ML20085K654
| ML20085K654 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/31/1995 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20085K651 | List: |
| References | |
| NUDOCS 9506280065 | |
| Download: ML20085K654 (98) | |
Text
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OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT l
Prepared By:
Production Engineering Division System Engineering Test and Performance Group s
MAY 1995
=..
FORT CALHOUN STATION O
MAY 1995 MONTHLY OPERATING REPORT w
1 i
OPERATIONS
SUMMARY
During the month of May, FCS operated at a nominal 100% power until May 11,1995, I
when a manual reactor trip was initiated due to an indicated component cooling water (CCW) leak in the upper oil reservoir of the Reactor Coolant Pump (RCP) RC-3D motor.
All four of the RCP motors' upper lube oil coolers were eddy current tested, and a total of 10 tubes were plugged The plant was retumed to power operation on May'15th. On May -
24th, the reactor was manually tripped from approximately 97% power due to new indications of a CCW leak into the upper oil reservoir motor bearing of the RC-3D motor.
]
The plant was taken to cold shutdown and the tube bundles in all four RCP motor upper i
oil reservoir lube oil coolers were replaced The plant was returned to power operation on I
May 29th.- Power was increased to a nominal 100% on May 31st.
During performance of daily Reactor Coolant System (RCS) sampling on May 5th, the RCS sample inboard containment isolation valve, HCV-2504A, did not indicate closed as required. Technical Specification (TS) Limiting Condition for Operation (LCO) 2.6(1)a was entered, and the RCS sample outboard containment isolation valve, HCV-25048, was deactivated and locked in the closed position to restore containment integrity. The limit switch on HCV 2504A was repaired and tested, and the valve was declared operable on May 6th.
On May 9th, HCV-2504A again failed to indicate closed as required. HCV-25048 was deactivated and locked in the closed position and TS LCO 2.6(1)a was entered. The actuator diaphragm was replaced and tested satisfactorily, a Local Leak Rate Test (LLRT) c was satisfactorily performed on HCV-2504A, and the valve was subsequently declared operable on May 10th. The actuator diaphragm was also replaced on HCV-25048.
1 i
I l
FORT CALHOUN STATION MAY.1995 MONTHLY OPERATING REPORT -
OPERATIONS
SUMMARY
(Continued)
The May 20th, RCS radioactivity exhibited an increasing trend. The Fuel Reliability Indicator (FRI) had increased from the May 11th value of 0.00024 Ci/g to 0.0678 Ci/g.
As required by Standing Order 0-43, " Fuel Reliability Action Plan", reactor coolant charging and letdown flows were increased to facilitate cleanup of the system. Standing Order 0-43 requires this action with a FRI between 0.05 and 0.2 Cilg. The FRI value had -
decreased to 0.024 Cilg prior to the reactor shutdown on May 24th. Fuel rod failures due to spacer grid fretting is the probable cause of the high activity. These failures were not -
unexpected since defective fuel rods due to fretting had been identified and replaced during the 1995 refueling outage.
c C
N
Year-To-Date Value Performance Categories
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ili. ?l10lQ ln^
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a Performance in Industry p%UM2 hem Unplanned TMrrml Upper 10% and better as w A
Unit p y] Unplanned E.
than 1995 OPPD goal Automatic Ftrtrrrerice Capability g 4j Capability ScremsTT,000 I
Factor E ji Loss Factor Hours C Ai l
Performance Better Than
-~cmggnp 21 ggygpaeng 7
1995 OPPD Goal On::t Sl5 il?
~ad M *\\
Performance Not Meeting HPSI Safety System W
m 1995 OPPD Goal
^'
Performance Performance j$findicator 7 Performance
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^
-ll l? }ly Feb March April g[?'l 95 35 1;hlr'deg h-Collective Volume of O~
l Redletion LowLevel y, Safety,
I Exposure Radioactive
' ^ Accialeng May 1995 1
Year-To-Date s
Weste f "h I ci ;
3,g pm Value 1995 Year-End I
ph
- s W
Performance Performance INPO PERFORMANCE INDICATORS E
l 6
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Screms Year-To-Date Value Performance Cateaories Criti I EEEE lII l;fll jlll 1
-5 Performance Better Than Industry Average Trend h'
hhNnt W
!Tath Endtis ActMidris Performance Better Than 1995 OPPD Goal l
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Perforr:Lince Not Meeting 1995 OPPD Goal or g@een industry Average Trend Seh j Forced.
$htp'yg
- Outage p FWktes Rate c
Feb.
March April ym w:.:.
95 35 95
~
May 1995 4_
,- Equipment
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- m Year-To-Date Best Posstble Forced lS Collective Value 1995 Year-End 10utages/1,000j, Radiation Performance Feibnew Crit. Hrs.
Exposure g
.,..q NRC PERFORMANCE INDICATORS m
FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT MAY 1995 -
SUMMARY
POSITIVE TREND REPORT POSITIVE TREND REPORT (continued)
Open CARS and irs A performance indicator with data representng three consecutrve months of improving performance or three (Page 65) consecutrse months of performance that is supenor to the stated goal is exhibrbng a poseve trend per Nuclear End of Positrve Trend Report.
Operabons Dusion Quairty Procedure 37 (NOD-QP-37).
The fogowing performance indicators exhibited poseve ADVERSE TREND REPORT trends for the reportng month:
A performance indicator with data representng three Hiah Pressure Safety injecton System Safety System consecutve months of dechning performance or three Performance consecutrve months of performance that is trending (Page 8) toward dochning as determined by the Manager - Stabon Engineenng, consttutes an adverse trend per Nuclear Emeroency AC Power System Safety System Operabons Dusion Quality Procedure 37 (NOD-QP-37).
Performance A supervisor whose performance indicator exhitxts an (Page 10) adverse trend by this definibon may specify in written form (to be pubhshed in this report) why the trend is not Emeraenev Diesel Generator Unit Reliabiktv adverse.
(Page 11)
The following performance indicators exhibited postve Diesei Generator Reliabihty (25 Demands) trends for the reportng month:
(Page 12)
Industnal Safety Accident Rate Emeroency Diesel Generator Unrenability (Page 2)
(Page 13)
Maintenance Workload Backtoos Missed Survedlance Tests Results in Licensee Event (Page 45)
Reports (Page 20)
End of Adverse Trend Report.
Unolanned Auto Scrams per 7.000 Hours Crfbcal Page 28)
INDICATORS NEEDING INCREASED Unolanned Safety System Actuations(INPO Definmon)
MANAGEMENT ATTENTION REPORT (Page 29)
A performance indicator with data for the reportng period Pnmary System Chemistry Percent of Hours Out of Limft that is inadequate when compared to the OPPD goalis (Page 38) defined as *Needing increased Management Attenton" per Nuclear Operatons Division Quality Procedure 37 Secondary System Chemistry (NOD-QP-37).
(Page 39)
The following performance indicators exhibited positrve Cents Per Kilowatt Hour trends for the reportng month:
(Page 41)
Disabhna iniurvMilness Frecuency Rate (Lost-Time 3
in-Line Chemistry Instruments Out-of-Service Accident Rate (Page 51)
(Page 3) l Hazardous Waste Produced Recordable IniurvMilness Frecuency Rate (Page 52)
(page 4)
Contaminated Radiaton Controlled Area (Page 53)
V
FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT MAY 1995 -
SUMMARY
INDICATORS NEEDING INCREASED MANAGEMENT ATTENTION REPORT (continued) pry Feedwater System Safety System Performance 7
(Pageg)
Temporary Mod 6 cations (Page 57)
Outstandina Mod 6cabons (Page 58)
PERFORMANCE INDICATOR REPORT IMPROVEMENTS / CHANGES i
This secton hets signmcant changes made to the report and to specmc indicators within the report since the previous month.
A computer system automation is currentty underway to more efficientty utilize computer equipment to collect, analyze and produce data for the performance indicator report.
End of Report Improvements / Changes Report.
9 vi
l i
I Table of Contents / Summary j
J l
oOALs.......................................................................x SAFE OPERATIONS Industrial Safety Accident Rate -INPO...............
2 Disabling injury / Illness Cases Frequency Rate 3
Recordable injury /l!Iness Cases Frequency Rate...
4 Clean Controlled Area Contaminations
>1,000 Disintegrations / Minute per Probe Area.............
.........5 Preventable / Personnel Error LERs '...
........6 Safety System Failures
.............. 7 Safety System Performance:
i High Pressure Safety lnjection System....
......................... 8 1
Auxiliary Feedwater System........................................
.....9 Emergency AC Power System..
..................10 1
Emergency Diesel Generator Unit Reliability..
..................11 Reliability (25 Demands)
. 12 Unreliability.
13 Fuel Reliability indicator........
......................14 Control Room Equipment Deficiencies 15 Collective Radiation Exposure 16 i
l Maximum individual Radiation Exposure............................
..... 17 Violation Trend.
...............18 1
Significant Events
. 19
]
3 Number of Missed Surveillance Tests Resulting in LERs 20 1
l C
I i
i
)
i 1
i l
l l
l l
1
eu N
f.
Table of Contents / Summary PERFORMANCE Pace Station Net Generation
...... 22
~
Forced Outage Rate.....
. 23
' Unit Capacity Factor...........
24 Equivalent Availability Factor
....... 25 Unit Capability Factor...................
26 Unplanned Capability Loss Factor 27 Unplanned Automatic Reactor Scrams per 7,000 Hours critical 28 Unplanned Safety System Actuations INPO Definition.....
. 29 NRC Definition
.................. 30 Gross Heat Rate 31 Thermal Performance....
.... 32 Daily Thermal Output
... 33 Equipment Forced Outages per 1,000 Critical Hours..
34 Component Failure Analysis Report (CFAR) Summary 35 Repeat Failures
. 36 Volume of Low-Level Solid Radioactive Waste.............
37 Primary System Chemistry l
Percent of Hours Out of Limit 38 39 Secondary System Chemistry.
d COST Cents Per Kilowatt Hour......
........... 41 Staffing level 42 Spare Parts inventory Value 43 v
h
t Table of Contents / Summary DMSION AND DEPARTMENT PERFORMANCE INDICATOBE h
Maintenance Workload Backlogs (Corrective Non-Outage.......
............45 Ratio of Preventhre to Total Maintenance & Preventive Maintenance items Overdue.....
46 Percentage of Total MWOs Completed per month identified as Rework 47 Overtime.................
.....................................48 Procedural Noncompliance lncidents...
...........49 Percent of Completed Scheduled Maintenance Activities 50 In-Line Chemistry Instruments Out-of-Service 51 Hazardous Waste Produced..
52 Contamlnated Radiation Controlled Area 53 Radiological Work Practices Program 54 Document Review 55 Loggablo/ Reportable incidents (Security)
.. 56 Modifications Temporary.
57 Outstanding.
58 Engineering Assistance Request (EAR) Breakdown
.. 59 Engineering Change Notices Status 60 Open
............... 61 Licensee Event Report (LER) Root Cause Breakdown...
62 Licensed Operator Requalification Training 63 License Candidate Exams..
64 Open Corrective Action Reports and incident Reports 65 Cycle 16 Refueling Outage MWO Planning Status 66 67 Outage Modification Planning Progress of 1994 On-Une Modification Planning
. 68 ACTION PLANS. DEFINITIONS. SEP INDEX & DISTRIBUTION UST 3
Action Plans
. 70 Performance indicator Definitions
. 73 Safety Enhancement Program Index 81 83 Report Disttibution List.
1 IX i
l OPPD NUCLEAR ORGANIZATION GOALS Vice President-1995 Priorities MISSION The safe, reliable and cost effective generation of electricity for OPPD customers through the l
professional use of nuclear technology. The Compariy shall conduct these operations l
prudently, efficiently and effectively to assure the health, safety and protection of all personnel, the general pub!!c and the anvironment.
-l t
Goal.S l
ft 911.:
SAFE OPERATIONS 0
t Supports: April 1994 Corporate Strategic Plan Goal 3, Obj: 3 & 4 A proactive, self-critical and safety conscious culture is exhibited throughout the nuclear
[
organization. Individuals demonstrate professionalism through self-ownership and personal initiative and open communication.
l 1995 Priorities:
l Improve SALP ratings.
i Improve INPO rating.
Reduce NRC violations with no violations more severe than level 4.
No unplanned automatic reactor scrams or safety system actuations.
Objectives to support SAFE OPERATIONS.
OBJECTIVE 1-1:
. No challenges to a nuclear safety system.
j OBJECTIVE 1-2:
Conduct activities in accordance with applicable policies, technical specifications, procedures, standing orders and work instructions.
I Less than 1.4 NRC violations per 1,000 inspection hours.
Fewer significant Corrective Action Documents (CADS) originating from activities.
o OBJECTIVE 1-3:
Identify conditions BEFORE they affect plant safety and reliability.
OBJECTIVE 1 Achieve all safety-related 1995 performance indicator goals in the Performance Indicator Report.
OBJECTIVE 1-5:
Zero Lost Time Injuries and recordable injuries rate BELOW 1.5 percent.
R i
t X
v
t OPPD NUCLEAR ORGANIZATION GOALS Vice President-1995 Priorities
{
raealt:
PERFORMANCE Supports: April 1994 Corporate Strategic Plan Goal 3, Obj: 2 and Goal 4, Obj: 1 Achieve high standards of performance at Fort Calhoun Station resulting in safe, reliable and i
cost effective power production.
1995 PRIORITIES:
Improve Quality, Professionalism and Teamwork.
lmprove Plant Reliability.
=
Meet or exceed INPO key parameters and outage performance goals.
Reduce the number of Human Performance errors.
Identify Programmatic performance problems through effective self assessment.
I i
Objectives to support PERFORMANCE:
OBJECTIVE 2-1:
Achieve an annual plant capacity factor of 70% and a unit capability factor of 81%.
OBJECTIVE 2 Execute the 1995 refueling outage in 49 days; emphasize shutdown plant safety.
t OBJECTIVE 2-3:
i Achieve all performance related 1995 performance indicator goals in the Performance Indicator Report.
i OBJECTIVE 2-4:
All projects and programs are planned, scheduled, and accomplished according to schedules, resource constraints, and requirements.
OBJECTIVE 2-5:
Team /Individuelownership, accountability, performance and teamwork is evident by improved plant reliability; improved ratings for both INPO and NRC; reduced number of human performance i
errors and identification of performance problems by effective self assessment and for individuals as measured by the successful completion of department goals & objectives and other '
specific measures.
I i
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OPPD NUCLEAR ORGANIZATION GOALS Vice President-1995 Priorities Goal 3:
COSTS Supports: April 1994 Corporate Strategic Plan Goal 2, Obj: 1,2 and 3, and Goal 6, Obj: 1 Operate Fort Calhoun in a manner that cost effectively maintains nuclear generation as an economically viable contribution to OPPD's " bottom line". Cost consciousness is exhibited at alllevels of the organization.
1995 Priorities:
Maintain total O&M and Capital Expenditures within budget.
Streamline work process to improve cost effectiveness.
Objectives to support COSTS:
l OBJECTIVE 3-1:
Conduct the nuclear programs, projects, and activities within the approved Capital and O&M budgets.
OBJECTIVE 3-2:
Implement nuclear related Opportunity Review recommendations according to approved schedules and attain the estimated cost savings.
C Goals Source:
Scofield (Manager)
X5 r
SAFE OPERAT ONS i
Goal: A proactive, self-critical and safety conscious culture i
is exhibited throughout the nuclear organization. Individu-als demonstrate professionalism through self-ownership and personal initiative and open communication.
4 5
1
--* -- Year-to-Date FCS Industrial Safety Accident Rate (INPO Definition)
-e-- FCS Average Rate (Last 12 Months)
-*-- FCS Year-End Goal (<0.50) l GOOD l
--#-- Industry Current Best Quartile (.24)
- *-- 1995 INPO industry Goal (<0.50) k 1.8 1.4 -
1.2 1-0.8 -
h 0.4 9 [ =
0.2 C
=
=
=
=
=
=
=
=
=
=
2 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1995 INDUSTRIAL SAFETY ACCIDENT RATE As stated in INPO's December 1993 publication ' Detailed Descriptions of World Associa-l tion of Nuclear Operators (WANO) Performance Indicators and Other Indicators for Use at U.S. Nuclear Power Plant': "The purpose of this indicator is to monitor progress in improv-ing industrial safety performance for utility personnel permanently assigned to the station."
The INPO industrial safety accident rate value year to date was 1.49 at the end of May 1995. The value for the 12 months from June 1,1994, through May 31,1995, was 0.67.
There were two lost-time accident and no restricted-time accidents in May 1995. There have been no restricted end five lost-time accidents during the year 1995.
The values for this indicator are determined as follows:
(number of restricted-time accidents + lost-time accidents + fatalities) x 200.000 (number of station person-hours worked)
The 1995 Fort Calhoun year-end goal is 50.50. The 1995 INPO industry goal is 50.50.
The approximate industry upper ten percentile value (for the period from 7/93 through 6/94) is 0.12.
c Data Source:
Sorensen/Skaggs (Manager / Source)
Chase / Booth (Manager / Source)
Accountability:
Chase / Conner Adverse Trend 2
+ 1995 Disabling injury / Illness Frequency
-X-1994 Disabling injury / Illness Frequency l GOOD l 2.-
-*- Average Rate (Last 12 Months) 1.8 --
f
- *- Fort Calhoun Goal 1.6 --
e 1.4 -
1.2 --
1--
0.8 --
^
^
O.6 -
N 0.4 a x_
--x-
-x 0.2 -
0 H
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1995 DISABLING INJURY /lLLNESS FREQUENCY RATE (LOST-TIME ACCIDENT RATE) i This indicator shows the 1995 disabling injury / illness frequency rate. The 1994 disabling injury / illness frequency rate is also shown.
The disabling injury / illness frequency rate year to date was 1.49 at the end of May 1995.
There was one disabling injury / illness reported for the month. This disabling injury re-suited from lifting procedure manuals causing a strained knee when bending over. There i
have been five disabling injuries in 1995.
The disabling injury / illness frequency rate for the 12 months from June 1,1994, through May 31,1995, was.80.
i The 1995 Fort Calhoun year-end goal for this indicator is a maximum value of 0.5.
