage of scheduled preventive maintenance items that are overdue. From the period of September 15th thru October 15th there were 24 PM's were completed late or not completed out of 435.
The 1997 Fort Calhoun monthly goal for the percentage of preventive maintenance items overdue is a maximum of 0.5%.
~
Data Source:
Chase / Johnson (Manager / Source)
Accountability:
Chase /Faulhaber Trend:
Needing increased Management Attention SEP 41 & 44 40 l
mNo, Maintentance items completed
% Identified as Repeat 800 -
008 6.0%
00 -
37g 40%
225 291
. 3.0%
f 179 179 2.0%
^
1 Nov Dec Jan Feb Mar A pr May June July Aug Sep Oct y Rew ork a s identified by Craft Fort Calhoun Goal (<3%)
3.0 %
I l
2.4 %
b 2%
1.7%
1.8 %
k 1.5 %
1.5 %
k 1.2 %
Nov Dec Jan Feb Mar Apr May June July Aug Sep Oct PERCENTAGE OF TOTAL MWDs COMPLETED PER MONTH IDENTIFIED AS REWORKIREPEAT 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 September though the 15th of October 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 concems.
Data Source:
Faulhaber/ Johnson (Manager / Source)
Accountability:
Chase /Faulhaber Trend:
Needs increased Management Attention i
41 a
lMtrthlyW(h) l l
--.- YTeI&rthlyAerage(OnOm)
Rut Calhoun"NUne"Ocal(10%
21.4 %
20.0% +
15.0%
9.8%
11.5 %
10.0%.
6.0%
A
^
4.5%
g
/
Q',
5.0%.
0.0%
,U i
Jan Asb Mar Apr May Jun Jd Aug Sep Oct tbv Dec MAINTENANCE OVERTIME The Maintenance Overtime Indicator monitors the ability to perform the desired maintenance activities with the allotted resou ces.
The percent of overtime hours with respect to normal hours was reported as 11.5% for the month of October 1997.
The 1997 Fort Calhoun monthly "on-line" goal for this indicator is a maximum value of 10%.
Data Source:
Chase / Johnson (Manager / Source)
Accountability:
Chase /Faulhaber Trend:
Needs increased Management Attention 42 l
l
i Human Performance CRs (Maintenance) 20.
18..
16.-
14 14..
ty 12 +
g 10 __
gu 8+
7 y
E 6__
5 4
d T 2I O
Apr May June July Aug Sep Oct PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)
This indicator shows the number of Condition Reports related to procedural noncompliance incidents assigned to the Maintenance Department.
2 Data Source:
Faulhaber/Burggraf (Manager / Source)
Accountability:
Chase /Faulhaber Trend:
None SEP 15,41 & 44 3
43 3
._e_ % P SS ooS
._,_ % tbn-PASS oo5'
+ %TotalooS Total % ooS Goal 14%.
12%.
10%
8%.
6%.
4% +
2% ;
x 0% =l a
=
=
=
=
=
=
8 8
k a
a a
e a
a a
a a
h b
k b
h k
b h
h IN-LINE CHEMISTRY INSTRUMENTS OUT-OF-SERVICE This indicator shows the percentage of hours the in line chemistry system instruments are inoperable for the reporting month. The chemistry systems involved in this indicator include the Secondary System and the Post Accident Sanipling System (PASS). At the end of October 1997, the percentage of hours the in-line chemistry system instruments were inoperable was 0.56%. The following instrument (s) were out of service for the current month:
1.
% PASS HOURS OUT OF SERVICE: None 2.
% NON-PASS HOURS OUT OF SERVICE: CPD Sodium and Al-110.
Data Source:
Chase /Ostien (Manager / Source)
Accountability:
Chase /Skiles Trend:
None 44
~
m W:st Produc:d Each Month (Kilograms)
Fort Calhoun Monthly Average Goal (150 kilograms) e Federal & State Monthly Limit (Max.of 1,000 kg) 1000 :
900..
800..
700 600..
w 500..
400.
- g:
300,
200 100 m
I 0
S
,E E
i E
E U
A E
p-4 8;
O Z
c HAZARDOUS WASTE PRODUCED This indicator shows the total amount of Hazardous Waste Produced by the Fort Calhoun Station each month, the monthly average goal and the monthly average total for hazardous waste produced during the last 12 months. This hazardous waste consists of non-halogenated hazardous waste, halogenated hazardous waste, and other hazardous waste produced.
During the month of October 1997,0.0 kilograms of non-halogenated,0.0 kilograms of halogenated and 0.0 kilograms of other hazardous waste were produced. Hazardous waste is counted based upon a full drum of waste.
. The 1997 Fort Calhoun Station (FCS) monthly average goal for hazardous waste produced is a maximum of 150 kilograms.
SPECIAL NOTE: FCS has recently revised it's classification with the State of Nebraska.
Due to our reduced waste generation over the past several years, we have revised our status from SMALL QUANTITY GENERATOR (</1000 kg/ month) to a CONDITIONALLY EXEMPT SMALL QUANTITY GENERATOR (<100 kg/ month).
Data Source:
Chase /Shubert (Manager / Source)
Accountability:
Chase / Hamilton Trend:
None 45
Ocrtamneted Padation Controted Area i
i Fort Calham(bal(5*4 10%.
9%.
vi..
7W 6%,
\\
1 4E 31 l
2%
i 1%
0% !
.I; l
,E S
k E
E E
E m
o z
w I
z 4
CONTAMINATED RADIATION CONTROLLED AREA This indicator shows the percentage of the Radiologically Controlled Area that is contaminated based on the total square footage. The 1997 monthly non-outage goal was revised from a maximum 10% to 5.0% contaminated RCA in May 1997. This indicator has an Adverse Trend since it exceed the FCS goal.
At the end of October 1997, the percentage of the total square footage of the RCA that was contaminated was 7.9%.
Data Source:
Chase / Williams (Manager / Source)
Accountability:
Chase /Gebers Trend:
Adverse SEP54 46 l
+ Poor Radiati:n Wcrk:r Practices Fort Calhoun Goal (<15)
+Tett PRWP for 1997 16 T 14 4 12.
10.
a 8.
6.
4.
2.
3 1
0 0
0 0
0 0:
Jan Feb Wr Apr Wy June July Aug Sep oct tbv Dec i
i l
RADIOLOGICAL WORK PRACTICES PROGRAM l
The Radiologica! 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 provido a means to qualitatively assess supervisor accountability for their workers' radiological performance. This indicator needs increased management attention due to a 3 month increasing trend of poor radiation worker practices based on YTD.
During the month of October, there was O PRWP identified.
TV.ere have been a total of 9 Poor Radiation Worker Practices in 1997.
The Fort Calhoun Station year-end goal for PRWPs is a maximum of 15.
3 Data Source:
Chase / Williams (Manager / Source)
Accountability:
Chase /Gebers Trend:
Needing increased Management Attention SEP52 47
O Dscuments Schoduled f 2r Roview g Documents Reviewed during month 5 Documents Overdue 400__
~
~
~
350 __
~
300 l 2501 200..
150__
100 +
0 _ _E_k_k_ ( k_ L B
2 a
z 5
,3 k
P 3
F w
a z
4 4
A E
l 1997 j
DOCUMENT REVIEW The Document Review indicator shows the number of completed, scheduled, and overdue (greater than 6 months past the scheduled due date) blennial reviews for the reporting month. The documents reviews are performed in-house and include Special Procedures, the Site Security Plan, Maintenance Procedures, Preventive Maintenance Procedures, and the Operating Manual.
During October 1997, there were 242 document reviews scheduled, while 53 reviews were completed. At the end of the month, there were 72 document reviews more than 6 months overdue. There were 22 new documents initiated during October 1997.
