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| ML20199K475 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/31/1997 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20199K459 | List: |
| References | |
| NUDOCS 9802060193 | |
| Download: ML20199K475 (83) | |
Text
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OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION PERFORMANCE INDICATORS I
DECEMBER 1997 SAFE OPERATIONS PERFORMANCE EXCELLENCE COST EFFECTIVENESS
$$0* IS$S 7)S8$$3es P PDR
Table of Contentsl. Sun) mary TABLE OF CONTENTS /
SUMMARY
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . 1-lil em <
M ONTH LY OPE RATIN G R EPORT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iv 1
WAN Q PERFO R M AN C E IN D EX TR E N D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v WANO PERFORMANCE INDEX INDICATOR . . . . . . . , , , , . . . . . . . . . . . . . . . . ........., . . . . . . Vi
. _WANO PERFORM ANCE INDICATOR TRENDS , , . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vli FORT CALHOUN STATION REPORT
SUMMARY
, . . . , . . . . . . , , . . . . . . . . . . . . . . . , , . . . , . . , vill
_ NUCLEAR PROGRAM GOALS AND OBJECTIVES , . . . . . , . . , , , . . . . . . . . . . . . . . . . . . . . . lx xli WANO PERFORMANCE INDICATORS Unit C apability Factor . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Unplanned Capability loss Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , , , . . , , , . . . . . 3 Unplanned Automatic Reactor SCRAMS per 7000 Fhurs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 l High Pressure Safety injection System . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . 5 l
l Auxiliary Feedwater System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 l
Emergency AC Power System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 The rmal Performance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Fuel Reliability indicator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . 9 Secondary System Chemistry . . . . . . . . . . . , . . . . . . . . . . , . ........... .. ........ ..... 10 Collective Radiation Exposure . . . . . . . . . . . ........ . ..................... ..... , 11 Industrial Safety Accident Rate . . . . . ..................... .. ... ......... ........ 12 Volume of Low Level Radioactive Waste . . . . . . ............. .. ............ .,.... 1?
SAFE OPERATIONS Disabling injury / Illness Cases Frequency Rate . . . . . . . .. ....... .. .. .. . . 15 Recordable injury / Illness Cases Frequency Rate . . . . .. .. .. ... ..... . . 16 Clean Controlled Arem ' ]ntaminations
>1,000 Disintegrations /Minuto per Probe Area .. . . . .. ., , .. .. 17 i
Table of Contents / Summary Preventable / Personnel Error LERs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 Licensee Event Report (LER) Root Cause Breakdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 Violation Trend . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 l
Maximum individual Radiation Exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 PERFORMANCE 2
Station Net Generation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 Forced Outage Rat e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 Unit Capacity Factor ... ........................................................... 25 Equivalent Availabihty Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 Unplanned Safety System Actuations INPO Definition .. .................. .... ................... ............ 27 NRC Definition .......................................................... 28 Gross Heat Rate . ....................... .................................. 29 Daily Thermal Output . ........... ..................................... ....... 30 Equipment Forced Outages per 1,000 Critical Hours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 Chemistry Action Levels E xceeded - Event Days . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 Primary System Lithium % Hours Out of Limit , . . . ........................... .... . 33 COST Cents Per Kilowatt Hour .......... . .. .................. ............. ........... 35 i- 4 DIVISION AND DEPARTMENT PERFORMANCE INDICATORS Maintenance
-J Workload Backlogs (Corrective Non-Outage) .. ................ . ....... ..... 37 Ratio of Preventive to Total Maintenance ... ... ..,............................. 38 Percentage of Total MWDs Completed per month identified as Rework . . . . . . . . . . . . . , , 39 Overtime . . . . . . . . . . . . . . . . . . . . . . . . . ............. ... . . ....... ... 40 Procedural Noncompliance Incidents . . . . . . . ........ ... ...... . ... ....... 41 In-Line Chemistry Instruments Out-of-Service .. . ..... .. ..... .... . . 42
, ii
Table of Contents / Summary '
Hazardous Waste Produced . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ' 4 3 Contaminated Radiation Controlled Area .....................,.. ...................... 44 Radiological Work Practices Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 5 l Docu ment Review . . . . . . . . . . . . . ................................................46
, Loggable/Reportabie lncidents (Security) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47 Temporary Modifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ............. 48 Outstanding Modifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 9 Engineering Assistance Request (EAR) Breakdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 Engineering Change Notices Status..................................................................51 Open......................,.............................................52 .
Safety System Failures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . 53 Ucensed Operator Requalification Training .............................. .............. 54 i
License Candidate Exams . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55 Co nd ition Reports , , . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 Cycle 18 Refueling Outage MWD Planning Status ................................ .... .. . ........... 57 Engineering Project Status . . . . . .............................................. 58-Outage Modification Planning . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 59 On-Line Modification Planning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 Progress of 1997 On-Line Modification Planning ......... ........................ ...... 61 A ACTION PLANS. DEFINITIONS. SEP INDEX & DISTRIBUTION LIST Action Pla n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . 63 Performance indicator Definitions . . . . . . . . . . . . . .......................... ........... 64 Safety Enhancement Program lndex ........................ .. .. ... ...... .. ..... 72 Report Distribution List ................ ..... .......... .. ............ .. . . . . 74 lii
FORT CALHOUN. STATION DECEMBER 1997 Monthly Operating Report l
l OPERATIONS
SUMMARY
Fort Calhoun Station s. OS) operated at a nominal 100% power level, until December 19,1997, when reactor power was reduced to 95% to perform Moderator Temperature Coefficient (MTC) testing. Following completion of MTC testing, reactor power was retumed to 100% reactor power on December 22,1997, through the end of the month.
1 J
iv
i gings Fort CathounindexValue 12/97 0 PPD Value was 87.5%
Industry Median index Value 3rd QRT. INPo Median is 86.4%
100 7
90 83.9 85.2 83.2 84.7 89.0 87.5 86.5 ,
llIi1.1TIl 96/4 97/1 97/2 97/3 oct Nov Dec WANO PERFORMANCE INDEX TREND The Wano Performance Index Trend calculation is made up of eleven variablas, each value is weighted to arrive at an overall index value. INPO calculates the Y ano Performance Index value based on the Industry reporting the information each quarter.
The variables are calculated over a defined period of time as listed below.
PERFORMANCE INDIC ATOR WElGHTED FACTOR IJME Unit Capability Factor 16 24 Months Unplanned Capability . ' Factor 12 24 Months High Pressure Safety injection 10 24 Months A: . ry Feedwater 10 24 Months
. E .srgency AC Power 10 24 Months Unplanned Auto Scrams /7000 Hours 8 24 Months Collective Radiation Exposure 8 24 Months Thermal Performance indicator 6 12 Months Secondary Chemistry Indicator 7 12 Months industrial Safety Accident Rate 5 12 Months Fuel Reliability Indicator 8 Quarterly v
. . . +
b
~
16.00 g MAXMM VALtE g Noverrt)er %7 O Decerrt)erW Y
14.00 !!
12.00 .
ggg ggg g
,g gg . sse sss _
s 8 888 888 8' i
d ddd ddd 8.00 888
""" 888 0dd 6.00 888 sds I
4.00 2.00 . ..
0.00 -
+ + + + + -+ + + , a _-. 4 UCF UCLF FPSI AFW EACP CRE UAS7 FRI CPI TPI ISAR WANO PERFORMANCE INDEX INDICATORS This graph shows the difference between the Maximum No. of points for each WANO indicator and the actual value achieved by Fort Calhoun.
The current graph shows the difference between November '97 and December '97.
