ML20148Q383
| ML20148Q383 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/31/1997 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20148Q373 | List: |
| References | |
| NUDOCS 9707070068 | |
| Download: ML20148Q383 (89) | |
Text
{{#Wiki_filter:... . FORT CALHOUN STATION PERFORMANCE INDICATORS
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May 1997 SAFE OPERATIONS PERFORMANCE EXCELLENCE COSTEFFECTIVENESS [87 ISSIS oE00hjS
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OMAHA PUBLIC POWER DISTRICT .I l FORT CALHOUN STATION i PERFORMANCE INDICATORS REPORT I l l May 1997 1 i i i i I Engineering and Operations Support Division
. NuclearLicensing
1 FORT CALHOUN STATION - l MAY 1997 ~' Monthly Operating Report l I i l i OPERATIONS
SUMMARY
1 l The Fort Calhoun Station (FCS) operated at a nominal 100% power level until April 21, 1997 when the reactor was manually tripped by the Control Room operators due to a ruptured extraction steam line. The determination was made to proceed to Cold Shutdown to make repairs to the Extraction Steam piping and other equipment. Plant startup ; commenced on May 11,1997 at 2157 hours and stabilized at 30% reactor power, until May l 14,1997 at 1245 hours. Reactor power was then increased and reached 100% power on May 19,1997 at 0300 hours. FCS experienced a second steam leak which caused the operators to reduce reactor powel to 10 percent. An investigation determined that a circumferential cracked weld down stream of a moisture separator occurred due to high system stress. The reactor remained critical while repairs were made on-line. On May 30,1997 at 0600 hours reactor power was returned to 100% for the remainder of the month. I O e I
-e- rertCalhounindexh g IrdskyMadanindexwiue 97/5lndustry Mxianves 86.P/. I 97/5 OPPDWiusves 86.3% l 83 _ :31 a
- 80 e -v " " - 85 l
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(. 70 -- I 60 -- g.. mforusy19s7wasas.3 40 : : l : : : : : : : ! l 964 95f1 95/2 963 96/1 96f2 96/3 96/4 97/1 Apr Nhy June I PERFORMANCE INDEX TREND The performance index trend calculation is made up of eleven variables each weighted to arrive at an overall index value. The thermal performance, secondary system chemistry, and industrial safety accident rate values are calculated for a one-year period. Fuel reliability is calculated on a quarterly basis. The - remaining values (unit capability factor, unplanned (unit) capability loss factor, unplanned automatic scrams per 7000 hours critical, safety system performance, and collective radiation exposure) are calculated for a two-year period. This method allows the index trend to be more responsive to changes in plant performance. INP0 no longer uses the volume of low-level radioactive waste as a plant indicator. The value will still be tracked, but the value will no longer be used in calculating the Station's Performance Index.
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i I eMAXNUM VALUE e Apil'97 OMay S7 16.00 - q MN- ! ggq na- ~~; 888 888 8.8
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ese SSS 2"2 8 888 8 8.00 - aRRgg aaa 5 g
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-4 i UCF UCLF HPSI AFW EACP CRE UAS7 FRI CPI TPI ISAR I l
f This graph shows the difference between the Maximum No. of points for each WANO indicator and the actual value achieved by Fort Calhoun. The [ current graph shows the difference between April'97 and May '97. UCF Unit Capability Factor TPI Thermal Performance Indicator ! UCLF Unplanned Capability Loss Factor CPI Secondary ChemistryIndicator ! HPSI High Pressure Safetyinjection ISAR Industrial Safety Accident Rate i AFW Auxiliary Feedwater . EACP Emergency AC Power UAS7 Unplanned Auto Scrams / 7000 Hours CRE Collective Radiation Exposure ; FRI Fuel ReliabilityIndicator ! I Per INPO, the Performance Indicator for the Volume of Low Level Radioactive Waste buried, will no longer be used in calculating the Station's Performance Index. All other parameters have been adjusted to reflect this change ! iii l l [
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l - FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT May 1997-
SUMMARY
F POSITIVE TREND REPORT ADVERSE TREND REPORT I A performance indicator with data representing three A performance indicator wnh data representing three
. consecutive months of improving performance or three consecutive months of declining performance or three consecuhve months of performance thatis superior to the consecutive months of performance that is trending stated goal is exhibiting a positive trend per Nuclear toward decining as determined by the Manager - Nuclear Opershons Division Quakty Procedure 37 (NOD-QP-37). Licensing, constitutes' an adverse trend per Nuclear
- Operabons DMsion Quahty Procedure 37 (NOD-QP-37).
i The fouowing performance indicators exhibited positive A supervisor whose performance indicator exhibits an trends for the reporting month: adverse trend by this deAnition may specify in written form . (to be published in this report) why the trend is not adverse. k Hiah Pressure Safety Iniection System Safety System The following performance indicators exhibited adverse Performance trends for the reporbng month: (Page 5) Maintenance Workload Backtoos ' Thermal Performance (Page 39) (Page 8) Secondarv Chemistry INDICATORS NEEDING INCREASED ! (Page 10) MANAGEMENT ATTENTION REPORT i INDUSTRIAL SAFETY ACCIDENT RATE A performance indicatorwith data for the reporting period (Page 13) that is inadequate when compared to the OPPD goal is . defined as 'Needing increased Management Attention" i I Qemistry Action Levels Exceeded-Event Days per (NOD-QP-37). (Page 34) Unit Cacability Factor PRIMARY SYSTEM LITHlUM % HOURS OUT OF LIMIT (Page 2) (Page 35) l Unoianned Cacability t.oss Factor , l , IN-LINE CHEMISTRY INSTRUMENTS OUT-OF- (Page 3) i SERVICE l (Page 44) Fuel Reliability index
- (Page 9)
Hazardous Waste Produced (Page 45) CLEAN CONTROLLED AREA CONTAMINATIONS l (Page 17) l Forced Outaae Rate l (Page 26) I
- Cents Per Kilowatt Hour
{, (Page 37) 9 Ratio of Preventive To Total Maintenance 1 (Page 40) Contaminated Radiation Controlled Area (Page 46) 4 jy Temocrary Modifications (Page 50) 1
l l . i l WANO INDICATOR VALUES { (As compared to previous month) . J j Uriit Capability Factor Decreasmg i 1 Unplanned Capability Loss Factor Decreasing i
. High Pressure Safetyrinjection . No Change )
Aux. Feedwater System No Change ! Emergency AC Power increasing Collective Radiation Exposure Decreasing Unplanned Automatic Reactor Scrams No Change Fuel Reliability Decreasing Chemistry Indicator increasing l Thermal Performance No Change Industrial Safety Accid %t Rate No Change l A i 3 ) 1 i 6 4 O V
1 4 Table of Contents / Summary p GQALS........................................................................em . . xii WANO PERFORMANCE INDICATORS 'D ! Unit Capability Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... ........................... 2 Unplanned Capability loss Factor . . . . . . . . . . . .... ... ... . .... ...... ............. 3 Unplanned Automatic Reactor SCRAMS per 7000 Hours . . . . . . . . . . . . . . . . . . . . . .........4 i 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 l .. 1 i Volume of low level Radioactive Waste . . . ... . . ...... .. .. ...... .... . 12 l ) H 1 1 Industrial Safety Accident Rate . . . . . . . . . .. . .... ... . ..... . ..............13 1 2 SAFE OPERATIONS . Disabling injury / Illness Cases Frequency Rate . ....... .. ... ..... .. .. . .. 15 e 4 Recordable injury / Illness Cases Frequency Rate . . . . . . . . . . . . . . . . . . . . . . ... . ... . 16
- Clean Controlled Area Contaminations 11,000 Disintegrations / Minute per Probe Area . ... .. . . .. .............17 Preventable / Personnel Error LERs . . . . . . . ............ .. .. ....... ... . .. . . 18
. Safety System Failures . ... .... . .. ... ... . .. . . ... . . . . .. . ... . 19 Maximum individual Radiation Exposure . . . . . . .. ..... . ... .... ..... .. . 20 a . , Violation Trend . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... . . .... .. . 21 1
Significant Events . . . . . . . . . . . . . . . . .. . ... . .. .. . . .. .. . .. 22 Missed Surveillance Tests Resulting in LERs . . . . . . . . . . . . . ... . . . . 23 vi
l l i l I Table of Contents / Summary l l L l P PERFORMANCE i , Station Net G en e ratio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 5 , Forced Outage Rate . .............................................................26 i Unit Capacity Factor . . . . . . . . . . . . . . ..... .................. ..... ........... . . 27 Equivalent Availability Factor . . . . . . . . . . ........ .......................... ........... 28 Unplanned Safety System Actuations INPO Definition . . . . . . . . . . . . . . . . . . . . . . . ... .... ... .. ......... .... . 29 NRC Definition . ................. ........ ............. .. . . ..........30 G ross He at 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 umit ....... .... .. . ............... .. . . ... 35 , i l COST Cents Per Kilowatt Hour . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... ......... ..... .. 37 i i DMSION AND DEPARTMENT PERFORMANCE INDICATORS l Maintenance Workload Backlogs (Corrective Non-Outage) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39 1 Ratio of Preventive to Total Maintenance . . . ... ................. . . . . .. .... 40 l Percentage of Total MWOs Completed per month identifieri as Rework . . . . . . . . . . . . . . 41 Ove rtim e . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . ... .. ...... ..... .. 42 Procedural Noncompliance incidents . . . . . . . . . . . ....... . ... .. ... ........ 43 In-Lir'e Chemistry instruments Out-of-Service ...... ...... .... ........... .... ... .. .. 44 Hazardous Waste Produced . .. . . ... ...... .. ... . ...... .............45 l 1 i
, Contaminated Radiation Controlled Area . . . . . . . . . . . . .. . .... . . 46 )
i 1 Radiological Work Practices Program ... ..... .. ..... .. . 47 1 1 Document Review . . . .. .. . .. .. .. . ... . . .. .. .. 48 l ! t t : 1 2 yll I
J N Table of Contents / Summary Loggable/Reponable incidents (Security) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49 Ternporay uoerncations . . . . . . . . . . . . . . . . ............................................So
. Outstanding Modmcations . . . . . . . . . . . . . . . . . . . . . . . . . . ... ............. . .. .. .... Si I
l Engineering Assstance Request (EAR) Breakdown .. ... ............ .. ... ........... .. 52 Engineering Change Notices Status .................. . . ............. ..... .................... ... ... 53 Open....................................................... ..... . . .. 54 Ucensee Event Report (LER) Root Cause Breakdown . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . ... 55 , Ucensed Operator Requalification Training ... .... . ...... . ......... . .. ........ .. 56 i Ucense Candidate Exams . . . . . . . . . . . . . . . . . . . . . .. . ... ......... . . .. ...,.. . 57 Condition Reports .. ......... ... .................... . .................. .... ... 58 Cycle 18 Refueling Outage ] MWO Planning Status .. ........... . . ... ... .... ............ ..... ...... 59 l Overall Project Status . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....... 60 i Outage Modification Planning ............ .. .... .. ..... .... .... . . . . . . . . . 61 On-Une Modification Planning . . . . . . ............ ... ......................... 62 ! Progress of 1997 On-Une Modification Planning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........63 l ACTION PLANS. DEFINITIONS. SEP INDEX & DISTRIBUTION UST , Action Pla ns . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. . ... .... ......... . ........... 64 Performance indicator Definitions . . . . . . . . . . . . . . . . . . . . ....... .. ... . . .. ......... 66 Safety Enhancement Program index . .............. . ..... .. ..................74 Report Distribution Ust . . . . . . . . . . . . . . . . . . . . . . . ...... . . ...........76 O viii
NUCLEAR PROGRAM 1997 GOALS AND OBJECTIVES FUTURE FOCUS and RELATIONSHIP to CHANGE
, The nation's electric utility industry is passing through a period of significant organizational, financial and cultural changes, in this new era, change is inevitable, progress and success are not. Fort Calhoun must react to these changes while improving capacity, SALP ratings and INPO ratings. ,
1 We must KNOW OUR COSTS to CONTROL COSTS. Understanding cost is essential to controlling l It, and controlling cost is essential to competing in today's market. j We are a leaming organization. We must BUILD ON OUR HIGH PERFORMANCE CULTURE. Individuals at alllevels must take responsibility for their actions and must be committed to improve their own performance. OUR CULTURE MUST SUPPORT THE NEW STRATEGIES. We must continue to develop and implement strategies that will allow us to effectively compete in the evolving market while still maintaining the highest levels of safety and reliability. Communicating is our key to improving. Follow up and feedback must be candid, forthright and timely. We recognize that change causes disruption of work and work flow. That change requires increased management direction. We need IN-DEPTH, RELENTLESS ATTENTION to our NEW FOCUS / STRATEGIES. VISION To be recognized as the best nuclear organization in the world and to preserve nuclear energy as a viable future energy source. i MISSION The safe, reliable and cost effective generation of electricity for OPPD customers through , conservative decision making and the professional use of nuclear technology. We will conduct these operations to assure the health, safety, and protection of our personnel, the general public, and the l environment. 1 e e ix i 1
( GOALS < Goal 1: SAFE OPERATIONS Supports: April 1996 Corporate *+-d;!c Plan Goal 3, Objective: 3 & 4 A proactive, self-critical and safety conscious culture is exhibited throughout the nuclear organization. Individuals demonstrate professionalism through self-ownership and personal initiative and open communication. 1997 Priorities:
. Achieve an overall SALP Rating of"1"in 1997.
. Focus on Achieving an INPO Rating of"1"in 1998.
Reduce 1997 NRC violations with no violations more severe than level 4.
. No unplanned automatic reactor scrams or safety system actuations. ,
Objectives to support SAFE OPERATIONS. OBJECTIVE 1-1: ; No challenges to a nuclear safety systems. OBJECTIVE 1-2: Comply with applicable policies, technical specs, procedures, standing orders and work instructions. 1 OBJECTIVE 1-3: . Identify conditions BEFORE they affect plant safety and reliability. Address every safety concem. l 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.
I i X l
_ . _ . ._ . _ _ . . . . _ . - . _ __ __ _ _ ~ _ _ _ _ _ _ _ l OPPD NUCI FAR ORGANIZATION GOALS 1997 Priorities l Goal 2: PERFORMANCE i Supports: April 1996 Corporate Strategic Plan Goal 3, Objective: 2; G-4, Objective: 1,2, & 3; G-5, Objective: 2 Nuclear teamwork achieves high performance at Fort Calhoun Station as exhibited by safe, reliable and 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 Hurnan Performance errors.
. Identify Programmatic performance problems through effective self assessment.
. Maintain a high level of readiness in the ERO.
Objectives to support PERFORMANCE: OBJEC11VE 2-1: Achieve an annual plant capacity factor of 92.7% and a unit capability factor of 96.0%.
]
OBJECTIVE 2-2: Training meets the needs of the plant and the National Academy accreditation objectives.
. Line managers use training to present, discuss & reinforce performance standards.
. Line managers monitor and assess personnel performance to determine how well standards are met.
. Line managers through personal involvement in training emphasize the importance of conducting activities within approved procedures / practices.
. Executive Training Committee:
. invites line supervisors to discuss the direction training is going for their specific area.
e invites the line and training supervisors responsible for each accredited program to provide a status of intemal accreditation assessments.
. ensures items such as training attendance, attentiveness, punctuality, etc. are , uniformly emphasized.