Data Source:
Sorensen/Skaggs (Manager / Source)
{
Accountability:
Chase / Conner Adverse Trend:
None SEP 25,26 & 27 3
2.5..
-*- 1995 Recordable injury / Illness Frequency
--M-1994 Recordable injury /linness Frequency
+
2.25 -
-*-- Average Rate (Last 12 Months)
Good
-*-- Fort Calhoun Goal i
2 y
1 75 -
1.5 -
2 1.25 -
1--
0.75 -
O.5 0.25 -
1 0-Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec 1995 RECORDABLE INJURY /lLLNESS FREQUENCY R ATE This indicator shows the 1995 recordable injury / illness frequency rate. The 1994 record-able injury / illness cases frequency rate is also shown.
A recordable injury / illness case is reported if personnel from any of the Nuclear Division are injured on the job and require corrective medical treatment beyond first aid. The recordable injury illness cases frequency rate is computed on a year-to-date basis.
There have been four recordable injury / illness cases in 1995. The recordable injury /
illness cases frequency rate year to date was 1.19 at the end of May 1995. There was no recordable injury / illness case reported for the month of May.
The recordable injury / illness cases frequency rate for the 12 months from June 1,1994, through May 31,1995, was 1.07.
The 1995 Fort Calhoun year-end goal for this indicator is a maximum value of 1.5.
Data Source:
Sorensen/Skaggs (Manager / Source)
Accountability:
Conner Adverse Trend:
None SEP 15,25,26 & 27 4
C::3 Contamination Events (Monthly)
--*- Contamination Events (YTD) l GOOD l l
60 --
Y e
50 -
40 --
39 31 30 +
N-10 -
4l l$,f i,*
~
s M
, ["y,
f Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1995 CLEAN CONTROLLED AREA CONTAMINATIONS 21,000 DISlNTEGRATIONS/
MINUTE PER PROBE AREA This indicator shows the Personnel Contamination Events in the Clean Controlled Area for contaminations 21,000 disintegrations / minute per probe area for the reporting month.
There were 8 contamination events in May 1995. There has been a total of 39 contami-nation events in 1995 through the end of May.
Data Source:
Chase /Little (Manager / Source)
Accountability:
Chase /Lovett Adverse Trend:
None SEP 15 & 54 5
51E5 Personnel Errors (Each Month) Preventable (18-Month Totals)
-G-Personnel Error (18-Month Totals)
- N
=
12 -
10 -
I C
C 6-4-
C C
3 2-0 l
Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 1993 1994 1995 PREVENTABLE / PERSONNEL ERROR LERs This indicator depicts 18-month totals for numbers of " Preventable" and " Personnel Error" LERs.
The graph shows the 18-month totals for preventable LERs, the 18-month totals for Personnel Error LERs and the Personnel Error totals for each month. The LERs are trended based on the LER event data as opposed to the LER report date.
In April 1995, there were no events which were subsequently reported as an LER.
However, one event that occurred in March 1995 was subsequently determined to be reportab!e as an LER. Although No LERs were categorized as Preventable or as a Personnel Error for the month of April, the one event from March 1995 was determined to be Preventable.
The total LERs for the year 1995 (through April 30,1995) is two. The total Personnel Error LERs for the year 1995 is zero. The total Preventable LERs for the year is one.
The 1995 goal for this indicator is that the year-end values for the 18-month totals be no more than 12 Preventable and 5 Personnel Error LERs.
c Data Source:
Trausch/Cavanaugh (Manager / Source)
Accountability:
Chase Adverse Trend:
None SEP 15 6
3 --
startup Shutdown l GOOD l IlllllllllI Operation
- Industry Average Trend h2--
p k
h d
A 1-b f
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92 2 92-3 92-4 93-1 93-2 93-3 93-4 94 1 94-2 94-3 94-4 95-1 Year-Ouarter SAFETY SYSTEM FAILURES This indicator illustrates the number of NRC Safety System Failures as reported by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data in the biannual
" Performance Indicators for Operating Commercial Nuclear Power Reactors" report. First Quarter 1994 through First Ouarter 1995 are projected.
The following NRC safety system failures occurred between the second quarter of 1994 and the first quarter of 1995.
First Ouarter 1993: The SG low pressure scram signal block reset values, for all 4 channels of both SGs, were greater than the allowed limits, rendering this scram input inoperable during cer-tain operating conditions.
Second Quarter 1993: A section of the piping configuration for the borated water source of the safety injection sytem was not seismically qualified. This could have resulted in a failure of the system to meet design requirements during a seismic event.
Fourth Ouarter 1993: 1) During surveillance testing, both PORVs for the LTOP system failed to open during multiple attempts. The failures were a result of differential expansion caused by a loop seat, inappropriate venting line back pressure, and cracked valve disks; 2) Calibration errors of the offsite power low signal relays could have prevented offsite power from tripping and the EDGs from starting in the required amount of time during a degraded voltage condition; 3) Both AFW pumps were inoperable when one was removed from service for testing and the control switch for the other pump's steam supply valve was out of the auto position; 4) Only one train of s
control room ventilation was placed in recirc when both toxic gas monitors became inoperable.
Later during surveillance, the other train auto-started and brought outside air into the control room for a six-minute period.
First Quarter 1994: A design basis review determined that an ESF relay could result in loss of safety injection and spray flow, due to premature actuation of recirculation flow.
Data Source:
Nuclear Regulatory Commission Accountability:
Chase Adverse Trend:
None 7
f 1
--+- 1995 Monthly High Pressure Safety injection System Unavailability Value
-W-- 1995 Year.to-Date High Pressure Safety injaction System Unavailability Value "d>""" 1995 Fort Calhoun Goal (0.004)
-dr= 1995 INPO Industry Goal (0.02)
--4b Industry Upper 10% (0.0011) 0.03 --
0.025 --
Y 0.02.
0.015 --
0.01 0 005 '
=
=
=
=
=
=
=
=
=
=
=
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=
=
2 7
l 1994 Unavailability Jan Feb Mar May Jun Jul Aug sep Oct Nov Dec value 1995 i
HIGH PRESSURE SAFETY INJECTION SYSTEM l
SAFETY SYSTEM PERFORMANCE This indicator shows the High Pressure Safety injection System unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for the reporting month.
l The High Pressure Safety System unavailability value for the month of May 1995 was i
0.0005. There was 0.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of planned unavailability, and no hours of unplanned un-availability, during the month. The 1995 year-to-date HPSI unavavailability value was 0.0003 at the end of the month. The unavailability value for the last 12 months was 0.0027.
There has been a total of 1.83 hours9.606481e-4 days <br />0.0231 hours <br />1.372354e-4 weeks <br />3.15815e-5 months <br /> of planned unavailability and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned l
unavailability for the high pressure safety injection system in 1995.
d The 1995 Fort Calhoun year-end goal for this indicator is a maximum value of 0.004. The l
1995 INPO industry goal is 0.02 and the industry upper ten percentile value (for the three-
.I year period from 1/92 through 12/94) is approximately 0.001.
Data Source:
Jaworski/Schaffer Accountability:
Jaworski/Schaffer Positive Trend 8
Monthly Auxiliary Feedwater System Unavailability
-M-- Year-to-Date Emergency AC Power Unavaliability
--*- Fort Calhoun Goal (0.01) l GOOD l
-e - 1995 INPo industry Goal (0.025)
--e-Industry Upper 10% (0.0021) 0.03 -
l 0.025 -
0.02 d 1
1 1
1 0.015 -
0.01 4 i
0.005 -
E
-- -G ----e
'y 0 :.
l l
l Unevasabimy Jen Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec value 1995 AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Auxiliary Feedwater System Unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for the reporting month.
l The Auxiliary Feedwater System Unavailability Value for May 1995 was 0.0. There were O hours of planned and 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned unavailability during the month. The year-to-date unavailability value was 0.0063 and the value for the last 12 months was 0.0058 at i
the end of the month.
There has been a total of 27.68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> of planned unavailability and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of un-l planned unavailability for the auxiliary feedwater system in 1995.
f The 1995 Fort Calhoun year-end goal for this indicator is a maximum value of 0.01.
l-The 1995 INPO industry goal is 0.025 and the industry upper ten percentile value is ap-proximately 0.002.
l L
Data Source:
Jaworski/Nay l
Accountability:
Jaworski/Nay Adverse Trend:
None 9
l
i 0.07.
C 3 Monthly Emergency AC Power Unavailability Value f
=W-Year-to-Dale Emergency AC Power Unsvaliability Value - Fort Calhoun Goal (0.024) l GOOD l 0.0s -
-*- 1996 INPO Industry Goal (0.025)
-e-Industry Upper 10% (0.0035) y 0.05 --
0.04 0.03 --
5 5
5 5
5 5
5 5
5 5
5 5
0.02 -
t 0.01 E
t
=
=,' :
=
=.
. rl Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1995 EMERGENCY AC POWER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Emergency AC Power System unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for the reporting month.
The Emergency AC Power System unavailability value for May 1995 was 0.0084. During the month, there were 12.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of planned unavailability for testing, and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned unavailability. The Emergency AC Power System unavailability valus year-to-date was 0.0039 and the value for the last 12 months was 0.0067 at the end of the month.
There has been a total of 28.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of planned unavailability and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned unavailability for the emergency AC power system in 1995.
The 1995 Fort Calhoun year-end goal for this indicator is a maximum value of 0.024.
The 1995 INPO industry goal is 0.025 and the industry upper ten percentile value is ap-proximately 0.0035.
Data Source:
Jaworski/Ronning Accountability:
Jaworski/Ronning Positive Trend based on performance better than goal 10
M Failures /20 Demands i Failures /50 Demands i
GOOD 1253 Failures /100 Demands
-e-TriggerValues/20 Demands iV
-*- Trigger Values /50 Demands
-*- Trigger Values-100 Demands d
8 -- :
7-6-
5-A i
a a
a i
2 a
4-3-
2 2-g 1
1 1
1 1
1 11 j
111 11 11 11 11 1-0 l
Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 EMERGENCY DIESEL GENERATOR UNIT RELIABILITY This bar graph shows three monthly indicators pertaining to the number of failures that were reported during the last 20,50, and 100 emergency diesel generator demands at the Fort Calhoun Station. Also shown are trigger values which correspond to a high level of confidence that a unit's diesel generators have obtained a reliability of greater than or equal to 95% when the failure values are below the corresponding trigger values. The Fort Calhoun 1995 goal is to have fewer failures than these trigger values.
The demands counted for this indicator include the respective number of starts and the respective number of load-runs for both Diesel Generators combined. The number of start demands includes all valid and inadvertent starts, including all start-only demands and all start demands that are followed by load-run demands, whether by automatic or manual initiation. Load-run demands must follow successful starts and meet at least one of the following criteria: a load-run that is a result of a real load signal, a load-run test j
3 expected to carry the plant's load and duration as stated in the test specifications, and a special test in which a diesel generator was expected to be operated for a minimum of one hour and to be loaded with at least 50% of design load (see exceptions and other demand criteria in the Definition Section of this report).
Data Source:
Jaworski/Ronning (Manager / Source)
Accountability:
Jaworski/Ronning Positive Trend i
11
j DO-1 Failuree/25 Demands DO-2 Failureet25 Demands l GOOD l
-O-Failure Trigger Value for 25 Demande/ Fort Calhoun Goal y
4-c 3
.i 3-l I
g.
1 1
1 1
1 1
1-ee ee ee ee ee ee e
e e
s e
e 0
Jun Jul Aug sep oct Nov Dec Jan Feb Mar Apr May 1994 1995 DIESEL GENERATOR RELIABILITY (25 DEMANDS)
This indicator shows the number of failures experienced by each emergency diesel gen-erator during the last 25 start demands and the last 25 load-run demands. A trigger value of 4 failures within the last 25 demands is also shown This trigger value of 4 failures within 25 demands is the Fort Calhoun goal for 1995.
It must be emphasized that, in accordance with NUMARC criteria, certain actions will take place in the event that any one emergency diesel generator experiences 4 or more fail-uros within the last 25 demands on the unit. These actions are described in the Defini-tions Section of this report. A System Engineering instruction has been approved for the Fort Calhoun Station to institutionalize and formally approve / adopt the required NUMARC actions.
Diesel Generator DG-1 has experienced one failure during the last 25 demands on the unit. On December 8,1994, DG-1 failed its monthly surveillance test because the inlet air damper would not open. The cause of the failure was found to be ice buildup on the 9
damper louvers from a previous snowstorm.
Diesel Generator DG-2 has not experienced any failures during the last 25 demands on the unit.
Data Source:
Jaworski/Ronning (Manager / Source)
Accountability:
Jaworski/Ronning Positive Trend due to performance better than goal
[
12
[
i I
j i
~
~
\\
m DG 1 UnreliabilityValue M DG 2 UnreliabilityValue coop m Station UnreliabilltyValue m industry Upper 10% (0.002 for a 3-Year Average) 0.08 -
-e-1995 Goal 0.07 -
0.06 -
0.05 0.05 -
c r
c 0.04 -
0.03 0.02 -
0.01 0
Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 EMERGENCY DIESEL GENERATOR UNRELIABILITY The purpose of this indicator is to monitor the likelihood that emergency AC power gen-erators will respond to off-normal events or accidents. It also provides an indication of the effectiveness of maintenance, operation and test practices in controlling generator unreliability.
The year-to-date station EDG unreliability at the end of May 1995 was 0.0. The 1995 goal for this indicator is a maximum value of 0.05.
For DG-1:
There were 6 start demands for the reporting month without a failure.
In addition, there was 2 load-run demand without a failure.
For DG-2:
There were 5 start demands for the reporting month without a failure.
In addition, there was 1 load-run demand without a failure.
Emergency diesel generator unreliability is calculated as follows:
i value per DG = SU + LU -(SU x LU) where SU = Start Unreliability = number of unsuccessful starts number of valid start demands 3
i LU = Load-run Unreliability = number of unsuccessful load-runs l
number of valid load-run demands l
l Station Value = average of DG-1 and DG-2 values Data Source:
Jaworski/Ronning (Manager / Source)
Accountability:
Jaworski/Ronning Positive Trend 13
Fuel Reliability lG000l
-*- 1995 INPO Industry Fuel Defect Reference (5 x 104 Microcuries/ Gram) 1995 Goal y
20 --
t E
p a
sn 0
k 15 -
w
'2 N
U P!j cycle 16 fE h
out 2
5-0 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 FUEL RELIABILITY INDICATOR The FUEL RELIABILITY INDICATOR (FRI) for May 1996 was 3.176 X 10d microcuries/ gram. The purpose of the FRI is to monitor industry progress in achieving and maintaining a high level of fuelintegrity. An effective fuel integrity and performance monitoring program provides a means to detect fuel failures and assess the fuel failure number, physical condition, exposure, mechanism, and location.
The May FRI value is based on data from May 1 through 3, May 5 through 8, and May 11. The Westinghouse Fuel Performance Group recommended calculating the May FRI value using data forthese days only. The days selected are when the plant chemistry values reached equilibrium from steady-state full power opera-tion.
Cycle 16 plant operation started on April 13 and attained 100% power on April 23. During May, the plant operated at 100% power until May 11th when the plant was tripped and remained at hot shutdown conditions for repairs to a Reactor Coolant Pump lubricant oil cooler. The plant commenced power increase on May 15th obtaining 100% power on May 17th. The plant remained at 100% power until May 23rd when the plant was tripped and brought to a cold shutdown condition for replacement of faulty Reactor Coolant Pump lubri-cant oil coolers. The plant remained a cold shutdown through May 28th. The plant once again commenced a power increase on May 29th and reached 95% on May 31st.
The May FRI value of 3.176 X 10d microcuries/ gram indicated an increase from the April FRI value of 0.9556 X 10d microcuries/ gram. The Xenon activity has shown an increase through the cycle. In May, there were several lodine-131 spikes during the plant trips and also increasing lodine-131 values during 100% opera-tion, indicating one or more failed fuel pins.
~
The INPO September 1992 report, " Performance Indicators for US Nuclear Utility Industry" (INPO No.92-011) states that "the 1995 industry goal for fuel reliability is that units should strive to operate with zero fuel defects. A value larger than 5 x 10-4 microcuries/ gram indicates a high probability of reactor core operation with one or more fuel defects. The determination of current defect-free operation requires more sophisti-cated analysis by utility reactor engineers." The value of 5.0 x 10-4 microcuries/ gram is defined as a " Fuel Defect Reference" number of a "Zero LeakerThreshold." Each utility will evaluate whether the core is defect free or not. The 1995 Fort Calhoun Station FR1 Performance Indicator goal is to maintain a monthly FRl below 5.0 x 10-4 microcuries/ gram.
Data Source:
Holthaus/ Weber Accountability:
Chase /Spijker Adverse Trend:
None 14
> Control Room Deficiences Repairable On-Line i
l GOOD l IEEE Total Number of Control Room Deficiencies 80 --
-<>- FCs Goal for Total Control Room Deficiencies (CRD's) (45) 70 -
60 -
,I Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1984 1995
> Operator Work Around CRD's Repairable On-Line oo i
EEEl Total Number of Operator Work Around CRD's T
-o-FCs Goal for Total Operator Work Around CRD's (5)
Y 12 -
h 10 -
p 8
k V
e-c e
=
=
=
r1
[;
__c o
-j
-j g
j e
v r
r4,
a rW; e re ro r
.ra rL o
n Jul Aug sep Oct Nov Dec Jan Feb Mar Apr Mag NUMBER OF CONTROL ROOM EQUIPMENT DEFICIENCIES This indicator shows the number of Control Room Deficiencies that are repairable during plant operations (on-line), the number of outstanding Control Room Deficiencies, the number of Operator Work Around (OWA) CRD's repairable on-line, the number of outstanding Operator Work Around CRD's and the Fort Calhoun goals.
There was a total of 51 Control Room Deficiencies at the end of May 1995. 33 of these deficiencies are repairable on-line and 18 require a plant outage to repair.
