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FORT CALHOUN STATION PERFORMANCE INDICATORS SEPTEMBER, 1990 N | |||
Prepared by: | |||
Production Engineering Division System Engineering PDR CK O O 85 PNU | |||
l OMAHA PUBLIC POWER DISTRICT FORT CALHOUN S1ATION PERFORMANCE INDICATORS PREPARED BY: | |||
PRODUCTION ENGINEERING DIVISION SYSTEM ENGINEERING SEPTEMBER 1990 | |||
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T TABLE OF CONTENTS PML L Distribution. . . . . . . . . . . . . . . . . . . . iv | |||
,, Preface . . . . . . . . . . . . . . . . . . . . . . 1 | |||
~ | |||
Purpose . . . . . . . . . . . . . . . . . . . . . . 3 Scope . . . . . . . . . . . . . . . . . . . . . . . 4 2-Adverse Trend Report. . . . . . . . . . . . . . . . 5 Indicators Needing Increased Management . . . . . . 6 Attention Index to Safety Enhancement Program (SEP) | |||
Indicators . . | |||
~ | |||
................. 9 Index to Performance Indicator Graphs . . . . . . . 12 Performance Indicator Graphs. . . . . . . . . . . . 17 Significant Items of Interest . . . . . . . . . . . 98 Definitions . . . . . . . . . . . . . . . . . . . . 99 R | |||
Basis for Establishing 1989 Performance Indicator Goal s . . . . . . . . . . . . . . . . 114 Operating Cycles and Refueling Outage Dates . . . 116 Production and Operation Records. . . . . . . . . . 118 Data Source . . . . . . . . . . . . . . . . . . . 119 References. . . . . . . . . . . . . . . . . . . . 123 | |||
DISTRIBUTION V. W. Anderson D. C. Gorence W. L. Neal R. L. Andrews R. E. Gray J. B. Newhouse W. R. Bateman M. J. Guinn M. W. Nichols 1 K. L. Belek E. R. Gundal C. W. Norris L A. D. Bilau A. L. Gurtis J. T. O'Connor B. H. Blome R. H. Guy W. W. Orr C. N. Bloyd R. M. Hawkins L. L. Parent J. P. Bobba M. C. Hendrickson T. L. Patterson C. E. Boughter R. R. Henning R. L. Phelps M. A. Breuer K. R. Henry T. M. Reisdorff C. J. Brunnert J. B. Herman B. A. Reneaud M. W. Butt G. J. Hill A. W. Richard C. A'. Carlson K. C. Holthaus T. J. Sandene J. W. Chase L. G. Huliska C. A. Sayre G. R. Chatfield R. L. Jaworski B. A. Schmidt A. G. Christensen R. A. Johansen S. T. Schmitz | |||
: 0. J. Clayton J. W. Johnson F. C. Scofield R. P. Clemens W. C. Jones L. G. Sealock < | |||
R. G. Conner J. D. Kecy H. J. Sefick : | |||
J. L. Connolley J. D. Keppler P. Sepcenko C. M. Cook D. D. Kloock J. W. Shannon M. R. Core J. C. Knight R. W. Short 3 S. R. Crites D. M. Kobunski J. R. Shuck D. W. Dale G. J. Krause C. F. Simmons-R. C. DeMeu1meester L. J. Kripal E. L. Skaggs R. D. DeYoung J. B. Kuhr F. K. Smith D. C. Dietz L. T. Kusek R. L. Sorenson D. E. Dirrim L. E. Labs D. E. Spires K. S. Dowdy M. P. Lazar K. E. Steele J. A. Drahota R. C. Learch W. Steele T. R. Dukarski S. E. Lee H. F. Sterba R. G. Ellis R. E. Lewis R. K. Stultz R. G. Eurich R. C. Liebentritt G.. A. Teeple H. J. Faulhaber C. J. Linden M. A. Tesar M. A. Ferdig B. R. Livingston T. G. Therkildsen V. H. Frahm J. M. Lofshult P. L. Thompson F. F. Franco- J. H. MacKinnon J. W. Tills H. K. Fraser G. D. Mamoran D. R. Trausch J. F. W. Friedrichsen J. W. Marcil P. R. Turner R. M. Fussell N. L. Marfice J. M. Uhland S. K. Gambhir D. J. Matthews C. F. Vanecek J. K. Gasper J. M. Mattice G. L. Van Osdel W. G. Gates T. J. McIvor L. P. Walling M.'O. Gautier R. F. Mehaffey J. M. Waszak J. M. Glantz R. A. Miser W. O. Weber J. T. Gleason K. J. Morris G. R. Williams | |||
. L. V. Goldberg D. C. Mueller S. J. Willrett R. J. Mueller W. C. Woerner iv i | |||
PREFACE PERFORHANCE INDICATORS REPORT IMPROVEMENTS One section has been added to the Performance Indicators Report. This section is the Refueling Outage Section. Three indicators have been added which justified the addition of this new section. These are: | |||
: 1) - The MWO Overall Status (1991 Refuelino Outaae) Indicator found on page 89 has been added to the Performance Indicators Report. This indicator shows the total number of MWO's that have been written for completion during the 1991 Refueling Outage and the number of MWO's ready for work (parts for these MWO's are staged, procedures are approved, and paperwork is ready for field use) . Also shown are the number of MWO's that are ready to work for the 1991 Refueling Outage. Any MWO's written after the start of the outage will be labeled as Emergent MW0's. | |||
Additional data points will be added to this indicator as information becomes available. | |||
: 2) The Proaress of 1991 Outaae Modification Plannina Indicator found on page 90 has been added. This indicator shows the number of modifications approved for planning (to determine feasibility) for completion during the 1991 Refueling Outage. Additional data points will be added to this indicator as information becomes available. | |||
: 3) The Overall Pro.iect Status (1991 Refuelino Outaae) Indicator found on page 91 has been added to the Performance Indicators Report. This indicator shows the status of the projects which affect the scope of the 1991 Refueling Outage. Additional data points will be added to this indicator as information becomes available. | |||
Four indicators have been changed. The Fuel Reliability Indicator is in the Operations Section, the- Maintenance Work Order Backloa (Corrective Non-Outaae) Indicator is 'in the Maintenance Section, the Number of Hot Soots Indicator is in the Chemistry and Radiological Protection Section, and the Inventory Accuracy Indicator is in the Material and Outside Services Section. | |||
The Fuel Reliability Indicator found on page 24 has been changed. The Industry Median value has been added to this indicator. This indicator uses a industry normalized letdown purification rate. The' fuel reliability factor was also calculated using Fort Calhoun's actual letdown purification rate. These calculations revealed that the use of the pl ant's actual letdown purification rate would result in an approximate 45% increase in the fuel reliability indicator data. | |||
The Maintenance Work Order Backloa (Corrective- Non-Outaae) Indicator found on page 42 has been changed. The goal for the number of open corrective non-outage MW0's has been changed to 500 open MW0's. This goal was previously set at 600 open MW0's. | |||
1 i | |||
PREFACE PERFORMANCE INDICATORS REPORT IMPROVEMENTS The Number of Hot Scots Indicator found on page 56 has been changed. The number of additional hot spots which were identified during the reporting has been added to this indicator. Previously, this indicator showed only the number of hot spots known to exist in the Fort Calhoun Station at the end of the reporting month. This change to this indicator should represent more accurately the involvement of the Station in reducing the number of hot spots. | |||
The Inventory Accuracy Indicator found on page 65 has been changed. The graphical presentation of this indicator has been modified. Previously, this indicator was shown in column graph form, but now it will be presented in line graph form. | |||
One indicator has been added to the Industry Key Parameters Section and the Operations Section. | |||
The Unolanned Safety System Actuations - | |||
(NRC Definition) Indicator found on page 21 has been added. This indicator shows the number of NRC definition safety system actuations each month, a twelve month running total of NRC definition safety system actuations, and the critical hours for the Fort Calhoun Station. | |||
The number of NRC definition safety system actuations include the High Pressure Safety Injection System (HPSI), the Low Pressure Safety Injection (LPSI). the Safety Injection Tanks, and the Emergency Diesel | |||
~ | |||
Generators. The NRC classification of safety system actuations includes actuations when major equipment is operated and when the logic systems ' | |||
for the safety systems are challenged. , | |||
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l PURPOSE This program titled " Performance Indicators" is intended to provide selected Fort Calhoun plant performance information to OPPD's personnel responsible for optimizing unit performance. The information is presented i n a way that provides ready identification of trends and a means to track progress toward reaching corporate goals. The information can be used for assessing and monitoring Fort Calhoun's plant performance, with emphasis on safety and reliability. ~ Some performance indicators show company goals or industry information. This information can be used for comparison or as a means of promoting pride and motivation. | |||
4 4 | |||
s 3- | |||
SCOPE 4 1 | |||
In order for the Performance Indicator Program to be effective, , | |||
the following guidelines were followed while implementing this program: | |||
Select the data which most offectively monitors Fort 3 | |||
Calhoun's performance in key areas. | |||
Present- the data in a straight forward graphical format using averaging and smoothing techniques, include established corporate goals and industry information for comparison. | |||
Develop formal definitions for each performance parameter. , | |||
4 This will ensure consistency in future reports and allow comparison with industry averages where appropriate. | |||
Comments and input | |||
* are encouraged to ensure that this program is tailored to address the areas which are most meaningful to 4 | |||
the people using the report. | |||
l | |||
ADVERSE TREND REPORT The Adverse Trend Report explains the conditions under which certain indicators are showing adverse trends. An indicator that is defined as AN ADVERSE TREND IS ONE IN WHICH THE DATA REPRESENTED FOR THREE CONSECUTIVE MONTHS IS SHOWING A DECLINE IN PERFORMANCE for that particular indicator. Indicators which show an apparent three month decline, but are uni considered an adverse trend, will display an explanation which defines the reason why an adverse trend does not exist. | |||
Enaineerina Assistance Reauest (EAR) Priority Breakdown - Page 76 The number of open EAR's has increased from 59 at the end of May of 1990 tc 4 at the end of September of 1990. The major reason for the increast a the number of open EAR's is the result of discrepancies between old procedures and the new procedures which are being upgraded by the Procedure Upgrade Project. | |||
Personnel Turnover Rate - Page 81 The personnel - turnover rate for the Nuclear Operations Division (NOD) and the Production Engineering Division (PED) has been increasing. There have been 30 resignations from N0D in the last 12 months and 11 resignations from PED in the last 12 months. | |||
f INDICATORS NEEDING INCREASED MANAGEMENT ATTENTION This section lists the indicators which show inadequacies as compared to the OPPD goal and indicators which show inadequacies as compared to the industry upper quartile. The indicators will be compared to the industry upper quartile as relevant to that indicator. | |||
Forced Outaae Rate - Page 18 The forced outage rate for the month of September 1990 was reported as being higher than the Fort Calhoun goal of 2.4%. This rise in the forced outage rate during the month of August was due to seal problems encountered in reactor coolant pump RC-3A. These problems resulted in 172.6 forced outage hours. During the month of September the plant was shutdown due to design basis questions. This forced outage resulted in 105.6 forced outage hours being reported. | |||
Unolanned Safety System Actuations - (INPO Definition) - Page 20 The Fort Calhoun Station has experienced an unplanned safety system actuation during 1990. This unplanned actuation was a start and load of DG-2 due to an inadvertent trip of backup lockout relay 86/2BF5. The Fort Calhoun goal for unplanned safety system actuations during 1990 was set at zero actuations. | |||
Gross Heat Rate - Page 22 The monthly gross heat rate for the months of August and September were reported as being above the Fort Calhoun monthly goal. Thase high monthly gross heat rates were due to two forced shutdowns of the plant which occurred during August and September. | |||
The year to date gross heat rate is currently above the goal of 10,326 BTV/KWH The gross heat rate values for January and February were high due to the fact that the first stage of the high pressure turbine was removed - during the months of January and February. During May startup from the 1990 Refueling Outage caused the gross heat rate to be high, t _During July, August, and September various derates, and two forced outages caused the gross- heat rate values for these months to be higher than the Fort Calhoun goal. | |||
i- Eouivalent Availability Facter - Page 23 The monthly EAF for September was below the goal of 93% due to the forced outage which occurred during September involving design basis questions. The year to date EAF is currently below the year to date goal of 56.4% due to various power fluctuations which occurred during the month of June and due to forced outage hours which occurred during the months of August and September. | |||
-Fuel Reliability Indicator (FRI) - Page 24 The FRI has been above the Fort Calhoun goal of 1.0 nanocuries/ gram. The FRI value for September using the actual plant letdown rate was reported as 2.05'nanocuries/ gram. | |||
INDICATORS NEEDING INCREASED MANAGEMENT ATTENTION (CONTINVED) | |||
DG Reliability last 100 DemenJ1 - Page 32 The diesel generator start and load reliability of DG-1 is currently below the Fort Calhoun goal of 95%. This is due to the fact that diesel generator DG-1 has experienced 7 start and load failures in its last 100 demands. | |||
DG Reliability last 20 Demands - Page 33 The start and load reliability of diesel generator DG-1 is below the Fort Calhoun goal of 95% reliability. This low start and load reliability for diesel generator DG-1 is due to two start and load failures which occurred in July 1990. These two failures were caused by high engine coolant temperature problems. | |||
Corrective Maintenance Backloa Greater Than 3 Months Old (Non-Outaae) Page 36 The percentage of open corrective non-outage MWO's older than 3 months old is currently above the industry quartile value of 45.8% due to 230 open MWO's that are older than 3 months old. | |||
. Ratio'of Preventive to Total Maintenance - Page 37 The ratio of preventive to total maintenance was reported below tne Fort Calhoun goal of 60% and below the industry upper quartile value of 57.7%. This ratio decreased due to the high number of hours in which maintenance was involved in corrective maintenance activities associated with the forced outage which occurred in September. | |||
Number of Out-of-Service Control Room Instruments - Page 39 The number of out-of-service control room instruments has been above the Fort Calhoun goal of 7 out-of-service control room instruments and above the industry upper quartile value of 7 out-of-service control room l instruments since November of 1989. | |||
1 Check Valve Failure Rate - Page 46 The. Fort Calhoun check valve failure rate is currently above the industry check valve failure rate. The reason for the high check valve L | |||
failure rate is that the plant is performing maintenance on check valves which have not been tested for failures before. The check valve failure rate is expected to decrease as the check valves are maintained and monitored through the Check Valve Program. | |||
In-Line Chemistry Instruments Out-of-Service - Page 50 The number of instruments out of service at the end of. September was above the goal of 6 out-of-service instruments. The current number of chemistry instruments that are out-of-service is 7. | |||
1 l- | |||
INDICATORS NEEDING INCREASED MANAGEMENT ATTENTION (CONTINUED) | |||
'otal Skin and Clothina Contaminations - Page 53 The total number of skin and clothing contaminations has been above the fort Calhoun goal of 150 contaminations since the month of April 1990. | |||
The total number of skin and clothing contaminations has been above the industry upper quartile value of 129 contaminations since the month of March 1990. The high number of skin and clothing contaminations dyring the months of March and April 1990 was due to increased activity in the Radiation Controlled Area (RCA) associated with the 1990 Refueling Outage. | |||
Decontaminated Auxiliary Buildino - Page 54 The square footage of the auxiliary building which is decontaminated is currently below the Fort Calhoun goal of 85% (non-outage). This is due to activities which took place in the auxiliary building associated with the forced outage which occurred during September. | |||
Temoorary Modifications (Excludino Scaffoldino) Page 75 The number of temporary modifications which are installed in the plant is currently above the Fort Calhoun goal of 15 temporary modifications. | |||
The number of temporary modifications which are installed in the plant has been decreasing and is expected to keep decreasing. | |||
SAFETY ENHANCEMENT PROGRAM (SEP)- | |||
PERFORMANCE INDICATORS The purpose of the Safety Enhancement Program (SEP) Performance Indicators pages is - to list the indicators related to the SEP items with parameters > | |||
that can be trended. | |||
SEP Reference Number 15 - Increase HPES and IR Accountability ELqg Through Use of Performance Indicators Procedural Noncompliance Incidents (Maintenance) . .,. . . . . . 41 Total Skin and Clothing Contaminations . . . . . . . . . . . . . 53 1 | |||
Recordable Injury Cases frequency Rate . . . . . . . . . . . . . 79 Number of Personnel Errors Reported in LER's . . . . . . . . . . 80 j CAR's Issued versus Significant CAR's Issued versus NRC Violations Issued versus LER's Reported . . . . . . . . . . 97 | |||
.SEP Reference Number 20 - Quality Audits and Surveillance Programs are Evaluated, Improved in Depth and Strengthened CAR's Issued versus Significant CAR's Issued versus NRC Violations Issued versus L.ER's Reported . . . . . . . . . . 97 SEP Reference Number 21 - Develop and Conduct Safety System Functional-Inspections , | |||
CAR's Issued versus Significant CAR's Issued versus NRC Violations Issued versus LER's Reported . . . . . . . . . . 97 SEP Reference Number 24 - Complete Staff Studies Sta f fi ng Level . . . . . . . . . . . . . . . . . . . . . . . . . 82 SEP Reference Number 26 - Evaluate and Implement Station Standards for Safe Work Practice Requirements l. | |||
L Disabling Injury Frequency Rate ........... . . . . 27 | |||
- Recordable Injury Cases Frequency Rate . . . . . . . . . . . . . 79 I | |||
SEP Reference Number 31 - Develop Outage and Maintenance Planning Manual and Conduct Project Management Training MWO Overall Status (1991 Refueling Outage) . . . . . . . . . . . 89 Progress of 1991 Outage Modification Planning. . . . . . . . . . 90 1 | |||
Overall Project Status (1991 Refueling Outage. . . . . . . . . . 91 | |||
.g. | |||
SAFETY ENHANCEMENT PROGRAM (SEP) | |||
PERFORMANCE INDICATORS (CONTINUED) | |||
SEP Reference Number 36 - Reduce Corrective Non Outage Backlog Maintenance Work Order Backlog (Corrective Non Outage Maintenance) . . . . . . . . . . . . . . 42 SEP Reference Number 41 - Develop and Implement a Preventive Maintenance Schedule Ratio of Presentive to Total Maintenance . . . . . . . . . . . . 37 Preventive Maintenance items Overdue . . . . . . . . . . . . . . 38 SEP Reference Number 43 - Implement the Check Valve Test Program Check Valve Failure Rate . . . . . . . . . . . . . . . . . . . . 46 SEP Reference Number 44 - Compliance With and Use of Procedures Procedural Noncompliance Incidents (Maintenance) . . . . . . . . 41 SEP Reference Number SR - Establish Supervisory Accountability for Workers Radiological Practices Radiological Work Practices Program. . . . . . . . . . . . . . . . 55 SEP Reference Number 54 - Complete Implementation of Radiological Enhancement Program Personnel Radiation Exposure (Cumulative) . . . . . . . . . . . 25 Volume of Low-Level Solid Radioactive Waste. . . . . . . . . . . 26 Total Skin and Clothing Contaminations . , , . . . . . . . . . . 53 Decontaminated' Auxiliary Building. . . . . . . . . . . . . . . . 54 SEP Reference Number 58 - Revise Physical Security Training and Procedure Program Loggable/ Reportable Incidents (Security) . . . . . . . . . . . . 59 Security Incident Breakdown ...t. . . . . , . . . . . . . 60 Security System Failures . . . . . . . . . . . . . . . . . . . . , 61 gE. p Number 60 - Improve Controls Over Surveillance Test Program Missed Surveillance Tests Resulting in Event Reports . . . . . . . . . . . . . . . . . . . . . 43 SAFETY ENHANCEMENT PROGRAM (SEP) | |||
PERFORMANCE INDICATORS (CONTINUED) | |||
SEP Reference Number 61 - Modify Computer Program to Correctly Schedule Surveillance Tests Number of Missed Surveillance Tests Resulting in Licensee Event Reports . . . . . . . . . . . . . . . . . . . . . 43 SEP Reference Number 62 - Establish Interim System Engineers Temporary Modi fications. . . . . . . . . . . . . . . . . . . . . 75 Engineering Assistance Request Priority Breakdown. . . . . . . . 76 SEP Reference Number 62 - Establish Interim System Engineers (Continued) | |||
Engineering Change Notice Status . . . . . . . . . . . . . . . . 77 Engineering Change Notice Breakdown. . . . . . . . . . . . . . . 78 SEP Reference Number 68 - Assess Root Cause of Poor Operator Training and Establish Means to Monitor Operator Training SRO License Examination Pass Ratio . . . . . . . . . . . . . . . 83 R0 License Examination Pass Ratio . . . . . . . . . . . . . . . 84 License Candidate Exams. . . . . . . . . . . . . . . . . . . . . 85 SEP Reference Number 71 - Improve Controls over Temporary Modifications Temporary Modifications ....................75 a | |||
n | |||
c PERFORMANCE INDICATORS INDEX TO GRAPHS INDUSTRY KEY PARAMETERS i Forced Outage Rate . . . . . . . . . . . . . . . . . . . . . . . 18 Unplanned Automatic Reactor Scrams While Critical. . . . . . . . 19 Unplanned Safety System Actuations - (INPO Definition) . . . . . 20 l | |||
Unplanned Safety System Actuations - (NRC Definition). . . . . . 21 Gros s Heat Rate. . . . . . . . . . . . . . . . . . . . . . . . . 22 l Equivalent Availability Factor . . . . . . . . . . . . . . . . . 23 Fuel Reliability Indicator . . . . . . . . . . . . . . . . . . . 24 Personnel Radiation Exposure (Cumulative). . . . . . . . . . . . 25 ; | |||
Volume of Low level Solid Radioactive Waste. . . , . . . . . . . 26 Disabling injury Frequency Rate. . . . . . . . . . . . . . . . . 27 l | |||
l | |||
't i | |||
l l | |||
l i | |||
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E | |||
_ PERFORMANCE INDICATORS | |||
, INDEX 10 GRAPHS (CONTINUED) | |||
OPERATIOM Station Net Generation . . . . . . . . . . . . . . . . . . . . 17 Forced Outage Rate . . . . . . . . . . . . . . . . . . . . . . . 18 Unplanned Automatic Reactor Scrams While Critical. . . . . . . . 19 Unplanned Safety System Actuations (INPO sefinition) . . . . . . 20 h Unplanned Safety System Actuations (NRC Definition). . . . . . . 21 Gross Heat Rate. . . . . . . . . . . . . . . . . . . . . . . 22 Equiv31ent Availability Factor . . . . . . . . . . . . . . . . 23 fuel Reliability Indicator . . . . . . . . . . . . . . . . . . . 24 L Daily Thermal Output . . . . . . . . . . . . . . . . . . . . . . 28 f | |||
Equipment Forced Outages per 1000 Critical Hours . . . . . . . . 29 Operations and Maintenance Budget. . . . . . . . . . . . . . . . 30 Document Review. . . . . . . . . . . . . . . . . . . . . . . . 31 tiAINTENANCE y | |||
Diesel Generator Reliability (100 Demands) . . . . . . . . . . . 32 Diesel Generator Reliability (20 Demands). . . . . . . . . . . . 33 Age of Outstanding Maintenance Work Orders . . . . . . . . . . . 34 E 35 Maintenance Work Order Breakdown . . . . . . . . . . . . . . . . | |||
Corrective Maintenance Backlog >3 Months Old . . . . . . . . . . 36 | |||
= 37 Ratio of Preventive to Total Maintenance . . . . . . . . . . . . | |||
Preventive Maintenance items Overdue . . . . . . . . . . . . . . 38 39 Number of Out-of Service Control Room Instruments. . . . . . . . | |||
43 Maintenance Overtime . . . . . . . . . . . . . . . . . . . | |||
Procedural Noncompliance incidents (Maintenance) . . . . . . . . 41 Maintenance Work Order Backlog (Corrective Non-Outage) . . . . . 42 13-m | |||
m PERFORMANCE INDICATORS INDEX TO GRAPHS (CONTINUED) | |||
MAINTENANCE fCONTI M D1 Number of Surveillance Tests Resulting in Licensee Event Reports . . . . . . . . . . . . . . . . . . . . . 43 Number of Nuclear Plant Reliability Data System (NPRDS) | |||
Reportable Fail ures. . . . . . . . . . . . . . . . . . . . . . . 44 Maintenance Effectiveness. . . . . . . . . . . . . . . . . . . . 45 Check Valve Failure Rate . . . . . . . . . . . . . . . . . . . . 46 i CHEMISTRY AND RADIOLOGICAL PROTECTION Personnel Radiation Exposure (Cumulative). . . . . . . . . . . . 24 Volume of low-level Solid Radioactive Waste. . . . . . . . . . . 25 Secondary System Chemistry . . . . . . . . . . . . . . . . . . . 47 Primary System Chemistry Percent of Hours Out of Limit . . . . 48 Auxiliary Systems Chemistry Hours Outside Station Limits . . . . 49 In Line Chemistry Instruments Out of Service . . . . . . . . . . 50 i Hazardous Waste Produced . . . . . . . . . . . . . . . . . . . . 51 Maximum Individual Radiation Exposure. . . . . . . . . . . . . . 52 x Total Skin and Clothing Contaminations . . . . . . . . . . . . . 53 Decontaminated Auxiliary Building. . . . . . . . . . . . . . . . 54 Radiological Work Practices Program. . . . . . . . . . . . . . . 55 Number of Hot Spots . . . . . . . . . . . . . . . . . . . . . . . 56 Gaseous Radioactive Waste Being Discharged to the Environment. . 57 Liquid Radioactive Waste Being Discharged to the Environment . . 58 i SECURITY loggable/ Reportable incidents (Security) . . . . . . . . . . . . 59 Security incident Breakdown, , . . . . . . . . . . . . . . . . . 60 Security System Failures . . . . . . . . . . . . . . . . . . . . 61 l | |||
PERFORMANCE INDICATORS INDEX TO GRAPHS (CONTINUED) ; | |||
MATERIALS AND OUTSIDE SERVICES Amount of Work On Hold Awaiting Parts. . . . . . . . . . . . . . 62 l Spare Parts inventory Value. . . . . . . . . . . . . . . . . . . 63 Spare Part s i s sued . . . . . . . . . . . . . . . . . . . . . . . 64 Inventory Accuracy . . . . . . . . . . . . . . . . . . . . . . . 65 Stockout Rate. . . . . . . . . . . . . . . . . . . . . . . . . . 66 Warehouse Receipts . . . . . . . . . . . . . . . . . . . . . . . 67 Warehouse i s sue s . . . . . . . . . . . . . . . . . . . . . . . . 68 Warehouse Returns. . . . . . . . . . . . . . . . . . . . . . . . 69 l | |||
Material Requests Awaiting Approval . . . . . . . . . . . . . . . 70 Expedited Purchases. . . . . . . . . . . . . . . . . . . . . . . 71 Invoice Breakdown. . . . . . . . . . . . . . . . . . . . . . . . 72 Material Request Planning. . . . . . . . . . . . . . . . . . . . 73 DESIGN ENGINEERING Outstanding Modifications. . . . . . . . . . . . . . . . . . . . 74 Temporary Modifications. . . . . . . . . . . . . . . . . . . . . 75 Engineering Assistance Request (EAR) Priority Breakdown. . . . . 76 | |||
; Engineering Change Notice Status . . . . . . . . . . . . . . . . 77 Engineering Change Notice Breakdown. . . . . . . . . . . . . . . 78 INDUSTRIAL SAFETY Disabling injury Frequency Rate. . . . . . . . . . . . . . . . . 26 I | |||
Recordable Injury Cases Frequency Rate . . . . . . . . . . . . . 79 HUMAN RESOURCES l-i Number of Personnel Errors Reported in LERs. . . . . . . . . . . 80 l | |||
l l | |||
1 l | |||
PERFORMANCE INDICATORS INDEX TO GRAPHS (CONTINUED) | |||
HUMAN RESOURCES (CONTINVED) | |||
Personnel Turnover Rate. . . . . . . . . . . . . . . . . . . . . 81 St a f fi ng Level . . . . . . . . . . . . . . . . . . . . . . . . . 82 TRAINING AND OVAllFICATION SRO License Examination Pass Ratio . . . . . . . . . . . . . . . 83 R0 License Examination Pass Ratio. . . . . . . . . . . . . . . . 84 License Candidate Exams. . . . . . . . . . . . . . . . . . . . . 85 Hotlines . . . . . . . . . . . . . . . . . . . . . . . . . . . . 86 Classroom (Instructor) Hours . . . . . . . . . . . . . . . . . . 87 Total Hours of Student Training. . . . . . . . . . . . . . . . . 88 REFUELING OU1 AGE MWO Overall Status (1991 Refueling Outage) . . . . . . . . . . . 89 Progress of 1991 Outage Modification Planning. . . . . . . . . . 90 Overall Project Status (1991 Refueling Outage) . . . . . . . . . 91 OVAllTY ASSURANCE Number of Violations per 1000 Inspection Hours . . . . . . . . . 92 Cumulative Violations and Non Cited Violations (NCV's) . . . . . 93 Percent of CAR's Greater Than Six Months Old . . . . . . . . . . 94 Overdue and Extended Corrective Action Reports . . . . . . . . . 95 Corrective Action Reports Current Status . . . . . . . . . . . . 96 CAR's !ssued versus Significant CAR's issued versus. . . . . . . 97 NRC Violations issued versus LERs Reported l | |||
l 16- | |||
1 l | |||
l 500000- 1 IStation Net Generation 400000-M I e | |||
9 l a | |||
W 300000-a t , | |||
t H 200000-o u , | |||
r s | |||
100000-O' Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 STATION NET GENERATION This indicator shows the net generation of the Fort Calhoun Station for the reporting month. | |||
During the month of September 1990, a net total of 272,573.0 MWH was generated by the Fort Calhoun Station. The net generation for the month of August was low due to a forced outage which occurred during the month. This forced outage was due to seal problems on reactor coolant pump RC 3A, The net generation for the month of September was also low due to a forced outage. | |||
The forced outage was due to a design basis question on containment cooling capabilities. | |||
The not generation totals for the months of March and April were zero and the net generation total for the month of May was low due to the plant being shutdown for the 1990 Refueling Outage. | |||
Adverse Trend: None | |||
- Forced Outage Rate 6 -G- fort Calhoun Goal G Industry Upper 10 Percentile 5-GOOD 4- 4 R | |||
a t 3-e o....o.- q...o...s --o...o...q...o...s..O--D 2-1.4 , | |||
l-0 0 D' D'' ' O ' ^ D ~ ' ' D ' ' | |||
* D ~D 0 0 9 O O 3 | |||
'87 '88 '89 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 FORCED OUTAGE RATE The forced outage rate was reported as 3.2% for the month of September 1990. The continuation of the forced outage rate for the fort Calhoun Station during the month of September was due to a forced outage which occurred due to design basis questions on containment cooling capabilities. | |||
The last forced outage at fort Calhoun occurred in August of 1990. | |||
The industry upper ten percentile value for the forced outage rate is 0.25%. | |||
The 1990 goal for forced outage rate is 2.4% | |||
and is based on seven days. of forced outage time. The basis for establishing the 1990 performance goals can be found on page 114. | |||
Adverse Trend: None - Reason for increase is given above. | |||
l 10- | |||
1 5 | |||
n Reactor Scram G- Fort Calhoun Goal O Industry Upper 10 Percentile 4-S GOOD 3 | |||
c r + | |||
a m , | |||
2-1 1- 0---- G --- G -- - e-- -- o---- o--- - o ---- o -- -- o - ---o -- - -o - - - o | |||
$rei 0 0 0 " | |||
0 C O ;_: m- :< . | |||
'86 '87 '88 '89 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 UNPLANNED AUTOMATIC REACTOR SCRAMS WHILE CRITICAL There were no unplanned automatic reactor scrams in September. It has been 1,551 days since the last unplanned automatic reactor scram which occurred on July 2, 1986. | |||
The 1990 goal for unplanned automatic reactor scrams while critical has been set at 1. | |||
The industry upper ten percentile value is zero scrams per unit on an annual btsis. The Fort Calhoun Station is currently in the upper ten percentile of nuclear plant performance in this area. | |||
Adverse Trend: None 1 | |||
4- M Safety System Actuations e- Fort Calhoun Goal O Industry Upper 10 Percentile 3-A C | |||
t j GOOD k2 o | |||
k n | |||
s 1- &--- O---- Q, N uis | |||
'\ i Vi$ | |||
0 0 0 0 | |||
'87 '88 '89 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Ag S ! | |||
1989 1990 UNPLANNED SAFETY SYSTEM ACTUATIONS - (INPO DEFINITION) | |||
There were no unplanned safety system actuations during the month of September 1990. | |||
The 1990 goal for the number of unplanned safety system actuations is zero. This goal is based on past performance at the Fort Calhoun Station. | |||
The industry upper ten percentile value for the number of unplanned safety system actuations per year is zero. | |||
Adverse Trend: None Q Safety System Actuations (SSA's) | |||
- 12 Month Running Total SSA's | |||
--- Critical Hours 10- 1000 1 N 8- 800 N u , ,,,---, f,,,,,---, u m . | |||
,i \ l \ ,i \ ;, , , ,,\ m b < \ l 'i \ ; \ b 6- \/ # | |||
600f S I | |||
'\, l V o - | |||
, o i | |||
.I \, l f | |||
4' 400 g t S f ) l g3 S l o l !, | |||
A ; , | |||
; u | |||
?gti ! ! | |||
l r | |||
5 5 2- l - , l 200 l :n ll l | |||
. : A % ,i y I | |||
, mt + | |||
M 0 0 0 | |||
'88 '89 JFMAMJJAS0ND JFMAMJJA S0ND 1989 1990 UNPLANNED SAFETY SYSTEM ACTUATIONS - (NRC DEFINITION) | |||
The Unplanned Safety System Actuations - (NRC Definition) Indicator has been added to the- Performance Indicators Report. This indicator shows the number of safety system actuations (SSA's) which include the High and Low Pressure Safety Injection Systems, the Safety Injection Tanks, and the Emergency Diesel Generators. The NRC classification of SSA's includes actuations when major equipment is o)erated and when the logic systems for these safety systems are cla11enged. | |||
The last event of this type occurred in June 1990 when Diesel Generator D 1 was started due to a turbine trip. This trip was a result of a failure to reset the plant output circuit breaker following an attempt to synchronize the main generator. | |||
The majority of SSA's displayed above were related to 1990 Refueling l | |||
Outage activities and are currently being reviewed under the Safety i System Actuation Reduction Program. The goal of this Program is to reduce the number of SSA's at Fort Calhoun. | |||
Adverse Trend: None - Program to reduce the number of SSA's is being implemented. | |||
l | |||
13000- | |||
[_J Monthly Gross Heat Rate | |||
- Year-to Date Gross Heat Rate G- Fort Calhoun Monthly Goal | |||
-+- Fort Calhoun Year to Date Goal 12000 O Industry Upper 10 Percentile B | |||
T ' | |||
U | |||
/ | |||
K GOOD y 11000-H 10520 | |||
&,s - | |||
e a U~ E U~O U U ~ | |||
O ~ | |||
O 10014 s m p, p S. ~ - | |||
M qlf$ , | |||
9000 | |||
'87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 GROSS HEAT RATE The gross heat rate for the Fort Calhoun Station was reported as 10,347 BTV/KWH during the month of September. This monthly gross heat rate was above the monthly gross heat rate goal of 10,125 BTV/KWH The high monthly gross heat rate was due to the shutdown of the plant which occurred due to a forced outage during the month of September. | |||
The year-to date gross heat rate was reported as 10,409 BTU /KWH. This year to date value was higher than the year to date gross heat rate goal of 10,294 BTV/KWH. The year-to-date gross heat rate is above the Fort Calhoun goal due to the fact that the first stage of the high pressure turbine was removed prior to the 1990 Refueling Outage. Additionally, the gross heat rate values for the months of May, June, and July 1990, were high due to startup after the 1990 Refueling Outage and various derates. | |||
The year-to date gross heat rate value is expected to decrease as the river water temperature decreases. The above monthly and year to-date Fort Calhoun goals are the best gross heat rate that can be achieved by the Fort Calhoun Station. Currently the plant is above the year-to date gross heat rate goal. If the station operates at 100% for the rest of 1990, this | |||
! goal will be approached but will not be achieved. | |||
The gross heat rate industry upper ten percentile value is 9,935 BTV/KWH. | |||
Adverse Trends: None I IMonthly EAF ' | |||
- Year-to-Date EAF jy G- Fort Calhoun Monthly Goal 1 | |||
-+- Fort Calhoun Year to-Date Goal GOOD | |||
-G Industry Upper 10 Percentile 100- l | |||
&- - - - -& - - - G -- - -- -O | |||
_%, O' , | |||
\ | |||
p-77 80 Dy G- O --G- -O~ O- - G - - G -D- -O l 71 i 1' l l | |||
" 66 i ! | |||
q 60- \' | |||
r ' | |||
/ /. | |||
~ | |||
/, e s f N | |||
[40- | |||
\ ,/ | |||
h~ h. - | |||
i, .y . | |||
s - - | |||
\ l 20- | |||
? \ l W . | |||
i l l l , | |||
7 | |||
\ | |||
g ; | |||
l O 6 ^ - | |||
'87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 10VIVALENT AVAILABILITY FACTOR The Equivalent Availability Factor (EAF) Indicator has been changed. | |||
l This indicator now shows a monthly EAF goal as well as a year-to date l | |||
EAF goal. The 12 month average EAF has been deleted and replaced with year-to date data. | |||
l l The EAF was reported as 73.1% for the month of August. This EAF was lower than the Fort Calhoun monthly goal of 93% due to a forced outage which occurred during the month of August. This forced outage occurred due to problems encountered with a seal in reactor coolant pump RC 3A. | |||
l The year-to-date EAF was reported as 48.8%. This year-to date value was lower than the year-to-date goal of 51.9%. -The low year-to-date EAF was due to various power fluctuations which occurred during the month of June and the forced outage which occurred during the month of August. | |||
The EAF industry upper ten percentile value is 82.5%. | |||
Adverse Trends: None 8 - Fuel Reliability Indicator G- Fort Calhoun Goal | |||
< O Industry Upper 10 Percentile Industry Median 6-n a | |||
n g~o 1 - | |||
; 4 2.4 u | |||
\ GOOD | |||
{ 41 s 4" | |||
u * \ | |||
*RAg 5 rBfd v, 1.5 r m | |||
1 i,Q n'' | |||
" a m 2' \d 6 a a a E O | |||
'? | |||
Q$ y Q | |||
$g | |||
& ~ ~ O - - - -O - - - s - - - O - - - -& - - - & - -- O - - - tr - - O - - - -t> - - - D h | |||
t$$lT vdl 0 m n n n n g g .1, o .g g- 9 ! | |||
'88 '89 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 FUEL RELIABillTY INDICATOR The Fuel Reliability Indicator has been changed. The industry median value has been added to this indicator. | |||
The FRI was reported as 1.40 nanocuries/ gram for the ; | |||
month of September. This INPO indicator uses an industry normalized letdown purification rate. The FRI was also ; | |||
calculated using Fort Calhoun's actual letdown purification rate. These calculations revealed that the use of .the plant's actual letdown purification rate would result in an approximate 45% increase in the FRI data. | |||
The FRI value using the plant's actual letdown purification rate was reported as 2.05 nanocuries/ gram. | |||
The 1990 fuel reliability goal has been set at 1.0 nanocuries/ gram. | |||
The fuel reliability indicator industry upper ten percentile value is 0.04 nanocuries/ gram. | |||
I Adverse Trend: None 1 | |||
l- - | |||
l l | |||
1 Personnel Radiation Exposure 388 400 G- Fort Calhoun Goal l O Industry Upper 10 Percentile h,,t s | |||
d@ GOOD l J**1 300- 1 22 + e .- D | |||
,, - & _ _ 9. . . | |||