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t i i l OPPD NUCLEAR ORGANIZATION GOALS 1997 Priorities Goal 2: PERFORMANCE (Continued) OBJECTIVE 2-3: Achieve all performance-related 1997 performance indicator goals in the Performance Indicator Report. Focus on performing basic skills well, while pursuing efficient, cost-effective work processes. Identify the barriers to excellence and resolve them. 1 l OBJECTIVE 2-4:
.q Plan for the completion of the 1998 refueling outage in 42 days ofless. '
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 Supports: April 1996 Corporate Strategic Plan Goal 2, Objective: 1, 3, and Goal 5, Objective: 1 Operate Fort Calhoun cost effectively to contribute to OPPD's " bottom line". Cost consciousness is exhibited at all levels of the organization. 1997 Priorities: l
. Maintain total O&M and Capital Expenditures within budget. , j
. Streamline work process to improve cost effectiveness. l
. Implement Opportunity Review recommendations. l Objectives to support COSTS:
OBJECTIVE 3-1: Conduct the nuclear programs, projects, and activities within the approved Capital and O&M budgets. 1 OBJECTIVE 3-2: Significantly reduce operating costs through full support of Utilities Service Alliance initiatives by maximizing sharing of resources, leveraging of buying power and elimination or reduction of redundant support services. Goals Source: Lounsberry (Manager) xii
U i i i t t r i . i I i e 1 i 1 ( 2 k I ! l i ! l 4 WANO ! B l PERFORMANCE l l t l ND CATORS l 5 i t l t a t4 I i i I i j l . l i i h i i i l 4 4 b b l - -- ____ _ _ _ _ _ _ -- .,-... .
M26thly U111 Ca ptillity F2 ster
.-x . 12 Usst:t Uzit Ccpa tility Faster
- 1997 Fort Calheen Goal (99%)
e --- Ye a f 2000 W AN O Ind ustry O sal (87%) . 10 0% -- - - - _ 7 7 Q. -u TM .
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40% -- 20% -- 0% Jun Jul Aug Sap O ct Nov Dec Jan Feb M ar Apr M ay UNIT CAPABILITY FACTOR This indicator shows the plant monthly Unit Capability Factor (UCF) value, a rolling 12-month average, the OPPD goal, and the WANO 2000 goal. UCF is defined as the ratio of the available , energy generation over a given period of time to the reference energy generation over the same time period, expressed as a percentage. The UCF for May 1997 was reported as 43.7%. The year-to-date UCF was also reported as 92.4%, the UCF for the last 12 months (June 1996 through May 1997) was 69%, and the 36-month average (June 1994 through May 1997) was reported as 81.5%. Energy losses, from May 28 thru May 29, circumferential cracking of a weld down stream of a moisture separator due to high system stresses. Energy losses from April through mid May were attributed to a steam leak in the fourth stage eextraction steam system. Energy losses for April 1997 are attributed to a steam leak in the fourth stage extraction steam system Energy losses for June 1996 are due to a forced outage when the Anti-Rotation Device on Reactor Coolant Pump RC-3B-M failed. Energy losses for Sept., Oct., & Nov.,1996 due to the scheduled Refueling Outage. Energy losses for Dec.1996 are due to MOV-CV leakage The Year 2000 WANO industry goal is 87% and the industnf current best quanile 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 May 1997, the FCS Value was 12.66. This compares to the previous month's value 14.13. Data Source: Generation Totals Report & Monthly Operating Report Accountability: Chase Trend: Increased Management Attention 2
. . Mordhly Lkiplanned Capability Ims Faer
-A- 12&rdh Rdhng Aerage
.+- FortOdhmmGael(tEP4
-r,- year 2000waroindueycosi gra on, -
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Jm M Aup Sep Oct Nov Dec Jun Feb Mar Apr Muy UNPLANNED CAPABILITY LOSS FACTOR This indicator shows the plant monthly Unplanned Capability Loss Factor (UCLF), a rolling 12-month average, the OPPD goal, and the Year 2000 WANO goal. 'JCLF is defined as the ratio of the unplanned energy losses during a given period of time, to the reference energy generation expressed as a percentage. Unplanned energy loss is defined as energy not produced as a result of unscheduled shutdowns, outage extensions, or load reductions due to causes under plant management control. Energy losses are considered , to be unplanned if they are not scheduled at least four weeks in advance. The UCLF for the month of May 1997 was reported as 56.3%. The year-to-date UCLF was 7.63%, the UCLF for the last 12 months (June 1996 through May 1997) was 14.48%, and the 36-month average UCLF (June 1994 through May 1997) was reported as 8.5% at the - end of the month. The Year 2000 WANO industry goal is 3.0% and the industry current best quartile value is approximately 3.2%. The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 1.58%. The maximum index point value for this indicator is 12. At the end of May 1997 the FCS Value was 11.55. This compares to the previous month's value of 11.66. Data Source: Generation Totals Report & Monthly Operating Report l Accountability: Chase , l Trend: Increased Management Attention ' i 3
--+- 12 M eath Colling Av erag e
+- FCS Reactor Scrams Per 7,000 Hours Critical for last SS months
, -*- Fort C alh oun G oal(0.o)
Year 2000 WANO Industry Goal (1) 3 -- 2--
'1 - - -- V- - --
o al> + + + + 0 * ; + ; e , Jun Jul Aug Sep O ct Nov Dec Jan Feb M ar Apr M ay FCS Reactor Scrams 1997 4 -- 3-- 2-- 1 , 1-- o o o o o o o o o o o ,o o ! 95 96 Jun Jul Aug Sep Oct Nov Dee Jan Feb Mar Apr May UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7000 HOURS CRITICAL The upper graph shows the 12-month rolling average, the 36-month average, the OPPD goal for 1997 and the Year 2000 WANO goal. The lower graph shows the number of unplanned automatic reactor scrams that occurred during the last 12 months. This indicator is defined as the number of unplanned automatic scrams that occur per 7,000 hours of critical operation. ' There were no unplanned automatic reactor scrams during the month of May 1997. The 12-month rolling average (June 1996 through May 1997) was 0. The 36-month value (June 1994 through May 1997) was 0.311. 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 hours critical. The maximum index point value for this indicator is 8. At the end of the May 1997, the FCS Value was 8.0. This compares to the previous month's value of 8.0. Data Source: Monthly Operating Report & Plant Licensee Event Reports (LERs) Accountability: Chase Trend: None 4
m MonthlyHPSIsystem UnavailabilityValue
-*- 12 Month Rolling Avera08 *
--*-- Fort calhoun Goal (0.003)
-e-- Year 2000 WANo Industry Goal (0.02) 0.02 -- 4 o o a o a a o a a a o ,
0.015 -- . 0.01 --
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e~ e + : e s : e + o e 0 l l s ': ; e ; :' l :' , .
" ~~* l 1996 Jun Jul Aug Sep oct Nov Dec Jan Feb Mar Apr May 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 May 1997.
The HPSI System unavailability value for the month of May 1997 was 0.0041. There were 9.2 hours of planned unavailability, and 0 hours of unplanned unavailability, during the month. The 12 month rolling average was (June 1996 through May 1997) was 7.9E-5, - and the year-to-date HPSI unavailability value was 1.020E-3 at the end of the month. For the previous year there was a total of 1.2 hours of planned unavailability and 0.0 hours of unplanned unavailability for the HPSI system. The 1997 Fort Calhoun year-end goal for this indicator is a maximum value of 0.003. The Year 2000 WANO industry goal is 0.02. The maximum index point value for this indicator is 10. At the end of May 1997 the FCS Value was 10. This compares to the previous month's value of 10. Data Source: Phelps/Schaffer (Manager / Source) Accountability: Phelps/Schaffer Trend: Positive 5 , i i 1
i Fm Monthly Auxiliary Feedwater System Unavailability
-x-12 Month AFW Unavailability .
-*-- Fort Calhoun Goal (0.01)
Year 2000 WANo industry Goal (0.025) 0.025 -- y , 0.022 0.02 -- t .. :. . , . :. l 0.015 -. 0.013es 0.01 -- : : : : : : : : : j 0.004s3 0.00604 0.005 -- 0.00358 . 0.00186
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O l , l l , l l l l , l l 1997 Jun Jul Aug Sep oct Nov Dec Jan Feb Mar Apr May AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE ! ! This indicator shows the Auxiliary Feedwater (AFW) System Unavailability value, as a defined by INPO in the Safety System Performance indicator Definitions, for the month of i ! May 1997. i
- The AFW System Unavailability Value for May 1997 was 0.0 hours. There were 0.0 hours 4 of planned and 0.00 hours of unplanned unavailability during the month. The 12 month
- rolling average (June 1996 through May 1997) was 0.00435, and the year-to-date -
- unavailability value was 0.00607 at the end of May 1997.
The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 0.01.
- The Year 2000 WANO industry goal is 0.025.
The maximum index point value for this indicatoris 10. At the end of May 1997, the FCS
- Value was 10. This compares to the previous month's value of 10.
I Data Source: Phelps/Fritts (Manager / Source)
- Accountability
- Phelps/Fritts
. Trend: None i
a 6 i ?
m Monthly Emergency AC Power UnavailabilityValue
--++- Year-to-Date Emergency AC Power UnavailabilityValue
-*- Fort Calhoun Goal (0.024) t Year 2000 WANO Industry Goal (0.025) 0.05 --
0.04 -- : 0.03 -- . 4=====4 0.02 -- 0.01 -- X X ~x x X -- - x 0 i I I I
" l 1 I I I E
I I I Jun Jul Aug- Sep Oct Nov Dec Jan Feb Mar Apr May EMERGENCY AC POWER SYSTEM - SAFETY SYSTEM PERFORMANCE This indicator shows the Emergency AC Power System unavailability value, as defmed by WANO in the Safety System Performance Indicator Definitions, for the month of May 1997. The Emergency AC Power System unavailability value for May 1997 was 0.006. During the month, there were 8.9 hours ofplanned unavailability, and 0.0 hours ofunplanned unavailability for testing and repairs. The Emergency AC Power System unavailability value year-to-date was 0.010 and the value for the last 12 months (June 1996 through May 1997) was 0.011. There have been 71.2 hours (36.75 for DG-1 and 34.45 for DG-2) of planned unavailability and 0.0 hours of unplanned unavailability for the emergency AC power system in 1997. There were a total of 163.5 hours ofplanned unavailability and 3.7 hours of unplanned unavailability for the emergency AC power system in 1996. The 1997 Fort Calhoun year-end goal for this indicator is a maxunum value of 0.024. The Year 2000 WANO industry goalis 0.025. The maximum index point value for this indicator is 10. At the end of May 1997, the FCS Value was
- 10. This compares to the previous month's value of10. .
Data Source: Phelps/Ronning (Manager / Source) Accountability: Phelps/Ronning Trend: None 7
._ . _ . - _ _ . . _ . . . _ _ . _ . _ . _ . _ . . _ _ _ ~ . . _ . _ _ . _ . ~ _ . _ . . . _ . _ . . . _ _ _ . _ . . . _ . _ _ _ . _ .
m MonthlyThermalPerformance i i
' 12. Month Rolling Av: rage I -*-- Fort camoun Goal (99.9%)
j -*- Year 2000 WANo industry Goal (99.8%) . !~ l 100% --
~
_. ? A E E - . E 1 1 l ! 09% --
)
f 1996 l RFO i 98 % l l l l l l l l LH j Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May THERMAL PERFORMANCE l This indicator shows the monthly Thermal Performance Value, the rolling 12-month l average, the OPPD goal, and the Year 2000 WANO goal. The thermal performance value for the month of May 1997 was 99.87%. The year to date value was reported as 99.8%. The 12 month rolling average (June 1996 through May 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 May 1997, the FCS Value was 5.34 This compares to the previous month's value of 5.34.
. Data Source: Phelps/Naser(Manager / Source)
Accountability: Phelps/Naser Trend: Positive 8
m Fusi R: liability (E 4)
-*- Yoct 2000 WANO etil (5 x 10 4 MicracurieNG rim)
-*-- 1997 Carl 147E-4 320.. 299.16 l 280 -- 257.07 217.e 3 240 --
I 200 - , 3,, , 180 -- 1996 j 120 -- RFO ,, y 80 - S 40 -- tea m 2D 45 3, , 0 "t- "rt"-
"t"" -"" """ * ""*- 1" - ~"* '"""t *"""'t M "r " M"t" ~1 " E"~r E i Jun Jul Aug sep Oct Nov Dec Jan Feb Mar Apr M ay FUEL RELIABILITY INDICATOR The FUEL RELIABILITYINDICATOR(FRI) for May 1997 was 29.7 E-4 microcuries/ gram. This FRI value is trending similar to the April 1997 FRI of 31.1 E-4 microcuries/ gram. Only the steady state data at 100%
power and an average letdown flow of 33.67 gpm from May 22 through 27 was used in the calculation of the May FRI. The plant was manually tripped at approxunately 8:23 p.m. on April 21 and did not return to 100% power until May 19. On May 27 power was also reduced for a steam line repair with a return to 100% power during the evening of May 31. The Cycle 17 FRIin the first six months of operation contmues to trend simdar to the Cycle 16 FRI values. Based on the coolant chemistry data through the end of May 28, there is no change to the April 1997 Westinghouse fuel failure prediction of 8 to 14 leaking rods at lower core power levels (i.e.,<50% or 3 to 5 leaking rods at care average power. During May, most isotopics did not have time to obtain an equilibrium state due to the plant trip and a power reduction. It typically takes a muumum of three weeks at 100% power to obtain an equilibrium state for the I-131 and Xe-133 isotopics. The purpose of the FRI is to monitor industry progress in achiesing and maintaining a high level of fuel integrity. An effective fuel integrity and performance monitoring program prosides a means to detect fuel failures and assess the fuel failure number, physical condition, exposure, mechanism, and location. The purpose of the FRI is to monitor industry progress in achiesing and maintammg a high level of fuel integrity. An effective fuel integrity and performance monitoring program prosides a means to detect fuel failures and assess the fuel failure number, physical condition, exposure, mechanism, and location. The 1997 Fort Calhoun Station FRI Performance Indicator goal is to maintain FRI below 147 x 10-4 microcuries
/ gram. This goalis based upon previous cycles fuel performance, results of the most recent fuel inspection and reconstitution campaigns, and an improved fuel failure resistant grid design in the new assemblies (Batch U) in -
the Cycle 17 core. The maxunum index point value for this indicator is 8. At the end of the May 1997, the FCS Value was 3.24. l This compares to the previous month's value of 3.79. 1 Data Source: Gumn/Guliani Accountability: Chase /Stafford Trend: Increased Management Attention 9
.- . . ~ . . - . - - - - - - - - -
m MonthlyChernistryindicator
-*-- 12-Month Rolling Average .
Fort Calhoun Goal (1.17) 2.6 -- 2.s -- 2.4 -- 2.3 - 2.2 -- 2.1 -- 2-- 1.9 -- 1.s -- .
> 1.7 --
1.6 - 1.s --
- a 4 6 o A- L 2 1.2 -- Y .
1.1 -- - " 1-- 0.9 -- 0.s -- 1996 RF0 0.7 -- ! 0.6 -- I 0.5 I I I l l
! ! l I l l l
Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May I . SECONDARY SYSTEM CHEMISTRY 1 i j Criteria for calculating the Secondary System Chemistry Performance Index (CPI) are as follows: ) 1) the plant is at greater than 30% power. j 2) the power is changing at less than 5% per day.