There were 4 OWA CRD's identified at the end of the month on equipment tags: CH-208, RC-3C and RC-3D on C/R Panel CB-1/2/3; and FW-54 on C/R Panel CB-10/11. 3 OWA CRD's require an outage to repair.
The 1995 Fort Calhoun monthly goal for this indicator is a maximum of 45 CRD's and 5 OWA CRD's.
L Data Source:
Chase / Tills (Manager / Source)
Accountability:
Chase /Faulhaber y
Adverse Trend:
None is
=
m Monthly Personnel Radiation Exposure
--*-- Personnel cumulative Radiation Exposure l GOOD l
^
FCs Goal (143.1 Person-Rem) 150 r
^
0 0
^
^
^
^
^
o qq y 130 --
120 -
110 -
c '00 ~
+,
E 90 -
(W of 80 -
D k 70 --
i2b D
' 60 -
$b 50 -
f M-30 -
m f!9 6
20 Q
10 -
0-Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1995 COLLECTIVE RADIATION EXPOSURE The 1995 Fort Calhoun goal for collective radiation exposure is less than 143.1 person-Rem.
The exposure for May 1995 was 5.915 person-Rem (by ALNOR).
The year-to-date exposure through the end of April was 130.650 person-Rem (TLD & ALNOR).
The 1995 INPO industry goal for collective radiation exposure is 185 person-rem per year.
The current industry best quartile is 145 person-rem per year. The yearly average for Fort Calhoun Station for the three years from 6/92 through 5/95 was 113.076 person-rem per year.
c Data Source:
Chase /Little (Manager / Source)
Accountability:
Chase /Lovett Adverse Trend:
None SEP54 16
1
~
O Highest Exposure (May)
)
Ill Highest Exposure (1995) oPPD 4500 mRemlyr. Limit 4000-3000 -
i i
2000 -
itse E
""""2 flu %!
WS FCs Goal 261 5
i
~"
l I
o Highest Highest Exposure Exposure (May)
(1995).
MAXIMUM INDIVIDUAL RADIATION EXPOSURE During May 1995, an individual accumulated 261 mrem, which was the highest indi-vidual exposure for the month.
The maximum individual exposure for the year of 1,000 mrem was exceeded during March 1995 when an individual received 1,266 mrem. (875 mrem of this was received during orifice plate repair in a steam generator.) However, the OPPD 4500 Mrem /yr limit is not expected to be exceeded.
i The OPPD limit for the maximum yearly individual radiation exposure is 4,500 mrem /
year. The 1995 Fort Calhoun year-end goal is a maximum of 1,000 mrem.
i 3
Data Source:
Chase /Little (Manager / Source)
Accountability:
Chase /Lovett Adverse Trend:
None 17
I"""3 FCs Cited Violations (Monthly)
CD FCs Non-Cited Violations (Monthly) l Good l
-G-FCs Cited Violations (12-Month Average) f
-*- FCs Non-Cited Violations (12-Month Average) 14 --
12 --
10 --
6-
~
2 0
May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 1994 1995 VIOLATION TREND This indicator illustrates a 12-month trend for Fort Calhoun Station Cited Violations, Non-Cited Violations and Cited Violations for the Top Quartile plants in Region IV. Addition-ally, the Fort Calhoun Station cited and non-cited violations will be illustrated monthly for the past 12 months. The 12-month trend for the Region IV top quartile lags 2-3 months behind the Fort Calhoun Station trend. This lag is necessary to compile information on other Region IV plants.
The following inspections were completed during April 1995:
IER No.
Title 95-07 Monthly Resident inspection 95-08 Liquid and Gaseous Radioactive Waste Treatment To date, OPPD has received four violations for inspections conducted in 1995.
Level ill Violations 0
Level IV Violations 2
Level V Violations 0
Non-Cited Violations 2
Total 4
The 1995 Fort Calhoun Station Goal for this performance indicator is to be at or below the cited violation trend for the top quartile in Region IV.
Data Source:
Trausch/Cavanaugh (Manager / Source)
Accountacility:
Trausch Adverse Trend:
None 18 l
l
NRC significant Events Good l
--e-- Industry Average Trend 9
1-w Y
f 0.5 -
I 2
- -r Om
,--:~,- L i O
-r-9? 2 92-3 92 4 93-1 93-2 93-3 93-4 94-1 94-2 94-3 94-4 95 1 Year - Quarter 2
INPo significant Events (sERs) l Goop l 2-m f
1 1
1 1
1 0
h hh h
h
'~
- - -h 92-2 92-3 92-4 93-1 93-2 93-3 93 4 94-1 94-2 94-3 94-4 95-1 Year - Quarter SIGNIFICANT EVENTS This indicator illustrates the number of NRC and INPO Significant Events for Fort Calhoun Station as reported by the Nuclear Regulatory Commission's Office for Analysis and Evalu-ation of Operational Data in the biannual " Performance Indicators for Operating Commer-cial Nuclear Power Reactors" report and INPO's Nuclear Network.
The following NRC significant events occurred between the second quarter of 1992 and the first quarter of 1995:
Third Quarter 1992: The failure of a Pressurizer Code safety valve to ressat initiated a LOCA with the potential to degrade the reactor coo! ant pressure boundary.
The following INPO significant events, as reported in Significant Event Reports (SERs),
occurred between the second quarter of 1992 and the First Quarter of 1995:
Second Quarter 1992: Intake of Transuranics during Letdown Filter Change-out.
Third Quarter 1992: 1) RC-142 LOCA; and 2) Premature Lift of RC-142.
First Quarter 1993: Inoperability of Power Range Nuclear Instrumentation Safety Channel D.
Second Quarter 1993: SBFU Breaker Relay (Switchyard) Plant Trip l
Fourth Quarter 1993: Unexpected CEA Withdrawal.
First Quarter 1994: Unplanned dilution of Boron concentration in the RCS.
Data Source:
Nuclear Regulatory Commission & INPO Accountability:
Chase Adverse Trend:
None 19
m l
l 1
~
3 --
D Missed sTs Resulting in LERs l- -
l 1
1--
l 0
0 0
0 0-
'O f
l0 93 94 Jan Feb Mar Apr May Jun Jul
-Aug Sep det Nov Dec j
ws NUMBER OF MlSSED SURVEILLANCE TESTS i
RESULTING IN LICENSEE EVENT REPORTS l
This indicator shows the number of missed Surveillance Tests (STs) that result in Lic-ensee Event Reports (LERs) during the reporting month. The graph on the left shows the yearly totals for the indicated years.
l There were no missed surveillance tests resulting in LERs during May 1995.
On December 28,1994, during the performance of OP-ST-SHIFT-0001, data was not entered for Steam Generator level per Surveillance Requirements.
l The 1995 Fort Calhoun monthly goal for this indicator is 0.
I C
Data Source:
Monthly Operating Report & Plant Licensee Event Reports (LERs)
Accountability:
Chase /Jaworski l
Positive Trend SEP 60 & 61 l
20
PERFORMANCE
~
Goal: To strive for Excellence in Operations utilizing the highest standards of performance at Fort Calhoun Station that result in safe, reliable plant operation in power produc-tion.
o e
s 21
50 -
B Not Generation (10,000 Mw hours) 40 -
}
"'I 33.s1 M.14 33.se e
l 30 -
e f
2222 21.19
.20 -
15.29 i
Cycle 15 Refueling 10 -
Outage o
0 1
Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May e
1994 1995 STATION NET GENERATION l
During the month of May 1995, a net total of 228,248 MWH was generated by the Fort Calhoun Station. Cumulative net generation for Cycle 16 was 381,165 MWH at the end of l
the month.
Unplanned energy losses for the month of May 1995 were attributable to: (1) on May 11, 1995, at 1105 hrs. the Fort Calhoun Station generator and reactor were manually tripped
(
because it was determined that component cooling water was leaking into the lube oil system of RC-3D reactor coolant pump motor; after repairs and inspections of all the RCP motors, the reactor was taken critical at 0313 on May 15,1995, and the generator was put i
on line at 1056 on May 15,1995; and (2) on May 24,1995, at 0029 hrs. the Fort Calhoun generator and reactor were manually tripped because of a similar leak. The reactor was brought critical at 2135 on May 28,1995, and the generator was put on-line at 0907 on May 29,1995, after replacement of all of the reactor coolant pump lube oil cooler heat exchangers.
Data Source:
Station Generation Report Accountability:
Chase Adverse Trend:
None i
22
-l
-l
)
C""3 Forced outage Rate (Monthly)
.g,
-+- Forced outage Rate (12 Months) l Good l 38% -
-+- Fort Calhoun Goal (2.4%)
m-l 25% -
l 20% -
15% -
mm
~
C d*18 F
10% -
netsmiing 8% -
om
=
=
=
=
=
=
+
l
=
0
=
0 0
2 C
M 0%
i
- 92 93 94 Jun Jul Aug sep od Nov Dec Jan Feb Mar Apr ' May t
1994 1994 FORCED OUTAGE RATE l
1 The forced outage rate'(FOR) was reported as 3.0% for the twelve months from June 1, l
1994, through May 31,1995. The 1995 year-to-date FOR was 9.6% at the end of the
.I
- month, i
i Unplanned energy losses for the month of May 1995 were attributable to: (1) on May 11,.
l 1995, at 1105 hrs. the Fort Calhoun Station generator and reactor were manually tripped because it was determined that component cooling water was leaking into the lube oil.
{
system of RC-3D reactor coolant pump motor; after repairs and inspections of all the RCP.
motors, the reactor was taken critical at 0313 on May 15,1995, and the generator was put on line at 1056 on May 15,1995; and (2) on May 24,1995, at 0029 hrs. the Fort Calhoun j
generator and reactor were manually tripped because of a similar leak. The reactor was brought critical at 2135 on May 28,1995, and the generator was put on-line at 0907 on May 29,- 1995, after replacement of all of the reactor coolant pump lube oil cooler heat exchangers.
i The 1995 Fort Calhoun year-end goal for this indicator is a maximum value of 2.4%
Data Source:
Monthly Operations Report j
Accountability:
Chase Adverse Trend:
None 23 i
P1 Monthly Unst Capacity Factor
-e-- Unit Capacity Factor for Cycles 15 & 18 120.00% -
-*-- 36-Month Average Unit Capacity Factor
--M - FCS Goal (85%)
100.00% -
2 3
5 h
h y
80.00% -
=
so.00%
40.00% -
~
c ycle is 20.00% -
us ns 0.00%
Jun Jul Aug Sep O ct Nov Dec Jan Feb Mar Apr May 1994 1995 UNIT CAPACITY FACTOR This indicator shows the plant monthly Unit Capacity Factor, the Unit Capacity Factor for the current fuel cycle and the 36-month average Unit Capacity Factor.
Unplanned energy losses for the month of May 1995 were attributable to: (1) on May 11, 1995, at 1105 hrs. the Fort Calhoun Station generator and reactor were manually tripped because it was determined that component cooling water was leaking into the lube oil system of RC-3D reactor coolant pump motor; after repairs and inspections of all the RCP motors, the reactorwas taken critical at 0313 on May 15,1995, and the generator was put on line at 1056 on May 15,1995; and (2) on May 24,1995, at 0029 hrs. the Fort Calhoun generator and reactor were manually tripped because of a similar leak. The reactor was brought critical at 2135 on May 28,1995, and the generator was put on-line at 0907 on May 29,1995, after replacement of all of the reactor coolant pump lube oil cooler heat exchangers.
At the end of the month, the Cycle 16 Unit Capacity factor was 54.51%, and the Unit Capacity Factor for the last 36 months was 80.88%. The 1995 Fort Calhoun goal for this indicator is 85%.
The Unit Capacity Factor is computed as follows:
4 Net Electrical Enerav Generated (MWH)
Maximum Dependable Capacity (Mwe) X Gross Hours in the Reporting Period Data Source:
Monthly Operating Report Accountability:
Chase Adverse Trend:
None 24 L
C Monthly EAF Year-to-Date Average Monthly EAF
-dr-- 12-Month Average EAF
--M-Industry Median Value(76.7%for a 3 Year Average) l GOOD l e
W
=
=
i E
5"?
~
/
x2
~
=
s s
s a
=
=
=
a w
E8 N=
=
B~g 60% -
~
40% -
Cycle 15 Refueling Outage 0%
52 5 M Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 EQUIVALENT AVAILABILITY FACTOR This indicator shows the plant monthly Equivalent Availability Factor (EAF), the year-to-l date average monthly EAF, and the year-end average monthly EAF for the previous three years.
The EAF for May 1995 was reported as 62.7% due to the refueling outage. The year-to-date monthly average EAF was 67.4% at the end of the month.
The Fort Calhoun average monthly EAF for the three years prior to this report was 85.9%.
l The industry median EAF value for the three-year period from 7/90 through 6/93 was l
76.7%.
l l
Data Source:
Dietz/Parra (Manager / Source)
Accountability:
Chase Adverse Trend:
None 25 i
C::::3 Monthly Unit Capability Factor
-M-Year-to-Date Unit capability Factor d
-+- 36-Month Unit Capability Factor l Good l 1994 and 1995 Fort Calhoun Goals 1.000 -
~
- 1994 and 1995 INPo industry Goals (80%)
-aw rp}
f f
?
h jTh 5 g
umma
- - - " - " ^
^
0.800 -
15
%f
'i 5
ga o
{4
{$
y,,j id 4
3 gj
$p
. i m
0.600 1
- n$<,g h
y[g g@
g j
j
/?
I
'j g
g
- j
%g 1
0.400 i
0
.i
^
h
((
g j
Refueling h
- i
- jj g
,y outage g
0.200 1j 0.000
-~
(fl p,h kN
[
hl
$f f
Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 UNIT CAPABILITY FACTOR This indicator shows the plant monthly Unit Capability Factor (UCF) value, the year-to-date UCFs, the 36-month average UCFs, and the UCF goals. UCF is defined as the ratio of the available energy generation over a given period of tima to the reference energy Generation (the energy that could be produced if the unit were operated continuously at full power under reference ambient conditions) over the same time period, expressed as a percentage (refueling penods excluded).
The UCF for May 1995 was reported as 63.5%. The year-to-date UCF was 46.7%, the UCF for the last 12 months was 77.6%, and the 36-month average UCF was reported as 81.4% at the end of the month.
Unplanned energy losses for the month of May 1995 were attributable to: (1) on May 11,1995, at 1105 hrs. the Fort Calhoun Station generator and reactor were manually tripped because it was determined that component cooling water was leaking into the lube oil system of RC-3D reactor coolant pump motor; after repairs and inspections of all the RCP motors, the reactor was taken critical at 0313 on May 15,1995, and the generator was put on line at 1056 on May 15,1995; and (2) on May 24,1995, at 0029 hrs. the Fort Calhoun generator and reactor were manually tripped because of a similar leak. The reactor was brought critical at 2135 on May 28,1995, and the generator was put on-line at 0907 on May 29,1995, after replacement of all of the reactor coolant pump lube oil cooler heat exchangers.
The 1995 INPO industry goalis 80% and the industry current best quartile value (for the three-year period ending 12/94)is approximately 85%. The 1995 Fort Calhoun year-end goal for this indica-toris a minimum of 79.65%.
Data Source:
Generation Totals Report & Monthly Operating Report Accountability: Chase Adverse Trend:
None 26
I C-3 Monthly Unplanned Capability Loss Factor l GOOD l 40% ~
--e-- Year To.Date Unplanned Capability Loss Factor 1
.-dr-- 12-Month Average Unplanned Capability Loss Factor f
l 35%
-*- Fort Calhoun Goal (3.97%)
--o-- 1995 INPO Industry Goal (4.5%)
~
--o-- Industry Current Best Quartile 30% -
25 %
1 A
[
20% -
15% -
.A 10% -
/
c
\\
5% -
1 1
=
1 1
1 1
1.
2 l
1 E
E 2 x- '
j Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1894 1995 UNPLANNED CAPABILITY LOSS FACTOR 1
This indicator shows the plant monthly Unplainned Capability Loss Factor (UCLF), the year-to-date UCLF and the goal. UCLF is defined as the ratio of the unplanned energy losses during a given period of time, to the reference energy generation (the energy that could be produced if the unit were operated continuously at J
full power under reference ambient conditions), expressed as a percentage.
Unplanned energy losses for February 1995 were due to a problem with a control element assembly seal j
leakage of reactor coolant. Unplanned energy losses for March 1995 were due to the start of the plant's 15th refueling outage,19 days prior to the originally scheduled start date.
The UCLF for the month of May 1995 was reported as 36.62%. Unplanned energy loss is defined as the energy that was not produced during the period of unscheduled shutdowns, outage extensions, or load reductions due to causes under plant management control. Energy losses are considered to be unplanned if they are not scheduled at least fourweeks in advance. The year-to-date UCLF was 21.08%, the UCLF for the last 12 months was 11.57%, and the 36-month average UCLF was reported as 7.77% at the end of the rnonth.
Unplanned energy losses for the month of May 1995 were attributable to: (1) on May 11,1995, at 1105 hrs.
the Fort Calhoun Station generator and reactor were manually tripped because it was determined that com-ponent cooling water was leaking into the lube oil system of RC-3D reactor coolant pump motor; after repairs j
and inspections of all the RCP motors, the reactor was taken critical at 0313 on May 15,1995, and the generator was put on line at 1056 on May 15,1995; and (2) on May 24,1995, at 0029 hrs. the Fort Calhoun generator and reactor were manually tripped because of a similar leak. The reactor was brought critical at 2135 on May 28,1995, and the generator was put on-line at 0907 on May 29,1995, after replacement of all of the reactor coolant pump lube oil cooler heat exchangers.
The 1995 INPO industry goal is 4.5% and the industry current best quartile value is approximately 3.2% or lower. The 1995 Fort Calhoun year-end goal forthis indicator is a maximum value of 3.97%.
Data Source:
Generation Totals Report & Monthly Operating Report Accountability:
Chase AdverseTrend: None 27
5-
- FCs Reactor Scrams Per 7,000 Hours Critcal Year to Date
-+-- FCS Reactor Scrams Per 7,000 Hours Critical for last 36 months
-*- 1995 & 1994 Fort Calhoun Goals (0.0) 4
-*- 1995 INPO Industry Goal (1)
-G-- Industry Upper 10% (1 per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical) 3 2
0 0
1 :.