CALCULATED OVER A 2 YEAR PERIOD CALCULATED OVER A 12 MONTH PERIOD UCF Unit Capability Factor TPI Thermal Performance Indicator UCLF Unplanned Capability Loss Factor CPI Secondary Chemistry Indicator HPSI High Pressure Safety injection ISAR Industrial Safety Accsdent Rate AFW Auxiliary Feedwater EACP Emergency AC Power CALCULATED OVER A QUARTERLY PERIOD UAS7 Unplanned Auto Scrams / 7000 Hours FR1 Fuel Reliability Indicator CRE Collective Radiation Exposure vi
_ _ _ _ _ = _ - _ _ _ _ _ _ - _ _ - _ -
l WANO PERFORMANCE INDEX TRENDS '
-(As compared to previous month)-
Unit Capability Factor No Change Unplanned Capability Loss Factor No Change High Pressure Safety injec'Jon No Change Aux. Feedwater System No Change Emergency AC Power increased
. Collective Radiation Exposure No Change -
- Unplanned Automatic Reactor Scrams No Change Fuel Reliability - No Available Points Chemistry Indicator No Change Thermal Performance No Change Industrial Safety Accident Rate No Change l
-e vii
FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT DECEMBER 1997-
SUMMARY
POSITIVE TREND REPORT EBCCCD! ace of Total MWD's Comoleted Per k'onth Idengurd, as Rework /Regggj (Page 39)
A performance indicator with data representing three consecutve months of improving performance or three In-Line Chemistrv Instmments Out.Of-Se vice consecutive rnonths of performance that is supenor to b J (Page 42)
.- stated goal is exhibiting a positive trend per Nudear Operations Division Quality Procedure 37 (NOD QP-37). Hazardous Waste Produce (Page 43)
The following performance indicators exhibited positive trends for the reporbng rnonth: Outstandino ModrficatigrA (Page 49)
Unolanned Automatic Reactor Scrams ADVERSE TREND REPORT (Page 4)
A performance indicator with data represen9ng three liQb Piessure Safety Iniection System Safety SystMD consecutive months of declining performance or three Performance (Page 5) consecutve months of performance that is trending toward dedining as determined by the Manager . Nudear Aur. Feed Water System Safety System Parformance Licensing, constitutes an adverse trend per Nuclear
. Mge 6) Operations Division Quality Procedure 37 (NOD QP-37). A supervisor whose performance indicator exhibits an adverse
- neronnev AC Power System Safety System trend by this definition may specify in written form (to be Performance (Page 7) published in this report) wt y the trend is not adverse.The following performance indicators exhibited advern trends Thermal Fw-tnn ace (Page 8) for the reporbig month.
Secondary System Chemistrv(Page 10) Fuel Reliability Indicaigt (Page g)
Industrial Safety Accident Rate (Page 12) Ratio of Preventive to Total Maintenance Preventive Maintenance items Overdue (Page38)
Volume of Low-level Radioactive Waste (Page 13)
( INDICATORS NEEDING INCREASED MANAGr1ENT ATTENTION REPORT Disablino iniurv / Ittness Frecuenev Rate (Page 15) A performance indicator with data for the reporting period that is inadequate when compared to the OPPD goal is Recordable Iniurv rillness Fmouenev Rate defined as "Needing increased Management Attention" per
. (Page 16)
(NOD-QP-37).
UncInned Safety System Actuations (INDO Definition) Unit Caoability Factor (Page 2)
(Page 27)
Uno!anned Canability Loss FactorfPage 3)
Unclanned Safe'v System Actuations (NbtC Definition)
, (Page 28) Forced Outace Rate (Page 24)
Gross Heat Rate (Page 29) Unit Cacacity Factor (Page 25)
. Chemistrv Action Levels Exceeded-Event Davs Eauivalent Availability Factor (Page 26)
(Page 32)
Eautoment Forced Outaoes Per 1.000 Critical Hours Primary System Ltthium % Hours out of Umit (Page 31)
(Page 33) Cents Per Kilowatt Hour (Page 35) htaintenance Workload Backloo (Page 37)
Vili
____a
NUCLEAR PROGRAM 1997 GOALS AND OBJECTIVES FUTURE FOCUS and RELATIONSHIP to CHANGE The nation's electric utility industry is passing through a period of significant organizational, financial and cultural changes, in this new era, change is inevitable, progress and success are not. Fort Calhoun must react to these changes while improving capacity, SALP ratings and INPO ratings.
We must KNOW OUR COSTS to CONTROL COSTS. Understanding cost is essential to controlling it, and controlling cost is essential to competing in today's market.
We are a learning organization. We must BUILD ON OUR HIGH PERFORMANCE CULTURE.
Individuals at all levels must take responsibility for their actions and must be committed to improve their own performance.
l OUR CULTURE MUST SUPPORT THE NEW STRATEGIES. We must continue to deve.op cnd implement strategies that will allow us to effectively compete in the evolving market while still maintaining the highest levels of safety and reliability. Communicating is our key to l improving. Follow up and feedback must be candid, forthright and timely.
We recognize that change causes disruption of work and work flow. That change requires increase 1 lanagement direction. We need IN-DEPTH, RELENTLESS ATTENTION to cur NEW fos.')S/ STRATEGIES.
Y! SIDE To be recognlied as the best nucler organization in the world and to preserve nuclear energy cs a viable future energy source.
MISSION The safe, reliable and cost effective generation of electricity for OPPD custometa through conservatbie decision making and the professional use of nuclear technology. We will conduct these operations to assure the health, safety, and protection of our personnel, the general public, and the environment.
l ix
OPPD NUCLEAR ORGANIZATION GOALS Goal 1: SAFE OPERATIONS Supports: April 1996 Corporate Strategic Plan Goal 3, Objective: 3 & 4 -
A proactive, self-critical and safety conscious culture is exhibited throughout the nuclear organization. Individuals demonstrate professionalism through self-ownership and personal initiative and open communication.
1997 Priorities:
Achieve an overall SALP Rating of "1" in 1997.
Focus can Achieving an INPO Rating of"1"in 1998.
Reduce 1997 NRC violations with no violations more severe than level 4.
No unplanned automatic reactor scrams or safety system actuations.
Objectives to support SAFE OPERATIONS.
OBJECTIVE 1-1:
No challenges to a nuclear safety systems.
OBJECTIVE 1-2:
Comply with applicable policies, technical specs, procedures, standiDO orders and work instructions.
OBJECTIVE 1-3:
Identify conditions BEFORE they affect plant safety and reliability. Address every safety concern.
OBJECTIVE 1-4:
Achieve all safety-related 1997 performance indicator goals in the Performance Indicator Report.
OBJECTIVE 15:
Zero Lost Time injuries and recordable injuries rate BELOW 1.5 percent X
OPPD NUCLEAR ORGANIZATION GOALS 1997 Priorities Goal 2: PERFORMANCE Supports: April 1996 Corporate Strategic Plan Goal 3, Objective: 2; G-4, Objective: 1, 2, & 3; G 5, Objective: 2 Nuclear teamwork achieves high wrformance at Fort Calhoun Station as exhibited by safe, reliable and cost effective power production.
1997 PRIORITIES:
- Improve Quality, Professionalism and Teamwork.
Maintain High Plant Reliability.
- -
- Pursue efficient, cost-effective work processes, e Meet or exceed INPO key parameters.
- Reduce the number of Human Perfonnance errors.
- Identify Programmatic performance problems through effective self assessment.
- Maintain a high level of readiness in the ERO.
Objectives to support PERFORMANCE:
OBJECTIVE 21:
Achieve an annual plant capacity factor of 92.7% and a unit capability factor of 96.0%
i OBJECTIVE 2-2:
Training meets the needs of the plant and the National Academy accreditation objectives.
. Line managers use training to present, discuss & reinforce performance standards, e
Line managers monitor and assess personnel performance to determine how well sta 'dards are met.
Line managers through personal involvement in training emphasize the importance of c.onducting
= sctivities within approved procedures / practices.
. Executive Training Committee:
+ invites line supervisors to discuss the direction training is going for their specific area.
+ invites the line and training supervisors responsible for each accredited program to
=-
provide a status of internal accreditation assessments.
+
ensures items such as training attendance, attentiveness, punctuality, etc. are uniformly
.. emphasized Xi
OPPD NUCLEAR ORGANIZATION GOALS 1997 Priorities Goal 2: PERFORMANCE (Continued)
OBJECTIVE 2 3:
Achieve all performance-related 1997 performance indicator goals in the Performance Indicator Report.
Focus on performing basic skills well, while pursuing efficient, cost-effective work processes. Identify the barriers to excellence and resolve them.
OBJECTIVE 2 4:
Plan for the completion of the 1998 refueling outage in 42 days or less.
OBJECTIVE 2 5:
Teamwork is evident by improved plant reliability, an effective omergency response organization, reduc.ed number of human performance orrors and effective self assessment.
Daall: COSTS Supports: Apn! 1996 Corporate Strategic Plan Goal 2, Objective: 1, 3, and Goal 5,
, Objective: 1 Operate Fort Calhoun cost effectively to contribute to OPPD's " bottom line". Cost consciousness is exhibited at all levels of the organization.
1997 Priorities:
Maintain total O&M and Capital Expenditures withiri budget.
Streamline work process to improve cost effectiv ..ess.
- Implement Opportunity Review recommendations.
Objectives to support COSTS:
. OBJECTIVE 31:
Conduct the nuclear programs, projects, and activities within the approved Capital and O&M budgets.
OBJECTIVE 3 2:
Significantly reduce operating costs through full support of Utilities Service Alliance initiatives by maximizing sharing of resources, leveraging of buying power and elimination or reduction of redundant support services.