- The CPI for May 1997 was 0.86. The CPI value for the past 12 months (June 1996 through May 1997) was 1.29. In order to place the FCS in the industry's upper quartile, the 1997 goal has been -
j changed from a CPI value < l.4 to the CPI value < 1.17. I Six parameters are used in the CPI calculation. Four of the parameters were below the INPO mean i value which are as follows: 1) steam generator chloride, 2) sulfate, i 3) feedwateriron, and condensate pump discharge dissolved oxygen. Steam Generator sodium was i above the mean value and has remained unchanged from the previous month. FH-6 copper remains i 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 May 1997, the FCS Value was j- 6.68. This compares to the previous month's value of 6.37.
i
- Data Source
- Hamilton /Ostien (Manager / Source i
Accountability: Hamilton Trend : Positive
+
10 1 l 4
m Canthly Perstna:1 Radi:/Jan Expaturs
-+-- C u m ul:tivo Pc t 22asi Ridi;tlin Exposura
--e-- F C S Ceci 38 pst:24a. RED 40 -- -
- : -o-~~ o o- o o o o a 36 --
30 -- 26 -- ' l 4 - i 20 --
.l l
16 -- 10 -- 1 6-- e 0 Jan Feb M ar Apr May Jun Jul Aug Sep O ct Nov Dec COLLECTIVE RADIATION EXPOSURE The 1997 Fort Calhoun goal for collective radiation exposure is set at 38.0 person-REM. The exposure for May 1997 was 5.753 Person-Rem (ALNOR). The year-to-date exposure through the end of May 1997 was 18.214 Person-Rem
'(ALNOR).
This indicator is a " COLLECTIVE" indicator. WANO does not differentiate between on-line and outage exposure. The Year 2000 WANO industry goal for collective radiation exposure is 120 person-rem per year. For the three year period (June 1994 through May 1997), the collective radiation exposure was 401.317 person-rem (ALNOR). This gives a Fort Calhoun Station a three year average of 133.7723 person-rem per year (ALNOR). The maximum index point value for this indicator is 8. At the end of May 1997 the FCS Value was 7.2. This compares to the previous month's value of 7.2. Data Source: Chase / Williams (Manager / Source) Accountability: Chase /Gebers Trend: None SEP54 11
1 m MonthlyVolume cf LLRW(w.c.)
-*- Year-to-Date Cumulative Radioactive Waste Buried I
_, -+- Fort Calhoun Goal (1200 cu.ft.) . 1200 - e + * : + + .e e- e e 1100 -- ; I
,1,000 --
900 -- 800 -- . 700 -- g .00 -- 800 -- 400 -- 300 -- 200 -- 8 E E S 100 - -{ ts E G
-x ti Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov . Dec VOLUME OF LOW-LEVEL RADIOACTIVE WASTE
- This indicator shows the volume of the monthly radioactive waste buried, the
- cumulative year-to-date radioactive waste buried, and the Fort Calhoun goal.
Cu.Ft. Amount of solid radwaste shipped off-site for processing during current month 00.0
- 9'Jme of solid radwaste buried during May 1997
. 17.4 .
Cumulative volume of solid radioactive waste buried in 1996 16.0 Amount of solid radwaste in temporary storage 136.3 The 1997 Fort Calhoun Station goal for the volume of solid radioactive waste (buried) is i 1200 cubic feet. The Year 2000 WANO industry goal is 45 cubic meters (1,589 cubic feet) per year. The industry upper ten percentile value is approximately 27.33 cubic meters (965.3 cubic feet) per year. This indicator is no longer used by INPO. The indicator will still be tracked, but will no longer be used in computing the Station's Index Number. j-Data Source: Chase /Breuer (Manager / Source) Accountability: Chace/Gebers Trend: None SEPS4 12
--o- Monthly industrist Accident Rate
-e-- 12 Month Rolling Average .
- $- FCS Year End Goal (<0.00)
-ty- Year 2000 WANO industry Goal (<0.40) 1.2--
1-- - 0.8 -- 0.6 -- ,
," h , , , , , ,
0.4 I i I I $ 1 -
.', A 0.2 -
0 - - - . - June July Aug Sep Oct Nov Dec Jan Feb Mar Apr May 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 man-hours are not included in the indicator. This indicator is defined as the number of accidents per 20,000 man-hours worked for all utility personnel permanently assigned to the station that result in any of following:
+ One ormore days ofrestricted 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 May 1997 was 0.00. The 12 month rolling average (June 1996 through May 1997) was 0.1502. The year to date value was 0.00 at the end of May 1997. There were no restricted-time and no lost-time accidents in May 1997. The 1997 Fort Calhoun year-end goalis 50.50. The Year 2000 WANO industry goal is 50.40. The maximum index point . value for this indicator is 5. At the end of May 1997, the FCS Value was 5.0 This compares to the previous month's value of 5.0. Data Source: Sorensen/Blumenthal (Manager / Source) Chase / Booth (Manager / Source) Accountability: Chase / Bishop Trend: Positive 13
)
SAFE OPERAT ONS i Goal: A proactive, self-critical and safety conscious culture 3 is exhibited throughout the nuclear organization. ! Individuals demonstrate professionalism through self-ownership and personal initiative and open communication. d. i l . l l l 14 1
l l l --+-- Monthly Disabling injury 41Inees Fraquency ,
*~ 12 Month Rolling Average I l ,
-e- 1997 OPPD Goal l-2 --
TJ -- 1.6 -- 14 . 1.2 -- 1-- l l
\
0.3 -- N
\
0.6 -- ._
\
7m ; - --a l g, 2 2 0.2 -- h,. , 0 . : : 0 -
- l l Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May l DISABLING INJURY / ILLNESS FREQUENCY RATE (LOST-TIME ACCIDENT RATE) l I
This indicator shows the May 1997 disabling injuryTdiness frequency rate and the disabling ! injury / illness rate for the past 12 months (rciling average). For the month of May 1997 the disabling injury /diness frequency rate was 0.00. For the 12 month
- period (June 1996 through May 1997) the disabling injury /diness rate was 0.15. There were no disabling injuryTdiness cases reported for May 1997.
The 1997 Fort Calhoun Station year-end goal for this indicator is a mammum value of 0.5. 1 Data Source: S orensen/Blumenthal (Manager / Source) Accountability: Chase / Bishop Trend: None SEP 25,26 & 27
! 15 t
1
---o- Mon 2lyR:cordible injuryntin:ss FrequencyRate ;
-*----Colling 12 MonIt Avtrags j I
o Fort Calhoun Coal 4.5 -- I 4.0 - 35-- 3'0 -- ", 2.5 -- -
), --k _
2.0 - - ,4 -- _ g g -
- - ~
1.50 - - e -o 4 e - e ...... 4 - o - o
? 4 10 , l , l Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May RECORDABLE INJURY / ILLNESS FREQUENCY RATE This indicator shows the monthly recordable injury / illness frequency rate, a rolling 12 i month average, and the OPPD goal. A recordable injury / illness case is reported if personnel from any of the Nuclear Divisions are injured on the job and require corrective medical treatment beyond first aid. The :ecordable injury / illness cases frequency rate is computed on a rolling 12 month average.
The recordable injury / illness frequency rate for the month of May 1997 was 1.55. The recordable injury / illness frequency rate for the past 12 months (June 1996 through . May 1997) was 1.65. During the month of May 1997, there was 1 recordable injury in which an employee reported, while welding. Slag fell between the welding jacket sleeve and shirt sleeve which resulted in the employee receiving first, second, and third degree burns to the left forearm.
. l There have been a total of 4 recordable injury / illness cases in 1997. l
~
The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 1.5.
]
Data Source: Sorensen/Blumenthal (Manager / Source) Accountability: Bishop Trend: None SEP 15,25,26 & 27 I 16 l l I
I l l M C ontamination Events (M onthly)
+ Contamination Eve nts (YTD) 1- 100 -
l 30 -- 00 -- s-10 -- 00 -- 00 -- l 40 -- ; t l 30 -- 20 -- o s0 -- *
,f
~
l ,/* Jan Feb M ar Apr M ay Jun Jul Aug sep O ct Nov Dec l 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 21,000 disintegrations / minute per probe area for May 1997. l There was 3 contamination events in May 1997. There have been 12 contamination events in 1997 through the end of May 1997. ; Data Source: Chase / Williams (Manager / Source) i Accountability: Chase /Gebers Trend: Needs Management Attention SEP 15 & 'J4 I 17 l I l
I I m P;rsonn:1 Errora (Esch Mon 2)
- +- Pr;v table (18-Mon"i Totals) c P;rsinn:1 Error (18-Month Tot:Is)
, 20 -- - 15 -- d , 10 --
-j ,
~
~
C C [ c 0 , , , Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May PREVENTABLE / PERSONNEL ERROR LERs This indicator depicts 18-month totals for numbers of " Preventable" and " Personnel Error" LERs. The graph shows the 18-month totals for preventable LERs, the 18-month totals for Personnel Error LERs, and the Personnel Error totals for each month. The LERs are trended based on ine LER event date as opposed to the LER report date. Due to the manner in which cocumentation is closed out, data for this Performance Indicator lags by one month. . In May 1997, there were two events which were subsequently repoded as an LER. One LER was categorized as Preventable and one LER was categorized as Personnel Error , for the month of May. The total LERs for the year 1997 is four. The total Personnel Error LERs for the year 1997 is one. The 1997 goal for this indicator is that the year-end values for the 18-month totals not exceed 12 Preventable and 5 Personnel Error LERs. , Data Source: Tills /Cavanaugh (Manager / Source) Accountability: Chase Trend: None SEP 15 18
l l . l r i Startup l - m Shutdown . l Operations
. o . Industry Average Treruf E
l :li I E l '5 1 -- o .c- .... .a --
.a - - -
o -- o - o -o c l $ 0 ' 92-2 92-3 92-4 93-1 93-2 93-3 93-4 94-1 94-2 94-3 94-4 95-1 Year-Quarter SAFETY SYSTEM FAILURES This indicator lilustrates the number of NRC Safety System Failures as reported by the Nuclear Regulatory i Commission's Office for Analysis and Evaluation of Operational Data in the biannual " Performance Indicators l for Operating Commercial Nuclear Power Reactors" report. The following safety system failures occurred between the 2nd quarter of 1992 and the 1st quarter of 199b: F 1st Quarter 1993: The SG low pressure scram signal block reset values, for all 4 channels of both SGs, were l 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 l system was not seismically qualified. This could have resulted in a failure of the system to meet design requirements during a seismic event. 4th Quarter 1993: 1) During surveillance testing, both PORVs for the LTOP system failed to open during multiple attempts. The failures were a result of differential expansion caused by a loop seal, excessive venting l line back pressure, and cracked valve disks; 2) Calibration errors of the offsite power low signal relays could l have prevented offsite power from tripping and the EDGs from starting in the required amount of time during
- a degraded voltage condition; 3) Both AFW pumps were Inoperable when one was removed from service for testing and the control switch for the other pump's steam supply valve was out of the auta position.4) Only one train of control room ventilation was placed in recire 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-I minute period.
1 1st Quarter 1994: A design basis review determined that an ESF relay could result in loss of safety injection and spray flow, due to premature actuation of recirculation flow. I 4th Quarter 1994: An accident scenario was identified that could result in the inoperability of both control room air conditioning units. Following certain accident conditions, CCW temperature could rise causing compressor rupture disc failure and a release of freon. There were no safety system failures since the 4th quarter of 1995. Data Source: Nuclear Regulatory Commission Accountability: Chase Trend: None 19 l
aus W Mordy M Expmn mR . t- 3 Year te date
- +--Fort Calhoun Gael 1000 mR 1000 0 0 0 0 0 0 0 0 0 0 0 0 900-800 -
700 - - 600 500 - 400-300 - 200 - E
&n Feb Mar Agr May .A.n .M Aug Sep Oct Nov Dec MAXIMUM INDIVIDUAL RADIATION EXPOSURE This indicator shows the highest exposure for an individual during January 1997.
For the month of May 1997, an individual accumulated 157 millirem, which was the highest individual exposure for the month. For the year to date, an individual has accumulated a total of 549 millirem (TLD). The 549 mR is down from the previous reading of 556 mR due to TLDs being read. The 556 1 mR came from ALNOR readings, and in general, are higher than TLD readings. l i The OPPD limit for the maximum yearly individual radiation exposure is 4,000 mrem / year. The 1997 Fort Calhoun Station year-end goal is a maximum of 1,000 mrem. l l Data Source: Chase / Williams (Manager / Source) Accountability: Chase /Gebers Trend: None 20
. _.. . . - . __. . . _ . . . . . _ . . - _ . _ _... _m_.m. __ . , _ . _ . . _ _ . . _ . . . _ _ . . . -.m_.__ .__.m_._ _ _ _ . . _
m FIS Cited VIItatieIs pactly) c FIS Cat-Cited Violacess(Muthly) i FIS Cited VIIlatie3s(1241Ds2 Averigs) 4
-4>-- FCS Non Cited Violations (1248enth Average)
-pe- Region IV Cited Violadens(12 Month Average for Region IV top quartile) 12 --
6-- O &"" - % 4-- C : : : : : : : : : a
- n. un a e, m ,, m, June July Aug Sep Oct Nov Dec Jan Feb M ar Apr May VIOLATION TRENT This indicator illustrates a 12-month trend for Fort Calhoun Station Cited Violations, Non-Cited Violations and Cited Violations for the Top Quartile plants in Region IV.
Additionally, the Fort Calhoun Station Cited and Non-Cited Violations for the past 12 ' months will be illustrated monthly. The 12-month trend for the Region IV top qua,rtile lags 2-3 months behind the Fort Calhoun Station trend. This lag is necessary to compile information on other Region IV plants. The following inspections were completed during May 1997: IER No. Title 97-01 Initial Operator Exams 97-02 Emergency Program Plan 97-06 Engineering & Technical Support Team Inspection 97-07 Resident Monthly l 97-08 Physical Security Program - l 97-09 Special Inspection-Steam Line Rupture l 97-11 Special Inspection-incorrect Estimate to Criticality ' To date, OPPD has received six violations from inspection reports received in 1997. Level lli Violations 0 Level IV Violations 4 Non-Cited Violations .2 Total 6
. The 1997 Fort Calhoun Station Goal for this performance indicator is to be at or below the cited violation trend for the top quartile plants in Region IV.
Data Source: Tills /Cavanaugh (Manager / Source) Accountability: Tills Trend: None 21
NRC Significant Events
-o- IndustryAverageTr:nd 1 1 1- -
0.5 -- , , 0 , S , 92 93 94 95-1 95-2 95-3 95-4 96-1 96-2 96-3 96-4 Year - Quarter e INPO SignFicant Events (SEs) l 3 *I 3-2 , 2-- 9 1-- 0 0 0 0 0 0 0 0 l l l l ; , , ; 93 94 95-1 95-2 95-3 95 4 96-1 96-2 96-3 96-4 97 1 l l Year-Quarter SIGNIFICANT EVENTS 1 NRC SIGNIFICANT EVENTS , The folowing SEs were identified between the 2nd Quarter of 1992 and the 1st quarter of 1995 (as reported in the NRC's
' Performance Indicators for Operating Nuclear Power Reactors' report dated June 30,1995):
3rd Quarter 1992: The failure of a Pressurizer Code Safety Valve to reseat initiated a LOCA with the potential to degrade the reactor coolant pressure boundary. 4th Quarter 1994: A potential accident scenario iruolving a large break LOCA or a main steam line break inside containment could result in the inoperabiltty of both control room A.C. units. INPO SIGNIFICANT EVENTS The following SEs have been identified since 2nd Quarter of 1992 by INPO: 2nd Quarter 1992: Intake of transulanics during letdown filter change-out. 3rd Quarter 1992: Safety Valve malfunction (RC-142). 1st Quarter 1993: Inoperability of Power Range Nuclear Instrumentation Safety Channel D. 2nd Quarter 1993: Inadequate control of Switchyard activities. 3rd Quarter 1993: Loss of reactor coolant due to malfunction of Pressurizer Safety Valve. 1st Quarter 1994: 1) Unexpected CEA withdrawal. (Event occurred November 13,1993 but was not identified as an SE until 1st Quarter 1994).