=
=
=
=
=
=
=
0:
Jun Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 3
4-O FCs Reactor scrams 3
2 2
0 0
0 0
0 0
0 0
0 0
0 0
0 m
0 91 at 83 M u
Jul Aug sep Oct Nov Dec Jan Feb Mar Apr Mg UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7,000 HOURS CRITICAL The upper graph shows the number of unplanned automatic reactor scrams per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical (as defined in INPO's 12/93 publication " Detailed Descriptions of Interna-tional Nuclear Power Plant Performance Indicators and Other Indicators") for Fort Calhoun Station. The lower graph shows the number of unplanned automatic reactor scrams that occurred during each month for the last twelve months.
The year-to-date station value was 0.0 at the end of May 1995. The value for the 12 months from June 1,1994, through May 31,1995, was 0.0. The value for the last 36 months was 1.62.
The 1995 Fort Calhoun goal for this indicator is 0. The 1995 INPO industry goal is a maximum of one unplanned automatic reactor scram per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical. The indus-try upper ten percentile value is approximately 0.48 scrams per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical.
c Data Source:
Monthly Operations Report & Plant Licensee Event Reports (LERs)
Accountability:
Chase Positive Trend 28
I l
l 1
0 0
0 0
0 0
0 e
o e
o o
o i
i 80 H
91 92 93 94 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 UNPLANNED SAFETY SYSTEM ACTUATIONS -(INPO DEFINITION)
There were no INPO unplanned safety system actuations during the month of April 1995.
There was one INPO unplanned safety system actuation during the month of February 1994. It occurred on February 11,1994, when supervisory relay 86B/CPHSS failed, which resulted in tripping relay 86B/CPHS. The CPHS relay trip actuated the Safety injection Actuation Signal, Containment isolation Actuation Signal, Ventilation isolation Actuation Signal and Steam Generator Isolation Signal. The Steam Generator Isolation Signal au-tomatically closed both main stam isolation valves, which resulted in a concurrent turbine and reactor trip.
An INPO unplanned safety sytem actuation also occurred during the month of July 1992 due to the loss of an inverter and the subsequent reactor trip on 7/3/92.
The 1995 Fort Calhoun goal for this indicator is 0.
Data Source:
Monthly Operations Report & Plant Licensee Event Reports (LERs)
Accountability:
Jaworski/Foley/Ronning Positive Trend 29 i
)
A
p IllE23 Safety System Actuations (NRC Definition)
C 1995 FCS Goal (0) 12-Month Running Total ssAs (NRc Definition)
--*-- Critical Hours ens is
- ,0,';
o....
.m
.=
g
. soo g m
s.
4eo $
a m
4-
.m j y
f 2
4 j
g3
~"$
Ti l
0 0
92 93 94 J J A S O N D J F MAM J J A S O N D J F J F MA M UNPLANNED SAFETY SYSTEM ACTUATIONS -(NRC DEFINITION)
This indicator shows the number of unplanned safety system actuations (SSAs), which includes the High and Low Pressure Safety injection Systems, the Safety injection Tanks, and the Emergency Diesel Generators. The NRC classification of SSAs includes actua-tions when major equipment is operated and when the logic systems for these safety systems are challenged.
There was one NRC unplanned Safety system actuation during the month of February 1994. It occurred on February 11 when supervisory relay 86B/CPHSS failed, which re-suited in a concurrent turbine and reactor trip.
There has been no unplanned safety system actuations in the last 12 months. The 1995 Fort Calhoun goal for this indicator is 0.
Data Source:
Monthly Operations Report & Plant Licensee Event Reports (LERs)
Accountability:
Jaworski/Foley/Ronning Adverse Trend:
None 30
i m Monthly Gross Heat Rate 11 ~ Year-to-Date Gross Heat Rate lGCODl
^
1994 & 1995 Fort Calhoun Goals 10.75 -
\\
10.5 -
- ,g k
I f
?p h 10.25 -
h E
h y;
es as
- s E
F H
~
Bus i
si 10 -
o
~
b 11 it p
4 g
h h
i f
2 h hh f cycieis 9
L E
!?
3 p Refusimg
'z
+
l h
9.75 -
g
- .7
(;,
]
jl q
g g Outage h?
y Y3 Q
r X
n VJ a
rs v
i>r 4
et F
9.5 l
92 ID 94 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 GROSS HEAT RATE This indicator shows the Gross Heat Rate (GHR) for the reporting month, the year-to-date GHR, the goals and the year-end GHR for the previous three years.
The gross heat rate for Fort Calhoun Station was 10,219 for the month of May 1995. The _
1995 year-to-date GHR was 10,127 at the end of the month.
l The GHR varies with fluctuations in river water temperature. In general, the GHR im-proves during the winter months and degrades during the summer. This is because the gross heat rate is not normalized to the design river water temperature of 60 degrees Fahrenheit.
The 1995 Fort Calhoun year-end goal for this indicator is <10,157.
Data Source:
Holthaus/Willett (Manager / Source)
Accountability:
Chase /Jaworski Adverse Trend:
None 1
31
Monthly Thermal Performance CC 12-Month Average
--M-- Year to-Date Average Monthly Thermal Performance d
)
1996 Fort Calhoun Goal (99.9%)
j i
--e-19W INPO Industry Goal (99.8%)
GOOD
-e-Industry Upper 19% (99.7%)
100 %
I C
g l
s u
-x g
I s
l, Cyc516 f
99% -
j l
}
flli l
Refuehng j
h k
[
l5 N *9' l
(!
'i I!
I l-
[
98 %
Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 THERMAL PERFORMANCE This indicator shows the Thermal Performance Value for the reporting month, the year-to-date average monthly thermal performance value, the Fort Calhoun goals, the 1995 INPO industry goal and the approximate upper ten percentile value.
The thermal performance value for May 1995 was 99.67. The year-to-date average monthly thermal performance value was 99.3, at the end of the month. The average monthly value for the 12 months from June 1,1994, through May 31,1995, was 99.3%.
The 1995 Fort Calhoun year-end goal for this indicator is a minimum of 99.6%. The 1994 Fort Calhoun goal was a minimum of 99.5%. The 1995 INPO industry goal is 99.5% and the industry upper 10 percentile value is approximately 99.9%.
O Data Source:
Jaworski/Shubert Accountability:
Jaworski/Gorence Adverse Trend:
None 32 l
-+--Thermal Output -Fort Calhoun 1495 MW Goal
--dr--Tech Spec 1500 MW Limit 1600 -
- . C C C C C C C C C; O C C C C C C C C C ;
- C C C C 0-4 1400 -
Y 1200-wete, Leet we os wet Leek we sa l
system of RC-30 system of RC 3D E
,eector coolant
,eector coolant i
i g s00 -
- ete,
-, at, i
l 600 -
l t
400-200 -
0 4: -
1 2 3 4 6 8 7 8 9 10 11 12 13 14 16 16 17 18 19 20 21 22 23 24 25 28 27 28 29 30 31 DAILY THERMAL OUTPUT The thermal output graph displays the daily operating power level during May 1995, the 1500 thermal megawat average technical specification limit, and the 1495 the rmal mega-watt Fort Calhoun goal.
Unplanned energy losses for the month of May 1995 were attributable to: (1) on May 11, 1995, at 1105 hrs. the Fort Calhoun Station generator and reactor were manuali tripped f
because it was determined that component cooling water was leaking into the tube oil system of RC-3D reactor coolant pump motor; after repairs and inspections of all the RCP motors, the reactor was taken critical at 0313 on May 15,1995, and the generator was put on line at 1056 on May 15,1995; and (2) on May 24,1995, at 0029 hrs. the Fort Calhoun generator and reactor were manually tripped because of a similar leak. The reactor was brought critical at 2135 on May 28,1995, and the generator was put on-line at 0907 on May 29,1995, after replacement of all of the reactor coolant pump lube oil cooler heat exchangers.
t Data Source:
Holthaus/Willett (Manager / Source)
Accountability:
ChaseTTills Adverse Trend:
None 33 l
+ Equipment Forced Outage Rdef1,000 Critical Hrs. (12-Month Interval) 9
-e-1994 & 1996 Fort Calhoun Year-End Goals (0.2)
}
0.8 -
GOOD 0.6 0.4 -
p f
o 11 0.2 ;
E E
p, g
0 0
0 g
pf 3
y g
o 32 93 94 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1996 2-Number of Equipment Forced Outages per Month 1-l l.
l f i l
1 0
Jm Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1996 EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS The equipment forced outage rate per 1,000 critical hours for the 12 months from June 1,1994, through May 31,1995, was 0.409. The year-to-date rate per 1,000 critical hours for the months from January through May 1995 was 1.369.
Unplanned energy losses for the month of May 1995 were attributable to: (1) on May 11,1995, at 1105 hrs. the Fort Calhoun Station generator and reactor were manually tripped because it was determined that component cooling water was leaking into the lube oil system of RC-3D reactor coolant pump motor; after repairs and inspections of all the RCP motors, the reactor was taken critical at 0313 on May 15,1995, and the generator was put on line at 1056 on May 15,1995; and (2) on May 24,1995, at 0029 hrs. the Fort Calhoun generator and reactor were manually tripped because of a similar leak. The reactor was brought critical at 2135 on May 28,1995, and the generator was put on-line at 0907 on May 29,1995, after replacement of all of the reactorcoolant pump lube oil cooler heat exchangers.
An equipment forced outage also occurred on February 20,1995, when the plant experienced a problem with a control element assembly motor drive and a related small leak of reactor coolant.
The 1995 Fort Calhoun year-end goal for this indicator is a maximum value of 0.20.
Data Source:
Monthly Operations Report & Plant Licensee Event Reports (LERs)
Accontability:
Chase /Jaworski Adverse Trend:
None 34
20 - - Component Categories
--+- Applicatbn Categories
--*-- Total Categories 15 J h
g 10 -
I I
I i
6-0 D93 J94 F
M A
M J
J A
S O
N D94 J95 F
M A
M95 Errorloperating Action 11.4%
M Wear Out/
Maintenance /
Action
/^
27.1%
9 5
e s
oth Percent of Total Failures Devices Engineering / Manufacturing During the Past 18 Months 4.3%
Design Defect 4.3%
4.3%
COMPONENT FAILURE ANALYSIS REPORT (CFAR)
SUMMARY
The top chart illustrates the number of compoent categories, application categories and total categories in whcih the Fort Calhoun Station has significantly higher (1.645 standard deviations) failure rates than the industry failure rates during the past 18 months (from August 1993 through January 1995). Fort Calhoun Station reported a higherfailure rate in 4 of the 87 component categories (valves, pumps, motors, etc.) during the past 18 months. The station reported a higher failure rate in 3 of the 173 applicate captegories (main steam stop valves, auxiliary / emergency feedwater pumps, control element drive motors, etc.) during the past 18 months.
The pie chart depicts the breakdown by INPO cause categories (see the " Definitions" section of this report for descriptions of these categories) for the 83 failure reports that were submitted to INPO by Fort Calhoun Station during the past 18 months. Of these, the failure cause was known for 70. The pie chart reflects known failure causes.
Data Source:
Jaworski/ Frank (Manager / Source)
Accountability:
Jaworski/ Frank Adverse Trend:
None 35
-+- Components with more than One Failure
- M-Components with more than Two Failures t
20 -
15 -
10 -
~
8 8
8 8
8
^
-4 4
5 1
1 1
1 1
1 1
1 0'
Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 REPEAT FAILURES The Repeat Failures Indicator (formerly called the " Maintenance Effectiveness perfor-mance indicator) was developed in response to guidelines set forth by the Nuclear Regu-latory Commission's Office for Analysis and Evaluation of Operational Data (NRC/AEOD).
The NRC requirement for a Maintenance Effectiveness Performance Indicator has been dropped, but station management considers it useful to continue to track repetitive com-ponent failures using the Nuclear Plant Reliability Data System (NPRDS).
This indicator shows the number of NPRDS components with more than one failure during the eighteen-month CFAR period and the number of NPRDS components with more than two failures during the eighteen-month CFAR period.
During the last eighteen reporting months, there were 3 NPRDS components with more than one failure. None of these 3 had more than two failures. The tag numbers of the l_
components with more than one failure are: AC-10C, NT-001, and RC-374. Recommen-dations and actions to correct these repeat failures are listed in the quarterly Component Failure Analysis Report.
Data Source:
Jaworski/ Frank (Manager / Source)
Accountability:
Chase j
Adverse Trend:
None 36 i
P Radioactive Waste Buried This Month (cu.ft.)
C 900 -
- Cumulative Radioactive Waste Buried
-e-1995 Fort Calhoun Goal (900 cu.ft.)
l GOOD l 300 __
700 --
600-
[500-c 3
ki 4,3 M4 -
u 300 -
200 --
Ni jf[
100 -
0 Jun Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 VOLUME OF LOW-LEVEL SOLID RADIOACTIVE WASTE This indicator shows the volume of the monthly radioactive waste buried, the cumulative annual total for radioactive waste buried, the Fort Calhoun and INPO goals, and the approximately industry upper 10%.
Cu.Ft.
j Amount of solid radwaste shipped off-site for processing during current month 0
Volume of solid radwaste buried during current month 0
Cumulative volume of solid radioactive waste buried in 199s O
Amount of solid radwaste in temporary storage 0
The 1995 Fort Calhoun goal for the volume of solid radioactive waste (buried) is 900 cubic 1
feet. The 1995 INPO industry goal is 110 cubic meters (3,884 cubic feet) per year. The industry upper ten percentile value is approximately 27.33 cubic meters (965.3 cubic feet) per year.
f
\\
Data Source:
Chase /Breuer (Manager / Source)
Accountability:
ChaseILovett Adverse Trend:
None SEP 54 37
i i
Primary system Chemistry Percent of Hours Out of 3% -
~*
U"N GOOD
--G-Fort Calhoun Goal (0.02) 2%
C
^
1%
Cycle 18 Refueling pa outage M
0%
Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 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 6 key chemistry parameters. The key pa-rameters are: lithium, dissolved oxygen, chlorides, flouride, hydrogen and syspended sol-ids.100% equates to all 6 parameters being out of limit for the month.
The Primary System Chemistry Percent of Hours Out of Specification was 1.98% for the month of May 1995 for lithium and hydrogen being higher than normal due to plant startup conditions.
The 1995 Fort Calhoun monthly goal for this indicator is a maximum of 2% hours our of limit.
c Data Source:
Smith / Spires (Manager / Source)
Accountability:
Chase / Smith Positive Trend 38
1 l
" "T
~"
1.6 -
0 12-Menth Average l GOOD {
--e-Fort Calhoun Goal (1.4)
}
)
1.5 -
I 1.4 -
0 1
1 1
i a
a i
a i
1.3 l
I l
1.2 -
l
]
\\
l 1:
i l
) 5 1.1 1
'kh a
s!
!a
!!J x
1 1
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1995 SECONDARY SYSTEM CHEMISTRY
)
Criteria for calculating the Secondary System Chemistry Performance Index (CPI) are: 1)
The plant is at greater than 30% power; and 2) the power is changing at less than 5% per day.
The CPI for May 1995 was 1.24, which is higher than usual due to plant startup condi-tions. The 12-month average CPI value was 1.07 at the end of the month.
The 1995 Fort Calhoun monthly goal for the CPI is a maximum value of 1.40.
4 Data Source:
Smith / Spires (Manager / Source)
Accountability:
Chase / Smith Positive Trend due to performance better than goal 39
)
COST L
Goal: Operate Fort Calhoun Station in a manner that cost effectively maintains nuclear generation as an economically viable contribution to OPPD's bottom line. Cost conscious-ness is exhibited at all levels of the organization.
)
40
1 4.
-e-Actuals -
-e-Budget 2.
Plan 3.75 --
3.5 --
3.25 -
z 3
4 io 2.75 -
/
s
{,
2.5 -
2.25 -
2 D91 D92 D93 D94 J95 F M
A M
J J
A S
O N D95 D96 D97 D98 D99 Months CENTS PER KILOWATT HOUR The purpose of this indicator is to quantify the economical operation of Fort Calhoun Station.
The cents per kilowatt hour indicator represents the budget and actual cents per kilowatt hour on a 12-month rolling average for the current year. The basis for the budget curve is the approved 1994 and 1995 revised budgets. The basis for the actual curve is the Finan-cial and Operating Report.
The December 31 amounts are also shown for the prior years 1992,1993 and 1994. In addition, the report shows the plan amounts for the years 1996 through 1999 for refer-ence. The basis for the dollars are the Nuclear Long Range Financial Plan and the 1995 Corporate Planning and Budget Review. The basis for the generation is provided by j
Nuclear Fuels.
The unit price (2.95 cents per kilowatt hour for April 1995) averaged lower than budget due to generation exceeding the budget.
1 Data Source:
Scofield/Jamieson (Manager / Source)
Accountability:
Scofield Positive Trend 41
E Nuclear Services Division O Production Engineering Division 5 Nuclear Operations Division B Total Nuclear g,
300 N
7se m
,a y
Jan-91 Jan-92 Jan-93 Jan-94 Apr-94 Jul-94 Oct-94 Dec-94 Mar-95 Actual Staf8ng Level (Upvated Quarterly)
STAFFING LEVEL The actual staffing levels for the three Nuclear Divisions are shown on the graph above.
The authorized staffing levels for 1995 and 1996 are:
Authorized Staffing 1995 1996 440 432 Nuclear Operations Division 181 175 Production Engineering Division 114 113 NuclearServices Division 735 720 Total 9
k Data Source:
Ponec/Kobunski Accountability:
Ponec Adverse Trend:
None SEP 24 42
-*-- Spare Parts inventory Value ($ Million) 16.8 -
16.6 -
i.
16.4 -
lo
_! 16.2 -
i t
c 16 -
- 15.8 -
g 15.6 -
t l
15.4 15.2 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 Spare Parts Inventory Value The spare parts inventory value at the Fort Calhoun Station at the end of May 1995 was reported as $15,796,306.
This month's increase is due to retums of outage materials.