Data Source:
Chase /Plath (Manager / Source)
Accountability:
Chase /Skiles Trend:
None SEP 46 i
48
O Syst:m Failurcs a Non-System Failures 27 25 25.
21 20
- 18 16 15.L 12 12 10.
9 2
2 2
Nov Dec Jan Feb Mar Apr May June July August sep Oct l
'.OGGABLE/ REPORTABLE INCIDENTS (SECURITY)
The Loggable/ Reportable incidents (Security) Indicator is depicted in the above graphics display. The graph depicts the total number of loggable/ reportable non-system failures and system failures which occurred during the reporting month.
During the month of October 1997, there were 26 loggable/ reportable incidents identified. System failures accounted for 81% of the total failures. 62% of the system failures were environmental. Fourlost/ unattended security badges, one security force error accounted for the non-systems failures during the reporting month.
Lost / Unattended security badging incidents continue to increase.
This indicator provides information on security performance for Safety Enhancement Program (SEP) Item No. 58.
Data Source:
Sefick/Woemer (Manager / Source)
Accountability:
Sefick Trend:
None SEP 58 49
i cmporcry Modification 3 >1-cycle aid (RFO r0 quired far removsi)
T i
m Temporary Mrdifications >6 mcnths and (R3mcy::ble en linn Fort Calh:un Goals far >1-cycle and >6 mcnths cid 3
3 3
-3.
2.5 _.
0 k
k k
f
.I k
I E
TEMPORARY MODIFICATIONS This indicator provides informatior, on the number of Temporary Modifications (TMs).
greater than one fuel cycle old requiring a refueling outage (RFO) for removal and the number of temporary modifications removable on-line that are greater than six months -
old. The 1997 Fort Calhoun monthly goals for this indicator are zero.
There are currently two (2) temporary modifications that are greater than one-fuel cycle old requiring an outage for removal. TM 96-014, Reactor Coolant Gas Vent Line Pressure High Alarm, was installed April 22,1996. Repairs for this TM were completed during the 1996 RFO, but the reactor coolant gas vent line pressure is still high. MR-FC 97-011 was initiated to solve this problem and currently DEN is planning the modification. MR-FC-97-011 is expected to be completed during the 1998 RFO. TM 96-018, Equipment Drain Header Soft Rubber Patch was installed June 16,1996.
MWO 963468 is currently scheduled for the 1998 RFO.
At the end of October 1997, there'was one (1) TM installed that was greater than six months old that could be removed on-line. TM 96-039, Railroad Siding / Corridor 26 Door, was installed November 1,1996.. EAR 97-219 will close this TM. EAR 97-219
- requires System Engineering review and approval. EAR 97-219 is expected to be completed by May 1,1998.
At the end of October 1997, there was a total of 13 TMs installed in the Fort Calhoun Station. Ten (10) of the 13 installed TMs require an ' outage for removal and 3 are
. removable on-line. In 1997, a total of 17 TMs have been installed. - At the end of October 1997, there were two (2) procedural or maintenance configuration alterations (PMCAs) (a special classification of TM) installed in the Fort Calhoun Station using PRC approved procedures which are controlled by Standing Order O-25.
Data Source:
Phelps/ Frank (Manager / Source)
Accountability:
Phelps/ Core Trend:
None SEP 62&71 50 l
r-1 TotalMxl6cationPac'agesOpen Fort CalhounYearEnd Goal (68) n T
n n
n n
n 75 3
n 70 - 3 71 u
65 f~'l 96 Jan Feb Mar Apr May Jun JLi Aug Sep Oct Nw Dec OUTSTANDING MODIFICATIONS This indicator shows the total number of Outstanding Modifications (excluding outstanding modifications which are orocosed to be cancelled).
Reporting Cateaorv
'94
_'Q5
'93
'QI
'93
. 93 Month Form FC-1133 Backlog /in Progress 0
0 0
1 0
0 1
Mod. Requests Being Reviewed 0
0 0
1 0
7 8
Design Engr. Backlog /In Progress 0
0 0
0 6
3 9
Construction Backlog /in Progress 1
0 4
0 11 0
22 Design Engr. Update Backlog /In Progress _5
.12
_Z
.2
._3
_Q
__2A Totals 6
12 11 10 17 10 66 (Outage + OnLine) (2+4)
(5+7)
(9+2) (2+8) (16+1) (7+3)
At the end of October 1997,26 modification requests have been issued this year and 7 modification requests have been cancelled. The Nuclear Projects Review Committee (NPRC) has conducted 69 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) has completed 22 backlog modification request reviews this year.
The 1997 year-end Fort Calhoun goal for this indicator is a maximum of 68 outstanding modifications.
Data Source:
Jaworski/ Walling (Manager / Source)
Lounsberry/Belek (Manager / Source)
Accountability:
Lounsberry/Jaworski Trend:
None 51
50 EARS Req uiring Engine ering Clos cout. Net in Closecut 8
U 40.
38
~
33 33 30 1
~
~
27 28 3g 20 21 20.
17 16
~"
13 14 g
10 10+l 7
8 6
2 9
2 2
1 E
O
~
Aug Sep Oct Au0 Sep Oct A ug Sep Oct Aug Sep Oct 0 3 Months 3 6 Months 612 Months et t Months a Engineering Response g Closcout(SE) 30 -
q, y
20 -
4 5
10 1
3 0
1 2
0 3
0 I
Priority 0 Priorky 1 Priority 2 Priority 3 Priority 4 Priority 5 Priority 6 81 E A R s 43 O ve ra u s j
Clos sous on
- O ' *f' 3
R e s,,,n e o ve re u.
c io,s u o i, 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 outsta' ding EARS.
The Total EAR breakdown is as follows:
EARS opened during the monin 15
'I EARS closed during the month 31 Total EARS open at the end of the month 124 Data Source:
Jaworski/Livingston (Manager / Source)
Accountability:
Phelps/Jaworski
~
Trend:
None SEP 62 52
44 y hihn CLo8E0uf 134 sti
'd 10%
DEN
=4 Monthe M Nes gg 71%
D 37%
g jj f ?. h.
N f
x R$$gh 1
lECN STATUS - CVERALL B TCKLOG l
57 O Backlogged O Received g Completed 0 3 Months 2su 4 5'.'.
150 1110 110 118 119 117 125 49 20 25 52416 2314 3
25
>6 Months 3-6 M onths 50._ }
31 20 26 }
26 rei
.--<1
-~ha
~
~ %
m 1rs 50 ' May June July Aug Sep Oct asKw e a etsto 250 -
2n i 150 i 90 85 si 84 77
,,, i s7
.r*
21
? 14 1
72 10
?
- 37 50y 4 13 g
12 5
13 4 10 5 9
16
(
0 _L W m
M ay June July Aug Sep Oct S M M N HrG 300 I225 250 206 211 217 204 213 17 200f-
,,3 y,,,,,
8,""'"'
l w
44%
3 150 1 i
4-1001 1 II
- 9 7 33 4
12 5
50 +
10
- 12 5
6 h
8 i
5 0 e i =2=a+
w
,_ A 78
>J Months May June July Aug sep Oct er 3g PROCURBENT/CONSTUCTION 250 7
4 2001 0 3 Months 3 6 Months 150I 14.3 %
8.2 %
8 39 46 42 44 46 49 4622
- t4 n m cc ep;; a
=:- ~
s J
M ay June July Aug Sep Oct lD R A FTIN G /C LO S E O U Tl ENGINEERING CHANGE NOTICE STATUS Data Source:
Jaworski/Livingston (Manager / Source)
Accountability:
Jaworski/Phelps Trend:
None SEP62 53
I 253 251 P'k ses r eto hi2 16 0 16 5 7
yp
'l
- B:
B':
m May-97 Jun-97 Juf e/
Au/7 Se6 37 Oct 97 245 Subs *tute Replacemert item ECNs Open sm TM % M=M pg p g
15 31 28 fi 3
.. a
,_,,.2 a f
L"j'
'* 8%
43 55 52 51 44 52 29j 0 1._.