- 2) Unplanned dilution of Boron concentration in the Reactor Coolant System.
1st Quarter 1996: During pressurizer solid plant operation, the Low Temperature Overpressurization l I (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
I Mased STs Resulting in LERs ; i 3 -- , I i-2-- l 1-- O O O 0 0 0 l 0 : : : : : : : : l l : l
- 96 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec I
NUMBER OF MISSED SURVEILLANOE TESTS RESULTING IN LICENSEE EVENT REPORTS This indicator shows the number of missed Surveillance Tests (STs) that resulted in Licensee Event Reports (LERs) during May 1997. l
. 1 There were no missed surveillance tests resulting in LERs during May 1997.
The 1997 Fort Calhoun monthly goal for this indicator is 0. Data Source: Monthly Operating Report & Plant Licensee Event Reports (LERs) Accountability: Chase /Phelps Trend : None SEP 60 & 61 23
l I l ! l i l 1 - l l PERFORMANCE l l < f j Goal: To strive for Excellence in Operations utilizing ,the j highest standards of performance at Fort Calhoun Station that j result in safe, reliable plant operation in power production. l l l I n i i i i l I 1 1 i l 24 i . l 4 0
l l l Net Generation (10,000 MWh) ,
- 40 --
34.84 34.st 34,43 35.14 32.s2
;- 30 os 0--
24.37 h RCP z outa g. RFO g 20 -- ts.os k 15.18 l , 10 -- ! O i i I I I
- ! , I I I I Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May
! STATION NET GENERATION l l I During the month of May 1997, a net total of 165945.2 MWh were generated by the Fort Calhoun Station. Cumulative net generation for Cycle 16 was 5,418,326.6 MWh Cumulative net generation for Cycle 17 was 1,806,389.7 MWh at the end of May 1997. Data Source: Station Generation Report Accountability: Chase Trend: None 25 3
Y r i MonthlyForced outage Rate
-+-Rolling 12 Month Average -
-*- 1997 Fort Calhoun Goal (1.4%)
50% -- _ 45% -- c sgg ..
~
35% -- c 3ng .. - 25% -- 25 -- 15% -- 10% -- / 5% - T : : : : : 0 0 0 /
= ' = = ' = = ' = '
= = = = =
0% . l : l l 96 Jun .lul Aug Sep oct Nov Dec Jan Feb Mar Apr May FORCED OUTAGE RATE The forced ouage rate (FOR) for the month of May 1997 was 43.3 %. The forced outage rate for the previous 12 months (June 1996 through May 1997) was 12.02%. The 1997 year-to-date FOR was 15.0% at the end of May 1997. Energy Losses are described in the " Unit Carability 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: Increased Management Attention 26 l
m MonthlyUnitCapacityFactor
~ G Year-t>Date thitCapacstyFador x Unit CapacityFactorfor Cycle 17
-+ 1997 FCS Goal (96.WA) 117A-
~
1FA- ' " '
"*~" -a spa .., w k
- g. e__ . . _ .
..D,. ,, e d.... .. ... -
e sea - Chcie17 WA- \ 474 -
- m. \/
=-
19A -
\ j/
\;
rA \ \ \ ;
\ : E, \ , : : : n C-16 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May UNIT CAPACITY FACTOR
.i This indicator shows the plant monthly Unit Capacity Factor, the Unit Capacity Factor for
- the cunent fuel cycle, the year-to-date, and the 1997 OPPD Station goal.
l l Unit Capacity Factor = Net Electrical Enerav Generated (MWH) j Max. Dependable Capacity (MWe) X Gross Hours in the Reporting Period i i l Cycle 16 Unit Capacity factor was 85.23%. i l At the end of May 1997, the Cycle 17 Unit Capacity Factor was 70.82%. The Unit ! Capacity Factor for the last 36 months (June 1994 through May 1997) was 81.5%. The j 1997 Fort Calhoun annual goal for this indicator is 96.00%. !' The year-to-date value is 92.4%. i- Data Source: Monthly Operating Report Accountability: Chase ] Trend: None j 27 l 4 l J 1
Mrathly EAF
~*- Year-to-Dat] Avsr:ge Centhly EAF
-*- 12 Cznth Rolling Av:r ge
-*-CPPD Ctrl 183% -- ,
s c
~
Y " 7 91% - % s ;;-a ..-- = c '
/ ,
i' s,2', m- %
..i. _
1996 RFO 0% SS May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr. May 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 May 1997 was 45.7 %. The 12 month rolling average (June 1996 through May 1997) was 69.29%. The equivalent availability factor for the past three years (June 1994 through May 1997) wr.s 82.98%. The Fort Calhoun Station goal for this indicator is an EAF of 93.00%. Data Source: Dietz/Vandervert/Mikkelsen (Managers / Source) Accountability: Chase Trend: None 28 I i l _a
M d. ))stemActudions(N'O Definition)
-e - 6. oosito)
--+- Ind'JetryUrps10 Percent 0e(0) -
3.. Q 2-- - l 1-- , i 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 , e : : : : : : : : : : : : : , : : : l. l 96 Jun .Ad Aug Sep Oct Nov Dec Jan Feb Mar Apr Mr/ l UNPLANNED SAFETY SYSTEM ACTUATIONS -(INPO DEFINITION) There were no WANO unplanned safety system actuations during the month. i There were no WANO unplanned safety system actuations during 1996. The 1997 Fort Calhoun goal for this indicator is 0. l.
~
Data Source: Accountability: Monthly Operating Report & Plant Licensee Event Reports Phelps/Foley Trend: None .~ . 29 1
I Scfaty Syst3m A: tutti na (NRC Definition) i < FCS Goal (0) { , --+- C ritical H o u rs l 10 -- 1996
-- 800 RFo 8- RFO c
-- 600 6-- - -- 500 f 4~~
-- 400 $
h f -- 300
-- 200 o 2--
m <
-- 100 1 0 -l l l l ;l l l l l l l l l l l ; l l l l l l l l l l 0 MAMJJASONDJFMAMJJASONDJFMAM 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/Foley Trend: None O 30
- . . . . . . - . . . - . . - . . _ . . . - . - = - - - . _ . . _ - . .
! m Gross Hcat Rate
-- Year-to-Date Gross Heat Rate l -+- Fort Calhoun Goal .
14.75 -- i 14.25 -- 13.75 - , 13.25 -- h 12.75 -- - E S 12.25 -- m g 11.75 -
" 11.25 --
i 10.75 -- 10.75 - .. w 1" - - g 3 9.75 -- 1 j 9.25 - , 96 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May -l .I f l GROSS HEAT RATE l
- l. This indicator shows the Gross Heat Rate (GHR) for the reporting month, the year-to-date GHR, the goals, and the year-end GHR for the previous three years.
i The gross heat rate for Fort Calhoun Station was 10,038 BTU /kWh for the month of May , 1997. The 1997 year-to-date GHR was 10,025 BTU /kWh at the end of the month. The GHR varies with fluctuations in river water temperature. In general, the GHR improves during the winter months and degrades during the summer. This is because the l gross heat rate is not normalized to the design river water temperature of 60 degrees j Fahrenheit. l The 1997 Fort Calhoun year-end goal for this indicator is 10,166 BTU /kWh.
! Data Source: Guinn/Schawe (Manager / Source) i Accountability: Chase /Skiles i Trend: None 31 l
I i
-+-Thermal QAput
-+-Fort onthoun ime MChel
,, + Tech 8pec1500Mundt -
) eooonnn0 0 e n n o n o n n ,,u-a n o n o n <s nnnno l 16-q 130- -
4 i I I G-
=
8(D - I G- . ED-0: 0 0 0 0 0 0 0 0 0 . , , , , , . 1 2 345 6 78 9 10 11 12 13 14 15 16 17 18 19 2D 21 22 23 24 25 3 27 3 29 30 31 DAILY THERMAL OUTPUT l The thermal output graph displays the daily operating power level during May 1997, the l 1500 thermal megawatt average technical specification limit, and the 1498 thermal megawatt Fort Calhoun goal. ; Data Source: Guinn/Schawe (Manager / Source) - Accountability: Chase /Short l Trend: None , 32
-+- Monthly Equipment FoR
--M-- Equipment FOR/1,000 Critical Hrs. (Rolling 12-Month Interval)
--*-- Fort Calhoun Year-End Goals (0.2) 2--
4 1 4 S E ! h 1 - \ 0 0 : : : : 0
~
Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May E EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS 2 The equipment forced outage rate per 1,000 critical hours for the 12 months from June 1,1996, through May 31,1997, was 0.289. The year-to-date rate per 1,000 critical hours for the months from February 1,1997 through May 31,1997 was 0.376. n An equipment forced outage occurred during the month of June 1996, due to the failure of the Anti-Rotation Device associated with RC-3B-M. The equipment forced outage that occurred April 21,1997 was attributed to the rupture of ) 4 a fourth stage extraction steam pipe. A second outage occurred on May 24 due to weld I crack which caused reactor power to be reduced to 10% while repairs were made on-line. 4
. The 1997 Fort Calhoun year-end goal for this indicator is a maximum value of 0.20. 1 1
Data Source: Monthly Operating Report & Plant Licensee Event Reports (LERs) l Accountability: Chase /Phelps ' Trend: None l 4 33
.. - ~. - . _ -
, CHEMISTRY ACTION LEVELS EXCEEDED i l mums Ewnt Days +A:erage Ewnt Days +--oPPD umiit 3-2.5 - p 2- 0 -
'l 1.5 - i l
l
- l 3
q l O.5 - 0 k $ k k k lk E k i E a Y f i a a a s s a e a e $ e 1 a MONTH l 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 level is exceeded. The parameter action levels are delineated in Chemistry procedure CH-AD-0003, " Plant System Chemical Limits and Corrective Actions". An action level is considered to have been exceeded for the purpose of this indicator, whenever the parameter exceeds the CH-AD-0003 action level for the current system mode, with the exception of the SteamGenerators during Mode 1. The Steam Generators are considered to have exceeded an action level in Mode 1 when the
- plant power is greater than 30% and the power is changing less than 5% per day.
The number of event days can exceed the number of days in a month since each event is l counted sepaiately and there can be multiple events per day. The 1997 Fort Calhoun goal for this indicator is the 12-month average of two event days per month. There is no goal established for the number of event days per individual month. Historical data is used to calculate the monthly average event days. The 12-month average was calculated by dividing the number of event days by the number of preceding months, until twelve months were reached. There were no event days in May. ,, Data Source: Chase / Hamilton (Manager / Source) Accountability: Hamilton l Trend: Positive l l 34 l
l i i%Fixssof dumit l 1100 . -+-CPPD God (5%)
, 1400--
l 1 REl -- ! E00 -- . 0 0 0 0 0 0 0 0 0 0 0 0 1 1 100--
- l E00 : : : : : l l : : l l l 1 5 3 E " U j 5 E 7 ' < $ O z o
$" E 7 a 2 4 2
t PRIMARY SYSTEM LITHlUM % HOURS OUT OF LIMIT i 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 1.21% for the month of ; May 1997. The 1997 Fort Calhoun Station monthly goal for this indicator is a maximum of 5% hours out of limit. - 1 i 4 i s. Data Source: Chase / Hamilton (Manager / Source) Accountability: hamilton Trend: Postive 35 4 4
l. j w i i l cost l Goal: Operate Fort Calhoun Station in a manner j that cost effecibaly maintains nuclear generation j as an economically viable contribution to OPPD's i bottom line. Cost consciousness is exhibited at all l levels of the organization. i. i i 36
--*-- Actual -e- Bud 0et --e - Plan 3.80 3.80 - -
3.40 - 3.20 - A 8"' 2.s0 - m'%_a e.% 1 2.80 - 2.40 - "' 2.20 - 2.00 E E a E R g'2 < 2 ' ' < m o z o ggggg bbbbb I CENTS PER KILOWATT HOUR - ; April 1997 The purpose of this indicator is to quantify the economical operation of Fort Calhoun Station. I The cents per idlowatt 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 a. mounts 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 Pfanning and Budget Review. The basis for the generation is provided by Nuclear Fuels. .
- The 12-month rolling average unit price (period of March,1996 through April,1997) averaged above the )
budget due to 12-month rolling expenses exceedmg the budget and the 12 month rolling average (3/96 through . 4/97) is 3.24 cents per kilowatt hour.
\
The year-to-date average is trending in a negative direction. Cents per KWH Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Budget Y-T-D 2.83 2.66 2.58 2.55 2.31 2.50 2.51 2.49 2.48 2.48 2.46 2.45 ; Actual Y-T-D 2.89 2.60 2.54 2.75 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 l Data Source: Lounsberry/ Dent (Manager / Source)
, . Accountability: Lounsberry Trend: Increased Management Attention 37 i
i l l l l l k DIVISION AND l i DEPARTMENT l PERFORMANCE l I INDICATORS . Goal: Achieve high standards at Fort Calhoun Station
- resulting in safe, reliable and cost effective power production.
l t I f 38
d 1 l Corrective Maintenance m Preventive Maintenance
~
i i Non-Corrective /PlantIrnprovements Fort Calhoun Goal j 1000 " 870 780 720 684 632 l l Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Non-Outage Maintenance Work Document Backlog a TotalIMtk Past compktion Cornpleted $ En .m s W -- s 62%
$0212$l'f"$12 P1' E bi E ..$74k!
ses ]' f Priaity Pricity Pricrty Pnaty Pncrity 1 2 3 4 5 Not completed MAINTENANCE WORKLOAD BACKLOG i , 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 350 non-outage corrective maintenance MWDs. The current backlog ofcorrective MWDs is 379. To ensure that the MWD backlog is worked in a timely
} manner, non-outage maintenance completion goals have been established as follows: ^ G9.al Priority 1 Immediate Action 24 hours Priority 2 Urgent 5 days 4 Priority 3 Operational Concerns 21 days
- Priority 4 Routine Corrective 90 days i Priority 5 Non-Essential 180 days
. O Data Source: Chase / Johnson (Manager / Source)
Accountability: Chase /Faulhaber l* Trend: Adverse SEP 36 39 I i
. _ - . . _ _ _ . . _ . _ . . - _ _ _ . . . _ _ _ _ . _ _ . _ - . . . _ . _ , _ _ _ . _ _ . . . _._....._m_.._ . . . . _ . _ . _ . . _ .
Ratio cf Pr2Vcntys to Tetal Mtinun:nsa 90% -- 30% -- *
~
3 70% -- 80% -- 50 % - 40% -- h%-- Data N/A N/A 20% -- 10% -- - 0% i i l I I I I I I I I l Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May M Preventive Maintenance items Overdue
-*-- Fort Calhoun Goal 3% "
2.50% 2% -- 0.76% 0.83% - 1% "
- 0.39% 0.10 % 0.56% 0.58%
0.00% 0% - 1 1 I , , I i l Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 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 83.6% for the month of May 1997. The lower graph shows the percentage of scheduled preventive maintenance items that are overdue. During May 1997,356 PM items were completed. The 1997 Fort Calhoun monthly goal for the percentage of preventive maintenance items , overdue is a maximum of 0.5%. Data Source: Chase / Johnson (Manager / Sources) ' . Accountability: Chase /Faulhaber Trend: Increased Management Attention SEP 41 & 44 40
I l l
, Monthly Overtime (On Line) ;
Y-T-D M onthly Average (On Line) Fort Cathoun "O n-Line" 0 cal (10%) 10.0% -- : : * = * : : : : , , 9.8 % 9,.0 % -- I s.0% -- ' i 7.0% -- ' 6.0% --% ! 5.0% - K 4.0% -- 3.0% -- 2.0% -- 1.7% 1.0% -- , 0.0 % 0 0"' Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec , MAINTENANCE ONLINE OVERTIME The Maintenance Overtime Indicator monitors the ability to perform the desired maintenance activities with the allotted resources while on-line. The percent of overtime hours with respect to normal hours was reported as 0% for the . month of May 1997. Forced outage overtime was 35.5%, therefore on-line overtime was zero for the month. 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 /Fauthaber Trend: None 42
_ _ _.__ _ ___ _ _ _ _ _ _ _ _ _ _ _-. _ ._ _ _ __ _._ _ _.. _ ._.. _ ___ _ . _ _. _ _ ~ . - . _. _ _ .___._ _ _ _ . 4 4 Hum n Performrnes cRs (Msintsnsnce) 20 -- it -- 4
/
16 -- t 14 - , I! 12 --
?