Goals Source: Lounsberry (Manager)
Xii i
l l
- WANO PERFORMANCE INDICATORS 9
1
m coettMy U211 C opsbuity Fact r
{
NOS r".'r$ c."i$eu*a'*o'."[i psM"
+ Ye ar 2000 W ANO Indus try 0041(47%)
110% .. g gg,g 100.0% 100.0% 100.0% 100.0%
100% 05.4% 100.0 % 100.0 %
1 70% . : ; .0;0% .6% : : 7 1%-P 4 5 s0%
v_. - - - -
80% .
.0% - -
30% .
20% +
10%.
0%
4 I ) I I j T I I 8 I $ r l
UNIT CAPABILITY FACTOR
. UCF is defined as the ratio of the available energy generation over a given period of time to the reference energy generation over the same time period, expressed as a percentage. The UCF for Decembe 1997 was reported as 100%. The year-to-date UCF was also reported as 90.2%, the UCF for the last 12 months (January 1997 through December 1997) was 90.2%, and the 36-month average (January 1995 through December 1997) was reported as 80.6%.
Enerer Losses:
- Forced Outage - Condenser circulating valve repairs and leakage on Condenser "B,
Event Period: September 10, thru 13,1997.
l
- Power Reduction - Faulty Manual Transfer switch on instrument inverter "A ",
Event Period: August 26, thru 28,1997.
Forced Outage - Circumferential cracking of a weld down stream of a moisture separator due to high system stresses, 4
Event Period: May 28, thru May 29,1997.
Forced Outage - Steam leak in the fourth stage extraction steam system, Event Period: April through mid May 1997 The Year 2000 WANO industry goal is 87% and the industry current best quartile value is approximately 85%. The 1997 Fort Calhoun annual goal for this indicator is a mirdmum of 96.0%. The maximum index point value for this indicator is 16.00. At the end of the Decem')er 1997, the FCS Value was 13.48. This compares to the previous month's value 13.48.
Data Source: Generation Totals Report & Monthly Operating Report Accountability: Chase Trend: Needing Increased Management Attention 2
a Dnthly unplan:t;d Capability Lisa Factir
.Y r th a o's (158
+ YOar 2000 CANO 1;;d:a try Orl(4.5%)
60%
56.30 %
50% .
40%_
30.50 %
30% + - 24.50 %
~
20%-
4 % 0.00 % o. con 0.00%
0.00 % 0.00 % 0.00 % , ,
10% 4 : : ;- " " - '
O.0'0 D ; O 0% -- - -- - - - - - - -- -
4 ! a k I f k I I 5 $ $
a UNPLANNED CAPABILITY LOSS FACTOR This indic1 tor shows the plant monthly Unplanned Capability Loss Factor (UCLF), a rolling 12-month average, the OPPD goal, and the Year 2000 WANO goal. UCLl< is defined as the ratio of the unplanned energy losses during a given period of time, to the refercsce energy generation expressed as a percentage. Unplanned energy loss is defined as energy not produced as a result of unscheduled shutdowns, outage extensions, or lead reductions due to causes under plant management control. Energy losses are considered to be unplanned if they are not scheduled at least four weeks in advance.
The UCLF for the month of December 1997 was reported as 00.0%, the Year-To-Date UCLF was 9.80%, the UCLF for the last 12 months (January 1997 through December 1997) was 9.80%, and the 36-month average UCLF (January 1995 through December 1997) was repcrted as 9.3% at the end of the month.
The Year 2000 WANO industry goal is 3.0% and the industry current best quartile value is approximately 3.2%. The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 1.58%.
The maximum index point value for this indicator is 12.00. At the end of December 1997 the FCS Value was 12.00. This compares to the previous month's value of 12.00. ,
Data Source: Generation Totals Report & Monthly Operating Report Accountability: Chase Trend: Needing increased Management Attention 3
1
12 Month Rolling Aver;pe FCS Re:ct:r Scrams P:r 7,000 Hours critical f r last 36 m:nths l
Fort calhoun ooal(0.0) i Year 2000 WANo industry ooal(1) 3 2+
1 0: : : : : : : : : :
o 2 Jan Feb Mar Apr May June July Aug Sep Oct Nov Dec
, FCf Reactor Scrarns .1997 -
4 .,.
3..
2+
1 7
0 0 0 0 0 0 0 0 0 0 0 0 Jan Fe b Mar Apr May June Juh Aug Sep Oct Nov Dec
^
UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7000 HOURS CRITICAL The upper graph shows the 12-month rolling average, the 3S-month average, the OPPD goal for 1997 and the Year 2000 WANO goal. The lower graph shows the number of unplanned automatic reactor scrams that occurred during the last 12 months. This indicator is defined as the number of unplanned automatic scrams that occur per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of critical operation.
There were no unplanned automatic reactor scrams during the month of December 1997. The 12-month rolling average (January 1997 through December 1997) was 0.
The 36-month value (January 1995 through December 1997) was 0.310.
The 1997 Fort Calhoun Station goal for this indicator is 0. The Year 2000 WANO Industry goal is a maximum of one unplanned automatic reactor scram per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> critical. The maximum index point value for this indicator is 8. At the end of the December 1997, the FCS Value was 8.0. This compares to the previous month's value of 8.0.
Data Source: Monthly Operating Report & Plant Licensee Event Reports (LERs)
Accountability: Chase Trend: Positive 4
m Monthly HPSI System Unavallability Value
+ 12 Month Rolling Average Fort Calhoun Goal (0.003)
Year 2000 WANO Industry Goal (0.02) 0 02 - : : : : : : : : : : : :
0.015 .
0.01 - ,
0.005 ..
0 : : : A: ; ; ; ; ; ; ,
Jan Feb Mar Apr May June July Aug Sep Oct Nov Dec HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the High Pressure Safety injection (HPSI) System unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for December 1997.
The HPSI System unavailability value for the month of December 1997 was 0.0. There were 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of planned unavailability, and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned unavailability, during the month. The 12 month rolling average was (January 1997 through December 1997) was 0.81 X E-5, and the year-to-date HPSI unavailability value was 9.8 x E-4 at the end of the month. For the previous year there was a total of 1.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of planned unavailability and 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of unplanned unavailability for the HPSI system. ,
The 1997 Fort Calhoun year-end goal for this indicator is a maximum value of 0.003.
The Year 2000 WANO industry goal is 0.02 . .
The maximum index point value for this indicator is 10. At the end of December 1997 3 the FCS Value was 10. 1 his compares to the previous month's value of 10.
Datc Source: Phelps/Schaffer (Manager / Source)
Accountability: Phelps/Schaffer Trend: Positive 5
l l
1 n Ab Fort Calhoun Goal (0.01) laNiity
_ _ _ _ Year 2000 WANO Industry Goal (0.025) 0.025 , ___ ___ ___
0.02 +
0.015 - 0.013 0.01 .. 0.009 0.005 . -
' 0.501 0.002 0
= ES -
Jan Feb Mar Apr May June July Aug Sep Oct Nov Dec AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Auxiliary Feedwater (AFW) System Unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for the month of December 1997.
The AFW System Unavailability Value for December 1997 was 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. There were 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of planned and 00.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of Unplanned Train Unavailability hours during the month. The 12 month rolling average (January 1997 through December 1997) was 0.004, and the year-to-date unavailability value was 0.004 at the end of December 1997.-
. The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 0.01. The Year 2000 ' NANO industry goal is 0.025.
The maximum index point value for this indicator is 10. At the end of December 1997, the FCS Value was 10. This compares to the previous month's value of 10.
Data Source: Pheira/Fritts (Manager / Source)
Accountability: Phelps/Fritts Trend: Postive 6
__E
m Monthly Emer.ency AC Powor Unavailability Value
. Yest to.Dete Emer.ency AC Powe, Uneveliability Value Fort Calhoun Goel(...t4)
,.,,. _._._ ve e , . .. . w n o in..e ,, aos no... .i
.....I
.. 3 ..
..2..
..1..
=
, .M.N. ,
,E; , , . .
-k- 1 5 k. E f $ $ 5 8 5 [ . i EMERGENCY AC POWER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Emergency AC Power System unavailability value, as defined by WANO in the Safety System Performance Indicator Definitions, for the month of December 1997. The Emergency AC Power System unavailability value for December 1997 was 0.018. The Emergency AC Power System unavailability value year-to-date was 0.015 and the value for the last 12 months (January 1997 through December 1997) was 0.015.
Monthly Statistics Planned Unavailability: DG.1: 11.5 DG-2: 15.8 Total: 27.3 YTD: 221.7 Hours -
Unplanned Unavailability: CG-1: 0.0 - DG-2: 0.0 Total: G/J YTD: 84.7 Hours -
There were a total of.188.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of planned unavailability and 3.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> of unplanned unavailability for the emergency AC power system in 1996. -
The 1997 Fort Calhoun year-end goal for this indicator is a maximum value of 0.024.