O Data Source:
Steele/Huliska (Manager / Source)
Accountability:
Willrett/McCormick Adverse Trend:
None 43
1 l
DIVISION AND DEPARTMENT PERFORMANCE INDICATORS Goal: AcTtb"e high standards at Fort Calhoun Station re-sulting ie sale, reliable and cost effective power production.
44 c_--_.
Corrective Maintenance Preventive Maintenance C"""3 Non-Corrective / Plant improvements -e-Fort Calhoun Goal 800,
"AZ.
Tai g
g 700 82s 5
5 A
E "ff k
681 5
600 565
?
A if R
c
=
5 a
y 0
O Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 Non-Outage Maintenance Work Order Backlog E MWos Which Exceed Maintenance Completion Goals O Total MWos 600 500 400 -
300 -
200 212 eo s.v.
'" te s. v.
-+
m e.v.
35 i
0-1 I
0 Priority 1 Priority 2 Priority 3 Priority 4 Priority 5 Priority 6 Non-Outage Maintenance Work Order Backlog MAINTENANCE WORKLOAD BACKLOGS This indicator shows the backlog of non-outage Maintenance Work Orders remaining open at the end of the reporting month. It also includes a breakdown by maintenance classifica-tion and priority. The 1995 goal for this indicator is 400 non-outage corrective mainte-nance MWOs. To ensure that the MWO backlog is worked in a timely manner, non-outage maintenance completion goals have been established as follows:
Goal Priority 1 Emergency N/A Priority 2 Immediate Action 2 days Priority 3 Operations Concern 14 days Priority 4 Essential Corrective 90 days Priority 5 Non-Essential Corrective 180 days Priority 6 Non-Corrective / Plant improvements N/A L
Improvements in the maintenance planning and scheduling process will allow more timely responses to maintenance work requests. Implementation is scheduled for 5/1/95.
Data Source:
Chase /Schmitz (Manager / Source)
Accountability:
Chase /Faulhaber Adverse Trend SEP 36 45 i
l
100 % -
Ratio of Preventive to Total Maintenance 90 %
80%
70%
60% -
50%
40 %
30% -
20 %
10%
0% --
i I
i i
I i
i i
Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 2%
m Preventive Maintenance items Overdue
--e-Fort calhoun Goal 1%
0%
i -
1 i-t I
i i-l-
t i
i i
Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 RATIO OF PREVENTIVE TO TOTAL MAINTENANCE &
PREVENTIVE MAINTENANCE ITEMS OVERDUE The top graph shows the ratio of completed non-outage preventive maintenance to total completed non-outage maintenance. The ratio was 61.92% for the month of May 1995.
The lower graph shows the percentage of scheduled preventive maintenance items for May that are overdue. During May 1995,701 PM items were completed. Eleven (11) of these PM items (1.6% of the total) were not completed within the allowable grace period or administratively closed.
The 1995 Fort Calhoun monthly goal for the percentage of preventive maintenance items overdue is a maximum of 0.5%.
Accountability:
Chase /Faulhaber Data Source:
Chase /Schmitz/Meistad (Manager / Sources)
Adverse Trend:
None SEP 41 46
6% -_
Rework as identified by Craft s.9%
- a
-o--
Fort Calhoun Goal (<3%)
5% -
4.7%
b R
4 3"
4%
g 3.3%
Y 3% -
0
^
3 l
g,yg 7
r p
1.9%
l o
g*" o* o o
7
'-~ '
0%
' ^
-+
Oct-94 Nov-94 Dec-94 Jan-95 Feb-95 Mar-95 Apr-95 May-95 l
PERCENTAGE OF TOTAL MWOs COMPLETED PER MONTH IDENTIFIED AS REWORK This graph indicates the percentage of total MWOs completed per month identified as rework. Rework activities are identified by maintenance planning and craft.
This indicator is calculated from the 15th to the 15th of each month due to delay in closing open MWO's at the end of each month.
The Fort Calhoun monthly goal for this indicator is <3%.
Data Source:
Faulhaber/Schmitz (Manager / Source)
Accountability:
Chase /Faulhaber Adverse Trend:
None 47 i
0.45 M Maintenance Overtime j
GOOD i
--M-12-Month Average Maintenance Overtime 0.4 -
y O
Fort Calhoun "On-Line" Goal (10%)
0.35 -
I*;)
0.3 0.25 -
0.2 -
i 0.15 -
0.1 -
c'
^
IE!
0.05 -
i p
0 l
Jun Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May i
1994 1995 MAINTENANCE OVERTIME The Maintenance Overtime Indicator monitors the ability to perform the desired mainte-nance activities with the allotted resources.
The percent of overtime hours with respect to normal hours was reported as 18% for the month of May 1995. This was due to the 1995 refueling outage and is within acceptable limits. The 12-month average percentage of overtime hours with respect to normal hours was reported as 11.4% at the end of the month.
The 1995 Fort Calhoun monthly "on-line" goal for this indicator is a maximum value of 10%.
a Data Source:
Chase /Schmitz (Manager / Source)
Accountability:
Chase /Faulhaber Adverse Trend:
None 48 l
l l
1 l
I O Open irs Related to the Use of Procedures (Maintenance) 3, G Closed irs Ralated to the Use of Procedures (Maintenance) l E Pree.edural Noncompliance irs (Maintenance) 2 1
111 1
1-i i
=
000 000 000 e
600 000 000 o j o oc 000 000 0
=,
Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)
This indicator shows the number of open Maintenance Incident Reports (irs) that are related to the use of procedures, the number of closed irs that are related to the use of procedures, and the number of open and closed irs that received procedural noncompli-ance cause codes for each of the last twelve months.
There were no procedural noncompliance incidents for maintenance reported for the month of May 1995. The procedure for reporting of this information and data is being investi-gated. Any changes or revisions will be reported in the June 1995 report.
Data Source:
Chase (Manager)
Accountability:
Chase / Conner Adverse Trend:
None f
l 49
IEllllE Completed Scheduled Activities (All Crafts)
IE3 Number of Emergent MWos Completed
- 120 g
O Fort Calhoun Goal (80%)
j 90% -
102 80% -
C f
g
]
70% -
l
_ y f
60% -
y a
s
/
j
-- 60 3:a 2
50 %
63
'g 1
l j
2 l
~
I i
E 3
40% -
S fg 30% -
L, 4
4o h 3
g 20% -
- 20 O
N
~
S 10%-
j 0%
~
0 February '95 March '95 April '95 May '95
(*% Completed Scheduled Activities Not Available)
PERCENT OF COMPLETED MAINTENANCE ACTIVIYlES (ALL MAINTENANCE CRAFTS)
This indicator shows the percent of the number of completed scheduled maintenance activities as compared to the number of scheduled maintenance activities conceming all Maintenance Crafts. Maintenance activities include MWRs, MWOs, STs, PMOs, calibra-tions, and miscellaneous maintenance activities. The number of emergent MWOs com-pleted for the month is also shown.
The data for this indicator is not available due to software changes required for implemen-tation of the Integrated Plant Schedule.
The 1995 Fort Calhoun monthly goal for completed scheduled maintenance activities is 80%.
O Data Source:
Chase /Schmitz (Manager / Source)
Accountability:
Chase /Faulhaber Adverse Trend:
None SEP 33 50
i-t M % of Hours the in-Line Chemistry Instruments are Inoperable
--e-1995 Fort Calhoun Goal (10%)
10% -
c
=
=
9% -
8% ~
7 M-a 8% -
t s?T h,f kb 5% -
+.
%l h
h@ h 2
4% -
Y M
sj
{[!
Ifs s
3% -
25 -
?k k
h4 b$
R 0%
I Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 IN-LINE CHEMISTRY INSTRUMENTS OUT-OF-SERVICE This indicator shows the percentage of hours the in-line chemistry system instruments are inoper-able forthe reporting month. The chemistry systems involved in this indicatorinclude the Second-ary System and the Post Accident Sampling System (PASS).
At the end of May 1995, the percentage of hours the in-line chemistry system instruments were inoperable was 5.78%.
The entire instrument channel is considered inoperative if: 1) the instrument is inoperative,2) the 1
chart recorder associated with the instrument is inoperative, or 3) the alarm function associated with the instrument is inoperative, if any of the functions listed above are not operational, then the instrument is not performing its intended function.
]
The 1995 Fort Calhoun monthly goal for this indicator is a maximum of 10% in-line chemistry instruments inoperable. 5 out-of-service chemistry instruments make up 10% of all the chemistry instruments that are counted for this indicator, b
i
?
Data Source:
Chase /Reneaud (Manager / Source)
Accountability:
Chase /Jaworski Pocitive Trend due to performance better than goal 51
m Waste Produced Each Month (Kilograms)
+ Monthly Average Weste Produced During the last 12 Months -
o un Monthly Average Goal (150 kilograms) 1000:"
X X
X X
X X
X X
X x
x 800 -
- 600 -
E52 8-g 200 -c
=
=
=
=
=
=
=
=
a NIS
~
^
T mim 1
Jun Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 HAZARDOUS WASTE PRODUCED This indicator shows the total amount of hazardous waste produced by the Fort Calhoun Station each month, the monthly average goal and the monthly average total for hazard-ous wast produced during the last 12 months. This hazardous waste consists of non-halogenated hazardous waste, halogenated hazardous waste, and other hazardous waste produced.
During the month of May 1995,0.0 kilograms of non-halogenated,0.0 kilograms of halo-genated and 0.0 kilograms of other hazardous waste was produced. The total hazardous waste produced during the last 12 months is 54.51 kilograms.
Hazardous waste is counted based upon a full drum of waste.
The 1995 Fort Calhoun monthly average goal for hazardous waste produced is a maxi-mum of 150 kilograms.
h.'
Data Source:
Chase /Carlson (Manager / Source)
Accountability:
Chase / Smith PositiveTrend I
f 52 l
l 1
l-IEEE Contaminated Radiation controlled Area 15%.
-e-Fort Calhoun Goal V
12% -
c C
c C
o Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 CONTAMINATED RADIATION CONTROLLED AREA This indicator shows the percentage of the RCA that is contaminated based on the total square footage. The 1995 monthly non-outage goal is a maximum of 9.5% contaminated RCA.
At the end of May 1995, the percentage of the total square footage of the RCA that was contaminated was 9.4%.
l
?
t Data Source:
Chase /Gundal(Manager / Source)
Accountability:
Chase /Lovett Positive Trend SEP 54 53
l
+ Identified PRWPs (Year to Date) l GOOD l
+ 1995 Fort Calhoun Goal (<20) f 20 :
O e 18 -
16 -
13 n.14 12 13 12 -
g io --
Ps 3g6 "4--
- n. 2 0
Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec 1994 1995 RADIOLOGICAL WORK PRACTICES PROGRAM The Radiological Work Practices Program Indicator shows the number of Poor Radiologi-cal Work Practices (PRWPs) which were identified during the reporting month.
The number of PRWPs which are identified each month should indirectly provide a means to qualitatively assess supervisor accountability for their workers' radiological performance.
During the month of May 1995, there was O PRWPs identified.
There have have 13 PRWPs in 1995.
The 1995 year-end goal for PRWPs is a maximum of 20.
6 s
r Data Source:
Chase /Little (Manager / Source)
Accountability:
Chase /Lovett Adverse Trend:
None SEP 52 54 t
O Documents Scheduled for Review 350 -
l
~
B Documents Reviewed l
B Documents Overdue l
300 -
. 250 -
I 200 -
i j
r 150 -
100 -
Jun Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 1
DOCUMENT REVIEW l
l This indicator shows the number of completed, scheduled, and overdue (greater than 6 months past the scheduled due date) biennial reviews for the reporting month. These document reviews are performed in-house and include Special Procedures, the Site Se-curity Plan, Maintenance Procedures, Preventive Maintenance Procedures, and the Op-erating Manual.
During May 1995, there were 136 document reviews scheduled, while 57 reviews were l
completed. At the end of the month, there were 3 document reviews more than 6 months
~
overdue. There were 10 new documents initiated during May.
i 1
1 l
Data Source:
Chase /Plath l
Accountability:
Chase /Jaworski Adverse Trend:
None l
\\
55
)
o" System Failures l GOOD l 50 -
lV 4, -
37 4
30 -
as 33 n
go 21 32 20 -
is g
- eg g
10 -
'b si W
Eil.3 M
h$
6 M
Jun Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 l
16 Non-System Failures is GOOD]
14 -
1 12
{
10 -
5 6-s a
4 4
y g q 4
3 3
- I m,
Mi p
s 0
Jun Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 LOGGABLE/ REPORTABLE INCIDENTS (SECURITY)
The Loggable/ Reportable incidents (Security) Indicator is depicted in two separate charts.
The first chart shows the total number of loggable/ reportable incidents concerning system failures which occurred during the reporting month. The second chart depicts the total number of loggable/ reportable incidents non-system failures conceming Security Badges, Access Control and Authorization, Security Force Error, and Unsecured Doors.
During the month of May 1995, there were 24 loggable/ reportable incidents identified compared to 26 for the previous month. System failures accounted for 22 (92%) of the loggable/ reportable incidents. A single microwave zone contributed to 5 of the loggable/
reportable system failures. A lost / unattended security badge and an unsecure vital area i
door, both human error incidents, were the two non-system failures identified during the reporting period.
Data Source:
Sefick/Woerner(Manager / Source)
Accountability:
Sefick Adverse Trend:
None SEP 58 58
Temporary Modifications >1. cycle old (RFO required for removal)
Temporary Modifications >6 months old (Removable on-line)
-e-Fort Calhoun Goal for Temporary Modifications > 1-cycle old
--M - Fort Calhoun Goal for Temporary Modifications > 6 months old O
P February *05 March '95 April '95 M a y '95 TEMPORARY MODIFICATIONS This indicator provides information on the number of temporary modifications greater than one fuel cycle old requiring a refueling outage (RFO) for removal and the number of tem-porary modifications removable on-line that are greater than six months old. The 1995 Fort Calhoun monthly goals for this indicator are zero. However, one temporary modifica-tion (BAST level indication) has been approved by management to exceed these goals due to cost effectiveness considerations (reference PED-STE-94-042).
There is currently 1 temporary modification that is greater than one-fuel cycle old requiring a refueling outage to remove: RC-3D cover gasket pressure indicator, which is awaiting completion of MWO 941450, which is scheduled for a future refueling outage whenever cover gaskets are replaced. In addition, at the end of May 1995, there were 4 temporary modifications installed that were greate. than six months old that can be removed on-line.
These were: 1) Local indication for BAST CH-11 A and CH-11B, in which Operations is reviewing a draft FLC. After review, Licensing is to issue an FLC, and the NRC is to approve; 2) Control system for intensifier on HCV-2987, which is awaiting completion of ECN 94-280, scheduled for completion as 1995 on-line 9/95; 3) brace to IA header "T" to water plant, which is awaiting completion of ECN 94-482, scheduled for issue from DEN-Mechanical 8/25/95; and 4) braces on main instrument air header, which is awaiting comple-tion of ECN 94-482, scheduled for issue from DEN-Mechanical 8/25/95.
At the end of May 1995, there was a total of 15 TMs installed in the Fort Calhoun Station.
?
5 of the 15 installed TMs require an outage for removal and 10 are removable on-line. In 1995, a total of 15 temporary modifications have been installed.
Data Source:
Jaworski/Tumer(Manager / Source)
Accountability:
Jaworski/Gorence Trend:
Needs increased Management Attention SEP 62 & 71 57
Total Modification Packages Open 127
+ f ort Calhoun Year-End Goal 120 y
100 g
100 -
2 so l h l l lll l I !
~
'92
'93
'94 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1996 OUTSTANDING MODIFICATIONS This indicator shows the total number of outstanding modifications (excludina outstandina modifications which are proposed to be cancelled).
Cateaory Reportino Month Form FC-1133 Backlog /In Progress O
Mod. Requests Being Reviewed 4
Design Engr. Backlog /in Progress 31 Construction Backlog /in Progress 40 Design Engr. Update Backlog /in Progress
_3 Total =
78 At the end of May 1995,9 additional modification requests had been issued this year and 3 modification requests had been cancelled. The Nuclear Projects Review Cor. mittee (NPRC) had completed 15 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) had completed 4 backlog modification request reviews this year.
- A review of the reports used to determine the total number of outstanding modifications and their various stages of accomplishment was undertaken at the request of the Nuclear Planning Department. The results of the review determined that the reports were not providing complete / accurate data. The reports have been corrected. The revised totals beginning with the March 1995 data are reflected in the current graph.
The 1995 year-end Fort Calhoun goal for this indicator is a maximum of 50 outstanding modifications.
Data Source:
Skiles/Ronne (Manager / Source)
Scofield/Lounsberry (Manager / Source)
Accountability:
Scofield/Phelps Trend' Needs increased Management Attention 58
80 -
EARS Requiring Engineering Closeout - Not in Closeout D sE D DEN
~
~
20 -
U, UU U
0 1
Mar Apr May Mar Apr May Mar Apr May Mar Apr May 04 Months 34 Months 6-12 Months
>12 Months May 1995 Overdue EARS 100-O Engineering Response O Closecut(sE) 80 -
20 -
E Priority 0 Priority 1 Priority 2 Priority 3 Priority 4 Priority 5 Priority 6 l'
i Priority 1 & 2 C:::':1 Priority 3 Total open EARS l 150 -
100
]
[
[
3 3
E Q
50 -
0 H
May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 1994 1995 24 EARS en 97 EARS 76 EARS 73 ovenho
$N 76 ovenks RequMng Resefwed and Closomns 13.9 %
Reponses
=
e Y
NQf' j
7-Nh_
j
'E -...
__s ENGINEERING ASSISTANT REQUEST BREAKDOWN This indicator shows a breakdown of the number of EARS assigned to Design Engineer-1 ing and System Engineering. The 1995 year-end goal for this indicator is a maximum of l
140 outstanding EARS.
Total EAR breakdown is as follows:
EARS opened during the month 15 EARS closed during the month 24 Total EARS open at the end of the month 173 Data Source:
Skiles/Mikkelsen (Manager / Source) f Accountability:
Jaworski/Skiles Adverse Trend:
None SEPG2 1
59
]
)
0-3 Monthe =
DEN = 14 7 Ckeews = 136
> 0 RAenthe.