10 -- j 8-- 6 6 6-- i ; i i t i i Nov Dec Jan Feb Mar Apr May PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE) This indicator shows the number of Condition Reports related to procedural noncompliance incidents assigned to the Maintenance Department. Data Source: Faulhaber Accountability: Chase /Faulhaber Trend: None SEP 15,41 & 44 - 43 1
. _ _ _ . _ . _ _ _ , _ _ . . . _ . _ _ _ _ _ _ _ _ _ _ . = - _ . _ _ _ . _ _ _ . . _ . _ _ _ _ . _ _ - . _ . . - . . . _ . . . - _ . . . _ . _ . . . . _ . - _ _ _ _ _ _ . _ . .
m No. Mairtertance items completed -+--% k$erti6ed as Repeat l 700- 6.0%
) -
600 - l" 526 - 5.0% l
~
4.0% 288
- 3.0% l 4 300 - 252 23g 179 248 I 00 4 0 i
- i i i 0.0%
i Jun JJ Aug Sep Oct Nov Dec Jan Feb Mar Apr May b i
- m Rework as identified by Craft j j -*- Fort C alhoun G oal(<3% ) l 4
4.sm 7 5'/. . . i & 1 l ( 4% -- 3% -- o- - 2% - s..m 885 .s g s.e s s.s m l N .,, _. 3 ...m ...m ...m i** l 0% : : ,
- , I l :
j Jun Jul Aug Sep Oct Nov Dec Jan Feb M ar Apr M ay i i ! PERCENTAGE OF TOTAL MWDs COMPLETED - !; PER MONTH IDENTIFIED AS REWORK / REPEAT ' I i This graph indicates the percentage of total MWDs completed per month identified as rework. Rework activities are identified by maintenance planning and craft. l This indicator is calculated from the 15th of April to the 15th of May, 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: None 41
-4p.--% PASS OOS -X-% Non-PASS 005
. -A- % Total 005 -+--Total % OOS Goal .
60% - 45% - 40% -
, 35% -
j 30% - l - 2s% . i 20% - 15% - 10% , t^ : : : : : : : : : ss " ~E' 0% x - --y
/ . .
9; y - ----g .
- 1 -
- :Nx-! =
g E E E E 3 8 E
~
2 3 3 g E k k $ N $ b b k $ h k i IN-LINE CHEMISTRY INSTRUMENTS OUT-OF-SERVICE This indicator shows the percentage of hours the in-line chemistry system instruments arc inoperable for the reporting month. The chemistry systems involved in this indicator include the Secondary System and the Post Accident Sampling System (PASS). At the end of May 1997, the percentage of hours the in-line chemistry system instruments were inoperable was 3.46%. The following instrument was out of service for the current month:
- 1. % PASS HOURS OUT OF SERVICE - NONE >
- 2. % NON-PASS HOURS OUT OF SERVICE Al *l10 Hydrogen was out of service from 4/12 thru 5/31 1997.
The entire instrument channel is considered inoperative if: 1) the instrument is inoperative,
- 2) the chart recorder associated with the instrument is inoperative, or 3) the alarm function associated with the instrument is inoperative. If any of the functions listed above are not -
operational, then the instrument is not performing its intended function. Data Source: Chase /Ostien (Manager / Source Accountability: Chase /Skiles Trend: Positive 44 l l
M Weste Produced Each Month (KHograms)
-*- Fort Calhoun Conthly Average Goal (150 kilograms) a Federal & State Monthly Unit (Max. of 1,000 kg) ,
1000- 6- .. t. e o .. ; ; ; e 900 - ' I y 800 --
~
g s g 600 -- Ei 500 --
- g .L g..
200 -- 0 + e + e. e + e- e + e 100 -- O l , l l , ; l Jun Jul Aug Sep oct Nov Dec Jan Feb Mar Apr May HAZARDOUS WASTE PRODUCED l 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. i During the month of May 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 cort Calhoun monthly average goal for hazardous waste produced is a maximum
, of 150 kilograms.
i Data Source: Chase /Shubert (Manager / Source) l Accountability: Chase / Hamilton i Trend: Positive 45 l
.. . ..... - . . . . . . . . ~ - . - . . - . - - . . . . _ . . . _ _ . . . . . . ~ . _ - . - - . . _ - - , . . . _ . - _ _ .
t m Centandn: led Radliti:n Controlled Aron i
-4>-- Fort Calhoun Goal (5%) ,
10% -- : : : e : : ::::.. L-9% -- 2 l.,e llllll lllm I l I l i Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 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 goalis a maximum of 5.0% contaminated RCA. At the end of May 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: Needs increased Management Attention SEP 54 '! 46
i
- Ps r R:di: tion Werk:r Pr:ctic:s
- Fcrt cchoun Grcl(c15) 1s .
14 - 12 - 10's 8-8- 4-2 2
^ ^
2- ~ \ 0 Jan Feb
'/
Mar AF May June July Aug Sep Oct Nov Dec RADIOLOGICAL WORK PRACTICES PROGRAM l 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 l to qualitatively assess supervisor accountability for their workers' radiological performance.
]
During the month of May 1997, there were 2 PRWP identified. . There have been a tota: of 4 Poor Radiation Worker Practices in 1997, l The Fort Calhoun Station year-end goal for PRWPs is a maximum of 15, l i I l- i i Data Source: Chase / Hamilton (Manager / Source) Accountability: Chase /Gebers ! Trend: None SEP 52 1 47 l l
- - . . - .-. .- ~ .-
4 O Documents scheduled for R; view 5 Documents Reviewed 1
, 5 Documentsoverdue
- 450 -
400 . - 356 -- 3o0 . -
~
250 - 200 -- 150 - 100 -- 50 - 0--- k l - 1- +- +- +- +- +- k- l Jun Jul Aug sep oct Nov Dec Jan Feb Mar Apr May 1996 DOCUMENT REVIEW 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 May 1997, there were 300 document reviews scheduled, while 120 reviews were completed. At the end of the month, there were 37 document reviews more than 6 months overdue. There was 7 new documents initiated during May 1997. Data Source: Chase /Plath Accountability: Chase /Skiles Trend: None SEP 46 48
O Systam Fallures O M o n S ysts m Failu re s 27 25 -- 20 -- , , , , gg.. Jun Jul Aug Sep O ct Nov Dec Jan Feb M er Apr May l LOGGABLE/ 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 May 1997, there were 15 loggable/ reportable incidents identified. l System failures accounted for 87% of the total failures. Six (6) of the thirteen (13) non-
- environmental system failures (47%), involved the x-ray machine. I&C technicians are l currently working with the vendor attempting to solve the problem. There were no environmental failures during the reporting month. The two non-system failures consisted of one security force error, and one error involving visitor control.
i This indicator provides information on security performance for Safety Enhancement Program (SEP) Item No. 58. Data Source: Sefick/Woerner (Manager / Source) Accountability: Sefick l-Trend: None SEP58 49 l i i
C""""I Tempor:ry Mafifications >1 cycle sid (RF3 r3quir2d f tr ramovt!) m Tampor:ry Cedifications >$ m3nths eli(Removibl] an-lins)
--+-- Fart Ctlhzun Ostis fJr >1-cycl 3 (nd >6 months aid 3-- .
~ 2.5 -- 2-- * * ' ' 1.5 -- 1 ' ' i
- 1 9_
0.6 o - .'- +
- *=
.'-w --* _
. _. a.- . 4- +.
June Jul Aug sep O ct Nov Dec Jan Feb Mar Apr May l TEMPORARY MODIFICATIONS l This indicator provides information on the number of temporary modifications (TMs) greater than one ' fuel cycle old requiring a refueling outage (RFO) for removal and the number of temporary modifications removable on-line that are greater than six months old. The 1997 Fort Calhoun monthly goals for this indicator are zero. J 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. Repairs for this temporary modification 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 developing a planning estimate for this modificaton. TM 96-018, equipment drain header soft rubber patch. MWO 963468 is ready to work for removal of this TM. MWO 963468 is expected to be completed during the 1998 RFO. TM 96-046 was still installed at the end of May 1997,but was removed on June 2,1997. At the end of May 1997, there were three (3) TMs installed That were greater than six months old that could be removed on-line. TM 96-022 containment low flow purge, was installed on June 14, i 1996. ECN 96-450 was initiated to allow this TM to be a permanent installation. ECN 96-450 is . expected to be completed and TM 96-022 removed by July 15, 1997. TM 96-039, Railroad Siding / Corridor 26 door. Was installed November 1.1996. System Engineering is required to initiate closing ducumentation for this TM. TM 96-039 is expected to be removed by September 1,1997. TM 96-046, SI-7B charging valve was installed November 26,1996. At the end of May 1997, there was a total of 11 TMs in the Fort Calhoun Station. Six (6) of the 11 installed TMs require an outage for removal and 5 are removable on-line. In 1997, a total of 9 temporary modifications have been installed. At the end of May 1997, there were two (2) procedural or maintenance configuration alterations (temporary modifications) installed using PRC approved procedures. Thesc' procedural or maintenance configuration alterations are controlled by - Standing Order O-25 Data Source: Phelps/ Frank (Manager / Source) - Accountability: Phelps/ Core Trend: Increased Management Attention SEP 62 & 71 50
.... __ _ _ . _ _ m_ _ _ . . . . . _ .___m . . _ .
' i Total Modesason Packag:s Open Fort Calhoun Year-End Goal (68) .
, 30 -- n u ."-
~
1s -- u 70 -- - e = . *- e. . . e * * * . ss ' ' - 96 Jan Feb Mar Apr May Jun Jul Aug Sep oct Nov Dec OUTSTANDING MODIFICATIONS l l This indicator shows the total number of outstanding modifications (excludina outstandino modifications which are orocosed to be cancelled). l Cateaorv 'jL4 M M '2Z E _H Month Form FC-1133 Backlog /In Progress 0 0 0 1 0 0 1 Mod. Requests Being Reviewed 0 0 0 2 4 5 11 Design Engr. Backlog /in Progress 0 0 -0 0 18 0 18 Construction Backlog /in Progress 4 2 11 3 1 0 21 3 l Design Engr. Update Backlog /In Progress .J 11 .12 J ._Q __Q. _ 29. I
- Totals 7 13 23 6 23 5 77 l (outage + online) (0+2) (5+8) (14+9) (2+4) (21+2) (3+2) l l At the end of May 1997, 22 modification requests have been issued this year and 2 l modification requests have been cancelled. The Nuclear Projects Review Committee .
(NPRC) has conducted 50 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) has completed 0 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
- S1 i
6
=
40 -- EARS Requiring Engin:cring Closscut . Net in Cl:sacut 30 30 -- 24 - g SE D DEN 26 26 4
~ .
20 -- 13 15 1 1 y ' 8 7 - 8 10 - 4 5 4 5 - g - I ;u . 'n 1 5,; .m ,1 ; $1 . Mar Apr May Mar Apr May Mar Apr May Mar Apr May 1 0 3 Months 3-6 Months 6-12 Months >12 Months O Engineering Response 5 Closeout (sE) 20 - 12
, 10 10 - 2 3 6 6 0
o 1 g g1 , , j j2 , , ,1 , 0 0 , Priority 0 Priority 1 Priority 2 Priority 3 Priority 4 Priority 5 Priority 6 39 Omdue Cosecut Reponses l 12% y5%
Response
88 % 14 Omdue Qasecuts 11.7 % 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 thit indicator is a maximum of 140 outstanding EARS. The Total EAR breakdown is as follows: . l EARS opened during the month 9 EARS closed during the month 13 Total EARS open at the end of the month 120 Data Source: Jaworski/Livingston (Manager / Source) Accountability: Phelps/Jaworski Trend: None SEP62 52
. _ _ _ - . . ~ ..- . ~ . . _ - . _ . . ~ - _ . _ - - . ~ . ~ . . . ~ . - . - _ . . - _ ~ - . . . _ - - . . - . - . - - . . _ . . - . . _ - . . _ . . _ _ _ _ _ . . _ _ _ _
j 3, 11 0 39 i ) CLolEOUT DEN o.3 M. 4.
, ,2wt 2,s , g'
- 49% l i ~
! E Backlogged O Received B Completed 2L0 -
" .d"- ~L:
i 200 - - l 150 - ,. ,, us us m 8 0 4 0 - .. . . . .s. . e. . . Dec Jan Apr " b*** " ' "' ! Feb Mar May 256 - 36
& ntbs
- 200 -
5
~
03 i & nths
M
) 100 - = = = ,. = gg4 ) Dec Jan Feb Mar Apr May 3 75% j 300 - 8 " t ses o.: u ..en. g et III III 4% 3 4 M.nths
.... .i 0
Nc# Dec Jan Feb Mar Apr l 250 200-. . i 150 - .a in s 100- si n f 0 he. ........ Dec Jan Feb Mar Apr May l
~
- ENGINEERING CHANGE NOTICE STATUS Data Source
- Jaworski/Livingston (Manager / Source)
- Accountability
- Jaworski/Phelps Trend: None SEP 62 53 4
a w _ _ _ _ _ _ . _
. _ . _ _ ._--_--__--_-.______.m_ _ _ _ _ - _ _ - _ - _ _ _ _ _ _
80 124 90 P rl*rley 9s ! DC 7YPE . FC TYPE is* y <e 7% ,s,a
, s r rierig sa:
i . < > . 2ss - o c.g . . . . j s tif vrE -rm.@. . _- ss* Total Open ECNs = , 27(
, l 457 sse Total Open ECNs = 457 i I
s9% O D E N . Closeset er Draf ting Not C omplete ! 5 M aintes sateK ens trection# rec urement. Werk N ot C emplete i 5 : ystem E ngineering . R es ponse. C onfinuation Not C omplete ! 5 DE N . E agiseering Net C emplete ""*$'g*** l 150 -- is, "' "* ens 4 , al 2, s 838
- 5 8 t,
t.
. 32. B8 . . .o. . ..;r . . .