The Year 2000 WANO industry goal is 0.025. The maximum index point value for this Indicator is 10.0. At the end of December 1997, the FCS Value was 8.0. This -
compares to the previous month's value of 7.0.
Data Source: Phelps/Ronning (Manager / Source)
Account ibility: Phelps/Ronning Trend: Positive 7
m MonthlyThermalPerformance
, ,12. Month Rolling Average Fort Calhoun Goal (99.6%)
Year 2000 W ANO Industry Goal (99.5%)
W . . . .
l*
l 99%.
i 98%
4 $ $ I I j k I d 5 5 $
i THERMAL PERFORMANCE This indicator shows the monthly Thermal Performance Value, the rolling 12-month average, the OPPD goal, and the Year 2000 WANO goal.
The thermal performance value for the month of December was 100%. The year to date value was reported as 99.9%. The 12 month rolling average (January 1997 through December 1997) was reported as 99.9%.
. The 1997 Fort Calhoun year-end goal for this inoicator is an index value which is >
99.6%. The Year 2000 WANO industry goal is 99.5%.
The maximum index point value for this indicator is 6. At the end of December 1997,
, _the FCS Value was 6.00. This compares to the previous month's value of 6.00.
Data Source: Phelps/Naser(Manager / Source)
Accountability: Phelps/Naser Trend: Positive I
8
EEEg Fu e l Re lia bility (E 4 Microcuries/ Gram)
Year 2000 W ANO Goal ($ x E.4 Microcuries/ Gram) 19 9 7 Goal (14 7 x E.4 M icroc urle s /Gra m ) l 160 - l
[ 140 1 g 120 l j 100 I 86 H 33 60 45 d 40 1 3 e.1 18.6 22.s 31.1 29.7 5 y
'at- =m 0
E 3 5 % $ u 2 _ , _ _ _
1 ~
k b a k $ $
' k $ $ o $ b l .
FUEL RELIABILITY INDICATOR -
The monthly FUEL RELIABILITY INDICATOR (FRI) for December 1997 was 99 x E-04 microcuries/ gram based on the steady state data at 100% power. Several days after December 21 did not meet the steady state criteria for the FRI calculation, due to performance of the TS required at power MTC test.
NOTE: The corrected Fuel Reliability Indicator (FRI) for November 1997 is 86 X E-04.
Coolant activity data through December 31,1997 shows the presence of 24 leaking rods at core average power. If the leaking rods are at 70% or 50% of core average power, the number of leaking rods changes to 40 and 65, respectively. The increase in predicted failures from November is primarily due to the increase in Xenon-133. The Cesium data indicates the leaking fuel is most likely in the second and third bumed fuel regions (Batches S and T) which have the original grid design. These batches will be permanently discharged from the reactor core during the spring 1998 refueling outage. However, unusual RCS activity data from early December may indicate the presence of one high power failure from the new fuel region (Batch U) with the new grid design. Confirmation of the fuel region (s) with failures cannot occur until the fuel inspection campaign during the spring 1998 refueling outage.
The Cycle 17 monthly FRI is trending slightly lower than the Cycle 16 FR1 at the same time in the fuel cycle due to the large contribution of the lodine-134 from the " tramp" Uranium. The lodine-134 activity is released to the coolant from the tramp activity that is plated out on fuel assembly surfaces due to fuel failures in prior cycles, in the FRl equation, the lodine-134 activity is subtracted from the lodine-131 activity. This cycle, the tramp activity is trending two times higher than Cycle 16 while the lodine 131 is trending similar to the Cycle 16 values at the s6me point in the cycle. Therefore, the Cycle 17 calculated FRl value is trending lower.
The plant is currently in Action Level 4 Standing Order SO-O-43, " Fuel" Reliability Action Plan", based on M conservative call with 24 core average power failures.
The maximum index point value for this indicator is 8.0. At the end of the December 1997, the FCS Value
- was 0.0. This compares to the previous month's value of 0.0.
Data Source: Guinn/Roenigk (Manager / Source)
Accountability: Chase /Stafford Trend: Adverse 9
l
m !WhlyChemistryindicator Fort Calhoun Goal (1 A)
T 2*I0 2.43 2.51 2.25 2
1.75 -
1.5 1.31 1.27 3,33 1.x W 1.32 L1 1 1 1.05 1.1 1,11 d.25.itu ll c .D w 6 > e h m n, +4 >
tc 5 l
~
A I 5 $ 8 N $ o E $
SECONDARY SYSTEM CHEMISTRY Criteria for calculating the Secondary System Chemistry Performance Index (CPI) are as follows:
- 1) the plant is at greater than 30% power.
- 2) the power is changing at less than 5% per day.
The CPI for DE . amber 1997 is 1.11. The CPI value for the past 12 months (January 1997 through Decomuer 1997) was 1.27. The CPI value in the industry's upper quartile is 1.17.
Six parameters are used in the CPI calculation. Four of the parameters were below the INPO mean value which are as follows: 1) steam generator chloride,2) sulfate,3) feedwater iron, and condensate pump discharge dissolved oxygen. Slight increase in CPI observed this month due to power reduction for work on Stator Cooling Heat Exchangers. Morpholine injection began this month for iron reduction. Results of analysis are inconclusive at this time. Trending continues.
The maximum index point value for this indicator is 7. At the end of December 1997, the FCS Value was 7.00. This compares to the previous month's value of 7.00.
Data Source: Hamilton /Ostien (Manager / Source)
Accountability: Hamilton Trend: Positive 10
m MartNyPerscnWRutationEposure
_,_ ctmmele Rorsemel Rutation Eposure Boed criALMRRuring FCSOtud 3BpersonRN 45 ..
40 -- .
.J
~
E
- 30 ..
CF -
g 25 .
E ao -
= .
15.
10 -- 3 084 7.090 1.734 67/5 6753 a785 3364 6 008 5._ 1.678 g 1.803 22 0 E. num E E E mm E l aan r4 hr 5 hy Jm Jd Ag Sep Od 2v Dec l
l COLLECTIVE RADIATION EXPOSURE The 1997 Fort Calhoun Non-Outage goal for Collective Radiation Exposure is set at 38.0 person-rem. The exposure for December 1997 was 2.356 Person-rem (ALNOR). The year-to-date dose through the end of December 1997 was 40.873 Person-rem (TLD). Total non outage dose was 31.3 rem; therefore, the collective dose goal was met for 1997. Dose for the Steam Pipe Rupture outage was 9.5 rem.
This indicator is a " COLLECTIVE" incicator. WANO does not differentiate between on-line and outage exposure. The Year 2000 WANO industry goal for collective radiation expc .ure is 120 person-rem per year. For the three yeai period (January 1995 through December 1997), the total collective radiation exposure is 413.90 person-rem (ALNOR). The Fort Calhoun Station
- annual average over 3 years was 137.96 person-rem per year (ALNOR). .
The maximum index point value for this indicator is 8.00. At the end of December 1997 the FCS Value was 8.00. This compares to the previous month's value of 8.00. .
Data Source: Chase / Williams (Manager / Source)
Accountability: Chase /Gebers Trend: None SEP54 11 l
I
MorthlyIrdstrial Acddert Rde 12 Morthlbihng Aworage FCSYear. Bid Goal (450)
_.o._ Year 2003YNotrestryGoal(440) 0.6 ,
0.5 OAb - - - - - - - - - - -
0.3- I 0.2.
0.1
-N _ _ _
0: : : : : 5 5 5 . = =
Jan Feb hr Apr Wy Jme Jdy Aug _ Sep Oct ttu Dec INDUSTRIAL SAFETY ACCIDENT RATE The purpose of this indicator is to monitor progress in improving industrial safety performance for utility personnel permanently assigned to the station. Contractor work-hours are eot included in the indicator. This indicator is defined as the number of accidents per 200,000 work-
' hours worked for all utility personnet permanently assigned to the station that result in any of following:
one or more days of restricted work (excluding the day of the accident.)
One or more days aw1y from work (excluding the day of the acc. dent.)
Fatalities.
ISAR = (number of restncted-time accidents + lost-time accidents + fatalities) x 200.000 (number of station person-hours worked)
The Fort Calhoun Station industrial safety accident rate for the month of December 1997 was 0.00.
The 12 month rolling average (January 1997 through December 1997) was 0. The year to date
. value was 0 at the end of December 1997.
Thers were no restricted-time and no lost-time accidents in December 1997. The 1997 Fort
. Calhoun year-end goal is 50.50. The Year 2000 WANO industry goal is 50.40. The maximum index point value for this indicator is 5.0. At the end of December 1997, the FCS maximum index i point Value was 5.0, which compares to the previous month's maximum index point value of 5.0.