,gj m - | |||
g...O -9 . . . .O W | |||
: m. . . | |||
vp 11 R | |||
;4 g gnn. - | |||
H a, | |||
*. O O O0 0 -O O- O- D- O O O sj , | |||
c | |||
$lli #\- | |||
93.4 100- | |||
/ | |||
lg g); - | |||
; ,o | |||
/ | |||
jhi, i, ,- | |||
/ | |||
^ | |||
T O'" | |||
'87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 PERSONNEL RADIATION EXPOSURE (CUMULATIVE) | |||
During September 1990, 5.8 man rem was recorded by TLD's worn by personnel while working at the Fort Calhoun Station. | |||
The monthly cumulative exposure goal for September was 269.3 man-rem while the actual cumulative exposure through September totaled 251.3 man rem. The exposure cumulated in 1990 has been high due to the increased activity in the Radiation Controlled Area (RCA) associated with the 1990 Refueling Outage. | |||
The personnel radiation exposure industry upper ten percentile is 166 man rem per unit per year. | |||
Adverse Trend: None SEP 54 25- | |||
O Monthly Radioactive Waste Shipped 12500- - Cumulative Radioactive Waste Shipped | |||
-G- Fort Calhoun Goal s Industry Upper 10 Percentile C | |||
u I GOOD L | |||
c 7500- 4, 6195 F m e e | |||
4454 , | |||
t 5000- o---- o- - - -e---- o -- -o --- e-- --o ---e-- --o -- - e - -- o - -- o 7 / | |||
M M Q g o. - o . O O O D- -O O O O O | |||
*< 1722 Y 2500-N,) E SI g | |||
3 'i 9 0 | |||
'87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 - | |||
VOLUME OF LOW LEVEL SOLID RADIOACTIVE WASTE The above graph shows the amount of low-level radioactive waste shipped off site for disposal. The table below lists the amount of waste actually shipped off-site for disposal and the amount of low level radioactive waste which is in temporary storage. | |||
The volume of solid radioactive waste is (cubic feet): | |||
Amour,t Shipped in September - | |||
0.0 Amount in Temporary Storage - 983.0 1990 Cumulative Amount Shipped - | |||
1568.6 1990 Goal - | |||
5000.0 The industry upper ten percentile value is 3,072 cubic feet per unit per year. The Fort Calhoun Station was in the upper ten percentile of nuclear plants for this indicator in 1986, 1987 and 1988. | |||
Adverse Trend: None SEP 54 l u | |||
\ | |||
2- E 1990 Disabling Injury Frequency Rate | |||
* 1989 Disabling Injury frequency Rate 1.75- 5 Year Average Disabling Injury Frequency Rate e- Fort Calhoun Goal 1.5- G Industry Upper 10 Percentile 1.25-R a GOOD 3 | |||
t s, 4 | |||
.75- | |||
.5 , . s' | |||
: o. . .. . e. . . h g. . , . . . .o.....o..._ o .....s ....o TX L aA 0 | |||
Dj 5 | |||
~% | |||
m m - - - - | |||
m m Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec DISABLING INJURY FRE0VENCY RATE (LOST TIME ACCIDENT RATE) | |||
This indicator shows the current monthly disabling injury rate in column form. The 1989 disabling injury frequency rate and the Fort Calhoun Station 5 year average disabling injury frequency rate are also shown. There were zero disabling injuries reported at the Fort Calhoun Station in September. The total number of disabling injuries in 1990 is one. | |||
l The 1990 disabling injury frequency rate goal was set at 0.31% and l was based on one disabling injury occurring in 1990. | |||
The industry upper ten percentile disabling injury frequency rate-is 0%. | |||
The year end disabling injury frequency rates for 1987, 1988, and i 1989 were 0.6, 1.6, and 0.4 respectively. | |||
Adverse Trend: None SEP 26 | |||
- - Thermal Output ; | |||
- Technical Specification Limit | |||
-O Fort Calhoun Goal 1500: ro ^^^;m ;m esc;;;; s;; ;m ^ | |||
. co 1200-' ( | |||
,y (j | |||
g 900- 'j a .! | |||
w - , | |||
a 600- . | |||
t ; , .j s : ;1 300 f 'g 0< , , , , , , , , , , , , , , , | |||
a 1 7 14 21 28 September 1990 DAILY THERMAt OUTPUT The above thermal output graph displays the daily operating power level, the 1500 thermal megawatt average technical specification limit, and the 1495 thermal megawatt Fort Calhoun goal. The cross hatched area represents the difference between the maximum allowable operation and the actual plant operation. | |||
The percent power operation of the Fort Calhoun Station during September 1, 1990 through September 3, 1990 was below 30%. The plant was then operated at approximately 100% until September 29, 1990 when the plant was shutdown for a forced outage. This forced outage was due to design basis questions. | |||
It must be noted that normal update oscillations on test point XC105 prevent Operations from continually operating the plant above 1495 thermal megawatts. Because of these oscillations, power is sometimes backed down to decrease the risk of violating the 1500 thermal megawatt technical specification limit. | |||
Adverse Trend: None 2- | |||
- Equipment Forced Outage Rate 1.8-1.6-1.4-1.2 GOOD R | |||
a + | |||
1 t , | |||
.8- | |||
.6- | |||
.4- | |||
,,* I 3,,, - | |||
.2-0 0 0 | |||
'87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 E0VIPMENT FORCED OUTAGES PER 1000 CRITICAL HOURS There wert zero equi) ment forced outage hours reportec during the month of September 1990. | |||
The last equipment forced outage occurred in August of 1990 and vas due to seal problems on rtactor coolant pump RC 3A l Adverse Trend: None i | |||
1 1 | |||
t | |||
l | |||
- Actual Operations Expenditures | |||
, ) | |||
+ Operations Budget gy100-i i i o l 50-na | |||
" -/ i 5 d' , . l | |||
$ g5 | |||
,/~__, | |||
s O' | |||
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 40 3 | |||
- Actual Maintenance Expenditures | |||
"" " """ "9 M 30-i 1d #- | |||
1o y9 p"y i1 | |||
/ ~~",g | |||
*l sr1- 0 ,/, | |||
5 0 | |||
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 OPERATIONS AND MAINTENANCE BUQQ[I The Operations and Maintenance Budget Indicator shows the budget year to date as well as the actual expenditures for operations and maintenance for the Fort Calhoun Station. | |||
The budget year-to-date for Operations was 61.2 million dollars for September while the actual cumulative expenditures through September totaled 53.3 million dollars. | |||
The budget year-to date for Maintenance was 20.8 million dollars for September while the actual cumulative expenditures through September totaled 15.1 million dollars. | |||
Although Operations and Maintenance are currently 13.6 million dollars under budget, a cost variances study from January through August 1990, predicts that Operations and Maintenance will- be approximately 8.7 million dollars under budget at year end 1990. | |||
Adverse Trends: None 1500- .. | |||
Documents Scheduled for Review x- Documents Reviewed | |||
+ Overdue Documents X 1200- U ND | |||
", 900- l bu l \ | |||
em - | |||
l \ | |||
re l \ i n 600- l \ | |||
0 t l \ ! : | |||
is l \ ! \ | |||
l \ | |||
300- l \\ | |||
n ; | |||
,e' \ l \' | |||
x 's , .... -g -4, , | |||
x [ y.N "h.N | |||
; f. 4"',,,,7 ~~Y "3 | |||
((_ | |||
Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 DOCUMENT REVIEW This indicator shows the number of biennial reviews completed during the reporting month, the number of biennial reviews scheduled for the reporting month, and the number of biennial reviews that are overdue. | |||
These document reviews are performed in-house and include Special Procedures, the Site Security Plan, Maintenance Proceddres, Preventive Maintenance Procedures, and the Operating Manual. | |||
During September there were 36 document reviews completed while 35 document reviews were scheduled. At the end of September, there were 41 document reviews overdue. The overdue document reviews at the end of September consisted primarily of maintenance documents. | |||
During the month of September there were 15 new or renamed documents reviewed. These new or renamed documents will need to be reviewed again in 1992. | |||
The high number of documents scheduled for review for the month of June 1990 was due to the high number of document reviews that were completed during the- month of June 1988. The reviews that were completed during June 1988 were due to be reviewed in June 1990. | |||
Adverse Trend: None 31 | |||
100- ; Diesel Generator No. 1 98; X- Diesel Generator No. 2 O- Fort Calhoun Goal 96- | |||
: o. . . . . e . . . . e . . . q . . . . s . . . . e . . . . o . . . . q. . . . . e . . . . .e . . . . q. . . . . e 94- .x- x x -x - -; :- -K -x X X- X - . l l p | |||
92-e r 90-C e 88- ^ | |||
n . | |||
t 86- GOOD 84-82-80 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 DG REllABILITY LAST 100 DEMANDS Diesel generator D 1 did not have a start and load failure during September 1990. Diesel generator D1 has a 93 percent reliability factor over the last 100 valid demands. | |||
Diesel generator D 2 did not have a start and load ftilure during September 1990. Diesel generator D2 has a 95 percent reliability factor over the last 100 valid demands. | |||
At the present time, the Fort Calhoun Station is exploring the possibilities of a program for improving the reliability of the Emergency Diesel Generators. | |||
The Fort Calhoun goal for the diesel generator reliability is 95%. D2 curre.ntly meets this goal over the last 100 demands on the unit. | |||
Adverse Trend: None | |||
+ Diesel Generator No. 1 | |||
-X Diesel Generator No. 2 G- Fort Calhoun Goal 100- l ; ; ; ; : | |||
95- 0-- - - - G --- -- D - --- + -- -- e--- - - - - e -- - - G - - - - a - - - - e - - - - G - - - - - e P | |||
e r | |||
C 90- , ; , | |||
n t | |||
A 85- GOOD 80 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 DG REllABillTY LAST 20 DEMANDS Diesel generator D 1 did not have a start and load-failure during September 1990. Diesel generator D 1 has a 90 percent reliability factor over the last 20 valid demands. | |||
Diesel generator D 2 did not have a start and load failure during September 1990. Diesel generator D 2 has a 95 percent reliability factor over the last 20 valid demands. | |||
At the present time, the Fort Calhoun Station is exploring the possibilities of a program for improving the reliability of the Emergency Diesel Generators. | |||
The fort Calhoun goal for the diesel generator reliability for the last 20 demands is set at 95%. Diesel D-2 presently meets this goal. | |||
Adverse Trend: None l | |||
l 400-M July 1990 | |||
' "9" 0 | |||
u I ISeptember 1990 300-l t | |||
a , | |||
n d | |||
i 200-9 = | |||
. me M gj W =r; O 100- kHi - | |||
@$ ifMW3 s ver am 0- - | |||
0-3 36 69 9-12 >12 Age in Months AGE OF OUTSTANDING MAINTENANCE WORK ORDERS (CORRECTIVE NON 0UTAGE) | |||
This indicator shows the age of corrective non-outage maintenance work orders (MWO's) remaining open at the end of the reporting month, idyytrseTrend: None 500-E July 1990 | |||
@ August 1990 El--- 1 ISeptember 1990 400 , | |||
l | |||
\ | |||
300-s we | |||
\ | |||
$ I | |||
$$ J@? @ | |||
200- S$$ $N l M3 22: | |||
. EN S$ | |||
w: mu | |||
;iul im an - | |||
100- Es tgi My | |||
. S ne: | |||
wa | |||
$S a:_a 35 am 9&E :E,C =5 Ed?E 0- | |||
" 5h - | |||
Total Open Total Open Open Open MW0s Open Safety High | |||
> 3 Months Safety Related MW0s Priority Old Related MW0s MW0s MW0s > 3 Months Old MAINTENANCE WORK ORDER BREAKDOWN (CORREC11VE NON-0UTAGE) | |||
This indicator shows the total number of corrective non-outage MW0's remaining open at the end of the reporting month, along with a breakdown by several key categories. | |||
Adverse Trend: None l | |||
l 1 | |||
*35- | |||
- Corrective Maintenance Backlog > 3 Months Old | |||
<>- Industry Upper Quartile , | |||
l 80- | |||
. , )1 60- / I P . | |||
o.._. o._ _o _ o. .4 - O - O --O - --O - -O O- O c 40 e | |||
n t - | |||
GOOD 20-t 0 | |||
Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 CORRECTIVE MAINTENANCE BACKLOG GREATER THAN 3 MONTHS OLD (NON 0VIAGE) | |||
This indicator shows the percentage of open corrective non outage maintenance work orders that are greater than three months old at the end of the reporting month. | |||
The percentage of open corrective non outat;c maintenance work orders that are greater thin three months old at the end of September wts reported as 56.7% | |||
The industry upper quartile value for corrective maintenance backlog greater than 3 months old is 45.8%. | |||
Adverse Trend: None | |||
- Ratio of Preventive to Total Maintenance | |||
+ Industry Upper Quartile 90- -G- Fort Calhoun Goal 80-70-P | |||
[ 60- p ---- o----- o- ---9 --- 9 ---- o-----o --.- y - ...g ---- o-.--.gf -- _o c . | |||
V' V~ V- 'V~ N 'V V V -V V- v- v e | |||
n 50-t . | |||
^ | |||
40-30 20 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 RATIO 0F PREVENTIVE TO TOTAL MAINTENANCE (NON 0UTAGE) | |||
The ratio of preventive to total maintenance indicator shows the ratio of completed non outage preventive maintenance to total completed non outage maintenance. | |||
The ratio of preventive to total maintenance at the Fort Calhoun Station decreased to 54,9% in September The low ratios in August and September were due to the increased involvement of maintenance in corrective maintenance activities associated with the two forced outages which occurred in August and September. | |||
The Fort Calhoun goal is to have a ratio of preventive to total maintenance greater than 60%. | |||
l The industry upper quartile value for the ratio of | |||
; preventive to total maintenance is 57.7%. | |||
Adverse Trend: None - Reason for trend is given above. | |||
SEP 41 L | |||
- Preventive Maintenance items Overdue 5- o- Industry Upper Quartile O- Fort Calhoun Goal 4-GOOD P 4 e 3-r C - | |||
e | |||
* 2- | |||
. c>. .q- o. o. .o C ---- e ---- G-----G-----o -----O s ----o---- O ---- O -----O ---- O [ | |||
~ | |||
O Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 EREVENTIVE MAINTENANCE ITEMS OVERDVE , | |||
The purpose of this indicator is to monitor progress in the administration and execution of preventive maintenance programs. A small percentage of preventive maintenance items overdue indicates a station commitment to the preventive maintenance program and an ability to plan, schedule, and perform preventive maintenance tasks as programs require. | |||
During September 1990, 917 PM items were completed. A total of 2 PM items were not completed within the allowable grace period. | |||
The fort Calhoun goal is to have less than 1.2% preventive maintenance items overdue. The industry upper quartile for preventive maintenance items overdue is 1.2%. The Fort Calhoun Station is currently performing in the industry upper quartile for this indicator. | |||
Adverse Trend: None SEP 41 38- | |||
1 40 Wi Total Control Room Instruments Out-of-Service | |||
<>- Industry Upper Quartile For Total Out-of-Service Instruments G- Fort Calhoun Goal for Total Out-of-Service Instruments 30- - | |||
I GOOD m$ 7-? | |||
Nn a N us | |||
* 4' ,,2 Ot - f'' .M br '1 q | |||
's eu 20- ~~0 cf E f .*' 05 ki rm s!$; Yn, 3 d ;,, 4 gj e 4 4 s" ;d on #' d Vj .,.4 a ft i*l ~~~;' d ' | |||
4 2i s ,' | |||
4 ij IM 3 sg 10- 7 | |||
~~~ | |||
7 y | |||
$ b p bi ~y ijq W b. . f$ b .. | |||
+f O~. .&r4uy 4 4y., | |||
4;;. wg :y ~4 c4 gyj tG y, ;pi. | |||
um | |||
,.p.7 . . .,4 -.. | |||
. ~4, g3 .. | |||
9% .m .._ | |||
4 ... ... | |||
4y, .. | |||
, 4, ,4, ... | |||
9;: | |||
79 ga! | |||
m %; y & +y: } | |||
7, A g+ y' | |||
~ ,- | |||
'Ag j | |||
3,9n +4 up j" | |||
py c ,p! | |||
s, 4r&g Y j | |||
? - ;Q;,g | |||
;p | |||
,.s f.g prp | |||
%%g q;;m; e %A #,, s % :tWi M3 e3.,) ' ch yw | |||
~" " | |||
24 M &g$ | |||
a &, | |||
"~ | |||
Ms'd g'(g M%q | |||
~ | |||
'~ J*6g1,e +- | |||
%4 | |||
* 0-Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 NUMBER OF OUT-OF SERVICL CONTROL ROOM INSTRUMENTS This indicator shows the number of out of service control room instruments, the industry upper quartile for this indicator, and the Fort Calhoun goal. | |||
There was a total of 23 out-of-service control room instruments at the end of August. | |||
The Fort Calhoun goal is to have less than 7 out of service control room instruments. | |||
The industry upper quartile value for the number of out-of-service control room instruments is 7. | |||
Adverse Trend: None 80- | |||
- Maintenance OvertimeI 12 Month Average G- Fort Calhoun Goal GOOD Y | |||
60- | |||
,0------O P , | |||
e ' | |||
'\ ~ | |||
g. | |||
40- N, c / | |||
e / \ . | |||
\, | |||
n , j t ; > | |||
& - - - - G-- --- G - -- - - O GF---- G--- -- O -- - - - O X b, 20- | |||
^w: | |||
0 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 MAINTENANCE OVERTIME The Maintenance Overtime Indicator monitors the ability to perform the desired maintenance activities with the allotted resources. | |||
Excessive overtime indicates insufficient resource allocation and can lead to errors due to fatigue. | |||
The percent of overtime hours with respect to normal hours was reported as 8.3% during the month of September 1990. The 12 month , | |||
average percentage of overtime hours with respect to normal hours was reported as 17.1%. | |||
The high percentage of overtime hours reported for the months of February 1990 through May 1990 was due to increased maintenance support associated with the 1990 Refueling Outage. The high percentage of overtime hours reported for August and September 1990 was due to maintenance activities associated with the 2 forced outages during these months. | |||
The Fort Calhoun goal for the percent of maintenance overtime hours worked has been set at 25% for non outage months and 50% for outage months. | |||
Adverse Trend: None | |||
-40 l | |||
20- 1 IOpenIR'sRelatedtotheUseofProcedures(Mainterance) | |||
E Closed IR's Itelated to the Use of Procedures (Maintenance) li Procedural Noncompliance IR's (Maintenance) | |||
N 15-u m | |||
b , | |||
e r | |||
o 10-f 88 I ~3 R | |||
e ., | |||
s ~ | |||
55 5 r | |||
33 | |||
~" | |||
33 l'i ' | |||
, 3 ~ | |||
3 l 22 e e h,1 3 | |||
d d ~Q1_ 1 11 3 1 g 40 s o 000 'B 'E BE FF]o yo oo[ loo 000 000 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE) | |||
This indicator shows the number of identified Maintenance Incidents Reports (IR's) that are related to the use of procedures, the number of closed IR's that are related to the use of procedures (includes IR's that were caused by procedural noncompliance), and the number of closed IR's that were caused by procedural noncompliance. | |||
It should be noted that the second and third columns will lag behind the first column until the IR's are closed. This reporting method is due to the process in which IR's receive category codes. | |||
IR's receive their category codes when they are closed. | |||
Adverse Trend: None SEP 15 & 44 | |||
900-Open MWO's G- Fort Calhoun Goal 800-o 700-Nf - | |||
u mM bW 600- & ---- G - -- - G - --- G - -- -G--- - G --- - e---- G ---- e ---- G --- --O | |||
\ | |||
e0 s, r' | |||
500- _ | |||
V 'o N | |||
400-300 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 MAINTENANCE WORK ORDER BACKLOG (CORRECTIVE NON 0UTAGE MAINTENANCE) | |||
The Maintenance Work Order Backlog (Corrective Non-Outage Maintenance) Indicator has been changed The goal for this indicator has been changed from 600 open corrective non-outage MW0's to 500 open corrective non-outage MWO's. | |||
This indicator shows the number of corrective non-outage maintenance work orders that are open | |||
.at the end of the reporting month. | |||
At the end of September 1990, .there were 406 corrective non-outage maintenance work orders remaining open. | |||
The goal for this indicator is to have less than 500 corrective non-outage maintenance work orders remaining open. | |||
Adverse Trend: None SEP 36 l | |||
// c | |||
5- 1 Number of Missed ST's Resulting in LER's 4-N 3' u | |||
m b | |||
e r 2-1- | |||
0 0 0 0 0 0 0 0 0 0 0 0 | |||
Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 NUMBER OF MISSED SURVEILLANCE TESIS RESULTING IN LICENSEE EVENT REPORTS 1 This indicator shows the number of missed L Surveillance Tests (ST's) that result in Licensee Event Reports-(LER's) during the L reporting month-. | |||
During the month of September 1990, there were no missed ST's that resulted in LER's. | |||
Adverse Trendi None SEP 60 & 61 1 35-I ITotal NPRDS Component Failures 30- e Confirmed NPRDS Component Failures 25-N uf ma 20- 7 D'I b1 ., | |||
g P ru hf h@ih [$ e i; ; | |||
r 15- % j$ | |||
oe fs | |||
;6 e M g f g _7 10-m i | |||
,j IE | |||
?"3 i | |||
%p!{ [ | |||
% $j$f | |||
$i y % | |||
[' | |||
5- [" | |||
i1 | |||
!!If | |||
.$j h | |||
ji Yk | |||
$3 f | |||
_L | |||
.[T ij g | |||
]!A 12 B; b $ $, $ As M gM # | |||
Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 NUMBER OF NUCLEAR PLANT REllABILITY DATA SYSTEMS (NPRDS) | |||
REPORTABLE FAILURES | |||
'This indicator shows the total number of NPRDS component failures and the number of confirmed NPRDS component failures. The total number of NPRDS component failures is based upon the number of failure reports sent to INP0. The number of confirmed NPRDS component failures is based upon the number of failure reports that have been accepted by INPO. The difference of these two figures .is the number of failure reports still under review by INP0. | |||
During September 1990, there was a total of zero confirmed NPRDS component failures. , | |||
Adverse Trend: None IS- + Components With More Than One failure | |||
-X- Components With More Than Two Failures N | |||
i u m ' | |||
b GOOD 10- c o | |||
f C | |||
o | |||
/ | |||
m o p | |||
b 5-o n | |||
,/ ,X. , ~,, ' y_ _ _ _ _ _ y_ _ _ _ _ _y_ _ _ _ _ ,g n * ,x' '' x '~ | |||
t s X' 'X-~~~~'X-~~~- M-~~~~'X 0 | |||
l Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 i-MAINTENANCE EFFECTIVENESS The Maintenance Effectiveness Indicator was developed following guidelines set forth by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (NRC/AE0D). The NRC/AE0D is currently developing and verifying a maintenance effectiveness indicator using the Nuclear Plant Reliability Data System (NPRDS) component failures. | |||
This indicator shows the number of NPRDS components with more than one failure during the last twelve months and the number of NPRDS components with more than two failures during the last twelve months. The number of NPRDS components with more than two failures in a twelve-month period should indicate the effectiveness of plant maintenance. | |||
= During September 1990, there were 6 NPRDS components with more than one failure and 2 NPRDS componer,ts with more than two failures. The tag numbers of the : NPRDS components with more than two failures in the last twelve months include: CH-1B and CH-10. | |||
Adverse Trend: None | |||
20- - Check Valve failure Rate a Industry Check Valve Failure Rate o 15-F a GOOD 3 | |||
\' | |||
M ie r1n 10- | |||
'1t i | |||
p oH e**u r r 5-s 3 -. . . g. _ -3 6- 6 -f -6 0 | |||
Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov 1989 1990 CHECK VALVE FAllVRE RATE This indicator shows the Fort Calhoun check valve failure rate and the industry check valve failure rate. | |||
The data for the industry check valve failure rate is three months behind the Performance Indicators Report reporting month due to the time involved in collecting and processing the data. | |||
The industry failure rate is based upon failures that have occurred in-the previous 18 month interval. i For' June 1990, the Fort Calhoun ' Station reported a check valve failure rate 'of 7.38E-6 while the industry reported a failure rate of 2.54E-6. At the end of September, the Fort Calhoun Station reported a check valve failure rate of 4.01E-6. At this present time, the check valve failure rate for Fort Calhoun is higher than the industry check valve failure rate. The reason for the high check valve failure rate is that the plant is performing maintenance on check valves which have not been tested for failures bei're. As time goes on, the check valve failure rate is expected to decrease due to the fact that the check valves are now being maintained through the Check Valve Program. | |||
Adverse Trend: None SEP 43 | |||
- Secondary System CPI | |||
+ ec n ary System UI Umn 1.5- | |||
-O- Industry Upper Quartile l- 4----+----4----+---+---+---+----+----+----+----&----+ | |||
~ | |||
GOOD | |||
'38 .5- + # | |||
. N | |||
~ | |||
o__o._..o... .o -v~ 7-~O ~O^-O~~O~~O~~O O '" | |||
0 | |||
'88 '89 Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug 1989 1990 1000 - Hours Chemistry is Outside OG Guidelines 757.7 800- | |||
,y n f o 600-F$ GOOD u - | |||
359 'l r 400 + | |||
w n s , | |||
*^ | |||
M 200-h[i | |||
'87 '88 Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug 1989 1990 SECONDARY SYSTEM CHEMISTRY The top graph, Secondary System Chemistry Performance Index (CPI), is calculated using three parameters. The three parameters used include; cation conductivity in steam generator blowdown, sodium in steam generator blowdown, and condensate pump discharge dissolved oxygen. The CPI was reported as 0.56 for the. month of August. The CPI values for June, July, and August are high | |||
'due to startup after the 1990 Refueling Outage, various fluctuations in power which have occurred, and a forced outage in August. The industry upper quartile value for this indicator was 0.16 for August 1989 through December 1989. The CPI industry value then changed to 0.24 for 1990. | |||
The bottom graph, ligsrs Chemistry is Outside Owners Guidelines, tracks the total hours of 13 parameters exceeding guidelines during power operation. The number of hours outside. owners group guidelines was reported as 0.1% for the month of August. | |||
The above two chemistry indicators are one month behind the reporting period due to the time needed for data collection and evaluation of the station chemistry data. | |||
Adverse Trends: None 10- - Primary System Chemistry Out of Limit 8-P s. | |||
GOOD | |||
. + | |||
n t 4-1.9 2- | |||
'do fh , | |||
0 .:' | |||
0 | |||
'88 '89 Sep 0'ct Nov Dec Jan Feb Mar Apr May Jun Jul A'u's 1989 1990 i | |||
PRIMARY SYSTEM CHEMISTRY PERCENT OF HOURS OUT OF LIMIT The Primary System Chemistry - Percent of Hours Out of Limit- indicator tracks the - primary system chemistry performance by monitoring six key chemistry parameters. | |||
The Primary System Chemistry Percent of Hours Out of Limit was reported as 0.0% for the month of August. | |||
The high percent of- hours out of limit for the primary system during June and July was due to | |||
-startup after the 1990 Refueling Outage and various power fluctuations which occurred during June and July.100% equates to all six parameters being out of limit for the month. | |||
Adverse Trend: None | |||
- Auxiliary System Chemistry Out Of Limit | |||
-O- Industry Upper Quartile 40- , | |||
- GOOD | |||
+ | |||
30- | |||
~ | |||
H o | |||
u 20-r s | |||
10-0 0 0 -O~4 ~O ~ ~4 4 | |||
'88 '89 S'ep Oct Nov Dec Jan Feb Mkr Ahr Miy Jun Jul Ah 1989 1990 AUXILIARY SYSTEM (CCW) CHEMISTRY HOURS OUTSIDE STATION LIMITS The Auxiliary System Chemistry Hours Outside Station Limits indicator tracks the monthly ~ | |||
hours that the Component Cooling Water (CCW) system is outside the station chemistry limit. The above chemistry indicator is one month behind the reporting period due to the time needed for data collection and evaluation of the chemistry data for the station. | |||
The auxiliary system chemistry hours outside station limits was reported as zero for the month of August. | |||
The industry upper quartile value for auxiliary systems ' chemistry hours outside station limits is 2.6 hours. The Fort Calhoun Station is currently .- performing in the upper quartile of all nuclear power plants for this indicator. | |||
Adverse Trend: None . | |||
ggg Number of Out-of-Service Instruments 20 -G- Fort Calhoun Goal | |||
$$5 16- a:M ___m ._ | |||
m a e ra;n :== = a=m Nn - Y N 5 b u3 M MM | |||
=== | |||
N$ [dj M EE rz: = = - gum sgg 13 3 m t 12 #=m 55 "*" | |||
br M*5 E5 -- | |||
E2 I*"" M=" === | |||
5N3 e ?" 5EE #= ==' D 'M | |||
= === 5 :: 55 rm UUi5 55 | |||
,= | |||
NE 55 m ;; | |||
ny | |||
=5 N %% | |||
=2; AYIE a== | |||
, m t== =: | |||
o" EN E ' E= 2 * = | |||
A :--- | |||
f ~_fi M 21 $22 E;d 5t2 X 25 = ama X?2 ++-e | |||
- 35 * ==as a== MM-v?X; RQX-gq3-- EWr EDE gge-Kg -ier;i 4-f~~ Efd 5M0 $7$3 Es =LT=1~ F55 $9] a =-i g, | |||
;gg g_:ggg 3% e=a ;;3 ;; - g;;;; | |||
Eam 555 iAd | |||
=== ;;;; 77=- | |||
$%PiGM mx8 21=+; =-. | |||
[*M ?33] M _1 i!j$ ;= = if5 | |||
. _ _ = | |||
= 2. = | |||
ma; | |||
:= | |||
Ej == h=55 | |||
;=aw | |||
= =~ | |||
e== == iiM z RJi = Mi:2 ::a ems ==W :=m === | |||
## ""* ## ;^ = "" *"" = = = == - - | |||
0 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 IN-LINE CHEMISTRY INSTRUMENTS OUT-OF-SERVICE This indicator shows the total number of in-line chemistry system instruments that are out-of-service at the end of 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 September there were a total of 7 in-line chemistry instruments that were out-of-service. Four of these instruments were from the Secondary System and three were from PASS. | |||
The Fort Calhoun goal for the number of in-line chemistry system instruments that are out-of-service has been set at 6.. Six out-of-service chemistry instruments make up 10% | |||
of all the chemistry instruments which are counted for this indicator. | |||
Adverse Trend: None 10000- I ' Total Waste Produced | |||
- Federal and State Limit 8000-K i0 1I 6000-W 9 | |||
ra a s mt 4000 s | |||
e 2000- | |||
' ' ' ' I I ' ' | |||
0-Oct Nov Dec Jein Feb Mar Apr May Jun Jul Aug Sep 1989 1990 M7ARD0VS WASTE PRODUCED This indicator shows the total amount of hazardous waste produced by Fort Calhoun each month. This hazardous waste consists of non-halogenated hazardous waste, halogenated hazardous waste, and other hazardous waste produced. | |||
During the month of September, 0.0 kilograms of | |||
- non-halogenated hazardous waste was produced, 9.9 kilograms of halogenated hazardous waste was produced, and 0.0 kilograms of other hazardous waste was produced. | |||
The large . amount of hazardous waste produced during the month of October 1990 was caused by a mercury spill at the sulfuric acid tank located on the east side of the~ service building. | |||
Adverse Trend: None 5000; I IMonth M Quarter OPPD Limit | |||
.1 Year 4000-3000-m R ~ | |||
E M | |||
2000-1000-e e | |||
0 September 1990 MAXIMVM INDIVIDVAL RADIATION EXPOSURE During September 1990, an individual accumulated 550 mrem which was the highest individual exposure for the month. | |||
The maximum individual exposure to date for the third quarter of 1990 has been 794 mrem. | |||
The maximum . individual exposure reported to date for 1990-has been 2,090 mrem. | |||
The high maximum individual exposure reported so far for the 1990 year to date value was a contract generator jumper. | |||
The maximum accumulated 1989 individual exposure was 1,165 mrem, received by a Health Physicist. | |||
The OPPD limit for the maximum yearly individual radiation exposure is 4,500 mrem / year'. | |||
Adverse Trend: None 1 | |||
l 6 Monthly Contaminations | |||
- Cumulative Contaminations 500) | |||
O fort Calhoun Goal i l< Industry Upper Quartile 400. | |||
357 P | |||
- e R) r fy s 300- GOOD gj o et n + | |||
P n d | |||
fY e | |||
I 200- | |||
~157 C- - - - O - - - & - - o - - - & - - - O - - - O - -- -O- - - - O - - - O - - - -O t $j "~;"1 | |||
- - ~- < :. O O- Q Q O O O g | |||
g , | |||
100- | |||
$Nh m8 l _,V1 f | |||
a p - l,_ | |||
9 L '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec | |||
! 1990 l | |||
l TOTAL SKIN AND CLOTHING CONTAMINATIONS There was a total of 2 skin and clothing contamination reported I 'for the Fort Calhoun Station during September,1990. There has been a total of 212 skin and clothing contaminations so far in 1990. The high number of skin and clothing contaminations which occurred during the months of March and April 1990 were related to- increased activity in the- Radiation Controlled Area (RCA) during the 1990 Refueling Outage. | |||
There was a total of 157 skin and clothing contaminations in 1989. | |||
The 1990 goal for. skin and clothing is 150 contaminations. This 1990 goal of 150 contaminations includes a Fort Calhoun goal of 23 skin contaminations. | |||
The industry upper quartile value for total skin and clothing contaminations is 129 per unit ennually. | |||
Adverse Trend: None SEP 15 & 54 Decontaminated Auxiliary Building G- Fort Calhoun Goal 100-n._- -_n.----O . ,,G---- a - ^ O 80-P 60-c e - | |||
n 40-A GOOD 20-0 - | |||
Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 DECONTAMINATED AVXIllARY BUllDING This graph shows the percentage of the auxiliary building which is decontaminated (clean) based on the total square footage and a Fort Calhoun goal of 85% | |||
decontaminated auxiliary building (non-outage months) and a goal of 75% | |||
decontaminated auxiliary building (outage months). | |||
As of September 30, 1990, 84.5% of the total square footage of the auxiliary building was decontaminated. | |||
Adverse Trend: None SEP 54 20- | |||
>.m Number of Identified PRWP's N | |||
u 15-m b | |||
e . | |||
r 10-P R | |||
7 W , | |||
p s 5- ?@ | |||
3 m: | |||
'd 2 2 ,,l gg ?' ;f 1 1 1 0 m p. gj [g;j o p gj o Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 RADIOLOGICAL WORK PRACTICES PROGRAM The Radiological Work Practices Program Indicator shows the number of Poor Radiological Work Practices (PRWP's) which were identified during the reporting month. | |||
The number of PRWP's which are identified each month should indirectly provide a means to qualitatively assess supervisor accountability for their workers' radiological performance. | |||
During the month of September 1990, zero PRWP's were identified. | |||
Adverse Trend: None SEP 52 75 I I Total Number of Hot Spots l se Number of Additional Hot Spots Identified l | |||
NH uo 50- - - | |||
_ c-- | |||
mt b | |||
es rp - | |||
o ot fs 25-0 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1990 1991 NUMBER OF HOT SPOTS The Number of Hot Spots Indicator has been changed to include the number of additional hot spots which are identified during the reporting month. | |||
This indicator shows the total number of hot spots which have been identified to exist in the Fort Calhoun Station and have been documented through the use of a hot spot identification sheet. A hot spot is defined as a small localized source of high radiation. A hot spot occurs when the contact dose rate of an item or piece of equipment is at least 5 times the General Area dose rate and the item i or piece of equipment's dose rate is equal to or greater than 100 mrem / hour. | |||
l- | |||
! - At the end of September, 50 hot spots were identified and documented to exist in the Fort Calhoun Station. During the month of September, one- additional hot spot was identified to exist in the Fort Calhoun | |||
! Station. | |||
The Station ALARA committee established a goal to eliminate at least 5 hot spots during 1990. The Fort Calhoun Station has exceeded this goal. | |||
l Adverse Trend: None l | |||
l | |||
I IMonthly Radioactive Gas Discharged | |||
- Cumulative Radioactive Gas Discharged G- Cumulative Goal 785 800-GOOD C 600-u r | |||
i e | |||
p i s 400-o---- o --- o--..o ._- e._. .g._ _ e... G- - - -O ---G-- --&--- O | |||
; ) | |||
] | |||
4 k -- | |||
164 200-1 l | |||
' - x YD$2 0 F' ' ' | |||
'88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 GASE0US RADI0 ACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT The gaseous radioactive waste being i discharged to the environment is shown for January 1990 through June 1990. A total of l 261 curies have been released to the environment from Janutry through June of 1990. 'The Fort Calhoun Station goal is 360 curies for this indicator. | |||
The high value of gaseous radioactive waste that .was released to the environment during the month of February 1990 was due to containment purge associated with the 1990 Refueling Outage. | |||
The gaseous radioactive waste being discharged to the environment is calculated every six months. | |||
Adverse Trend: None I ! Monthly Radioactive Liquid Discharged | |||
- Cumulative Radioactive Liquid Discharged | |||
-G- Cumulative Goal 228 231 300-228 | |||
-. o ..g..e... e...o...o..e ..e ..s..s-- o-.. o gg u 200-h da | |||
,[ J s e j G000 | |||
$5 i s 100- 4' WY . | |||
n dn | |||
'87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 20000-Ty h | |||
15000-G u | |||
a s 10000-aj n | |||
d s | |||
3 5000-f 0 | |||
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 LIOUID RADI0 ACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT The liquid radioactive waste being discharged to the environment is shown for the months of January 1990 thro"gh June 1990. The liquid radioactive waste that .was discharged to the envir]nment from all sources totaled 55 curies from January- through June 1990. The Fort Calhoun Station goal for 1990 is 256 curies. | |||
The bottom graph shows the volume of liquid radioactive waste that has been released from the radioactive waste monitor tanks and steam generators. The volume of liquid radioactive waste discharged to the environment from the radioactive waste monitor tanks and the steam generators totaled 11.6 million gallons from January.through June 1990. | |||
The liquid radioactive waste that was released to the environment includes liquid released- from the steam generators due toithe fact that radioisotopes were. detected in the steam generator blowdown. | |||
The liquid radioactive waste being discharged to the environment is calculated every six months. | |||
Adverse Trend: None 100' (3 Number of Loggable/ Reportable Incidents N-80- 77 m | |||
b B&W^ | |||
e | |||
- J '1'1L | |||
't r ?$y g y o "t; | |||
" A f }' m 5 | |||
1 | |||
" 40- } | |||
; a 1 Y d d - | |||
e ; { | |||
i' i nt 20- y s g ; | |||
, , 0 _ . . | |||
0 0 O | |||
LOV Badges Escort System Key Access failures Control Control August 1990 LOGGABLE/ REPORTABLE INCIDENTS (SECURITY) | |||
The Loggable/ Reportable Incidents- (Security) Indicator shows the total number of loggable/ reportable incidents concerning Licensee Designated Vehicles (LDV's), security badges, security key control, escorting, access control, and security system failures for the reporting month. | |||
During the month of September 1990, there were 80 loggable/ reportable incidents identified. Security system failures accounted for 77 of the loggable/ reportable incidents (96%) reported this month. CCTV failures accounted for 57% of the system failures during the month of September 1990. The majority of these failures were due to environmental conditions (sunspots and shadows) which occur on an almost daily basis. | |||
Adverse Trend: None SEP 58 | |||
y Licensee Designated Vehicles (LDV's) llll. Security i>adges , | |||
i l Security Key Control l Escorting Access Control Security System failures LDV 1% Badges 3% | |||
f f A s | |||
i N. | |||
i I | |||
System Failures 96's | |||
.\. : | |||
'z 'x | |||
~ | |||
