ML20203B099
| ML20203B099 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/31/1998 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20203B094 | List: |
| References | |
| NUDOCS 9902100223 | |
| Download: ML20203B099 (62) | |
Text
{{#Wiki_filter:OMAHA PUBLIC POWER DISTRICT l , I I
; ~ 7 ,,j g " ( . _ . .
l . . - . ;j. . .[ c Q ;-. $ ,l5 Y
.dj;i
>i
'~ '
9 ilpllllip3 ,. ., g l 3 -w a I I I I FORT CALHOUN STATION E PERFORMANCE INDICATORS E DECEMBER 1998 [ a _ I A - _-___________.
OMAHA PUBLIC POWER DISTRICT I I I
.- , [r ,ffh
; f. - .,
1 . Li.L~ i I ' m: l . . . . 1 . I - I I FORT CALHOUN STATION [ PERFORMANCE INDICATORS [ DECEMBER 1998 [ [ ;;g21ggggg;;gagg{s R
Table of Contents / Summary ease TABLE OF CONTENTS /
SUMMARY
. .. . . .. . . . 1 ,
MONTHLY.
SUMMARY
REPORT ... .. .. .. .. . .4 , WANO PERFORMANCE INDEX TREND . . , , ... . . . .. . 5 WANO PERFORMANCE INDEX INDICATOR .. . . . . .... . . . 6 PERFORMANCE INDICATORS
SUMMARY
REPORT .. . . 7 INPO NOTEWORTHY / SIGNIFICANT EVENTS . .. . 8 WANO PERFORMANCE INCICATORS Unit Capability Factor .. . . .. ... . . . 10 Unplanned Capability Loss Factor . . .. . . 11 Unplanned Automatic Reactor SCRAMS per 7000 Hours . .. . 12 High Pressure Safety injection System . . . . .. . . 13 Auxiliary Feedwater System . ... . . . . 14 Emergency AC Power System .. 15 Thermal Performance . .. . ... . . . . 16 Fuel Reliability indicator . . . .. . . 17 Secondary System Chemistry . .. . . . 18 Collective Radiation Exposure . . . . . . . . . .. 19 industrial Safety Accident and Disabling injury / Illness Rate . . 20 Volume of Low Level Radioactive Waste . .. . . . . 21 Personnel Error Rate . .. . .. ... . 22 j i SAFE OPERATIONS i Recordable injury / Illness Cases Frequency Rate . . 24 Clean Controlled Area Contaminations _>1,000 Disintegrations / Minute per Probe Area . 25 1
Table of Contents / Summary Preventable / Personnel Error LERs . . . 26 Licensee Event Report (LER) Root Cause Breakdown . 27 Violation Trend . . . . . .. . ... . . . . . 28 COST Cents Per Kilowatt Hour . . .. . . 30 DMSiON AND DEPARTMENT PERFORMANCE INDICATORS Maintenance Workload Backlog (Corrective Non-Outage) . . . 32 Ratio of Preventive to Total Maintenance . . . 33 Procedural Noncompliance incidents 34 Contaminated Radiation Controlled Area . .. . . . 35 Radiological Work Practices Program .. . . . . . 36 Document Review ... . . . . . 37 Security incidents .. . ... . . .. . . . 38 Temporary Modifications . . .. . . . 39 Outstanding Modifications . . . . . .. . (Data unavailable due to RAMS conversion) Engineering Assistance Request (EAR) Breakdown (Data unavailable due to RAMS conversion) Engineering Change Notices Status .. . .. ..
. (Data unavailable due to RAMS conversion)
Open .. . . . . . . (Data unavailable due to RAMS conversion) Maintenance Rule SSC Unavailability . . . . . . 40 Licensed Operator Requalification Training .. . . . ... ... . . . 41 License Candidate Exams . .. .. . . . . . . 42 Cycle 19 Refueling Outage MWD Planning Status . .... . . . . . . 43 Component Testing Department, Special Services Engineering Department 1998 Outage . . 44 Progress of 1999 Refueling Outage Modifications Cycle 19 . . . . 45 Progress of Cycle 19 Outage MODS and ECN's Added to 1999 RFO After Freeze 46 2
. Table of Contents / Summary 4 Progress of 1998 On-Line Modification Planning .. ... . . . . 47 i ACTION PLANS. DEFINITIONS. SEP INDEX 1 Action Plans . .. ... .. . . . . . .. . .. ... . . ., 49 Performance Indicator Definitions . .. . .... .. . . . ... .. . 50 Safety Enhancement Program index .. . . .. . ... . ... . .. . 55 Current Production and Operations" Records"/ Station Operating Cycles and RFO Dates . . 57 Milestone Schedule . . . ... .. . .. . . . . 58 Monthly Performance Indicator Sources . .. . .. . .. . . 60 3 i
FORT CALHOUN STATION Monthly Summary OPERATIONS During the month of December 1998, the Fort Calhoun Station (FCS) operated at a nominal 100% power. Normal plant maintenance, and equipment rotation activities were performed. WANO PERFORMANCE INDICATORS 1 l I The overall WANO Performance Index was 88% during the 4th Quarter of 1998. Significant percentage point losses are attributed to the WANO Performance Indicators listed below-
- 1. The Unit Capabliity Factorindicator, calculated over the previous 24 months, contributed to a 1.3 point loss as a result of unplanned energy losses defined on page 10. l l
- 2. The Unpienned capability Loss Factorindicator calculated over the previous 24 months, contributed to a 5.5 point loss as a result of unplanned energy losses defined on pages 10 and 11.
- 3. Tne coisective Radiation Exposure indicator, calculated over the previous 24 months, contributed to a 3.1 point loss, which was attributed to fuel failures and recent high exposure jobs during the refueling outage on page 19.
1 l
- 4. The Emergency AC Power hdicator, calculated over the previous 24 months, contributed to a 1.5 I l point loss, which was a result of on-line maintenance on page 15.
l
- 5. The Chemistry Performance inderindicator, calculated over the previous 12 months, contributed to a 0.4 point loss, which is due to copper tubes in heat exchangers and mechanical shock to systems in the past year from forced outages defined on page 10.
i i l l 4 i
l 18.00 8 16.00 t s M AXlM U M VAL U E EThnf Otr '98 g Fourth Qtr '98 14.00 - S
~
1a.00 888 888 8 666 666 6 10.00 -
"hy g ggg ggg 8.00 - 8 k8 8 gog 6.00 - 0,8
,- *bd OOO een 4.00 -
2.00 - . 0.00 l + + + + i 1
+ + + H UCF UCLF HPSI AFW EACP CRE UA7 FRI CPI TPI ISAR WANO PERFORMANCE INDEX INDICATORS This graph shows the dfference between Third Qtr '98 and Fourth Qtr '98 actual values achieved by Fort Calhoun.
CALCULATED OVER A 24 MONTH PERIOD MAXIMUM / ACTUAL VALUES TREND UCF Unit Capability Factor 16/14.70 Positive UCLF Unplanned Capability Loss Factor 12/ 6.50 Positive HPSI High Pressure Safety injection 10/10.00 Positive AFW Auxiliary Feedwater 10/10.00 Positive EACP Emergency AC Power 10/ 8.50 Negative UA7 Unplanned Auto Scrams / 7000 Hours 8 / 8.00 Positive CRE Collective Radiation Exposure 8/ 4.70 Neutral CALCULATED OVER A 12 MONTH PERIOD TPI Thermal Performance Indicator 6 / 6.00 Positive CPI Secondary Chemistry indicator 7/ 6.60 Positive ISAR Industrial Safety Accident Rate 5 / 5.00 Positive CALCULATED OVER A QUARTERLY PERIOD FRI Fuel Reliability Indicator 8 / 8.00 Positive 5
PERFORMANCE INDICATORS
SUMMARY
REPORT PDSITIVE TREND REPORT ADVERSE TREND REPORT A performance hdicator with data representng three consecunve A performance hdicator with data representing three months ofimproving performance or three consecunve months of consecutive months of declining performance or three consecutive performance that is superior to the stated goal is exhbiting a months of performance that is trending toward declining as positive trend per Nuclear Operations Division Quality Procedure determined by the Manager - Nuclear Licensing, consstutes an 37 (NOD-QP-37). The foliosig performance indicators exhibited adverse trend per Nudear Operations Dusion Quality Procedure positive trends for the reporting month: 37 (NOD-QP-37). A supenisor whose performance hdcator exhbits an adverse trend by this definition may specify in written
, Unit Caoabiltv Factor (Page 10) form (to be published h this report) why the trend is not adverse.The follovdng performance hdicators exhbited adverse UnolannedCapablev Loss Factor (Page 11) trends for the reporting month.
Unolanned Automatic Reactor Scrams (Page 12) Temporary Modineations (Page 39) Hiah Pressure SafetyIniecton System Safety Svetem N 6 n,.,w (Page 13) INDICATORS NEEDING INCREASED MANAGEMENT ATTENTION REPORT Aux. Feed Water Svstem Safety Svstem Performance (Page 14) A performance hdicator with data for the repor1ing period that is Thermal N bo .is(Page 16) hadequate when compared to the OPPD goalis defined as "Needing increased Management Atention* per (NOMP-37). Fuel Reimbilty indmator (Page 17)
!~rn.ie,,cv AC Power (Page 15)
Industrial Safety Accident & disablina Inlurv/ Illness (Page 20) Clean Controlled Area Contaminations (Page 2b) Document Review (Page 37) Cents Per Kiowatt Hour (Page 30) t l 6
-ene.au.6A&.SM M6 4 WMe - re--dEEAJ*-. .M..-' ---h6mNMw em M 43.*,E &wmA-& -M 4 mmiin. dmarame.ast w ga 4.e m he.h ada am.e 4 w - p6m %demmis sk.-a N
i i i f l I i 1 I i i e l WANO i PERFORMANCE i ND CATORS I l 7
(. - _ _ i INPO NOTEWORTHY / SIGNIFICANT EVENTS [ I a Significant O Noteworthy u Historical I OTotal (Sianificant+ Noteworthy) I a Current Events Total (Total - Historical) 16 14 l 1010 11 g 10 g g 1 2 o o o o 3 g r- -- i r i i 1993 1994 1995 1996 1997 1998 l Definition: FCS Events, are screened and designated by INPO as Significant events that exhtait one or more of the following characteristics:
- 1) severe or unusual transients,2) safety system malfunctions or improper operations,3) major equpment damage caused by lengthy unplanned outages or segruficant reductions in power levels, replacement of or extensive repairs to major equipment, fuel rod fatures requiring a shutdown, and 4) other events involving nuclear safety and plant reliablity. Noteworthy events are determined to be not "Significant," but indicative of (i.e indcates the existence of precursors) maintenance, operations, administrative or management problems.
Historical Events are events classified by OPPD as caused by conditions greater than eighteen months old. j Analysis: Sianificant Events for December 1996, s e none Noteworthy Events since start of INPO Cvele: e inadvertent Fire Detection Panel Alarm Durbg Fire System Testing Results in Dscharging Carbon Doxide into the Generator Exciter e Emergency Temporary Modification to Ventiation System Places Plant b Unaruityzed Condtion. Transformer Fautt and Loss of Off-site Power Whle Shutdown Due to inadvertent Actuation of Transformer Deluge System.