Data Source: Sorensen/Blumenthal (Manager / Source)
Chase / Booth (Manager / Source)
Accountability: Chase /Gebers Trend: Positive 12
e MonthlyVolume of LLRW (Iu.f'.)
Year to Oste Cumulative Radioactive Wasb Buried Fort Calhoun Goal (1200 cu.ft.)
1200-1100 ..
1000 900 . q 800. -@
8 1* $
$ 600 ,
i 1 l u 500 -
400 -
300l a h g g k 2H .. g E -
100 . g 0 : _ _ _ ~ -
, , , :.E Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec a
VOLUME OF LOW-LEVEL RADIOACTIVE WASTE This indicator shows tne volume of the monthly Radioactive Waste buried, the cumulative year-to-date radica::tive waste buried, and the Fort Calhoun goal.
Ft 8 .m*
Amount of sohd radwaste shipped off-site for processing during current month : 1040.0 29.12 Volume of sokd radwaste buried during December 1997 : 60.3 1.7 Cumulative volume of solid radioactive waste buried in 1997 : 793.6 22.2 Amount of solid radwaste in temporary storage : 00.0 0.0 The 1997 Fort Calhoun Station goal for the volume of solid radioactive waste (buried)is .
1200 cubic feet. The Year 2000 WANO industry goal is 45 cubic meters (1,589 cubi:: feet) per year. The industry upper ten percentile value is approximately 27.33 cubi,c meters (965.3 cubic feet) per year. This indicator is no longer tned by INPO. The indicator will still be tracked, but ,
will no longer be used in computing the Station's Index Number.
, Data Source: Chase /Breuer (Manager / Source)
Accountability: Chase /Gebers Trend: Positive SEP 54 13 1
_ _ _ _ _________.-,.____m______-----
SAFE OPERATIONS l
Goal: Ap ictive, self-critical and safety conscious culture is e,.albited throughout the nuclear organization. Individuals demonstrate professionalism through self-ownership and personalinitiative and open communication.
4 14 l
m, , -
+ Monthly DisablinginjuryMiness Frequency
.% 12 Month RotHng Average 1997 F.C.S. Goal (0,$)
0.6 ,
0.61
' 0,4 ,
e 0.3 0,3
~
O : : : : : : : : : _ .
Jan Feb Mat Apr May June July Aug Sep Oct Nov Dec DISABLING INJURY /lLLNESS FREQUENCY RATE (LOST-TIME ACCIDENT RATE)
This Indicatr shows the December 1997 Disabling injury /lllness Frequency Rate and the disabling injury / illness rate for the past 12 months (rolling average).
For the month of December 1997 the disabling injury / illness frequency rate wt s 0.00. For the 12 month period (January 1997 through December 1997) the disabling injury /illn6ss rate was
, 0.04 There were no disabling injury / illness cases reported for December 1997,
. The 1997 Fori Calhoun Station year end goal for this indicator is a maximum value of 0.5, Data Source: Sorenson/Blumenthal (Manager / Source)
Accountability: Chase /Gebers Trand: Postive SEP 25,26 & 27 15
. _ . - - . - __ --- -. - - _ - - - . . ~ - . .
+ Monthly Recordable injury / Illness Frequency Rate
+ Rolling 12 Month Ave age Fort Calhoun Qual (1.5) 4.6 7
4.0 .
3.6 .
3.0 .
2.W . .
4 2.0 .
1.6
~
5 b W' '
1.0 -
Jan Feb Mar Apr May June July Aug Sep oct Nov Dec L
RECORDARLE INJURY /lLLNESS FREQUENCY RATE This indicator shows the monthly Recordable injury /lliness Fiequency Rate, a 'olling 12 inonth average, and the OPPD goal, A recordable injury / illness case is reported if personnel from any of the Nuclear Divisions are injured on the job and require corrective medical treatment beyond first aid. The recordable injury / illness cases frequency rate is computed on a rolling 12 month average.
The recordable injury / illness frequency rate for the month of December 1997 was 1.30.-
The recordable injury / illness frequency rate for the past 12 months (January 1997 through December 1997) was 1.30, During the month of December 1997, there was no recs ^'s injury. There has been a total of 8 recordable injury / illness cases in 1997.
The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 1.5.
Data Source: Sorensen/Blumenthal (Manager / Source)
Accountability: Gebers Trend: Positive SEP 15,25,26 & 27 16
i uma catamirationsets(wntNg i
-* CataminenBatn(YT4 '
100--
90 .
79 80 .
70 . 68
. .ry
- so .
40 ".'/ i
}y+ 24 J
l II 20 . 16 I
8 11 I
l 10 5 5 4 4 6 6 5 o
Jan M mEaae hr Jd ais Feb Apr May Jun As Sep Oct Nw Dec CLEAN CONTROLLED AREA CONTAMINATIONS >1,000 DISINTEGRATIONS / MINUTE PER PROBE AREA This indicator shows the Personnel Contamination Events in the Clean Controlled Area for contaminations >1,000 disintegrations / minute per probe area for December 1997,
, There were 5 personnel contamination events in December 1997. The intal year-to-date of Personnel events was 79 by the end of December 1997.
Data Source: Case / Williams (Manager / Source)
Accountability : Chase /Gebars Trend: None SEP 15 & 54 9
17
so -
j
- W W'"" 18 Month Totals
@n. _. _ rr.v.nt.bi.
3 m. ,_ e.r.or ia,ror A, ___ . _ , ,
/p$ke-e-pb h*
- e. -. ._
0 1I11i!i!!1ill1ii11 .
PREVENTABLEIPERSONNEL 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 date as opposed to the LER report date.
NOTE: Due to the way LERs are tracked & reported, this indicator is one-month behind, in November 1997, there was one event which was subsequently reported as an LER No LER's were categorized as Preventable and no LERs were categorized as Personnel Error for the month of November. The total LERs for the year 1997 is Seventeen. The total Personnel Error LERs for the year M7 is five.
The 1997 goal for this indicator is that the year-end values for the 18 month totals not exceed 12 Preventable and 5 Personnel Error LERs.
Data Source: Tills /Matzke (Manager / Source)
- Accountability: Chase Trend: None SEP 15 18
f.isc 10%
Admn 27 %
Design
. 33 %
LO Dr.
13%
PAst UW Br-7% 10%
l l LICENSEE EVENT REPORT (LER) ROOT CAUSE BREAKDOWN This indicator shows the LERs by event date broken down by Root Cause Code for each of the past eighteen months from June 1,1996, through November 30,1997. To ha mat ?' i ant with the Preventable / Personnel Error LERs indicator, this indicator is reported by the LER event date, as opposed to the LER report date.
The cause codes are intended to identify possible programmatic deficiencies. For detailed descriptions of these codes, see the " Performance Indicator Definitions" section of this report.
NOTE: Due to the way LERs are tracked & reported, this indicater is one-month behind.
There was One event in November 1997 that resulted la a LER.
There were no missed surveillance tests resulting in LERs during November 1997. The 1997 Fort Calhoun monthly goal for this indicator is 0.
^
Data Source: Tills /Matzke (Manager / Source)
Accountability: Chase Trend: None SEP 60 & 6',
19
gaan FC8 Ch*d Viettate CMnthly) g, N a FCS Non. Cited V6olations (WontMy)
C._ ,, ,
G -
u 18 0- [ 12 s_ _ ,
gL l 10 6.- .
6! i 4- -
di 4l ll
- I; h
- !I 1 h
4 4
3 5 I 1I4 .i 4 I $
14t-8 E $.
1
- VIOLATION TREND This indicator depicts twelve months of violation data for Fort Calhoun Station. Illustrated monthly are Cited Violations and Non-Cited Violations.
The following inspection reports noting violations were received during December 1997:
ylolation Level IEfLNL Title
, IV (3) 97-19 Resident Monthly inspection l NCV (2)
{
To date, OPPD has received seventeen violations for inspections completed in the current SALP cycle, Level 111 Violations 1 LevelIV Violations 8 lion-Cited Violations _J_
Total 17 The 1997 Fort Calhoun Station Goal for this performance indicator is to be at or below the cited violation trend for the top quartile plants in Region IV.
Data Source: Tills /Cavanaugh (Manager / Source)
Accountability: Tills Trend: None 20
m F4ft$1 P,bnthly hdNduol Exposuro nR
, ,f 6ghest hdNdual Exposure Year to-date trR FCS Annualyear end Goal 1000 nR'ndkdual I
l 1000 I
900.
800
~ ~
700.
600
~
~ ~
W.
I 400.
300 l
! 200.
100 I
O_ _- E E E Jan fob ihr Apr thy Jun Jul Aug Sep Oct Nov Dec
.il ANIM UM INDIVIDUAL RADI ATION EXPOSURE This indicator show s the highest exposure for an individual during the year 1997.