'*"r..uv&C..ets'.*6',..
I 253 256 253 250 251 Pr only II 5
May 97 Jun 97 Jul 97 Aug 97 Se p-97 Oct 97 SubstRute Replacement kom ECNs Open p,
y 7
4)
S 49 Prkrity 5&G Praty t&2 Priority 3&4 M4 30 E1*4 st s.
I so 1.
8 M ay June July Aug Sep Oct Document Change ECNs Open ENGINEERING CHANGE NOTICES OPEN Data Source:
Jaworski/Livingston (Manager Source)
Accountability:
Phelps/Jaworski Trend:
None SEP 62 1
54
i Startup i
m Shutdown sunnuma Operations
...o.. Industry Average Trend 2-1.5 -
1 u.
1 1-y 0.5 + D
'O o...
....a
..'G
0
~0GGo i
O a
93 1 93 2 93 3 93-4 94 1 94 2 94 3 94-4 95 1 95 2 95 3 95 4 Year-Quarter 1
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 seisnne 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 valvo 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 swRch for the other pump's steam supply valve was out of the auto position.4) Only one train of control room ventilation was placed in recirc when both toxic gas monitors became inoperable. Later during surveillance testing, the other train auto-started and brought outside air into the control room for a six minute period.
1st Quarter 1994: A design bicsis 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 sinco the 4th quarter of 1995.
Data Source:
Nucleer Regulatory Commission Accountability:
Chase Trend:
None 55
O Totsi R3qualFe,aticn 1 raining Hours O Simulator Training Hours g Non-Requalification Training Hours O Number of Exam Failures 35 34 33 33 31 31 31 30 25 I
20 +
4 gg 15.
4 4
4 12 8
8 10 g
g gg y
y 6
5 3
0._.
i.
y
]~
Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle 96 3 96 5 96 7 97 1 97 2 97 3 97-4 97 5 97 6 LICENSED OPERATOR REQUALIFICATION TRAINING This indicator provides information on the total number of hours of training given to each crew during each cycle. The simulator training hours shown on the graph are a subset of the total training hours. Non-Requalification Training Hours are used for AOP/EOP verification & validation, INPO commitments, GET, Fire Brigade, Safety Meetings, and Division Manager lunches.
Exam failures are defined as failures in the written, simulator, and Job Performance Measures (JPMs) segments of the Licensed Operator Requalification Training.
Note: Rotation 97-6 was the Annual Licensed Operator Requalification Examination rotation for 1997. There were Three (3) individual and one (1) crew simulator exam failures during rotation 97-6. All remediations were completed prior to the end of the exam week.
Conceming Reactor Operator and Senior Reactor Operator Candidate exams:
Currently, there is no Initial Licer. sed Operator trainging class in session.
Data Source:
Conner /Guliani(Manager / Source)
Accountability:
Conner /Guliani Trend:
None SEP 68 56
O SRo Extms Administered O SRO Exams Passed O RO Exams Administered 3 Ro Exams Passed i
10 O
77 77 77 77 0
5.
l l
i l
0000 00 00 00 00 0000 0000 0000 0000 0000 0
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1
i LICENSE CANDIDATE EXAMS - 1997 This indicator shows the number of Senior Reactor Operator (SRO) and Reactor Operator (RO) quizzes and exams taken and passed each month. These internally administered quizzes and exams are used to plot the SRO and RO candidates' monthly progress.
During the month of October 1997, there were no (SRO) or (RO) training classes in session.
Data Source:
Conner /Guliani(Manager / Source)
Accountability:
Conner /Guliani Trend:
None SEP 68 57
m Asad/ to cose
.oased I
%_ Total Ob I
4000 3500.
3000.
.I 2s00 2000.
'S 4.
n 1000 e
_~
1 500.
J 0
8 8
8 8
8 E
B 5
a 5
e a
a a
m k
$mg$
E $k E
k Ek h $$$
_a CONDITION REPORTS BY LEVEL This indicator shows the total number of Condition Reports which are Closed, Ready to Close, Open and the Total Number of Condition Reports to date.
Level 1 Level 2 Level 3 Level 4 Level 5 Level 6 Total Open 25 15 122 828 31 244 1270 Closed 15 14 128 1314 519 327 2317 390 condition Reports are classified as READY to CLOSE.
Data Source:
Tesar/Burggraf (Manager /Sotree)
Accountability:
Andrews/Gambhir Trend:
None 1
i i
4 58
OWN M W D HOLDS Parts a W # W"'"
System Sm.
ett Planner
/
ECNs 1200 <
7e ns 31 %
5%
L 5"
.,,, { m J
2eo IN EW g 887 m
N2 g
g m
we um ue w
sov we MWD PLANNING STATUS (CYCLE 18 REFUELING OUTAGE)
This indicator shows the total number of Maintenance Work Requests (MWRs) and Maintenance Work Documents (MWDs) that have been approved for inclusion in the Cycle 18 Refueling Outage. This graph indicates:
Parts Holds - Planning Complete, Awaiting Parts System Engineering Holds - Awaiting System Engineering input to Planning Planner Holds - Maintenance Planner has not completed planning the work package.
ECN Hold - Awaiting Substitute Replacement items ECN from DEN.
In Review - Planning Complete awating SE, ISI and QC review.
Data Source:
Chase / Johnson (Manager / Source)
Accountability:
Chase / Herman Trend:
None SEP 31 59
_A
N g September 5 october O ovember Projection
- T 70 gg 3
88
- ~
3 3
3 3
m 8
'll ll3 5
R$3 2
II lF I
ll I
5 ! *!
$3 3j f
E!.
i 3
3
$i E
!)
SPECIAL SERVICES ENGINEERING DEPARTMENT 1998 OUTAGE PROJECTS STATUS REPORT Data Source:
Phelps/Sweamgin (Manager.' Source)
Accountability:
? helps /Boughter Trend:
None SEP 31 60
h 12/27G7.
4 h
11/27/97.
g 10/28S7.
I Z.
a 8
=
e s
=
=
7/3097.
R s
s N
h 6/30/97.
U b
b 531/97 '
~
, ActualFTCDate g
jgy,
a Ta W FTE M e 3/2!97.
1/31/97 <
1/1!97 1.....
a PROGRESS OF 1998 REFUELING OUTAGE MODIFICATIONS CYCLE 18 This indicator shows the status of Modifications approved for installation during the Cycle 1E Refueling Outage (March 1998).
The goal for this indicator is to have all modification packages which were identified prior to March 20,1997, PRC approved by September 15,1997.
October 1997 Modifications added: 0 Deleted = 0 Data Source:
Jaworski/Wallmg (Manager / Source)
Accountability: Gambhir/Jaworski Trend:
None SEP 31 61
_o
, Actual PRC Date Target PRC Date l
2/W8 Ls 12/17/97,,
e a
10/2M7,
- S'H7.
k 7/20/97.$
g
$/31/97 4/11/97 2/20/97 l
1/1/97 I gg es 89 i'
l PROGRESS OF CYCLE 18 OUTAGE MODS AND ECN'S ADDED TO '98 REFUELING OUTAGE AFTER FREEZE DATE This indicator will show the status of Modifications and ECN's approved for installation during the Cycle 18 Refueling Outage. The goal for this indicator is to have all modification packages PRC approved by their target date.