D ec.96 jan.97 F e b.97 M ar.97 Apr 97 M a y.97 ! 4 Facility Change ECNs Open l
'"- ni .., rasay
,,. , ,ie s.,
==- ,, "
n ,,, ,,, ... L"
'g 250 - 4, i, 64 200 -
W- e4 s2 83 ' 0
>: i i
n i t i
- i k
P riori'Y 3"" Dec46 Jan47 Feb47 Mar 47 Apr47 May47 g7g substitute Replacement item ECNs Open goI a " , '. , 70 ,, ,,
*' ,,,.,.., l e r,.;; .,
( 10 - g is as so O i i i i i i p rier6ey Dec Jan Feb Mar Apr May ,ss** Document Change ECNs Open ENGINEERING CHANGE NOTICES OPEN Data Source:
~
Jaworski/Livingston (Manager Source) i Accountability: Phelps/Jaworski l Trend: None SEP 62 l 54
0 Administrativ3 Control Problem O Ucensed Cperator Error E OtherPersonnelError ,
,, 5 Maintenance Problem D Design /constructionlinstallation/ Fabrication Problem E Mbc 3 .- -
2 - 1 . . . . 0 Jun Jul Aug Sep Oct ll. Nov Dec Jan Feb Mar Apr May LICENSEE EVENT REPORT (LER) ROOT CAUSE BREAKDOWN This indicator shows the LERs by event date broken down by Root Cause Code for each f of the past twelve months from June 1,1996, through May 31,1997. To be consistent l 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 two events in May 1997 that resulted in a LER. Data Source: Tills /Cavanaugh (Manager / Source) ' Accountability: Chase Trend: None l 1 55 1 I l
1 i - O TotalRequaufication Training Hours , a Simulator Training hours a Non-Requaufication Training Hours j O Number of Eram Failures 35 34 5-, 34 y n 1 30 -- i l 25 --
- 22
! 20 - l 16 5.5 2 jg . 14 4 4 1 2 2 2 10 -- g 8 8 8
.5 7 7 1
6 6 5 g.- 4 2~ 2 2 0--- 1 -+ '
+ 1 4 cycie cycle cycie cnie cycie eyes. cycie cycie cyca
- 95 5 95-6 96 1 96-2 96-3 96 5 96 7 97 1 97 2 l l
'. LICENSED OPERATOR REQUALIFICATION TRAINING i This indicator provides information on the total number of hours of training given to 4 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 j AOP!EOP verification & validation, INPO commitments, GET, Fire Brigade, Safety i 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.
~
l - i Data Source: Conner /Guliani(Manager / Source) j Accountability: Conner /Guliani
- Trend: None SEPG8 56 i
i
_ - - . . . . . . .- . - -- . . . . . - _ _ . - _ - . _ . ~ . . . _ . - - . _ _ . _ . _ _ . 3 SRO Exams AdmlAlstired O S30 Exams Passed O RO Exams Administs red a RO Exams Passed 10 -- l i L-77 77 77 77 l 5-- l 000.0 00 00 00 00 , Jan Feb Mar Apr M ay Jun Jul Aug Sep O ct Nov Dec LICENSE CANDIDATE EXAMS - 1997 This indicator shows the number of Senior Reactor Operator (SRO) and Reactor Operator , (RO) quizzes and exams taken and passed each month. These internally administered i quizzes and exams are used to plot the SRO and RO candidates' monthly progress. l l During the month of May 1997, there were 7 individuals who passed SRO l comprehensive written exams. Data Source: Conner /Guliani(Manager / Source) l Accountability: Conner /Guliani Trend: None SEP68 l 1 i l 1 57 I i
m Ready to dose Q Qosed .
- ; Total CRs
-+ - Open '
1 2500 -
< e[ I 2000 - #
a 1500 - 1 1000 - 0 7 soo . 0 . . . t b t
? .
t b E k E A E gE$ u, E h E b 2 k a h m h m
$ .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 23 13 109 842 24 67 1088 ,
-Closed 11 4 93 985 423 144 1660 168 Condition Reports are classified as READY to CLOSE.
At the end of February 1997, all "OPEN" incident Reports are closed. Data Source: Tesar/Burggraf (Manager / Source) Accountability: Andrews/Gambhir Trend : None 58
O Total O utage MWDs
~
W MWDs Ready to Work s00 -- ME l 500 -- , Spruerirg l 4% Parts 4% 4oo - , B"N;13 l 1 300 -- ) 200 -- I 1 1ss 2ss 1ss . In RNeW 100 -- tss m% o ; i i F e b.97 Mar 97 Ap r.97 May 97 i l l l 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 l 18 Refueling Outage. This graph indicates: ! - Parts Holds - Planning Complete, Awaiting Parts i i - System Engineering Holds - Awaiting System Engineering input to Planning i ~ Planner Holds - Maintenance Planner has not completed planning the work package. ECN Hold - Awaiting Substitute Replacement items ECN from DEN. Data Source: Chase / Johnson (Manager / Source) Accountability: Chase / Herman Trend: None SEP 31 59
O Lc:t Month O This Menth O For Sch:dule 120 -- 110 -- i 100 -- go .. 80 -- . 70 - g so -- y so -- g..
- R 30 -- ,
20 . s ea ae e a s aes s . o ,
.i , , , ,
b 4 5
$j.
i 1 g m n. (# i y w s
- e = 8
- s. .
$ h & E S.e SPECIAL SERVICES ENGINEERING DEPARTMENT 1998 OUTAGE PROJECTS STATUS REPORT 1-June-97 Data Source: Phelps/Sweamgin (Manager / Source)
Accountability: Phelps/Boughter Trend: None SEP 31 60
l l l l
, e ActualPRCDate
. Target PRC Date
~ '~ - - - - - - - - -
l . . . . . . . . . 7/35S7 - 6/30S7 -
~
l S/3157-5/1/97 - N1/97 - 3/2S7 - 1/31/97 - 1/1/97 lillillilillilill!! PROGRESS OF 1998 REFUELING OUTAGE MODIFICATIONS CYCLE 18 This indicator shows the status of Modifications approved for installation during the Cycle 18 Refueling Outage (March 1998). The goal for this. indicator is to have all modification packages which were identified prior to March 20,1997, PRC approved by September 15,1997. Modifications added: 0 Deleted = 0 May 1997 Data Source: Jaworski/ Walling (Manager / Source) Accountability: Gambhir/Jaworski Trend: None SEP31 l l 61
)
i l
s e a a s a a a a e 8f2lMr7 m a e a e a e a a
?m-em. :
5r31M - - 91 5 - N1m - ar2e - 1/31M - 1/1 M s 6 a a a m I PROGRESS OF CYCLE 18 OUTAGE MODS ADDED TO '98 REFUELING OUTAGE AFTER FREEZE DATE This indicator will show the status of modifications approved for installation during the Cycle 18 Refueling Outage. Since the baseline schedule has yet to be established, there is no information available at this time. The goal for this indicator is to have all modification packages PRC approved by their target date. May 1997 Mooifications Added: = 1 Deleted = 0 Data Source: Jaworski/ Walling (Manager / Source) - Accountability: Gambhir/Jaworski Trend: None SEP31 , l 1 62
, . No Data Available - 1 4 PROGRESS OF 1997 ON-LINE MODIFICATION PLANNING This indicator shows the status d modifications approved or in review for approval for on-line installation during 1997. Modifications added to the on-line list after March 20,1997 freeze date are FC 97-D16 (tomado venting) and FC 97-003 (supplemental co,oling for FW-3). No PRC target approval date available, requires planning estimate. The goal for this indicator is to have all modification packages PRC approved by their scheduled date. l May 1997 Modifications Added: 2 Deleted = 0 Data Source: Jaworski/ Walling (Manager / Source)
. Accountability: Gambhir/Jaworski Trend: None SEP33 63
m.-aa w.-. . - e.-.a.4-# --.-m --ew--wa a --M,w dx me.-.mse..mame NMEma- -.wheWB.Emd4M-mheA-m..Mab--- '
-4M-JL 4 4Ef-44A.W4=.#AM-Detet-.sa..h.-.-wahp.44 M M_MAM-A 44.ah w_sh _MhJJ 4
h 4 i i f
- i i
I l s - I ACT ON PLANS I l 1 4 4 l l I r i 4 l I~ i t 1 4 4 4 i l 64 1 4 i i e i e d 1 - d
i i l. i -ACTION PLANS ! This section lists action plans that have been developed for the performance indicators ; j 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 ;
j Increased Management Attention for three (3) consecutive months. ) ' I in accordance with Revision 3 of NOD-QP-37, the following performance indicators would l
- require action plans based on three (3) consecutive months of performance cited as
; "Needing increased Management Attention":
5
. Maintenance Workload Backlogs (page 39) ,
l l j 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 j Station. This will significantly improve our " WRENCH TIME" by removing i inefficiencies and related hurdles that prevent work from being accomplished in a l timely manner. In addition, it is expected that schedule compliance will also j increase and our maintenance backlog will decrease. This project is scheduled tc j be fully implemented by July 1997. j i !
^ i I l I ! I i i* i 1 i b i
- - - - . - ~ . . - . _ . , _ - - . ~.- ~ - . . - . - - -.- - . - . - - - . - - . . - . . - . - - .
4
. PERFORMANCE INDICATOR DEFINITIONS
- i AUXLIARY FEEDWATER SYSTEM SAFETY SYSTEM CLEAN CONTROLLED AREA CONTAMMATIONS 3.1,000
- P5FORMANCE OtSINTEORATIONS/ MINUTE PER PROBE AREA The sum of the known (pienned and unplanned) unavailable The personnel contenunebon events in the clean contnWed aros.
hours.and the estimated unevailable hours for the aunihery This indcator tracks personnel performance for SEP #15 & 54. feedseter system for the reporbng period dMded by the critical , hours for the reporting period mulhpiled by the number of trains CONTAMINATED RADIATION CONTROLLED AREA I' in tas etedhary feedwater system.- The percentage of the Radiation ControBed Area, which includes i COLLECTIVE MADIATION EXPOSURE the audhary buildmp, the radweste building, and areas of the 1 C/RP buildeg, that is contommated bened on the total square CoInche redimon aposure is the total entemel whole body dose footage. Tfus indcator tracks performance for SEP #54. recewed by all on-site personnel (includrg contractors and viellors) dunng a tone period, as measured by the DAILY THERMAL OUTPUT thermoluminescent dosimeter (TLD). Cotectise radiaten suposure is reported in units of person-rom. This indicator tracks This indcator shows the daily core thermal output as measured radiologmal work performance for SEP #64. from computer point XC105 (in thermal megewetts). The t500 MW Tech Spec Imit, and the unmet portion of the 1495 MW FCS ! COMPOlENT FAILURE ANALYSIS REPORT (CFAR) daily goal for the reportmg month are also shown.
SUMMARY
The summary of INPO categones for Fort Calhoun Station with sigrdoently higher (1.645 standard deviabons) failure rates than This indcator shows the number of failures occurring for each the rest of the industry for an seghteen-month time period. emergency stenal generator durtng the last 25 start demands and , Failures are reported as remponent (i.e., pumps, motors, main the last 25 lood-run demands , steem stop valves, control element motors, etc.) categones DISABLING INJURYALLNESS FREQUENCY RATE Failure cause Categones are: (LOSS TIME ACCIDENT RATE) Age 4tormal Use -thought to be the consequence of expected This indicator is dermed as the number of accidents for all utility weer, agmg, end-os-life, or normal use , persormel permanently assagned to the station, invoMng days avey from work per 200,000 marWmurs worked (100 man-years). Manufacturing Defect a failure attributable to inadequate The does not include contractor personnel. Thes indicator tracks assembly or initial quelRy of the responsible wi@.We or personnel performance for SEP #25,26 & 27. system. DOCUMENT REVIEW (BIENNIAL) Engineenng/ Design a failure attributable to the inadequate design of the responsible -v.wa or system. The Documord Review Indicator shows the number of documents reviewed, the number of documents scheduled for review, and the , Other Devices - a failure attnbutable to a failure or number of document reviews that are overdue for the repurbng mesoperaten of another w,,i~,&J or system, includmg monh A documerd review is coneadored overdue if the review is associated devees not complete within six months of the assagned due date. This indicator tracks performance for SEP 846. Maintenance / Action - resulhng from improper maintenance, , lack of memtenance, or personnel errors that occur dunng EMERGENCY AC POWER SYSTEM SAFETY SYSTEM mentenance actmheson the component.. PERFORMANCE - Testing Action - resulhng from improper testing or personnel The sum of the known (pionned and unplanned) unavaliable and errors that occur during testmg actMtses the echmeted unavailable hours for the emergency AC power system for the reportog period dMded by the number of hours in initial Ir*Mdmi Error - caused by improper inibal the reportng period multiplied by the number of trains in the installation of equipment emergency AC power system. CENTS PER KILOWATT HOUR The purpose of this indcator is to quantify the Mu . opershon of Fort Calhoun Stahon. The cents per idlowett hour indmetor represents the budget and actual cents per kilowett hour on a twelve-rnonth average for the current year. The been forthe budget curve is the approved yearty budget The basis for the actual curve is the Financial and Operstmg Report. I 66 i i
__ __ . _ _ _ _ _ _ - . . _ ._ _. - ___ _ _ _ _ _ _ _ _ _ _ _ _ _ ._ _ . _ _m ..._m. . . _ _ i '. PERFORMANCE INDICATOR DEFINITIONS - j
- EMERGENCY DIESEL GENERATOR USET RELIABILITY E) A failure to olert because a portion of the startmg .
system was desabled for test purpose, if fotowed by a I i This imlicolor shows 9m nunther of latures that were reported during successful etert wth the etertmg system in its normal
- the lost 20,50, and 100 energonoy esset genmotor dernands et g* angnment' i
- Fort Ceewun 8tehon. Also shown are trigger welues weiich correiste to 1 e high level of conndence that a units diesel generators have atitested j a rehabday of greater then or aquel to 96% when #w dernand leaures Each emergency generator failure that resuRs in the generator ere sees then sw tnggw weiums. boog deciered moperable should be counted as one demand and
- one Inewo. Exploratory tests during correceve maintenance and i j 1) Number of Start Demands: AR valid and hhdvertent start Die successful test that fogows repair to vertfy operabuity should t demands, inclueno as start-only demands and as alert not be counted as demands or femuros when the EDG has not I
! demands that see fotowed by load 4un demands, whether by been declared operable again. l automanc or menuel initiation A start-only demand is e j
- i. demand h which tia emergency generator is eterted, but no EMERGENCY DIESEL GE9ERATOR UNREUABILITY l
i t attemptis madetoloadthe generalor This irusemaer mensues the total unrohntduty of emergency diseel -!
- 2) Number of Start Failures' Any fedure within the genenators in general, unrebatehty is the ratio of unsuccessful emergency generator system that prevents the generator opershons (elests or lood runs) to the number of valid demands l
- born achievkig specified frequency and voltage is classified Toted unretsbety is a combinelion of start unreliebdity and toed- !
as a wed start fouure. This includes any conshon identified run unreinbety in the course of maintenance triapaehans (with the
- emergency generator in standby mode) that definitely would ENGifEERING ASSISTANCE REQUEST (EAR)
I have resulted in a start fauure if a demand had occurred BREAKDOWN i . l This indicolor shows a breakdown, by age and priority of the
- 3) Number of LoadJtun Demands: For a valid lood-run demand to be counted, the load run attempt must meet one EAR, of the number of EARS assigned to Design Engineenng or more of the fonowing crttena: Nuclear and System Engmeenng This indicator tracks performance for SEP #62.
- A) A lood-run of any durobon that resuRs from a real j automebc or manuel trubshon. ENGifEERING CHANGE NOTICE (ECN) STATUS 4
j B) A lood-run test to satisfy the plants load and duration The number of ECNs that were opened, ECNs that were as ste*ed in each test's specifications carrydeled, and open hacidog ECNs swelbng completion by DEN for the reportmg month. This indicator tracks performance for C) Other special tests in which the emergency generator SEP #62. l
- is expected to be operated for at least one hour whee i loaded with at least 50% of its design loed. ENG1 PEERING CHANGE NOTICES OPEN e
This indicator breaks down the number of Engineenng Change 3 4) Nienber of Load 4 tun Failures: A lood-run fedure should be counted for any reason in which the emergency Notices (ECNs)Itut are asegned to Desen Engmeenng Nuclear i , generator does not pick up load and run as predicted.. (DEN), System Engmeenng, and Maintenance The graphs j j Faaures are counted during any vand lood-run demands provide dets on ECN Facinty Changes open, ECN Substitute i Replacement items open, and ECN Document Changes open.