For the month of December 1997, an individual accumulated 145 milllRem, which was the highest indis idua! esposure for the month.
For the year to date. an individual has accumulated a i tal of 747 millirem TLD and ALNOR readings.
The 1997 Fort Calhoun Station Annual Administrative year-end goalis a maximum of 1,000 milllRem from all sources of occupational exposure at FCS. The OPPD limit for the maximum yearly individual radiation exposure is 4,000 mill! Rent' year from all sources of occupational exposure.
4 Data Source: Chase / Williams (Manager / source)
Accountability: Chase /Gebers Trend: None 4
21
4 i
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 production.
22
_.__-__.i___._ _ . . . _ _
l Net Generation (10,000 MWh) !
29 36.1 43 35.14 34,4g 35.1 34,,
33,,
7 25.9 24.31 l .
18.08
' g 20 I
N 10 .
?
{
0, + _._ _ _ : - .+++ -
k b $ k $ k k $ $ b b b STATION NET GENERATION During the month of December 1997, a net total of 363248.4 MWh were generated by the Fort Calhoun Station. Cumulatiu net generation for Cycle 17 was 4,172,354.70 MWh at the end of December 199'/. Cumulative net generation for Cycle 16 was 5,418,326.6 MWh.
Data Source: Station Generation Report Accountability: Chase
. Trend: None s
a 23
--.u- .-, J e.- 1- -. -,. .~4.+4 e %-- - A .4 4*wL-,-------J--L-5 .* ?mA4+- D-*I -.1.Li4-.~ * . +w& _w - -h -a 4 -h--m- - 4 -. . - - - , . s Monthly Forced outage Rate l
+Molling 12 Month Average 1997 Fort Calhoun Goal (1.4Y4 60% .,.
45% ., 43 %
40%1 36% .
31 %
30% d -
25% ,
- 20 %
15%.
10%
10%.
5% w -
T
./
5% . - e :
0% 0% 0% 0% 0% 0% 0% 0% 0%
0%
96 Jan Feb Mar Apr May June July Aug i oct Nov Dec FORCED OUTAGE RATE The Forced Outage Rate (FOR) for the month of December 1997 was 0.00%. The forced outage rate for the previous 12 monthr (January 1997 through December 1997) was 7.00%. The 1997 year-to-date FOR was 7.00% at the end of December.
Energy Losses are described in the " Unit Capability Factor" indicator, page 2 of this report.
The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 1.4%.
Date Source: Monthly Operating Report Accountability: Chase Trend: Needing increased Management Attention 24
, i MonthlythitCapacityFactor
,_ Year 400ste Unit Capacity Factor
. thitcepecityFactorforCple 17 iM7 R:8 Gael (96.00%
110 % - Cyde 17 100 % . y A v - - - -
M. -
_ N : .- g ?
80%-
10% .
gw,s -4 : - - -
60% .
f -
'. 60% .
~
40%.
l 30% . I
!' 20% _ il l 10%+
l 0% I C 16 Jan Feb Mar Apr May June July Aug Sep Od Mw l Dec l I I
UNIT CAPACITY FACTOR t
This indicator shows the plant monthly Unit Capacity Factor, the Unit Capacity Factor for the current fuel cycle, the year to-date, and the 1997 OPPD Station goal.
Unit Capacity Factor =._._ Not Electrical Eneray Generated IMWH)
Max. Dependable Capacity (MWe) X Gross Hours in the Reporting Period Cycle 16 Unit Capacity factor was 76.8%.
At the end of December 1997, the Cycle 17 Unit Capacity Factor was 100.00.The Unit Capacity Factor for the last 36 months (January 1995 through December 1997) was 83.1. The 1997 Fort Calhoun annual goal for this indicator is 96.0%.
The year-to-date value is 91.9%.
Data Source: Monthly Operating Report Accountability: Chase Trend: Needing increased Management Attention l
l 25
L.'Y e Mrage MonHyEM
.-6 g, Rolling Amtage 96.1 % 99.2 % 99.1 % 97.5 % 97.5 % 98.7 % 98.3 % 99.2 % l 100 % - -
. 92A% - -
+ N "s-80% . N
66.7 %
73.6%
;
,,,. -~1 : : : <
60 % .
j 50% . 45.7 % ,
40% .
30% .
20% .
10% .
0% :
Jan Feb Mar Apr May June July Aug Sep Oct Nov Dec t
EQUlVALENT AVAILABILITY FACTOR This indicator shows the plant monthly Equivalent Availability Factor (EAF), the year-to-date average montnly EAF, the 12 month rolling average, and the OPPD goal.
The EAF for December 1997 was 99.2 %. The 12 month rolling average (January 1997 through December 1997) was 88.8%. The equivalent availability factor for the ,
past three years (January 1995 through December 1997) is 82.1%.
The Fort Calhoun Station goal for this indicator is an EAF of 93.0%. .
Data Source: Dietz/Mikkelsen (Managers / Source)
- Accountability
- Chase
- Trend: Needing Increased Management Attention l
i 26 l
t
m balety System .ktuations (INPo Definnien)
FCS Goal (0)
,_ Industry Upper 10 Pe;contile (0) 3.
- 2. l
. I 1
0 0 0 0 0 0 0 0 0 0 0 0 0 0 -
96 Jan Feb Mar Apr May June July Aug sep Oct Nov Dec l
UNPLANNED SAFETY SYSTEM ACTUATIONS -(INPO DEFINITION)
There were no WANO unplanned safety system actuations during the month of December 1997.
There were no WANO unplanned safety system actuations during 1996.
The 1997 Fort Calhoun goal for this indicator is 0, Data Source: Monthly Operating Report & Plant Licensee Event Reports Accountability: Phelps Trend: Positive g
Safety System Actuations (NRC Definition) ]
m FCS Goal (0) l
+ Critical Hours 10 _
1997 RFo 800 l 1700
_ 600 6 _
- 500 400 x 4 t
[300 )
_200 l
100 0 - > ! O J F M A M J J A S O N D UNPLANNED SAFETY SYSTEM ACTUATIONS -(NRC DEFINITION)
This indicator shows the number of Unplanned Ssfety System Actuations (SSAs), which includes the High and Low Pressure Safety injection Systems, the Safety injection Tanks, and the Emergency Diesel Generators. The NRC classification of SSAs includes actuations when major equipment is operated and when the logic systems for these safety systems are challenged.
There have been no unplanned safety system actuations in the last 12 months. The 1997 Fort Calhoun goal for this indicator is 0.
Data Source: Monthly Operating Report & Plant Licensee Event Reports (LERs) -
Accountability: Phelps Trend: Positive 28
.._. . _ . . _ . . . _ _ _ _ - . _ . . . _ . _ _ - . _ _ __ _._ _ _.._ ~. _ __ . _ _ _ _ _ . _ -
y, Gross Heat Rate
, .-, Year.404ete Gross Heat Rate Fort Calhoun Oosi 10.75 + .
4 E- 8 O
- S o o I
~
"~~
10.25 . h h
.e-- -
- - ~ - -
9.75 y 9.25 .
.Jan Feb Mar Apr May June July Aug Sep Oct Nov Dec 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 9,988 BTUlkWh for the month of
- December 1997. The 1997 year-to-date Average GHR was 10,129 BTU /kWh at the end of the month.
The GHR varies with fluctuations in river water temperature. In general, the GHR improves during the winter months and degrades during the summer. This is because the gross heat rate is not normalized to the design river water temperature of 60 degrees Fahrenheit.
The 1997 Fort Calhoun year-end goal for the Average GHR indicator is 10,166 BTU /kWh.
Data Source: Guinn/Schawe (Manager / Source)
Accountability: Phelps/Naser Trend: Positive 29
l i
1800 g-g g a &
99ggg1 g g g - _ _ ua- ., .:. ; ; . . ggg,ggggg l 1480 +
1440
+7he rm el output '
1440
- Fort Calhoun 1496 M W
- Ocel eTech Spec 1800 M W 1420 + Lim it 1400 1380 _
1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 i
DAILY THERMAL OUTPUT The thermal output graph displays the daily operating power level during December 1997, the 1500 thermal megawatt average technical specification limit, and the 1498 thermal megawatt Fort Calhoun goal.
Fort Calhoun Station (FCS) operated at a nominal 100% power level, unt'l December 19,1997, when reactor power was reduced to 95% to perform Moderator Temperature Coefficient (MTC) testing. Following completion of MTC testing, reactor power was returned to 100% reactor power on December 22,1997, through the end of the month. ,
Data Source: Guinn/Schawe (Manager / Source) .