. Atodiary Feedwater Pump Overspeed and Overpressurization of System Piping.
- Reactor Coolant Pump Cavitation During Planned Pressure Reducton P
Noteworihv Historical Events since start of INPO Cvele: e inappropriate Emergency Diesel Generator Operablity Criteria. Waste Disposal System Valves susceptible to over pressurization during post accident samping due to potential valve failure not considered during System Design. Containment Hydrogen Panel Components Exceed Qualified Life Due to incorrect Calculation Assumptions.
. Degraded Steam Generator Tube Left in Service Due to Personnel Error.
8
WANO PERFORMANCE INDEX TREND
-e-trdex Median : Index Best Quartile --*--Irdex Worst Quartite --+-Fort Calhoun f a 100 - -
100 95 - - 95 90 - - : : : - 90
~ - - -
85 - 85 80 - _ 80 75 - /: -
- 75 70 - -- 70 65 - -- 65 60 ; , ; . . , , , ; , .
; , ,. . , , : 60
% A n$A U @ @ @3 9 " e o@ e " . 9@@$9"8 8 8 U "
s s s e b$$$gggg!!!!-- ---- gsh ! $ $ ! - ,/
' FortCalhounindexCalculation Dec-98 OVERALL PERFORMANCE INDICATOR : WElGHT VALUE' INDEX. : PRODUCT Unit Capability Factor (2yr) 0.16 as.s 91.6 14.7 Unpl. Cap. Loss Factor (2yr) 0.12 s.s 54.0 s.s Unplanned Auto Scrams (2yr) 0.os o.o 100.0 s.o Safety System Performance:
PWR High Press. Inj. (2yr) 0.10 0.000 100.0 10.0 PWR Aux. Feedwater (2yr) 0.10 0.002 100.0 10.0 Emergency AC Power (2yr) 0.10 0.016 85.0 a.s Thermal Performance (1yr) 0.06 100.0 100.0 s.o Fuel Rel. (Most recent Qtr) 0.08 1.sE-04 100.0 s.o Chemistry Perf. Ind. (1yr) 0.07 1.15 94.4 3.s Collective Rad. Exposure (2yr) 0.0s 223 58.9 4.7 Ind. Safety Acc. Rate (1yr) 0.05 0.17 100.0 s.0
! l _
" Total. INDEX '48.0 9
UNIT CAPABILITY FACTOR I a Monthly Unit Capability Factor -e- 24 Month Unit Capability Factor ^ M {
- 2cos $ $g gg, ggggg$ , g g gg E8 8 g8= 88 888 "
g Rg:88: soo n . m : sg* : : : :'-': 8 8 = a _
$g -
a_ a - ', # " " E R wlll m-m { ecos j - , =,. _ _ _ . a_a r - - so os .
" 1998 RFO do o% -
20.0% . gg o o c o% - - --
- -- - , - + + -- J.- - + - - - ,
B B B g "B k k ayaB 8 8 8 8 8 8 8 8 8 8 8 8 kbbkhkb$h8bbbbb$$kb$h$bb
. Year to Date 12 Month 24 Month 36 Month I 81.4 % 81.4 % 85.8 % 83.2 %
UNIT CAPABILITY 1996 1997 1998 1999 2000 2001 2002 2003 FACTOR (PERCENT) ANNUAL GOAL 83.6 96.0 87.5 84.3 95.9 85.5 82.2 95.9 ANNUAL 78.1 90.1 81.4 PERFORMANCE TilREE YEAR 83.9 82.5 83.2 AVERAGE INDUSTRY MEDIAN 82.8 83.6 >87.0 ( 3 Year Aserage) Definition: Unit Capability Factor (UCF)is dermed as the ratio of the available energy generation over a ghen period of tone to the r reference energy generation over the same tune period, expressed as a percentage. { Analysis: The 24 Month UCF value remains at a steady but level value because of the December 1997 UCF, which is being replaced by the December 1998 UCF value, was also 100 percent. FCS has performed well throughout the year of 1998; however, the 1998 UCF Goal was not met, because of the extended 1998 Refueling Outage. A 24 month calculation of the WANO UCF indicator was 1 $.70 points out of 16.0 points. At the end of the Fourth Quarter 1998 the FCS Value was 14.70 which compares to the Third Quarter 1998 value of12.30. 10
UNPLANNED CAPABILITY LOSS FACTOR r c----l Monthly Unplanned Capability Loss Factor e- 24-Month Rolling Average Fort Calhoun Goal (3 5%) - +-. WAN O Industry Median (2.2%) 60% - h 50% - ( 40% - p 5 6 30% - - g 1998 RFo 20% - 10% - M o%
'=. .
. T T
. T-M "n = = ~
= =
a: - - : - -
== : : a a: aa 4$3<Ii1I}A$l=x$:ei!$g $4 4 !A81e Yeerto'Detoj ; '12 Month :- 24 MAnth 136 Month 3.8% 3.8% 6.9% 7.2%
UNPLANNED CAP. 1996 1997 1998 199b l2000 2001 2002 2003 LOSS FACTOR ANNUAL GOAL 3.0% 1.58 % 3.5% 3.0% 4.1% 3.0% 3.1% 4.1% ACTUAL CAPABILITY 7.9% 9.9% 3.8% THREE YEAR AVG. 6.6% 9.3% 7.2% Definition: Unplanned Capability Loss Factor (UCLF) is calculated as the ratio of Unplanned Energy Losses during a gun period of time to Reference Energy Generation. Unplanned Energy Loss (J defined as energy not produced such as: unscheduled shutdowns, outage extensions, or load reductions due to causes under plant management control if they are not scheduled at least four weeks in advanco. Analysis: , The 24 Month UCLF value remains at a esdy but level value because of the December 1997 UCLF, which is being replaced by the December 1998 UCLF '.r.lue, which was also O percent. FCS has peformed well throughout the year of 1998; however, the 1998 UCLF Gol wa. nM met, because of the unplanned capability loss that extended the 1998 Refueling Outage. The FCS 24-morith UGC of 6.9% exceeds the 2.2% median for the industry. A 24 month calculation of the WANO UCLF indicator was 6.b ceints out of 12.0 points. At the end of the Fourth Quarter the FCS Value was 6.5, which compares to the Th' d Guarter value of 5.40. l 11
l l UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7000 HOURS CRITICAL
--e- 12 Month Rolling Average
-+- FCS Reactor Scrams Per 7,000 Hours Critical for last 36 months
-- Fort Calhoun Goal (0.0)
-en- W ANO Industry Median (0)
-m- FCS Reactor Scrams - 1997-98 2 --
1-- 1998 RFO O: : : : : : : : -
- =
7 E E E I k @ E l
,$ E
< ] Z o
Year to Date 12 Month : ' " 24 Month as Month: , 0.0% 0.0% 0.0% 0.0% i UNPLANNED AUTOMATIC 1996 1997 1998 1999 2000 2001 2002 2003 REACTOR SCRAMS ANNUAL GOAL 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% 0.0% ACTUAL PERFORMANCE 0.0% 0.0% 0.0% THREE YEAR AVERAGE 0.48% 0.31 % 0.0% _Definitinn: Unplanned Automatic Scrams per 000 Critical Hours (UA7)is defined as the number of unplanned automatic scrams (RP's Logic Actuations) that occu per 7000 hours of entical operation. The value is calculated by multiplying the total of automatic scrams by the tc al hours criticalin the same time period. Analysis: FCS contnues to perform in the top industry quartile with Automatic Trip Free Operation. The last event at FCS, that resulted from an automatic trip, was in August 1995. A 24 month calculation of the UA7 indicator was 8.0 points out of 8.0 points. At the end of the Fourth Quarter 1998 the FCS Value was 8.0 which compares to the Third Quarter 1998 value of 8.0. i i 12 l
HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE m ->- M onthly HPSI Syste m Unavaila bility Value
-*-- 12 M onth Rolling Average Fort Calhoun Goal (0.003)
-o- W ANO Industry Median (0.002) 0.0 2 +
0.015 - 0.01 -- 19 9 8 R FO 0.006 t 0 5 5 5 5 5 5 5 5 4 ! a a ! I i i a 8 3 3 Year to Date 12 Month 24 Month - 36 Month 0.0% 0.0% 0.0% 0.0% IIPSI SAFETY SYSTEM 1996 1997 1998 1999 2(HMI 2001 2002 2003 (SPI) ANNUAL GOAL 0.003 % 0.003 % 0.003 % 0.003 % 0.003 % 0.003 % 0.003 % 0.003 % ACTUAL 0.0% 0.0% 0.0% PERFORMANCE TIIREE YEAR 0.0% 0.001 % 0.0% AVERAGE Definition: High Pressure Safety System (SP1)is defmed as the sum of the known (planned and unplanned) unasallable hours and the performance estanated unavailable hours for the high pressure safety injection system for the reponing period divided by the entical hours for the reporting period multiphed by the number of trams in the high pressure safety i gxt, n s3 stem. j Analysis: The availabihty of the HPSI System remains at 100 percent due to high equipment rehability and judicious planning and scheduling of maintenance. This places FCS as one of the best performers in the industry for this indicator. A 24 month calculation of the SP1 indicator was 10.0 points out of 10.0 points. At the end of the Four2i Quarter 1998 the FCS Value was 10.0, which compares to the Third Quarter 1998 value of 10.0. 13
AUXILLARY FEEDWATER SAFETY SYSTEM PERFORMANCE
---o--12 Month AFW Unavalf ability ,
Fort Calhoun Goal (0.01)
---- WANO Industry Modlan (0.001) 0.015 -
0.013 - 0.011 - 0.000 0.007 0.006 0.006 0.005 - teseRFo
~
0.003 - ._ 0.t\01 - - - - - - r - - - r - - a- - - r - - - - - - j- - - - g - - - g 4 001 - Jan Feb Mar Apr May June July Aug Sep Oct Nov Dee Year to Date : 12 Month 24 Month 38 Month 0.001 % 0.001 % 0.002 % 0.002 % AFW SAFETY 1996 1997 1998 1999 2000 2001 2002 2003 SYSTEM (SP2) ANNUAL GOAL 0.01 % 0.01 % 0.01 % 0.01 % 0.01 % 0.01 % 0.01 % 0.01% ACTUAL 0.002 % 0.004 % 0.001 % PERFORMANCE THREE YEAR 0.001 % 0.001 % 0.002 % AVERAGE Definition: Auxilary Feedwater Safety System (SP2)is dermed as the sum of the known (planned and unplanned) unavailable hours and the estimated performance unavailable hours for the auxihary feedwater system for the reporting period divided by the critical hours for the reporting period multiphed by the number of trains in the auuhary feedu ater system. Analysis: AFW system availability goals were achieved in 1998. In January, scheduled outages of 2 hours for Fi%10 surveillance testing and 6 hours for FW-6 breaker maintenance were completed. In September, during a 9 hour outage, the speed limitmg govemor was adjusted. This performance places FCS as one of the top performers in the mdustry for this indicator. A 24 month calculation of the SP2 indicator was 10.0 poin's out of 10.0 points. At the end of the Fourth Quarter 1998 the FCS Value was 10.0 which compares to the Third Quarter 1998 value of 10.0. 14
EMERGENCY AC POWER SAFETY SYSTEM ?ERFORMANCE m M o n thly E m e rg e n c y AC P o w e r U n a va ila b Hity Valu e
--as- Y e a r to -D a to E m e rg e n c y AC P o w e r U n a va lla bility Va lu e F o rt C a lh o u n G o a l (0.0 2 4 )
+ W AN O In d u s try M e dia n(0.0 0 5 )
0.07 - 0.06 - g 0.05 - o od 1 a e : li 0.03 8 8 8 \g o 8 a o o, 0.02 - % __ E 0.01 - ;
~"
g s &M M " ~
~ -M M "
, 3 m 0 M A M M- ,
h h k b 5 5 $ k E $ $ 0 h b ummeramme wrme emarun-memmy Planned Hours DG-1 DG-2 Total Hours Total Hours YTD Unavailability 7.0 Hours 2.7 Hours 9.7 227.65 Unplanned Hours DG-1 DG-2 Total Hours Total Hours YTD Unavailability 29.85 Hours 0.0 Hours 29.85 29.85 EMERGENCY AC POWER 1998 1997 1998 1999 2000 2001 2002 2003 SAFETY SYSTEM (SP5) ANNUAL GOAL 0.024 % 0.024 % 0.024 % 0.024 % 0.024 % 0.024 % 0.024 % 0.024 %
~
ACTUAL PERFORMANCE 0.010 % 0.015 % 0.02 % Definition: _ Emitgency AC Power Performance (SPS)is defined as the sum of the known (planned and unplanned) unavailable and the satirnated unavailable hoursfor the emergency AC power system for the reporting period divided by the number of hours in the reporting period multiplied by the number of trains in the emergency AC power system. Analysis: To maintain outage DC availability, planned on-line DC maintenance outages were conducted in July and August. The scope and duration of these outages proceeded as planned. In December 1998, failure of the water jacket temperature switch on DC-1 resulted in 29.85 hours of unavailability. The 1998 performance gc,al was achieved. This performance places FCS at the median of the industry for this indicator. A 24 month calculation of the SPS indicator was 8.5 points out of 10.0 points. At the end of the Fourth Quarter 1998 the FCS Value was 8.5 which compares to the Third Quarter 1998 value of 8.8. 15 l
THERMAL PERFORMANCE m Monthly Thermal Performance C"- J 12. Month Rolling Average Fort Calhoun Goat (99.7%)
-agr - W ANO Industry Median (99.t%)
h # 199s 8 h f f 9 RFO ! ! ! h *
~
bb - F E-" E" I & b
- i) 8 r" d
es%
! l- l l k l _b _.