233 26 5 %
24 8%
38 1 %
t M
y
,eoeuresnent/ Cons See Engr. = tg 3 4 M onthe =
tr = 171 18%
11p ECN Status -Overall Backlog
>e D Backlogged D Received D Completed 52 o 3 na,,e.. e 36 4 %
44 2 %
2s T roo -
160-43
,1,
- 1
=
5 5
100-5 f
E 5
F-u
.i i
3 a"
=-
=
f a'
a
.o n
_ IN,, L
$1.bk,,$
. d k
84
- 30 D.c-94 Jan Feb Mar Apr May.96 Design Engineering
> 0 M oe,he 0 3 M enens =
360 64 38 g00 64 D
~ '- ' ' ~ ' -.
39 0%
140 -
h N
wo-r
,J
~
m n
5 s
1 r'..
t
=
0
-+
w o.....
s..
System Engineering ru 1
> e m-l ee 200 -
4e.%
~
~
f a
m 5
z voo.
e-
-i i
i i
1 i
F M
i i
5
--lg
=-
i >.
k
.E-
,, eg$4 so -
h,.
=
oA bYbY+ b b',~D-b
-+-
34 ;;~ -
o.C...
s.,,
Procurement / Construction u**
250 <
> g gonens.
o-3 Months e 33 60 300 -
31 6 %
44.1 %
in -
e i
=
=
w a
=
m no-t j
.l 5
l l
gl s
- ,,pk e
e.. -
Ab,,
b S,_ Eb
~
i _. N kk f
I 3,
p s.n M.,
Draftina/ Closeout 2* 8' ENGINEERING CHANGEWOTICESTATUS Data Source:
Skiles/Mikkelsen (Manager / Source)
Accountability:
Skiles/Jaworski Adverse Trend:
None SEP 62 60
t DC Type =
Prtority 5 &
Priority 1 &
72 FC Type =
6 = 125 2=109 g nu 177 f.8%
SRIType d%,
i y
306 Priority 3 &
?"
,,i ii,u "
f 55.1%
-J 4 = 320 l.
7 w
---7 57.7%
Total Open ECNs by Type (554 Total)
Total Open ECNs by Priority (554 Total) i O DEN - Clomeout or Draning Not Complete Pnorthes Priorsties i
a Maintenance / Construction / Procurement. Work Not Complete 5&6 1&2 3
O System Engineering Response, Confirmation Not Complete 25A%
16.8%
l 5 DEN. Engineering Not Complete
[
Total FC ECNs Open j
,u i s s iiii s ili"'
200 -
188 See sia 577 i
Dec44 Jan Feb Mar Apr May45 Prtorttees l
Facility Change ECNs Open 3&4 l
88.8 %
2.s 302 3o.
Priorities Pnonties reo 300 -
aos zu 5&s 1&2 M
14A%
26.9%
se
,4 250 -
d l"gk j
v 200-o iiii,1 l-l=
~
ia -
[
1a.
"s.
g,,1 g,, i Pnorthes 0-
-+--
I i
i
- A4 Dec44 Jan Feb Mar Apr May45
"'7" Substitute Replacement item ECNs Open 100 r 145 Pnortbes 140 -
113 8
8 120 -
p l
o M
s, k
j a
,0 n
$4 36 33 48 3o 30 31 0
i i
i i
i pygargges Priarteles Dec44 Jan Feb Mar Apr May45 s&s 3&4 Document Change ECNs Open so M 47 8 ENGINEERING CHANGE NOTICES OPEN Data Source:
Skiles/Mikkelsen (Manager / Source)
Accountability:
Skiles/Jaworski Adverse Trend:
None SEP 62 61
]
=
0 Administrative Control Problem 3-E Licensed Operator Error 5 Other Personnel Error 5 Maintenance Problem O Design / Construction / installation /Fabriation Problem E Equipment Failures u
1-l
+
0 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 1994 1995 LICENSEE EVENT REPORT (LER) ROOT CAUSE BREAKDOWN This indicator shows the LERs by event date broken down by Root Cause Code for each of the past twelve months from May 1,1994, through April 30,1995. To be consistent with the Preventable / Personnel Error LERs indicator, this indicator is reported by the LER event date, as opposed to the LER report date.
The cause codes are intended to identify possible programmatic deficiencies. For de-tailed descriptions of these codes, see the " Performance Indicator Definitions" section of this report.
There were no events in April 1995 that resulted in an LER. However, as discussed above, one event subsequently determined to be reportable as an LER occurred in March 1
1995.
1 Data Source:
Trausch/Cavanaugh (Manager / Source)
Accountability:
Chase Adverse Trend:
None 62 l
i D Total Requalification Training Hours O simulator Training Hours G Non-Requalification Training Hours B Number of Exam Failures 40 -
37 37 37 37 3s.5 f
35 - 32.5 L
30 M-I 25 -
20 -
37 10 14 15 -
[
12 **
11.5
.jj 10 10 -
h 7.5 l
5 l
[
j ;
I U
)
J R
!! 4.5 i
b ti 0
0 0
0 Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle 94-2 94-3 94-4 94-5 94-6*
94 7 95-1 95-2
- Note 1: The simulator was out-of-service during Cycle 94-4.
" Note 2: Includes 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of General Employee Training.
LICENSED OPERATOR REQUALIFICATION TRAINING This indicator provides information on the total number of hours of training given to each crew during each Cycle. The simulator training hours shown on the graph are a subset of the total training hours. Non-Requalification Training Hours are used for APO/EOP verification & validation, INPO Commitments, GET, Fire Brigade, Safety Meetings, and Division Manager lunches.
Exam failures are defined as failures in the written, simulator, and Job Performance Measures (JPMs) segments of the Ucensed Operator Requalification Training.
Rotation 95-2 was shortened to support the 1995 Refueling Outage. Also, the Simula-tor was out of service during this rotation for scheduled maintenance. There were no written examination failures during Rotation 95-2.
l L
Data Source:
Gasper /Guliani (Manager / Source)
Accountability:
Gasper /Guliani Adverse Trend:
None SEP 68 63 8
5 SRO Exams Administered D SRO Exams Passed D RO Exams Administered 5 RO Exams Passed 20 -
15 -
l 10 -
.E Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 LICENSE CANDIDATE EXAMS This indicator shows the number of Senior Reactor Operator (SRO) and Reactor Operator (RO) quizzes and exams taken and passed each month. These internally administered quizzes and exams are used to plot the SRO and RO candidates' monthly progress.
For the month of May 1995, no RO or SRO examinations were administered, with the exception of one remedial examination. The examinee passed his remedial examination.
Data Source:
Gasper /Guliani(Manager / Source)
I Accountability:
Gasper /Guliani Adverse Trend:
None SEP 68
)
64 i
51513 Open Cars > 6 Months Old l
C"""3 Open Signifloant CARS l GOOD l
+ Total Open Cars 80
-e-1995 Goal Y
y 40 -
30 -
20 -
is si u
u Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 EIEER Open irs >6 Months Old C Open SignificantIRs
+ tow Open irs 450 -
0
^
400 -
350
[
0~
m u.
l
[
5p b blg us u7 b
[ "I ft b l(
2 i
Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1994 1995 OPEN CORRECTIVE ACTION REPORTS AND INCIDENT REPORTS i
This indicator shows the total number of open Corrective Action Reports (CARS), CARS
>6 months old, the total number of Open irs, irs >6 months old, the number of open significant CARS and the number of open significant irs.
At the end of May 1995, there were 42 open CARS,18 of these CARS were greater than 6 months old. There were 6 Open Significant CARS at the end of the month.
Also, at the end of May 1995, there were 174 open irs.104 of these IRS were greater i
than 6 months old. There were 48 Open Significant irs at the end of the month.
f The 1995 monthly goal for the number of CARS greater than 6 months old is less than 30.
As of April 21,1995, CARS are no longer being issued. All future corrective actions will be documented on irs.
Data Source:
Orr/Gurtis (Manager / Source)
Conner /Plott Accountability:
Andrews/Phelps/Patterson Positive Trend I
65
=
Data for the 1996 Refueling Outage will not be available until the summer of 1995.
1 MWO PLANNING STATUS (CYCLE 16 REFUELING OUTAGE)
This indicator shows the total number of Maintenance Work Requests (MWRs) and Main-tenance Work Orders (MWOs) that have been approved for inclusion in the Cycle 16 Refueling Outage. This graph indicates:
- Parts Holds (Part hold removed when parts are staged and ready to use)
- Engineering Holds (Engineering hold removed when appropriate engineering paper work or support is received for the package)
- Planning Holds (Planning hold removed when planning is completed to the point l
when package is ready or other support is necessary to continue the planning I
process)
- Planning Complete (status given when only items keeping the job from being ready to work are parts or engineering support)
- Ready (status when all planning, supporting documentation, and parts are ready j
to go) f Data Source:
Chase /Schmitz Accountability:
Chase /Faulhaber Adverse Trend:
None 66
Data for Progress of Cycle 17 Outage Modification Planning will not be available until July 1,1995.
l PROGRESS OF CYCLE 17 OUTAGE MODIFICATION PLANNING I
l The data is represented with respect to the baseline schedule and the current schedule.
This information is taken from the Modification Variation Report provided by the Design l
l Engineering group.
i Data Source:
Skiles/Ronne (Manager / Source)
Accountability:
Phelps/Skiles Adverse Trend:
None SEP 31 I
67 l
4
--+-- Baseilne Schedule for PRC Approval
-e-Projected / Actual Schedule for PRC Approal Total Modification Packages (11) (1 is Close Out Only)
.::::./:^
10 Y
8--
O
$57
- [:::.
E UE u>
115 -
i
- n. <
e oQ4--
ja.
a.
E*
3--
E5 j
2--
n.
81-0 E.EEE*EEEE.EEEE*E,EEEEEE$E e
s -,
u.
n s e
- S Ns5 5S5S5S bnS S*5# 5S5S5 - - -
PROGRESS OF 1995 ON-LINE MODIFICATION PLANNING (FROZEN SCOPE OF 10 MODIFICATIONS)
This indicator shows the status of modifications approved for on-line installation during 1995. The data is represented with respect to the baseline schedule (established 1/13/
- 95) and the current schedule. This information is taken from the Modification Variation Report produced by the Design Engineering Nuclear group.
The goal for this indicator is to have all modification packages identified prior to 1/13/95 PRC approved by October 30,1995.
May 1995 Modifcations Added: 0 Deleted = 1 Mod FC94-001 was cancelled.
Data Source:
Skiles/Ronne (Manager / Source)
Accountability:
Phelps/Skiles Adverse Trend:
None SEP 31 68
e a
a a-
--..-.-- -..a.
m a
J 4
'O 1
3 I
ACTION PLANS
?
0 69 l
. -._ ~-,
r-
.---r-
=
ACTION PLANS This section lists action plans that have been developed for the performance indicators cited as Adverse Trends during the month preceding this report. Also included are Action Plans for indicators that have been cited in the preceding month's report as Needing increased Management Attention for three (3) consecutive months.
In accordance with Revision 3 of NOD-QP-37, the following performance indicators would require action plans based on three (3) consecutive months of performance cited as "Needing Increased Management Attention"-
Industrial Safety Accident Rate (page 2)
Thermal Performance (page 32)
Temporary Modifications (page 57)
Outstanding Modifications (page 58)
The action plan for Industrial Safety Accident Rate (page 2) is as follows:
REVERSING THE INDUSTRIAL SAFETY ADVERSE TREND
'
- RESTATED ACCIDENT REPORTING PROCEDURES / PROTOCOL
-Necessary because 3 Lost Times involved late reporting and delayed Physician care
- PROVIDING TREND ANALYSIS BY DEPARTMENT, TO RESPONSIBLE FIRST LINE SUPERVISORS
-Information is from documented injury reports.
-OSHALOG 200, Manager Plus will provide future information to Trend Breakdown and Cost Benefit Analysis C1
- ATTENDING EMERGENT WORK MEETINGS TO OVERSEE PRIORITY ASSIGNED TO SAFETY RELATED WORK PROJECTS
- SAFETY COMMITTEE IS ASSIGNING DEADLINES TO WORKING SAFETY SUGGESTIONS 70
ACTION PLANS (continued)
The action plan for industrial Safety Accident Rate (page 2) continues as follows:
- ERECTED A STATION INDUSTRIAL SAFETY STATUS BOARD L
- SAFET( PERFORMANCE ENHANCEMENT COMMITTEE WILL MEET DAILY UNTIL WINDOW IMPROVES
- REQUESTED AN INPO STAFF ASSISTANCE VISIT
- lNDUSTRIAL SAFETY IS ON PLANT MANAGERS PRIORITY LIST ON PLAN OF DAY The action plan for Thermal Performance (page 32) is as follows:
. Initial results from testing to verify FW flow requirements indicate biased results from plant instruments is causing the thermal performance indicator to be under-reported. Corrections to the indicator will be made before October 1,1995.
The action plan for Temporary Modifications (page 57) is as follows:
. The Temporary Modification program needs to have its program goals revised to reflect current NPRC scheduling practices. This will be completed by July 1, 1995.
Review of the Outstanding Modifications (page 58) has developed the following results:
- A review of the reports used to determine the total number of outstanding modifications and their various stages of accomplishment was undertaken. The results of the review determined that the reports were not providing complete / accurate data. The reports have been corrected. The revised totals beginning with the March 1995 data are reflected in the current data.
l 71
PERFORMANCE INDICATOR DEFINITIONS AUKKJARY FEEDWATER SYSTEM SAFETY SYSTEM CLEAN CONTROLLED AREA CONTAMWdATIONS t 1,000 PERFORMANCE DIGINTEGRATIONS/INNUTE PER PROSE AREA The sum of the known (pionned and unplanned) unevedeble The personnel contaminebon events in the cimen controNed area.
hours and the ashmetod unswetable hours for the suuulary This indicator tracks personnel performance for SEP #15 & 54.
feedseter system for the reportin0 period dMded by the ortlical hours for me reporting period muniphed by the number of trains CONTAMalATED RADIATION CONTROLLED AREA 3
in the stadliery feedwater system.
The percentage of the Redistion Controned Area, which includes
- COLLECTIVE RADIATION EXPOSURE the ausdhary budding, the redweste building, and areas of the C/RP bulkhng, that is contommated booed on the total square Colecthe raideten aposuis is the total estemel whole-body does footeps. This indicolor tracks performance for SEP #54.
received by at on-elle personnel (including contractors and victors) during a time period, es meneured by the DAK.Y TDERMAL OUTPUT thermoluminsecent dosimeter (TLD). CcNechve radiobon oposure is reported in unas of persorHom. This indicator tracks This indicator shows the daily core thermal culput as measured radiological work performance for SEP f54.
from computer point XC105 (in thermal megewetts). The 1500 MW Tech Spec Irrdt, and the unmet perhon of the 1495 MW FCS COMPOIENT FAILURE AP8ALYSIS REPORT (CFAR) delly goal for the reportng month are also shown.
SUMMARY
DIESEL GE9ERATOR RELIABILITY (25 Demands)
The summary of INPO categorise for Fort Calhoun Station with signficantly higher (1.646 standard deviations) failure roles then This indicator shows the number of fadures occumng for each the rest of the industry for an eighleerwnonth t;me period.
emergencydesel generator during the lset 25 start demands and Failures are reported es component (i.e., pumpe, motors, main the last 25 load-run demands sleem stop volves, control element motors, etc.) categones DISABLING DlJURYtILLNESS FREQUENCY RATE Fanure Cause Categones are:
(LOSS TIME ACCIDENT RATE)
Weer OutfAging. a failure thought to be the consequence of This indicator is defined as the number of accedents for aN utgity
=r=r4=r8 weer or agm0-Personnel permanently seeigned to the station, inwoMng days away tem eerk per 230,000 merWiours worked (t 00 man-years).
Manufacturing Defect - a failure attributobie to ir=riary=8=
This does not include contractor personnel. This indicator tracks 4
assembly or initial quehty of the responsible component or personnel performance for SEP #25,26 & 27.
system.
DOCUMENT REVIEW (EEmmRAL)
EngneeringiDesign a fauure attributobie to the irW=s=
design of the responelbie component or system The Documord Review Indkator shows the number of documents roweved, the number of documenes scheduisd for review, and the Other Devices. a failure attributobie to a fabure or number of document reviews that are overdue for the reportng mioopershon of another component or system, icluding month. A documeri review is connedored overdue if the review is
===ar*8ari devices not compiste within siit months of the seeigned due dele. This indecolor tracks performance for SEP #46.
Maintenance / Testing. a fanure that is a result of improper molnlenance or testing, lock of meirtenance, or personnel errors that occur during memtenance or testing actMhos EMERGENCY AC POWER SYSTEM SAFETY SYSTEM performed on the responsible component or system, including PERFORMANCE failure to follow procedures The sum of the known (planned and unpionned) uneveNeble and Errors - falures attributable to incorrect procedures that were the echmeled unevenable hours for the emergency AC power followed as written, improper installation of equipment, and system lor tw reportmg period dMded by the number of hours in poreannel errors (including fauure to follow procedures the reportng period multiphed by the number of trains in the property). Also included in this category are failures for which emergency AC power system.
.cause is unknown or cannot be assigred to any of the Procedmg cologones CENTS PER KILOWATT HOUR The purpose of this indicator is to quantify the economecal operation of Fort Calhoun Stehen. The cents per knowett hour indcolor represorts the budget and actual cents por kilowett hour on a tweMHnorth sterage for the current year. The basis for the budget cune is the approved yeerty budget. The beeis for the actuel curve is the Fmencial and Operstmg Report.
72
PERFORMANCE INDICATOR DEFINITIONS EMERGENCY Det:SEL GENERATOR UNIT RELIABILITY E) A failure to start because a porton of the starting system was disabled for test purpose, if followed by a successful This indcator shows the number of failures that were reported start with the starting system in its normal alignment.
during the last 20, 50, and 100 emergency diesel generator demands at the Fort Calhoun Statiort Also shown are tngger Each emergency generator failure that results in the generator e
values which correlate to a high level of confidence that a unit's berig decim@ operable should be counted as one demand and diesel generators have obtained a reliability of greater than or one falure. Exploratory tests dunng corrective maintenance and 5
equal to 95% when the demand failures are less than the ingger the successful test that follows repair to venfy operability should values.
not be counted as demands or failures when the EDG has not been declared operable again.