October 1997 Modifications /ECN's Added = 1 Deleted = 0 Data Source:
Jaworski/ Walling (Manager / Source)
Accountability: Gambhir/Jaworski Trend:
None SEP 33 62
No 1997 On Line Modifications Currently Approved I
PROGRESS OF 1997 ON LINE MODIFICATION PLANNING This indicator shows the status of modifications approved or in review for approval for on line installation during 1997.
i The goal for this indicator is to have all modification packages PRC approved by their scheduled date.
September 1997 Modifications Added: 0 Deleted: 0 Data Source: Jaworski/ Walling (Manager / Source)
Accountability:
Gambhir/Jaworski Trend:
None SEP 31 63
t e
O ACTION PLANS 64
ACTION PLANS This section lists action plans that have been developed for the perfomiance indicators cited as Adverse Trends during the month preceding this report. Also included are Action Plans for indicators that have been cited in the preceding month's report as Needing increased Management Attention for three (3) consecutive months.
in accordance with Revision 5 of NOD-QP-37, the following perfonnance indicators would require action plans based on three (3) consecutive months of perfonnance cited as "Needing increased Management Attention":
Fuel Reliability Indicator (page 9) l Based on the large number of predicted fuel failures and the expectation that future fuel failures will be identified, the Fuel Performance functional area performance is l
considered to be POOR for the 3rd quarter of 1997. The plant is currently in " Action l
Level 3" in accordance with Standing Order 0-43," Fuel Reliability Action Plan,"
based on the August prediction of15 core average power failures.
Maintenance Workload Backlogs (page 39)
A Work Management System improvement project is currently in progress. The purpose of this project is to stream line the maintenance process at Fort Calhoun Station. This will significantly improve our " WRENCH TIME" by removing inefficiencies and related hurdles that prevent work from being accomplished in a timely manner. In addition, it is expected that schedule compliance will also increase and our maintenance backlog will decrease. This project is scheduled to be fully implemented by July 1997.
G 65
-- ~ _ - -
PERFORMANCE INDICATOR DEFINITIONS i
AUXILIARY FEEDWATER SYSTEM SAF E1Y SYSTEM budget. The basis for the actual curve is the Financial and PERFORMANCE Operahng Report The sum of the known (planned and unplanned) unavailable CLEAN CONTROLLED AREA CONTAMINATIONS t 1,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> and the estimated unavailable hours for the auxthary OlSINTEGRATIONS/ MINUTE PER PROBE AREA feedwater system for the reporting penod divided by the crthcal hours for the reporbng penod multiplied by the The personnel Contaminabon events in the clean controlled number of trains in the auxiliary feedwater system.
area. This indicator tracks personnel performance for SEP
- 15 & 54.
COLLECTIVE RADIATION EXPOSURE CONTAMINATED RADIATION CONTROLLED AREA Collective radiation exposure is the total extemal whole-body dose received by all on-site personnel (including The percentage of the Radiat on Controlled Area, which contractors and visitors) dunng a bme period, as measured includes the auxiliary building, the radwaste building, and by the thermoluminescent dosimeter (TLO). Collecbve areas of the C/RP building, that is contaminated based on radiabon exposure is reported 6n units of person-rem. This the total square footage. This indicator tracks performance irdcator tracks radiological work performance for SEP #54.
for SEP #54 COMPONENT FAILURE ANALYSIS REPORT (CFAR)
DAILY THERMAL OUTPUT
SUMMARY
This indicator shows the daily oore thermal output as The summary of INPO categones for Fort Calhoun Station measured from c: imputer point XC105 (in thermal with significantly higher (1.645 standard deviations) failure megawatts). The 1500 MW Tech Spec limit, and the unmet rates than the rest of the Industry for an eighteerwnonth portion of the 1495 MW FCS daily goal fcr the reporting time penod. Failures are repuried as component (1 e.,
month are also shown.
pumps, motors, main steam stop valves, control element motors, etc.) catepones.
DIESEL GENERATOR RELtABILITY (25 Demands)
Failure Cause Categones are:
This indicator shows the number of failures occumng for Age / Normal Use -thought to be the consequence of each emergency diesel generator dunng the last 25 start expected wear, aging, endof life, or normal use,
demands and the last 25 load run demands.
Manufacturing Defect. a fal?ure attributable to DISABLING INJURY /lLLNESS FREQUENCY RATE inadequate assembly or trutial quauty of the responsible (LOSS TIME ACCIDENT RATE) wne4, erd or system.
This indicator is defined as the number of accidents for all Engineering / Design. a failure attributable to the utihty personnel permanently assigned to the station, inadequate design of the responsible component or involving days away from work per 200.000 man-hours
- system, worked (100 man years). This does r$ot include contractor personnel. This indicator tracks personnel performance for Other Devices. a failure attributable to a failure or SEP #25,26 & 27.
misopersbon of another component or system, including associated devices, DOCUMENT REVIEW (BIENNIAL)
Maintenance / Action. resulting from impropor The Document Review Indicator shows the number of maintenance, tack of maintenance, or personnel errors documents reviewed, the number of documents scheduled that occur dunng mainbnance ectivibeson the for review, and the number of document reviews that are component.,
overdue for the reporting month. A document review is 1esting Action. resulting from improper tesbng or considered overdue if the review is not complete within six personnel errors that occur during tesbng activtbes.
months of the assigned due date. This indicator tracks initial Installation Error. caused by improper initial performance for SEP #46.
,I installabon of equipment EMERGENCY AC POWER SYSTEM SAFETY SYSTEM CENTS PER KILOWATT HOUR PERFORMANCE The purpose of this indecator is to quanbfy the economical The sum of the known (planned and unplanned) unavailable operation of Fort Calhoun Station. The cents per kilowatt and the estmated unavailable hoursfor the emergency AC l
hour indicator represents the budget and actual cents per power system for the reporting pehod divided by the number kilowatt hour on a twelve-month everage for the current of hours in the reputting penod multiplied by the number of year. The basis for the budget curve is the approved yeariy trains in the emergency AC power system.
66
PERFORM %CE INDICATOR DEFINITION EMEQGENCY DIESEL. GENERATOR UNIT ItELIABILITY E) A failure to start because a portion of the starting system was disabled for test purpose, if followed by a Tnis tr4cator vvws the nunter or tallwes that we reported dwing success 411 start with the starbng system in its nomial the last 20, 60, and 100 ene'gency d esel gene stor demands at the shgnment.
Fort Calhoun Staten Also shown ese tngger values @nch corretate Each emergency generator failure that results in the to e regh level of exinfdence that a units desel genersos have generator being declared inoperable should be Counted as otened a rebatesty of greater than or nual to 9$% when the demand one demand and one failure. Exploratory tests dunng tallwes are less than the Ingger values CorreCttve rnalntenance and the successful test that follows repair to venfy operabihty should not be counted as
- 1) Number of Start Demands! All vahd and inadvertent demands or failures when the EDG has not been declared start demands, incluing all start only demands and all operable again.
start demands that are followed by loa:1-run demands, whether by automabc or manualinitation. A stan only EMERGENCY DIESEL GENERATOR UNRELLABILITY demand is a demand in which tne emergency generator is started, but no attempt is made to load the This indicator measures the total unrehabihty of emergency generator, diesel generators, in general, unreliabihty is the ratio of unsuccessful operabons (starts or load runs) to the number
- 2) Number of Start Faltures: Any failure wtthin the of valid demands. Total unrehability is a combinabon of start emorgency generator system that prevents the unrehabihty and load-run unrehability, generator from achieving specified frequency and voltage is classified as a valid start faihire. This ENGINEERING ASSISTANCE REQUEST (EAR) includes any condsbon identified in the course of BREAKDOWN maintenanz inspections (with the emergency generator in standby mode) that definitely would have This indicator shows a breakdown, by age and prionty of the resulted in a start failure if a demand had occurred.