~
9ss L. -
+ +
+
+
+
+
4 Year to Date 12 Month . 24 Month . , 3624 M 100 % 100 % 99.9 % 99.9 % THERMAL 1996 1997 1998 1999 2000 2001 2002 20',J PERFORMANCE (TPI) ANNUAL GOAL 99.6% 99.6 % 99.7 % 99.7 % 99.8 % 99.8 % 99.8 % 99.8 % ACTUAL 99.7 % 99.9% 100 % PERFORMANCE THREE YEAR 99.7 % 99.9 % 99.9 % AVERAGE Definition: Thermal Performance Indicator (TPI) is defined as the ratio of the design gross heat rate (corrected) to the adjusted actual gross heat rate, expressed as a percentage. Analysis: FCS contmues to peform at tne expected thermal efficiencies. Variations in the monthly Thermal Performance are the result of environmental factors, which are seasonally dependent. Unplanne,1 equipment outages or degradation has not affected the units efficiency. This performance places FCS as one of the top performers in the industry for this indicator. A 12 month calculation of the TPI indicator was S.0 points out of 6.0 points. At the end of the Fourth Quarter 1998 the FCS Value was 6.0 which compares to the Third Quarter 1998 value of 5.7. 16
FUEL RELIABILITY IND!CATOR Fuel Reliability (E-04 Microcuries/ Gram) A End of1998 Goal (17.3 E-04 Microcuries/ Gram)
-e- WANO Industry Median (0.21 E-04 Microcuries/ Gram ) y h 100 - 5.2
$ 10 - 4.7 SA A 8 1.8
- s 1-g
$ 0.1 -
% 0.04 0.01 0.01 m 0.01 -
Jun Jul Aug Sep Oct Nov Dec
- 12 Month . 24 Month 38 Month
' Year to Dett-5.2E-04 5.2E-04 4.5E-03 1.0E-02 FUEL REllABILTY 1997 1998 1999 2000 2001 2002 2003 (FRI)
ANNUAL GOAL 147E-04 17.3E-04 5.0E-04 5.0 E- 5.0E-04 5.0E-04 5.0E-04 04 ACTUAL 99E-04 5.2E-04 PERFORMANCE Definition: Fuel Reliability (FRI) is defined es the steady-s'ite primary coolant 1-131 activity corrected for the tramp uranium contribution and norrrulized to a cog sn purification rate. f Analysis: Elimination of the initial We ghouss fuel design which resulted in spacer grid induced fretting of fuel pins was succesdu! in significantly reducing RCS activity in Cycle 18. Further needed improvements will { be implemented through removal of replacement ABB bundles in Cycle 19. Coolant activity data through December 1998 shows the presence of two defective fuel rods. At the beginning of Cycle 18, lodine cctivity levels were higher than expected for a defect free core. This was due to having operGd ,/;(h fuel failures for the last 2.5 cycles which contributed tramp lodine-134 and lodine-131 intc Cycia 18. The cuarterly calculation of the FRiindicator was 8.0 points out of 8.0 points. At the end of the Fourth Quarter 1998 the FCS Value was 8.0 which compares to the Third Quarter 1998 value of 8.0. r I7 r
I SECONDARY SYSTEM CHEMISTRY m Monthly Chemistry Indicator 1998 Fort Calhoun Goal (1.1)
--m-WANO Industry Median (1.04)
~
1.36 I 1.4 - 1.2 - 1.1 1.11 1.04 1.29 1.12 1.1 1.09 1.1 1-0.8 - l 0.6 - 0.4 - 1888 RFO i 0.2 - 0 0 0-- -+- * --+- -.+- .
--+- -w a !
Jan Feb Mar Apr May June July Aug sep Oct Nov Dec l l
' Year to Date l12 Month 24 Month 36 Month 1.16 1.16 1.24 1.25 SECONDARY SYSTEM 1997 1998 1999 2000 2001 2002 2003 CHEMISTRY (CPI)
ANNUAL GOAL 1.4 1.1 <1.1 <1.2 <1.15 <1.15 <1.15 ACTUAL 1.33 1.16 1 PERFORMANCE Definition: Secondary System Chemistry Indicator (CPI)is defined as a calculation based on the concentration of key impurities in the secondary side of the plant. These key impurities are the most likely cause of deterioration of the steam generators. Criteria for calculating the cpl are: 1) The plant is at greater than 30 percent power; and 2) the power is changing less than 5% per day. Analysis: Following the 1998 Refueling Outage, the CPI ran high due to normal startup outage recovery. There were no unusual or unanticipated chemistry events during 1998. The 1998 CPI performance goal was not met. Note: The theoretical minimum CPI value range for FCS is 1.1 to 1.2 which is due to the Secondary system copper content and a lack of condensate polishing & blowdown recovery systems. This performance places FCS in the lowest quartile of plants for this indicator. The 12 month calculation of the CPlindicator was 6.6 points out of 7.0 points. At the end of the Fourth Quarter 1998 the FCS Value was 6.6 which compares to the Third Quarter 1998 value of 6.6. I8 l
COLLECTIVE RADIATION EXPOSURE M onthly R a diation Dose (S R D)
- A ccu m ulated Dose based on SRD reading 250000 --
E : : : : 0 200000 -- E E z 150000 -- 2 100000 - n n g o 50000 --@ g a g g g g m m
- s g
-+
8 5 N @ u h h 0 -- :- m + + + + - ' - + - + - , , Jan Feb M ar Apr M ay Jun Jul Aug Sep Oct Nov Dec
' Yearto Date .12 Month - 24 Month as Month 223.22 REM 223.22 REM 131.91 REM 163.28 REM COLLECTIVE RAD. EXPOSURE 1996 1997 1998 1999 2000 2001 2002 2003 (CRE)
(MAN REM) ANNUAL GOAL 138.0 38.0 <244,0 <200.0 TBD TBD TBD TBD ACTUAL PERFORMANCE 226.02 40.6 224.0 THREE YEAR AVERAGE 117.0 138.0 163.0 INDUSTRY MEDIAN 145.0 144.0 223.2 3 YEAR Avg.
- TBD - To Be Detennined Definition:
Collective Radiation Exposure (CRE) is defined as the total external whole-body dose received by all on-site personnel (including contractors and visitors) during a time period as measured by the thermoluminescent dosimeter (TLD). Collective radiation exposure is reported in units of person-rem. Analysis: Excellent cooperation and adherence to ALARA pnneiples by all radiation workers coupled with daily monitoring of accumulated exposures, thorough job planning and structured pre-job bnefings, resulted in achieving the 1998 CRE goal,in spite of exceeding the planned outage dose. The outage dose was exceeded due to emergent but planned additions to the outage. This performance places FCS in the lowest quartile of plants for this indicator. A 24 month calculation of the CRE indicator was 4.7 points out of 8.0 points. At the end of the Fourth Quarter 1998 the FCS Value was 4.7, which compares to the Third Quarter 1998 value of 4.7. 19
INDUSTRIAL SAFETY ACCIDENT RATE m Y-T-D Industrial Safety Accident & Disabling injury / Illness Rate
-*-- 12 Month Rolling Average FCS Year End Goal (<0.40)
-e--- Year 2000 WANO Industry Goal (<0.40) 0.9 0.8 - n 0.7 - $
ko 8 " o E N b N 4 6 o 6 e o o ' o 0.4 1 m ---m----m----e----o--. 0.3 - 0.2 - 0.1 - o o 0 - - r-- Jan Feb Mar Apr May June July Aug Sep Oct Nov Dec Year to Date - .12R$onth 24 Rionth . 38 Rionth
- 0.31 0.31 0.16 0.21 INDUSTRIAL SAFETY 1996 1997 1998 1999 2000 2001 2002 2003 ACCIDENT RATE (ISAR)
ANNUAL GOAL <0.5 <0.5 <0.4 <0.4 <0.4 <0.4 <0.4 <0.4 ACTUAL PERFORMANCE 0.29 0.0 0.31 Defirition: Industrial Accident Safety Rate (ISAR)is defined as the number of accidents for all utility personnel permanently assigned to the station, involving days away from work per 200,000 man-hours worked (100 mtn-years). The purpose of this indicator is to monitor progress in improving ind ustrial safety performance for utility personnel permanently assigned to the station. Contractor work-hours are not includedin this Indicator. An:lusis: The 1998 ISAR goal was achieved. Two lost time accidents occurred in 1998, one in March and a second in October. The March event ended a 545 day continuous accident free run, a new FG record. This performance places FG in the Third quartile of plants for this indicator. A 12 month calculation of the ISAR indicator was 5.0 points out of 5.0 points. At the end of the Fourth Quarter 1998 the FG Value was 5.0, which compares to the Thl:0 Ouarter 1998 value of 5.0. 20
l VOLUME OF LOW-LEVEL RADIOACTIVE WASTE M onthly V olume of LLRW (cu. meter) am Y ear-to.Date Cumulative Radioactive W aste Buried -
-.-e-- W AN O Industry M edian (54 cu. meter)
Fort Cahoun Goal (23 cu. meter ) 1r 60.00 -
= = = = : : = = = = =
{ 50.00 - 40.00 - f o 30.00 - % a 8 b 8 O E N 20.00 - R R E gg 2
- 10.00 - 8 & & gs s g 8 g I nn 8w gw 8 w 8 0.00 + A,8 v*E -
E,8v*En , n Jan Feb M ar Apr M ay Jun Jul Aug Sep Oct Nov Dec { l Year to Date .. '~12 Month 24 Month 28 Month 22.53 22.53 44.75 63.13 VOL of LOW-LEVEL 1996 1997 1998 1999 2000 2001 2002 2003 RAD WASTE (RWV) ANNUAL GOAL 18.6 34.0 <23.0 <23.0 TBD TBD TBD TBD ACTUAL 18.4 22.2 22.53 PERFORMANCE
- Volume in cubic meters. ** TBD - To Be Detennined Definition:
Low-level Radioactive Waste (LLRW) is defined as the volume oflow-level solid radioactive waste actually shipped for burial. This indicator also shows the volume of low-level radioactive waste which is in temporary storage, the amount of radioactive oil that has been shipped off-site for processing, and the volume of solid dry radioactive waste which has been shipped off-site for processing. Low-level refers to all radioactive waste that is not spent fuel or a by-product of spent fuel processing. Analysis: The volume of radioactive waste buried in 1998 was higher than desired due to the Cycle 17's high RG activity created by failed fuel. Cycle 18's fuel performance improvements are expected to reduce waste generation. This performance places FG in the third quartile of plants for this indicator. The LLRWindicator is no longer calculated as part of the WANO PIIndex by INPO. 21
Personnel Error Rate
,0 . . r e <a: ~ aasco'- -~' e <a I 9000 8 81 a 51 6000 10 . . . ,
@ e 0m .