- 1) Number of Start Demands: All valid and inadvertent start demands, including all start only demands and all start EMERGENCY DIESEL GENERATOR UNRELIABILITY demands that are fokmed by load-run demands, whether by automate or manual initiation. A start only demand is a TNs indcater meestres the total unreliability of emergency diesel demaruf b whch the emergency generator is started, but no generators. In general, unreliability is the rate of unsuccessful attempt is rnade to load the generator, operations (starts or load-runs) to the number of valid demands.
Total unreliability is a combinaten of start unreliability and load-
- 2) Number of Start Failures: Any failure within the run unreliability.
emergency generator system that prevents the generator from schwung specified frequency and voltage is classified ENGINEERING ASSISTANCE REQUEST (EAR) as a void start falure. This includes any condition identified BREAKDOWN in the course of rnaintenance inspectons (with the emergency generator in standby mode) that definitely would This indicator shows a breakdown, by age and priority of the have resulted in a start failure if a demand had occurred.
EAR, of the number of EARS assigned to Design Engineenng Nuclear and System Engineering. This andcator tracks
- 3) Number of Load-Run Demands: For a valid load-run performance for SEP #62.
demand to be counted the load-run attempt must meet one or rnore of the following critena:
ENGINEERING CHANGE NOTICE (ECN) STATUS A) A load-run of any duration that results from a real The number of ECNs that were opened, ECNs that were automate or manualinitiation.
completed, and open backlog ECNs awaiting completion by DEN for the reporting month. This indcator tracks performance for B) A load-run test to satisfy the plants load and duraten SEP #62.
as stated in each test's spectfcations.
ENGINEERING CHANGE NOTICES OPEN C) Other special tests in which the emergency generator is expected to be operated for at least one hour while This indcator breaks down the number of Engineenng Change loaded with at least 50% of its desgn load.
Nobces (ECNs) that are assigned to Design Engineenng Nuclear (DEN), System Engineering, and Maintenance. The graphs
- 4) Number of Load-Run Failures: A load-run failure should provide data on ECN Facility Changes open, ECN Substitute be counted for any reason in whch the emergency Replacement items open, and ECN Document Changes open.
generator does not pick up load and run as predcted.
This indcator tracks performance for SEP #62.
Failures are counted dunng any valid load-run demands.
EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL
- 5) Exceptions: Unsuccessful attempts to start or load <un HOURS should not be counted as valid demands or failures when they can be attributed to any of the following Equipmert forced outages per 1,000 critcal hours is the inverse of the mean time between forced outages caused by equipment A) Spunous inps that would be bypassed in the event of failures. The mean time is equal to the number of hours the an emergency.
rnetor is crtical in a penod (1,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />) divided by the number of forced outages caused by equipment failures in that perkx1 B) Malfmeban of equipmert that is not required dunng an emergency.
EQUIVALENT AVAILABILITY FACTOR C) Intentonal termination of a test because of abnormal This indcator is defined as the ratio of gross available genersten condtions that would not have resulted in major diesel to gross maxrnum generaten, expressed as a percentage.
generator damage or repair.
Available generston in the energy that can be produced if the unit is operated at the maximum power level permitted by equipment D) Malfuncbons or operating errors which would not have and regulatory imtabens. Maximum generation is the energy that prevented the emergency generator from being csn be produced by a unit in a given penod if operated restarted and brought to load within a few minutes.
continuously at maximum capacity.
1 73 l
l 1
PERFORMANCE INDICATOR DEFINITIONS FORCED OUTAGE RATE INDUSTRIAL SAFETY ACCIDENT RATE -INPO This indicator is defined as the percentage of time that the unit Thisindicator is defined as the number of accidents per 200,000 was unavailable due to forced events compared to the time man hours worked for all utility personnel permanently assagned planned for electncal genershon. Forced events are failures or to the station that result in any of the following other unplanned conddions that require removing the unit from sonnee before the end of the next weekend Forced events
- 1) One or more days of restrided work (excluding the day of include start-up failures and events iniheted while the unit is in the accident);
d reserve shutdown (i e., the urut is available but not in service).
- 2) One or more days away from work (excludeng the day of the FUEL RELIABILITY INDICATOR accadent); and This in&stor is defined as the steady-state pnmary cooient 3-131
- 3) Fatelltees.
activity, corrected for the tramp urarvum contribuhon and normanned to a common punficehon rate. Tramp uraruum is fuel Contractor personnel are not included for this indicator, which has been W on reactor core intemels from previous defocuve fust or is present on the surface of fuel elements from IN11NE CHEMISTRY INSTRUMENTS OUT OF SERVICE
~'
the manufactunng process Steady state is defined as continuous operation for at leest three days at a power loved that Total number of in-hne chemistry instruments that are out-of-does not wry more then + or -5%. Plants should collect date for servios in the Secondary Syelem and the Post Accident Semphng the hecolor at a power level above 85%, when panam Plants System (PASS).
that did not operate at steady-state power above 85% should collect date for this indicator at the highest steady-state power LICENSE CANDIDATE EXAMS level attained during the month.
This in&stor shows the number of SRO and/or RO quizzes and The denety conochon factor is the robo of the specific volume of exams that are admnetered and poseed each month. This coolant at the RCS operating temperature (540 degrees F., Vf =
indicator tracks tranng performance for SEP#68.
0.02146) divided by the specific volume of coolant at normal inklown temperature (120* F at outlet of the letdown cooling heat LICENSED OPERATOR REQUALIFICATION TRAINING ene&enger. Vf = 0.016204), which results in a density correchon factor for FCS equelto 1.32.
The total number of hours of trasning given to each crew during each cycle. Also petuded are the simulator training hours (which GROSS HEAT RATE are a subset of the total training hours), the number of non-REQUAUFICATION training hours and the number of exam Gross heat rate is defined as the ratio of total thermal energy in failures. TNs indicator tracks training perforrnance for SEP #68.
Britesh Thermal Urvts (BTU) produced by the reactor to the total gross electncal energy produced by the generator in lolowett-hours (KWH),
HAZARDOUS WASTE PRODUCED The total amount (in Kilograms) of non-helogenated hazardous weste, heiogeneled hazardous weste, and other hazardous weste produced by FCS each month.
HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE The sum of the known (planned and unplanned) unavailable hours and the eshmeted unevailable hours for the high pressure safety injection system for the reportsng period devided by the crtical hours for the reporting penod muluphed by the number of traens in the high pressure safety infechon system.
74
PERFORMANCE INDICATOR DEFINITIONS LICENSEE EVENT REPORT (LER) ROOT CAUSE Preventive Actions taken to maintain a piece of equipment BREAKDOWN w thin design operating conditions, prevent equipment failure, and entend its lie and are performed pnor to equipment failure.
This indicator shows the number and root cause code for Licensee Event Reports. The root cause codes are as fonows:
Non Corrective / Plant improvements Maintenance e
actMties performed to implement station improvements or to
- 1) Administrative Control Problem - Management and repair non-plant equipment.
supervisory defciencies that affect piant programs or actrvtes (Le., poor planning, breakdown or lack of adequate Maintenance Work Priorities are defined as:
management or supervisory control, incorrect procedures, etc).
Emergency Conditions which significantly degrade station safety or availabihty.
- 2) Licensed Operator Error - This cause code captures errors of omamonkernmiseen by beensed reactor operators immediate Action - Equipment defcsencies which dunng plant actMbes.
signifcantly degrade station relability. Potential for urut shutdown or power reduction.
- 3) Other Personnel Error - Errors of omission / commission committed by norFicensed personnel involved in plant Operations Concern - Equipment defciencies which hinder actMbes.
station operation.
- 4) Maintenanos Problem The intent of this cause code is to Essential - Routtne corrective maintenance on essental capture the full range of problems which can be attributed stabon systems and equipment.
in any way to programmabc defeiences in the maintenance functional organization. ActMties included in the category Non-Essential - Routine corrective maintenance on non-are maintenance, testing, surveillance, cahbration and essental station systems and equipment.
radiation protection.
Plant improvement Norworrective maintenance and piant
- 5) Dee6gn/ConstructiorWinstallation/ Fabrication Problem -
improvements.
l This cause code covers a fun range of programmatic deficiencee in the areas of design, construction, installation, This indcator tracks maintenance performance for SEP #36.
and tabncation (le., loss of control power due to underrated fuse, equiprnent not quahfied for the environment, etc.).
MAXIMUM IND!VIDUAL RADIATION EXPOSURE
- 6) Equipment Failures (Electronic Piece-Parts or The total maximum amount of radiation received by an indMduni Environmental-Related Failures) - This code is used for person wortang at FCS on a monthly, quarterly, and annual basis.
spunous failures of electronic piece-parts and failures due to meteorologeal conditions such as lightning, ice, high MWO PLANNING STATUS (CYCLE 18 REFUELING winds, etc. Generally, it includes spunous or one-hme OUTAGE) faknes. Electric components included in this category are circuit cards, rectifers, bistables, fuses, capacitors, diodes, The total number of Maintenance Work Orders that have been resistors, etc.
approved for inclusion in the Cycle 16 Refueling Outage and the number that are ready to work (parts staged, planning complete, LOGGABLE/ REPORTABLE INCIDENTS (SECURITY) and an other paperwork ready for feld use). Also included is the number of MWOs that have been engineenng holds (ECNs, The total number of securtty incidents for the reporting month procedures and other miscellaneous engineering holds), parts depicted in two graphs. This indcator tracks security hold, (parts staged, not yet inspected, parts not yet arrived) and performance for SEP #58.
planning hold (job scope not yet completed). Maintenance Work Requests (MWRs) are also shown that have been identifed for MAINTENANCE OVERTIME the Cycle 16 Refuehng Outage and have not yet been converted to M W Os.
The percent of overtime hours compared to normal hours for maritenance. The ricludes OPPD personriel as well as contract personnel.
MAINTENANCE WORKLOAD BACKLOGS 1
)
This indcator shows the backlog of non-outage Maintenance Work Orders remdining open Si the end of the reporting month.
i I
Maintenance clas sifcations are defined as fonows:
Correctin Repair and restorabon of equipment or corway #,,that have failed or are malfunctioning and are not perforrring their intended function.
75
.~
PERFORMANCE INDICATOR DEFINITIONS IN OF CONTROL ROOM EQUIPMENT DEFICENCIES
- 2) ModAcation Requests Being Reviewed. This category includes A control room equipment donciency (CRD) is donned as any component which is operated or controlled from the Control A) Mod Gcation Requests that are not yet rowowed
.l Room, proddes indremon or eierm to the Control Room, provides testing e=PahWhen from the Control Room, provides automehc B) Modficalion Requests being rowowed by the Nuclear actions from or to the Control Room, or prowdes a poselve Projects Review Committee (NPRC) 6 function for the Control Room and has been identshed as deAclart,i.e., does not perform under ad condmons as designed C) Modfcation Requests being reviewed by the Nuclear e
The deAnton also apphes to the Allemate Shutdown Peneis Al-Projects Committee (NPC).
17g, Al-185, and Al-212.
These Modincehon Requests may be reviewed several times A plot component which is dancient or inoperable is considered betare they are approved for accomplishment or canceled Some an " Operator Work Around (OWA) llem" If some other schon is of these Modincehon Requests are retumed to Engmeonng for.
required by an operator to -,,,,.. for the condition of the more kiformehon, some approved for evaluation, some approved component Some exemples of OWAs are:
for study, and some approved for planrung Once pionning is completed and the scope of the work is cleerty defined, those
- 1) The control room level indcolor does not work but a local Mn,ese=han Requests may be approved for accomphehment with eight glees can be reed by en Operator out in the plent; a year aampiad for construchon or they may be conceled AN of these different phemes requwe review.
- 2) A deficient pump caimot be repared because replacement
?
i parts require a long ised time for pw -
"2 ri, thus
- 3) Design Engineering Backlogan Progrees Nuclear requmns the redundant pump to en operated conhnuously; Plannmg has asegned a year in which construchon wW be completed and design work may be in progrees
- 3) Special actions are required by an Operator haea"=a of equipment design probisms These schons may be
- 4) Construction Bacidog4n Progress. The Construchon l
described in Operabans Memorandums, Operator Notes, or Paciage has been lesund or construchon has begun but the may requre changes to Operahng Procedures; modificehon has not been =ecaf*=rt by the System Acceptance Commmee (SAC).
- 4) DeAment plant equipment that is required to be used during
[
Emergency Operstang Procedures or Abnormed Operating
- 5) Daeign Engineering Update Backlogan Progress. PED 4
Procedures, has recorved the Modificehon Completion Report but the
- 5) System indicahon that provides critical informehon during I
normalor abnormelopershons The above menhoned outetending modificahons do not include l
madrrcetens which are proposed for canceNeten NUISER OF MISSED SURVEILLANCE TESTS RESULTING f
IN LICENSEE EVENT REPORTS OVERALL PROJECT STATUS (REFUELING OUTAGE)
The number of Surveillance Tests (STs) that result in Licensee This indestor shows the status of the pregocts which are in the l
Event Reports (LERs) dunng the reporting month. This ind6cator scope of the Refuelmg Outage j
tracks missed STs for SEP 900 & 61, PERCENTAGE OF TOTAL MWOs COMPLETED PER MONTH OPEN CORRECTIVE ACTION REPORTS & INCIDENT IDENTIFIED AS REWORK REPORTS The percenlege of total MWOs compieled per rnonth identined as This Inckstor depisye he total number of open Correcbve Acton rework. Rework ochvtes are identried by maintenance plannmg Reports (CARS), the number of CARS that are older then six and craft Rework is: Any additional work requwed to correct morths and the number of eigrvficant CARS. Also deployed are dotcances decovered during a failed Post Maintenance Test to the number of open incident Reports (irs), the number of irs ensure the component / system posses anh==T==nt Post that are grooter then six months old and the number of open Memtenance Test agnifcant irs.
PERCENT OF COMPLETED SCHEDULED MAINTENANCE j
OUTSTANDING MODFICATIONS ACTMTIES 1
The number of Modukahon Recpmels (MRs) in any state between The percent of the number of completed memtenance actMhes y
heissuance of a Modificaten Number and the complebon of the as compared to the number of scheduled momeenance actMiles drewmg update.
each month. TNs percentage is shown for aH memtenance crafts. Also shown are the number of cmorgent MWOs.
- 1) Form FC.1133 Backlog 4n Progrees This number Maintenance actMtes include MWRs, MWOs, STs, PMOs, represents modifcabon requests that have not been plant calibrations, and other mecolleneous actMtes. This indicator approved during the reportmg month.
tracks Memtenance performance for SEP #33.
76 m...
PERFORMANCE INDICATOR DEFINITIONS PREVENTAsLEeERSONNEL ERROR LERe maruru naras WORK PRACTICES PROGRAM TNs indcator is a tw==hhan of LERs. For purposes of LER The number of identmed poor radiciogme! work prochoes event closemcohon, e *Proventable LER"is donned as:
(PRWPs) for the reportmg month. TNs indmetor tracks radiologmal work performance for SEP #52.
An event for which the root cause is personnel ermr (i.e.,
9 Inoppropriate schon ty one or more indMduals), inadequate RADIO OF PREVENTIVE TO TOTAL MAINTENANCE &
admmiserative cordrois, e design construchon, tres=hnn, PREVENTlWE MAINTENANCE ITEMS OVERDUE o
inm fatwtcehon problem (irwoMng work completed by or supervised by OPPD personnoi) or a maintenance problem The rollo of proverthe mortenance (includmg survoitence testing (attributed to irW* or improper uphosphopelt of plant and cohbration procedures) to the sum of nonautoge correchve i
equipmert). Also, the cause of the event must have occurred maintenance and preventive mentononce completed over the vdihin appresdmetely two years of the " Event Dele" specmed in reporting penod. The raho, expressed as a percentage, is the LER (e.g., en ewont for wNch the cause is attributed to a rabh bened on men-hours. Also deployed are the percent problem with the artgined design of the plant would not be of preventive memtenance items in the month that were not considered preventatdo).
completed or admmetratruely closed by the scheduled date plus a grace pertod squel to 25% of the scheduled intonel TNs For purposes of LER event closelficehon, a " Personnel Error" indestor tracks preventive memtenance actMhes for SEP #41.
LER is defined as follows:
RECORDAsLE INJURYALLNESS CASES FREQUENCY An ownt for which the root cause is inappropnote action on the RATE port of one or more indMduals (as opposed to being attributed to e department or a general group). Also, the inappropnele The number of injunes requring more then normed first aid por action must have occurred within approsdmetely two years of 200.000 men-hours worked TNs indcator trends personnel the " Event Date" specmed in the LER.
performance for SEP #15,25 and 26.
l AdcAlorusy, each event ciesesfied as e " Personnel Error" should REPEAT FAILURES siso be closamed as "Proventable" TNs ir*=hw trends personnel performance for SEP llem #15.
The number of Nuclear Plant Rehobety Data System (NPRDS) components with more then one failure and the number of PRIMARY SYSTEM CHEMISTRY % OF HOURS OUT OF NPRDS components wth more tien two failures for the eighteen.
LleMT month CFAR period.
The percent of hours out of limit are for six primary chemetry SAFETY SYSTEM FAILURES l
parameters dMded by the total number of hours poseitse for the month. The key parameters used are: LitNum, Chionde, Safety system fadures are any events or condshons that could Hydrogen, Desolved Oxygen, Fluoride and Suspended Solids.
prevent the fulfillment of the oefety functens of structures or EPRI hmits are used.
systems. If a system consists of muniple redundant subsystems or trains, failure of ou trains constitutes a safety system feMure.