Accountability: Chase /Short Trend: None 30 l
+ Monthy Equipment FOR
_a_ Equipment FOR/1,000 CrMical Hrs. (Rolling 12-Month interval)
Fort Calhoun Year End Goals (0.20) 2 7
1 1.7 5 ,.
1.5 -
1.25 -
1 0.7 5 +
0.5 9
1 0.25 1
- N / i N f- s; ; ;
O ;
Jan
=
Feb TMar Apr May June 1
Juh T
Aug Sep
\
oct Nov Dec a
EQUlPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS The Equipment Forced Outage rate per 1,000 critical hours for the Rolling 12 months from January 1,1997 through December 31,1997, was 0.24. The year-to-date rate per 1,000 critical hours for the months from January 1,1997 through December 31, 1997 was 0.24.
The 1S97 Fort Calhoun year-end goal for this indicator is a maximum value of 0.20.
Data Source: Monthly Operating Report & Plant Licenseo Event Reports (LERs)
Accountability: Chase /Phelps Trend: Needing increased Management Attention 31
1 CHEMISTRY ACTION LEVELS EXCEEDED a Evert Days .-p Average Event Days 6 6 i 6 - -
6.
- 4. -
3.
=
1 / m ,
V WT ff( & & o o o i4 i 4
$ {~
f t
i2 !
~
4 I
2 4 [
~ E f
CHEMISTRY ACTION LEVELS EXCEEDED - EVENT DAYS The Chemistry Action Levels Exceeded indicator tracks the number of days in which chemistry parameters exceeded a corresponding action level for the reporting month, as well as a 12-month average of days an action levelis exceeded. ' e parameter action levels are delineated in Chemistry procedure CH AD-0003,' Plant System Chemical Limits and Corrective Actions."
An action levelis considered to have been exceeded for the purpose of this Indicator, whenever the parameter exceeds the CH AD-0003 action level for the current system mode, with the exception of the Steam Generators during Mode 1.
The Steam Generators are considered to have exceeded an action levelin Mode 1 when the plant power is greater than 30% and the power is changing less than 5% per day.
The number of event days can exceed the number of days in a month since each event is counted separately and there can be multiple events per day.
The 1997 Fort Calhoun goal for this indicator is the 12-month average of two event days per ,
month. There is no goal established for the number of event days per individual month.
Historical data is usM to calculate the monthly average event days. The 12 month average ,
was calculated by dividing the number of event days by the number of preceding months, until twelve months were reached.
There were O Event Days in December.
Data Source: Chase / Hamilton (Manager / Source)
Accountability: Hamilton Trend: Positive 32
i i% Hours Out of t.imit i 6.00 ,. CFDGoal(5%) l 5.00 .
4.00 .
3.00 .
., 2.00 + 1.61 1.48 1.21 .-
1.08 _
1.00 - -
1 0.00 0,00 c 00 0.00 0.00 0.00 0.00 0.00 I 0.00 # .
l I k f fk PRIMARY SYSTEM LITHlUM % HOURS OUT OF LIMIT The Primary System Lithium Percent Hours Out of Limit indicator treeks the hours per month that the primary system lithium is out of specification.
The Primary System Lithium Percent Hours Out of Limit was 0.00% for the month of December 1997.
The 1997 Fort Calhoun Station monthly goal for this indicator is a maximum of 5% hours out of limit.
Data Source: Chase / Hamilton (Manager / Source)
Accountability: Hamilton
- Trond: Positive 33
COST Goal: Operate Fort Calhoun Station in a manner that cost effectively maintains nuclear generation as an economically viable contribution to OPPD's bottom line. Cost consciousness is exhibited at all levels of the organization.
6 34
+ Actual + Budget F'Lan 3.80 3.40 -
' ^
a
^
2.00 .
% ._ - - ~
2.60 .
, 2.40 3.20 2.00 aaa aa = = = === = =
i 1e1148iiI4%i}I)1aggggg
, ~ ~
CENTS PER KILOWATT HOUR November 1997 The purpose of this indicator is to quantify the economical operation of Fort Calhoun Station.
The Cents Per Kilowatt Hour indicator represents the budget and uctual cents per kilowatt hour on a 12 month rolling .vorage for the current year. The basis for the budget curve is the approved 1996 and 1997 revised budgets. The basis for the actual curve is the Financial and Operating Report.
The December 31 amounts are also shown for the prior years 1992 through 1996, in addition, the report shows the plan amounts for the years 1998 through 2002 for reference. The basis for the dollars are the Nuclear Long Range Financial Plan and the 1997 Corporate Planning and Budget Review. The basis for the generation is provided by Nuclear Fuels.
The 12 month rolling average unit price period of ( December,1996 through November,199T) tveraged above the budget due to 12-month rolling expenses exceeding the budget and the 12 month budgeted generation falling below budget. The 12 month rolling average (12/96 through 11/97) is 2.89 cents per kilowatt hour.
The year to date average is trending in a downward direction.
Cents per KWH Jan Feb Mar Anr May Jun Jul Aun Set Oct Nov Dec Cudget Y.T D 2.83 2.67 2.58 2.55 2.44 2.46 2.49 2.47 2.49 2.48 2.46 2.44
, Actual Y T 0 2.89 2.60 2.54 2.75 2.99 2.90 2.83 2.79 2.79 2.73 2.72 0.00 NOTE: This information normally lags by a month due to the rhort tum around required for processing.
Data Source: Lounsberry/ Dent (Manager / Source)
Accountability : Lounsberry Trend: Needing increased Management 35
1
~
DIVISION AND DEPARTMENT PERFORMANCE INDICATORS Goal: Achieve high standards at Fort Calhoun Station resulting in safe, reliable and cost effective power production.
36
m Corrective Maintenance gagg Preventive Maintenance
, i Non Corrective /Plantimprovements Fort Calhoun Goal (260) 742 729 628 713 763 J 682 624 674 636 644 600 i 200.
100 _
0, a- + + - + 4. . ~ ~ a- -_
a Non-outa0e Maintenance Work Document Backlog g Tota'PMos Pa at Com ple tion Com pleted 88 6a 0 4 o._ -_ L w not Compieten nney nury nuty nmy nuty 1 2 3 4 5 MAINTENANCE WORKLOAD BACKLOG This indicator shows the backlog of non-outage Mdotenance Work Documents remaining open at the end of the reporting month .also includes a breakdown by maintenance classification and priority. The 1997 goal for this indicator is 250 non-outage corrective maintenance MWDs. The current backlog of corrective MWDs is 219 To ensure that the MWD backlog is worked in a timely manner, non outage maintenance completiori goals have been established as follows:
GDal Priority 1 Immediate Action 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Priority 2 Urgent 5 days Priority 3 Operational Concerns 21 days Priority 4 Routine Corrective 90 days Priority 5 Non Essential 180 days The 1997 Maintenance workload backlog goai was revised from a maximum 350 to 250 in September 1997 Data Sourc : Chase / Johnson (Manager / Source)
Accountabi!ity: Chase /Faulhaber Trend: Positive SEP 36 37
Ratio of Pr;ventive t) Tot:1 M:Intonance 90% , 84 %
7 77% 74 % 76%
80% a 70%
74 %
70% cog 6W 61 %
60% . 52%
60 % ,) 3 i M]j i h
40% 1 l.. 9 30% 1 "
j 20% ) C
! 1c% 4 0% i_ l - . _ . . _ __ _._
l '
l !i f ! I I .
l $ I l 8 I $
gggy Preventive M aintenance item s Ove rdue Fort Calhoun Goal
~
6.80%
8% 1 4.09%
! 3% i 2.50% 2.40%
's% i , ?
gg 0.63% 0.46% 0.00% 0.56% 0.58 % 0.20% 0.30% 3 0% u:s - s- m. _ ,_a Am _ _ _
4 I I I I j k I I 5 I 3 j 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 ratioo: preventive to total maintenance was 70% for the month of December 1997.
The lower graph shows the percentage of scheduled preventive maintenance items that are overdue. From the period of November 15th thru December 15th there were 17 PM's were completed late or not completed out of 490. ,
The 1997 Fort Calhoun monthly goal for the percentage of pieventive maintenance items overdue is a maximum of 0.5%
Data Source: Chase / Johnson (Manager / Source)
Accountability: Chase /Faulhaber Trond: Adverse SEP 41 & 44 3S 1
w_-__,-._. _ - - - , - - - - - - - _ - - - - _ , _ - - - _ . . - - . - , - - - , _ - _ _ - - - - _ - - - - _ . ~ _ - , , , , - - - _ - _ _ _ _ . - - _ - - - - - - - - - - . - - - _ - - - , . , - _, - - . _ - - _ _ - - - - - _ - - _ _ - - , _ . _ _ -
mNo. M aintentence item s com pletes
- % Identified et Re0eet 400 808 60%
y _
7 600d gyg 160%
400- 8
42 ,40%
to
$60 246 262 30%
gg,
,00 i.0 . 0%
100 , , 1.0 %
Jan Feb War A pr May June July Aug Sep Cet Nov Dee l m Rework as h'entified by Craft Fort Calhoun Goal (<3%)
3%
~
$9% 1 %
B 2%
1.6%
m 18%
16%
1.2%
1.0% 09%
g g 0% .- -,- .-
M_ , , m. .