[ t L 5 "' ' ... i.0 , , , , , , ... [ I 2 0m . m ,,, a ,e - - 2 000 1se t ce ( 1 000 - 0 =0 . _B,
, ,. _ , I- --
-m.--- w --m - - 0 6e - + -e , - 0 6, -~ 4
_m,' " m ' " ' " , mLE ' " ' " ' " E ' " [
/ff/Y///V/Y* $ k////f/fthhf
{ Defizition: Th'a indicator monitors human error events at FCS which are classified as a
- Noteworthy Event," under the criteria specifed in the Condition Report Program. Noteworthy events may be classifed as level one, two, or three on a Condition Report or cs defined but not limited to the examples listed below-Error Rate = number of human errors x hours everv two weeks 100,000 hrs
- 1. Recordable injury in industrial safety.
- 2. Valve Mispositioning event caused by plant personnel.
- 3. Equipment tagging error affects safe operation of the plant, readiness or personal safety.
- 4. Improper use or failure to use safety equipment or performing a task in an unsafe manner.
S. Any event involving loss of radioactive material control that may cause or potentially result in an individual receiving an unauthorized exposure.
- 6. Any spill er spread of radioactive material, which results in an impact on the plant or affect the general health and safety of the general public or plant personnel.
( 7. Failure to utilize, or adhere to sound iadiation principles, or accepted administrative controls to keep occupational radiation exposure, or exposure to members of public ALARA.
- 8. Chemistry parameter (s) out of specification, involving insufficient chemistry corrective action or oversight.
- 9. Volation of procedure or human performance error.
- 10. Less than 3 deep (qualifed members) in minimum staffing position for the Control Room, TSC, OSC, and EOF.
- 11. Any unplanned impact to offsite evacuation routes or relocation capability.
- 12. Any failure or theft of emergency response equipment or supplies necessary to complete classification, notification, trotective action recommendation or FRO command & control functions.
- 13. Inadequate Er*to training or qualification.
- 14. Fa8ure to adequately staff the ERO in actual responses or drill notifcation.
r
SAFE OPERATIONS Goal: A proactive, self-critical and safety conscious culture is exhibited throughout the nuclear organization. Individuals domonstrate professionalism through self-ownership and parsonal initiative and open communication. . 23
RECORDABLE INJURY /lLLNESS FREQUENCY RATE m Monthly Recordable injury / Illness Frequency Rate
- 1998 Fort Calhoun YTD Goal (1.5) 3-1.5 - : : : : : : : : : : : :
O.63 0.43 0.5 - 0 + Jan Feb Mar Apr May Jun Jul Aug Sep oct Nov Dec This indicator shows the monthly Recordable injury / Illness Frequency Rate. A recordable injury / illness case is reported if personnel from any of the Nuclear Divisions are injured on the job and require corrcctive medical treatment beyond first aid. There were no recordable injuries for the month of December 1998. The 1998 Fort Calhoun Station year-to-date recordable injury rate is 1.72. The goal for this indicator is a maximum value of 1.5. D ta Source: Sorensen/Gunn (Manager / Source) Accountability: Short Trcnd: None SEP 15,25,26 & 27 s t 24 I .
CLEAN CONTROLLED AREA CONTAMINATIONS >1,000 DISINTEGRATIONS / MINUTE PER PROBE AREA g Contamination Events (Monthly) { B Contamination Events (YTD) [ [ Y 100 - 96 97 ( %- y 80 - 77 70 - 65 60 - 50 - 40 - M 5 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec This indicator shows the Personnel Contamhation Events in the Clean Controlled Area for contaminations >1,000 disintegrations / minute per probe area for December 1998. Th:re was 3 personnel contamination events in December 1998. The total year-to-date of Personnel events is 100 at ths end of December 1998. This indicator has been classified as "Needing increased Management Attention," duo to an upward trend of Year to date contamination events over the past three months. Data Source: Solymossy/ William s (Manager / Source) Accountability: Solymossy/Short Trcnd: Needing increased Management Attention SEP 15 & 54 25 [
1 PREVENTABLE / PERSONNEL ERROR LERs
--+-Total Events 35 - -e- Preventa ble
-+-Personel Error 12 Month Totals 30 -
25 - 20 -
'S - s 18 .
16 17 -- 10 - 7 6 6 6 6 6 5$ 5 5 5 - _ _ 2 2 3 3 5 5 5 6 - 5 5 2 4 4 2 3 a 8 8 8 8 8 8 8 8 8 8 8 b k $ b $ $ k b $ $ $ h This indicator depicts 12-month totals for numbers of " Preventable" and " Personnel Error" LERs. The graph shows the 12-month totals for preventable LERs, the 12-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. In November 1998, there were no events which was subsequently reported as LER. No LER wac categorized as " Preventable" and No LER was categorized as " Personnel Error" during the month of November. The total LERs for the year 1998 are thirteen. The total Personnel Error LERs for the yeac 1998 are three. The year-to-date goal for this indicator is that the year-end values for the 12-month totals not to exceed 3 Preventable and 1 Personnel Error LERs. NOTE: Due to the way LERs are tracked & reported, this indicator lags by one-month. Data Source: Frans/Matzke (Manager / Source) Accountability: Solymossy Trend: None SEP 15 26
LICENSEE EVENT REPORT (LER) ROOT CAUSE BREAKDOWN Misc Admn 0% 8% LO Err. 0% Other Eir. 17% Design 50 % y ,: [Lil. '
- - y ' ' , .-;.4'y yJ e% ea R'e' s V',
g' yk
, a Maint.
25% This indicator shows the LERs by event date broken down by Root Cause Code for each of the past twelve months from December 1997, through November 30, 1998. To be consistent with the Preventable / Personnel Error LERs indicator, this indicator is reported by the LER event date, as opposed to the LER report date. The cause codes are intended to identify possible programmatic deficiencies. For detailed descriptions of these codes, see the " Performance indicator Definitions" section of this report. NOTE: Due to the way LERs are tracked & reported, this indicator is one-month behind.There were no events in November 1998 that resulted in an LER. There were no missed surveillance tests resulting in LERs during November 1998. The 1998 Fort Calhoun monthly goal for this indicator is 0. Data Source: Frans/Matzke (Manager / Source) Accountability: Solymossy Trend: None SEP 60 & 61 27
VIOLATION TREND 1erscwsens instacwmmaru D. 14 g 12-
- o. $.
- :[
6 Q. 6 2 4 2 2 2 0 0 0 0 . am re, m apr uw an .u Aus ap as w me Jun Ab W Apr My an .M Ag hp om b me umu uretywners -*- stannummons. -turreosmunTom m**8v**sans -1sesratcahamTaw -.-mannuammause. This indicator depicts the current year of cited violation data plus the past year of violation data for Fort Calhoun Station. Also depicted is the Region IV upper quartile for the current and past year. The following inspection reports noting no violations were issued during December 1998: Violation Level IER No. Title (0) 98-13 Liquid & Gaseous Radioactive Waste Effluents (0) 98-26 Radiation Protection (0) 98-25 Emergency Preparedness Program To d:te, OPPD has received eleven violations for inspection reports issued in 1998. Level 111 Violations 0 Level IV Violations .11 Total 11 Tha 1998 Fort Calhoun Station Goal for this performance indicator is to be at or below the cited violation trend for the upper quartile plants in Region IV. D:ta Source: Frans/Cavanaugh (Manager / Source) Accountability: Frans Trend: None i 28 i
COST l i Goal: Operate Fort Calhoun Station in a manner that cost ; effectively maintains nuclear generation as an economically i viable contribution to OPPD's bottom line. Cost consciousness is exhibited at all levels of the organization. l I 29
l CENTS PER KILOWATT HOUR l l November 1998 ' l 12 Month Rolling Average j --*- A c tu al -e- Budget ---o- Plan l 4.00 - j 3.50 - l
~
f 3.00 I _ ; _ V 2.50 2.00 l 1.50 1.00 8 EbEEEk$Ek{8ka 4 4 4 4 8 8 4 4 3 4 8 8 4 4 EHEE l i 12 $EE i Th3 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 1998 revised budget. The basis for the actual curve is the Financial and Operating Report. Tha D cember 31 amounts are also shown for the prior years 1993 through 1997. In addition, the report shows the plan amounts for the years 1999 through 2002 for reference. The basis for the dollars are the Nuclear Long Range Financial Plan cnd ths 1998 Corporate Planning and Budget Review. The basis for the generation is provided by Nuclear Fuels. l The 12-month rolling average unit price period of( December 1997 through November 1998) averaged above budget due to the extended refueling outage and less generation during the period. The 12 month rolling average is 3.24 cents per kilowatt hour. l The yerr-to date ('YTD) average is trending in a positive direction. Qents per KWH Jan Feb Mar Apr May Jun Jul Aua Seo Oct Nov Dec Cudget YTD 2.84 2.67 3.07 4.75 4.52 4.04 3.76 3.53 3.42 3.33 3.21 3.12 Actual 2.96 2.85 3.00 3.26 4.16 4.39 4.03 3.77 3.59 3.40 3.32 ProjectedYTD 3.22* NOTE: This information lags by a month due to the short tum around required for processing. {
- Projected numbers reflect the values for YTD if the plant is to operate within bu-dgets for the remaining period of the year.