EAR. of the number of EARS assigned to Design Engineenng Nuclear and System Engineenng. This
- 3) Number of Load-Run Demands: For a vahd load 4un indicator tracks performance for SEP #62.
demand to be counted, the load-run attempt must rneet one or more of the following entena:
ENGINEERING CHANGE NOTICE (ECN) $TATUS A) A load-run of any duration that results from a real The number of ECNs that were opened. ECNs that were automabc or manual initiation.
cx)mpleted, and open backlog ECNs awaiting complebon by DEN for the reporting month. This indicator tracks B) A load-run test to satisfy the plant's foad and performance for SEP #62, duration as stated in each test's specificabons.
ENGINEERING CHANGE NOTICES OPEN C) Other special tests in which the emergency generator is expected to be operated for at least This indicator breaks down the number of Engineenng one hour wNie loaded with at least 50% of its Change Nobces (ECNa) that are assigned to Design design load.
Engineenng Nuclear (DEN), System Engineering, and Maintenance. The graphs provide data on ECN Facility
- 4) Number of Load-Run Failures: Aload4un failure Changes open, ECN Substitute Replacement items open, should be counted for any reason in which the and ECN Document Changes open. This indicator tracks emergency generator does not pick up load and run as performance for SEP #62.
predicted. Failures are counted during any vahd load-run demands.
EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS
- 5) Exceptions: Unsuccessful attempts to start or load-run should not be counted as vahd demands or failures Equipment forced outages per 1,000 crit cal hours is the g
when they can be attributed to any of the following:
inverse of the mean time between forced outages caused by N
equipmont failures. The mean time is equal to the number
) S trips that would be bypassed in the event of hours the reactor is enticalin a period (1,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />) an e ncy.
divided by the number of forced outages caused by equipment failures in that period.
B) Malfuncbon of equipment that is not required dunng an emergency.
EQUIVALENT AVAILABILITY FACTOR y
C) Intenbonal terminabon of a test because of This indicator is defined as the rabo of gross available abnormal conditions that would not have resutted generation to gross maximum generation, expressed as a in major diesel generator damage or repair, percentage. Available generation is the energy that can be produced if the Unit is operated at the maximum power level D) Malfunchons or operating errors which would not permitted by equipment and regulatory limitations.
have prevented the emergency generator from Maximum genersbon is the energy that can be produced by being restarted and brought to load within a few a unit in a given period if operated conbnuously at maximum mlnutes.
- caoacity, 67
PERFORMANCE INDICATOR DEFINITIONS FORCED OUTAGE RATE
- 2) One or more d:ys tway from work (:xcluding th3 day of the accident); and This indicator is defined as the perci Ltage of time that the
- 3) Fatabbes.
unit was unavailable due to forced events compared to the time planned for electrical generaton. Forced events are Contractor personnel are not included for this indicate.
failures or other unplanned mr@ bons that require removing the unit from service tefore the end of the next weekend.
IN LINE CHEMISTM INSTRUMENTS OUT OF SERVICE Forced ever.ts indude start-up failures and events initiated while the unit is in reserve shutdown (l e., the unit is Total number of in4ine chemistry instruments that are out-of-available but not in service).
service in the Secondary System and the Post Accident Sampling System (PASS).
FUEL REllABILITY INDICATOR LICENSE CANDIDATE EXAMS This indicator is defined as the steady-state primary coolant 1-131 achvity, corrected for the tramp uranium contribution This indicator shows the number of SRO and/or RO qutzzes and normalized to a common punfication rate. Tramp and exams that are administered and passed each month.
uranium la fuel whkt) has been depostted on reactor core This irdcator tracks training performance for SEP #68.
Intemals from previous defective fuel or is present on the surface of fuel elements from the manufactunng process.
LICENSED OPERATOR REQUALIFICATION TRAINING Steady state is defined as conbnuous operabon for at least three days at a power level that does not vary more than +
The total number of hours of training given to each crew or 5%. Plants should collect data for this indicator at a dunng each cycle. Also provided are the simulator training power level above 85% when possible. Plants that did not hours (which are a subset of the total training hours), the operate at steady-state power above 85% should collect number of non-REQUALIFICATION training hours and the data for this indicator at the highest steady-state power level number of exam failures. This indicator tracks training attained dunng the month, performance for SEP # 68.
The density correction factor is the rabo of the specific LICENSEE EVENT REPORT (LER) RO DT CAUSE volume of coolant at the RCS operating temperature (540 BREAKDOWN degrees F., Vf a 0.02146) divided by the specific volume of coolant at normal letdown temperature (120' F at outlet of This indicator shows the number and root cause code for the letdown cooling heat exchanger, VI = 0.016204). which Licensee Event Reports. The root cause codes are as results in a density correct 6on factor for FCS equal to 1.32.
follows:
GROSS HEAT RATE
- 1) Administrative Control Problem. Management and supervisory deficiencies that affect plant programs or Gross heat rate is defined as the rabo of total thermal activites (i.e., poor planning, breakdown or lack of energy in British Thermal Units (BTV) produced by the adequate management or supervisory control, incorrect reactor to the total gross electncal energy produced by the procMures, etc).
generator in id60watthurs (KWH).
- 2) Licensed Operator Error. This cause code captures HAZARDOUS WASTE PRODUCED errors of omission / commission by licensed reactor operators dunng plant activities.
The total arnount (in Kilograms) of non-halogenated hazardous waste, halogenated hazardous waste, and other
- 3) Other Personnel Error. Errors of hazardous waste produced by FCS each month.
omission / commission mmnvtted by non-licensed personnel involved in plant activities.
HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE
- 4) Maintenance Problem. The intent of this cause code is to capture the full range of problems wtiich can be The sum of the known (planned and unplanned) unavailable attributed in any way to programmatic deficiencies in hours and the estimated unavailable hours for the high the maintenance functional organization. Activities pressure safety injection system for the reporting penod included in this category are maintenance, testing, divided by the entical hours for the reporting penod surveillance, calibrabon and radiation protechon.
multipled by tha number of trains in the high pressure safety injechon system.
- 5) DesigrVConstruction/ Installation / Fabrication Problem. This cause code covers a full range of INDUSTRIAL SAFETY ACCIDENT RATE. INPO programmatic This indicator is defined as the number of accidents per 200,000 man-hours worked for all utility personnel permanently assigned to the stabon that result in any of the following:
- 1) One or more days of restricted work (excluding the day of the accadent);
68
PERFORMANCE INDICATOR DEFINITIONS deficienoes in the areas of design, construcbon, This indicator tracks rnaintenance partornnance for EMP installabon, and fabricabon (i.e., loss of control power dae to
- 36 MAXIMUM INDMDUAL RADIATIOf4xPOS US, underrated fuse, equipment not quahfied for the environment, etc.).