- 5) Excephons: Unsuccessful attempts to start or lood-run This indicator tracks performance for SEP #62, l
t should not be counted as valid demands or faGures when they can be attributed to any of the fotowng EQUFMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS A) Spurious tript that would be bypassed in the event of l Equipment forced outages per 1,000 critical hours is the inverse 8 an emergency. j of the mean time between forced outages caused by equipment B) Malfunc%n of equipmerd that is not requesd during an failures. . The mean time is equel to the number of hours the
- emerge ncy. randor is estical in a period (1,000 hours) duded by the number of forced outages caused by equipmerd failures in that period.
! C) Intentest termanabon of a test because of abnormel ! condblons that would not have resuked in mapor dweel EQUlVALENT Avan ans TY FACTOR generator damage or repair. f, This hermaar la denned as the robo of gross even able genersbon D) Malfundians or operahng errors which would not have to gross meelmum genershon, expressed as a percentage ! prevented the emergency generator frorn being Avatatile genershon is the energy that can be produced if the unit restarted and brought to lood witNn a few rrunutes is operated at the maximum power level permitted by equipment { and relNatoryimanhons_ Mesmum genernhon is the energy that j can be produced by a unit in a given period if operated i continuously at maidmum capacity 1 l i i
! 67 4
l
- ~ . . . . . . - - - . - . _ _ - _ _ . ~ _ - ~ . . - . - ~ ~ . - . - _ - . - . _ . - - . , - - - - . - _ - -
- PERFORMANCE INDICATOR DEFINITIONS -
- 2) One or more days away from work (aciudng the day of the -
FORCED OUTAGE RATE accident); and
- 3) Fatelties This , indicator is defined as the percentage of time that the unit .
was unavailable due to forced events compared to the time Contractor personnel are not included for this indcator planned for electrical genershon. Forced events are failures or other unplanned condlhons that require removing the unit from W4.NE CIEMISTRY DISTRUMENTS OUT OF SERVICE l
- servloe before the end of the nom weekend Forced events include start-up failures and events inlheted while the unit is in Total number of irWine chemistry instruments that are out-of-reserve shutdown (Le.,the unit is avallable but not in service). service h the Secondary System and the Post Accident Samphng
~
System (PASS).
- FLEL REL1ASE.lTY pmICATOR LICENSE CAtmlDATE EXAMS Ties becator is denned as the steady-etate primary cooient M31 schwity, corrected for the tramp uraruum contribubon and Thls indcator shows the number of SRO and/or RO quizzes and normatead to a common punncation rate. Tramp uranium is fuel exams that are admrustered and poseed each month. This which has been deposted on reactor core Irdemets from previous indestor tracks traming performance for SEP #68.
defective fuel or is present on the surface of fuel elements from the manufactunng process Steady state is defined as LICENSED 0PERATOR REQUALIFICATION TRAINING j continuous opershon for at least three days et a power level that I does not very more then + or-5%. Plants should collect data for The total number of hours of trae ? given to each crew during tis indcator at a power level above 86%, when possible. Plants each cycle. Aino pnMded are the sk unter trarung hours (which that did not operate at steady-state power above 85% should are a subset of the total traeung hours), the number of non-conect data for this indestor at the highest steady-etste power REQUALIFICATION traming hours and the number of exam level attamed dunng the month. failures. This indcator tracks traeung performance for SEP # 68. The density correchon factor is the ratio of the specife volume of coolant at the RCS operahng temperature (540 degrees F., Vf = LICENSEE EVENT REPORT (LER) ROOT CAUSE 0.02146) devided by the specific volume of cooient at normed BREAKDOWN istdtzm terrquereture (120* F at outlet of the letdown cochng heet enchanger. Vf = 0.016204), which results in a density correchon This mdcator shows the number and root cause code for factor for FCS equelto 1.32. LJcensee Event Reports. The root cause codes are as fotows: GROSS HEAT P" iE 1) Administrative Control Problem - Management and supervisory descencies that affect piant programs or Gross heet rate is defined as the ratio of total thermal energy in adMbos (i.e., poor planrung, breakdown or lack of adequate British Thermal Units (BTU) produced by the reactor to the total management or supervoory control, incorrect procedures, gross electrical energy produced by the generator in Idtowatt- etc). hours (KWH). *
- 2) Licensed Operator Error - This cause code captures HAZARDOUS WASTE PRODUCED errses of ommemnloommesen by licensed reactor operators during plant actMbss The total amount (in Kilograms) of non-halogenated hazardous ;
weste, halogensted hazentous weste, and other hazardous waste 3) Other Personnel Error Errors of ommsen/ commission produced by FCS each month. commit *ed by non-hoensed personnel irwolved in plant actMhos HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE 4) Mantonence Proidem.The intent of this cause code is to capture the fun range of protdems which can be attnbuted The sum of the known (pionned and unplanned) unavailable in any way to programmehc deficsoncess in the mantenance hours and the setsmaled uneveMoble hours for the high pressure funcbonel orgemzshon ActMbes included in this category safety injechon system for the reporting ported divided by the are maintenance, testmg, survedlance, celibrahon and crScal hours for the reporting period mulbphed by the number of redebon protechort trams in the high pressure safety injechon system.
- 5) r . 2 ^- ^ J ^ ~ - -"abr6 cation Probiern -
IleUSTRIAL SAFETY ACCIDENT RATE lNPO This cause code covers a fun range of programmate . deReencess in me areas of design, construction, instatehon, This indcator is defined as the number of accidents por 200,000 and febncubon (Le., loss of control power due to underroted merkhours worked for as utelty personnel permanently assigned fuse, equipment not queirned for the erMronment, etc.). to the station that result in any of the fonowing
- 1) One or more days of restricted work (excludog the day of the accsdent);
68
~.. - - - - _ . . _ . - - - . - - - . . - - _ _ _ . - . . - . . - - - - . . . - - - . - ~ . - -
i
- . PERFORMANCE INDICATOR DEFINITIONS - -
- 6) Equipment FaMures (Electronic Piem or The talel madmum amount of radubon recorved by an indMdual .
4 Environmental Related Failures) . This code is used for person worldng at FCS on a monthly, quarterly, and annual basis. apunous failures of electronc poco-parts and fauures due .. ! to ,
- _. M condlhons such as hghtnmg, ice, high MWO PLANNING STATUS (CYCLE 17 REFUELING ,
' winds, etc. Generouy, it includes spunous or one time OUTAGE)
! sedures. Electric components mciudad in this category are
- - catuit cards, reclifiers, testables, fuses, cepecitors, diodes, The total number of Memtenance Work Orders that have been appnwed for inclusion in the Cycle 17 Refueling Oubge and the reestors, etc.
number that are ready to work tparts staged, pionning compiste, 4 LOGGABLEstEPORTABLE BfCSENTS (SECURITV) and as amor papenvork ready for field use). Also included is the { number of MWOs that have been engineenne holds (ECNs, t The total number of securty incedents for the reportmg month procedures and other mecebeneous engineering holds), parts 1 depeted in two graphs. TNs indmetor tracks securtly hold, (parts eleged, not yet inspected, parts not yet arrived) and [ performance for SEP #58. planning hold Gob scope not yet compieled) Maintenance Work Requests (MW!ts) are also shown that have been identined for j
- me Cycle 17 Refusiing Outage and have not yet been converted MAINTENANCE OVERTIME ,
to MWOs. < The percent of overtime hours compared to normal hours for mortenance. This incdudes OPPD personnel as wed as contract NUIMER OF CON 7ROL ROOM EQUIPMENT DEFICIENCIES personnel
- A control room equepment derciency (CRD) is defined as any j MAINTENANCE WORKLOAD BACKLOGS component which is operated or contround from the Control i Room, pnwides hdicahon or alarm to the Contml Room, provides This indicator shows the bacidog of non-outage Maintenance testing e=pam== from the Control Room, provides automete '
i Work Orders romerung open at the end of the reporbng month. actions from or to the Control Room, or provides a peserve i Montenance ciesmificahons are defined as follows: function for the Control Room and has been idenufied as l deAcsert,i.e., does not perform under au condihons as desagned. Corrective - Repair and restorsbon of equipment or This dear 9an also apphes to the ARomete Shutdown Panets Al- ! components that have failed or are motfunchonmg and are not 179, Al-185, and Al-212. 3 performmg their intended funchon. A plant component which is deficient or inoperable is consadored i l Preventive Actions taken to maintain a piece of equipment an " Operator Work Around (OWA) ltem" If some other acten is { wthin design operahng condihons, prevent equipment fadure, required by an operator to compensate for the condehon of the , 1 and seend as Ils and are performed pnor to equipment failure. component Some examoies of OWAs are: , Non CorrectivelPlant -Improvements - Maintenance 1) The cortsel room level indmetor does not work but a local
- actrvibes performed to implement station improvements or to sight glass can be read by an Operator out in the plant;
- repair norydent equipment ,
} 2) A danciert pump cannot be repeered because replacement " i Maintenance Work Priertties are donned as: parts requre e long lead time for puiC Trf, thus requring the redundant pump to be operated conhnuously, 4 Emergency - Condlhons which signincently degrade station p safety or availotnlity 3) Special schons are requred by en Operator because of , equipment design problems These actions may be l Immediate Action - Equipment deficences which descrtied in Opersions Memorandums, Operator Notes, or 9 sagrancantly degrade station rehabihty Potential for unit may require changes to Opershng Procedures, l shutdown or power reducten. , ' 4) Danciert plant equipment that is requred to be used during 1 Operations Concern - Equipment donconcess which hinder Emergency Operahng Procedures or Abnormal Operating ) j station opershon. Procedures; i ) Essential - Rouhne corrective mantenance on essenhal 5) System indcahon that provides entcal informehon during !" stelion systems and equipment. normal or abnormalopershons J Non4seential - Routine corrective maintenance on non-f. essenhol staban systems and equipment. NUMBER OF MISSED SURVEILLANCE TESTS RESULTING Plant knprovement - Non-correceve rnemtenance and plant l impnwoments IN LICENSEE EVENT REPORTS I 1 i TNs mdicator tracks maintenance performance for SEP #36. The number of Surveinance Tests (STs) that result in Licensee i Evert Reports (LERs) during the reporting month. This indicator MAXIMUM INDIVIDUAL RADIATION EXPOSURE tracks messed STs for SEP #60 & 61. { 4 i; 69 i
- PERFORMANCE INDICATOR DERNITIONS OPEN gdCEIENT REPORTS deksenses decovered during a faaed Post Memtenance Test to-ensure the component / system passes subsequent Post Tres hdoster depisys the total number of open incident Reports Memtenance Test. (irs),9m rsonhor of irs that are greater then six months old and the number of open sqpilficent irs. ' PERCENT OF COMPLETED SCDEDULED MAINTENANCE ACTIVITIES OUTSTABEIDIG MODFICATIONS
- The percent of the number of completed mentenance actMbes The number of % Requests (MRs) in any etste between as compared to the number of scheduled memtenance actMties tie leeuence of a hema =8-1 Number and the complebon of the each month. This percentage is shown for el maintenance drawing upsete. crons. Aino shown are the number of emergent MWOs.
Memtenance notweles include MWRs, MWOs, STs, PMOs,
- 1) Porin PC 1133 Bacidegen Progress. This number cautwahons, and other minoegeneous notMbes This indicator represents modscehon requests that have not been plant tracks Maintenance performance for SEP #33.
appnwed during the reportmo month. PERPORMANCEINDICATORINDEX
- 2) ==d=t Requests Being Reviewed. This cologory includes This imicekir hdem is a=iam from a weighted combinebon of sloven performmes indicator values, which include the fotowing A) . Modificehon Requests that are not yet reviewed Unt CapabiNty Factor, Unit Capotely Loos Factor, HPSI, AFW, Emergency AC Power System Unplanned Automebc Scrams,
- 8) Madncebon Requests being reviewed by the Nuclear Codeotive Redishon Esposure, Fuel Rehability, Thermal Projects Review Commutes (NPRC). Portsmance, Secondary Syelem Chemmtry, and Induetnel Safety Accident Rate.
C) Modficebon Requests being reviewed by the Nucieer Projects Commmee (NPC). PftEVENTABLEJPERSONIEL ERROR LERs These Modlncehon Raquests may be reviewed several times This indicator is a breakdown of LERs. For purposes of LER beforethey are approtedfor accomplishment or conceled Some event cisoodeshon, a
- Preventable LER' is deAnod as:
of these Modecation Requests are retumed to Engmeenne for more informehen, some approved for evaluehon, some approved An event for which the root cause is personnel error (i.e., for study, and sorre approved for pionnmg Once pionn:ng is inappropnete action by one or more indmduais), inodoquete completed and the scope of the work is cieerty defined, these adminstrative controis, e desegn construchon, installabon, MocIHoobon Requests may be approved for accompinhment with instenshon, febncehon problem (mvoMng work u-;'_M by a year essgned for construchon or they may be conceled ARof or supenseed by OPPD personnel) or a maintenance problem these different phases requre review. (ettnbuted to inartargumes or improper = , _; ,,,e of plant equipment). Also,the cause of the event must have occurred
- 3) Design Engineering Bacidogan Progress Nucieer umiin appnaevutely two years of the " Event Dete" specified in Planrung has seeigned a year in which construebon wlR be the LER (e.g., an event for which the cause is attributed to a ,
completed and design work mey be in progress problem with the enginal design of the plant would not be considered p. " ).
- 4) Construction Bacidog4n Progress. The Construchon Package has been lesund or construchon has begun but the For purposes of LER event cleosincebon, a " Personnel Error" modificebon has not been accepted by the System LERis defined as fotows:
Acceptance Comminee (SAC). An evert for which en root cause is inapprepnete ocean on the
- 5) Deelen Engineering Update Becidogan Progress. PED part of one or more induduals (as opposed to being attnbuted has recorved the ModtAcehon Compiehon Report but the to a department or a general Foup). Also, the inappropnote drawings have not boon updated action must have occurred within approiemetely two years of the
- Event Dele" specmed in the LER.
The ateve menhoned outetendng modecemons do not inciude modMcehons which are proposed for cancetshon.
- AdmoneNy, each event closeined as a " Personnel Error" should OVERALL PftOJECT STATUS (REFUELING 0UTAGE) also be closamed as "Proventabie' This indacator trends personnel performance for SEP llem #15.
Thas indicator shows the status of the propoets which are in the , ecope of tra Refueling Outage PftiMARY SYSTEM LIT 19UM % OF HOURS OUT OF LIMIT PERCENTAGE OF TOTAL MW0s COMPLETED PER MONTH The percert of hows out of limit are for Nthium duded by the total BENTFED AS ftEWORK number of hours possible for the month. The percordage of total MWOs completed per month identmed as PROCEDURAL NONCOMPLIANCE INCIDENTS rework Roverkamuses are identmed by maintenance piennmg (MAINTENANCE) and craft. Rework is: Any addihonal work requred to correct 70
. PERFORMANCE INDICATOR DEFINITIONS The number of identified incidents conceming maintenance Accident Monitonng Instrumentabon, Auxiliary (and procedi,ral problems, the number of closed irs related to the use Emergency) Feedwater System, Combustrbie Gas Control, of procedures (includes the number of closed irs caused by Component Cooling Water System, Containment and proceduralim Waae), and the number of closed procedural Cartarimert isoisten, Containment Coolant Systems, Control iu n,und irs. This recator trends pe sonnel poLn,..c. Room Emergency Ventilation System, Emergency Core for SEP #15,41 and 44. Cooling Systems, Engineered Safety Features Instrumentation, Essential Cong. 6d Air Systems, Essenbal or Emergency PROGRESS OF CYCLE 17 "DUTAGE MODIFICATION Service Water, Fire Detection or Suppression Systems, PLANNtNG isolation Condenser, Low Temperature Overpressure Protecten, Main Steam Line isolation Valves, Onsite This indcator shows the status of modifcations approved for Emergency AC & DC Power w/ Distribution, Radiation wng66u dunng the Refuehng Outage. Monitanng Instrumentaten, Reactor Coolant System, Reactor Core isolabon Coohng System, Reactor Tnp System and PROGRESS OF 1995 ON4.INE MODIFICATION PLANNING instnanentation, Recirculaton Pump Trip Actuaton instrumentation, Residual Heat Removal Systems, Safety This indcator shows the status of modifcatens approved for Valves, Spent Fuel Systems, Standby Uguid Control System completion dunng 1995. and Ultimate Heat Sink.