Dita Source: Gayoso/ Huang (Manager / Source)
. Accountability. Gayoso/ Huang Tr:nd: Needing incresed Management Attention i 4
30
t { { { c DIVISION AND t DEPARTMENT I PERFORMANCE l INDICATORS Goal: Achieve high standards at Fort Calhoun Station resulting in safe, reliable and cost effective power production. { [ 31 L - - -
m_. . . . . - . _ _ . _ _ . _ _ . . . _ _ . . _ _ __ _ . _ . _ . . . _ - . _ _ _ . _ . _ _ . . . _ _ _ . . . _ _ ____.. ____ _. j MAINTENANCE WORKLOAD BACKLOG j m Corrective Maintenance m Preventive Maintenance j i i Non CorrectivelPlant im provem ents Corrective Maintenance Goal (200) i j s00 -- s0s 773 ! s00 -- 696 723 732 656 692 700 -- 600 -- 522 516 49, 500 -- 400 __ 332 300 -- 200 -- 100 -- 0-- ,- t 1 --+- -+- + -+- + - i ; e a w x g b o a y > u 4 5 $ N' $ g 4 Et & O E & N on .Ont an e_Mainte n ance._W.s tk_Q tileLB a c klon This indicator shows the backlog of non-outage Maintenance Work Orders remaining open at the end of the reporting month. Brokendown by maintenance classification. The 1998 goal for this indicator is 200 non-outage corrective maintenance MWOs. The current backlog of corrective MWOs is 294. Data Source: Solymossy/ Johnson (Manager / Source) Accountability: Solymossy/Clemens Trend: None SEP 36 l 32
.- ~..~-.--.-n.-.~- ... - - - - . - ~ - - - ~ ~ - - - - - - - ---~- - -- ~-~ --^ - -' ^ ~ - " - '
i ! RATIO OF PREVENTIVE TO TOTAL MAINTENANCE ! PREVENTIVE MAINTENANCE ITEMS OVERDUE m Ratio of P reventive 'to Total M sintenance Fort Calhoun Goal 65% 100% 93% l 90% 80% 76% 77% 76% 78% 77% 75 4 74 % Jan Feb Mar A pr May June J uly A ug Sep Oct Nov Dec m Preventive Maintenance items Overdue Fort Calhoun Goal 2%
~
6.02 % 6% - 5% - 4% - 3.03% 3.60% 3% -_ 2.60 % 2.60 % 2.04 % 2 4 2% - 1% -- 0.80 % 0.60% 0.70 % 0% -- ; -+- -t- -+- ; ---H --+- + + + -+- -i Jan Feb Mar Apr May June July Aug Sep Oct Nov Dec Th3 top graph shows the ratio of completed non-outage preventive maintenance to total completed non-outage maintenance. liis ratio of preventiw to total maintenance was 77% for the month of December 1998. Th310wer graph shows the percentage of scheduled preventive maintenance items that were not completed by the late finish dats. From the period of (November 16th thru December 15th) there were 17 PM's that were completed late or not completed out of 484 scheduled. The 1998 Fort Calhoun monthly goal for the percentage of preventive maintenance items overdue is a maximum of 2%. Data Source: Solymossy/ Johnson (Manager / Source) Accountability: Solymossy/Clemens Trend: None SEP 41 & 44 i 33 l I
f PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE) l Human Performance CRs (Maintenance) 20 - 18 -- 16 16 -- y 14 - 12 -- 11 10 -- 4 8-6- 4-- 3 j 2 2 2 1 2+ 1 O 0-- -+ E+ + + -+ E-t- -+ E + O m , f Jan Feb Mar Apr May June July Aug Sep Oct Nov Dec This indicator shows the number of Condition Reports related to procedural noncompliance incidents assigned to the Maintenance Department. Data Source: Clemens/Burggraf (Manager / Source) Accountability: Solymossy/Clemens Trend: None SEP 15,41 & 44 r 34 l 1 i . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
i CONTAMINATED RADIATION CONTROLLED AREA m Contaminated Radiation Controlled Area 1998 Fort Calhoun Goal (69Q 6% -- V 6%- 4.8% 4.8% 4.8% 4.8% 4.8% 4.8% 4.8% 4.8% 4.8% 4.8% 4.7% 4.7% 4%- 3% - 2% - 1% + 0%-- --+- --+- -+- -+ i i H- -+- -+-- -l -+- H Jan Feb Mar Apr May June July Aug Sep Oct Nov Dec This indicator shows the percentage of the Radiologically Controlled Area (RCA) that is contaminated based on the total square footage of 70475. At the end of December 1998, the total contaminated area was 3312 square feet which is 4.7 percent of the RCA . The monthly FCS goal for 1998 is a Maximum of 5% Contaminated Area. Data Source: Solymossy/ Williams (Manager / Source) Accountability: Soly nossy/Short Trend: None SEP 54 35 ( ,
RADIOLOGICAL WORK PRACTICES PROGRAM m Monthly Poor Radiation Worker Practices e Total PRWP for 1998 1998 Fort Calhoun Goal (<20) V 25 - 20 - 18 18 18 18 l' 15 15 - 14 i 11 l 10 - l 5- 33 3 3 j 2 O O O O O O O +- -+--- - + -+- + Jan Feb Mar Apr May June July Aug Sep oct Nov Dec The Radiological Work Practices Program Indicator shows the number of Poor Radiological Work Practices (PRWPs) which were identified during the reporting month. The number of PRWPs which are identified each month should indirectly provide a means to qualitatively assess supervisor accountability for their workers' radiological performance. , During the month of December there was 1 PRWP identified. There have been a total of 19 Poor Radiation Worker Practices in 1998. The 1998 FCS goal is <20 PRWPs, the 1997 goal was <15 PRWPs. Data Source: Solymossy/ Williams (Manager / Source) Accountability: Solymossy/Short Trond: None SEP52 36
9 l DOCUMENT REVIEW , f 3 Documents Scheduled for Review a Document Reviews complete during mor.th O Documents Overdue 300 -- 250 -- 200 -- 160 --
+ i i + + i + _+ + __.
Jan Fe b Mar Apr May June J uly Aug Sep Oct Nov Dec 1998 The Document Review indicator shows the number of completed, scheduled, and overdue (greater than 6 months past the scheduled due date) biennial reviews for the reporting month.The documents reviews are performed in-house and include Special Procedures, the Site Security Plan, Maintenance Procedures, Preventive Maintenance Procedures, and the Operating Manual. During December 1998, there were 137 document revews scheduled, while 46 reviews were completed. At tha end of the month, there were O document reviews more than 6 months overdue. There were 4 nsw documents initiated during December 1998. Data Source: Ponec/Plath (Manager / Source) Accountability: Ponec Trond: Positive SEP 46 R i 37
4 l l ! SECURITY INCIDENTS i 36 { 30 -- i 26 -- - - 20 - l i - s ! . [ N, i $6 _ A, s
- f. _
l . ~ - 10 -- - - - - - - - -- - l 6- - - - - - - - - - - - 0- , 4 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NoV DEC \ l 98 Loggables 98 Non-Loggables
- 97 Loggables - + - - 97 Non-Loggables l:
I l ! Tho Loggable and Non-Loggable incident (Security) Indicators Sire depicted in the chart above. The ! chart depicts the total number of loggable and non-loggable human error events and system failures which occurred during the reporting month. During the month of December 1998, there were seventeen (17) loggable incidents anct nine (9) non-loggable incidents dentified (excluding access denials). Of all incidents identified this month seven (7) wero human error events. Of loggable events, five (5) were human performance errors and twelve (12) wsre system failures. There were five (5) human performance errors attributed to the security department in December. There were no access denials during the reporting period. Human parformance within the security department continues to be a focal point. This indicator provides information on secunty performance for Safety Enhancement Program (SEP) Item No. 58. Data Source: Sefick/ Clark (Manager / Source) Accountability: Se.Sck Trend: None SEP 58 38
TEMPORARY MODIFICATIONS f a m Temporary Modircations >1-fuel cycle old (RFO required for retroval) m Temporary Moc(cations >6 months old (Renovable orkline)
- Fort Calhoun Goals for both Tenporary Modircations' categories (0) 7 7 l 7-l 6 6 6-5 4
4 22 2 2 2 2 2 0 0 0 0 0 0 0 0 Jan Feb Mar Apr f May June Jury Aug Sept Oct Nov Dec Thi3 indicator provides informaton on the number of Temporary Modifications (TMs) greater than one fuel cycle old r requ'ing a refueling outage (RFO) for removal and the number of TMs removable on-line that are greater than six months old. The 1998 Fort Calhoun monthly goals for both of the TM categories are zero. At tha end of December 1998, there were no TMs that were greater than one-fuel cycle old requiring an outage for remova!. At th3 end of December 1998, there were seven (7) TM's installed that were greater than six months old which could be removed on-line. DCN #0006121 (TM 96-039), Railroad Siding / Corridor 26 Door, was installed November 1,1996. DCN #0006164 ( TM 97-021), CCW corrosion monitor, was installed February 18,1998. DCN #0006165 (TM 97-022), LPSI Header Pressure Gauge at PT-325, was installed December 12,1997. DCN #0006186 (TM 98-003), FI-1112, FW-54 Suction Flow Indicator, was installed March 16,1998. DCN #0006187 (TM 98-004), TPCW System Corrosion Monitor was installed March 24,1998. DCN #0006188 (TM 98-005), YlT 6286 A&B YlT 6288 A&B was installed February 27,1998. DCN #0006197 (TM 98-014), FW-10 Speed Control Loop, was installed May 29, 1998. At the end of December 1998, there was a total of twelve (12) TMs installed in the Fort Calhoun Station. Four (4) of the twelve (12) installed TMs require a RFO for removal and eight (8) are removable on-line, in 1998, a total of twenty two (22) TMs have been installed. At the end of December 1998, there were four (4) procedural or m:intenance configuration afterations (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: Core /Plott (Manager / Source) Accountability: Core Trend: Adverse SEP 62&71 j 39
[ [ Maintenance Rule SSC Unavailability [ e summu s S S C s E xceeding Unevalla bility c rite ria -*- % E x c e e d in g U n e v a lla b i'ity C rit e ria
-+--G o a l s 4 % E x c e e d in g C rite ria g3
[ g,_ - l,-
= =
2- -
=
1 1 I 1 1 1 1 4 -s e 1.e 7 2 s7 3.o r 4 87 1 -s e 2-88 s.s e 4.s e I Q1R [ [ [ As of the fourth quarter of 1998, only one SSC, the non-safety related inverter, EE-43, is exceeding it's - three year unavailability performance criteria. Performance is indicative of success in Maintenance, Planning & Scheduling, and Operations efforts to control equipment out of service time. [ [ Data Source Skiles/Swearngin/ Johnson (Manager / Source) Accountability: Skiles 4 Trcnd: None [ ( 40
LICENSED OPERATOR REQUALIFICATION TRAINING O Total Requalification Training Hours a Simulator Training Hours E Non Rcqualification Training Hours a Number of Exam Fellures 35 - ' 32 33 32 ,, 32 32 . 30 - 25 - 20 20 - 16 - 14 14 4 2 2 e 10 - 8 g , , , g, , 7 6 4 0 0 0 000 0 0 4-- , Cycle IV-7 Cycle 98-1 Cycle 98 2 Cycle 98-3 Cycle 98-4 Cycle 98-5 Cycle 98-6 Cycle 98 7 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: All examination failures were remediated without impacting the operations shift schedule. Data Source: Westcott/Guliani (Manager / Source) Accountability: Westcott/Guliani Trend: None SEP 68 41
LICENSE CANDIDATE EXAMS - 1998 m SRO Exams Administered a SRO Exams Passed D RO Exams Administered m RO Exams Passed is g 18 18 18 18 16 -- 12 2 122 1 21 12 2 10 + 5-- 44 44 0000 0000 0000 0000 0000 0000 0000 0 '
; i i i t i Jan Feb Mar Apr May June July Aug Sep Oct Nov Dec 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.