The tcNat mammum amount of radiation recevedbyan indMdual person
- 6) Equipment Failures (Electronic Piece-Parts or Environmental Related Failures). This code is used working at FCS on a monthly, quarterly, and annua %gis, for spurtous failures of electronic p6ece-parts and failures due to meteorological condtons such as MWD PLANNING STATUS (CYCLE 17 REIppEllNG bghtning, ice, high winds, etc. Generally, it indudes OUTAGE) spunous or one-time failures. Electnc components included in this category are circuit cards, rectifiers, The total number of Maintenance Work Docurpents h at bistables, fuses, capacitors, diodes, resistors, etc.
have been approved for indusion in the Cyao 17 Refueling Outage and the number that are ready to *org (parit LOGGABLE/ REPORTABLE INCIDENTS (SECURITY) staged, planning complete, and all other paperworw sy a
for field use). Also induded is the numtser og lAWDsthat The total number of securtty incidents for the reporting have been engineenng holds (ECNs, procedures and other month depicted in two graphs. This indicator tracks security rniscellaneous engineering holds), parts hbid, (parts slaged, performance for SEP #$8.
not yet inspected, parts not yet arrived) ancs plaming hold (Job scope not yet o>mpleted). Maintensneg Work R% pests MAlfGENANCE OVERTIME (MWRs) are also shown that have been ident ied for tre f
Cycle 17 Refueling Outage and have not yet geen cWorted The percent of overtime hours compared to normal hours for to M W Os.
maintenance. This indudes OPPD personnel as well as contract personnel.
NUMBER OF CONTROL ROOM EQUIPMENT DEFICIENCIES MAINTENANCE WORKLOAD BACKLOGS A control room equipment deficiency (CRD)is defineca as This indicator shows the backlog of norHNtage any component which is operated or carltrc>tled frorn the Maintenance Work Orders remaining open at the end of the Control Room, provides indication or alarrrn to the Corstrol reporting month. Maintenance dassifications are defined as Room, provides tesbng capabilibes frorn the contrd Roorn, follows:
providee automatic acbons from or to the Contrd Rocm, or provides a passive funcbon for the Control Moorn and has Corrective. Repair and restoration of equiprnent or been,dentified as deficier..,i.e., does not Derfo m uncs r all r
e components that have failed or are ma' functioning and condibons as designed. This definibon also apphesIO the are not performing their intended funcbon.
Allemate Stutdown Panels Al.17g, Al t M. and Al-21:2 PreYontive. Acbons taken to maintain a piece of A plant component which is deficient or inoperable is equipment within design operahng conditions, prevent considered an
- Operator Work Around(CNA)Iterrfif some equipment failure, and extend its life and tre performed other action is required by an operator to compensate for the pnor to equipment failure.
condibon of the component. Some exarop4esof DAs are:
Non Corrective / Plant improvements. Maintenance
- 1) The controf room level indicator does iot wort bNt a r
activities performed to implement stabon improvements or local sight glass can be read by an O erstor art in the b
to repair non-plant equipment.
plant; Maintenance Work Priorttles are defined as:
- 2) A defident pump cannot be repaired Lwegute replacement parts require a long lea:1 tm for e
Emergency. Condibons which significantly degrade purchase /dehvery, thus requinng the r evndanlmimp e
stabon safety or availabihty, to be operated continuously; immediate Action Equipment deficiencies which
- 3) Special schons are required by an 04erstor beosause of significantly oegrade stabon reliabihty. Potenbal for unit equipment design problems. These a tions rwy be c
shutdown or power reduction.
desenbed 6n Operabons Memorandurns, Operator Notes, or may require changes to Opt >rabng Operations Concern. Equipment deficencies whid)
Procedures; hinder stabon operation.
- 4) Deficient plant equipment that is required to be Lased Essential. Roubne corrective maintenance on essental during Emergency Operatin Procedt.tres or Ab%rmal u
stabon cystems and equipment.
Operatng Procedures; Non-Essential. Roubne correcuve maintenance on non-
- 5) System indicabon that provides criticial infortnahon essential station systems and equipment.
during normal or abnormal operations Plant improvement. Non corrective maintenance and plant improvements.
69
PERFORMANCE INDICATOR DEFINITIONS NUMBER OF MISSED SURVEILLANCE TESTS PERCENTAGE OF TOTAL MWDs COMPLETED PER RESULTING IN LICENSEE EVENT REPORTS MONTH IDENTIFIED AS REWORK The humber of Surveil!ance Tests (STs) that result in The percentage of total MWDs completed per month Licensee Event Reports (LERs) dunng the reporting rnonth.
Idenbfied as rework. Rework activities are 6denbfed by Th6s indicator tracks missed STs for SEP #60 & 61, maintenance planning and craft. Rework is: Any additional OPEN INCIDENT REPORTS work required to correct deficiencies discovered during a l
failed Post Maintenance Test to ensure the This indicator displays the total number of open incident component' system passes subsequent Post Maintenance l
Reports (irs), the number of irs that are greater than six Test l
months old and the number of open significant irs.
PERCENT OF COMPLETED SCHEDULED OUTSTANDING MODIFICATIONS MAINTENANCE ACTIVITIES The number of Modificabon Requests (MRs)in any state The percent of the number of completed maintenance between the issuance of a Mod.ficabon Number and the activibes as compared to the number of scheduled Complebon of the drawing update.
maintenance act vites each month. This percentage is j
shown for all maintenance crafts. Also shown are the
- 1) Form FC ii33 Backlog /In Progress. This number number of emergent MWDs. Maintenance activibes include represents modificabon requests that have not been MWRs, MWDs, STs, PMOs, calibrabons, and other plant approved during the reporting month.
miscellaneous activtt es. This indicator tracks Maintenance periormance for SEP 833.
- 2) Modification Requests Being Reviewed. This category includes:
PERFORMANCE INDICATOR INDEX A) Modificabon Requests that are not yet reviewed.
This indicator index is calculated from a weighted combination of eleven performance indicator values, which B) Modification Requests being reviewed by the include the following: Unit Capability Factor, Unit Capability Nuclear Projects Review Committee (NPRC).
Loss Factor, HPSI, AFW, Emergency AC Power System.
Unplanned Automate Scrams, Collective Radiabon C) Modificabon Reavests being reviewed by the Exposure, Fuel Rehability, Thermal Performance. Secondary Nuclear Projects Committee (NPC).
System Chemistry, and Industrial Safety Accident Rate.
These Modificabon Requests may be reviewed several PREVENTABLE / PERSONNEL ERROR LERs times before they are approved for accomphshrtent or canceled. Some of these Modification Requests are This indicator is a breakdown of LERs. For purposes of retumed to Engineenng for more informabon, some LER event classificabon, a
- Preventable LER* la defined as:
approved for eve'uation, some approved for study, and some approved or planning. Once planni, J is completed An event for which the root cause is personnel error (i.e.,
and the scope nf the work is clearty defined, these inappropnate action ty one or more individuals),
Modificahon Requests may be approved for accomphshment inadequate administrative controls, a design construction, with a year assigned for construction or they may be installation, installation, fabncaton prob,em (involving canceled. All of these d,fferent phases require review, work completed by or supervised by OPPD personnel) or a maintenance problem (attributed to inadequate or
- 3) Design Engineering Backlog'In Progress. Nuclear improper upkeep / repair of plant equipment). Also, the Planning has assigned a year in which construction will cause of the event must have occurred within be completed and design work rnay be in progress.
approximately two years of the
- Event Date" specified in the LER (e.g., an event for which the cause is attributed
- 4) Construction Backlog!!n Progress. The Construction to a problem with the original design of the plant would Package has been issued or coretruchon has begun not be considered preventable),
but the modificabon has not teen accepted by the System AcceptanN Committee (SAC).
For purposes of LER event classificabon, a
- Personnel Error" LER is defined as follows:
- 5) Design Engineering Update Backloglin Progress.
PED has received the Modificabon Completion Report An event for which the root cause is inappropriate action but the drawings have not been updated.The above on the part of one or more individuals (as opposed to i
mentioned outstanding modifications do not include being attributed to a department or a general group).
modificabons which are proposed for cancellabon.
Also, the inappropriate action must have occurred within approximately two years of the
- Event Date* specifed in OVERALL PROJECT STATUS (REFUELING OUTAGE) the LER.
This indicator shows the status of the projects which are in the scope of the Refuehng Outage.