SECVRITY INCIDENT BREAKDOWN The Security Incident Breakdown Indicator shows the percentage of incidents concerning the following items for the reporting month. These items include: Licensee Designated Vehicles (LDV's), security badges, security key control, escorting, access control, and security system failures. | |||
Security items ,_thenber of incidents SEP 193Q AUG 1990 Licensee Designated Vehicles (LDV's) 1 1 Security Badges 2 5 Security Key Control 0 0 Escorting 0 1 0 0 Access Control Security System Failures 77 59 Total 80 66 Adverse Trend: None SEP 58 t . _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ . _ . . _ | |||
50-40 H 40-u m | |||
b e | |||
31 30-o f | |||
f a 20 i | |||
1 u | |||
r 10-3 2 | |||
0 - | |||
I I' ' | |||
Alarm System CCTV Computer Terminal Door Card Reader SECURITY SYSTEM FAILURES The Security System Failures Indicator shows the number of incidents concerning the following items for the reporting month. These items include: alarm system failures, CCTV failures, security computer failures, terminal failures, door equipment failures, and card reader failures. | |||
System Failures Number of Incidents SEP 90 AUG 90 Alarm Systems 31 22 CCTV 40 23 Computer 2 3 < | |||
Terminal 1 4 Door Equipment 3 6 Card Reader 0 1 l Total 77 59 Adverse Trend: None SEP 58 l | |||
15- - Amount of Work On Hold Awaiting Parts 12-GOOD P 9- + | |||
e c - | |||
e n | |||
t 6-3- | |||
0 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 , | |||
AMOUNT OF WORK ON HOLD AWAITING PARTS (NON-0UTAGE) | |||
This procurement indicator displays the amount of open, non outage, maintenance items that are. on hold- awaiting parts, to the total amount of open, non-outage, maintenance items, expressed as a percentage. | |||
The percentage of work on hold awaiting parts increased to 3.9% in September. | |||
As of September 30, 1990, there were a total of 939 open, non-outage, maintenance items with 37 of these items on hold awaiting parts. | |||
Adverse Trend: None i | |||
l l | |||
12- | |||
- Spare Parts Inventory Value M | |||
i | |||
) | |||
o 10-n s | |||
o ~ | |||
f 1 | |||
a r | |||
8-s f | |||
s l | |||
6 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep | |||
! 1989 1990 l | |||
l l | |||
l l SPARE PARTS INVENTORY VALV.E 1 | |||
The spare parts inventory value at the Fort i Calhoun Station at the end of September 1990 was reported as $9,720,256. | |||
Adverse Trend: None 750-T | |||
~ | |||
- Spare Parts issued I h l 0 | |||
;; 600-S I | |||
a - | |||
l n l d 450-s 0 | |||
I 300-D o | |||
1 150-r s | |||
0 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 SPARE PARTS ISSUED The value of the spare parts issued during September 1990, totaled $129,980. | |||
Adverse Trend: None | |||
- Inventory Accuracy 100-95< | |||
P e | |||
r e | |||
e 90-n t | |||
85-l l .. | |||
80 t Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 INVENTORY ACCURACY The Inventory Accuracy Indicator has been changed. | |||
The percentage of the inventory accuracy is now shown l- in line graph form. Previously, this percentage was | |||
) shown in column graph form. | |||
This indicator shows the accuracy of the actual parts count for the warehouse compared to the counts contained in the MMIS computer system for the , | |||
reporting month, i During September, 463 di fferent line items were L counted in the warehouse. Of the 463 line items counted 10 items needed count adjustments. The | |||
' inventory accuracy for the month of September was reported as 98%. | |||
Adverse Trend: None p | |||
5- - Pick Tickets With Parts Not Available , | |||
l 1 | |||
1 4- l P | |||
pi ec j rk 3 C | |||
eT ni tc k 2-oe ft . | |||
s 1-0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 STOCK 0VT RATE This indicator shows the percentage of the number of Pick Tickets generated with no parts available during the reporting month. | |||
During the month of September, a total of 852 Pick Tickets were generated. Of the 852 Pick Tickets generated, one Pick Ticket was generated with no , | |||
parts available. | |||
Adverse Trend: None 1500 O Total Receipts Spare Parts Receipts | |||
-O' Standard Stores Receipts | |||
~ | |||
'' Direct Charge Receipts 1200-N R | |||
u e 900-b'c e | |||
p ' | |||
O t 600- , | |||
s f , | |||
y e 300- O | |||
/ | |||
' g ,... -l. r - --Q '. Y | |||
,. K h . ''['~ ~.6 | |||
.> 6 O -o 0 | |||
Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan 1990 1991 WAREHOUSE RECEIPTS This indicator shows the total number of warehouse receipts, the number of spare parts receipts, the number of standard stores receipts, and the number of direct charge receipts during the reporting month. | |||
During September the warehouse received a total of 575 receipts. Of the 575 receipts received, 157 were spare parts receipts, 95 were standard stores receipts, and 323 were direct charge receipts. | |||
Adverse Trend: None | |||
4000- O Total Issues 6- Spare Parts Issues O Standard Stores Issues | |||
* Direct Charge Issues 3000-N ga s | |||
s e 2000-u r | |||
O. | |||
o | |||
* f | |||
'O -O 1000- a O | |||
. [& ,,, | |||
O -' O g g...._f -6 0 | |||
Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan 1990 1991 WAREHOUSE ISSUES This indicator shows the total number of warehouse issues, the number of spare parts issues, the number of standard stores issues, and the number direct charge issues for the reporting month. | |||
During September the warehouse completed a total of 1,178 issues. Of the- 1,178 issues completed, 235 were sparo parts issues, 685 were standard stores issues, and 258 were direct charge issues. | |||
Adverse Trend: None | |||
80- -O- Total Returns Spare Parts Returns | |||
. O Standard Stores Returns H- Direct Charge Returns 60-T Po et . | |||
c | |||
* 40-n1 ,a ts s O'.- | |||
ou ' | |||
fe .b -, , | |||
20 , | |||
l N, l l '6 o B- / | |||
O o 9.O - | |||
0 feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan 1990 1991 WAREHOUSE RETURNS The Warehouse Returns indicator shows the percentage of the total number of warehuuse returns, the number of spare parts returns, the number of standard stores returns, and the number of direct charge returns compared to the total number of warehouse issues during the reporting month. | |||
During the month of September there were a total of 1,178 warehouse issues. Of the 1,178 issues, there were 534 total returns. These returns consisted of 45T' spare parts returns and 82 standard stores returns. | |||
Adverse Trend: None | |||
25- 1 IJuly 1990 9 August 1990 : | |||
September 1990 H 20 a | |||
t e | |||
Nr u i 15- ' | |||
ma b1 , | |||
e rR ;_,. | |||
e 10- V4 oq di? | |||
fu . | |||
e s | |||
+' I t 5-5 - | |||
$3l | |||
.; e MM 0 --- -- -- E b 0-5 6-10 11-15 16-20 21-30 >30 Age in Days MATERIAL RE0 VESTS AWAITING APPROVAL This indicator shows the number of material requests awaiting approval at the end of the reporting month broken down into their age by days. | |||
At the end of September,16 material requests were awaiting approval. | |||
Adverse Trend: None | |||
~70- | |||
1 l | |||
l | |||
- Percentage of Total Purchases that are Expedited 1.5-P e | |||
r c l-e n | |||
t | |||
.5-0 - | |||
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 EXPEDITED PURCHASES This indicator shows the percentage of expedited purchases compared to the total number of purchase orders generated during the reporting month. | |||
6 i During September, there was a total of l 223 purchase orders generated. Of the 223 I purchase orders generated, there was one expedited purchase. | |||
Adverse Trend: None l | |||
l l | |||
71- | |||
l l | |||
150-I IJuly 1990 m August 1990 l . | |||
i September 1990 I 120- | |||
!i a | |||
, N 3 | |||
, $n90-V | |||
! b e] | |||
C . | |||
1 | |||
) o e@ ,{- j fs ny; | |||
$(;'ij l 30- jy _ | |||
\ | |||
a E dir. | |||
~ | |||
0 --- - M *' | |||
Shelf Life CQE Miscellaneous LNyllCE BREAKDOWN This indicator simws the number of invoices that are on hold at the end of the reporting month due to shelf life, CQE, and miscellaneous reasons. | |||
At the end of September 4 invoices were on hold due to shelf life reasons, 84 invoices were on hold due to CQE reasons, and 70 invoices were on hold . | |||
due to miscellaneous reasons. | |||
Adverse Trend: None | |||
10b - Percentage of Material Requests for Issues with the Request Date the same as the Need Date 80- | |||
- = | |||
z | |||
[60-r C | |||
e , | |||
n 40-t 20-0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 MATERIAL RE0 VEST PLANNING This indicator shows the percent of material requests (MR's) for issues with their request date the same as their need date compared to the total number of MR's for issues for the reportin9 month. | |||
During the month of September, a total of 852 MR's were received by the warehouse. Of the 852 total MR's received by the l warehouse, 569 % 's were for issues with l | |||
their request date the same as their need date. | |||
Adverse Trend: None i | |||
l l | |||
700- - Total Modification Packages Open 600-500-425 425 - | |||
7 y - | |||
384 & 400-s L | |||
!Y,, d f;g 3, ]$ 300- | |||
$$ k )hf) 200 | |||
'87 '88 '89 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 OUTSTANDING MODIFICATIONS The total number of outstanding modifications decreased by one during the month of September. | |||
CATEGORY AUG 90 SEP 90 Form FC ll33 Backlog /In Progress 15 12 Mod Requests Being Reviewed 108 141 Design Engr. Backlog /In Progress 113 84 Construction Backlog /In Progress 42 44 Desian Enar. Uodate Backloa/In Proaress _62 _51 Total 338 337 As of the end of September 49 additional modification requests have been issued this year and 12 modification requests have been cancelled. The Nuclear Projects Review Committee (NPRC) has completed 110 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) has completed 105 backlog modification request reviews this year. | |||
The number of reviews completed is high due to the fact that some of these requests were reviewed more than once. | |||
Adverse Trend: None 100- Total Temporary Modifications M - | |||
e- Fort Calhoun Goal | |||
! Nd 80-ui - | |||
[ 60-ec - | |||
ra 40- | |||
; t , | |||
20- | |||
~ ~ * ~ ~ O '~ 3 .... . .... . .... . .... . .... e 0 | |||
Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 July 1990 M | |||
o 8- W August 1990 Nd I ISeptember 1990 ui 6-mi y l} | |||
bi j ec 4- N U c! t;;r I | |||
ra :" 5 , | |||
t nits ?? <= w oi 2- ?? 7N h5 5 @ | |||
fo NP di $ $ $M n | |||
0- | |||
= | |||
== - - | |||
!G is foi 3 | |||
0-3 3-6 6-9 9-12 > 12 Age in Months TEMPORARY MODH ICATIONS (EXCLUDINGSCAFFOLDING) | |||
The top graph shows the total number of temporary modifications installed in the Fort Calhoun Station and a Fort Calhoun goal. | |||
The number of electrical temporary modifications and the number of mechanical temporary modifications have been deleted from this indicator because the Plant no longer categorizes temporary modifications in this manner. | |||
I f At the end of September, there was a total of 18 temporary l modifications installed in the Fort Calhoun Station. The Fort l Calhoun goal for the total number of installed temporary l | |||
modifications is less than 15 installed temporary modifications. | |||
I l | |||
The bottom graph, e.ge of Temocrary Modifications, displays the age of all temporary modifications by months installed in the plant. | |||
Adverse Trend: None SEP 62 & 71 1 | |||
50- I IOpen EAR'5 EAR's Closed During the Reporting Month | |||
- EAR's > 30 Days Past Current Schedule 40-o l Nf 30-u mE . | |||
bA eR r's 20-I 10-0- - | |||
Priority 1 Priority 2 Priority 3 Priority 4 September 1990 ENGINEERING ASSISTANCE RLQE11 PRIORITY BREAKDOWN This indicator shows the number of open and closed Engineering Assistance Requests (EAR's) broken down into priorities at the end of the reporting month. Along with the priority breakdown, the number of EAR's remaining open 30 days past the current schedule are shown for each priority category. | |||
>30 Days Past Priority Open Closed Current Schedule M 629 len M 829 la M enn la Priority 1 6 6 9 1 4 4 3 4 5 Priority 2 12 13 19 0 8 9 4 6 5 Priority 3 30 29 26 0 7 11 11 16 15 Priority 4 21 35 40 1 8 11 10 12 9 Total 69 83 94 2 27 35 28 38 34 Adverse Trend: The number of open EAR's has increased from 59 in May 1990 to 94 in September 1990. The major reason for the increase in the number of open EAR's is the result of discrepancies between old procedures and the new procedures which are being upgraded by the Procedures Upgrade Project. | |||
SEP 62 1 | |||
l 150- -G- Totol ECN's Open | |||
+(- ECN's Opened During the Month o ECN's Completed During the Month 120-N u | |||
m | |||
/g - -(N b | |||
e 90- 'y o | |||
g\ / | |||
'\ | |||
/\\ , | |||
f - | |||
l '\ | |||
60- oj '\ | |||
,K ~ .. | |||
E C Q , , | |||
q j ., \ | |||
.g g | |||
N | |||
~, , | |||
y, ,' , r, | |||
, x ~ "U - | |||
5 g, x . . . _ .>! ',y ' 's N | |||
o 'y ' > | |||
o 0 | |||
Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 ENGINEERING CHANGE NOTICE STATUS The indicator shows the total number of open Engineering Change Notices (ECN's), the number of ECN's opened during the reporting month, and the number of ECN's completed during the reporting month. | |||
At the end of September 1990, there was a total of 87 open ECN's. During the month of September, 19 ECN's were opened, and 29 ECN's were completed. | |||
Adverse Trend: None SEP 62 300- 1 IDocument Change M Substitute Replacement Item Facility Changes 250-228 200- 196 MEi | |||
$N$ | |||
150-- ES$ | |||
ud 11M 100-raa | |||
. n$ | |||
gy 50- AM 29 24 NN; N | |||
Xh 7 7 14 8 7 0- ' I Total ECN's ECN's Opened ECN's Completed Total ECN's Open During the Month During the Month Received ENGINEERING CHANGE NOTICE BREAKDOWN This indicator breaks down the total number of Engineering Char.ge Notices (ECN's) that remain open at the end of the reporting month, the number of ECN's that were opened during the reporting month, the number of ECN's that were completed during the reporting month, and the number of ECN's received by Design Engineering during the reporting month into several categories. These categories include: | |||
ECN's requiring a document change to complete, ECN's requiring substitute replacement items to complete, and ECN's requiring facility changes to complete. | |||
l Total Open Opened Completed Received l | |||
Document Changes 34 7 14 228 l | |||
Substitute Replacement 29 5 8 196 Facility Changes 24 7 7 102 Adverse Trend: None SEP 62 5- E]1990RecordableInjuryFrequencyRate | |||
+- 1989 Recordable Injury Frequency Rate i 4.5- I | |||
-+- 5 Year Average Recordable Injury Frequency Rate 4-1 3.5-GOOD 3-R - , | |||
O a 2.5- , | |||
e 4's ' | |||
,.+.,' | |||
2- \ , | |||
. 's s ,- | |||
p' ~ , '+ . x 1.5-N,, +...., | |||
,....A.,,,......+..._+....+ | |||
/ ~"T" l- ,, p y 3 | |||
.5- | |||
~ | |||
[ | |||
j/ \, - | |||
h 3 j, 7 ([ I, jy; g ^'_ ?[. O,U ' plql b, %* ,' , | |||
^ | |||
A* ' | |||
'" 'O' 0 >~ | |||
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec RECORDABLE INJVRY CASES FRE0VENCY RATE This indicator shows the monthly recordable injury cases frequency rate in column form. The above graph also includes the 1989 recordable injury cases frequency rate and the Fort Calhoun Station 5 year avera9e recordable injury cases frequency rate. | |||
A recordable injury case is reported if Nuclear Operations Division personnel are injured on the job and require corrective medical treatment. The recordable cases frequency rate is computed on a year-to date basis. There were zero recordable injury cases reported during the month of September. There has been a total of 5 recordable injury cases so far in 1990. | |||
There were eleven recordable cases reported in 1989, eleven reported in 1988, and eight reported in 1987. The year end recordable injury frequency rates for 1987, 1988, and 1989 were 2.5, 2.6, and 2.2 respectively. | |||
Adverse Trend: None SEP 15 & 26 l | |||
l l | |||
o Licensee Event Reports I IPersonnel Errors Reported in LERs | |||
- Cumulative Licensee Event Reports | |||
---- Cumulative Personnel Errors Reported in LERs 50-46 7 - | |||
Ah! | |||
39 M | |||
I 40-14; | |||
% a1 nn ;; - | |||
G n;;; 31 | |||
$3 p h E | |||
;;,26 ;A 30-aa v- a . | |||
q Q f: r@; | |||
l_7 . | |||
^> g ?, , | |||
Ia | |||
./ $+ lt12 N | |||
% i 10-0 | |||
- A A ' | |||
'87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 NUMBER OF PERSONNEL ERRORS REPORTED IN LER'S The Number of Personnel Errors Reported in LER's Indicator reports the Licensee Event Reports (LER's) by their event date, in September 1990, there were 5 LER's reported. Out of the 5 LER's which occurred, there was one LER attributable to personnel error. | |||
There have been 25 LER's reported so far in 1990 and 7 LER's have been attributable to personnel errors. | |||
Adverse Trend: None SEP 15 L | |||
{_]NuclearDivisionsTurnoverRate | |||
- OPPD Corporate Turnover Rate 8-T u 6-r n , | |||
o y | |||
e 4-r | |||
~ | |||
R a | |||
t 2-e I | |||
0 Nuclear Operations Production Engineering Nuclear Services Division Division Division PERSONNEL TURNOVER RATE The turnover rate for three Nuclear Divisions is shown for the last twelve months. | |||
The personnel turnover rate is plotted against the OPPD corporate turnover rate of 4.0%. This OPPD corporate turnover rate is based on the turnover rate over the last three years. | |||
Adverse Trend: The turnover rates for the NOD and PED have been increasing. The high turnover rate for NOD was due to 30 resignations which have occurred in the last 12 months. The high turnover rate for PED was due to 11 resignations which have occurred in the last 12 months. | |||
j | |||
600- 8 Actual Staffing 561 IAuthorized Staffing I | |||
534 | |||
($lkltejW 51 | |||
:- %4 | |||
+m nsew 47% | |||
,,/ c , | |||
P 400- giggd,.WW j e - | |||
%wy r x.. , | |||
s );ts'g"JLW! | |||
o - | |||
Ubhw:a Hf WM n z;pg*fggg p | |||
n g#4 m+g s /,i e v gn$ | |||
1 200-j:as"'"h; ;m 193 | |||
- ,1 , s,.~/, | |||
O,I g };, ,) f 1 . . , _, | |||
.h4\fyg Q:(w;7. 'hidig'Q' -l['));li swg; v. g ,% .; ,: | |||
.I, y9ikke# 4$9y;, d t{,4 : p,y | |||
~ 7;;g;g t e. Q. | |||
ni@f'- )f:;i tja jp4d(Cef 56 52 | |||
? | |||
m e @u m wo,?'f3 , | |||
lSRf;fdW #SMMM[0 typ't'q;[.ij Nuclear Operations Production Engineering Nuclear Services Division Division Division STAFFING LEVEL The authorized and actual staffing levels are shown for the three Nuclear Divisions. | |||
Adverse Trend: None SEP 24 I ISRO Exaaination Pass Ratio 100-80-f 0 . | |||
P a 60-s s . | |||
N 40-t i | |||
o 20-No Exams No Exams No Exams Administered Administered Administered 0 | |||
NRC Administered NRC Administered NRC Administered OPPD Administered Generic Site Specific Requalification Requalification Fundamental Exams Exams Exams Exams SRO LICENSE EXAMINATION PASS RATIO The SRO License Examination Pass Ratio indicator shows the number of NRC administered Generic Fundamentals Exams (GFE's), | |||
the number of NRC administered Site Specific Exams, the number i | |||
of NRC administered license requalification exams, and the number of OPPD administered license requalification exams. | |||
No SR0 License examinations were administered during September 1990. The table below lists the examination pass ratio for exarinations which have been taken during 1990. | |||
OPPD ADMINISTERED NRC ADMINISTERED l | |||
Requal Generic Fund. Site Spec. Requal. | |||
% PASS RATIO % PASS RATIO % PASS RATIO % PASS RATIO DATE Feb 1990 - 100 SEP 68 Adverse Trend: None i | |||
[]R0Exa2inationPassRatio l 100-R 80-0 | |||
~ | |||
P a | |||
60- i s | |||
s R | |||
a 40-t i . | |||
o 20-No Exams No Exams Administered Administered NRC Administered NRC Administered NRC Administered OPPD Administered Generic Site Specific Requalification Requalification Fundamental Exams Exams Exams Exams R0 LICENSE EXAMINATION PASS RATIO , | |||
The R0 License Examination Pass Ratio Indicator shows the number of NRC administered Generic Fundamentals Exams (GFr.'s), the number of NRC administered Site Specific Exams, the number of NRC administered license requalification exams, and the number of OPPD administered license requalification exams. | |||
No R0 License examinations were administered during the month of September 1990. The table below lists the examination pass ratio for examinations which have been taken during 1990. | |||
OPPD ADMINISTERED NRC ADMINISTERED Requal Generic Fund. Site-Spec. Requal. | |||
DATE % PASS RATIO- % PASS RATIO % PASS RATIO % PASS RATIO Feb 1990 - 100 - | |||
May 1990 - - 100 - | |||
Adverse Trend: None SEP 68 84- | |||
i R SRO Exams Administered 20- SRO Exams Passed | |||
@ R0 Exams Administered L43 R0 Exams Passed u | |||
15-m b 3 e 1 y r .y C 1 ; | |||
o 10- i ; | |||
f g j t c E - | |||
t { . | |||
I x ; q. | |||
a ;: $ , | |||
m 5 4 [ | |||
s j jj-( i 3 :p "Y h | |||
= | |||
5 };; | |||
: a 5$ $$ | |||
M{ | |||
x! | |||
ll s 0 | |||
*2 | |||
* d #3 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan 1990 1991 i l | |||
LICENSE CANDIDATE EXAMS This indicator- shows the number of SRO and R0 quizzes and exams taken and passed each month. These internally administered quizzes and exams are used to plot the SAO and R0 candidates' monthly progress. | |||
During the month of September 1990, no SR0 , | |||
exams were administered. | |||
During the month of September 1990, no R0 | |||
_ exams were administered. | |||
Adverse Trend: None SEP 68 l | |||
l 85-i | |||
l l | |||
@@ Hotlines Initiated 50- | |||
* Hotlines Closed M Hotlines Open Under 4 Weeks l 45- I Hotlines Open Over 4 Weeks N | |||
u 40-m b 35-e r | |||
30-o f 25- | |||
"o 20 ~ | |||
t i > : | |||
1 15- !! i j e ] _1 1 1 "e 10- 5> ! - | |||
:: s 3 T | |||
5 | |||
:x l 1 y E | |||
rg | |||
[ | |||
2 :}s lMr :l.1_).: | |||
Oct Nov Dec Jan Feb f :YO 3 Ml d A Mar Apr May Jun Jul Aug Sep 1989 1990 HOTLINES This indicator shows the number of Hotlines initiated during the reporting month, the number of Hotlines closed during the reporting month, the number of Hotlines that remain open and are less than four weeks-old, and the number of Hotlines that remain open and are older than four weeks old. | |||
During the month of September 1990, there were 3 Hotlines initiated, 12 Hotlines closed, I Hotline that remained open and was less than four weeks old, and 1 Hotline that remained open and was older than four weeks old. | |||
Adverse Trend: None 86- | |||
4- | |||
[] Planned Classroom Hours l I Actual Classroom Hours T _ | |||
h 3 _ | |||
u f - | |||
q s .t_ | |||
* ' ~ | |||
a .. | |||
~ | |||
? | |||
5 2-o l ! - | |||
f 9, ./ . D , | |||
- -' a ; | |||
3 , | |||
-_ ~ | |||
H G ,. .y a o 4 | |||
~; - ~- | |||
u l- S. f f- s _ | |||
r 4 1 ,. | |||
m ' ' | |||
i: f, ,s % , | |||
~ | |||
a , | |||
, i | |||
$> g. $, ) l 1 ). k y d s:l ' | |||
,, , , ., ;y' ''A sf- | |||
'I', k' g k [' x' ) 'f 0" | |||
Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug 1989 1990 CLASSROOM flNSTRUCTOR) HOUR 1 This indicator displays the number of planned classroom hours and the number of actual classroom hours for the fort Calhoun Station. | |||
This indicator is one month behind the reporting month due to the time to collect and process the needed information. | |||
Adverse Trend: None 87-m | |||
I IOperations E Maintenance B Chemistry and Radiation Protection 30 | |||
* Technical Support G 3 General Employee Training T | |||
h Other o 25-u s | |||
a n 20-N o 15- y lb yg w m " ~ | |||
g : | |||
10-r f | |||
~ | |||
g .... - | |||
..... g ..... | |||
l 5- - - | |||
r"~ | |||
[_, ..... | |||
L. | |||
~{ L. . | |||
O Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug 1989 1990 TOTAL HOURS OF STUDENT TRAINING This indicator shows the total number of student hours for Operations, Maintenance, Chemistry and Radiation Protection, Technical Support, General Employee Training, and Other training conducted for the Fort Calhoun Station. | |||
This indicator is one month behind the reporting month due to the time needed to collect and evaluate the data. | |||
Total Hours TRAINING dVL 1990 AVG 1990 Operations 2.742 2,664 Maintenance 3, ISO 4,660 Chemistry and 580 2,013 Radiation Protection Technical Support 1,768 3,293 General Employee Training 3,359 4,983 Other .. | |||
277 443 Total 11,906 18,056 Adverse Trend: None 1 | |||
1 Total Outage MWO's MWO's Ready to Work ; | |||
400 1 | |||
\ | |||
300- -------------------------------------------------- ---------------------------- | |||
i N | |||
u mM bW e0 200- ------------------------------------------------------------------------------- | |||
r' 3 3 s | |||
~ | |||
o f | |||
100- ------------------------------------------------------------------------------- | |||
0-Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul 1990 1991 MWO OVERALL STAT _L!S (1991 REFUEllNG OUTAGE) | |||
The MWO Overall Status (1991 Refueling Outage) Indicator has been added to the Performance Indicators Report. | |||
This indicator shows the total number of MWO's that have been written over the past reporting periods for completion during the 1991 Refueling Outage and the number of MWO's that are ready for work (the parts for these MWO's are staged, the procedures are approved, and the paperwork is ready for field use). Any MWO's written after the start of the outage will be reflected in the indicator labeled Emeraent MWO's. Approximately 3000 maintenance orders were completed during each of the previous two refueling outages. | |||
Additional data points will be added to this indicator as information becomes available. | |||
Adverse Trend: None SEP 31 | |||
- Total Outage Modifications Mods With Planning Document Approved | |||
-s- Mods With Final Design Approved Hods With Construction Package Approved 30 M | |||
o Nd ui 20- ---------------------------------------------------------------------------------- | |||
mi bi eC , | |||
ra t | |||
10- ------~~------------------------------------------------------------------------- | |||
n s | |||
O Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul 1990 1991 PROGRESS OF 1991 OUTAGE MODIFICATION PLANNING The Progress of 1991 Outage Modification Planning Indicator has been added to thc Fort Calhoun Station Performance Indicators Report. | |||
This indicator shows the number of modifications approved for planning (to determine feasibility) for completion during the 1991 Refueling Outage. Additional data points will be added to this indicator as information becomes available. | |||
The current schedule for completion of the modification phases of the 1991 Refueling Outage is as follows. | |||
Outage Scope Freeze ............................ OCT 1, 1990 Pl anning Documents Approved . . . . . . . . . . . . . . . . . . . FEB 22, 1991 Final Designs Approved . . . . . . . . . . . . . . . . . . . . . . . . APR 24, 1991 Construction Packages Approved ................ JUN 15, 1991 Schedul e incorporated . . . . . . . . . . . . . . . . . . . . . . . . . JUL 26, 1991 Materi al On Si te . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . JUL 26, 1991 Construction Started .......................... OCT 21, 1991 Construction Complete .......................... NOV 4, 1991 Accepted By SAC ............................... NOV 15, 1991 Adverse Trend: None SEP 31 | |||
- Total Outage Projects 50 1 1 | |||
i 40- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - | |||
I Np j u ! | |||
~~-~~~~~~~~~~-~~~~~~~~~~~~--*~~~~----'''~~~~~~~~~~~~~~~~~~~~---~~~~~~~~~~~-~~~~~~ | |||
m' 30 '' | |||
b e,j - | |||
rC t 20' ' ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - - - - - - * - - - - ~ ~ - ~ ~ ~ ~ - - - ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ ' ~ ~ ~ ~ ~ ~ ~ ~ | |||
o 5 | |||
i , | |||
10- ------------------ ------ ------------------------------------ ---- ------------- | |||
0-Aug Sep Oct Nov Occ Jan Feb Mar Apr May Jun Jul 1990 1991 OVERALL PROJECT STATUS | |||
.(1991 REFUELING OUTAGE) | |||
The Overall Project Status (1991 Refueling Outage) Indicator has been added to the Performance Indicators Report. | |||
This indicator shows the status of the projects which affect the scope of the 1991 Refueling Outage. | |||
t Additional data points will be added to this indicator as l information becomes available. | |||
The schedule for t' 1991 Refueling Outage projects .is as follows. | |||
l All Projects identified and Outage Scope Frozen ....... OCT 1, 1990 All Projects Scheduled in Detail ...... JUN 28, 1991 Adverse Trend: None SEP 31 | |||
- Violations per 1000 Inspection Hours ! | |||
G- Fort Calhoun Goal i 15-11.1 { | |||
10.6 n ' | |||
5iM | |||
@ GOOD J 12- | |||
'y 4 | |||
a 4 F9 g j | |||
r | |||
;Ml 7,3 a - | |||
9 Ng' ' ,j gg$ CF- -- G - -- G - - - - n - ---O - --O - -- G- -- - G -- - -O -- - G - -- G -- - O pf #n ~q . , | |||
o 'f-t e | |||
y | |||
., 6-y, cny | |||
%.v $' | |||
14 3-7 ,. | |||
l f) 7 -w L,9 | |||
'87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 VIOLATIONS PER 1000 INSPECTION HOURS This indicator displays the number of NRC violations cited in inspection reports per 1000 NRC inspection hours. This indicator was calculated using the number of violations and the number of inspection hours from submitted inspection reports. These inspection reports consisted of reports from the months of January 1990 through August 1990. | |||
This indicator is one month behind the reporting month due to the time involved with collecting and processing the data. | |||
The violations per 1000 inspection hours indicator was reported as 7.6 for the month of August 1990. | |||
There have been a total of 1,972 inspection hours in 1990 which have resulted in 15 violations. | |||
The goal for the number of violations per 1000 inspection hours is less than 8.2. | |||
Adverse Trend: None 75- l l Number of Violations During the Last 12 Months C Number of NCV's During the Last 12 Months V | |||
~ | |||
i o | |||
1 a | |||
50- 47 Nt u | |||
i ~ | |||
m0 41 41 bn 3g 37 | |||
's . 36 34 34 r, - - | |||
0 0 | |||
fd 25-N C 16 19 | |||
~ | |||
20 | |||
? | |||
h4 2J 1 16 y 14 m ) oi w ' | |||
--- 14 11 g | |||
On f .! | |||
i 41 n | |||
si | |||
.:y $~ : 7 s "j 1 3s :n a . | |||
g . | |||
g | |||
.; ; . A't v M i G ,, | |||
b L$ s'f ?? s ; jf. | |||
;t 1,< . n; v < | |||
:: . >Q~ | |||
"' a* | |||
0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 CUMULATIVE VIOLATIONS AND NCV's (TWELVE M') NTH RUNNING 10TAL) | |||
The Cumulative Violations and Non Cited Violations (NCV's) Indicator shows the cumulative number of violations for the last twelve months and the cumulative number of NCV's for the last twelve months. | |||
During the last twelve months, 28 violations have been identified and 14 NCV's have been identified. | |||
Adverse Trend: None 93- | |||
- Total Outstanding CAR's G Outstanding CAR's > Six Months Old Outstanding CAR's That Are Modification Related 200-150-o Ni - | |||
u N100-eR r' , | |||
s Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 l | |||
OUTSTANDING CORRECTIVE ACTION REPORTS This indicator shows the total number of outstanding Corrective Action Reports (CAR's), the number of outstanding CAR's that are greater than six months old, and the number of outstanding CAR's that are modification related. | |||
As of the. end of September 1990, there were 142 outstanding CAR's, 53 CAR's that are greater than six months old, and 11 CAR's that are modification related. | |||
Adverse Trend: None f | |||
, i | |||
{ | |||
l 94 | |||
y40- -e. NOD Overdue CAR's u 30- -a- NOD CAR's With Extensions Granted ' | |||
cc 20-bA | |||
' [g --- by . . --- q~ ----- Q-Q'. 4-----s.....p....g Nov Dec Jan Feb MYr Air May JYn JYi A79 Sep Oct 1989 1990 o 50- | |||
-e- ED Overdue CA0's N f 40-u 6- PED CAR's With Extensions Granted l mC 30- , | |||
bA 20- | |||
'!r 10- O ' | |||
O ""'O'' | |||
'b- ! | |||
s U" " ' 6-N-=- M M C g g g '$ | |||
Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct i 1989 1990 10-0 Other Overdue CAR's j N 8-u 6- Other CAR's With Extensions Granted ! | |||
mC 6- ; | |||
2 s n n A' * - A" - :-, i W''S~~ ,In | |||
- ~ . 1 o | |||
Nov Dec J FTb MYr Apr -N~~In MTy J Jul Aug Sep Oct 1989 1990 OVERDUE AND EXTENDED CORRECTIVE ACTION REPORTS This indicator shows the number of overdue CAR's and the number of CAR's which received extensions broken down by organization. | |||
OVERDVE CAR's ORGANIZATION JyL.92 AVG 90 EP_9A l 0 0 1 NOD PED 0 1 1 Others 0 0 0 i, | |||
I Total 0 1 2 CAR's WITH EXTENSIONS GRANTED i ORGANIZATION JUL 90 AVG 90 Ef._93 N00 4 2 3 l PED 7 13 5 Others 0 1 0 Total 11 16 8 | |||
!I Mverse Trend: None ! | |||
l 4 | |||
Ny150- -e- NOD CAR's >6 Months Old | |||
" 6- NOD CAR's <6 Months Old mc 100 50 6-- -6 ' " - - - - - - -- - -& - - - --b. . g . . . . .b -- - - -6 r C U ^ ' " n 0 | |||
s Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov 1989 1990 o 150-Nf PED CAR's >6 Months Old U | |||
100- 6- PED CAR's <6 Months Old mC bA f) ["' Wh .... - -- ---- ~b 5 0 _ | |||
Dec Jan feb Mar Apr May Jun Jul Aug Sep Oct Nov 1989 1990 o 40-Nf C Other CAR's >6 Months Old u 30-Other CAR's <6 Months Old mC bA 20- | |||
,, . 6... -6 .. , ,,,,4 ,,,,, ,... -A ,,, | |||
r 10- 6--- . g , | |||
s 0 0 0 " O " | |||
O'n n Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov 1989 1990 CORRECTIVE ACTION REPORTS CURRENT STATUS This indicator shows the number of CAR's that are older than 6 months and the number of CAR's that are less than 6 months old broken down by organization. | |||
CAR's GREATER THAN 6 MONTHS OLD ORGANIZATION JVL 90 AVG 90 SEP 90 ' | |||
N0D 8 6 9 PED 49 48 45 Others 3 1 1 1 ' | |||
Total 60 55 55 CAR's LESS THAN 6 MONTHS OLD ORGANIZATION JVL 90 AUG 90 SEP 90 N00 39 45 47 PED 31 35 34 Others 8 13 6 Total 78 93 87 Adverse Trend: None 4 | |||
. . . ~ . | |||
1990 1989 NRC OPPD SIGNIFICANT _ NRC OPPD -SIGNIFICANT CAR's- CAR's VTOLATIONS LER'S CAR's' CAR's VIOLATIONS LER'S. | |||
SALP FUNCTIONAL-AREA 9 | |||
0 8 2 l 37 (1) 0 1 A. Plant Operations- 0 0 30 1 2 1 23 (1) 2 B.~ Radiological Controls 140 8 2 10 164 (12) 8 (1) S 4 C. Maintenance / | |||
Surveillance 6 0 2 0 0 0 D. Emergency 8- 0' Preparedness 6 10 23 0 4 2 (1) 26 2 E. Security. | |||
134 2 7 7 120 (18) 3 (1) 1 II (4) | |||
F. Engineering / | |||
Technical Support 0 0 68 0 1 0 16 (1) 0 G. Safety Assessment / | |||
Quality 6 Verification 0 0 0 T 0 0 0 1 1 H. Other 26 31 390 (33) 13 (2) 13 26 (S) 417 13 Total CAR'S ISSUED VERSUS SIGNIFICANT CAR'S VERSUS NRC VIOLATIONS ISSUED VERSUS LE (CAR's) issued by the Nuclear The above matrix shows the number of Corrective Action Reports Services Division versus the number of Significant CAR's issued by the Nuclear Services Division issued by the Nuclear Regulatory Commission (NRC) for the Fort versus the number of violat!ns Calhoun Station in 1989 and #0. Included in this table is the number of Licensee Event Reports (LER's) identified by the station each year. The number of MRC violations reported are one month behind the' reperting month due to the time involved in collecting and processing the violations. | |||
In September, 1990, there were 33 CAR's issued, 2 Significant CAR's issued, and S LER's identified. During August zero NRC violations were issued. Thus no violations were attributable to personnel error. The monthly distribution of CAR's, Significant CAR's, NRC violations, and LER's are shown in parentheses, SEP 15, 20 & 21 1 | |||
SIGNIFICANT ITEMS OF INTEREST This section is intended to provide information on events which are significant to the Fort Calhoun Station and will give a " heads-up" look at what is scheduled in the coming months. | |||
The Procedure Upgrade Project and the Plant have approved and issued 811 safety related procedures. | |||
This meets a Safety Enhancement Program (SEP) Item Number 48 milestone commitment. | |||
The NRC- Maintenance Inspection Team follow-up review has been rescheduled until November 1990. | |||
The 56 day 1991 Refueling Outage is planned to start 9/28/91 and finish 11/22/91. | |||
The 1990 Emergency Preparedness Graded Exercise is planned _for the week of 11/26/90. | |||
1 I | |||
l l | |||
l l | |||
l FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS AGE OF OUTSTANDING MAINTENANCE WORK ORDERS This indicator tracks the total number of outstanding corrective non-outage Maintenance Work Orders :.t the Fort Calhoun Station versus their age in months. | |||
! AMOUNT OF WORK ON HOLD AWAITING PARTS This indicator is defined as the percentage of open, non-outage, maintenance work orders that are on hold awaiting parts, to the total number of open, non-outage, maintenance work orders. | |||
AUXILLARY SYSTEMS CHEMISTRY HOURS OUTSIDE STATION LIMITS The cumulative hours that the Component Cooling Water system is outside the station chemistry - limit. The hours are accumulated from the first sample exceeding the limit until additional sampling shows the parameter to be back within limits. | |||
CHECK VALVE FAILURE RATE The Fort Calhoun check valve failure rate and the industry check valve failure rate (failures per 1 million component hours). The data for the industry failure rate is three months behind the Performance Indicators Report reporting month. This indicator tracks performance for SEP item 43. | |||
CLASSROOM (INSTRUCTOR) HOURS The number of planned classroom hours and the number of actual classroom | |||
-hours for the Fort Calho? Station. | |||
CORRECTIVE ACTION REPORT CURRENT STATUS The number of Corrective Action- Reports (CAR's) that are- older than 6 months and the number of CAR's that are less than 6 months old broken down by organization for the last 6 months.- | |||
CORRECTIVE MAINTENANCE BACKLOG GREATER THAN 3 MONTHS OLD The percentage of total outstanding corrective maintenance items, not requiring an outage, that are greater than three months old at the end of the period reported, h | |||
L l | |||
FORT CALH0VN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) | |||
CVMULATIVE VIOLATIONS AND NON-CITED VIOLATL(LNS (TWELVE-MONTH RUNNING TOTAL) l The cumulative number of violations and Non-Cited Violations for the last 12 months. | |||
DAILY THERMAL OUTPUT The daily core thermal output as measured from computer point XC105 in thermal megawatts. | |||
DIESEL GENERATOR RELIABILITY A Diesel Generator (DG) unit consists of the engine, generator, combustion air system, cooling water system, fuel supply system, lubricating oil system, starting air system, autostart controls, manual controls, and diesel generator breaker. | |||
Reliability of each DG unit will be reported for two situatior s, one for the last 20 demands and one for the last 100 demands. Reliability is the ratio of the number of successful runs to the number of demands, for each individual DG unit. | |||
A successful run. is defined as a start of a DG unit and the loading of this unit to a minimum of 50% rated load (1250 KW) for a minimum time period of 60 minutes. | |||
A failure is defined as the failure to start, accelerate, and assume the design rated load for the given time period as specified for an emergency or a valid test. | |||
The total number of demands (or valid tests) will be equal to the sum of the failures and the successful runs. | |||