Dec;mber 1998, there were 12 (SRO) exams administered and 18 (RO) exams administered. 12 SRO exams were passed and 18 RO exams were passed. D:ta Source: Westcott/Guliani (Manager / Source) Accountability: Westcott/Guliani Trsnd: None SEP 68 42 l
MWD PLANNING STATUS (1999 REFUELING OUTAGE) O EON H LD 0 MWtTSNoT YET FROCESSED 700 3 600] 500 -
,g3 434 3,3 MWD HOLDS 400- DATA UNAVAILABLE 300- 3 34 30 200 -
100 - 0 -- , i - - , Oct-98 Now98 Dec 38 This indicator shows the total number of Maintenance Work Requests (MWRs) and Maintenance Work Orders (MWOs) that have been approved for inclusion in Cycle 18 RFO. 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: Solymossy/ Johnson (Manager / Source) Accountability: Sollymossy/ Herman Trend: None SEP 31 l 43
l l!llll;ill; ,' OO3mOZAZA ymadZO nmT>MHEmg
)
D*U tmmOgr
/ mmy5Om(/)
- mzOEmma zO gmT> gmzq "eWWocyDQm y3Otm A(t) mqb$M3mm03H m m -rgH na;* r0 mO: moU c o, - o, _ o, 0, $y M
* - Ua% &
0, a Nu,N % % _ 0i mm " a.oaa ._ @ m e 0i 04 ,i i 4 l i 4 l 4 J s s T g s g s s n n t c e C n m n e e o o e icv E it s a it s l v v it c it j o r t e x e a la e c r e n T E T V V p e p P S a s - l l A t o r l P f b r e I S I l e v a k c e d t e I l n In s a o b h a e n r e u V C r e u o e c n f p F is n e n S ie O o r a le r G la R r o o m B t o C a M i r M t e c S A i c r o B >- W Omts eo nC Oo5 RE eah ccam2 5a$Sqme ae*
>O8 cam 4
5 Oo8 %EEeR@ecaa- ' B3% Zoae $'S
,1!
PROGRESS OF 1999 REFUELING OUTAGE MODIFICATIONS CYCLE 19 1990 Refueling Outage Mods PRC Approved - March 21,1999
;00% _ 93% 3 80% -
60% E 60% - 50 % 50%
! 40% - 30%
20% - 0% 0% 0% - 0% ,
- E ,--E,- E,- , , i ,
- n s m - ~ m e en , e 5 5 5 5 8 8 8 8 8 5 5 8 8 ss8 @ @ $ 8 8 8 Modifica tions mPercent Complete This indicator shows the status of Modifications approved for installation during the Cycle 19 Refueling Outage (September 1999).
Tha goal for this indicator is to have all modification packages which were approved for accomplishment prior to September 25,1998, PRC approved by March 21,1999. Dec:mber 1998 M.odifications added: 0 Deleted = 0 1 Data Source: Skiles/ Walling (Manager / Source) Accountability: Phelps/Skiled Trend: None SEP 31 s 45
PROGRESS OF CYCLE 19 OUTAGE MODS AND ECN'S ADDED TO 1999 REFUELING OUTAGE AFTER [ FREEZE DATE ( There Have Been No MODS or ECNs added since Freeze Date f This indicator will show the status of Modifications and ECN's approved for installation during the Cycle 19 Refueling Outage. Target date is September 25,1998. f December 1998 Modifications /ECN's Added = 0 Deleted = 0 Data Source: Skiles/ Walling (Manager / Source) Accountability: Phelps/Skiles Trend: None SEP 33 f ( l 46
f PROGRESS OF 1998 ON-LINE MODIFICATION PLANNING Progress of 98 on-line
-{
m Percent Complete a Target Approve Date 102 % - 11/21/98 100% T - 11/1/98 98% - m - 10/12/98 96% - - 9/22/98 94 % ~ 9/2/98 92 % -- 8/13/98 90 % + 7/24/98 88 % - 7/4/98 86 % - 6/14/98 84 % . ++4 + + , ' 5/25/98
% 8 3 2 S Es R 233ZEEE 88EEEEE
88888
{ This indicator shows the status of modifications approved or in review for approval for on-line installation during 1998. The goal for this indicator is to have all MOD /ECN packages approved by their scheduled date. Dacomber 1998 MOD /ECN Added:0 Deleted: 0 Data Source: Skiles/ Walling (Manager / Source) Accountability: Phelps/Skiles Trend: None SEP 31 47
l 1 ACTION PLANS SEPINDEX 48
ACTION PLANS This $3ction lists action plans that have been developed for the performance indicators cited as Adverse Trends during the month preceding this report. Also included are Action Plans for indicators that have been cited in the preceding month's report as Needing increased Management Attention in accordance with Revision 5 of NOD-QP-37, for three (3) consecutive months. Adverse Trends
- Temporary Modifications (page 3g)
Based on the current trend of Temporary Modifications >6 months old (removable on-line) the Temporary Modifications Indicator is classifisd as *Needs increased Management Attention *. Presently, there are r,ix (6) Temporary Modifications which have been instslisd greater than six months. An action plan has been developed to expedite removal of the TMs and increase management's awareness of the issue. System Engineering will be actively pursuing resolution on closure of these Temporary Modifications. Needina increased Manaoement Attention e Emergency AC Power (page 15) This indicator was high in July and August due to planned maintenance. For the first time, diesel refueling frequency tasks were p2rformed on line. Approximately 60 hours was required on each diesel for on line maintenance. The decision to perform on-line maintenance was a management decision with full knoWedge that unavailability would increase. It is expected that unavailability will go down to previous lowlevels for the next 12 months.
. Clean Controlled Area Contaminations (page 25)
The Routine Decon Schedule was revised to improve the daily maintenance of clean areas in the RCA. A status sheet with a sign-off will provide administrative guidance and controls to ensure clean areas are being properly mahtained by a designated rasponsible person. These improvements should result in less Clean Controlled Area Contaminations.
- Cents Per Kilowatt Hour (page 30)
The increased cest has been due to the unexpected refueling outage extension which also caused the higher expenditures and the less power generated. Nuclear Planning Department has initiated cost awareness efforts by distributing the monthly update on power generation, O/M cost and Capital cost tc all nuclear departments and year-to-date cost data to all nuclear personnel. In addition, the Nuclear organization is developing the 1999 Business Plan based on the Six Factor Formula -CHOICE to address the issues and actions on safe operations, high performance and competitive cost. The effectiveness of the Business Plan will be ev21uatsd routinely by the nuclear management team. 49 5I --
PERFORMANCE INDICATOR DEFINITIONS PERFORMANCE INDICATOR INDEX HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE This indicator index is calculated from a weighted combination of eleven performance ir,dicator values, which The sam of the known (planned and unplanned) unavailable include the following: Unit Capability Factor, IJnplanned hours and the estimated unavailable hours for the high C:p'bility Loss Factor, HPSI, AFW, Emergency AC Power pressure safety injection system for the reporting period Syst:m, Unplanned Automate Scrams, Collective Radiation divided by the entical hours for the reporting period multiplied Exposure, Fuel Reliability, Thermal Performance, Secondary by the number of trains in the high pressure safety injection Systm Chemistry, and Industrial Safety Accident Rate. system. (Page 13) ( Page 6 ) AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM UNITCAPABILITYFACTOR PERFORMANCE f The ratio of the available energy generation over a given time The sum of the known (planned and unplanned) unavailable [ penod to the reference energy generation (the energy that hours and the estimated unavailable hours for the auxiliary [ could be produced if the unit were operated continuously at feedwater system for the reporting penod divided by the full power under reference ambient conditions) over the critical hours for the reporting penod multiplied by the number same time penod, egressed as a percentage. ( Page 10 ) of trains in the auxiliary feedwater system. [ ( Page 14 ) l UNPLANNED CAPABILITY LOSS FACTOR EMERGENCY AC POWER SYSTEM SAFETY SYSTEM The ratio of the unplanned energy losses dunng a given PERFORMANCE period of time, to the reference energy generation (the f Energy that could be produced if the unit were operated The sum of the known (planned and unplanned) unavailable continuously at full power under reference ambient and the estimated unavailable hoursfor the emergency AC g conditions) over the same time period, expressed as a power system for the reporting period divided by the number [ perc:ntage. ( Page 11 ) of hours in the reporting period multiplied by the number of trains in the emergency AC power system.( Page 15) UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7,000 CRITICAL HOURS THERMAL PERFORMANCE This indcator is defined as the number of unplanned The ratio of the design gross heat rate (corrected) to the tutomate scrams (RPS logic actuatons) that occur per adjusted actual gross heat rate, expressed as a percentage. 7,000 hours of critical operation. ( Page 16) ( The value for this indicator is calculated by multiplying the total numoer of unplanned automate reactor scrams in a FUEL RELIABILITY INDICATOR specific time period by 7,000 hours, then dividing that number by the total number of hours enticalin the same time f p:riod. The indicator is further defined as follows: This indicator is defined as the steady-swte primary coolant l-131 activity, corrected for the tramp uranium contribution and normalized to a common punficaton rate. Tramp uranium is j 1) Unplanned means that the scram was not an fuel which has been deposited on reactor core intemals from ( anticipated part of a planned test. previous defectiw fuel or is present on the surface of fuel elements from the manufacturing process. Steady state is
- 2) Scram means the automate shutdown of the defined as continuous operation for at least three days at a reactor by a rapid inserton of negatiw reactivity power level that does not vary more than + or -5% Plants (e.g., by control rods, liquid injection system, etc.) should collect data for this indicator at a power level above that is caused by actuation of the reactor protection 85%, when possible. Plants that did not operate at steady-state system. The signal may have resulted from power above 85% should collect data for this indcator at the exceeding a set point or spurous. highest steady-state power level attained during the month.
f The density correction factor is the ratio of the speerfic volume
- 3) Automatic means that the initial signal that caused of coolant at the RCS operating temperature (540 degrees F.,
actuation of the reactor protection system logic was Vf = 0.0217) divided by the specirc volume of provided from one of the sensor's monitoring plant parameters and conditions, rather than the manual scram switches or, manual turbine trip switches (or j push-buttons) provided in the main controtroom. I 4) Cntical means that during the steady-state condition of the reactor prior to the scram, the effective multiplication (k ,) was essentialry equal to one ( Page 12) 50 t I i
PERFORMANCE INDICATOR DEFINITIONS coolInt at normal letdown tsmperature (120' F at outlet of the also shows the volume of low-level radioactive waste which is leidown coohng heat exchanger, Vf = 0.0163), which results in in temporary storage, the amount of radcactive oil that has a dansrty correction factor for FCS equal to 1.33. Leen shipped off-site for processing, and the volume of solid ( Pege 17 ) dry radioactive waste which has been shipped off-site for processing. Low-level solid radioactive waste consists of dry SECONDAR1f SYSTEM CHEMISTRY PERFORMANCE active waste, sludges, resins, and evaporator bottoms INDEX generated as a result of nuclear power plant operaton and maintenance. Dry radioactive wasto includes contaminated The Chemistry Performance index (CPI) is a calculation based rags, cleaning materials, disposable protective clothing, plastic on tha concentration of key impunties in the secondary side of containers, and any other matenal to be disposed of ata low-the plant. These key impuntes are the most likely cause of level radcactie waste disposal site, except resin, sludge, or deterioration of the steam generators. Criteria for calculatog evaporator bottoms. Low-level refers to all redcactive waste . . . the CPI are: that is not spent fuel or a by-product of spent fuel processing. This indicator tracks radiological work performance for SEP ..