70
PERFORMANCE INDICATOR DEFINITIONS Add!ttonally, each cont dessified as a ' Personnel Error
- SAFETY SYSTEM FAILURES should also be dassified as
- Preventable.' This indicator trends personnel performance for SEP llem #15.
Safety system failures are any events or conditions that muld prevent the fumilment of the safety functions of PRIMARY SYSTEM LITHlUM % OF HOURS OUT OF structures or systems. If a system consists of multple LIMIT redundant subsystems or trains, failure of all trains conshtutes a safety system failure. Failure of one of two or The percent of hours out of limit are for lith 6um div6ded by more trains is tot counted as a safety system failure. The the total number of hours possible for the month.
definition for the indicator parallels NRC reporting requirements in 10 CFR 50.72 and 10 CFR 50.73 The PROCEDURAL NONCOMPLlANCE INCIDENTS following is a list of the major safety systems sub systems.
(MAINTENANCE) and components monitored for this inr%.or:
)
The number of identified inddents conceming maintenance Acddent Monitoring instrumentation, Auxthary (and procedural problems, the number of dosed irs related to Emergency) Feedwater System, Combushble Gas the use of procedures (indudes the number of closed irs Control, Component Coohng Water System, Containment caused by procedural noncompliance), and the number of and Containment isolabon, Containment Coolant closed procedural noncomphance irs. This indicator trends Systems, Control Room Emergency Venblabon System, personnel performance for SEP #15,41 and 44.
Emergency Core Cookng Systems Engineered Safety Features instrumentation Essential Compressed Air PROGRESS OF CYCLE 17 OUTAGE MODIFICATION Systems, Essental or Emergency Service Water, Fire PLANNING Oetecbon or Suppression Systems, tsolabon Condenser, Low Temperature Overpressure Protection, Main Steam This indicator shows the status of modificabons approved for Une isolation Valves. Onsite Ernergency AC & DC Power complebon dunng the Refuehng Outage.
w/Distnbubon, Radiabon Monitonng instrumentabon, Reactor Coolant System Reactor Core isolabon Coohng PROGRESS OF 1995 ON LINE MODIFICATION System, Reactor Tnp System and Instrumentabon, PLANNING Recirculation Pump Trip Actuation Instrumentation, Residual Heat Removal Systems, Safety Valves, Spent This indicator shows the status of modifications approved for Fuel Systems Standby Liquid Control System and complebon during 1995 Ultimate Heat Sink.
RADIOLOGICAL WORK PRACTICES PROGRAM SECONDARY SYSTEM CHEMISTRY PERFORMANCE INDEX The number of identified poor radiological work practices (PRWPs) for the reporting rnanth. This indicator tracks The Chemistry Performance Index (CPI)is a calculabon radiological work performance for SEP #52.
based on the concentration of key impunbes in the secondary side of the plant. These key impurit es are the RATIO OF PREVENTIVE TO TOTAL MAINTENANCE &
must likely cause of deteriorabon of the steam generators.
PREVENTIVE MAINTENANCE ITEMS OVERDUE Criteria for calculatng the CPI are:
The ratio of preventive maintenance (indudmg surveillance
- 1) The plant is at greater than 30 percent power; and tesbng and calibration procedures) to the sum of non outage cor acbve maintenance and preventive maintenance
- 2) the power is changing less than 5% per day, completed over the reporting period. The ratio, expressed as a percentage, is calculated based on man-hours. Also The CPI is calculated using the following equabon:
displayed are the percent el preventive maintenance items in the month that were not completed or administrabvely CPI = ((sodium /0.79) + (Chloride /1.52) + (Sutfate/1.44) +
dosed by the scheduled date plus a grace penod equal to (Iron /3 30) + (Copper /0.30)+(Condensate O2/2.90)y6 25% of the scheduled interval. This indicator tracks preventive maintenance activities for SEP #41.
Where: Sodium, sulfate, chloride and condensate dissolved oxygen are the monthly average blowwwn concentrations RECORDABLE INJURY /lLLNESS CASES FREQUENCY in ppb, iron and copper are monthly time weighted average RATE feedwater concentrabons in ppb. The denominator for each of the five factors is the INPO median value. If the monthty The number of injunes requinng rnore than normal first aid average for a specific parameter is less than the INPO per 200,000 marbhours worked. This indicator trends median value, the median value is used in the calculation.
personnel performance for SEP #15,25 and 26.
REPEAT FAILURES The number of Nuclear Plant Rehabihty Data System (NPROS) components with more than one failure and the number of NPRDS components with more than two failures for the eighteen-month CFAR penod.
71
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PERFORMANCE INDICATOR DEFINITIONS SiONIFICANT EVENTS
- 2) Jumpers and blocks which are installed for Surveinance Tests, Maintenance Procedures, Cahbrabon Procedures, S6gnifkant events are the events 6dentsed by NRO staff Special Procedures or Operabng Procedures are not through detaned screening and evaluabon of operating considered as temporary modAcations unless the experience. The scrocrung process includes the daity jumper or blod remains in place after the test or review and discussion of all reporied operabng reactor procedure is complete. Jumpers and blocks installed in events, as well as other operational data such as special test cr lab instruments are not considered as temporary tests or construchon acuvities. An event 60entfied from the modAcabons.
screening process as a 66pnAcant event candidate is further evaluated to determine if any actual or potenbal threat to the
- 3) Scaffold is not considered a temporary rnodificabon.
health and safety of the pubhc was involved. SpecAc Jumpers and blocks which are installed and for which examples of the type of crtierta are summarized as follows:
MRs have been submitted will be considered as
- 1) Degradabon of important safety equipment; temporary modAcabons until final resolubon of the MR and the jumper or block is removed or is permanenUy
- 2) Unexpected plant response to a trans6ent; recorded on the drawings. This indicator tracks temporary modAcabons for SEP #62 and 71,
- 3) Degradation of fuelintegrity, pnmary coolant pressure boundary, important assodated features; THERMAL PERFORMANCE
- 4) Scram with complicabon:
The rabo of the design gross heat rate (co rected) to the adjusted actual gross heat rate, expressed as a percentage.
- 5) Unplanned release of radioactivity; UNIT CAPABILITY FACTOR
- 6) Operabon outside the limits of the Technical Spedficabons:
The rabo of the avatable energy genersbon over a given bme period to the reference energy genershon (the energy
- 7) Other.
that could be produced if the unit were operated conhnuously at full power under reference ambient INPO signAcant events reported in this indicator are SERs condibons) over the same bme period, expressed as a (Significant Event Reports) which inform utilities of percentage, signAcant events and lessons teamed idenbfied through the SEE-IN screening process.
UNIT CAPACITY FACTOR SPARE PARTS INVENTORY VALUE The net electrical energy generated (MWH) divided by the product of maximum dependable c2.pacity (net MWe) hmes The dollar value of the spare parts inventory for FCS during the gross hours in the reporbng period expressed as a the reportng period.
percent. Net electrical energy generated is the gross electrical output of the unit measured at the output terminals STAFFING LEVEL of the turbine generator minus the normal stabon service loads during the gross hours of the reporting penod, The actual stamng level and the authortzed staffing level for expressed in megawatt hours, the Nuclear Operations Dreision, The Producbon Engineenng Division, and the Nuclear Services Division, UNPLANNED AUTOMATIC REACTOR SCRAMS PER This indicator tracks performance for SEP #24, 7,000 CRITICAL HOURS STATION NET GENERATION This indicator is defined as the number of unplanned automabc scrams (RPS logic actuabons) that occur per The net genersbon (sum) produced by the FCS dunng the 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of entical operabon, reporting month.