This definition of DG Reliability was taken from.the U.S. Nuclear Regulatory Commission " Regulatory Guide 1.108, Revision 1". This is the definition being applied in calculating the diesel . generator reliability at the Fort Calhoun Station. | |||
1 DISABLING INJURY FRE00ENCY RATE (LOST TIME ACCIDENT RATE) | |||
This indicator is defined as the number of accidents for all utility personnel permanently assigned to the station, involving days away from I work per 200,000 man-hours worked (100 man-years). This does not include contractor personnel. This indicator tracks personnel performance for Safety Enhancement Program (SEP) Item 26. | |||
-100- | |||
FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) | |||
DOCUMENT REVIEW (BIENNIAL) | |||
The Document Review Indicator shows the number of documents reviewed during the reporting month, the number of documents scheduled for review during the reporting month, and the number of document reviews that are overdue. | |||
ENGINEERING ASSISTANCE RE0 VEST (EAR's) PRIORITY BREAKDOWN The number of open and closed EAR's broken down into priorities at the end of the reporting month. This indicator tracks performance for SEP item 62. | |||
ENGINEERING CHANGE NOTICE (ECN) BREAKDOWN The breakdown of the total number of open ECN's, the number of ECN's that were opened during the reporting month, the number of ECN's that were completed during the reporting month, and the number of ECN's received during the reporting month into three categories. These categories include; 1) document changes are required to complete the ECN's, 2) substitute or replacement items are required to complete the ECN's, or 3) facility changes are required to complete the ECN's. This indicator tracks performance for SEP item 62. | |||
ENGINEERING CHANGE NOTICE (ECN) STATUS The number of ECN's that remain open at the end of the reporting month, the number of ECN's that were opened during the reporting month, and the number of ECN's that are completed during the reporting month. This indicator tracks performance for SEP item 62. | |||
E001PMENT FORCED OUTAGES PER 1000 CRITICAL HOURS Equipment forced outages per 1000 critical hours is the inverse of the L mean time between forced outages caused by equipment - failures. The mean L time is equal to the number of hours the reactor is critical in a period l (1000 hours) divided by the number of forced outages caused by equipment failures in that period. | |||
E0VIVALENT AiAILABILITY FACTOR This indicator is defined as the ratio of gross available generation to gross maximum generation, expressed as a percentage. Available generation is.the energy that can be produced if the unit is operated at the maximum power level permitted by equipment and regulatory limitations. Maximum generation is the energy that can be produced by a unit in a given period if operated continuously at maximum capacity. | |||
EXPEDITED PURCHASES The percentage of expedited purchases which occurred during the reporting month compared to the total number of purchase orders generated. | |||
-101- | |||
FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) | |||
FORCED OUTAGE RATE This indicator is defined as the percentage of time that the unit was unavailable due to forced events compared to the time planned for electrical generation. Forced events are failures or other unplanned conditions that require removing the unit from service before the end of the next weekend. Forced events include startup failures and events initiated while the unit is in reserve shutdown (i.e., the unit is available but not in service. | |||
FUEL REllABillTY INDICATOR This indicator is defined as the steady-state primary coolant I-131 activity, corrected for the tramp uranium contribution and normalized to a common purification rate. | |||
Tramp uranium is fuel which has been deposited on reactor core internals from previous defective fuel or is present on the surface of fuel elements from the manufacturing process. | |||
Steady state is defined as continuous operations above 85 percent power for at least seven days. | |||
This INPO indicator uses an industry normalized letdown purification rate. The FRI has also been calculated using Fort Calhoun's actual letdown purification rate. These calculations revealed that the use of the plant's actual rate would result in an approximate 45% increase in FRI data. | |||
GASEOUS RADI0 ACTIVE-WASTE BEING DISCHARGED TO THE ENVIRONMENT This indicator displays the total number of Curies of all gaseous radioactive nuclides released from the Fort Calhoun Station. | |||
GROSS HEAT RATE' Gross heat rate is defined as the ratio of total thermal energy in British Thermal Units (BTU) produced by the reactor to the total gross electrical energy produced by the generator in kilowatt-hours (KWH). | |||
HA7ARD0US WASTE PRODUCED The total amount (in Kilograms) of non-halogenated hazardous waste, halogenated hazardous waste, and other hazardous waste produced by the Fort Calhoun ~ Station each month. | |||
HOTLINES The number of Hotlines that are initiated, closed, overdue, and open for a given month, A Hotline is a training document sent out for. immediate review. The Hotline should be reviewed and signed within 5 days of receipt of the Hotline. | |||
-102- | |||
FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINVED) | |||
HOURS CHEMISTRY IS OUTSIDE OWNERS GROUP GUIDELINES Total hours for 13 secondary side chemistry parameters exceeding guidelines during power operation. Power operation is defined as greater than 30% power. The 13 parameters tracked are steam generator pH, cation conductivity, boron silica, chloride, sul f ate, sodium, feed water pH, dissolved oxygen, hydrazine, iron, copper, and condensate pump discharge dissolved oxygen. | |||
IN LINE CHEMISTRY INSTRUMENTS OUT-0F-SERVICE Total number of in line chemistry instruments that are out-of-service in the Secondary System and the Post Accident Sampling System (PASS). | |||
INVENTORY ACCURACY The percentage of line items that are counted each month by the warehouse which need count adjustments. | |||
INVOICE BREAKDOWN The number of invoices that are on hold due to shelf life, CQE, and miscellaneous reasons. | |||
LLQJa CANDIDATE EXAMS This indicator shows the number of SR0 and/or R0 quizzes and exams that are administered and passed each. month. The License Candidate Exams Indicator tracks Training performance for Safety Enhancement Program Item Number 68. | |||
LIOVID RADI0 ACTIVE WASTE BEING DISCHARGED TO THE' ENVIRONMENT This indicator displays the volume of liquid radioactive waste released , | |||
from the radioactive waste monitor tanks. The curies from all releases from the Fort Calhoun Station-to the Missouri River are also shown. | |||
LOGGABLE/REDORTABLE INCIDENTS (SECURITY) | |||
The total rumber of security incidents for the reporting . month.. This , | |||
indicator tracks security performance for Safety Enhancement Program Item > | |||
l-Number 58. | |||
MAINTENANCE EFFECTIVENESS The number of Nuclear Plant Reliability Data System (NPRDS)' components with more than one failure and the number of NPRDS components with more than two failures during the last twelve months. | |||
-103- | |||
FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) | |||
MAINTENANCE WORK ORDER BACKLOG The number of corrective non outage maintenance work orders that remain open at the end of the reporting month. This indicator was added to the Performance Indicators Report to trend open corrective non-outage maintenance work orders as stated in Safety Enhancement Program (SEP) | |||
Item No. 36. | |||
MAINTENANCE WORK ORDER BREAKDOWN This indicator is a breakdown of corrective non-outage maintenance work l orders by several categories that remain open at the end of the reporting month. | |||
MAINTENANCE OVERTIME The percentage of overtime hours compared to normal hours for maintenance. This includes OPPD personnel as well as contract personnel. | |||
MATERIAL RE0 VEST PLANNING The percent of material requests (MR's) for issues with their request date the same as their need date compared to the total number of MR's. | |||
MATERIAL RE0 VESTS AWAITING APPROVAL The number of material requests awaiting approval at the end of the reporting month broken down by their age in days. | |||
MAXIMUM INDIVIDUAL RADIATION EXPOSVRE The total maximum amount of Gamma and Neutron- (Whole Body) radiation received by an individual person working at the Fort Calhoun Station on a monthly, quarterly, and annual basis, i | |||
MWO OVERALL STATUS (1991 REFUEllNG OUTAGE) | |||
The total number of Maintenance Work Orders (MW0's) that have been written for completion during the 1991 Refueling Outage. MW0's which are written after the start of the Refueling Outage will be labeled Emergent MWO's. This indicator tracks performance for SEP Reference Number 31. | |||
@gER OF HOT SPOTS The number of radiological hot spots which have been identified and-documented to exist at the Fort Calhoun Station at the end of the | |||
- reporting month. A hot spot is a small localized source of radiation. A hot spot occurs when the contact dose rate of an item is at least 5 times the General Area dose rate _ and the item's dose rate is equal to or greater than 100 mrem / hour. | |||
-104- | |||
FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINVED) | |||
EUMBER OF NUCLEAR PLANT REllABILITY DATA SYSTEM (NPRDS) FAILVRE REPORTS SUBMITTED The data plotted is the total number of NPRDS component failures (confirmed and- possible) and the number of confirmed NPRDS component failures. The total number of NPRDS component failures are based on the number of failure reports that have been sent to the Institute of Nuclear Operations (INPO). | |||
Confirmed NPRDS component failures are based upon failure reports that have been accepted by INP0. Possible NPRDS component failures are based upon failure reports that are still under review by INPO. | |||
NPRDS is the Nuclear Plant Reliability Data System, and is a utility industry users group program which has been outlined by INP0 and implemented at the Fort Calhoun Station. | |||
NUMBER OF OUT-0F-SERVICE CONTROL ROOM INSTRUMENTS A control room instrument that cannot perform its design function is considered as out-of-service. A control room instrument which has had a Maintenance Work Order (MWO) written for it and has not been repaired by the end of the reporting period is considered out-of-service and will be counted. The duration of the out-of-service condition is not considered. | |||
Computer CRTs are not considered as control room instruments. | |||
NUMBER OF PERSONNEL' ERRORS REPORTED IN LER'S The number of Licensee Event Reports (LERs) attributed to personnel error on the original LER submittal. This indicator trends personnel performance for SEP ltem No. 15. | |||
NUMBER OF MISSED SVRVEILLANCE TESTS RESULTING IN LICENSEE EVENT REPORTS The number of Surveillance Tests (ST's) that result in Licensee Event Reports (LER's) during the- reporting. This indicator tracks missed ST's | |||
-for. Safety Enhancement Program (SEP) Item Numbers 60 and 61. | |||
OPERATIONS AND MAINTENANCE EUDGET The year to date budget compared to the actual expenditures for operations and maintenance. | |||
OUTSTANDING CORRECTIVE ACTION REPORTS This indicator displays the total number of outstanding Corrective Action Reports (CAR's), the number of CAR's that are older than six- months and the number of modification related CAR's. | |||
-105-i | |||
FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) l l | |||
OUTSTANDING MODIFICATIONS The number of Modification Requests (MR'S) in any state between the issuance of a Modification Number and the completion of the drawing update. 1 Form FC ll33 Backlog /In Progress The Form FC-ll33 has not been plant approved. | |||
Modification Requests Being Reviewed This category includes: | |||
1.) | |||
* Modification Requests that are not yet reviewed 2.) | |||
* Modification Requests being reviewed by the Nuclear Projects Review Committee (NPRC) 3.) | |||
* Modification Requests being reviewed by the NuclearProjectsCommittee(NPC) | |||
* These Modification Requests may be reviewed several times before they are approved for accomplishment or cancelled. Some of these Modification Requests are returned to Engineering for more information, some apprcved for evaluation, some approved for ' | |||
study, and some approved for planning, Once planning is completed and the scope of the work is clearly defined, these Modification Requests may be approved for accomplishment with a year assigned for construction or they may be cancelled. All of these differentphasesrequirereview. | |||
Design Engineering Backlog /In Progress Nuclear Planning has assigned a year in which construction will be completed and design work may be in progress. | |||
Construction Backlog /In Progress The Construction Package has been issued or construction has begun but the modification has not been accepted by the System Acceptance Committee (SAC). | |||
~ | |||
Design Engineering Update Backlog /In Progress PED has received the Modification Completion Report but the drawings have not been updated. | |||
OVERALL PROJECT STATUS (1991 REFUELING OUTAGE) | |||
The number of projects which affect the scope of the 1991 Refueling Outage. | |||
This indicator tracks performance for SEP Reference Number 31. , | |||
1 | |||
-106-1 | |||
l l | |||
FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINVED) | |||
OVERDVE AND EXTENDED CORRECTIVE ACTION REPORTS l The number of overdue Corrective Action Reports (CAR's) and the number of CAR's which received extensions broken down by organization for the last 6 months. | |||
PERSONNEL RADIATION EXPOSURE (CUMULATIVE) | |||
Collective radiation exposure is the total external whole-body dose received by all on-site personnel (including contractors and visitors) during a time period, as measured by the thermoluminescent dosimeter (TLD). Collective radiation exposure is reported in units of man-rem. | |||
This indicator tracks radiological work performance for Safety Enhancement Program (SEP) Item Number 54. | |||
PERSONNEL TURNOVER RAR The ratio- of the number of turnovers to average employment. A turnover is a vacancy created by voluntary resignation from the company. Retirement, death, termination, transfers within the company, and part-time employees are not considered in turnover. | |||
PREVENTIVE MAINTENANCE ITEMS OVERDVE This indicator is defined as the percentage of preventive maintenance items in the month that were not completed by the scheduled date plus a grace period equal to 25 percent of the scheduled interval. This indicator tracks preventive maintenance activities for Safety Enhancement Program (SEP) Item Number 41. | |||
PRIMARY SYSTEM CHEMISTRY - PERCENT OF HOURS OUT OF llMIT The percent of hours out of limit are for six primary chemistry parameters divided by the total number of hours possible for the month. | |||
The key parameters used are: Lithium, Chloride, Hydrogen, Dissolved Oxygen, Fluoride, and Suspended Solids. EPRI limits are used. | |||
PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE) | |||
-The number of identified incidents concerning maintenance procedural problems, the number of closed IR's related to .he use of procedures (includes the number of closed IR's caused by proceau 'l noncompliance), | |||
and the number of closed procedural noncompliance IR's. This indicator trends personnel performance for SEP ltem Numbers 15 and 41. | |||
PROGRESS OF 1991 OUTAGE MODIFICATION PLANNING The number of modifications approved for planning (to determine feasibility) for completion during the 1991 Refueling. This indicator tracks performance for SEP Reference Number 31. | |||
-107- | |||
FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINVED) | |||
RADIOLOGICAL WORK PRACTICES PROGRAM l The number of identified poor radiological work practices (PRWP) for the reporting month. This indicator tracks radiological work performance for l Safety Enhancement (SEP) Item Number 52. | |||
RATIO 0F PREVENTIVE TO TOTAL MAINTENANCE The ratio of preventive maintenance (including surveillance testing and calibration procedures) to the sum of non-outage corrective maintenance and preventive maintenance completed over the reporting period. The ratio, expressed as a percentage, is calculated based on man-hours. This indicator tracks preventive maintenance activities for Safety Enhancement Program (SEP) Item Number 41. | |||
RECORDABLE INJURY CASES FRE0VENCY RATE (RECORDABLE INJURY RATE) | |||
The number of injuries requiring more than normal first aid per 200,000 manhours worked. This indicator trends personnel performance for SEP ltem No. 15 and SEP Item 26. | |||
R0 LICENSE _ EXAMINATION PASS RATIO The R0 license examination pass ratio for NRC administered Generic | |||
- Fundamentals Exams (GFE's), NRC administered Site Specific Exams, NRC administered license requalification exams, and OPPD administered license i requalification exams. This indicator tracks Training performance for Safety Enhancement Program Item Number 68. | |||
SECONDARY SYSTEM CHEMISTRY PERFORMANCE INDEX , | |||
The Chemistry Performance Index (CPI) is a calculation based on the concentration of key impurities in the secondary side of the plant. These key impurities are the most' likely cause of deterioration of the steam generators. The chemistry parameters are reported only. for the period of time greater than 30 percent power. | |||
The following equation is how the CPI is calculated: | |||
CPI = ((Ka/0.8) + (Na/20) + (02 /10)) / 3 Where the-following parameters are monthly averages of; Ka = average blowdown cation conductivity Na - average blowdown sodium concentration 02 average condensate pump discharge dissolved oxygen concentration | |||
-108- | |||
FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) | |||
SECURITY INCIDENTS BREAKDOWN This indicator shows a percentile breakdown of the types of Security incidents for_the reporting month. | |||
The following items are the types of Security incidents represented in this indicator. | |||
Licensee Designated Vehicles (LDV's) | |||
Incidents related to the use of LDV's, e.g. keys left in the vehicle, loss of keys, or failure to return keys. | |||
Security Badges incidents involving lost / unattended badges, badges removed from site, or failure to wear badges. | |||
Escorting Incidents involving escort responsibilities, e.g. improper control or escort of a visitor (s). | |||
Security System Failures Incidents involving alarm system failures, CCTV failures, security computer failures, terminal failures, door equipment failures, and card reader failures. | |||
Security Key Control Incidents involving Security key control, e.g. lost Security keys, Security keys removed from site, or failure to return | |||
' Security keys. This type of incident does not reflect incidents concerning LDV keys. | |||
Access Control Incidents involving the inspection and control of personnel, packages, and vehicles, e.g. failure to properly search personnel, packages, and vehicles. This item also includes the introduction of contraband or prohibited items into the Protected Area, or the attempted introduction of such items. | |||
This indicator tracks security performance for Safety Enhancement Program (SEP) Item Number 58. | |||
-109- | |||
l l | |||
FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINVED) | |||
SECURITY SYSTEM FAILURES 1 | |||
The number of Security incidents concerning alarm systems failures, CCTV failures, security computer failures, terminal failures, door equipment failures, and card reader failures. This indicator tracks security l performance for Safety Enhancement Program (SEP) Item Number 58. | |||
SPARE PARTS INVENTORY VALUE The dollar value of the spare parts inventory at the end of the reporting period. | |||
} PARE PARTS ISSVED The dollar value of the spare parts issued for the Fort Calhoun Station during the reporting period. | |||
SRO OPERATOR LICENSE EXAMINATION PA95_1AllQ The SR0 license examination pass ratio for NRC administered Generic Fundamentals Exams (GFE's), NRC administered Site Specific Exams, NRC administered license requalification exams, and OPPD administered license requalification exams. This indicator tracks Training performance for Safety Enhancement-Program item Number 68. | |||
STAFFING LEVEL The actual staffing level and the authorized staffing level for the Nuclear Operations Division, the Production Engineering Division, and the Nuclear Services Division. | |||
STATION NET GENERATION The net- generation (sum) produced by the Fort Calhoun Station during the l- reporting month. , | |||
STOCK 0VT RATE The total number of Pick Tickets that were generated during the reporting. | |||
month and the total number of Pick Tickets that were generated during the reporting month with no parts available. , | |||
TEMPORARY MODIFICATIONS l The number of temporary mechanical and electrical configurations to the L plant's systems. | |||
Temporary configurations are defined as electrical jumpers, electrical blocks, mechanical jumpers, or mechanical blocks which are installed in the plant operating systems and are not shown on the latest revision of the P&ID, schematic, connection, wiring, or flow diagrams. | |||
-110-l | |||
l e l FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) | |||
TEMPORARY MODIFICATIONS (CONTINUED) 1 Jumpers and blocks which are installed for Surveillance Tests, Maintenance Procedures, Calibration Procedures, Special Procedures, or Operating Procedures are not considered as temporary modifications unless the jumper or block remains in place after the test or procedure is complete. Jumpers and blocks installed in test or lab instruments are not considered as temporary modifications. | |||
N affolding is not considered a temporary modification. Jumpers and blocks which are installed and for which EEAR's have been submitted, will be considered as a temporary modifications until final resolution of the EEAR and the jumper or block is removed or is permanently recorded on the drawings. | |||
Th:s indicator tracks temporary modifications for Safety Enhancement Program (SEP) Item Number 62 & 71. | |||
TOTAL HOURS OF STUDENT TRAINING The total number of student hours of training for Operations, Maintenance, Chemistry and Radiation Protection, Technical Support, General Employee Training, and Other training conducted for the Fort Calhoun Station. | |||
TOTAL SKIN AND CLOTHING CONTAMINATIONS Reportable skin and clothing contaminations above background levels | |||
. greater than 5000 dpm/100 cm squared. This indicator trends personnel performance for SEP. Item No. 15. | |||
UNPLANNED AUTOMATIC REACTOR SCRAMS WHILE CRITICAL i | |||
This indicator- is defined as the number of unplaaned. automatic scrams l (reactor protection system logic actuations) that occur while the reactor i is critical. The indicator is further defined as follows: | |||
l l | |||
- Unplanned means that the scram was 'not part of a planned test 1 or evolution. | |||
- Scram means the automatic shutdown of the reactor by a rapid insertion of all. control rods that is caused. by actuation of the reactor protection system. The scram. signal may have resulted from exceeding a setpoint or may have been' spurious. | |||
- - Automatic means that the initial signal that caused. actuation of the reactor. protection system logic was provided from one of the sensors monitoring plant parameters and conditions, rather than the manual scram switches (or pushbuttons) in the main control room. | |||
-111- | |||
FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) | |||
UNPLANNED AUTOMATIC REACTOR SCRAMS WHILE CRITICAL (CONTINVED) | |||
Critical means that during the steady-state condition of the reactor prior to the scram, the effective multiplication factor (keff) was equal to one. | |||
UNPLANNED SAFETY SYSTEM ACTUATIONS - (INP0 DEFINITION) | |||
This indicator is defined as the sum of the following safety system actuations: | |||
the number of unplanned Emergency Core Cooling System (ECCS) actuations that result from reaching an ECCS actuation setpoint or from a spurious / inadvertent ECCS signal the number of unplanned emergency AC power system actuations that result from a loss of power to a safeguards bus An unplanned safety system actuation occurs when an actuation setpoint for a safety system is reached or when a spurious or inadvertent signal is generated (ECCS only), and major equipment in the system is actuated. | |||
Unplanned means that the system actuation was not part of a planned test or evolution. | |||
The ECCS actuations to be counted are actuations of the high pressure injection system, the low pressure injection system, or the safety injection tanks. | |||
UNPLANNED SAFETY SYSTEM ACTUATIONS - (NRC DEFINITION) | |||
The number of safety system actuations which include (Roly) the High Pressure Safety Injection System, the 'ow Pressure Safety Injection System, the Safety Injection Tanks, and the Emergency Diesel Generators. ' | |||
The NRC classification of safety system act3ations includes actuations when major equipment is operated 104 when the logic systems for the above safety systems are challenged. | |||
VIOLATIONS PER 1000 INSPECTION HOURS This indicator- is defined as the number of violations sited in NRC-inspection reports. for the' Fort Calhoun Station per 1000 NRC inspection hours. The violations are reported in the year that the inspection was actually performed and not based on when the inspection report is received. The hours reported for each inspection report are used as the t inspection hours, q | |||
-112- | |||
FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINVED) | |||
VOLUME OF LOW-LEVEL SOLID RADI0 ACTIVE WASTE This indicator is defined as the volume of low level solid radioactive waste actually shipped for disposal. This indicator also shows the volume of low-level radioactive waste which is in temporary storage. | |||
Low-level solid radioactive waste consists of dry active waste, sludges, resins, and evaporator bottoms generated as a result of nuclear power plant operation and maintenance. | |||
Dry active waste includes contaminated rags, cleaning materials, disposable protective clothing, plastic containers, and any other material to be disposed of at a low level radioactive waste disposal site, except resin, sludge, or evaporator bottoms. Low level refers ,o all radioactive waste that is not spent fuel or a by-product of spent fuel processing. | |||
This indicator tracks radiological work performance for Safety Enhancement Program (SEP) Item Number 54. | |||
HAREH0VSE ISSUES The total number of warehouse issues, the number of non-CQE stock issues, the number of CQE stock issues, the number of direct charge non CQE issues, and the number of direct charge CQE issues which occurred during the reporting month. | |||
WAREHOUSE RECEIPTS The total number of warehouse receipts, the number of non-CQE stock receipts,- the number of CQE stock receipts, the number of cirect charge non-CQE receipts, and the number of direct - charge CQE receipts which occurred during the reporting month. | |||
L WAREHOUSE RETURNS The percentage of the total number of warehouse returns, the number of I spare parts returns, the number of standard stores returns, and the number of direct charge returns compared to the total number of warehouse issues. | |||
-113- | |||
BASIS FOR ESTABLISHING 1990 PERFORMANCE INDICATOR GOALS This secti_on will explain the basis used in establishing the 1990 performance goals. | |||
FORCED OUTAGE RATE AND E0VIVALENT AVAILABILITY FACTOR The Forced Outage Rate (FOR) and Equivalent Availability Factor (EAF) goals have been established from 1990 to 1992. The following table is a breakdown of the hours allotted for each category over the next three l years. l STARTUP GENERATOR FORCED OUTAGE PLANNED ON LINE OUTAGE TIME OUTAGE PERIOD EAF FOR JLAB (HOURS) (HOURS) (HOURS) (HOURS) .di&Q). 151 L%1 1990(*) 6356 168 172 2064 8760 65.4 2.4 1991(*) 6956 168 172 1464 8760 75.9 2.3 1992 8520 240 0 0 8760 92.9 2.7 | |||
(*) Refueling Outage Years UNPLANNED AUTOMATIC REACTOR SCRAMS WHILE CRITICAL The 1990 goal for Unplanned Automatic Reactor Scrams While Critical has | |||
! been set at one. The Fort Calhoun Station has had one unplanned automatic reactor scram in the past four years of operation. | |||
l-UNPLANNED SAFETY SYSTEM ACTUATIONS-The Unplanned Safety System Actuations goal for 1990 has been established L at zero. The Fort Calhoun Statica did not have an unplanned safety system actuation for six years, l | |||
DR0SS HEAT RATE The 1990 Gross Heat Rate goal for the Fort Calhoun Station has been set at 10,200 BTU /KWH. This heat rate goal is based on 10,435 BTV/KWH for the | |||
: i. month of January, '10,450 BTU /KWH for the month of February, 10,325- | |||
- BTU /KWH for the month of May, 10,225 BTU /KWH for the month of June, 10,325 BTU /KWH for the month of July, 10,250 BTV/KWH for the month of August, 10,125 BTV/KWH for the month-of September, 10,050 BTV/KWH for the month of October, 10,000 BTV/KWH for the month of November, .and 9,975 l BTU /KWH for the month of December. | |||
-114- | |||
L BASIS FOR ESTABLISHING 1990 PERFORMANCE INDICATOR GOALS l (CONTINVED) | |||
FUEL RELIABillTY INDICATOR The 1990 Fuel Reliability Indicator (FRI) goal has been set at 1.0 nanocuries/ gram. This level allows for approximately one to two fuel pin failures. Although Cycle 11 was completed without ary apparent fuel pin failures, there are a number of Advanced Nuclear Fuels Corporation (ANF) assemblies entering into a third or fourth cycle of operation. When a fuel pin has been used for three or four fuel cycles there is an increased probability of fuel failure. The Failed fuel Action Pl an, Standing Order 0-43, allows for approximately four fuel pin failures prior to implementing any increased action levels. | |||
PERSONNEL RADIATION EXPOSURE (CVMULATIVE) | |||
The 1990 Personnel Radiation Exposure (Cumulative) goal is 287 man-ree. | |||
This goal was based on 234 man-rem of cumulative exposure for the 1990 Refueling Outage and approximately 5.9 man-rem of cumulative exposure for each non-outage month. | |||
VOLUME OF LOW-LEVEL SOLID RADI0 ACTIVE WASTE The 1990 Volume of Low Level Solid Radioactive Waste goal is 5,000 cubic feet. This goal was based on a recommendation made by the Fort Calhoun ALARA Committee and approved by the Division Manager of the Nuclear Production Division. | |||
DISABLING INJURY FRE0VENCY RATE The Disabling Injury frequency Rate 1990 goal has been set at 0.31. This goal allows for one lost time accident in the Nuclear Production Division during 1990. | |||
1. | |||
l | |||
-115- | |||
FORT CALHOUN STATION OPERATING CYCLES AND REFUEllNG OUTAGE DATES PRODUCTION CVMULATIVE EVENT FROM - | |||
TO (MWH) (MWH) | |||
Cycle 1 09/26/73 - 02/01/75 3,299,639 3,299,639 First Refueling 02/01/75 - 05/09/75 Cycle 2 05/09/75 - 10/01/76 3,853,322 7,152,961 Second Rnueling 10/01/76 - 12/13/76 Cycle 3 12/13/76 09/30/77 2,805,927 9,958,888 Third Refueling 09/30/77 - 12/09/77 Cycle 4 12/09/77 - 10/14/78 3,026,832 12,985,720 Fourth Refueling 10/14/78 - 12/24/78 Cycle 5 12/24/78 - 01/18/80 3,882,734 16,868,454 Fifth Refueling 01/18/80 06/11/80 Cycle 6 06/11/80 - 09/18/81 3,899,714 20,768,168 Sixth Refueling 09/18/81 - 12/21/81 Cycle 7 12/21/81 - 12/06/82 3,561,866 24,330,034 Seventh Refueling 12/06/82 - 04/07/83 Cycle 8 04/07/83-03/03/84 3,406,371 27,736,405 Eighth Refueling 03/03/84 - 07/12/84 Cycle 9 07/12/84 - 09/28/85 4,741,488 32,477,893 Ninth Refueling 09/28/85 - 01/16/86 Cycle 10 01/16/86 - 03/07/87 4,356,753 36,834,646 | |||
. Tenth Refueling 03/07/87 - 06/08/87 Cycle-ll 06/08/87 09/27/88- 4,936,859 41,771,505 Eleventh Refueling 09/27/88 - 01/31/89 Cycle 12 01/31/89 - 02/17/90 3,817,954 45,589,459 Twelfth Refueling 02/17/90 - 05/29/90 | |||
-116- | |||
FORT CALHOUN STATION OPERATING CYCLES AND REFUELING OUTAGE DATES (CONTINVED) | |||
PRODUCTION CVMULATIVE EVENT FROM - TO (MWH) (MWH) | |||
Cycle 13 05/29/90 - 09/28/91* | |||
Thirteenth Refueling 09/28/91*- 11/22/91* | |||
Cycle 14 11/22/91*- 02/12/93* | |||
Fourteenth Refueling 02/12/93*- 05/06/93* | |||
Cycle 15 05/06/93*- 09/30/94* | |||
Fifteenth Refueling 09/30/94*- 11/26/94* | |||
1 i | |||
I i | |||
* - Planned Dates | |||
-117- | |||
FORT CALHOUN STATION PRODUCTION AND OPERATION RECORDS The following seven items are the current production and operation | |||
" records" for the Fort Calhoun Station. | |||
-1. First Sustained Reaction. . . . . . . . . . . . . August 5, 1973 (5:47 p.m.) | |||
: 2. First Electricity Supplied to the System. . . . . August 25, 1973 | |||
: 3. Commercial Operation (180,000 KWH). . . . . . . . September 26, 1973 | |||
: 4. Achieved Full Power (100%) . . . . . . . . . . . . May 4,1974 | |||
: 5. Longest Run (477 days). . . . . . . . . . . . . . June 8, 1987 - Sept. 27,1988 | |||
: 6. Highest Monthly Net Generation (364,468,800 KWH). October 1987 | |||
: 7. Most Productive Fuel Cycle (4,936,859 MWH). . . . June 8, 1987 - Sept. 27, 1988 (Cycle 11) | |||
-118- | |||
PERFORMANCE INDICATOR DATA SOURCES PERFORMANCE INDICATOR MANAGER / INDIVIDUAL Age of Outstanding Maintenance Work Orders Patterson/Schmitz Amount of Work On Hold Awaiting Parts Patterson/ CHAMPS Auxiliary Systems Chemistry Hours Outside .ctation Limits Franco /Glantz CAR's Current Status Orr/Gurtis CAR's issued Versus NRC Violatior.s issued Orr/Gurtis Classroom (Instructor) Hours Gasper /Newhouse Corrective Maintenance Backlog > 3 Months Old Patterson/Schmitz Cumulative Violations and NCV's Chase /Simmons Daily Thermal Output Holthaus/ Gray Decontaminated Auxiliary Building Patterson/Gundal Diesel Generator Reliability DG Log Disabling injury-Frequency Rate Sorenson/Skaggs Document Review Patterson/McKay Engineering Assistance Requests Priority Breakdown Jaworski/ Van Osdel Engineering Change Notice Breakdown Phelps/Bera Engineering Change Notice Status Phelps/Bera Equipment Forced Outages per 1000 Critical Hours Holthaus/ Gray Equivalent Availability Factor Dietz/Kulisek | |||
. Expedited Purchases Willrett/Fraser Forced Outage Rate Holthaus/ Gray Fuel Reliability Indicator Holthaus/Lofshult Gaseous Radioactive Waste. Discharged to the-Environment Franco /Stultz Gross Heat Rate Holthaus/ Gray Hazardous Waste Produced Patterson/Sayre | |||
-119- | |||
PERFORMANCE INDICATOR DATA SOURCE (CONTINUED) | |||
Hotlines Gasper /Newhouse In Line Chemistry Instruments Out-of-Service Patterson/Renaud Inventory Accuracy Willrett/Fussell Invoice Breakdown Willrett/Fussell License Candidate Exams Gasper / Lazar Liquid Radioactive Waste Discharged to the Environment Franco /Stultz Loogable/ Reportable Security Incidents Sefick/Woerner Maintenance Effectiveness Jaworski/Dowiy Maintenance Work Order Backlog (Corrective Non-Outage) Patterson/Sch nitz Maintenance Work Order Breakdown Patterson/Schmitz Maintenance Overtime Patterson/Schmitz Material Request Planning Willrett/Fussell Material Requests Awaiting Approval Willrett/Fraser Maximum Individual Radiation Exposure Patterson/Mattice MWO Overall Status (1991 Refueling Outage) Patterson/ Hyde Number of Hot Spots Patterson/Mattice Number of NPRDS Reportable Failures Jaworski/ Dowdy Number of Out-of-Service Control Room Instruments Patters'on/ Adams Number of Personnel Errors Reported in LER's Chase /Simmons Number of Missed ST's Resulting in LER's Plant LER's Operations and Maintenance Budget Gleason/ Parent. | |||
Outstanding CAR's Orr/Gurtis Outstanding Modifications Jaworski/ Turner | |||
-120-i | |||
PERFORMANCE !NDICATOR DATA SOURCE (CONTINUED) | |||
Overall Project- Status (1991 Refueling Outage) Patterson/ Hyde Overdue and Extended CAR's Orr/Gurtis Personnel Radiation Exposure (Cumulative) Patterson/Mattice Personnel Turnover Rate Sorenson/ Burke Preventive Maintenance items Overdue Patterson/ Linden Primary System Chemistry - Percent Hours Out of Limits Franco /Glantz Procedural Noncompliance incidents (Maintenance) Patterson/McKay Progress of 1991 Outage Modification Planning Patterson/ Hyde Radiological Work Practices Program Patterson/Mattice Ratio of Preventive to Total Maintenance Patterson/Schmitz Recordable Injury Cases Frequency Rate Sorenson/Skaggs R0 License Examination Pass Ratio Gasper / Lazar Secondary System Chemistry Franco /Stultz Security Incident Breakdown Sefick/Woerner Security System Failures Sefick/Woerner Spare Parts Inventory Value Steele/Huliska Spare-Parts Issued Steele/ Miser SR0 License Examination Pass Ratio Gasper / Lazar Staffing Level Sorenson/ Burke Stockout-Rate Willrett/Fussell Temporary Modifications Jaworski/ Turner Total Hours of Student Training Gasper /Newhouse Total Skin and Clothing Contaminations Patterson/Mattice Unplanned Automatic Reactor Scrams While Critical Plant LER's | |||
-121- | |||
---..-g | |||
PERFORMANCE INDICATOR DATA SOURCE (CONTINUED) | |||
- Unplanned Safety System Actuations (INPO) Plant LER's Unplanned Safety System Actuations (NRC) Plant LER's Violations per 1000 Inspection Hours Chase /Simmons Volume of Low-level Solid Radioactive Waste Patterson/Breuer Warehouse Issues Willrett/Fussell Warehouse Receipts Willrett/Fussell < | |||
Warehouse Returns Willrett/Fussell | |||
-122- | |||
REFEllENCES l | |||
INPO Good Practices 0A-102, " Performance Monitoring - | |||
Management Information" IEEE Standard 762, "IEEE Trial Use Standard Definitions for Use in Reporting Generating Unit Reliability, Availability and Productivity" INPO Report Dated November 1984, " Nuclear Power Plant Operational Data" U.S. Nuclear Regulato.y Commission " Regulatory Guide 1.108 l ! | |||
I | |||
-123- | |||
_-_- -__ -_ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _}} | |||
Latest revision as of 07:18, 6 January 2021
| ML20065H684 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 09/30/1990 |
| From: | Oconnor J OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20065H683 | List: |
| References | |
| NUDOCS 9010300214 | |
| Download: ML20065H684 (128) | |
Text
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l OMAHA PUBLIC POWER DISTRICT FORT CALHOUN S1ATION PERFORMANCE INDICATORS PREPARED BY: PRODUCTION ENGINEERING DIVISION SYSTEM ENGINEERING SEPTEMBER 1990
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T TABLE OF CONTENTS PML L Distribution. . . . . . . . . . . . . . . . . . . . iv ,, Preface . . . . . . . . . . . . . . . . . . . . . . 1
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Purpose . . . . . . . . . . . . . . . . . . . . . . 3 Scope . . . . . . . . . . . . . . . . . . . . . . . 4 2-Adverse Trend Report. . . . . . . . . . . . . . . . 5 Indicators Needing Increased Management . . . . . . 6 Attention Index to Safety Enhancement Program (SEP) Indicators . .