- 1) The plant is at greater than 30 percent power; and #54. ( Page 21 ) .. .
- 2) the power is changing less than 5% per day. RECORDABLE INJURY /lLLNESS CASES FREQUENCY , .
RATE The CPIis calculated using the following equaton: .l.' The numberof injuries requaing more than normal first aid per . . CPI = ((sodium /0.79) + (Chionde/1.52) +(Sulfate /1.44) + 200,000 man-hours worked. This indicator trends personnel (Iron /3.30) + (Copper /0.30)+(Condensate O2/2.90))/6 performance for SEP #15,25 and 26. Where: Sodium, sulfate, chloride and condensate dissolved ( Page 24 ) oxygen are the monthly average blowdown concentrations in ppb, iron and copper are monthly time weighted average CLEAN CONTROLLED AREA CONTAMINATIONS > 1,000 feedwater concentratons in ppb. The denominator for esof the DISINTEGRATIONS / MINUTE PER PROBE AREA five factors is the INPO median value. If the monthly average for a specife parameteris less than the INPO median value, the The personnel contamination events in the clean controlled median value is used in the calculation. area. This indcator tracks personnel performance for SEP #15 ( Page 18) & 54. ( Page 25 ) COLLECTIVE RADIATION EXPOSURE PREVENTABLE / PERSONNEL ERROR LERs Collective radiaton exposure is the total extemal whole-body This indicator is a breakdown of LERs. For purposes of LER event dose received by all on-site personnel (including classification, a " Preventable LER"is defined as: contractors and visitors) dunng a time period, as measured by An event for which the root cause is personnel error (i.e., the thermoluminescent dosimeter (TLD). Collective radiation inappropnate action by one or more indrviduais), inadequate exposure is reported in units of person-rem. This indicator admnistrative mntrols, a design construction, installation, installaton, tracks radological work performance for SEP #54. fabrication problem (nvolving work completed by or supervised by ( Pag 319 ) OPPD personnel) or a maintenance problem (attrbuted to inadequale or mproper upkeephepair of plant equipment). Also, the cause of the INDUSTRIAL SAFETY ACCIDENT AND DISABLING event must have occurred within approximately two years of the INJURY /lLLNESS RATE " Event Date" specified in the LER (e g., an event for which the cause is attributed to a problem with the original design of the plant would The purpose of this indicator is to monitor progress in not be considered preventable). improving industrial safety performance for utility personnel permanently assigned to the staton. Contractor work-hours are For purposes of LER ewnt classifcaton, a " Personnel Error" not included in this indicator. Also, this indicator is defined as LER is defined as follows: the number of accidents for all utihty personnel permanently An event for which the root cause is inappropriate action on assigned to the station, involving days away from work per the part of one or more individuals (as opposed to being 200,000 man-hours worked (100 man-years). This does not attributed to a department or a general group). Also, the includa contractor personnel. This indicator tracks personnel happropriate acton must have occurred within approximately performance for SEP #25,26 & 27. two years of the " Event Date" specifed in the LER. (Page 20 ) Additionally, each event classifed as a " Personnel Error" should also be classired as " Preventable." This indicator VOLUME OF LOW 4.EVEL SOLID RADIOACTIVE WASTE trends personnel performance for SEP ltem #15. ( Page 26 ) This indcator is defined as the volume of low-level solid radioactrue waste actually shipped for burial. This indicator 51
PERFORMANCE INDICATOR DEFINITIONS CENTS PER KILOWATT HOUR LICENSEE EVENT REPORT (LER) ROOT CAUSE BREAKDOWN The purpose of this indcator is to quantify the economical operation of Fort Calhoun Staten. The cents per kilowatt hru This indicator shows the number and root cause code for indicator represents the budget and actual cents per kilowatt Licensee Event Reports. The root cause codes are as follows: hour on a twelve-month average for the current year. The basis
- 1) Administrative Control Problem - for the budget curve is the approved yearty budget. The basis Management and supervisory deficieneses that for the actual curve is the Financial and Operating Report affect plant programs or activities (i e., poor ( Page 30 )
planning, breakdown or lack of adequate management or supervisory control, incorrect MAINTENANCE WORKLOAD BACKLOG procedures, etc). This indicator shows the backlog of non-outage Maintenance 2 ) Licensed Operator Error- This cause code captures Work Documer*ts remaining open at the end of the reporting errors of omission / commission bylicensed reactor month. Maintenance classifications are defined as follows: operators during plant activities. Corrective - Repair and restoration of equipment or
- 3) Other Personnel Error- components that have failed or are malfunctioning and are not Errors of omission / commission committed by performing their intended function.
non-licensed personnel involved in plant activities. Preventive - Actions taken to maintain a piece of equipment within design operating conditons, prevent equipment failure,
- 4) Maintenance Problem - The intent of this cause code is and extend its hfe and are performed prior to equipment failure.
to capture the full range of problems which can be attributed in any way to programmate defciencies in the Non-Corrective / Plant improvements - Maintenance activrt es maintenance functional organization. Activities included in performed to implement station improvements or to repair non-this category are maintenance, testing, surveillance, plant equipment. cahbration and radiation protection. Maintenance Work Priorities are defined as:
- 5) Dezign/ Construction /InstallationIFabrication Problem -
This cause code covers a full range of programmate Emergency - Conditions which significantly degrade station defciencies in the areas of design, construction, installation, safety or availability. andfabncation (i.e., loss of control power due tounderrated fuse, equipment not quahfied for the environment, etc.). Immediate Action- Equipment derciencies which signifcantly degrade staton reliabilrty. Potential for unit shutdown or power
- 6) Equipment Failures (Electronic Piece-Parts or reduction.
Environmental-Related Failures)- This code is used for spurious failures of electronic Operations Concern - Equipment deficiencies which hinder piece- parts and failures due to meteoro!ogical conditions staten operation. such as lightning, ice, high winds, etc. Generally, it includes spurious or one-time failures. Electric components Essential- Routine corrective mantenance on essential station hcluded in this category are circuit cards, rectfsers, bistables, systems and equipment. fuses, capacitors, diodes, resistors, etc.In addition this indicator reports SEP # 6 & 61. (Page 27) Non-Essential - Routne corrective maintenance on non-essenttal station systems and equipment VIOLATION TREND This indcator is defined as Fort Calhoun Station Cited Plant Improvement - Non-corrective maintenance and plant Violatons and Non-Cited Violations trended over 12 months. improvements.This indicator tracks maintenance performance Additionally, CitedViolatons for the top quartile Region IV for SEP #36. ( Page 32 ) plant is trended over 12 months (lagging the Fort CalhounStation trend by 2-3 months). It is the FortCathoun Station goal to be at or below the crted violation trend for thstopquartileRegion IV plant. ( Page 28 ) 52
PERFORMANCE INDICATOR DEFINITIONS RATIO OF PREVENTIVE TO TOTAL MAINTENANCE & TEMPORARY MODIFICATIONS PREVENTIVE MAINTENANCE ITEMS OVERDUE The number of temporary mechanical and electrical The rato of preventive maintenance (including survettance configurations to the plant's systems. 13 sting and calibraton procedures) to the surn of non-ouuge correctNe mantenance and preventive maintuiance completed 1) Temporary confgurations are defined as ovsr the reporting period. The rato, expressed as a electricaljumpers, electrical blocks, mechanical percentage,is calculated based on man-hours. Also displayed jumpers, or mechanical blocks which are tre the percent of preventive mantenance items in the month installed in the plant operating systems and are that were not completed or administratnely closed by the not shown on the latest revision of the P&lD, scheduled date plus a grace period equal to schematic, connection, 25% of the scheduled interval.This indicator tracks preventive wiring, or flow diagrams. maint2 nance activities for SEP #41. ( Page 33 )
- 2) Jumpers and blocks which are installed for PROCEDURAL NONCOMPLIANCE INCIDENTS Surveillance Tests, Maintenance Procedures, (MAINTENANCE) Calibration Procedures, Special Procedures or Operating Procedures are not considered as The number of identified incidents conceming maintenance temporary modMcations unless the jumper or procedural problems, the number of closed irs related to the block remans in place after the test or procedure use of procedures (includes the number of closed irs caused is complete. Jumpers and blocks installed in test by procedural noncompliance), and the number of closed or lab instmments are not considered as procedural noncompliance irs. This indicator trends personnel temporary mod (cations.
parformance for SEP #15,41 and 44. ( Page 34)
- 3) Scaffold is not considered a temporary CONTAMINATED RADIATION CONTROLLED AREA modification. Jumpers and blocks which are installed and for which Mrs have been submitted The percentage of the Radiation Controlled Area, which will be considered as temporary mod (catons hcludes the attdiary building, the radwaste building, and areas unti final resolution of the MR and the jumper or of the C/RP building, that is contaminated based on the total block is removed or is permanently recorded on square footage. This indicator tracks performance for SEP the drawings. This indicator tracks temporary
#54. ( Page 35) mod (cations SEP #62 and 71. ( Page 39)
RADIOLOGICAL WORK PRACTICES PROGRAM LICENSED OPERATOR REQUALIFICATION TRAINING The number of identified poor radiological work practices The total numberof hours of training given to each crew during (PRWPs) for the reporting month. This indicator tracks each cycle. Also provided are the simulator training hours rsdiological work performance for SEP #52. ( Page 36) (which are a subset of the total training hours), the number of non-REQUALIFICATION training hours and the number of DOCUMENT REVIEW (BIENNIAL) exam falures. This indicator tracks training performance for SEP # 68. ( Page 41) The Document Review Indicator shows the number of documsnts reviewed, the number of documents scheduled for LICENSE CANDIDATE EXAMS review, end the number of document reviews that are overdue for the reporting month. A document review is considered This indicator shows the number of SRO and/or RO quizzes overdue if the reviewis not complete within six and exams that are administered and passed each month. months of the assigned due date. This indicator tracks This indicator tracks training performance for SEP #68. performance for SEP #46. ( Page 37 ) ( Page 42) SECURITY INC. ENTS The te'.al number ci secu ity incidents for the reporting mont* dspicted in two graphs. Thh indicator tracks secww performance for SEP #58. ( vage 38) 53
PERFORMANCE INDICATOR DEFINITIONS { MWD PLANNING STATUS (CYCLE 19 REFUELING PROGRESS OF CYCLE 19 OUTAGE MODS AND ECN'S OUTAGE) ADDED TO '99 REFUELING OUTAGE AFTER FREEZE DATE This indicator shows the total number of Maintenance Work Requests (MWRs) and Maintenance Work Documents This indicator will show the status of Modifcations and ECN's (MWDs) that haw been approved for inclusion in the Cycle 18 approwd for sistallaton during the Cycle 19 Refueling Outage. Refueling Outage. This indicator tracks performance #31 This indicator tracks performance for SEP #33. ( Page 43) ( Page 46) COMPONENT TESTING DEPARTMENT AND SPECIAL Progress of 1998 On-Line modification Planning SERVICES ENGINEERING 19980UTAGE PROJECTS STATUS REPORT This indicator shows the status of modWications approved or in review for approval for on-line installation dunng 1998. This This indicator tracks performance for SEP # 31. indcator tracks performance for SEP # 31. ( Page 44) ( Page 47 ) PROGRESS OF 1999 REFUELING OUTAGE MODIFICATIONS CYCLE 19 This indicator tracks performance for SEP # 31. ( Page 45) l 54
SAFETY ENHANCEMENT PROGRAM INDEX The purpose of the Safety Enhancement Program (SEP) Performance Indicators Index is to list performance bdicators related to SEP items with parameters that can be trended. SEP Reference Number 16 Eagit e increase HPES and IR Accountability through use of Performance Indicators Procedural Noncompliance incidents (Maintenance) . . . 34 Recordable injury /lliness Cases Frequency Rate 24 Clean Controlled Area Contaminations >1,000 Disintegrations / Minute Per Probe Area 25 Preventable / Personnel Error LERs .