The value for this indicator is calculated by multiplying the TEMPORARY MODIFICATIONS total number of unplanned automatic reactor scrams in a spedfic time penod by 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, then dividing that The number of temporary mechanical and electrical number by the total number of hours citical in the same configurabons to the plant's systems.
bme period. The indicator is further defined as follows:
- 1) Temporary configurabons are defined as electrical
- 1) Unplanned means that the scram was not an anticipated jumpers, electncal blocks, mechanical)umpers, or part of a planned test.
mechanical blocks which are instahed in the plant e
operabng systems and are not shown on the latest
- 2) Scram means the automatic shutdown of the retctor by revision of the PalD, schematic, connection, wiring, or a rapid inserton of negative reactrvity (e 9., by control flow diagrams.
ods, liquid injection system, etc.) that is caused by actuabon of the reactor protecton system. The signal may have resulted from exceeding a set point or -
spunous.
I 1
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PERFORMANCE INDICATOR DEFINITIONS
- 3) Automatic means that the initial signal that caused VIOLATION TRE ND actuation of the reactor protechon system logic was prov6ded from one of the sensor's monttonng plant This indicator is def ned as Fort Calhoun Station Cited i
parameters and condibons, rather than the manual Violabons and Non-Cned Violatons trended over 12 months.
scram switches or, manual turbine tnp swit:hes (or Additionally, Cited Violation for the top quartile Region IV push-buttons) provided in the main control room.
plant is trended over 12 months (lagging the Fort Calhoun Station trend by 2 3 months). It is the Fort Calhoun Station
- 4) Cnbcal means that during the steady-state condtbon of goal to be at or below the cited v6olabon trend for the top the reactor prior to the Scram, the effecbve multiplicatic quartile Region IV plant.
(k ) was essentially equal to one.
UNPLANNED CAPABILITY LOSS FACTOR VOLUME OF LOW LEVEL SOLID RADIOACTIVE WASTE The ratio of the unplanned energy losses during a given This indicator is defined as the volume of low-level sohd period of bme, to the reference energy generation (the radioachve waste actualty shipped for burial. This indicator energy that could be produced if the unit were operated also shows the volume of low level radioactive waste which conbnuously at full power under reference ambient is in temporary storage, the amount of radioachve c41 that condsbons) over the same time penod, expressed as a has been shipped off-site for processing, and the volume of percentage.
Solid dry radioactive waste which has been shipped off-site for processing. Low 4evel solid radioactive waste consists of UNPLANNED SAFETY SYSTEM ACTUATIONS.(INPO dry active waste, sludges, resins, and evaporator bottoms
+DEFINillON) generated as a result of nuclear power plant operabon and maintenance. Dry radioactive waste includes contaminated This indicator is defined as the sum of the following safety rags, cleaning matenals, disposable protective dothing, system actuations:
plastic containers, and any other material to be disposed of at a low-level radioactive waste disposal site, except resin,
- 1) The number of unplanned Emergency Core Cooling sludge, or evaporator bottoms. Low 4evel refers to all System (ECCS) actuabons that result from reaching an radioachve waste that is not spent fuel or a by-product of ECCS actuabon set point or from a spurtoustinadvertent spent fuel processing. This indicator tracks radiological ECCS signal work grformance for SEP a54,
- 2) The number of unplanned emergency AC power system actuabons that result from a loss of power to a safeguards bus. An unplanned safety system actuation occurs when an actuation set point for a safety system is reached or when a spur 60us or inadvertent signal is generated (ECCS only), and major equipment in the system is actuated. Unplanned means that the system actuabon was not part of a planned test or evolution.
The ECCS actuabons to be counted are actuabons of the high pressure injechon system, the low pressure injeebon system, or the safety injechon tanks.
UNPLANNED SAFETY SYSTEM ACTUATIONS. (NRC DEFINITION)
The number of safety system actuations which include (gnty) the High Pressure Safety injection System, the Low Pressure Safety injechon System, the Safety injechon Tanks, and the Emergency Diesel Generatocs. The NRC classificabon of safety system actuabons includes actuabons when major equipment is operated and when the logic systems for the above safety systems are challenged.
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73 m
SAFETY ENHANCEMENT PROGRAM INDEX l
The pulpose of the Safety Enhancement Program (SEP) Performance Indicators Index is to list performance indicators related to SEP ltems with parameters that can be trended.
AEPleference Number 15 Eagt
. Increase HPES and IR Accountability through use of Performance Indicators Procedural Noncompliance incidents (Maintenance).................................,,. 43 Recordable injury / Illness Cases Frequency Rate,,.....................................
10 Clean Controlled Area Contaminations 21,000 Disintegrations / Minute Per Probe Area..........
17 Preventable / Personnel Error LERs................................................. 18 SEP_ Referente Numbers 25. 26. & 27
. Training Program for Managers and Supervisors implemented
. Evaluate and implement Station Standards for Safe Work Practice Requirements e implement Supervisory Enforcement of Industrial Safety Standards Disabling lajurylltiness Frequency Rate.............................,,...............
15 Recordable injury /'llness Cases Frequency Rate.............................,,....
16 SEP Reference Numburli
. Develop Outage and Maintenance Planning Manual and Conduct Project Management Training MWO Plannlag Status (Cycle 17 Refueling Outage)..............,........................ 59 SS ED's Overall Project Status.....,................................................ 60 Overall Project Status (Cycle 17 Refueling Outage).................,,...............,,., 61 Progress of Cycle 17 Outage Modification Planning...................,,,,.....,,,,.., 63 SEP Reference Number 33
. Develop On Line Maintenence and Modification Schedule 1996 On 'ine Modificatiun Planning.................................................. 62 AEP Reference Number.36
. Rsduce Correctiva Non-Outage Baellog Maintenance Workload Backlogs (Corrective Non-Outage),...,,,,.......,............. 39 SEP Reference Numbers 41 & 44
. Develop ared implement a Preventive Maintenance Schedule
. Compilsnce With and Use of Procedures Ratio of Preventive to Total Muintenance & Preventive Maintenance items Overdue.....,,.,,, 40 Procedural Noncompliance inciJents (Maintenance).........,,........................,,. 43 SEP Reference Number 46 Design a Procedures Control and Administrative Program D ocu ment Review.........................................,.............,,..,.... 4 8 74
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SAFETY ENHANCEMENT PROGRAM INDEX SEPlittance Number 52 Eagn
. Estabilsh Supervisory Accountability for Workers Radiological Practices Radiological Work Practices Program......................................... 47 3
SLEP Reference Nn:nher 54
- Complete impler. aitation of Radiological Enhancement Program Clean Controlled Area Disintegrations 21,000 Counts / Minute Per Probe Area.................
17 Collective Radiation Exposure...............................................
11 Volume of Lc,w-Level Solid Radioactive Waste 12 Contaminated Radiation Controlled Area............................................ 46 l
= Revise Physical Security Training and Procedure Program Loggable/ Reportable incidents (Security)
........ 49 1
SEP Reference Numbers 60 & 61
. Improve Controls Over Surveillance Test Program
. Modify Computer Program to Correctly Schedule Survelliance Tests Number of Missed Surveillance Tests resulting in Licensee Event Reports...
.,........... 23 SEP Reference Number 62
. Establish Interim System Engineers Temporary Modification s....................................................,.. 50 Engineering Assistance Request (EAR) Breakdown................................. 52 Engineering Change Notice Status
..............., 53 Engineering Change Notices Open............................................... 54 SEP Reference Number 68
. Asscss Root Cause of Poor Operator Training and establish means to monitor Operator Training Licensa Operator Requahfication Training
.... 56 License Candidate Exams.....................................
........ 57 SEP Reference Number 71
. Improve Controls over Temporary Modifications Temporary Modifications.......................,.......
....... 50 75
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