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................. 9 Index to Performance Indicator Graphs . . . . . . . 12 Performance Indicator Graphs. . . . . . . . . . . . 17 Significant Items of Interest . . . . . . . . . . . 98 Definitions . . . . . . . . . . . . . . . . . . . . 99 R
Basis for Establishing 1989 Performance Indicator Goal s . . . . . . . . . . . . . . . . 114 Operating Cycles and Refueling Outage Dates . . . 116 Production and Operation Records. . . . . . . . . . 118 Data Source . . . . . . . . . . . . . . . . . . . 119 References. . . . . . . . . . . . . . . . . . . . 123
DISTRIBUTION V. W. Anderson D. C. Gorence W. L. Neal R. L. Andrews R. E. Gray J. B. Newhouse W. R. Bateman M. J. Guinn M. W. Nichols 1 K. L. Belek E. R. Gundal C. W. Norris L A. D. Bilau A. L. Gurtis J. T. O'Connor B. H. Blome R. H. Guy W. W. Orr C. N. Bloyd R. M. Hawkins L. L. Parent J. P. Bobba M. C. Hendrickson T. L. Patterson C. E. Boughter R. R. Henning R. L. Phelps M. A. Breuer K. R. Henry T. M. Reisdorff C. J. Brunnert J. B. Herman B. A. Reneaud M. W. Butt G. J. Hill A. W. Richard C. A'. Carlson K. C. Holthaus T. J. Sandene J. W. Chase L. G. Huliska C. A. Sayre G. R. Chatfield R. L. Jaworski B. A. Schmidt A. G. Christensen R. A. Johansen S. T. Schmitz
- 0. J. Clayton J. W. Johnson F. C. Scofield R. P. Clemens W. C. Jones L. G. Sealock <
R. G. Conner J. D. Kecy H. J. Sefick : J. L. Connolley J. D. Keppler P. Sepcenko C. M. Cook D. D. Kloock J. W. Shannon M. R. Core J. C. Knight R. W. Short 3 S. R. Crites D. M. Kobunski J. R. Shuck D. W. Dale G. J. Krause C. F. Simmons-R. C. DeMeu1meester L. J. Kripal E. L. Skaggs R. D. DeYoung J. B. Kuhr F. K. Smith D. C. Dietz L. T. Kusek R. L. Sorenson D. E. Dirrim L. E. Labs D. E. Spires K. S. Dowdy M. P. Lazar K. E. Steele J. A. Drahota R. C. Learch W. Steele T. R. Dukarski S. E. Lee H. F. Sterba R. G. Ellis R. E. Lewis R. K. Stultz R. G. Eurich R. C. Liebentritt G.. A. Teeple H. J. Faulhaber C. J. Linden M. A. Tesar M. A. Ferdig B. R. Livingston T. G. Therkildsen V. H. Frahm J. M. Lofshult P. L. Thompson F. F. Franco- J. H. MacKinnon J. W. Tills H. K. Fraser G. D. Mamoran D. R. Trausch J. F. W. Friedrichsen J. W. Marcil P. R. Turner R. M. Fussell N. L. Marfice J. M. Uhland S. K. Gambhir D. J. Matthews C. F. Vanecek J. K. Gasper J. M. Mattice G. L. Van Osdel W. G. Gates T. J. McIvor L. P. Walling M.'O. Gautier R. F. Mehaffey J. M. Waszak J. M. Glantz R. A. Miser W. O. Weber J. T. Gleason K. J. Morris G. R. Williams
. L. V. Goldberg D. C. Mueller S. J. Willrett R. J. Mueller W. C. Woerner iv i
PREFACE PERFORHANCE INDICATORS REPORT IMPROVEMENTS One section has been added to the Performance Indicators Report. This section is the Refueling Outage Section. Three indicators have been added which justified the addition of this new section. These are:
- 1) - The MWO Overall Status (1991 Refuelino Outaae) Indicator found on page 89 has been added to the Performance Indicators Report. This indicator shows the total number of MWO's that have been written for completion during the 1991 Refueling Outage and the number of MWO's ready for work (parts for these MWO's are staged, procedures are approved, and paperwork is ready for field use) . Also shown are the number of MWO's that are ready to work for the 1991 Refueling Outage. Any MWO's written after the start of the outage will be labeled as Emergent MW0's.
Additional data points will be added to this indicator as information becomes available.
- 2) The Proaress of 1991 Outaae Modification Plannina Indicator found on page 90 has been added. This indicator shows the number of modifications approved for planning (to determine feasibility) for completion during the 1991 Refueling Outage. Additional data points will be added to this indicator as information becomes available.
- 3) The Overall Pro.iect Status (1991 Refuelino Outaae) Indicator found on page 91 has been added to the Performance Indicators Report. This indicator shows the status of the projects which affect the scope of the 1991 Refueling Outage. Additional data points will be added to this indicator as information becomes available.
Four indicators have been changed. The Fuel Reliability Indicator is in the Operations Section, the- Maintenance Work Order Backloa (Corrective Non-Outaae) Indicator is 'in the Maintenance Section, the Number of Hot Soots Indicator is in the Chemistry and Radiological Protection Section, and the Inventory Accuracy Indicator is in the Material and Outside Services Section. The Fuel Reliability Indicator found on page 24 has been changed. The Industry Median value has been added to this indicator. This indicator uses a industry normalized letdown purification rate. The' fuel reliability factor was also calculated using Fort Calhoun's actual letdown purification rate. These calculations revealed that the use of the pl ant's actual letdown purification rate would result in an approximate 45% increase in the fuel reliability indicator data. The Maintenance Work Order Backloa (Corrective- Non-Outaae) Indicator found on page 42 has been changed. The goal for the number of open corrective non-outage MW0's has been changed to 500 open MW0's. This goal was previously set at 600 open MW0's. 1 i
PREFACE PERFORMANCE INDICATORS REPORT IMPROVEMENTS The Number of Hot Scots Indicator found on page 56 has been changed. The number of additional hot spots which were identified during the reporting has been added to this indicator. Previously, this indicator showed only the number of hot spots known to exist in the Fort Calhoun Station at the end of the reporting month. This change to this indicator should represent more accurately the involvement of the Station in reducing the number of hot spots. The Inventory Accuracy Indicator found on page 65 has been changed. The graphical presentation of this indicator has been modified. Previously, this indicator was shown in column graph form, but now it will be presented in line graph form. One indicator has been added to the Industry Key Parameters Section and the Operations Section. The Unolanned Safety System Actuations - (NRC Definition) Indicator found on page 21 has been added. This indicator shows the number of NRC definition safety system actuations each month, a twelve month running total of NRC definition safety system actuations, and the critical hours for the Fort Calhoun Station. The number of NRC definition safety system actuations include the High Pressure Safety Injection System (HPSI), the Low Pressure Safety Injection (LPSI). the Safety Injection Tanks, and the Emergency Diesel
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Generators. The NRC classification of safety system actuations includes actuations when major equipment is operated and when the logic systems ' for the safety systems are challenged. , l 2-l l-l-
l PURPOSE This program titled " Performance Indicators" is intended to provide selected Fort Calhoun plant performance information to OPPD's personnel responsible for optimizing unit performance. The information is presented i n a way that provides ready identification of trends and a means to track progress toward reaching corporate goals. The information can be used for assessing and monitoring Fort Calhoun's plant performance, with emphasis on safety and reliability. ~ Some performance indicators show company goals or industry information. This information can be used for comparison or as a means of promoting pride and motivation. 4 4 s 3-
SCOPE 4 1 In order for the Performance Indicator Program to be effective, , the following guidelines were followed while implementing this program: Select the data which most offectively monitors Fort 3 Calhoun's performance in key areas. Present- the data in a straight forward graphical format using averaging and smoothing techniques, include established corporate goals and industry information for comparison. Develop formal definitions for each performance parameter. , 4 This will ensure consistency in future reports and allow comparison with industry averages where appropriate. Comments and input
- are encouraged to ensure that this program is tailored to address the areas which are most meaningful to 4
the people using the report. l
ADVERSE TREND REPORT The Adverse Trend Report explains the conditions under which certain indicators are showing adverse trends. An indicator that is defined as AN ADVERSE TREND IS ONE IN WHICH THE DATA REPRESENTED FOR THREE CONSECUTIVE MONTHS IS SHOWING A DECLINE IN PERFORMANCE for that particular indicator. Indicators which show an apparent three month decline, but are uni considered an adverse trend, will display an explanation which defines the reason why an adverse trend does not exist. Enaineerina Assistance Reauest (EAR) Priority Breakdown - Page 76 The number of open EAR's has increased from 59 at the end of May of 1990 tc 4 at the end of September of 1990. The major reason for the increast a the number of open EAR's is the result of discrepancies between old procedures and the new procedures which are being upgraded by the Procedure Upgrade Project. Personnel Turnover Rate - Page 81 The personnel - turnover rate for the Nuclear Operations Division (NOD) and the Production Engineering Division (PED) has been increasing. There have been 30 resignations from N0D in the last 12 months and 11 resignations from PED in the last 12 months. f INDICATORS NEEDING INCREASED MANAGEMENT ATTENTION This section lists the indicators which show inadequacies as compared to the OPPD goal and indicators which show inadequacies as compared to the industry upper quartile. The indicators will be compared to the industry upper quartile as relevant to that indicator. Forced Outaae Rate - Page 18 The forced outage rate for the month of September 1990 was reported as being higher than the Fort Calhoun goal of 2.4%. This rise in the forced outage rate during the month of August was due to seal problems encountered in reactor coolant pump RC-3A. These problems resulted in 172.6 forced outage hours. During the month of September the plant was shutdown due to design basis questions. This forced outage resulted in 105.6 forced outage hours being reported. Unolanned Safety System Actuations - (INPO Definition) - Page 20 The Fort Calhoun Station has experienced an unplanned safety system actuation during 1990. This unplanned actuation was a start and load of DG-2 due to an inadvertent trip of backup lockout relay 86/2BF5. The Fort Calhoun goal for unplanned safety system actuations during 1990 was set at zero actuations. Gross Heat Rate - Page 22 The monthly gross heat rate for the months of August and September were reported as being above the Fort Calhoun monthly goal. Thase high monthly gross heat rates were due to two forced shutdowns of the plant which occurred during August and September. The year to date gross heat rate is currently above the goal of 10,326 BTV/KWH The gross heat rate values for January and February were high due to the fact that the first stage of the high pressure turbine was removed - during the months of January and February. During May startup from the 1990 Refueling Outage caused the gross heat rate to be high, t _During July, August, and September various derates, and two forced outages caused the gross- heat rate values for these months to be higher than the Fort Calhoun goal. i- Eouivalent Availability Facter - Page 23 The monthly EAF for September was below the goal of 93% due to the forced outage which occurred during September involving design basis questions. The year to date EAF is currently below the year to date goal of 56.4% due to various power fluctuations which occurred during the month of June and due to forced outage hours which occurred during the months of August and September.
-Fuel Reliability Indicator (FRI) - Page 24 The FRI has been above the Fort Calhoun goal of 1.0 nanocuries/ gram. The FRI value for September using the actual plant letdown rate was reported as 2.05'nanocuries/ gram.
INDICATORS NEEDING INCREASED MANAGEMENT ATTENTION (CONTINVED) DG Reliability last 100 DemenJ1 - Page 32 The diesel generator start and load reliability of DG-1 is currently below the Fort Calhoun goal of 95%. This is due to the fact that diesel generator DG-1 has experienced 7 start and load failures in its last 100 demands. DG Reliability last 20 Demands - Page 33 The start and load reliability of diesel generator DG-1 is below the Fort Calhoun goal of 95% reliability. This low start and load reliability for diesel generator DG-1 is due to two start and load failures which occurred in July 1990. These two failures were caused by high engine coolant temperature problems. Corrective Maintenance Backloa Greater Than 3 Months Old (Non-Outaae) Page 36 The percentage of open corrective non-outage MWO's older than 3 months old is currently above the industry quartile value of 45.8% due to 230 open MWO's that are older than 3 months old.
. Ratio'of Preventive to Total Maintenance - Page 37 The ratio of preventive to total maintenance was reported below tne Fort Calhoun goal of 60% and below the industry upper quartile value of 57.7%. This ratio decreased due to the high number of hours in which maintenance was involved in corrective maintenance activities associated with the forced outage which occurred in September.
Number of Out-of-Service Control Room Instruments - Page 39 The number of out-of-service control room instruments has been above the Fort Calhoun goal of 7 out-of-service control room instruments and above the industry upper quartile value of 7 out-of-service control room l instruments since November of 1989. 1 Check Valve Failure Rate - Page 46 The. Fort Calhoun check valve failure rate is currently above the industry check valve failure rate. The reason for the high check valve L failure rate is that the plant is performing maintenance on check valves which have not been tested for failures before. The check valve failure rate is expected to decrease as the check valves are maintained and monitored through the Check Valve Program. In-Line Chemistry Instruments Out-of-Service - Page 50 The number of instruments out of service at the end of. September was above the goal of 6 out-of-service instruments. The current number of chemistry instruments that are out-of-service is 7. 1 l-
INDICATORS NEEDING INCREASED MANAGEMENT ATTENTION (CONTINUED)
'otal Skin and Clothina Contaminations - Page 53 The total number of skin and clothing contaminations has been above the fort Calhoun goal of 150 contaminations since the month of April 1990.
The total number of skin and clothing contaminations has been above the industry upper quartile value of 129 contaminations since the month of March 1990. The high number of skin and clothing contaminations dyring the months of March and April 1990 was due to increased activity in the Radiation Controlled Area (RCA) associated with the 1990 Refueling Outage. Decontaminated Auxiliary Buildino - Page 54 The square footage of the auxiliary building which is decontaminated is currently below the Fort Calhoun goal of 85% (non-outage). This is due to activities which took place in the auxiliary building associated with the forced outage which occurred during September. Temoorary Modifications (Excludino Scaffoldino) Page 75 The number of temporary modifications which are installed in the plant is currently above the Fort Calhoun goal of 15 temporary modifications. The number of temporary modifications which are installed in the plant has been decreasing and is expected to keep decreasing. SAFETY ENHANCEMENT PROGRAM (SEP)- PERFORMANCE INDICATORS The purpose of the Safety Enhancement Program (SEP) Performance Indicators pages is - to list the indicators related to the SEP items with parameters > that can be trended. SEP Reference Number 15 - Increase HPES and IR Accountability ELqg Through Use of Performance Indicators Procedural Noncompliance Incidents (Maintenance) . .,. . . . . . 41 Total Skin and Clothing Contaminations . . . . . . . . . . . . . 53 1 Recordable Injury Cases frequency Rate . . . . . . . . . . . . . 79 Number of Personnel Errors Reported in LER's . . . . . . . . . . 80 j CAR's Issued versus Significant CAR's Issued versus NRC Violations Issued versus LER's Reported . . . . . . . . . . 97
.SEP Reference Number 20 - Quality Audits and Surveillance Programs are Evaluated, Improved in Depth and Strengthened CAR's Issued versus Significant CAR's Issued versus NRC Violations Issued versus L.ER's Reported . . . . . . . . . . 97 SEP Reference Number 21 - Develop and Conduct Safety System Functional-Inspections ,
CAR's Issued versus Significant CAR's Issued versus NRC Violations Issued versus LER's Reported . . . . . . . . . . 97 SEP Reference Number 24 - Complete Staff Studies Sta f fi ng Level . . . . . . . . . . . . . . . . . . . . . . . . . 82 SEP Reference Number 26 - Evaluate and Implement Station Standards for Safe Work Practice Requirements l. L Disabling Injury Frequency Rate ........... . . . . 27
- Recordable Injury Cases Frequency Rate . . . . . . . . . . . . . 79 I
SEP Reference Number 31 - Develop Outage and Maintenance Planning Manual and Conduct Project Management Training MWO Overall Status (1991 Refueling Outage) . . . . . . . . . . . 89 Progress of 1991 Outage Modification Planning. . . . . . . . . . 90 1 Overall Project Status (1991 Refueling Outage. . . . . . . . . . 91
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SAFETY ENHANCEMENT PROGRAM (SEP) PERFORMANCE INDICATORS (CONTINUED) SEP Reference Number 36 - Reduce Corrective Non Outage Backlog Maintenance Work Order Backlog (Corrective Non Outage Maintenance) . . . . . . . . . . . . . . 42 SEP Reference Number 41 - Develop and Implement a Preventive Maintenance Schedule Ratio of Presentive to Total Maintenance . . . . . . . . . . . . 37 Preventive Maintenance items Overdue . . . . . . . . . . . . . . 38 SEP Reference Number 43 - Implement the Check Valve Test Program Check Valve Failure Rate . . . . . . . . . . . . . . . . . . . . 46 SEP Reference Number 44 - Compliance With and Use of Procedures Procedural Noncompliance Incidents (Maintenance) . . . . . . . . 41 SEP Reference Number SR - Establish Supervisory Accountability for Workers Radiological Practices Radiological Work Practices Program. . . . . . . . . . . . . . . . 55 SEP Reference Number 54 - Complete Implementation of Radiological Enhancement Program Personnel Radiation Exposure (Cumulative) . . . . . . . . . . . 25 Volume of Low-Level Solid Radioactive Waste. . . . . . . . . . . 26 Total Skin and Clothing Contaminations . , , . . . . . . . . . . 53 Decontaminated' Auxiliary Building. . . . . . . . . . . . . . . . 54 SEP Reference Number 58 - Revise Physical Security Training and Procedure Program Loggable/ Reportable Incidents (Security) . . . . . . . . . . . . 59 Security Incident Breakdown ...t. . . . . , . . . . . . . 60 Security System Failures . . . . . . . . . . . . . . . . . . . . , 61 gE. p Number 60 - Improve Controls Over Surveillance Test Program Missed Surveillance Tests Resulting in Event Reports . . . . . . . . . . . . . . . . . . . . . 43 SAFETY ENHANCEMENT PROGRAM (SEP) PERFORMANCE INDICATORS (CONTINUED) SEP Reference Number 61 - Modify Computer Program to Correctly Schedule Surveillance Tests Number of Missed Surveillance Tests Resulting in Licensee Event Reports . . . . . . . . . . . . . . . . . . . . . 43 SEP Reference Number 62 - Establish Interim System Engineers Temporary Modi fications. . . . . . . . . . . . . . . . . . . . . 75 Engineering Assistance Request Priority Breakdown. . . . . . . . 76 SEP Reference Number 62 - Establish Interim System Engineers (Continued) Engineering Change Notice Status . . . . . . . . . . . . . . . . 77 Engineering Change Notice Breakdown. . . . . . . . . . . . . . . 78 SEP Reference Number 68 - Assess Root Cause of Poor Operator Training and Establish Means to Monitor Operator Training SRO License Examination Pass Ratio . . . . . . . . . . . . . . . 83 R0 License Examination Pass Ratio . . . . . . . . . . . . . . . 84 License Candidate Exams. . . . . . . . . . . . . . . . . . . . . 85 SEP Reference Number 71 - Improve Controls over Temporary Modifications Temporary Modifications ....................75 a n
c PERFORMANCE INDICATORS INDEX TO GRAPHS INDUSTRY KEY PARAMETERS i Forced Outage Rate . . . . . . . . . . . . . . . . . . . . . . . 18 Unplanned Automatic Reactor Scrams While Critical. . . . . . . . 19 Unplanned Safety System Actuations - (INPO Definition) . . . . . 20 l Unplanned Safety System Actuations - (NRC Definition). . . . . . 21 Gros s Heat Rate. . . . . . . . . . . . . . . . . . . . . . . . . 22 l Equivalent Availability Factor . . . . . . . . . . . . . . . . . 23 Fuel Reliability Indicator . . . . . . . . . . . . . . . . . . . 24 Personnel Radiation Exposure (Cumulative). . . . . . . . . . . . 25 ; Volume of Low level Solid Radioactive Waste. . . , . . . . . . . 26 Disabling injury Frequency Rate. . . . . . . . . . . . . . . . . 27 l l
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E _ PERFORMANCE INDICATORS , INDEX 10 GRAPHS (CONTINUED) OPERATIOM Station Net Generation . . . . . . . . . . . . . . . . . . . . 17 Forced Outage Rate . . . . . . . . . . . . . . . . . . . . . . . 18 Unplanned Automatic Reactor Scrams While Critical. . . . . . . . 19 Unplanned Safety System Actuations (INPO sefinition) . . . . . . 20 h Unplanned Safety System Actuations (NRC Definition). . . . . . . 21 Gross Heat Rate. . . . . . . . . . . . . . . . . . . . . . . 22 Equiv31ent Availability Factor . . . . . . . . . . . . . . . . 23 fuel Reliability Indicator . . . . . . . . . . . . . . . . . . . 24 L Daily Thermal Output . . . . . . . . . . . . . . . . . . . . . . 28 f Equipment Forced Outages per 1000 Critical Hours . . . . . . . . 29 Operations and Maintenance Budget. . . . . . . . . . . . . . . . 30 Document Review. . . . . . . . . . . . . . . . . . . . . . . . 31 tiAINTENANCE y Diesel Generator Reliability (100 Demands) . . . . . . . . . . . 32 Diesel Generator Reliability (20 Demands). . . . . . . . . . . . 33 Age of Outstanding Maintenance Work Orders . . . . . . . . . . . 34 E 35 Maintenance Work Order Breakdown . . . . . . . . . . . . . . . . Corrective Maintenance Backlog >3 Months Old . . . . . . . . . . 36
= 37 Ratio of Preventive to Total Maintenance . . . . . . . . . . . .
Preventive Maintenance items Overdue . . . . . . . . . . . . . . 38 39 Number of Out-of Service Control Room Instruments. . . . . . . . 43 Maintenance Overtime . . . . . . . . . . . . . . . . . . . Procedural Noncompliance incidents (Maintenance) . . . . . . . . 41 Maintenance Work Order Backlog (Corrective Non-Outage) . . . . . 42 13-m
m PERFORMANCE INDICATORS INDEX TO GRAPHS (CONTINUED) MAINTENANCE fCONTI M D1 Number of Surveillance Tests Resulting in Licensee Event Reports . . . . . . . . . . . . . . . . . . . . . 43 Number of Nuclear Plant Reliability Data System (NPRDS) Reportable Fail ures. . . . . . . . . . . . . . . . . . . . . . . 44 Maintenance Effectiveness. . . . . . . . . . . . . . . . . . . . 45 Check Valve Failure Rate . . . . . . . . . . . . . . . . . . . . 46 i CHEMISTRY AND RADIOLOGICAL PROTECTION Personnel Radiation Exposure (Cumulative). . . . . . . . . . . . 24 Volume of low-level Solid Radioactive Waste. . . . . . . . . . . 25 Secondary System Chemistry . . . . . . . . . . . . . . . . . . . 47 Primary System Chemistry Percent of Hours Out of Limit . . . . 48 Auxiliary Systems Chemistry Hours Outside Station Limits . . . . 49 In Line Chemistry Instruments Out of Service . . . . . . . . . . 50 i Hazardous Waste Produced . . . . . . . . . . . . . . . . . . . . 51 Maximum Individual Radiation Exposure. . . . . . . . . . . . . . 52 x Total Skin and Clothing Contaminations . . . . . . . . . . . . . 53 Decontaminated Auxiliary Building. . . . . . . . . . . . . . . . 54 Radiological Work Practices Program. . . . . . . . . . . . . . . 55 Number of Hot Spots . . . . . . . . . . . . . . . . . . . . . . . 56 Gaseous Radioactive Waste Being Discharged to the Environment. . 57 Liquid Radioactive Waste Being Discharged to the Environment . . 58 i SECURITY loggable/ Reportable incidents (Security) . . . . . . . . . . . . 59 Security incident Breakdown, , . . . . . . . . . . . . . . . . . 60 Security System Failures . . . . . . . . . . . . . . . . . . . . 61 l
PERFORMANCE INDICATORS INDEX TO GRAPHS (CONTINUED) ; MATERIALS AND OUTSIDE SERVICES Amount of Work On Hold Awaiting Parts. . . . . . . . . . . . . . 62 l Spare Parts inventory Value. . . . . . . . . . . . . . . . . . . 63 Spare Part s i s sued . . . . . . . . . . . . . . . . . . . . . . . 64 Inventory Accuracy . . . . . . . . . . . . . . . . . . . . . . . 65 Stockout Rate. . . . . . . . . . . . . . . . . . . . . . . . . . 66 Warehouse Receipts . . . . . . . . . . . . . . . . . . . . . . . 67 Warehouse i s sue s . . . . . . . . . . . . . . . . . . . . . . . . 68 Warehouse Returns. . . . . . . . . . . . . . . . . . . . . . . . 69 l Material Requests Awaiting Approval . . . . . . . . . . . . . . . 70 Expedited Purchases. . . . . . . . . . . . . . . . . . . . . . . 71 Invoice Breakdown. . . . . . . . . . . . . . . . . . . . . . . . 72 Material Request Planning. . . . . . . . . . . . . . . . . . . . 73 DESIGN ENGINEERING Outstanding Modifications. . . . . . . . . . . . . . . . . . . . 74 Temporary Modifications. . . . . . . . . . . . . . . . . . . . . 75 Engineering Assistance Request (EAR) Priority Breakdown. . . . . 76
- Engineering Change Notice Status . . . . . . . . . . . . . . . . 77 Engineering Change Notice Breakdown. . . . . . . . . . . . . . . 78 INDUSTRIAL SAFETY Disabling injury Frequency Rate. . . . . . . . . . . . . . . . . 26 I
Recordable Injury Cases Frequency Rate . . . . . . . . . . . . . 79 HUMAN RESOURCES l-i Number of Personnel Errors Reported in LERs. . . . . . . . . . . 80 l l l 1 l
PERFORMANCE INDICATORS INDEX TO GRAPHS (CONTINUED) HUMAN RESOURCES (CONTINVED) Personnel Turnover Rate. . . . . . . . . . . . . . . . . . . . . 81 St a f fi ng Level . . . . . . . . . . . . . . . . . . . . . . . . . 82 TRAINING AND OVAllFICATION SRO License Examination Pass Ratio . . . . . . . . . . . . . . . 83 R0 License Examination Pass Ratio. . . . . . . . . . . . . . . . 84 License Candidate Exams. . . . . . . . . . . . . . . . . . . . . 85 Hotlines . . . . . . . . . . . . . . . . . . . . . . . . . . . . 86 Classroom (Instructor) Hours . . . . . . . . . . . . . . . . . . 87 Total Hours of Student Training. . . . . . . . . . . . . . . . . 88 REFUELING OU1 AGE MWO Overall Status (1991 Refueling Outage) . . . . . . . . . . . 89 Progress of 1991 Outage Modification Planning. . . . . . . . . . 90 Overall Project Status (1991 Refueling Outage) . . . . . . . . . 91 OVAllTY ASSURANCE Number of Violations per 1000 Inspection Hours . . . . . . . . . 92 Cumulative Violations and Non Cited Violations (NCV's) . . . . . 93 Percent of CAR's Greater Than Six Months Old . . . . . . . . . . 94 Overdue and Extended Corrective Action Reports . . . . . . . . . 95 Corrective Action Reports Current Status . . . . . . . . . . . . 96 CAR's !ssued versus Significant CAR's issued versus. . . . . . . 97 NRC Violations issued versus LERs Reported l l 16-
1 l l 500000- 1 IStation Net Generation 400000-M I e 9 l a W 300000-a t , t H 200000-o u , r s 100000-O' Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 STATION NET GENERATION This indicator shows the net generation of the Fort Calhoun Station for the reporting month. During the month of September 1990, a net total of 272,573.0 MWH was generated by the Fort Calhoun Station. The net generation for the month of August was low due to a forced outage which occurred during the month. This forced outage was due to seal problems on reactor coolant pump RC 3A, The net generation for the month of September was also low due to a forced outage. The forced outage was due to a design basis question on containment cooling capabilities. The not generation totals for the months of March and April were zero and the net generation total for the month of May was low due to the plant being shutdown for the 1990 Refueling Outage. Adverse Trend: None
- Forced Outage Rate 6 -G- fort Calhoun Goal G Industry Upper 10 Percentile 5-GOOD 4- 4 R
a t 3-e o....o.- q...o...s --o...o...q...o...s..O--D 2-1.4 , l-0 0 D' D ' O ' ^ D ~ ' ' D ' '
- D ~D 0 0 9 O O 3
'87 '88 '89 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 FORCED OUTAGE RATE The forced outage rate was reported as 3.2% for the month of September 1990. The continuation of the forced outage rate for the fort Calhoun Station during the month of September was due to a forced outage which occurred due to design basis questions on containment cooling capabilities.