PROCEDURAL NONCOMPLIANCE INCIDENTS Failure of one of two or more trains is not counted as e oefety (MAINTENANCE) system failure. The definihon for the indicator pareuels NRC reporhng requremeras in 10 CFR 50.72 and 10 CFR 50.73. The The number of identified incedents concommg montenance fotowng is a tiet of the major safety systems, sut>eystems, and procedureiprotdens, the number of closed irs reisted to the use componards monitored for this indicator-of procedures (includes the number of closed irs caused by procedural nancomphence), and the number of ciceed procedural Accident Monitoring instrumentation, Auudiery (and noncomptance lRs. TNs kutcolor trende personnel performance Emergency) Feedwater System, Corwada Gas Contml, for SEP 815,41 and 44.
Component Cochng Water System, Contamment and l
Cortenmere sectshon, Contamment Coceent Systems, Control PROGRESS OF CYCLE 18 OUTAGE MODIFICATION Room Emergency Ventilshon System Emergency Core PLANNING FROZEN SCOPE OF 18 MODIFICATIONS)
Coolrg Sptoms Engineered Safety Fewtures instrumentshon, l
Essenhal Compressed Air Systems, Essenhol or Emergency TNs indicator shows the status of modtroshons approved for Service Water, Fire Detecamn or Suppreceion Systems, compleben during the Refusing Ouunge looishon Condeneer, Law Temperature Overpreneure j
Protection, Main Steam Line leoishon Velves, Onelle l
PftOGRESS OF 1996 ON LINE MODIFICATION PUUdNING Emergency AC & DC Power w0estribuhon, Redelion (FROZEN SCOPE OF 12 MODIFICATIONS)
Montarmg instrumentshon, Reactor Coolant System, Reactor Core leolabon Cochng System, Reactor Trip System and This indcator shows the status of modrficebens approved for Instrumentshon, Recwcuishon Pump Trip Actuohon complebon during 1995.
Instrumentshon, Reesdual Heat Removal Systems, Safety Velves, Spent Fuel Syelems, Standby Liquid Control System and Uthmete Heat Smk.
77
=
PERFORMANCE INDICATOR DEFINITIONS SECONDARY SYSTEM CIEMISTRY PERFORMANCE STAFFING LEVEL INDEX -
The actual atomng level and the authorimod elefRng level for the The Chenesty Portamience Indoc (CPI) is a
- man bened on Nuclear Opershons Duelon The Produchon Eigmeenng tte concertrahan of key impurthes in the secondary side of the DMemn,and the Nucieur Services DMeion. This indcator tracks 8
plant. These hay impurmes are the moet ilhely cause of performance for SEP #24.
detenorabon of the stoom generators. Crttorie for calculatmg the CPI are:
STATION IET GEIERATION
- 1) The plant is at greater then 30 percent power; and The not genershon (sum) produced by the FCS dunng the reportmg month.
- 2) the power is changmg less then 5% per day.
TEMPORARY MOOlFICATIONS The CPI is *= tad uomo the fonowing equehon The number - of temporary mechancel 'and electncel CPI = (sodium /0.90) + (Chionde/1.70) + (SuNebe/1.go) +
configurabons to the plants systems (Iron /4 40) + (CopperA130)/5.
- 1) Temporary conhgurahons are defined as electricaljumpers, where: Sodium, suuste and chiande are the montNy everage elecmcel blocks, machencel jumpers, or machenical blocks blowdown concentrations in ppb, iron and copper are monthly which are inetsted in the plant operating systems and are not time weighted everage feedwater concertrabons in ppb. The shown on the isteet revision of the PalD, schemahc, denommator for each of the Dve factors is the INPO medien connachon, wiring, or flow dimorems vehe. If the mortnly overage for a specifle parameter is less then the INPO medan value, the meden value is used in the
- 2) Jumpers and blocks which are instahed for Survesence
+ man Tests, Memtenance Procedures, Calibrabon Procedures, Spocal Procedures or Operahng Procedures are not SIGNIFICANT EVENTS canadored as temporary medlAcatens unless the jumper or block ramens M pleos aAer he test or procedure is complete Sigiskant events are the events identified by NRC stoff through Jumpers and blocks instated in test or lab instruments are detailed screenmg and ovelustion of operating esperience. The not considered as temporary modsflcshons acreenmg process includes the deity review and docussen of au reported operahng reactor events, as well as other opershonal
- 3) Scaffold is not considered a temporary modification data such as special toets or construchon actMbes An event Jumpers and blocks which are installed and for which MRs idenhnod from the screenmg process as a sigmAcont event have been submitted wil be considered as temporary cerufidste is further evolunted to determme if any actual or modincehons unti final resolubon of the MR and the jumper poteresi threat to the teeth and safety of the public was irwolved or block is removed or is permanently recorded on the Specific exemples of the type of criterie are summenrod as drawmps This indicator tracks temporary modificatens for fonows:
SEP #62 and 71.
- 1) Degradshon of importent safety equipment, THERMAL PERFORMANCE
- 2) Unexpected plant response to a trenesent, The rullo of he deoipi groes heat rate (corrected) to the arir dati actual groes heet rate, empressed as a percentage
- 3) Degradshon of fusi integrity, pnmery cooient pressure boundary, important==aard=d features; UNIT CAPASILITY FACTOR
- 4) Scram with --.,
The rate of the avouable energy genershon over a ghen time period to the reference energy genershon (the energy that could
- 5) Unplanned reisese of rantaaravity; be produced if the unit were operated conhnuously at fur power under reference embent conditions) over the some time period,
- 6) Opershon outeads the hmits of the Techncal MT,c supressed as e percentage
- 7) Other.
UNIT CAPACITY FACTOR INPO segnificent events reported in the indcator are SERs The not elecincel energy generated (MWH) duded by the (Signincent Event Reports) which inform utiNtes of segnificant product of maamum dependable capacRy (not MWe) times the events and leesons lemmed identified through the SEE-IN gross hours in the reportmg period empressed as a percent Not screenmg process electrical energy generated is the groes electrical output of the unit measured at the output terminels of the turbine generator SPARE PARTS INVENTORY VALUE minus the termal stehon service loads during the groes hours of the reporhng period, expeessed in megewett hours.
The doeler value of the spore parts inventory for FCS dunng the reporting period.
78
l i
l PERFORMANCE INDICATOR DEFINITIONS UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7,000 UNPLANNED SAFETY SYSTEM ACTIONS.pdRC CRmCAL HOURS DEFINITION)
TNs indcoor is donned as the numbw of unpionned automehc The nunter of safety system actuebons wNch include (gDk) the screms (reactor protecmon system logic actuohone) that occur per High Preneure Sofety injecton System, the Low Pressure Safety o'
7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of crthcol opershon.
Ingschon Syalam, the Safety injection Tanks, and the Emergency Diesel Generators The NRC cieselncehon of safety system The value for tNs indcator is calculated by mulhplying the total achatons indudes eduetons when mejor equipment is opereled number of unplanned automehc reactor screms in a specine time and when the logic systems for the ateve safety systems are penod by 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, then drviding that number by the total challenged nunter of hours cettel in the same tune period. The indicator is further denned as fotows:
VIOLATION TREND
- 1) Unplanned means that the scram was not an enheipoted part TNsindcatoris defined as Fort Calhoun Stahon Cited Veinhons of a pionnedlost.
and Non-Cited Veointions trended over 12 months. AddihoneNy, Caed Violabors for the top quartile Region IV plant is trended over
- 2) Scram means the automebc chutdown of the reactor by a 12 rnonths (legging the Fort Calhoun Station trend by 2-3 rapid insertion of nogshve reactrvey (e.g., by control rods, morths). R is the Fort Calhoun Staten geni to be et or boiow the liqLed tjocton ayatem, etc.) that is caused by actuation of the cited vioinhon trend for the top quartile Regen IV plant.
reactor protecten system. The scram signet may have resulted from exceedng a set point or may have been VOLUME 0F LOW LEVEL S0 LID ParwTIVE WASTE l
spurious This indcator is defined as the volume of low 4evel solid redoechve weets actusNy shipped for buriel. TNs indmotor also
- 3) Automshe means that the initial signal that caused actuation shows the volume of low-level radioechve weste which is in of the ruector protechon system logic was provided from one temporary storage, the amount of redmeetive oil that has been of the sensor's monitoring plant parameters and conditions, sNpped off-eNe for M, and the volume of schd dry ralhar Wien tie menuel saem switches or, manuel turtune trip radamethe weste which has been eNpped off-site for processing.
)
owsches (or pushMtons) provvied in the main control room.
Low-level solid radmachve weste consists of dry acthe weste, eludges, reams, and evaporotor bottoms generated as a resuR of
- 4) Crmcal means that during the steady-state condihon of the nudeerpower plant opershon and maintenance Dry radmoctive reactor prior to the scram, the effochve mulhphcahon (k,, )
westeindudse contemneled rags, cleaning materials, dara==M=
was sesentanNy equalto one.
prdecthe clothmg, piemlic contanors, and any other metenal to be i
deposed of at a low-level redmecthe weste disposal site, except UNPUUdNED CAPA31UTY LOSS FACTOR resin, sludge, or evaporator bottoms. Low-level refers to at rodeactive weste that is not spent fuel or a by-product of opent The reto of the unplanned energy losses during a given period of fuel processing This indcator tracks redelogeal work time, to tie reference energy genershon (the energy that could be performance for SEP #54.
produced if the unit were operated conhnuously at full power under reference ambient condmons) over the same time period, expressed as a percentage UNPLANNED SAFETY SYSTEM ACTUATIONS - (INPO DEFINITION)
TNs indutor is denned as the sum of the foNowing safety system actuohons:
- 1) The number of unplanned Emergency Core Cochng System (ECCS) actuatens that resut from reaching an ECCS actuetson est point or from a spunous/ inadvertent ECCS signal.
- 2) The number of unplanned omergency AC power system actuohons that reeut from a loss of power to a safeguards bus. An tmpienned safety system actuohon occurs when an actuaten set point for a safety system is reached or when a apurtous or inadvertent signal is generated (ECCS only), and major equipment in the system is actuated. Unplanned means that the system actuaten was not port of a planned test or evoluhon. The ECCS actuatens to be counted are actuatons of the Ngh pressure infecten system, the low pressure injection system, or the esfety infecten tanks.
79 l
--c,-.
y-
,-g
-.m.
SAFETY ENHANCEMENT PROGRAM INDEX The purpose of the Safety Enhancement Program (SEP) Performance Indicators index is to list performance indicators related to SEP items with parameters that can be trended.
i SEP Reference Number 15 Pace l
. Increase HPES and IR Accountability through use of Performance indicators L
Procedural Noncompliance Incidents (Maintenance).................
49 Clean Controlled Area Contaminations 11,000 Disintegrations / Minute Per Probe Area
...... 5 Recordable injuryAliness Cases Frequency Rate..........
.... 4 l
Preventable / Personnel Error LERs...........
....6 l
l SEP Reference Number 24
. Complete Staff Studies Staffing Level....................
. 42 SEP Reference Numbers 25. 26. & 27
. Training Program for Managers and Supervisors implemented
. Evaluate and Implement Station Standards for Safe Work Practice Requirements
. Implement Supervisory Enforcement of Industrial Safety Standards Disabling injuryAilness Frequency Rate 3
Recordable injuryAliness Cases Frequency Rate..
4 SEP Reference Number 31
. Develop Outage and Maintenance Planning Manual and Conduct Project Management Training l
MWO Planning Status (Cycle 16 Refueling Outage)
....... 66 Overall Project Status (Cycle 16 Refueling outage)
.... G7 Progress of Cycle 16 Outage Modification Planning.....
. 68 SEP Reference Number 33
. Develop On-Line Maintenance and Modification Schedule Percent of Completed Scheduled Maintenance Activities (All Maintenance Crafts).
50 SEP Reference Number 36
. Reduce Corrective Non-Outage Backlog Maintenance Workload Backlogs (Corrective Non-Outage)
...............45 SEP Reference Numbers 41 &_4_4
. Develop and implement a Preventive Maintenance Schedule
. Compliance With and Use of Procedures Ratio of Preventive to Total Maintenance & Preventive Maintenance Items Overdue.
46 Procedural Noncompliance incidents (Maintenance) 49 SEP Reference Number 46
. Design a Procedures Controland Administrative Program Document Review 55 80
SEP Reference Number 52 Egge
. Establish Supervisory Accountability for Workers Radiological Practices Radiological Work Practices Program.....
54 l
SEP Reference Number 54 p
. Complete implementation of Radiological Enhancement Program Collective Radiation Exposure
.. 16 Volume of Low-Level Solid Radioactive Waste......
37 Clean Controlled Area Disintegrations !.1,000 Counts / Minute Per Probe Area
.5 Contaminated Radiation Controlled Area 53 SEP Reference Number 58
. Revise Physical Security Training and Procedure Program Loggable/Reportableincidents(Security).
58 SEP Reference Numbers 60 & 61 l
l
. Improve Controls Over Surveillance Test Program Modify Computer Program to Correctly Schedule Surveillance Tests
(
Number of Missed Surveillance Tests resulting in Licensee Event Reports
. 20 SEP Reference Number 62
. Establish Interim System Engineers Temporary Modifications
...... 57 Engineering Assistance Request (EAR) Breakdown 59 Engineering Change Notice Status
. 60 I
Engineering Change Notices Open.....
.... 61 l
l SEP Reference Number 68
. Assess Root Cause of Poor Operator Training and establish means to monitor Operator Training License Operator Requalification Training
. 63 License Candidate Exams
............... 64 SEP Reference Number 71 improve Controls over Temporary Modifications e
i 57 Temporary Modifications l
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l 81 m.
REPORT DISTRIBUTION LIST i
R.L. Andrews J. D. Keppler K. L. Belek D. D. Kloock B. H. Biome L.T.Kusek C. E. Boughter M. P. Lazar C. J. Brunnert B. R. LMngston M. W. Butt D. L. Lovett C, A.Carlson J. H. MacKinnon G. R. Cavanaugh J. W. Marcil j
J. W. Chase N. L. Marfice A. G. Christensen R. D. Martin O. J. Clayton T. J. Mcivor R. P. Clemens K. G. Melstad R. G. Conner K. A. Miller J. L. Connolley P. A. Mruz G. M. Cook Nuclear Licensing S. R. Crites
& Industry Affairs D. W. Dale J. T. O'Connor D.C.Dietz W. W. Orr M. L. Ellis T. L. Patterson H. J. Faulhaber R. T. Pearce M. T. Frans R. J. Phelps D. P. Galle W.J.Ponec S. K. Gambhir C. R. Rice J. K. Gasper A. W. Richard W. G. Gates D. G. Ried S. W. Gebers G. K. Samide L V. Goldberg M. J. Sandhoefner D. J. Golden F. C. Scofield D. C. Gorence H. J. Sefick R. H. Guy J. W. Shannon A. L. Hale C. F. Simmons K. R. Henry E.L.Skaggs J. B. Herman J. L. Skilos T. L. Herman F. K. Smith K. C. Holthaus R. D. Spies L. P. Hopkins D. E. Spires C. K. Huang R. L. Sorenson T. W. Jamieson K. E. Steele R. L. Jaworski M. A.Tesar R. A.Johansen J. J. Tesarek J. W. Johnson J. W. Tills R. Jones
- D. R.Trausch I
W. C. Jones J. M. Waszak G. R. Williams S. J. Willrett 82
FORT CALHOUN STATION OPERATING CYCLES AND REFUELING OUTAGE DATES EVENT DATE RANGE PRODUCTION (MWH)
CUMULATIVE (MWH)
Cycle 1 09/26/73- 02/08/75 3,299,639 3,299,639 1st Refueling 02/08/75 - 05/11/75 O
Cycle 2 05/11/75-10/01/76 3,853,322 7,152,961 2nd Refueling 10/01/76-12/13/76 l
Cycle 3 12/13/76- 09/30/77 2,805,927 9,958,888
=
3rd Refueling 09/30/77 - 12/09/77 Cycle 4 12/09/77 -10/13/78 3,026,832 12,985,720 4th Refueling 10/13/78-12/24/78 Cycle 5 12/2A/78 - 01/18/80
_ 3,882,734 16,868,454 Sth Refueling 01/18/80 - 06/11/80 4
Cycle 6 06/11/80 - 09/18/81 3,899,714 20,768,168 6th Refueling 09/18/81 - 12/21/81 Cycle 7 12/21/81 - 12/03/82 3,561,866 24,330,034 7th Refueling 12/03/82- 04/06/83 Cycle 8 04/06/83- 03/03/84 3,406,371 27,736,405 8th Refueling 03/03/84- 07/12/84 Cycle 9 07/12/84 - 09/28/85 4,741,488 32,477,893 9th Refueling 09/28/85 - 01/16/86 Cycle 10 01/16/86 - 03/07/87 4,356,753 36,834,646 10th Refueling 03/07/87 - 06/08/87 Cycle 11 06/08/87 - 09/27/88 4,936,859 41,771,505 11th Refueling 09/27/88 - 01/31/89 Cycle 12 01/31/89 - 02/17/90 3,817,954 45,589,459 12th Refueling 02/17/90 - 05/29/90 Cycle 13 05/29/90- 02/01/92 5,451,069 51,040,528 13th Refueling 02/01/92- 05/03/92 Cycle 14 05/03/92- 09/25/93 4,981,485 56,022,013 14th Refueling 09/25/93-11/26/93 Cycle 15 11/26/93 - 02/20/95 5,043,887 61,065,900 15th Refueling 02/20/95 - 04/14/95 Cycle 16 04/14/95- 09/21/96 16th Refueling 09/21/96 - 11/02/96 (Planned Dates)
FORT CALHOUN STATION CURRENT PRODUCTION AND OPERATIONS " RECORDS" First Sustained Reaction August 5,1973 (5:47 p.m.)
[
Firct Electricity Supplied to the System August 25,1973 p
Commercial Operation (180,000 KWH)
September 26,1973 Achieved Full Power (100%)
May 4,1974
)
Longest Run (477 Days)
June 8,1987-Sept. 27,1988 i
Highest Monthly Net Generation (364,468,800 KWH)
October 1987 Most Productive Fuel Cycle (5,451,069 MWH - Cycle 13)
May 29,1990-Feb.1,1992 Shortest Refueling Outage (52 days)
Feb. 20,1995-April 14,1995 l