. 26 SEP Reference Numbers 25. 26. & 27
- Training Program for Managers and Supervisors implemented
. Evaluate and implement Station Standards for Safe Work Practice Requirements = lmplement Supervisory Enforcement ofIndustrial Safety Standards Industrial Safety Accident and Disabling injury / Illness Rate . 20 Recordable injury /lliness Cases Frequency Rate 24 SEP Reference Number 31 = D velop Outage and Maintenance Planning Manual and Conduct Project Management Training MWD Planning Status (Cycle 19 Refueling Outage) 47 Component Testing Department, Special Services Engineering Department 1998 Outage Projects .48 Progress of 1999 Refueling Outage Modifications Cycle 19 . 49 Progress of 1998 On-Line Modification Planning 51 SEP Reference Number 33
- Davslop On-Line Maintenance and Modification Schedule Progress of Cycle 19 Outage MODS and ECN's Added to '99 Refueling Outage After Freeze Date 50 SEP Reference Number 36
= Rsduce Corrective Non-Outage Backlog Maintenance Workload Backlogs (Corrective Non-Outage) . 32 SEP Reference Numbers 41 & 44
- Dsyslop and implement a Preventive Maintenance Schedule
. Compilance With and Use of Procedures Ratio of Preventive to Total Maintenance & Preventive Maintenance items Overdue 33 Procedural Noncompliance incidents (Maintenance) 34 SEP Reference Number 46 De::Ign a Procedures Control and Administrative Program Document Review 37 55
L g SAFETY ENHANCEMENT PROGRAM INDEX SEP Reiergy;;9 Number 52 Eagg
. Estabilv.h Supervisory Accountability for Workers Radiological Practices Radiological Work Practices Program 36 SEP Reference Number 64
. Complete implementation of Radiological Enhancement Program Collective Radiation E40sure . 19 Volume of Low-Level Solid Radioactive Waste . .. . 21 Clean Controlled Area Disintegrations 21,000 Counts / Minute Per Probe Area 25 Contaminated Radiation Controlled Area .. . . . 35 SEP Reference Number 61
. R2 Vise Physical Security Training and Procedure Program Secunty incidents . 38 SEP Reference Numbers 60 & 61
. Improve Controls Over Surveillance Test Program
. Modify Computer Program to Correctly Schedule Surveillance Tests Licensee Report LER Root Cause Breakdown Number of Missed Surveillance Tests resulting in Licensee Event Reports 27 SEP Reference Number 62
. E:tablish Interim System Engineers Temporary Modifications 39 Engineering Assistance Request (EAR) Breakdown . 41 Engineering Change Notice Status . 42 Engineering Change Notices Open .
43 SEP Reference Number 68
. Assess Root Cause of Poor Operator Training and establish means to monitor Operator Training License Operator Requalification Training 45 License Candidate Exams . 46 SEP Reference Number 71 . Improve Controls over Temporary Modifications Temporary Modifications . . . . 39 56
Fort Calhoun Station Opsrating Cycles and Refueling Outage Dates l EVENT l DATE RANGE l PRODUCTION (MWH) l CUMULATIVE (MWH) l Cycle 7 12/21/81-12/03/82 3,561,866 24,330,034 Cycle 8 04/06/83-03/03/84 3,406,371 27,736,405 Cycle 9 07/12/84-09/28/85 4,741,488 32,477,893 Cycle 10 01/16/86-03/07/87 4,356,753 36,834,646 Cycle 11 06.'08/87-09/27/88 4,936,859 41,771,505 Cycle 12 01/31/89-02/17/90 3,817,954 45,589,459 Cycle 13 05/29/90-02/01/92 5,451,069 51,040,528 Cycle 14 05/03/92-09/25/93 4,981,485 56,022,013 Cycle 15 11/26/93-02/20/95 5,043,887 61,065,900 Cycle 16 04/14/95-10/05/96 5,566,108 66,632,007 Cycle 17 11/25/97-04/01/98 5,183,108 71,815,678 Cycle 18 06/04/98-10/02/99 CURRENT PRODUCTION AND OPERATIONS " RECORDS" Firs
- Sustained Reaction August 5,1973 (5.47p.m.)
First Electricity Supplied to the System August 25,1973 Commercial Operation (180,000 KWH) September 26,1973 Achieved Full Power (100%) May 4,1974 Longest Run (477 Days) June 8,1987-September 27,1988 Highest Monthly Net Generation (364,468,800 KWH) October 1987 Most Productive Fuel Cycle (5,451,069 MWH-Cycle 13) May 29,1990-February 1,1992 Shortest Refueling Outage (53 days) February 20,1995-April 14,1995 October 4,1996-November 27,96 4 57
Milsstons Schedula 1999 OUTAGE MILESTONE WEEKS PRIOR MILESTONE STATUS TO START DUE DATE
- 1. Mod, ECN, & Project (approved for planning) 79 MAR 6 '98
- Freeze date Complete
. 2. System Window Structure Finalized 63 JUN 26 '98 Complete ~
- 3. " Backbone" Schedule Developed & Issued 60 JUL 17 '98 Complete
- 4. Begin System Window meetings 57 AUG 7 '98 Complete
- 5. Shift Outage Managers identified 57 AUG 7 '98 Complete
- 6. Mod & ECN (approved for accomplishment) 52 SEPT 11 '98 Freeze Date Complete
- 7. Special Project (approved for accomplishment) 44 NOV 20 '98 Freeze Date Complete
- 8. PMO and ST Freeze Date 40 DEC 18 '98
- 9. Preliminary Project Schedule Due Date 34 JAN 29 '99 (all Outage Projects) 26 MAR 26 '99
- 10. Modification Final Design Package Due Date 26 MAR 26 '99
- 11. Overall Outage Scope Freeze Date 26 MAR 26 '99
- 12. Complete System Window Review Meetings 16 JUN 4 '99 16 JUN 4 '99
- 13. Modification & ECN Plan & Schedule Due Date 12 JUL 2 '99
- 14. Project Plan & Schedule Due Date 12 JUL 2 '99
- 15. Preliminary Outage Schedule issued 12 JUL 16 '99 58
Milostons Schedulo 1999 OUTAGE MILESTONE WEEKS PRIOR MILESTONE STATUS TO START DUE DATE
- 16. Outage Management Team identified 12 Jul 2 '99
- 17. Modification & ECN Construction Work Order Due Date 9 Jul 16 '99
- 18. Resource Availabilities identified 8 JUL 23 '99
- 19. Issue Final Detailed Outage Schedule for Review 6 JUL 23 '99
- 20. Maintenance Work Orders " Ready to Work" 4 AUG 20 '99
- 21. All Material and Parts for the Frozen Outage scope 4 AUG 20 '99 On-Site
- 22. Management Meeting to Approve Final 4 AUG 20 '99 Outage Schedule
- 23. NSRG and Operations Review (and approval) 4 AUG 20 '99 of Schedule
- 24. ALARA Package, Radiation Work Permits 1 SEP 10 '99 c,d Tagouts Comp.
- 25. Breakers Open 0 SEP 18 '99 f
59 1
MONTHLY PERFORMANCE INDICATOR SOURCES WANO PERFORMANCE INDICATORS ARE IN BLUE Indicator Source Extension INPO Noteworthy /Significant Events . . . Donna Guinn 6937 Unit Capability Factor Unplanned Capability Factor ' Unplanned Automatic Reactor Scrams per 7000 Hours Critical . Mike Edwards 6929 High Pressure Safety injection System Safety System Performance Chuck Schaffer 6830 Auxiliary Feedwater System Safety System Performance . . Craig Fntts 6554 Emsrgency AC Power System Safety System Performance . Rich Ronning 6887 Thsrmal Performance . .. . Kevin Naser 6889 Fut! Releabilityindicator . Rich Roenigk 7214 S2condary System Chemistry . . . Mark Ostien 7109 Indu: trial Safety Accident & Disabling injury / Illness (Lost Time Accident Rate) R:cordable injury / illness Frequency Rate . . Duane Booth 6558 Colisctive Radiation Exposure Cisen Controlled Area Contaminations Contaminated Radiation Controlled Area Radiological work Practices Program . Colette Williams 7163 Volume of Low Level Radioactive Waste . . Mark Breuer 7193 Prov2ntable/ Personnel Error LERs Licensee Event Report (LER) Root Cause Breakdown . Erick Matzke 6855 Violation Trend . . .. Gary Cavanaugh 6913 Maintenance Rule SSC Unavailability. Steve Swearngin 6836 Cents Per Kilowatt Hour . . .
. Claudio Huang 6626 60
i MONTHLY PERFORMANCE INDICATOR SOURCES : Indicator Source Extension . Maint: nance Workload Backlog Ratio of Preventive to Total Maintenance Preventive Maintenance items Overdue MWD Planning Status (Cycle 18 Refueling Outage) . .. Martin Johnson 6956 Parconnel Error Rate Procsdural Noncompilance incidents (Maintenance) . Mike Burggraf 6675 Document Review . . . Judy Plath 7370 S:curityincidents . . . Al Clark 6666 Tcmporary Modifications . Russ Plott 6557 Out:t:nding Modifications g Progrsss of 1999 Refueling Outage Modifications Cycle 19 Progress of Cycle 19 Outage MODS and ECNS Added to 1999 Rzfurling Outage After Freeze Date Progrsss of 1998 ON-Line Modification Planning . . . Pat Walling 6950
~
Engin:ering Assistance Request Breakdown Enginzering Change Notice Status Enginzering Change Notice Open . . None Licensed Operator Requalification Training ,, Licanze Candidate Exams 1998 . Calvin Ralrick 6061 Component Testing Department and Special Services Enginzering Department 1999 Outage Projects Status Report . Chris Boughter 6684 61
- _ _ _ - _ _ _ _ . _ _}}