The last forced outage at fort Calhoun occurred in August of 1990. The industry upper ten percentile value for the forced outage rate is 0.25%. The 1990 goal for forced outage rate is 2.4% and is based on seven days. of forced outage time. The basis for establishing the 1990 performance goals can be found on page 114. Adverse Trend: None - Reason for increase is given above. l 10-
1 5 n Reactor Scram G- Fort Calhoun Goal O Industry Upper 10 Percentile 4-S GOOD 3 c r + a m , 2-1 1- 0---- G --- G -- - e-- -- o---- o--- - o ---- o -- -- o - ---o -- - -o - - - o
$rei 0 0 0 "
0 C O ;_: m- :< .
'86 '87 '88 '89 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 UNPLANNED AUTOMATIC REACTOR SCRAMS WHILE CRITICAL There were no unplanned automatic reactor scrams in September. It has been 1,551 days since the last unplanned automatic reactor scram which occurred on July 2, 1986.
The 1990 goal for unplanned automatic reactor scrams while critical has been set at 1. The industry upper ten percentile value is zero scrams per unit on an annual btsis. The Fort Calhoun Station is currently in the upper ten percentile of nuclear plant performance in this area. Adverse Trend: None 1 4- M Safety System Actuations e- Fort Calhoun Goal O Industry Upper 10 Percentile 3-A C t j GOOD k2 o k n s 1- &--- O---- Q, N uis
'\ i Vi$
0 0 0 0 '87 '88 '89 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Ag S ! 1989 1990 UNPLANNED SAFETY SYSTEM ACTUATIONS - (INPO DEFINITION) There were no unplanned safety system actuations during the month of September 1990. The 1990 goal for the number of unplanned safety system actuations is zero. This goal is based on past performance at the Fort Calhoun Station. The industry upper ten percentile value for the number of unplanned safety system actuations per year is zero. Adverse Trend: None Q Safety System Actuations (SSA's)
- 12 Month Running Total SSA's
--- Critical Hours 10- 1000 1 N 8- 800 N u , ,,,---, f,,,,,---, u m .
,i \ l \ ,i \ ;, , , ,,\ m b < \ l 'i \ ; \ b 6- \/ #
600f S I
'\, l V o -
, o i
.I \, l f
4' 400 g t S f ) l g3 S l o l !, A ; ,
; u ?gti ! !
l r 5 5 2- l - , l 200 l :n ll l
. : A % ,i y I
, mt +
M 0 0 0
'88 '89 JFMAMJJAS0ND JFMAMJJA S0ND 1989 1990 UNPLANNED SAFETY SYSTEM ACTUATIONS - (NRC DEFINITION)
The Unplanned Safety System Actuations - (NRC Definition) Indicator has been added to the- Performance Indicators Report. This indicator shows the number of safety system actuations (SSA's) which include the High and Low Pressure Safety Injection Systems, the Safety Injection Tanks, and the Emergency Diesel Generators. The NRC classification of SSA's includes actuations when major equipment is o)erated and when the logic systems for these safety systems are cla11enged. The last event of this type occurred in June 1990 when Diesel Generator D 1 was started due to a turbine trip. This trip was a result of a failure to reset the plant output circuit breaker following an attempt to synchronize the main generator. The majority of SSA's displayed above were related to 1990 Refueling l Outage activities and are currently being reviewed under the Safety i System Actuation Reduction Program. The goal of this Program is to reduce the number of SSA's at Fort Calhoun. Adverse Trend: None - Program to reduce the number of SSA's is being implemented. l
13000- [_J Monthly Gross Heat Rate
- Year-to Date Gross Heat Rate G- Fort Calhoun Monthly Goal
-+- Fort Calhoun Year to Date Goal 12000 O Industry Upper 10 Percentile B
T ' U
/
K GOOD y 11000-H 10520
&,s -
e a U~ E U~O U U ~ O ~ O 10014 s m p, p S. ~ - M qlf$ , 9000
'87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 GROSS HEAT RATE The gross heat rate for the Fort Calhoun Station was reported as 10,347 BTV/KWH during the month of September. This monthly gross heat rate was above the monthly gross heat rate goal of 10,125 BTV/KWH The high monthly gross heat rate was due to the shutdown of the plant which occurred due to a forced outage during the month of September.
The year-to date gross heat rate was reported as 10,409 BTU /KWH. This year to date value was higher than the year to date gross heat rate goal of 10,294 BTV/KWH. The year-to-date gross heat rate is above the Fort Calhoun goal due to the fact that the first stage of the high pressure turbine was removed prior to the 1990 Refueling Outage. Additionally, the gross heat rate values for the months of May, June, and July 1990, were high due to startup after the 1990 Refueling Outage and various derates. The year-to date gross heat rate value is expected to decrease as the river water temperature decreases. The above monthly and year to-date Fort Calhoun goals are the best gross heat rate that can be achieved by the Fort Calhoun Station. Currently the plant is above the year-to date gross heat rate goal. If the station operates at 100% for the rest of 1990, this ! goal will be approached but will not be achieved. The gross heat rate industry upper ten percentile value is 9,935 BTV/KWH. Adverse Trends: None I IMonthly EAF '
- Year-to-Date EAF jy G- Fort Calhoun Monthly Goal 1
-+- Fort Calhoun Year to-Date Goal GOOD
-G Industry Upper 10 Percentile 100- l
&- - - - -& - - - G -- - -- -O
_%, O' ,
\
p-77 80 Dy G- O --G- -O~ O- - G - - G -D- -O l 71 i 1' l l
" 66 i !
q 60- \' r '
/ /.
~
/, e s f N
[40-
\ ,/
h~ h. - i, .y . s - -
\ l 20-
? \ l W .
i l l l , 7
\
g ; l O 6 ^ -
'87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 10VIVALENT AVAILABILITY FACTOR The Equivalent Availability Factor (EAF) Indicator has been changed.
l This indicator now shows a monthly EAF goal as well as a year-to date l EAF goal. The 12 month average EAF has been deleted and replaced with year-to date data. l l The EAF was reported as 73.1% for the month of August. This EAF was lower than the Fort Calhoun monthly goal of 93% due to a forced outage which occurred during the month of August. This forced outage occurred due to problems encountered with a seal in reactor coolant pump RC 3A. l The year-to-date EAF was reported as 48.8%. This year-to date value was lower than the year-to-date goal of 51.9%. -The low year-to-date EAF was due to various power fluctuations which occurred during the month of June and the forced outage which occurred during the month of August. The EAF industry upper ten percentile value is 82.5%. Adverse Trends: None 8 - Fuel Reliability Indicator G- Fort Calhoun Goal
< O Industry Upper 10 Percentile Industry Median 6-n a
n g~o 1 -
; 4 2.4 u
\ GOOD
{ 41 s 4" u * \
*RAg 5 rBfd v, 1.5 r m
1 i,Q n
" a m 2' \d 6 a a a E O
'?
Q$ y Q
$g
& ~ ~ O - - - -O - - - s - - - O - - - -& - - - & - -- O - - - tr - - O - - - -t> - - - D h
t$$lT vdl 0 m n n n n g g .1, o .g g- 9 !
'88 '89 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 FUEL RELIABillTY INDICATOR The Fuel Reliability Indicator has been changed. The industry median value has been added to this indicator.
The FRI was reported as 1.40 nanocuries/ gram for the ; month of September. This INPO indicator uses an industry normalized letdown purification rate. The FRI was also ; calculated using Fort Calhoun's actual letdown purification rate. These calculations revealed that the use of .the plant's actual letdown purification rate would result in an approximate 45% increase in the FRI data. The FRI value using the plant's actual letdown purification rate was reported as 2.05 nanocuries/ gram. The 1990 fuel reliability goal has been set at 1.0 nanocuries/ gram. The fuel reliability indicator industry upper ten percentile value is 0.04 nanocuries/ gram. I Adverse Trend: None 1 l- - l l
1 Personnel Radiation Exposure 388 400 G- Fort Calhoun Goal l O Industry Upper 10 Percentile h,,t s d@ GOOD l J**1 300- 1 22 + e .- D
,, - & _ _ 9. . . ,gj m -
g...O -9 . . . .O W
- m. . .
vp 11 R
;4 g gnn. -
H a,
*. O O O0 0 -O O- O- D- O O O sj ,
c
$lli #\-
93.4 100-
/
lg g); -
; ,o
/
jhi, i, ,-
/
^
T O'"
'87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 PERSONNEL RADIATION EXPOSURE (CUMULATIVE)
During September 1990, 5.8 man rem was recorded by TLD's worn by personnel while working at the Fort Calhoun Station. The monthly cumulative exposure goal for September was 269.3 man-rem while the actual cumulative exposure through September totaled 251.3 man rem. The exposure cumulated in 1990 has been high due to the increased activity in the Radiation Controlled Area (RCA) associated with the 1990 Refueling Outage. The personnel radiation exposure industry upper ten percentile is 166 man rem per unit per year. Adverse Trend: None SEP 54 25-
O Monthly Radioactive Waste Shipped 12500- - Cumulative Radioactive Waste Shipped
-G- Fort Calhoun Goal s Industry Upper 10 Percentile C
u I GOOD L c 7500- 4, 6195 F m e e 4454 , t 5000- o---- o- - - -e---- o -- -o --- e-- --o ---e-- --o -- - e - -- o - -- o 7 / M M Q g o. - o . O O O D- -O O O O O
*< 1722 Y 2500-N,) E SI g
3 'i 9 0
'87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 -
VOLUME OF LOW LEVEL SOLID RADIOACTIVE WASTE The above graph shows the amount of low-level radioactive waste shipped off site for disposal. The table below lists the amount of waste actually shipped off-site for disposal and the amount of low level radioactive waste which is in temporary storage. The volume of solid radioactive waste is (cubic feet): Amour,t Shipped in September - 0.0 Amount in Temporary Storage - 983.0 1990 Cumulative Amount Shipped - 1568.6 1990 Goal - 5000.0 The industry upper ten percentile value is 3,072 cubic feet per unit per year. The Fort Calhoun Station was in the upper ten percentile of nuclear plants for this indicator in 1986, 1987 and 1988. Adverse Trend: None SEP 54 l u
\
2- E 1990 Disabling Injury Frequency Rate
- 1989 Disabling Injury frequency Rate 1.75- 5 Year Average Disabling Injury Frequency Rate e- Fort Calhoun Goal 1.5- G Industry Upper 10 Percentile 1.25-R a GOOD 3
t s, 4
.75-
.5 , . s'
- o. . .. . e. . . h g. . , . . . .o.....o..._ o .....s ....o TX L aA 0
Dj 5
~%
m m - - - - m m Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec DISABLING INJURY FRE0VENCY RATE (LOST TIME ACCIDENT RATE) This indicator shows the current monthly disabling injury rate in column form. The 1989 disabling injury frequency rate and the Fort Calhoun Station 5 year average disabling injury frequency rate are also shown. There were zero disabling injuries reported at the Fort Calhoun Station in September. The total number of disabling injuries in 1990 is one. l The 1990 disabling injury frequency rate goal was set at 0.31% and l was based on one disabling injury occurring in 1990. The industry upper ten percentile disabling injury frequency rate-is 0%. The year end disabling injury frequency rates for 1987, 1988, and i 1989 were 0.6, 1.6, and 0.4 respectively. Adverse Trend: None SEP 26
- - Thermal Output ;
- Technical Specification Limit
-O Fort Calhoun Goal 1500: ro ^^^;m ;m esc;;;; s;; ;m ^
. co 1200-' (
,y (j g 900- 'j a .! w - , a 600- . t ; , .j s : ;1 300 f 'g 0< , , , , , , , , , , , , , , , a 1 7 14 21 28 September 1990 DAILY THERMAt OUTPUT The above thermal output graph displays the daily operating power level, the 1500 thermal megawatt average technical specification limit, and the 1495 thermal megawatt Fort Calhoun goal. The cross hatched area represents the difference between the maximum allowable operation and the actual plant operation. The percent power operation of the Fort Calhoun Station during September 1, 1990 through September 3, 1990 was below 30%. The plant was then operated at approximately 100% until September 29, 1990 when the plant was shutdown for a forced outage. This forced outage was due to design basis questions. It must be noted that normal update oscillations on test point XC105 prevent Operations from continually operating the plant above 1495 thermal megawatts. Because of these oscillations, power is sometimes backed down to decrease the risk of violating the 1500 thermal megawatt technical specification limit. Adverse Trend: None 2-
- Equipment Forced Outage Rate 1.8-1.6-1.4-1.2 GOOD R
a + 1 t ,
.8-
.6-
.4-
,,* I 3,,, -
.2-0 0 0
'87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 E0VIPMENT FORCED OUTAGES PER 1000 CRITICAL HOURS There wert zero equi) ment forced outage hours reportec during the month of September 1990.
The last equipment forced outage occurred in August of 1990 and vas due to seal problems on rtactor coolant pump RC 3A l Adverse Trend: None i 1 1 t
l
- Actual Operations Expenditures
, )
+ Operations Budget gy100-i i i o l 50-na
" -/ i 5 d' , . l
$ g5
,/~__,
s O' Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 40 3
- Actual Maintenance Expenditures
"" " """ "9 M 30-i 1d #-
1o y9 p"y i1
/ ~~",g *l sr1- 0 ,/,
5 0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 OPERATIONS AND MAINTENANCE BUQQ[I The Operations and Maintenance Budget Indicator shows the budget year to date as well as the actual expenditures for operations and maintenance for the Fort Calhoun Station. The budget year-to-date for Operations was 61.2 million dollars for September while the actual cumulative expenditures through September totaled 53.3 million dollars. The budget year-to date for Maintenance was 20.8 million dollars for September while the actual cumulative expenditures through September totaled 15.1 million dollars. Although Operations and Maintenance are currently 13.6 million dollars under budget, a cost variances study from January through August 1990, predicts that Operations and Maintenance will- be approximately 8.7 million dollars under budget at year end 1990. Adverse Trends: None 1500- .. Documents Scheduled for Review x- Documents Reviewed
+ Overdue Documents X 1200- U ND
", 900- l bu l \
em - l \ re l \ i n 600- l \ 0 t l \ ! : is l \ ! \ l \ 300- l \\ n ;
,e' \ l \'
x 's , .... -g -4, , x [ y.N "h.N
; f. 4"',,,,7 ~~Y "3
((_ Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 DOCUMENT REVIEW This indicator shows the number of biennial reviews completed during the reporting month, the number of biennial reviews scheduled for the reporting month, and the number of biennial reviews that are overdue. These document reviews are performed in-house and include Special Procedures, the Site Security Plan, Maintenance Proceddres, Preventive Maintenance Procedures, and the Operating Manual. During September there were 36 document reviews completed while 35 document reviews were scheduled. At the end of September, there were 41 document reviews overdue. The overdue document reviews at the end of September consisted primarily of maintenance documents. During the month of September there were 15 new or renamed documents reviewed. These new or renamed documents will need to be reviewed again in 1992. The high number of documents scheduled for review for the month of June 1990 was due to the high number of document reviews that were completed during the- month of June 1988. The reviews that were completed during June 1988 were due to be reviewed in June 1990. Adverse Trend: None 31
100- ; Diesel Generator No. 1 98; X- Diesel Generator No. 2 O- Fort Calhoun Goal 96-
- o. . . . . e . . . . e . . . q . . . . s . . . . e . . . . o . . . . q. . . . . e . . . . .e . . . . q. . . . . e 94- .x- x x -x - -; :- -K -x X X- X - . l l p
92-e r 90-C e 88- ^ n . t 86- GOOD 84-82-80 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 DG REllABILITY LAST 100 DEMANDS Diesel generator D 1 did not have a start and load failure during September 1990. Diesel generator D1 has a 93 percent reliability factor over the last 100 valid demands. Diesel generator D 2 did not have a start and load ftilure during September 1990. Diesel generator D2 has a 95 percent reliability factor over the last 100 valid demands. At the present time, the Fort Calhoun Station is exploring the possibilities of a program for improving the reliability of the Emergency Diesel Generators. The Fort Calhoun goal for the diesel generator reliability is 95%. D2 curre.ntly meets this goal over the last 100 demands on the unit. Adverse Trend: None
+ Diesel Generator No. 1
-X Diesel Generator No. 2 G- Fort Calhoun Goal 100- l ; ; ; ; :
95- 0-- - - - G --- -- D - --- + -- -- e--- - - - - e -- - - G - - - - a - - - - e - - - - G - - - - - e P e r C 90- , ; , n t A 85- GOOD 80 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 DG REllABillTY LAST 20 DEMANDS Diesel generator D 1 did not have a start and load-failure during September 1990. Diesel generator D 1 has a 90 percent reliability factor over the last 20 valid demands. Diesel generator D 2 did not have a start and load failure during September 1990. Diesel generator D 2 has a 95 percent reliability factor over the last 20 valid demands. At the present time, the Fort Calhoun Station is exploring the possibilities of a program for improving the reliability of the Emergency Diesel Generators. The fort Calhoun goal for the diesel generator reliability for the last 20 demands is set at 95%. Diesel D-2 presently meets this goal. Adverse Trend: None l l 400-M July 1990
' "9" 0
u I ISeptember 1990 300-l t a , n d i 200-9 =
. me M gj W =r; O 100- kHi -
@$ ifMW3 s ver am 0- -
0-3 36 69 9-12 >12 Age in Months AGE OF OUTSTANDING MAINTENANCE WORK ORDERS (CORRECTIVE NON 0UTAGE) This indicator shows the age of corrective non-outage maintenance work orders (MWO's) remaining open at the end of the reporting month, idyytrseTrend: None 500-E July 1990
@ August 1990 El--- 1 ISeptember 1990 400 ,
l
\
300-s we
\
$ I
$$ J@? @
200- S$$ $N l M3 22:
. EN S$
w: mu
;iul im an -
100- Es tgi My
. S ne:
wa
$S a:_a 35 am 9&E :E,C =5 Ed?E 0-
" 5h -
Total Open Total Open Open Open MW0s Open Safety High
> 3 Months Safety Related MW0s Priority Old Related MW0s MW0s MW0s > 3 Months Old MAINTENANCE WORK ORDER BREAKDOWN (CORREC11VE NON-0UTAGE)
This indicator shows the total number of corrective non-outage MW0's remaining open at the end of the reporting month, along with a breakdown by several key categories. Adverse Trend: None l l 1
*35-
- Corrective Maintenance Backlog > 3 Months Old
<>- Industry Upper Quartile ,
l 80-
. , )1 60- / I P .
o.._. o._ _o _ o. .4 - O - O --O - --O - -O O- O c 40 e n t - GOOD 20-t 0 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 CORRECTIVE MAINTENANCE BACKLOG GREATER THAN 3 MONTHS OLD (NON 0VIAGE) This indicator shows the percentage of open corrective non outage maintenance work orders that are greater than three months old at the end of the reporting month. The percentage of open corrective non outat;c maintenance work orders that are greater thin three months old at the end of September wts reported as 56.7% The industry upper quartile value for corrective maintenance backlog greater than 3 months old is 45.8%. Adverse Trend: None
- Ratio of Preventive to Total Maintenance
+ Industry Upper Quartile 90- -G- Fort Calhoun Goal 80-70-P
[ 60- p ---- o----- o- ---9 --- 9 ---- o-----o --.- y - ...g ---- o-.--.gf -- _o c . V' V~ V- 'V~ N 'V V V -V V- v- v e n 50-t .
^
40-30 20 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 RATIO 0F PREVENTIVE TO TOTAL MAINTENANCE (NON 0UTAGE) The ratio of preventive to total maintenance indicator shows the ratio of completed non outage preventive maintenance to total completed non outage maintenance. The ratio of preventive to total maintenance at the Fort Calhoun Station decreased to 54,9% in September The low ratios in August and September were due to the increased involvement of maintenance in corrective maintenance activities associated with the two forced outages which occurred in August and September. The Fort Calhoun goal is to have a ratio of preventive to total maintenance greater than 60%. l The industry upper quartile value for the ratio of
- preventive to total maintenance is 57.7%.
Adverse Trend: None - Reason for trend is given above. SEP 41 L
- Preventive Maintenance items Overdue 5- o- Industry Upper Quartile O- Fort Calhoun Goal 4-GOOD P 4 e 3-r C -
e
- 2-
. c>. .q- o. o. .o C ---- e ---- G-----G-----o -----O s ----o---- O ---- O -----O ---- O [
~
O Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 EREVENTIVE MAINTENANCE ITEMS OVERDVE , The purpose of this indicator is to monitor progress in the administration and execution of preventive maintenance programs. A small percentage of preventive maintenance items overdue indicates a station commitment to the preventive maintenance program and an ability to plan, schedule, and perform preventive maintenance tasks as programs require. During September 1990, 917 PM items were completed. A total of 2 PM items were not completed within the allowable grace period. The fort Calhoun goal is to have less than 1.2% preventive maintenance items overdue. The industry upper quartile for preventive maintenance items overdue is 1.2%. The Fort Calhoun Station is currently performing in the industry upper quartile for this indicator. Adverse Trend: None SEP 41 38-
1 40 Wi Total Control Room Instruments Out-of-Service
<>- Industry Upper Quartile For Total Out-of-Service Instruments G- Fort Calhoun Goal for Total Out-of-Service Instruments 30- -
I GOOD m$ 7-? Nn a N us
- 4' ,,2 Ot - f .M br '1 q
's eu 20- ~~0 cf E f .*' 05 ki rm s!$; Yn, 3 d ;,, 4 gj e 4 4 s" ;d on #' d Vj .,.4 a ft i*l ~~~;' d '
4 2i s ,' 4 ij IM 3 sg 10- 7
~~~
7 y
$ b p bi ~y ijq W b. . f$ b ..
+f O~. .&r4uy 4 4y.,
4;;. wg :y ~4 c4 gyj tG y, ;pi. um
,.p.7 . . .,4 -..
. ~4, g3 ..
9% .m .._ 4 ... ... 4y, ..
, 4, ,4, ...
9;: 79 ga! m %; y & +y: } 7, A g+ y'
~ ,-
'Ag j
3,9n +4 up j" py c ,p! s, 4r&g Y j
? - ;Q;,g
;p
,.s f.g prp
%%g q;;m; e %A #,, s % :tWi M3 e3.,) ' ch yw
~" "
24 M &g$ a &,
"~
Ms'd g'(g M%q
~
'~ J*6g1,e +-
%4
- 0-Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 NUMBER OF OUT-OF SERVICL CONTROL ROOM INSTRUMENTS This indicator shows the number of out of service control room instruments, the industry upper quartile for this indicator, and the Fort Calhoun goal.
There was a total of 23 out-of-service control room instruments at the end of August. The Fort Calhoun goal is to have less than 7 out of service control room instruments. The industry upper quartile value for the number of out-of-service control room instruments is 7. Adverse Trend: None 80-
- Maintenance OvertimeI 12 Month Average G- Fort Calhoun Goal GOOD Y
60-
,0------O P ,
e '
'\ ~
g. 40- N, c / e / \ .
\,
n , j t ; >
& - - - - G-- --- G - -- - - O GF---- G--- -- O -- - - - O X b, 20-
^w:
0 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 MAINTENANCE OVERTIME The Maintenance Overtime Indicator monitors the ability to perform the desired maintenance activities with the allotted resources. Excessive overtime indicates insufficient resource allocation and can lead to errors due to fatigue. The percent of overtime hours with respect to normal hours was reported as 8.3% during the month of September 1990. The 12 month , average percentage of overtime hours with respect to normal hours was reported as 17.1%. The high percentage of overtime hours reported for the months of February 1990 through May 1990 was due to increased maintenance support associated with the 1990 Refueling Outage. The high percentage of overtime hours reported for August and September 1990 was due to maintenance activities associated with the 2 forced outages during these months. The Fort Calhoun goal for the percent of maintenance overtime hours worked has been set at 25% for non outage months and 50% for outage months. Adverse Trend: None
-40 l
20- 1 IOpenIR'sRelatedtotheUseofProcedures(Mainterance) E Closed IR's Itelated to the Use of Procedures (Maintenance) li Procedural Noncompliance IR's (Maintenance) N 15-u m b , e r o 10-f 88 I ~3 R e ., s ~ 55 5 r 33
~"
33 l'i '
, 3 ~
3 l 22 e e h,1 3 d d ~Q1_ 1 11 3 1 g 40 s o 000 'B 'E BE FF]o yo oo[ loo 000 000 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE) This indicator shows the number of identified Maintenance Incidents Reports (IR's) that are related to the use of procedures, the number of closed IR's that are related to the use of procedures (includes IR's that were caused by procedural noncompliance), and the number of closed IR's that were caused by procedural noncompliance. It should be noted that the second and third columns will lag behind the first column until the IR's are closed. This reporting method is due to the process in which IR's receive category codes. IR's receive their category codes when they are closed. Adverse Trend: None SEP 15 & 44
900-Open MWO's G- Fort Calhoun Goal 800-o 700-Nf - u mM bW 600- & ---- G - -- - G - --- G - -- -G--- - G --- - e---- G ---- e ---- G --- --O
\
e0 s, r' 500- _ V 'o N 400-300 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 MAINTENANCE WORK ORDER BACKLOG (CORRECTIVE NON 0UTAGE MAINTENANCE) The Maintenance Work Order Backlog (Corrective Non-Outage Maintenance) Indicator has been changed The goal for this indicator has been changed from 600 open corrective non-outage MW0's to 500 open corrective non-outage MWO's. This indicator shows the number of corrective non-outage maintenance work orders that are open
.at the end of the reporting month.
At the end of September 1990, .there were 406 corrective non-outage maintenance work orders remaining open. The goal for this indicator is to have less than 500 corrective non-outage maintenance work orders remaining open. Adverse Trend: None SEP 36 l
// c
5- 1 Number of Missed ST's Resulting in LER's 4-N 3' u m b e r 2-1- 0 0 0 0 0 0 0 0 0 0 0 0 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 NUMBER OF MISSED SURVEILLANCE TESIS RESULTING IN LICENSEE EVENT REPORTS 1 This indicator shows the number of missed L Surveillance Tests (ST's) that result in Licensee Event Reports-(LER's) during the L reporting month-. During the month of September 1990, there were no missed ST's that resulted in LER's. Adverse Trendi None SEP 60 & 61 1 35-I ITotal NPRDS Component Failures 30- e Confirmed NPRDS Component Failures 25-N uf ma 20- 7 D'I b1 ., g P ru hf h@ih [$ e i; ; r 15- % j$ oe fs
;6 e M g f g _7 10-m i
,j IE
?"3 i
%p!{ [
% $j$f
$i y %
[' 5- [" i1
!!If
.$j h
ji Yk
$3 f
_L
.[T ij g
]!A 12 B; b $ $, $ As M gM #
Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 NUMBER OF NUCLEAR PLANT REllABILITY DATA SYSTEMS (NPRDS) REPORTABLE FAILURES
'This indicator shows the total number of NPRDS component failures and the number of confirmed NPRDS component failures. The total number of NPRDS component failures is based upon the number of failure reports sent to INP0. The number of confirmed NPRDS component failures is based upon the number of failure reports that have been accepted by INPO. The difference of these two figures .is the number of failure reports still under review by INP0.
During September 1990, there was a total of zero confirmed NPRDS component failures. , Adverse Trend: None IS- + Components With More Than One failure
-X- Components With More Than Two Failures N
i u m ' b GOOD 10- c o f C o
/
m o p b 5-o n
,/ ,X. , ~,, ' y_ _ _ _ _ _ y_ _ _ _ _ _y_ _ _ _ _ ,g n * ,x' x '~
t s X' 'X-~~~~'X-~~~- M-~~~~'X 0 l Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 i-MAINTENANCE EFFECTIVENESS The Maintenance Effectiveness Indicator was developed following guidelines set forth by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (NRC/AE0D). The NRC/AE0D is currently developing and verifying a maintenance effectiveness indicator using the Nuclear Plant Reliability Data System (NPRDS) component failures. This indicator shows the number of NPRDS components with more than one failure during the last twelve months and the number of NPRDS components with more than two failures during the last twelve months. The number of NPRDS components with more than two failures in a twelve-month period should indicate the effectiveness of plant maintenance.
= During September 1990, there were 6 NPRDS components with more than one failure and 2 NPRDS componer,ts with more than two failures. The tag numbers of the : NPRDS components with more than two failures in the last twelve months include: CH-1B and CH-10.
Adverse Trend: None
20- - Check Valve failure Rate a Industry Check Valve Failure Rate o 15-F a GOOD 3
\'
M ie r1n 10- '1t i p oH e**u r r 5-s 3 -. . . g. _ -3 6- 6 -f -6 0 Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov 1989 1990 CHECK VALVE FAllVRE RATE This indicator shows the Fort Calhoun check valve failure rate and the industry check valve failure rate. The data for the industry check valve failure rate is three months behind the Performance Indicators Report reporting month due to the time involved in collecting and processing the data. The industry failure rate is based upon failures that have occurred in-the previous 18 month interval. i For' June 1990, the Fort Calhoun ' Station reported a check valve failure rate 'of 7.38E-6 while the industry reported a failure rate of 2.54E-6. At the end of September, the Fort Calhoun Station reported a check valve failure rate of 4.01E-6. At this present time, the check valve failure rate for Fort Calhoun is higher than the industry check valve failure rate. The reason for the high check valve failure rate is that the plant is performing maintenance on check valves which have not been tested for failures bei're. As time goes on, the check valve failure rate is expected to decrease due to the fact that the check valves are now being maintained through the Check Valve Program. Adverse Trend: None SEP 43
- Secondary System CPI
+ ec n ary System UI Umn 1.5-
-O- Industry Upper Quartile l- 4----+----4----+---+---+---+----+----+----+----&----+
~
GOOD
'38 .5- + #
. N
~
o__o._..o... .o -v~ 7-~O ~O^-O~~O~~O~~O O '" 0
'88 '89 Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug 1989 1990 1000 - Hours Chemistry is Outside OG Guidelines 757.7 800-
,y n f o 600-F$ GOOD u -
359 'l r 400 + w n s ,
*^
M 200-h[i '87 '88 Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug 1989 1990 SECONDARY SYSTEM CHEMISTRY The top graph, Secondary System Chemistry Performance Index (CPI), is calculated using three parameters. The three parameters used include; cation conductivity in steam generator blowdown, sodium in steam generator blowdown, and condensate pump discharge dissolved oxygen. The CPI was reported as 0.56 for the. month of August. The CPI values for June, July, and August are high
'due to startup after the 1990 Refueling Outage, various fluctuations in power which have occurred, and a forced outage in August. The industry upper quartile value for this indicator was 0.16 for August 1989 through December 1989. The CPI industry value then changed to 0.24 for 1990.
The bottom graph, ligsrs Chemistry is Outside Owners Guidelines, tracks the total hours of 13 parameters exceeding guidelines during power operation. The number of hours outside. owners group guidelines was reported as 0.1% for the month of August. The above two chemistry indicators are one month behind the reporting period due to the time needed for data collection and evaluation of the station chemistry data. Adverse Trends: None 10- - Primary System Chemistry Out of Limit 8-P s. GOOD
. +
n t 4-1.9 2-
'do fh ,
0 .:' 0 '88 '89 Sep 0'ct Nov Dec Jan Feb Mar Apr May Jun Jul A'u's 1989 1990 i PRIMARY SYSTEM CHEMISTRY PERCENT OF HOURS OUT OF LIMIT The Primary System Chemistry - Percent of Hours Out of Limit- indicator tracks the - primary system chemistry performance by monitoring six key chemistry parameters. The Primary System Chemistry Percent of Hours Out of Limit was reported as 0.0% for the month of August. The high percent of- hours out of limit for the primary system during June and July was due to
-startup after the 1990 Refueling Outage and various power fluctuations which occurred during June and July.100% equates to all six parameters being out of limit for the month.
Adverse Trend: None
- Auxiliary System Chemistry Out Of Limit
-O- Industry Upper Quartile 40- ,
- GOOD
+
30-
~
H o u 20-r s 10-0 0 0 -O~4 ~O ~ ~4 4 '88 '89 S'ep Oct Nov Dec Jan Feb Mkr Ahr Miy Jun Jul Ah 1989 1990 AUXILIARY SYSTEM (CCW) CHEMISTRY HOURS OUTSIDE STATION LIMITS The Auxiliary System Chemistry Hours Outside Station Limits indicator tracks the monthly ~ hours that the Component Cooling Water (CCW) system is outside the station chemistry limit. The above chemistry indicator is one month behind the reporting period due to the time needed for data collection and evaluation of the chemistry data for the station. The auxiliary system chemistry hours outside station limits was reported as zero for the month of August. The industry upper quartile value for auxiliary systems ' chemistry hours outside station limits is 2.6 hours. The Fort Calhoun Station is currently .- performing in the upper quartile of all nuclear power plants for this indicator. Adverse Trend: None . ggg Number of Out-of-Service Instruments 20 -G- Fort Calhoun Goal
$$5 16- a:M ___m ._
m a e ra;n :== = a=m Nn - Y N 5 b u3 M MM
===
N$ [dj M EE rz: = = - gum sgg 13 3 m t 12 #=m 55 "*" br M*5 E5 -- E2 I*"" M=" === 5N3 e ?" 5EE #= ==' D 'M
= === 5 :: 55 rm UUi5 55
,=
NE 55 m ;; ny
=5 N %%
=2; AYIE a==
, m t== =:
o" EN E ' E= 2 * = A :--- f ~_fi M 21 $22 E;d 5t2 X 25 = ama X?2 ++-e
- 35 * ==as a== MM-v?X; RQX-gq3-- EWr EDE gge-Kg -ier;i 4-f~~ Efd 5M0 $7$3 Es =LT=1~ F55 $9] a =-i g,
;gg g_:ggg 3% e=a ;;3 ;; - g;;;;
Eam 555 iAd
=== ;;;; 77=-
$%PiGM mx8 21=+; =-.
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0 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 IN-LINE CHEMISTRY INSTRUMENTS OUT-OF-SERVICE This indicator shows the total number of in-line chemistry system instruments that are out-of-service at the end of 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 September there were a total of 7 in-line chemistry instruments that were out-of-service. Four of these instruments were from the Secondary System and three were from PASS. The Fort Calhoun goal for the number of in-line chemistry system instruments that are out-of-service has been set at 6.. Six out-of-service chemistry instruments make up 10% of all the chemistry instruments which are counted for this indicator. Adverse Trend: None 10000- I ' Total Waste Produced
- Federal and State Limit 8000-K i0 1I 6000-W 9
ra a s mt 4000 s e 2000-
' ' ' ' I I ' '
0-Oct Nov Dec Jein Feb Mar Apr May Jun Jul Aug Sep 1989 1990 M7ARD0VS WASTE PRODUCED This indicator shows the total amount of hazardous waste produced by Fort Calhoun each month. This hazardous waste consists of non-halogenated hazardous waste, halogenated hazardous waste, and other hazardous waste produced. During the month of September, 0.0 kilograms of
- non-halogenated hazardous waste was produced, 9.9 kilograms of halogenated hazardous waste was produced, and 0.0 kilograms of other hazardous waste was produced.