RADIOLOGICAL WORK PRACTICES PROGRAM SECONDARY SYSTEM CHEMISTRY PERFORMANCE INDEX The number of idenbfed poor radidogeal wark practces (PRWPs) for the repore,g month. This indicator tracks The Cherrustry PA n a index (CPI) is a calculaton based on radologeal work performance for SEP #52. the concentrabon of key impunbes in the secondary side of the plant. These key impuntses are the most likely cause of RATIO OF PREVENTIVE TO TOTAL MAINTENANCE & detenorahon of the steam generators. Cnteria for calculating the PREVENTIVE MAINTENANCE ITEMS OVERDUE CPI are: The rabo ci;vevenhve maintenance (including surveillance testing 1) The plant is at greater than 30 percent power; and and calibratie procedures) to the sum of ncMxJtage corrective maintenance arn prever.tive maintenance completed over the 2) the power is changing less than 5% per day. reporting penod. The ratio, expressed as a percentage, is cabulated based on man-hours. Also displayed are the percent The CPI is calculated using the following equation: of preventive maintenance items in the month that were not completed or administratively closed by the scheduled date plus CPI = ((sodsurrA79) + (Chionde/1.52) + (Sulfate!1.44) + a grace penod equal to 25% of the scheduled hterval. This (Iron /3.30) + (Copper /0.30)+(Condensate 02/2.90))/6 indcator tracks preventive maintenance activibes for SEP #41. Where: Sodium, sulfate, chloride and condensate dissolved RECORDABLE INJURY / ILLNESS CASES FREQUENCY oxfgen are the monthly average blowdown concentrations in ppb, RATE iron and copper are monthly time weighted average feedwater concentrations in ppb. The denominator for each of the five The number of injunes requinng rnore than normal first aid per factors is the INPO median value. If the monthly average for a 200,000 man-hours worked. This indcator trends personnel specife parameter es less than the (NPO median value, the performance for SEP #15,25 and 26. median value es used in the calculabon. REPEAT FAILURES SIGNIFICANT EVENTS The number of Nuclear Plant Reliability Data System (NPRDS) Sgnifcart events are the events idenbfied by NRC staff through components with more than one failure and the number of detailed screening and evaluaton of operating expenence. The screerung process includes the daily review and descussion of all reported operating reactor events, as well as other operational NPRDS cornponents with more than two failures for the e ghteen- data such as specal tests or construebon activibes An event month CFAR pene,1 idenbfied from the screening process as a signifcant event carddate is further evalua'ed to determine if any actual or SAFETY SYSTEM FAILURES potenbal threat t the health and safety of the public was involved Specific examples of the type of crttena are su;nmarred as
. Safety system failures are any events or condsbons that could follows:
prevent the fulfdiment of the safety funcbons of structures or systems. If a system consrsts of mulbple redundant subsystems 1) Degradation of important safety equipment; or trains, failure of all trains constitutes a safety system failure. Failure of one of two or rnore trains is not counted as a safety 2) Unexpected plant response to a transsent; system failure. The definston for the indcator parallels NRC reportrg re:prements in 10 CFR 50.72 and 10 CFR 50.73 The 3) Degradation of fuel integnty, pnmary cootant pressure Mowing is a irst of the major safety systems, sut> systems, and boundary, rnportant associated features; wng. 4s monitored for this indicator; 71 l l
. PERFORMANCE INDICATOR DEFINITIONS
- 4) Scramwnhcompbcohon, - The ratio of the avouetde energy genershon over a given tone period to the reference energy generemon (the energy that could
- 5) Unplanned reisees of radioactivlty; he produced if the unit were operated conhnuously at fuu power under reference amtment condibons) over the some time period,
- 6) Opershon outside the Imits of the Techrucal Spacencebons, empreseed as e percentage
- 7) Other. UMT CAPACITY FACTOR INPO signincent events reported in this indicator are SERs The not electrical energy generated (MWH) divided by the (Senincent Event Reports) which inform utlubes of signlAcant product of maidmum dependelde cepecity (not MWe) times the events and lessons lemmed klontiAed through the SEE-lN pues hours in the reperbng period empressed as a percent Not l ecreening process electrical energy generated is the gross electrical output of the I utdt measured at the output terminels of the turtine generator SPARE PARTS INVENTORY VALUE mmus the normal etshon service loads during the groes hours of
- i. the reportmg period, arpressed in megewett hours.
The dotar value of the spare parts inventory for FCS during the reporeng period. UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7,000 l CRITICAL HOURS l !- STAFFING LEVEL This indicator is denned as the number of unplanned automebe l i The actual elefRng level and the authorteed etsfRng level for the scrams (RPS logic actuohons) that occur per 7,000 hours of Nuciser Opershons Dusson, The Produchon Engmeanng critical opershon. DMemn, and the Nucimer Savices Dmeion. The indestor tracks performance for SEP #24. The value for this indes*or is a=8eal=8-8 by muligilying the total rmentier of urgdenned automanc reactor screms in a specmc time STATION NET GEfERATION penod by 7,000 hours, then duding that number by the total number of hours artical in the some time period. The indicator is The not genershon (sum) produced by the FCS during the further deAnod es fotows: reporting trutti
- 1) Unplanned means ther the scram was not an entespeted part TEMPORARY MODIFICATIONS - of a planned test.
The number of temporsry mechencel and electrical 2) Scram means the automshe shutdown of the reactor by a configurabons to the rient's systems rapid inserbon of negetrve reactivity (e.g., by control rods, liquid kyscean system, etc.) that is caused by actuabon of the
- 1) Temporary configurshons are denned as electnceljumpers, rescaer prutocean system. The signal may have resulted from elecincel blocks, mechancel jumpers, or macherucal blocks exceeding a set point or spurious which are hoteAnd h the plant operahng systems and are not shown on the latest revnion of the PalD, echemebc, 3) Adamshe means that the initial signalthat caused actuation
- connochon, wiring, or flow diagrams of tie reactor protechon system logic was prcmded from one of the sensor's monitonng plant parameters and condibons,
- 2) Jumpers and blocks which are insteued for Survolgence rather tien tie marumi scram switches or, menuel turbine trip Tests, Wntenance Procedures, Cahbrahon Procedures, onetches (or push tamons) provided in the main control room.
Special Procedures or Operebng Procedures are not - considered e , temporary modifcebons unless the jumper or 4) Critical means that during the steady-etste condibon of the block ramens in piece enor the test or procedure is complete reactor prior to the screm, the effective multipbcobon (k ,,) Jumpers and blocks instoned in test or lab instruments are was essenbeNy equel to one. not considered as temponey medlAcebens UNPLANNED CAPA31LITY LOSS FACTOR
- 3) Scaffold is not coneadored a temporary medlAcetion.
Jumpers and blocks which are instated and for which MRs The ratio of tie unplanned energy losses during a given period of have been submitted wul be considered as temporary tme, to tie reference energy genershon (the energy that could be moencetons una nnel resolubon of the MR and the jumper produced if the unit were operated conhnuously at fuu power or tdock is removed or is permanently recorded on the under reference ambient conditons) over the same time period, . drawings This indmeter tracks temporary modifcebens for expressed as a percentage SEP 962 and 71, , TIERMAL PERFORMANCE The rute of tw deogn groes heat role (corrected) to the adjusted actual gross heet rate, empreened as a percentage UNIT CAPAgtUTY FACTOR 72
- PERFORMANCE INDICATOR DEFINITIONS UNPLANNED SAFETY SYSTEM ACTUATIONS . (INPO
+ DEFINITION)
This.indcatoris denned as the sum of the following safety system actusbons
- 1) The number of unplanned EmerDency Core Coohng System (ECCS) actuahons that resut from reacNng an ECCS actuaten set point or trorn a spunous/ inadvertent ECCS signal.
- 2) The number of unplanned ernergency AC power system actuations that resuR from a loss of power is a safeguards bus. An unplanned safety system actush occurs when an actuaten set pont for a safety systen,is reached or when a spunous or inadwortent signalis generated (ECCS only), and major equipment in the system is actuated. Unplanned means that the system actuation was not part of a planrwd test or evolution. The ECCS actuates to be counted are actuations of the high pressure injection system, the low pressure injection system, or the safety irp:: bon tanks.
UNPLANNED SAFETY SYSTEM ACTUATIONS .(NRC . DEFINITION) The runber of safety system actuatens which include (2nk) the High Pressure Safety injection System, the Low Pressure safety injecton System, the Safety injechon Tanks, and the Emergency Diesel Generators The NRC classification of safety system Whnns rh actuabons when major equipment is operated and, when the logic sptems for the above safety systems are chalienged. VIOLATION TREND TNs Mc*r is de'ined as Fort Calhoun Stat >on Cited Violations and Non-Cited Violations trended over 12 months. Addrtionally, Cted Violatons for the top quartile Region IV plant is trended over 12 months (lagging the Fort Calhoun Staten trend by 2-3 morths). R is the Fort Calhoun Station goal to be at or below the cited vlotation trend for the top quartale Region IV plant. VOLUE OF LOW-LEVEL SOLID RADIOACTIVE WASTE - This indicator is defined as the volume of low-level solid radoactive waste actually shipptd for burial. This indicator also shows the volume of low-level radcactive waste which is in temsnrary storage, the emount of radcactrve oil that has been shipped off-site for processing, and the volume of solid dry twr=*e waste which has been shipped off-site for processing. Low-level solid radioactrve weste consrsts of dry actrve weste,
, sludges, rouns, and evaporator bottoms generated as a resun of nuclear power plant operaton and maintenance. Dry radioactrve vaste irrW cortamruted rags, cleaning materiais, drsposable protectre clothng, pisshe cortaners, and any other material to be - disposed of at a low 4evel radioactive waste dtsposal sMe, except resin, sludge, or evaporator bottoms Low-level refers to all radcoctsve waste that is not spent fuel or a by-product of spent fuel iss,eeds. This indcator tracks radologeal work performance for SEP #54.
73 l l
. SAFETY ENHANCEMENT PROGRAM INDEX The purpose of the Safety Enhancement Program (SEP) Performance Indicators inder is to list performance indmators related to SEP items with parameters that can be trended.
SEP Reference Numberis Eana e increase HPES and IR Accountability through use of Performance indicators 4 Procedural Noncompliaiice incidents (Maintenance) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 Recordable injuryAliness Cases Frequency Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 Clean Controlled Area Contaminations 11,000 DisintegrationsAVhnute Per Probe Area ...........17 Preventable / Personnel Error LERs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 t l SEP Reference Numbers 25. 26. & 27
. Training Program for Managers and Supervisors implemented l . Evaluate and implement Station Standards for Safe Work Practice Requirements
. . implement Supervisory Enforcement of industrial Safety Standards Disabling injuryAllness Frequency Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 Recordable injuryMilness Cases Frequency Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 SEP Reference Number 31
. Develop Outage and Maintenance Planning Manual and Conduct Project Management Training MWO Planning Status (Cycle 17 Refueling Outage) ...... ................... ........... 59 SSED's Overall Project Status . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 Overall Project Status (Cycle 17 Refueling Outage) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 Progress of Cycle 17 Outage Modification Planning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 63 SEP Reference Number 33
. Develop On-Line Maintenance and Modification Schedule 1996 On-line Modification Planning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 62
- SEP Reference Number 36 e Reduce Corrective Non-Outage Backlog Mainteuice Workload Backlogs (Corrective Non-Outage) . . . . . ..... .... .............. 39 SEP Reference Numbers 41 & 44
. Develop and implement a Preventive Maintenance Schedule . Compliance With and Use of Procedures Ratio of Preventive to Total Maintenance & Preventive Maintenance items Overdue . . . . . . . . . . . . . 40
- Procedural Noncompliance incidents (Maintenance) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 SEP Reference Number 46
- Design a Procedures Controland Administrative Program Document Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... .... ... ..........48 74 i
SEP Reference Number 52 EAg1 -
. Establish Supervisory Accountability for Workers Radiological Practices Radiological Work Practices Program . ........ ..... ........... ............ .. . . 47 SEP Reference Number 54
. Complete implementation of Radiological Enhancement Program Clean Controlled Area Disintegrations >1,000 Counts / Minute Per Probe Area . . . . . . . . . . . . . . . . . 17 Collective Radiation Exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ... .... ... 11 Volume of Low-Level Solid Radioactive Waste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 .
Contaminated Radiation Controlled Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 SEP Reference Number 58
. Revise Physical Security Training and Procedure Program Loggable/ Reportable incidents (Security) . . . . . . . . . . . . . . . . . . . . . . . . . . . ...........49 SEP Reference Numbers 60 & 61
. Improve Controls Over Surveillance Test Program
. Modify Computer Program to Correctly Schedule Surveillance Tests ,
Number of Missed Surveillance Tests resulting in Licensee Event Reports .. .. . .... ..... 23 SEP Reference Number 62
. Establish Interim System Engineers Temporary Modifications ............. ...... .... .. .. .... ....... .. ...... ... 50 Engineering Assistance Request (EAR) Breakdown . . . . . . . . .... ........... .......... 52 Engineering Change Notice Status ....... ... ... .. .. . ....... . .. .. 53 Engineering Change Notices Open . .... ... ... ... ...... ......... .... 54 SEP Reference Number 68
. Assess Root Cause of Poor Operator Training and establish means to monitor Operator Training License operator Requalification Training . . . . . . . . . . . . . . . . . . . . . . . . . ... ... ..... 56 Ucense Candidate Exams . . . . . . . . . . . . . . .. .... . ................. .. .. 57 SEP Reference Number 71
. Improve Controls over Temporary Modifications Temporary Modifications .. .... . ......... . . .......... .... ..... .. .. 50 O
75
REPORT DISTRIBUTION LIST R. L. Andrews L.T.Kusek G.C. Bishop C. J. Linden C. E. Boughter S. A. Lindquist C. J. Bruhnert B. R. Livingston J. W. Chase E. R. Lounsberry R. G. Conner T. J. Mcivor M.R. Core K. A. Miller T. R. Dukarski P. A. Mruz l M. Edwards (7) R. J. Mueller l M. L. Ellis R. L. Plott H. J. Faulhaber W.J.Ponec S. K Gambhir D. G. Ried J. K Gasper M. J. Sandhoefner W. G. Gates F. C. Scofield - S. W. Gebers H. J. Sefick M. J. Guinn R. W. Short R. H. Guy J. L. Skiles A. L. Hale R. D. Spies (2) W. R. Hansher K. E. Steele K R. Henry D. E. Spires J. B. Herman M. A. Tesar R. P. Hodgson J. J. Tesarek C. K Huang J. W. Tills R. L. Jaworski D. R. Trausch ' J. W. Johnson L. P. Walling D.D. Kloo:k G. R. Williams O e 76 __ J}}