The large . amount of hazardous waste produced during the month of October 1990 was caused by a mercury spill at the sulfuric acid tank located on the east side of the~ service building. Adverse Trend: None 5000; I IMonth M Quarter OPPD Limit
.1 Year 4000-3000-m R ~
E M 2000-1000-e e 0 September 1990 MAXIMVM INDIVIDVAL RADIATION EXPOSURE During September 1990, an individual accumulated 550 mrem which was the highest individual exposure for the month. The maximum individual exposure to date for the third quarter of 1990 has been 794 mrem. The maximum . individual exposure reported to date for 1990-has been 2,090 mrem. The high maximum individual exposure reported so far for the 1990 year to date value was a contract generator jumper. The maximum accumulated 1989 individual exposure was 1,165 mrem, received by a Health Physicist. The OPPD limit for the maximum yearly individual radiation exposure is 4,500 mrem / year'. Adverse Trend: None 1 l 6 Monthly Contaminations
- Cumulative Contaminations 500)
O fort Calhoun Goal i l< Industry Upper Quartile 400. 357 P
- e R) r fy s 300- GOOD gj o et n +
P n d fY e I 200-
~157 C- - - - O - - - & - - o - - - & - - - O - - - O - -- -O- - - - O - - - O - - - -O t $j "~;"1
- - ~- < :. O O- Q Q O O O g
g , 100-
$Nh m8 l _,V1 f
a p - l,_ 9 L '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec ! 1990 l l TOTAL SKIN AND CLOTHING CONTAMINATIONS There was a total of 2 skin and clothing contamination reported I 'for the Fort Calhoun Station during September,1990. There has been a total of 212 skin and clothing contaminations so far in 1990. The high number of skin and clothing contaminations which occurred during the months of March and April 1990 were related to- increased activity in the- Radiation Controlled Area (RCA) during the 1990 Refueling Outage. There was a total of 157 skin and clothing contaminations in 1989. The 1990 goal for. skin and clothing is 150 contaminations. This 1990 goal of 150 contaminations includes a Fort Calhoun goal of 23 skin contaminations. The industry upper quartile value for total skin and clothing contaminations is 129 per unit ennually. Adverse Trend: None SEP 15 & 54 Decontaminated Auxiliary Building G- Fort Calhoun Goal 100-n._- -_n.----O . ,,G---- a - ^ O 80-P 60-c e - n 40-A GOOD 20-0 - Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 DECONTAMINATED AVXIllARY BUllDING This graph shows the percentage of the auxiliary building which is decontaminated (clean) based on the total square footage and a Fort Calhoun goal of 85% decontaminated auxiliary building (non-outage months) and a goal of 75% decontaminated auxiliary building (outage months). As of September 30, 1990, 84.5% of the total square footage of the auxiliary building was decontaminated. Adverse Trend: None SEP 54 20-
>.m Number of Identified PRWP's N
u 15-m b e . r 10-P R 7 W , p s 5- ?@ 3 m:
'd 2 2 ,,l gg ?' ;f 1 1 1 0 m p. gj [g;j o p gj o Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 RADIOLOGICAL WORK PRACTICES PROGRAM The Radiological Work Practices Program Indicator shows the number of Poor Radiological Work Practices (PRWP's) which were identified during the reporting month.
The number of PRWP's which are identified each month should indirectly provide a means to qualitatively assess supervisor accountability for their workers' radiological performance. During the month of September 1990, zero PRWP's were identified. Adverse Trend: None SEP 52 75 I I Total Number of Hot Spots l se Number of Additional Hot Spots Identified l NH uo 50- - - _ c-- mt b es rp - o ot fs 25-0 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1990 1991 NUMBER OF HOT SPOTS The Number of Hot Spots Indicator has been changed to include the number of additional hot spots which are identified during the reporting month. This indicator shows the total number of hot spots which have been identified to exist in the Fort Calhoun Station and have been documented through the use of a hot spot identification sheet. A hot spot is defined as a small localized source of high radiation. A hot spot occurs when the contact dose rate of an item or piece of equipment is at least 5 times the General Area dose rate and the item i or piece of equipment's dose rate is equal to or greater than 100 mrem / hour. l-
! - At the end of September, 50 hot spots were identified and documented to exist in the Fort Calhoun Station. During the month of September, one- additional hot spot was identified to exist in the Fort Calhoun
! Station. The Station ALARA committee established a goal to eliminate at least 5 hot spots during 1990. The Fort Calhoun Station has exceeded this goal. l Adverse Trend: None l l
I IMonthly Radioactive Gas Discharged
- Cumulative Radioactive Gas Discharged G- Cumulative Goal 785 800-GOOD C 600-u r
i e p i s 400-o---- o --- o--..o ._- e._. .g._ _ e... G- - - -O ---G-- --&--- O
; )
]
4 k -- 164 200-1 l ' - x YD$2 0 F' ' '
'88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 GASE0US RADI0 ACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT The gaseous radioactive waste being i discharged to the environment is shown for January 1990 through June 1990. A total of l 261 curies have been released to the environment from Janutry through June of 1990. 'The Fort Calhoun Station goal is 360 curies for this indicator.
The high value of gaseous radioactive waste that .was released to the environment during the month of February 1990 was due to containment purge associated with the 1990 Refueling Outage. The gaseous radioactive waste being discharged to the environment is calculated every six months. Adverse Trend: None I ! Monthly Radioactive Liquid Discharged
- Cumulative Radioactive Liquid Discharged
-G- Cumulative Goal 228 231 300-228
-. o ..g..e... e...o...o..e ..e ..s..s-- o-.. o gg u 200-h da
,[ J s e j G000
$5 i s 100- 4' WY .
n dn '87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 20000-Ty h 15000-G u a s 10000-aj n d s 3 5000-f 0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 LIOUID RADI0 ACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT The liquid radioactive waste being discharged to the environment is shown for the months of January 1990 thro"gh June 1990. The liquid radioactive waste that .was discharged to the envir]nment from all sources totaled 55 curies from January- through June 1990. The Fort Calhoun Station goal for 1990 is 256 curies. The bottom graph shows the volume of liquid radioactive waste that has been released from the radioactive waste monitor tanks and steam generators. The volume of liquid radioactive waste discharged to the environment from the radioactive waste monitor tanks and the steam generators totaled 11.6 million gallons from January.through June 1990. The liquid radioactive waste that was released to the environment includes liquid released- from the steam generators due toithe fact that radioisotopes were. detected in the steam generator blowdown. The liquid radioactive waste being discharged to the environment is calculated every six months. Adverse Trend: None 100' (3 Number of Loggable/ Reportable Incidents N-80- 77 m b B&W^ e
- J '1'1L
't r ?$y g y o "t;
" A f }' m 5
1
" 40- }
; a 1 Y d d -
e ; { i' i nt 20- y s g ;
, , 0 _ . .
0 0 O LOV Badges Escort System Key Access failures Control Control August 1990 LOGGABLE/ REPORTABLE INCIDENTS (SECURITY) The Loggable/ Reportable Incidents- (Security) Indicator shows the total number of loggable/ reportable incidents concerning Licensee Designated Vehicles (LDV's), security badges, security key control, escorting, access control, and security system failures for the reporting month. During the month of September 1990, there were 80 loggable/ reportable incidents identified. Security system failures accounted for 77 of the loggable/ reportable incidents (96%) reported this month. CCTV failures accounted for 57% of the system failures during the month of September 1990. The majority of these failures were due to environmental conditions (sunspots and shadows) which occur on an almost daily basis. Adverse Trend: None SEP 58
y Licensee Designated Vehicles (LDV's) llll. Security i>adges , i l Security Key Control l Escorting Access Control Security System failures LDV 1% Badges 3% f f A s i N. i I System Failures 96's
.\. :
'z 'x
~
SECVRITY INCIDENT BREAKDOWN The Security Incident Breakdown Indicator shows the percentage of incidents concerning the following items for the reporting month. These items include: Licensee Designated Vehicles (LDV's), security badges, security key control, escorting, access control, and security system failures. Security items ,_thenber of incidents SEP 193Q AUG 1990 Licensee Designated Vehicles (LDV's) 1 1 Security Badges 2 5 Security Key Control 0 0 Escorting 0 1 0 0 Access Control Security System Failures 77 59 Total 80 66 Adverse Trend: None SEP 58 t . _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ . _ . . _
50-40 H 40-u m b e 31 30-o f f a 20 i 1 u r 10-3 2 0 - I I' ' Alarm System CCTV Computer Terminal Door Card Reader SECURITY SYSTEM FAILURES The Security System Failures Indicator shows the number of incidents concerning the following items for the reporting month. These items include: alarm system failures, CCTV failures, security computer failures, terminal failures, door equipment failures, and card reader failures. System Failures Number of Incidents SEP 90 AUG 90 Alarm Systems 31 22 CCTV 40 23 Computer 2 3 < Terminal 1 4 Door Equipment 3 6 Card Reader 0 1 l Total 77 59 Adverse Trend: None SEP 58 l
15- - Amount of Work On Hold Awaiting Parts 12-GOOD P 9- + e c - e n t 6-3- 0 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 , AMOUNT OF WORK ON HOLD AWAITING PARTS (NON-0UTAGE) This procurement indicator displays the amount of open, non outage, maintenance items that are. on hold- awaiting parts, to the total amount of open, non-outage, maintenance items, expressed as a percentage. The percentage of work on hold awaiting parts increased to 3.9% in September. As of September 30, 1990, there were a total of 939 open, non-outage, maintenance items with 37 of these items on hold awaiting parts. Adverse Trend: None i l l
12-
- Spare Parts Inventory Value M
i
)
o 10-n s o ~ f 1 a r 8-s f s l 6 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep ! 1989 1990 l l l l l SPARE PARTS INVENTORY VALV.E 1 The spare parts inventory value at the Fort i Calhoun Station at the end of September 1990 was reported as $9,720,256. Adverse Trend: None 750-T
~
- Spare Parts issued I h l 0
- 600-S I
a - l n l d 450-s 0 I 300-D o 1 150-r s 0 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 SPARE PARTS ISSUED The value of the spare parts issued during September 1990, totaled $129,980. Adverse Trend: None
- Inventory Accuracy 100-95<
P e r e e 90-n t 85-l l .. 80 t Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 INVENTORY ACCURACY The Inventory Accuracy Indicator has been changed. The percentage of the inventory accuracy is now shown l- in line graph form. Previously, this percentage was ) shown in column graph form. This indicator shows the accuracy of the actual parts count for the warehouse compared to the counts contained in the MMIS computer system for the , reporting month, i During September, 463 di fferent line items were L counted in the warehouse. Of the 463 line items counted 10 items needed count adjustments. The ' inventory accuracy for the month of September was reported as 98%. Adverse Trend: None p
5- - Pick Tickets With Parts Not Available , l 1 1 4- l P pi ec j rk 3 C eT ni tc k 2-oe ft . s 1-0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 STOCK 0VT RATE This indicator shows the percentage of the number of Pick Tickets generated with no parts available during the reporting month. During the month of September, a total of 852 Pick Tickets were generated. Of the 852 Pick Tickets generated, one Pick Ticket was generated with no , parts available. Adverse Trend: None 1500 O Total Receipts Spare Parts Receipts
-O' Standard Stores Receipts
~
Direct Charge Receipts 1200-N R
u e 900-b'c e p ' O t 600- , s f , y e 300- O
/
' g ,... -l. r - --Q '. Y
,. K h . ['~ ~.6
.> 6 O -o 0
Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan 1990 1991 WAREHOUSE RECEIPTS This indicator shows the total number of warehouse receipts, the number of spare parts receipts, the number of standard stores receipts, and the number of direct charge receipts during the reporting month. During September the warehouse received a total of 575 receipts. Of the 575 receipts received, 157 were spare parts receipts, 95 were standard stores receipts, and 323 were direct charge receipts. Adverse Trend: None
4000- O Total Issues 6- Spare Parts Issues O Standard Stores Issues
- Direct Charge Issues 3000-N ga s
s e 2000-u r O. o
- f
'O -O 1000- a O
. [& ,,,
O -' O g g...._f -6 0 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan 1990 1991 WAREHOUSE ISSUES This indicator shows the total number of warehouse issues, the number of spare parts issues, the number of standard stores issues, and the number direct charge issues for the reporting month. During September the warehouse completed a total of 1,178 issues. Of the- 1,178 issues completed, 235 were sparo parts issues, 685 were standard stores issues, and 258 were direct charge issues. Adverse Trend: None
80- -O- Total Returns Spare Parts Returns
. O Standard Stores Returns H- Direct Charge Returns 60-T Po et .
c
- 40-n1 ,a ts s O'.-
ou ' fe .b -, , 20 , l N, l l '6 o B- / O o 9.O - 0 feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan 1990 1991 WAREHOUSE RETURNS The Warehouse Returns indicator shows the percentage of the total number of warehuuse returns, the number of spare parts returns, the number of standard stores returns, and the number of direct charge returns compared to the total number of warehouse issues during the reporting month. During the month of September there were a total of 1,178 warehouse issues. Of the 1,178 issues, there were 534 total returns. These returns consisted of 45T' spare parts returns and 82 standard stores returns. Adverse Trend: None
25- 1 IJuly 1990 9 August 1990 : September 1990 H 20 a t e Nr u i 15- ' ma b1 , e rR ;_,. e 10- V4 oq di? fu . e s
+' I t 5-5 -
$3l
.; e MM 0 --- -- -- E b 0-5 6-10 11-15 16-20 21-30 >30 Age in Days MATERIAL RE0 VESTS AWAITING APPROVAL This indicator shows the number of material requests awaiting approval at the end of the reporting month broken down into their age by days.
At the end of September,16 material requests were awaiting approval. Adverse Trend: None
~70-
1 l l
- Percentage of Total Purchases that are Expedited 1.5-P e
r c l-e n t
.5-0 -
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 EXPEDITED PURCHASES This indicator shows the percentage of expedited purchases compared to the total number of purchase orders generated during the reporting month. 6 i During September, there was a total of l 223 purchase orders generated. Of the 223 I purchase orders generated, there was one expedited purchase. Adverse Trend: None l l l 71-
l l 150-I IJuly 1990 m August 1990 l . i September 1990 I 120- !i a , N 3 , $n90-V ! b e] C . 1 ) o e@ ,{- j fs ny;
$(;'ij l 30- jy _
\
a E dir.
~
0 --- - M *' Shelf Life CQE Miscellaneous LNyllCE BREAKDOWN This indicator simws the number of invoices that are on hold at the end of the reporting month due to shelf life, CQE, and miscellaneous reasons. At the end of September 4 invoices were on hold due to shelf life reasons, 84 invoices were on hold due to CQE reasons, and 70 invoices were on hold . due to miscellaneous reasons. Adverse Trend: None
10b - Percentage of Material Requests for Issues with the Request Date the same as the Need Date 80-
- =
z [60-r C e , n 40-t 20-0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 MATERIAL RE0 VEST PLANNING This indicator shows the percent of material requests (MR's) for issues with their request date the same as their need date compared to the total number of MR's for issues for the reportin9 month. During the month of September, a total of 852 MR's were received by the warehouse. Of the 852 total MR's received by the l warehouse, 569 % 's were for issues with l their request date the same as their need date. Adverse Trend: None i l l
700- - Total Modification Packages Open 600-500-425 425 - 7 y - 384 & 400-s L !Y,, d f;g 3, ]$ 300- $$ k )hf) 200
'87 '88 '89 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 OUTSTANDING MODIFICATIONS The total number of outstanding modifications decreased by one during the month of September.
CATEGORY AUG 90 SEP 90 Form FC ll33 Backlog /In Progress 15 12 Mod Requests Being Reviewed 108 141 Design Engr. Backlog /In Progress 113 84 Construction Backlog /In Progress 42 44 Desian Enar. Uodate Backloa/In Proaress _62 _51 Total 338 337 As of the end of September 49 additional modification requests have been issued this year and 12 modification requests have been cancelled. The Nuclear Projects Review Committee (NPRC) has completed 110 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) has completed 105 backlog modification request reviews this year. The number of reviews completed is high due to the fact that some of these requests were reviewed more than once. Adverse Trend: None 100- Total Temporary Modifications M - e- Fort Calhoun Goal ! Nd 80-ui - [ 60-ec - ra 40-
- t ,
20-
~ ~ * ~ ~ O '~ 3 .... . .... . .... . .... . .... e 0
Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 July 1990 M o 8- W August 1990 Nd I ISeptember 1990 ui 6-mi y l} bi j ec 4- N U c! t;;r I ra :" 5 , t nits ?? <= w oi 2- ?? 7N h5 5 @ fo NP di $ $ $M n 0-
=
== - -
!G is foi 3
0-3 3-6 6-9 9-12 > 12 Age in Months TEMPORARY MODH ICATIONS (EXCLUDINGSCAFFOLDING) The top graph shows the total number of temporary modifications installed in the Fort Calhoun Station and a Fort Calhoun goal. The number of electrical temporary modifications and the number of mechanical temporary modifications have been deleted from this indicator because the Plant no longer categorizes temporary modifications in this manner. I f At the end of September, there was a total of 18 temporary l modifications installed in the Fort Calhoun Station. The Fort l Calhoun goal for the total number of installed temporary l modifications is less than 15 installed temporary modifications. I l The bottom graph, e.ge of Temocrary Modifications, displays the age of all temporary modifications by months installed in the plant. Adverse Trend: None SEP 62 & 71 1
50- I IOpen EAR'5 EAR's Closed During the Reporting Month
- EAR's > 30 Days Past Current Schedule 40-o l Nf 30-u mE .
bA eR r's 20-I 10-0- - Priority 1 Priority 2 Priority 3 Priority 4 September 1990 ENGINEERING ASSISTANCE RLQE11 PRIORITY BREAKDOWN This indicator shows the number of open and closed Engineering Assistance Requests (EAR's) broken down into priorities at the end of the reporting month. Along with the priority breakdown, the number of EAR's remaining open 30 days past the current schedule are shown for each priority category.
>30 Days Past Priority Open Closed Current Schedule M 629 len M 829 la M enn la Priority 1 6 6 9 1 4 4 3 4 5 Priority 2 12 13 19 0 8 9 4 6 5 Priority 3 30 29 26 0 7 11 11 16 15 Priority 4 21 35 40 1 8 11 10 12 9 Total 69 83 94 2 27 35 28 38 34 Adverse Trend: The number of open EAR's has increased from 59 in May 1990 to 94 in September 1990. The major reason for the increase in the number of open EAR's is the result of discrepancies between old procedures and the new procedures which are being upgraded by the Procedures Upgrade Project.
SEP 62 1
l 150- -G- Totol ECN's Open
+(- ECN's Opened During the Month o ECN's Completed During the Month 120-N u
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5 g, x . . . _ .>! ',y ' 's N o 'y ' > o 0 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 ENGINEERING CHANGE NOTICE STATUS The indicator shows the total number of open Engineering Change Notices (ECN's), the number of ECN's opened during the reporting month, and the number of ECN's completed during the reporting month. At the end of September 1990, there was a total of 87 open ECN's. During the month of September, 19 ECN's were opened, and 29 ECN's were completed. Adverse Trend: None SEP 62 300- 1 IDocument Change M Substitute Replacement Item Facility Changes 250-228 200- 196 MEi
$N$
150-- ES$ ud 11M 100-raa
. n$
gy 50- AM 29 24 NN; N Xh 7 7 14 8 7 0- ' I Total ECN's ECN's Opened ECN's Completed Total ECN's Open During the Month During the Month Received ENGINEERING CHANGE NOTICE BREAKDOWN This indicator breaks down the total number of Engineering Char.ge Notices (ECN's) that remain open at the end of the reporting month, the number of ECN's that were opened during the reporting month, the number of ECN's that were completed during the reporting month, and the number of ECN's received by Design Engineering during the reporting month into several categories. These categories include: ECN's requiring a document change to complete, ECN's requiring substitute replacement items to complete, and ECN's requiring facility changes to complete. l Total Open Opened Completed Received l Document Changes 34 7 14 228 l Substitute Replacement 29 5 8 196 Facility Changes 24 7 7 102 Adverse Trend: None SEP 62 5- E]1990RecordableInjuryFrequencyRate
+- 1989 Recordable Injury Frequency Rate i 4.5- I
-+- 5 Year Average Recordable Injury Frequency Rate 4-1 3.5-GOOD 3-R - ,
O a 2.5- , e 4's '
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Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec RECORDABLE INJVRY CASES FRE0VENCY RATE This indicator shows the monthly recordable injury cases frequency rate in column form. The above graph also includes the 1989 recordable injury cases frequency rate and the Fort Calhoun Station 5 year avera9e recordable injury cases frequency rate. A recordable injury case is reported if Nuclear Operations Division personnel are injured on the job and require corrective medical treatment. The recordable cases frequency rate is computed on a year-to date basis. There were zero recordable injury cases reported during the month of September. There has been a total of 5 recordable injury cases so far in 1990. There were eleven recordable cases reported in 1989, eleven reported in 1988, and eight reported in 1987. The year end recordable injury frequency rates for 1987, 1988, and 1989 were 2.5, 2.6, and 2.2 respectively. Adverse Trend: None SEP 15 & 26 l l l
o Licensee Event Reports I IPersonnel Errors Reported in LERs
- Cumulative Licensee Event Reports
---- Cumulative Personnel Errors Reported in LERs 50-46 7 -
Ah! 39 M I 40-14;
% a1 nn ;; -
G n;;; 31
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;;,26 ;A 30-aa v- a .
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'87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 NUMBER OF PERSONNEL ERRORS REPORTED IN LER'S The Number of Personnel Errors Reported in LER's Indicator reports the Licensee Event Reports (LER's) by their event date, in September 1990, there were 5 LER's reported. Out of the 5 LER's which occurred, there was one LER attributable to personnel error.
There have been 25 LER's reported so far in 1990 and 7 LER's have been attributable to personnel errors. Adverse Trend: None SEP 15 L
{_]NuclearDivisionsTurnoverRate
- OPPD Corporate Turnover Rate 8-T u 6-r n ,
o y e 4-r
~
R a t 2-e I 0 Nuclear Operations Production Engineering Nuclear Services Division Division Division PERSONNEL TURNOVER RATE The turnover rate for three Nuclear Divisions is shown for the last twelve months. The personnel turnover rate is plotted against the OPPD corporate turnover rate of 4.0%. This OPPD corporate turnover rate is based on the turnover rate over the last three years. Adverse Trend: The turnover rates for the NOD and PED have been increasing. The high turnover rate for NOD was due to 30 resignations which have occurred in the last 12 months. The high turnover rate for PED was due to 11 resignations which have occurred in the last 12 months. j
600- 8 Actual Staffing 561 IAuthorized Staffing I 534 ($lkltejW 51
- - %4
+m nsew 47%
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P 400- giggd,.WW j e -
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s );ts'g"JLW! o - Ubhw:a Hf WM n z;pg*fggg p n g#4 m+g s /,i e v gn$ 1 200-j:as"'"h; ;m 193
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m e @u m wo,?'f3 , lSRf;fdW #SMMM[0 typ't'q;[.ij Nuclear Operations Production Engineering Nuclear Services Division Division Division STAFFING LEVEL The authorized and actual staffing levels are shown for the three Nuclear Divisions. Adverse Trend: None SEP 24 I ISRO Exaaination Pass Ratio 100-80-f 0 . P a 60-s s . N 40-t i o 20-No Exams No Exams No Exams Administered Administered Administered 0 NRC Administered NRC Administered NRC Administered OPPD Administered Generic Site Specific Requalification Requalification Fundamental Exams Exams Exams Exams SRO LICENSE EXAMINATION PASS RATIO The SRO License Examination Pass Ratio indicator shows the number of NRC administered Generic Fundamentals Exams (GFE's), the number of NRC administered Site Specific Exams, the number i of NRC administered license requalification exams, and the number of OPPD administered license requalification exams. No SR0 License examinations were administered during September 1990. The table below lists the examination pass ratio for exarinations which have been taken during 1990. OPPD ADMINISTERED NRC ADMINISTERED l Requal Generic Fund. Site Spec. Requal.
% PASS RATIO % PASS RATIO % PASS RATIO % PASS RATIO DATE Feb 1990 - 100 SEP 68 Adverse Trend: None i
[]R0Exa2inationPassRatio l 100-R 80-0
~
P a 60- i s s R a 40-t i . o 20-No Exams No Exams Administered Administered NRC Administered NRC Administered NRC Administered OPPD Administered Generic Site Specific Requalification Requalification Fundamental Exams Exams Exams Exams R0 LICENSE EXAMINATION PASS RATIO , The R0 License Examination Pass Ratio Indicator shows the number of NRC administered Generic Fundamentals Exams (GFr.'s), the number of NRC administered Site Specific Exams, the number of NRC administered license requalification exams, and the number of OPPD administered license requalification exams. No R0 License examinations were administered during the month of September 1990. The table below lists the examination pass ratio for examinations which have been taken during 1990. OPPD ADMINISTERED NRC ADMINISTERED Requal Generic Fund. Site-Spec. Requal. DATE % PASS RATIO- % PASS RATIO % PASS RATIO % PASS RATIO Feb 1990 - 100 - May 1990 - - 100 - Adverse Trend: None SEP 68 84-
i R SRO Exams Administered 20- SRO Exams Passed
@ R0 Exams Administered L43 R0 Exams Passed u
15-m b 3 e 1 y r .y C 1 ; o 10- i ; f g j t c E - t { . I x ; q. a ;: $ , m 5 4 [ s j jj-( i 3 :p "Y h
=
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- a 5$ $$
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- d #3 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan 1990 1991 i l
LICENSE CANDIDATE EXAMS This indicator- shows the number of SRO and R0 quizzes and exams taken and passed each month. These internally administered quizzes and exams are used to plot the SAO and R0 candidates' monthly progress. During the month of September 1990, no SR0 , exams were administered. During the month of September 1990, no R0 _ exams were administered. Adverse Trend: None SEP 68 l l 85-i
l l
@@ Hotlines Initiated 50-
- Hotlines Closed M Hotlines Open Under 4 Weeks l 45- I Hotlines Open Over 4 Weeks N
u 40-m b 35-e r 30-o f 25- "o 20 ~ t i > : 1 15- !! i j e ] _1 1 1 "e 10- 5> ! -
- s 3 T
5
- x l 1 y E
rg [ 2 :}s lMr :l.1_).: Oct Nov Dec Jan Feb f :YO 3 Ml d A Mar Apr May Jun Jul Aug Sep 1989 1990 HOTLINES This indicator shows the number of Hotlines initiated during the reporting month, the number of Hotlines closed during the reporting month, the number of Hotlines that remain open and are less than four weeks-old, and the number of Hotlines that remain open and are older than four weeks old. During the month of September 1990, there were 3 Hotlines initiated, 12 Hotlines closed, I Hotline that remained open and was less than four weeks old, and 1 Hotline that remained open and was older than four weeks old. Adverse Trend: None 86-
4- [] Planned Classroom Hours l I Actual Classroom Hours T _ h 3 _ u f - q s .t_
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Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug 1989 1990 CLASSROOM flNSTRUCTOR) HOUR 1 This indicator displays the number of planned classroom hours and the number of actual classroom hours for the fort Calhoun Station. This indicator is one month behind the reporting month due to the time to collect and process the needed information. Adverse Trend: None 87-m
I IOperations E Maintenance B Chemistry and Radiation Protection 30
- Technical Support G 3 General Employee Training T
h Other o 25-u s a n 20-N o 15- y lb yg w m " ~ g : 10-r f
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O Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug 1989 1990 TOTAL HOURS OF STUDENT TRAINING This indicator shows the total number of student hours for Operations, Maintenance, Chemistry and Radiation Protection, Technical Support, General Employee Training, and Other training conducted for the Fort Calhoun Station. This indicator is one month behind the reporting month due to the time needed to collect and evaluate the data. Total Hours TRAINING dVL 1990 AVG 1990 Operations 2.742 2,664 Maintenance 3, ISO 4,660 Chemistry and 580 2,013 Radiation Protection Technical Support 1,768 3,293 General Employee Training 3,359 4,983 Other .. 277 443 Total 11,906 18,056 Adverse Trend: None 1 1 Total Outage MWO's MWO's Ready to Work ; 400 1
\
300- -------------------------------------------------- ---------------------------- i N u mM bW e0 200- ------------------------------------------------------------------------------- r' 3 3 s
~
o f 100- ------------------------------------------------------------------------------- 0-Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul 1990 1991 MWO OVERALL STAT _L!S (1991 REFUEllNG OUTAGE) The MWO Overall Status (1991 Refueling Outage) Indicator has been added to the Performance Indicators Report. This indicator shows the total number of MWO's that have been written over the past reporting periods for completion during the 1991 Refueling Outage and the number of MWO's that are ready for work (the parts for these MWO's are staged, the procedures are approved, and the paperwork is ready for field use). Any MWO's written after the start of the outage will be reflected in the indicator labeled Emeraent MWO's. Approximately 3000 maintenance orders were completed during each of the previous two refueling outages. Additional data points will be added to this indicator as information becomes available. Adverse Trend: None SEP 31
- Total Outage Modifications Mods With Planning Document Approved
-s- Mods With Final Design Approved Hods With Construction Package Approved 30 M
o Nd ui 20- ---------------------------------------------------------------------------------- mi bi eC , ra t 10- ------~~------------------------------------------------------------------------- n s O Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul 1990 1991 PROGRESS OF 1991 OUTAGE MODIFICATION PLANNING The Progress of 1991 Outage Modification Planning Indicator has been added to thc Fort Calhoun Station Performance Indicators Report. This indicator shows the number of modifications approved for planning (to determine feasibility) for completion during the 1991 Refueling Outage. Additional data points will be added to this indicator as information becomes available. The current schedule for completion of the modification phases of the 1991 Refueling Outage is as follows. Outage Scope Freeze ............................ OCT 1, 1990 Pl anning Documents Approved . . . . . . . . . . . . . . . . . . . FEB 22, 1991 Final Designs Approved . . . . . . . . . . . . . . . . . . . . . . . . APR 24, 1991 Construction Packages Approved ................ JUN 15, 1991 Schedul e incorporated . . . . . . . . . . . . . . . . . . . . . . . . . JUL 26, 1991 Materi al On Si te . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . JUL 26, 1991 Construction Started .......................... OCT 21, 1991 Construction Complete .......................... NOV 4, 1991 Accepted By SAC ............................... NOV 15, 1991 Adverse Trend: None SEP 31
- Total Outage Projects 50 1 1
i 40- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I Np j u !
~~-~~~~~~~~~~-~~~~~~~~~~~~--*~~~~----~~~~~~~~~~~~~~~~~~~~---~~~~~~~~~~~-~~~~~~
m' 30 b e,j - rC t 20' ' ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - - - - - - * - - - - ~ ~ - ~ ~ ~ ~ - - - ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ ' ~ ~ ~ ~ ~ ~ ~ ~ o 5 i , 10- ------------------ ------ ------------------------------------ ---- ------------- 0-Aug Sep Oct Nov Occ Jan Feb Mar Apr May Jun Jul 1990 1991 OVERALL PROJECT STATUS
.(1991 REFUELING OUTAGE)
The Overall Project Status (1991 Refueling Outage) Indicator has been added to the Performance Indicators Report. This indicator shows the status of the projects which affect the scope of the 1991 Refueling Outage. t Additional data points will be added to this indicator as l information becomes available. The schedule for t' 1991 Refueling Outage projects .is as follows. l All Projects identified and Outage Scope Frozen ....... OCT 1, 1990 All Projects Scheduled in Detail ...... JUN 28, 1991 Adverse Trend: None SEP 31
- Violations per 1000 Inspection Hours !
G- Fort Calhoun Goal i 15-11.1 { 10.6 n ' 5iM
@ GOOD J 12-
'y 4
a 4 F9 g j r
;Ml 7,3 a -
9 Ng' ' ,j gg$ CF- -- G - -- G - - - - n - ---O - --O - -- G- -- - G -- - -O -- - G - -- G -- - O pf #n ~q . , o 'f-t e y
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14 3-7 ,. l f) 7 -w L,9 '87 '88 '89 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 VIOLATIONS PER 1000 INSPECTION HOURS This indicator displays the number of NRC violations cited in inspection reports per 1000 NRC inspection hours. This indicator was calculated using the number of violations and the number of inspection hours from submitted inspection reports. These inspection reports consisted of reports from the months of January 1990 through August 1990. This indicator is one month behind the reporting month due to the time involved with collecting and processing the data. The violations per 1000 inspection hours indicator was reported as 7.6 for the month of August 1990. There have been a total of 1,972 inspection hours in 1990 which have resulted in 15 violations. The goal for the number of violations per 1000 inspection hours is less than 8.2. Adverse Trend: None 75- l l Number of Violations During the Last 12 Months C Number of NCV's During the Last 12 Months V
~
i o 1 a 50- 47 Nt u i ~ m0 41 41 bn 3g 37 's . 36 34 34 r, - - 0 0 fd 25-N C 16 19
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0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1990 CUMULATIVE VIOLATIONS AND NCV's (TWELVE M') NTH RUNNING 10TAL) The Cumulative Violations and Non Cited Violations (NCV's) Indicator shows the cumulative number of violations for the last twelve months and the cumulative number of NCV's for the last twelve months. During the last twelve months, 28 violations have been identified and 14 NCV's have been identified. Adverse Trend: None 93-
- Total Outstanding CAR's G Outstanding CAR's > Six Months Old Outstanding CAR's That Are Modification Related 200-150-o Ni -
u N100-eR r' , s Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1989 1990 l OUTSTANDING CORRECTIVE ACTION REPORTS This indicator shows the total number of outstanding Corrective Action Reports (CAR's), the number of outstanding CAR's that are greater than six months old, and the number of outstanding CAR's that are modification related. As of the. end of September 1990, there were 142 outstanding CAR's, 53 CAR's that are greater than six months old, and 11 CAR's that are modification related. Adverse Trend: None f , i { l 94
y40- -e. NOD Overdue CAR's u 30- -a- NOD CAR's With Extensions Granted ' cc 20-bA
' [g --- by . . --- q~ ----- Q-Q'. 4-----s.....p....g Nov Dec Jan Feb MYr Air May JYn JYi A79 Sep Oct 1989 1990 o 50-
-e- ED Overdue CA0's N f 40-u 6- PED CAR's With Extensions Granted l mC 30- ,
bA 20-
'!r 10- O '
O ""'O
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s U" " ' 6-N-=- M M C g g g '$ Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct i 1989 1990 10-0 Other Overdue CAR's j N 8-u 6- Other CAR's With Extensions Granted ! mC 6- ; 2 s n n A' * - A" - :-, i WS~~ ,In
- ~ . 1 o
Nov Dec J FTb MYr Apr -N~~In MTy J Jul Aug Sep Oct 1989 1990 OVERDUE AND EXTENDED CORRECTIVE ACTION REPORTS This indicator shows the number of overdue CAR's and the number of CAR's which received extensions broken down by organization. OVERDVE CAR's ORGANIZATION JyL.92 AVG 90 EP_9A l 0 0 1 NOD PED 0 1 1 Others 0 0 0 i, I Total 0 1 2 CAR's WITH EXTENSIONS GRANTED i ORGANIZATION JUL 90 AVG 90 Ef._93 N00 4 2 3 l PED 7 13 5 Others 0 1 0 Total 11 16 8
!I Mverse Trend: None !
l 4 Ny150- -e- NOD CAR's >6 Months Old " 6- NOD CAR's <6 Months Old mc 100 50 6-- -6 ' " - - - - - - -- - -& - - - --b. . g . . . . .b -- - - -6 r C U ^ ' " n 0 s Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov 1989 1990 o 150-Nf PED CAR's >6 Months Old U 100- 6- PED CAR's <6 Months Old mC bA f) ["' Wh .... - -- ---- ~b 5 0 _ Dec Jan feb Mar Apr May Jun Jul Aug Sep Oct Nov 1989 1990 o 40-Nf C Other CAR's >6 Months Old u 30-Other CAR's <6 Months Old mC bA 20-
,, . 6... -6 .. , ,,,,4 ,,,,, ,... -A ,,,
r 10- 6--- . g , s 0 0 0 " O " O'n n Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov 1989 1990 CORRECTIVE ACTION REPORTS CURRENT STATUS This indicator shows the number of CAR's that are older than 6 months and the number of CAR's that are less than 6 months old broken down by organization. CAR's GREATER THAN 6 MONTHS OLD ORGANIZATION JVL 90 AVG 90 SEP 90 ' N0D 8 6 9 PED 49 48 45 Others 3 1 1 1 ' Total 60 55 55 CAR's LESS THAN 6 MONTHS OLD ORGANIZATION JVL 90 AUG 90 SEP 90 N00 39 45 47 PED 31 35 34 Others 8 13 6 Total 78 93 87 Adverse Trend: None 4
. . . ~ .
1990 1989 NRC OPPD SIGNIFICANT _ NRC OPPD -SIGNIFICANT CAR's- CAR's VTOLATIONS LER'S CAR's' CAR's VIOLATIONS LER'S. SALP FUNCTIONAL-AREA 9 0 8 2 l 37 (1) 0 1 A. Plant Operations- 0 0 30 1 2 1 23 (1) 2 B.~ Radiological Controls 140 8 2 10 164 (12) 8 (1) S 4 C. Maintenance / Surveillance 6 0 2 0 0 0 D. Emergency 8- 0' Preparedness 6 10 23 0 4 2 (1) 26 2 E. Security. 134 2 7 7 120 (18) 3 (1) 1 II (4) F. Engineering / Technical Support 0 0 68 0 1 0 16 (1) 0 G. Safety Assessment / Quality 6 Verification 0 0 0 T 0 0 0 1 1 H. Other 26 31 390 (33) 13 (2) 13 26 (S) 417 13 Total CAR'S ISSUED VERSUS SIGNIFICANT CAR'S VERSUS NRC VIOLATIONS ISSUED VERSUS LE (CAR's) issued by the Nuclear The above matrix shows the number of Corrective Action Reports Services Division versus the number of Significant CAR's issued by the Nuclear Services Division issued by the Nuclear Regulatory Commission (NRC) for the Fort versus the number of violat!ns Calhoun Station in 1989 and #0. Included in this table is the number of Licensee Event Reports (LER's) identified by the station each year. The number of MRC violations reported are one month behind the' reperting month due to the time involved in collecting and processing the violations. In September, 1990, there were 33 CAR's issued, 2 Significant CAR's issued, and S LER's identified. During August zero NRC violations were issued. Thus no violations were attributable to personnel error. The monthly distribution of CAR's, Significant CAR's, NRC violations, and LER's are shown in parentheses, SEP 15, 20 & 21 1
SIGNIFICANT ITEMS OF INTEREST This section is intended to provide information on events which are significant to the Fort Calhoun Station and will give a " heads-up" look at what is scheduled in the coming months. The Procedure Upgrade Project and the Plant have approved and issued 811 safety related procedures. This meets a Safety Enhancement Program (SEP) Item Number 48 milestone commitment. The NRC- Maintenance Inspection Team follow-up review has been rescheduled until November 1990. The 56 day 1991 Refueling Outage is planned to start 9/28/91 and finish 11/22/91. The 1990 Emergency Preparedness Graded Exercise is planned _for the week of 11/26/90. 1 I l l l l
l FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS AGE OF OUTSTANDING MAINTENANCE WORK ORDERS This indicator tracks the total number of outstanding corrective non-outage Maintenance Work Orders :.t the Fort Calhoun Station versus their age in months. ! AMOUNT OF WORK ON HOLD AWAITING PARTS This indicator is defined as the percentage of open, non-outage, maintenance work orders that are on hold awaiting parts, to the total number of open, non-outage, maintenance work orders. AUXILLARY SYSTEMS CHEMISTRY HOURS OUTSIDE STATION LIMITS The cumulative hours that the Component Cooling Water system is outside the station chemistry - limit. The hours are accumulated from the first sample exceeding the limit until additional sampling shows the parameter to be back within limits. CHECK VALVE FAILURE RATE The Fort Calhoun check valve failure rate and the industry check valve failure rate (failures per 1 million component hours). The data for the industry failure rate is three months behind the Performance Indicators Report reporting month. This indicator tracks performance for SEP item 43. CLASSROOM (INSTRUCTOR) HOURS The number of planned classroom hours and the number of actual classroom
-hours for the Fort Calho? Station.
CORRECTIVE ACTION REPORT CURRENT STATUS The number of Corrective Action- Reports (CAR's) that are- older than 6 months and the number of CAR's that are less than 6 months old broken down by organization for the last 6 months.- CORRECTIVE MAINTENANCE BACKLOG GREATER THAN 3 MONTHS OLD The percentage of total outstanding corrective maintenance items, not requiring an outage, that are greater than three months old at the end of the period reported, h L l
FORT CALH0VN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) CVMULATIVE VIOLATIONS AND NON-CITED VIOLATL(LNS (TWELVE-MONTH RUNNING TOTAL) l The cumulative number of violations and Non-Cited Violations for the last 12 months. DAILY THERMAL OUTPUT The daily core thermal output as measured from computer point XC105 in thermal megawatts. DIESEL GENERATOR RELIABILITY A Diesel Generator (DG) unit consists of the engine, generator, combustion air system, cooling water system, fuel supply system, lubricating oil system, starting air system, autostart controls, manual controls, and diesel generator breaker. Reliability of each DG unit will be reported for two situatior s, one for the last 20 demands and one for the last 100 demands. Reliability is the ratio of the number of successful runs to the number of demands, for each individual DG unit. A successful run. is defined as a start of a DG unit and the loading of this unit to a minimum of 50% rated load (1250 KW) for a minimum time period of 60 minutes. A failure is defined as the failure to start, accelerate, and assume the design rated load for the given time period as specified for an emergency or a valid test. The total number of demands (or valid tests) will be equal to the sum of the failures and the successful runs. This definition of DG Reliability was taken from.the U.S. Nuclear Regulatory Commission " Regulatory Guide 1.108, Revision 1". This is the definition being applied in calculating the diesel . generator reliability at the Fort Calhoun Station. 1 DISABLING INJURY FRE00ENCY RATE (LOST TIME ACCIDENT RATE) This indicator is defined as the number of accidents for all utility personnel permanently assigned to the station, involving days away from I work per 200,000 man-hours worked (100 man-years). This does not include contractor personnel. This indicator tracks personnel performance for Safety Enhancement Program (SEP) Item 26.
-100-
FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) DOCUMENT REVIEW (BIENNIAL) The Document Review Indicator shows the number of documents reviewed during the reporting month, the number of documents scheduled for review during the reporting month, and the number of document reviews that are overdue. ENGINEERING ASSISTANCE RE0 VEST (EAR's) PRIORITY BREAKDOWN The number of open and closed EAR's broken down into priorities at the end of the reporting month. This indicator tracks performance for SEP item 62. ENGINEERING CHANGE NOTICE (ECN) BREAKDOWN The breakdown of the total number of open ECN's, the number of ECN's that were opened during the reporting month, the number of ECN's that were completed during the reporting month, and the number of ECN's received during the reporting month into three categories. These categories include; 1) document changes are required to complete the ECN's, 2) substitute or replacement items are required to complete the ECN's, or 3) facility changes are required to complete the ECN's. This indicator tracks performance for SEP item 62. ENGINEERING CHANGE NOTICE (ECN) STATUS The number of ECN's that remain open at the end of the reporting month, the number of ECN's that were opened during the reporting month, and the number of ECN's that are completed during the reporting month. This indicator tracks performance for SEP item 62. E001PMENT FORCED OUTAGES PER 1000 CRITICAL HOURS Equipment forced outages per 1000 critical hours is the inverse of the L mean time between forced outages caused by equipment - failures. The mean L time is equal to the number of hours the reactor is critical in a period l (1000 hours) divided by the number of forced outages caused by equipment failures in that period. E0VIVALENT AiAILABILITY FACTOR This indicator is defined as the ratio of gross available generation to gross maximum generation, expressed as a percentage. Available generation is.the energy that can be produced if the unit is operated at the maximum power level permitted by equipment and regulatory limitations. Maximum generation is the energy that can be produced by a unit in a given period if operated continuously at maximum capacity. EXPEDITED PURCHASES The percentage of expedited purchases which occurred during the reporting month compared to the total number of purchase orders generated.
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FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) FORCED OUTAGE RATE This indicator is defined as the percentage of time that the unit was unavailable due to forced events compared to the time planned for electrical generation. Forced events are failures or other unplanned conditions that require removing the unit from service before the end of the next weekend. Forced events include startup failures and events initiated while the unit is in reserve shutdown (i.e., the unit is available but not in service. FUEL REllABillTY INDICATOR This indicator is defined as the steady-state primary coolant I-131 activity, corrected for the tramp uranium contribution and normalized to a common purification rate. Tramp uranium is fuel which has been deposited on reactor core internals from previous defective fuel or is present on the surface of fuel elements from the manufacturing process. Steady state is defined as continuous operations above 85 percent power for at least seven days. This INPO indicator uses an industry normalized letdown purification rate. The FRI has also been calculated using Fort Calhoun's actual letdown purification rate. These calculations revealed that the use of the plant's actual rate would result in an approximate 45% increase in FRI data. GASEOUS RADI0 ACTIVE-WASTE BEING DISCHARGED TO THE ENVIRONMENT This indicator displays the total number of Curies of all gaseous radioactive nuclides released from the Fort Calhoun Station. GROSS HEAT RATE' Gross heat rate is defined as the ratio of total thermal energy in British Thermal Units (BTU) produced by the reactor to the total gross electrical energy produced by the generator in kilowatt-hours (KWH). HA7ARD0US WASTE PRODUCED The total amount (in Kilograms) of non-halogenated hazardous waste, halogenated hazardous waste, and other hazardous waste produced by the Fort Calhoun ~ Station each month. HOTLINES The number of Hotlines that are initiated, closed, overdue, and open for a given month, A Hotline is a training document sent out for. immediate review. The Hotline should be reviewed and signed within 5 days of receipt of the Hotline.
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FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINVED) HOURS CHEMISTRY IS OUTSIDE OWNERS GROUP GUIDELINES Total hours for 13 secondary side chemistry parameters exceeding guidelines during power operation. Power operation is defined as greater than 30% power. The 13 parameters tracked are steam generator pH, cation conductivity, boron silica, chloride, sul f ate, sodium, feed water pH, dissolved oxygen, hydrazine, iron, copper, and condensate pump discharge dissolved oxygen. IN LINE CHEMISTRY INSTRUMENTS OUT-0F-SERVICE Total number of in line chemistry instruments that are out-of-service in the Secondary System and the Post Accident Sampling System (PASS). INVENTORY ACCURACY The percentage of line items that are counted each month by the warehouse which need count adjustments. INVOICE BREAKDOWN The number of invoices that are on hold due to shelf life, CQE, and miscellaneous reasons. LLQJa CANDIDATE EXAMS This indicator shows the number of SR0 and/or R0 quizzes and exams that are administered and passed each. month. The License Candidate Exams Indicator tracks Training performance for Safety Enhancement Program Item Number 68. LIOVID RADI0 ACTIVE WASTE BEING DISCHARGED TO THE' ENVIRONMENT This indicator displays the volume of liquid radioactive waste released , from the radioactive waste monitor tanks. The curies from all releases from the Fort Calhoun Station-to the Missouri River are also shown. LOGGABLE/REDORTABLE INCIDENTS (SECURITY) The total rumber of security incidents for the reporting . month.. This , indicator tracks security performance for Safety Enhancement Program Item > l-Number 58. MAINTENANCE EFFECTIVENESS The number of Nuclear Plant Reliability Data System (NPRDS)' components with more than one failure and the number of NPRDS components with more than two failures during the last twelve months.
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FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) MAINTENANCE WORK ORDER BACKLOG The number of corrective non outage maintenance work orders that remain open at the end of the reporting month. This indicator was added to the Performance Indicators Report to trend open corrective non-outage maintenance work orders as stated in Safety Enhancement Program (SEP) Item No. 36. MAINTENANCE WORK ORDER BREAKDOWN This indicator is a breakdown of corrective non-outage maintenance work l orders by several categories that remain open at the end of the reporting month. MAINTENANCE OVERTIME The percentage of overtime hours compared to normal hours for maintenance. This includes OPPD personnel as well as contract personnel. MATERIAL RE0 VEST PLANNING The percent of material requests (MR's) for issues with their request date the same as their need date compared to the total number of MR's. MATERIAL RE0 VESTS AWAITING APPROVAL The number of material requests awaiting approval at the end of the reporting month broken down by their age in days. MAXIMUM INDIVIDUAL RADIATION EXPOSVRE The total maximum amount of Gamma and Neutron- (Whole Body) radiation received by an individual person working at the Fort Calhoun Station on a monthly, quarterly, and annual basis, i MWO OVERALL STATUS (1991 REFUEllNG OUTAGE) The total number of Maintenance Work Orders (MW0's) that have been written for completion during the 1991 Refueling Outage. MW0's which are written after the start of the Refueling Outage will be labeled Emergent MWO's. This indicator tracks performance for SEP Reference Number 31.
@gER OF HOT SPOTS The number of radiological hot spots which have been identified and-documented to exist at the Fort Calhoun Station at the end of the
- reporting month. A hot spot is a small localized source of radiation. A hot spot occurs when the contact dose rate of an item is at least 5 times the General Area dose rate _ and the item's dose rate is equal to or greater than 100 mrem / hour.
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FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINVED) EUMBER OF NUCLEAR PLANT REllABILITY DATA SYSTEM (NPRDS) FAILVRE REPORTS SUBMITTED The data plotted is the total number of NPRDS component failures (confirmed and- possible) and the number of confirmed NPRDS component failures. The total number of NPRDS component failures are based on the number of failure reports that have been sent to the Institute of Nuclear Operations (INPO). Confirmed NPRDS component failures are based upon failure reports that have been accepted by INP0. Possible NPRDS component failures are based upon failure reports that are still under review by INPO. NPRDS is the Nuclear Plant Reliability Data System, and is a utility industry users group program which has been outlined by INP0 and implemented at the Fort Calhoun Station. NUMBER OF OUT-0F-SERVICE CONTROL ROOM INSTRUMENTS A control room instrument that cannot perform its design function is considered as out-of-service. A control room instrument which has had a Maintenance Work Order (MWO) written for it and has not been repaired by the end of the reporting period is considered out-of-service and will be counted. The duration of the out-of-service condition is not considered. Computer CRTs are not considered as control room instruments. NUMBER OF PERSONNEL' ERRORS REPORTED IN LER'S The number of Licensee Event Reports (LERs) attributed to personnel error on the original LER submittal. This indicator trends personnel performance for SEP ltem No. 15. NUMBER OF MISSED SVRVEILLANCE TESTS RESULTING IN LICENSEE EVENT REPORTS The number of Surveillance Tests (ST's) that result in Licensee Event Reports (LER's) during the- reporting. This indicator tracks missed ST's
-for. Safety Enhancement Program (SEP) Item Numbers 60 and 61.
OPERATIONS AND MAINTENANCE EUDGET The year to date budget compared to the actual expenditures for operations and maintenance. OUTSTANDING CORRECTIVE ACTION REPORTS This indicator displays the total number of outstanding Corrective Action Reports (CAR's), the number of CAR's that are older than six- months and the number of modification related CAR's.
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FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) l l OUTSTANDING MODIFICATIONS The number of Modification Requests (MR'S) in any state between the issuance of a Modification Number and the completion of the drawing update. 1 Form FC ll33 Backlog /In Progress The Form FC-ll33 has not been plant approved. Modification Requests Being Reviewed This category includes: 1.)
- Modification Requests that are not yet reviewed 2.)
- Modification Requests being reviewed by the Nuclear Projects Review Committee (NPRC) 3.)
- Modification Requests being reviewed by the NuclearProjectsCommittee(NPC)
- These Modification Requests may be reviewed several times before they are approved for accomplishment or cancelled. Some of these Modification Requests are returned to Engineering for more information, some apprcved for evaluation, some approved for '
study, and some approved for planning, Once planning is completed and the scope of the work is clearly defined, these Modification Requests may be approved for accomplishment with a year assigned for construction or they may be cancelled. All of these differentphasesrequirereview. Design Engineering Backlog /In Progress Nuclear Planning has assigned a year in which construction will be completed and design work may be in progress. Construction Backlog /In Progress The Construction Package has been issued or construction has begun but the modification has not been accepted by the System Acceptance Committee (SAC).
~
Design Engineering Update Backlog /In Progress PED has received the Modification Completion Report but the drawings have not been updated. OVERALL PROJECT STATUS (1991 REFUELING OUTAGE) The number of projects which affect the scope of the 1991 Refueling Outage. This indicator tracks performance for SEP Reference Number 31. , 1
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l l FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINVED) OVERDVE AND EXTENDED CORRECTIVE ACTION REPORTS l The number of overdue Corrective Action Reports (CAR's) and the number of CAR's which received extensions broken down by organization for the last 6 months. PERSONNEL RADIATION EXPOSURE (CUMULATIVE) Collective radiation exposure is the total external whole-body dose received by all on-site personnel (including contractors and visitors) during a time period, as measured by the thermoluminescent dosimeter (TLD). Collective radiation exposure is reported in units of man-rem. This indicator tracks radiological work performance for Safety Enhancement Program (SEP) Item Number 54. PERSONNEL TURNOVER RAR The ratio- of the number of turnovers to average employment. A turnover is a vacancy created by voluntary resignation from the company. Retirement, death, termination, transfers within the company, and part-time employees are not considered in turnover. PREVENTIVE MAINTENANCE ITEMS OVERDVE This indicator is defined as the percentage of preventive maintenance items in the month that were not completed by the scheduled date plus a grace period equal to 25 percent of the scheduled interval. This indicator tracks preventive maintenance activities for Safety Enhancement Program (SEP) Item Number 41. PRIMARY SYSTEM CHEMISTRY - PERCENT OF HOURS OUT OF llMIT The percent of hours out of limit are for six primary chemistry parameters divided by the total number of hours possible for the month. The key parameters used are: Lithium, Chloride, Hydrogen, Dissolved Oxygen, Fluoride, and Suspended Solids. EPRI limits are used. PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)
-The number of identified incidents concerning maintenance procedural problems, the number of closed IR's related to .he use of procedures (includes the number of closed IR's caused by proceau 'l noncompliance),
and the number of closed procedural noncompliance IR's. This indicator trends personnel performance for SEP ltem Numbers 15 and 41. PROGRESS OF 1991 OUTAGE MODIFICATION PLANNING The number of modifications approved for planning (to determine feasibility) for completion during the 1991 Refueling. This indicator tracks performance for SEP Reference Number 31.
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FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINVED) RADIOLOGICAL WORK PRACTICES PROGRAM l The number of identified poor radiological work practices (PRWP) for the reporting month. This indicator tracks radiological work performance for l Safety Enhancement (SEP) Item Number 52. RATIO 0F PREVENTIVE TO TOTAL MAINTENANCE The ratio of preventive maintenance (including surveillance testing and calibration procedures) to the sum of non-outage corrective maintenance and preventive maintenance completed over the reporting period. The ratio, expressed as a percentage, is calculated based on man-hours. This indicator tracks preventive maintenance activities for Safety Enhancement Program (SEP) Item Number 41. RECORDABLE INJURY CASES FRE0VENCY RATE (RECORDABLE INJURY RATE) The number of injuries requiring more than normal first aid per 200,000 manhours worked. This indicator trends personnel performance for SEP ltem No. 15 and SEP Item 26. R0 LICENSE _ EXAMINATION PASS RATIO The R0 license examination pass ratio for NRC administered Generic - Fundamentals Exams (GFE's), NRC administered Site Specific Exams, NRC administered license requalification exams, and OPPD administered license i requalification exams. This indicator tracks Training performance for Safety Enhancement Program Item Number 68. SECONDARY SYSTEM CHEMISTRY PERFORMANCE INDEX , The Chemistry Performance Index (CPI) is a calculation based on the concentration of key impurities in the secondary side of the plant. These key impurities are the most' likely cause of deterioration of the steam generators. The chemistry parameters are reported only. for the period of time greater than 30 percent power. The following equation is how the CPI is calculated: CPI = ((Ka/0.8) + (Na/20) + (02 /10)) / 3 Where the-following parameters are monthly averages of; Ka = average blowdown cation conductivity Na - average blowdown sodium concentration 02 average condensate pump discharge dissolved oxygen concentration
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FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) SECURITY INCIDENTS BREAKDOWN This indicator shows a percentile breakdown of the types of Security incidents for_the reporting month. The following items are the types of Security incidents represented in this indicator. Licensee Designated Vehicles (LDV's) Incidents related to the use of LDV's, e.g. keys left in the vehicle, loss of keys, or failure to return keys. Security Badges incidents involving lost / unattended badges, badges removed from site, or failure to wear badges. Escorting Incidents involving escort responsibilities, e.g. improper control or escort of a visitor (s). Security System Failures Incidents involving alarm system failures, CCTV failures, security computer failures, terminal failures, door equipment failures, and card reader failures. Security Key Control Incidents involving Security key control, e.g. lost Security keys, Security keys removed from site, or failure to return
' Security keys. This type of incident does not reflect incidents concerning LDV keys.
Access Control Incidents involving the inspection and control of personnel, packages, and vehicles, e.g. failure to properly search personnel, packages, and vehicles. This item also includes the introduction of contraband or prohibited items into the Protected Area, or the attempted introduction of such items. This indicator tracks security performance for Safety Enhancement Program (SEP) Item Number 58.
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l l FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINVED) SECURITY SYSTEM FAILURES 1 The number of Security incidents concerning alarm systems failures, CCTV failures, security computer failures, terminal failures, door equipment failures, and card reader failures. This indicator tracks security l performance for Safety Enhancement Program (SEP) Item Number 58. SPARE PARTS INVENTORY VALUE The dollar value of the spare parts inventory at the end of the reporting period.
} PARE PARTS ISSVED The dollar value of the spare parts issued for the Fort Calhoun Station during the reporting period.
SRO OPERATOR LICENSE EXAMINATION PA95_1AllQ The SR0 license examination pass ratio for NRC administered Generic Fundamentals Exams (GFE's), NRC administered Site Specific Exams, NRC administered license requalification exams, and OPPD administered license requalification exams. This indicator tracks Training performance for Safety Enhancement-Program item Number 68. STAFFING LEVEL The actual staffing level and the authorized staffing level for the Nuclear Operations Division, the Production Engineering Division, and the Nuclear Services Division. STATION NET GENERATION The net- generation (sum) produced by the Fort Calhoun Station during the l- reporting month. , STOCK 0VT RATE The total number of Pick Tickets that were generated during the reporting. month and the total number of Pick Tickets that were generated during the reporting month with no parts available. , TEMPORARY MODIFICATIONS l The number of temporary mechanical and electrical configurations to the L plant's systems. Temporary configurations are defined as electrical jumpers, electrical blocks, mechanical jumpers, or mechanical blocks which are installed in the plant operating systems and are not shown on the latest revision of the P&ID, schematic, connection, wiring, or flow diagrams.
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l e l FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) TEMPORARY MODIFICATIONS (CONTINUED) 1 Jumpers and blocks which are installed for Surveillance Tests, Maintenance Procedures, Calibration Procedures, Special Procedures, or Operating Procedures are not considered as temporary modifications unless the jumper or block remains in place after the test or procedure is complete. Jumpers and blocks installed in test or lab instruments are not considered as temporary modifications. N affolding is not considered a temporary modification. Jumpers and blocks which are installed and for which EEAR's have been submitted, will be considered as a temporary modifications until final resolution of the EEAR and the jumper or block is removed or is permanently recorded on the drawings. Th:s indicator tracks temporary modifications for Safety Enhancement Program (SEP) Item Number 62 & 71. TOTAL HOURS OF STUDENT TRAINING The total number of student hours of training for Operations, Maintenance, Chemistry and Radiation Protection, Technical Support, General Employee Training, and Other training conducted for the Fort Calhoun Station. TOTAL SKIN AND CLOTHING CONTAMINATIONS Reportable skin and clothing contaminations above background levels
. greater than 5000 dpm/100 cm squared. This indicator trends personnel performance for SEP. Item No. 15.
UNPLANNED AUTOMATIC REACTOR SCRAMS WHILE CRITICAL i This indicator- is defined as the number of unplaaned. automatic scrams l (reactor protection system logic actuations) that occur while the reactor i is critical. The indicator is further defined as follows: l l
- Unplanned means that the scram was 'not part of a planned test 1 or evolution.
- Scram means the automatic shutdown of the reactor by a rapid insertion of all. control rods that is caused. by actuation of the reactor protection system. The scram. signal may have resulted from exceeding a setpoint or may have been' spurious.
- - Automatic means that the initial signal that caused. actuation of the reactor. protection system logic was provided from one of the sensors monitoring plant parameters and conditions, rather than the manual scram switches (or pushbuttons) in the main control room.
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FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) UNPLANNED AUTOMATIC REACTOR SCRAMS WHILE CRITICAL (CONTINVED) Critical means that during the steady-state condition of the reactor prior to the scram, the effective multiplication factor (keff) was equal to one. UNPLANNED SAFETY SYSTEM ACTUATIONS - (INP0 DEFINITION) This indicator is defined as the sum of the following safety system actuations: the number of unplanned Emergency Core Cooling System (ECCS) actuations that result from reaching an ECCS actuation setpoint or from a spurious / inadvertent ECCS signal the number of unplanned emergency AC power system actuations that result from a loss of power to a safeguards bus An unplanned safety system actuation occurs when an actuation setpoint for a safety system is reached or when a spurious or inadvertent signal is generated (ECCS only), and major equipment in the system is actuated. Unplanned means that the system actuation was not part of a planned test or evolution. The ECCS actuations to be counted are actuations of the high pressure injection system, the low pressure injection system, or the safety injection tanks. UNPLANNED SAFETY SYSTEM ACTUATIONS - (NRC DEFINITION) The number of safety system actuations which include (Roly) the High Pressure Safety Injection System, the 'ow Pressure Safety Injection System, the Safety Injection Tanks, and the Emergency Diesel Generators. ' The NRC classification of safety system act3ations includes actuations when major equipment is operated 104 when the logic systems for the above safety systems are challenged. VIOLATIONS PER 1000 INSPECTION HOURS This indicator- is defined as the number of violations sited in NRC-inspection reports. for the' Fort Calhoun Station per 1000 NRC inspection hours. The violations are reported in the year that the inspection was actually performed and not based on when the inspection report is received. The hours reported for each inspection report are used as the t inspection hours, q
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FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINVED) VOLUME OF LOW-LEVEL SOLID RADI0 ACTIVE WASTE This indicator is defined as the volume of low level solid radioactive waste actually shipped for disposal. This indicator also shows the volume of low-level radioactive waste which is in temporary storage. Low-level solid radioactive waste consists of dry active waste, sludges, resins, and evaporator bottoms generated as a result of nuclear power plant operation and maintenance. Dry active waste includes contaminated rags, cleaning materials, disposable protective clothing, plastic containers, and any other material to be disposed of at a low level radioactive waste disposal site, except resin, sludge, or evaporator bottoms. Low level refers ,o all radioactive waste that is not spent fuel or a by-product of spent fuel processing. This indicator tracks radiological work performance for Safety Enhancement Program (SEP) Item Number 54. HAREH0VSE ISSUES The total number of warehouse issues, the number of non-CQE stock issues, the number of CQE stock issues, the number of direct charge non CQE issues, and the number of direct charge CQE issues which occurred during the reporting month. WAREHOUSE RECEIPTS The total number of warehouse receipts, the number of non-CQE stock receipts,- the number of CQE stock receipts, the number of cirect charge non-CQE receipts, and the number of direct - charge CQE receipts which occurred during the reporting month. L WAREHOUSE RETURNS The percentage of the total number of warehouse returns, the number of I spare parts returns, the number of standard stores returns, and the number of direct charge returns compared to the total number of warehouse issues.
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BASIS FOR ESTABLISHING 1990 PERFORMANCE INDICATOR GOALS This secti_on will explain the basis used in establishing the 1990 performance goals. FORCED OUTAGE RATE AND E0VIVALENT AVAILABILITY FACTOR The Forced Outage Rate (FOR) and Equivalent Availability Factor (EAF) goals have been established from 1990 to 1992. The following table is a breakdown of the hours allotted for each category over the next three l years. l STARTUP GENERATOR FORCED OUTAGE PLANNED ON LINE OUTAGE TIME OUTAGE PERIOD EAF FOR JLAB (HOURS) (HOURS) (HOURS) (HOURS) .di&Q). 151 L%1 1990(*) 6356 168 172 2064 8760 65.4 2.4 1991(*) 6956 168 172 1464 8760 75.9 2.3 1992 8520 240 0 0 8760 92.9 2.7 (*) Refueling Outage Years UNPLANNED AUTOMATIC REACTOR SCRAMS WHILE CRITICAL The 1990 goal for Unplanned Automatic Reactor Scrams While Critical has ! been set at one. The Fort Calhoun Station has had one unplanned automatic reactor scram in the past four years of operation. l-UNPLANNED SAFETY SYSTEM ACTUATIONS-The Unplanned Safety System Actuations goal for 1990 has been established L at zero. The Fort Calhoun Statica did not have an unplanned safety system actuation for six years, l DR0SS HEAT RATE The 1990 Gross Heat Rate goal for the Fort Calhoun Station has been set at 10,200 BTU /KWH. This heat rate goal is based on 10,435 BTV/KWH for the
- i. month of January, '10,450 BTU /KWH for the month of February, 10,325-
- BTU /KWH for the month of May, 10,225 BTU /KWH for the month of June, 10,325 BTU /KWH for the month of July, 10,250 BTV/KWH for the month of August, 10,125 BTV/KWH for the month-of September, 10,050 BTV/KWH for the month of October, 10,000 BTV/KWH for the month of November, .and 9,975 l BTU /KWH for the month of December.
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L BASIS FOR ESTABLISHING 1990 PERFORMANCE INDICATOR GOALS l (CONTINVED) FUEL RELIABillTY INDICATOR The 1990 Fuel Reliability Indicator (FRI) goal has been set at 1.0 nanocuries/ gram. This level allows for approximately one to two fuel pin failures. Although Cycle 11 was completed without ary apparent fuel pin failures, there are a number of Advanced Nuclear Fuels Corporation (ANF) assemblies entering into a third or fourth cycle of operation. When a fuel pin has been used for three or four fuel cycles there is an increased probability of fuel failure. The Failed fuel Action Pl an, Standing Order 0-43, allows for approximately four fuel pin failures prior to implementing any increased action levels. PERSONNEL RADIATION EXPOSURE (CVMULATIVE) The 1990 Personnel Radiation Exposure (Cumulative) goal is 287 man-ree. This goal was based on 234 man-rem of cumulative exposure for the 1990 Refueling Outage and approximately 5.9 man-rem of cumulative exposure for each non-outage month. VOLUME OF LOW-LEVEL SOLID RADI0 ACTIVE WASTE The 1990 Volume of Low Level Solid Radioactive Waste goal is 5,000 cubic feet. This goal was based on a recommendation made by the Fort Calhoun ALARA Committee and approved by the Division Manager of the Nuclear Production Division. DISABLING INJURY FRE0VENCY RATE The Disabling Injury frequency Rate 1990 goal has been set at 0.31. This goal allows for one lost time accident in the Nuclear Production Division during 1990. 1. l
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FORT CALHOUN STATION OPERATING CYCLES AND REFUEllNG OUTAGE DATES PRODUCTION CVMULATIVE EVENT FROM - TO (MWH) (MWH) Cycle 1 09/26/73 - 02/01/75 3,299,639 3,299,639 First Refueling 02/01/75 - 05/09/75 Cycle 2 05/09/75 - 10/01/76 3,853,322 7,152,961 Second Rnueling 10/01/76 - 12/13/76 Cycle 3 12/13/76 09/30/77 2,805,927 9,958,888 Third Refueling 09/30/77 - 12/09/77 Cycle 4 12/09/77 - 10/14/78 3,026,832 12,985,720 Fourth Refueling 10/14/78 - 12/24/78 Cycle 5 12/24/78 - 01/18/80 3,882,734 16,868,454 Fifth Refueling 01/18/80 06/11/80 Cycle 6 06/11/80 - 09/18/81 3,899,714 20,768,168 Sixth Refueling 09/18/81 - 12/21/81 Cycle 7 12/21/81 - 12/06/82 3,561,866 24,330,034 Seventh Refueling 12/06/82 - 04/07/83 Cycle 8 04/07/83-03/03/84 3,406,371 27,736,405 Eighth Refueling 03/03/84 - 07/12/84 Cycle 9 07/12/84 - 09/28/85 4,741,488 32,477,893 Ninth Refueling 09/28/85 - 01/16/86 Cycle 10 01/16/86 - 03/07/87 4,356,753 36,834,646
. Tenth Refueling 03/07/87 - 06/08/87 Cycle-ll 06/08/87 09/27/88- 4,936,859 41,771,505 Eleventh Refueling 09/27/88 - 01/31/89 Cycle 12 01/31/89 - 02/17/90 3,817,954 45,589,459 Twelfth Refueling 02/17/90 - 05/29/90
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FORT CALHOUN STATION OPERATING CYCLES AND REFUELING OUTAGE DATES (CONTINVED) PRODUCTION CVMULATIVE EVENT FROM - TO (MWH) (MWH) Cycle 13 05/29/90 - 09/28/91* Thirteenth Refueling 09/28/91*- 11/22/91* Cycle 14 11/22/91*- 02/12/93* Fourteenth Refueling 02/12/93*- 05/06/93* Cycle 15 05/06/93*- 09/30/94* Fifteenth Refueling 09/30/94*- 11/26/94* 1 i I i
* - Planned Dates
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FORT CALHOUN STATION PRODUCTION AND OPERATION RECORDS The following seven items are the current production and operation
" records" for the Fort Calhoun Station.
-1. First Sustained Reaction. . . . . . . . . . . . . August 5, 1973 (5:47 p.m.)
- 2. First Electricity Supplied to the System. . . . . August 25, 1973
- 3. Commercial Operation (180,000 KWH). . . . . . . . September 26, 1973
- 4. Achieved Full Power (100%) . . . . . . . . . . . . May 4,1974
- 5. Longest Run (477 days). . . . . . . . . . . . . . June 8, 1987 - Sept. 27,1988
- 6. Highest Monthly Net Generation (364,468,800 KWH). October 1987
- 7. Most Productive Fuel Cycle (4,936,859 MWH). . . . June 8, 1987 - Sept. 27, 1988 (Cycle 11)
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PERFORMANCE INDICATOR DATA SOURCES PERFORMANCE INDICATOR MANAGER / INDIVIDUAL Age of Outstanding Maintenance Work Orders Patterson/Schmitz Amount of Work On Hold Awaiting Parts Patterson/ CHAMPS Auxiliary Systems Chemistry Hours Outside .ctation Limits Franco /Glantz CAR's Current Status Orr/Gurtis CAR's issued Versus NRC Violatior.s issued Orr/Gurtis Classroom (Instructor) Hours Gasper /Newhouse Corrective Maintenance Backlog > 3 Months Old Patterson/Schmitz Cumulative Violations and NCV's Chase /Simmons Daily Thermal Output Holthaus/ Gray Decontaminated Auxiliary Building Patterson/Gundal Diesel Generator Reliability DG Log Disabling injury-Frequency Rate Sorenson/Skaggs Document Review Patterson/McKay Engineering Assistance Requests Priority Breakdown Jaworski/ Van Osdel Engineering Change Notice Breakdown Phelps/Bera Engineering Change Notice Status Phelps/Bera Equipment Forced Outages per 1000 Critical Hours Holthaus/ Gray Equivalent Availability Factor Dietz/Kulisek
. Expedited Purchases Willrett/Fraser Forced Outage Rate Holthaus/ Gray Fuel Reliability Indicator Holthaus/Lofshult Gaseous Radioactive Waste. Discharged to the-Environment Franco /Stultz Gross Heat Rate Holthaus/ Gray Hazardous Waste Produced Patterson/Sayre
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PERFORMANCE INDICATOR DATA SOURCE (CONTINUED) Hotlines Gasper /Newhouse In Line Chemistry Instruments Out-of-Service Patterson/Renaud Inventory Accuracy Willrett/Fussell Invoice Breakdown Willrett/Fussell License Candidate Exams Gasper / Lazar Liquid Radioactive Waste Discharged to the Environment Franco /Stultz Loogable/ Reportable Security Incidents Sefick/Woerner Maintenance Effectiveness Jaworski/Dowiy Maintenance Work Order Backlog (Corrective Non-Outage) Patterson/Sch nitz Maintenance Work Order Breakdown Patterson/Schmitz Maintenance Overtime Patterson/Schmitz Material Request Planning Willrett/Fussell Material Requests Awaiting Approval Willrett/Fraser Maximum Individual Radiation Exposure Patterson/Mattice MWO Overall Status (1991 Refueling Outage) Patterson/ Hyde Number of Hot Spots Patterson/Mattice Number of NPRDS Reportable Failures Jaworski/ Dowdy Number of Out-of-Service Control Room Instruments Patters'on/ Adams Number of Personnel Errors Reported in LER's Chase /Simmons Number of Missed ST's Resulting in LER's Plant LER's Operations and Maintenance Budget Gleason/ Parent. Outstanding CAR's Orr/Gurtis Outstanding Modifications Jaworski/ Turner
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PERFORMANCE !NDICATOR DATA SOURCE (CONTINUED) Overall Project- Status (1991 Refueling Outage) Patterson/ Hyde Overdue and Extended CAR's Orr/Gurtis Personnel Radiation Exposure (Cumulative) Patterson/Mattice Personnel Turnover Rate Sorenson/ Burke Preventive Maintenance items Overdue Patterson/ Linden Primary System Chemistry - Percent Hours Out of Limits Franco /Glantz Procedural Noncompliance incidents (Maintenance) Patterson/McKay Progress of 1991 Outage Modification Planning Patterson/ Hyde Radiological Work Practices Program Patterson/Mattice Ratio of Preventive to Total Maintenance Patterson/Schmitz Recordable Injury Cases Frequency Rate Sorenson/Skaggs R0 License Examination Pass Ratio Gasper / Lazar Secondary System Chemistry Franco /Stultz Security Incident Breakdown Sefick/Woerner Security System Failures Sefick/Woerner Spare Parts Inventory Value Steele/Huliska Spare-Parts Issued Steele/ Miser SR0 License Examination Pass Ratio Gasper / Lazar Staffing Level Sorenson/ Burke Stockout-Rate Willrett/Fussell Temporary Modifications Jaworski/ Turner Total Hours of Student Training Gasper /Newhouse Total Skin and Clothing Contaminations Patterson/Mattice Unplanned Automatic Reactor Scrams While Critical Plant LER's
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PERFORMANCE INDICATOR DATA SOURCE (CONTINUED) - Unplanned Safety System Actuations (INPO) Plant LER's Unplanned Safety System Actuations (NRC) Plant LER's Violations per 1000 Inspection Hours Chase /Simmons Volume of Low-level Solid Radioactive Waste Patterson/Breuer Warehouse Issues Willrett/Fussell Warehouse Receipts Willrett/Fussell < Warehouse Returns Willrett/Fussell
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REFEllENCES l INPO Good Practices 0A-102, " Performance Monitoring - Management Information" IEEE Standard 762, "IEEE Trial Use Standard Definitions for Use in Reporting Generating Unit Reliability, Availability and Productivity" INPO Report Dated November 1984, " Nuclear Power Plant Operational Data" U.S. Nuclear Regulato.y Commission " Regulatory Guide 1.108 l ! I
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