Jan Feb Mar Apr May June July Aug Sep Oct Nov Dec PERCENTAGE OF TOTAL MWDs COMPLETED l PER MONTH IDENTIFIED AS REWORKIREPEAT This graph Indicates the percentage of total MWDs completed per month identified as
+
rework. Rework activitins are identified by maintenance planning and craft.
This indicator is calculated from the 15th of November through the 15th of December 1997, due to the delay in closing open MWDs at the end of each month.
The Fort Calhoun monthly goal for this indicator is <3% A dotalled review is conducted of rework items each month to identify generic concems.
Data Source: Faulhaber/ Johnson (Manager / Source)
Accountability: Chase /Faulhaber Trend: Positive 39
i i MarthlyOertime(OnUne) e VT0MarthlyAmorage(OnUne) 25.0% ,_
21 4 %
20.0% .
. 16.1 % j 15 5 ._ !
9.8%
11f4 gg, 10.0% .-
6W. f + - a .
5M._* 4%
- 1.7%
0.0% ; y n ;
OWo i
Jan Feb Mar Apr May Jm Jd Aug Sep Oct Nw Dec MAINTENANCE OVERTIME The Malvenance Overtime Indicator monitors the ability to perform the desired maintenance activities with the allotted resources.
The percent of overtime hours with respect to normal hours was reported as 9.9% for the month of December 1997.
The 1997 Fort Calhoun monthly "on line" goal for this indicator is a maximum value of 10 %
Data Source: Chase / Johnson (Manager / Source)
Accountability: Chase /Faulhaber Trend: None 40
..___m.._.__ _ _ _ _ _ _ . _ . _ _ . _ . _ . . . _ .
Human Performance CRs (Maintenance) 20 18 .
18 -. I 14 14 .-
l f 12 --
. 10 -
h a '
g 8._ 7
- I 8.. 5 4 4 4._ 3 il 2--
0 -
May June J uly Aug Sep Oct Nov Dec PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)
This indicator shows the number of Condition Reports related to procedural noncompliance incidents assigned to the Maintenance Department.
Data Source: Faulhaber/Burggraf (Manager / Source)
Accountability: Chase /Faulhaber Trend: None SEP 15,41 & 44 i
41
j + % TK5fDDS 4% bP58FDffl
+ % Total ooS Total % oos Goal
$4% ,
1 12%y i
10% .'
8% .
6% +
4% .
N.
2% ;
3 .
.% . = . = . . = = =
~ a a a a a a a 4 m a
! $ $ I 4 4 I A $ $ $
IN-LINE CHEMISTRY INSTRUMENTS OUT4F-SERVICE This indicator shows the percentage of hours the in-line chemistry system instruments are inoperable for the reporting month. The chemistry systems involved in this indicator include the Secondary System and the Post Accident Sampling System (PASS). At the end of December 1997, the percentage of hours the in-line chemistry system instruments were inoperable was 1.13%. The following instrument (s) were out of service for the current month:
- 1. % PASS HOURS OUT OF SERVICE: None
- 2. % NON-PASS HOURS OUT OF SERVICE:
S/G "A" sodium, A1-110 H2 analyzer.
O k Source: Chase /Ostien (Manager / Source)
Accous '. ability: Chase /Skiles Trend: Positive 42 1
m Wr.cto Produced Es:h Month (Kilogr:ms)
Fat Calhoun Monthy A6 tgo Goal (150 kilogr:ms)
+ Federal & State Monthy Limit (Max.of 100 kg)
Soo 46oh 1 4004 3s01 sooj asoy
~
200 1 150 !
100 l
so ,
of ; ,
i 4 $ $ k [ f k I I E $ $
HAZARDOUS WASTE PRODUCED This indicator shows the total amount of Hazardous Waste Produced by the Fort Calhoun Station each month, the monthly average goal and the monthly average total for hazardous waste produced during the last 12 months. This hazardous waste consists of non-halogenated hazardous waste, halogenated hazardous waste, anc other hazardous waste produced.
During the month of December 1997,0.0 kilograms of rion-halogenated. 0.0 kilograms of halogenated and 0.0 kilograms of other hazardous wbste were produced.
Hazardous waste is counted based upon a full drum of waste.
t
. SPECIAL NOTE:
FCS has recently revised it's classification with the State of Nebraska.
Due to our reduced waste generation over the past several years, we have revised our status from SMALL QUANTITY GENERATOR (</1000 kg/ month) to a CONDITIONALLY EXEMPT SMALL QUANTITY GENERATOR (<100 kg/ month).
Data Source: Chase /Shubert (Manager / Source)
Accountability: Chase / Hamilton Trend: Positive 43
, , Contaminated Radiation Controlled Area Fort Calhoun Goal (5*/4 10%
7 l
9% 1 s% . _ _ _ _ _ _ _ _
7%. _
s% .
5%. \ _
4% -
3%_
2% .
1%_
0% - >
j 4 $ $ I I j i I I 3 $ $
I CONTAMINATED RADIATION CONTR%.i ED AREA .
This indicator shows the percentage of the Radiologically Contro'!ed Area that is contaminated based on the total square footage. The 1997 monthly non-outage goal .
was revised from a maximum 10% to 5.0% contaminated RCA in May 1997. This -
indicator has an Adverse Trend since it exceed the FCS goal.
'At the end ,'f December 1997, the percentage of the total square footage of the RCA that was contaminated was 4.8%.
Data Source: Chase / Williams (Manager / Source)
Accountability: Chase /Gebers l Trend: None SEP54 j 44 l
l
+ Poor Radiati:n W;rker Practices l Fort Calhoun Goal (<10)
%_. Tc'cl PRWP for 1997 16 T
. 14 12 ,
l
--.. _. /
l f 6.
4, 2
2
- 2. 3 1 1
, 0- -
Jan Feb Wr Apr Wy June July Aug sep oct tev Dec RADIOLOGICAL WORK PRACTICES PROGRAM The Radiological Work Practices Program Indicator shows the number of Poor Radiological Work Practices (PRWPs) which were identified during the reporting month.
The number of PRWPs which are identified each month should indirectly provide a means to qualitatively assess supervisor accountability for their workers' radiological performance. This indicator needs increased mar,agement attention due to a 3 month
-Increasing trend of poor radiation worker practices based on YTD.
During the month of December, there was O PRWP idantified.
There have been a total of 10 Poor Radiation Worker Practices in 1997.
The1997 Fort Calhoun Station year-end goal foi PRWPs was revised by the Radiation Protection Department in October 1997 from a maximum value of <15 to <10.
Data Source: Chase / Williams (Manager / Source)
Accountability: Chase /Gebers Trend: None SEP 52 45 a
O Documonts Schodulad for Revl3w g Docum ent Review s com plete during m onth g Documents Overdue 400__ -
~
350 + -
300 _ _
250 + _ _
2001 1
150 1 100 .,
_ b_b. ! E kBL_ B. d ,
S 2 E R E b F t o 9
,E u. s < z < 4" o z z 4 E 1997 DOCUMENT REVIEW The Document Review indicator shows the number of completed, scheduled, and overdue (greater than 6 months past the scheduled due date) blennial reviews for the reporting' month. The documents reviews are performed in-house and include Special Procedures, the Site Security Plan, Maintenance Procedures, Preventive Maintenance Procedures, and the Operating Manual.
During December 1997, there were 321 document reviews scheduled, while 33 reviews were completed. At the end of the month, there were 98 document reviews more than 6 months overdue There were 6 new documents initiated during December 1997.
Data Source: Chase /Plath (Manager / Source)
Accountability: Chase /Skiles Trend: None SEP 46 46 l
O Syst:m F:llur:s t) Non System Faltures 27 25 .5
-l 21 18 13 13 12 12 12-Jan Feb Mar Apr May June J uly Augurt Sep Oct Nov Dec L
LOGGABLE/ REPORTABLE INCIDENTS (SECURITY)
The Loggable/ Reportable Incidents (Security) Indicator is depicted in the above graphics display. The graph depicts the total number of loggable/ reportable non-system failures and system failures which occurred during the reporting month.
During the month of December 1997, there were 14 loggable/ reportable incidents identifie( tem failures accounted for 86% of the total failures. One security force error ano c..s unattended security badge accounted for the non-systems failures during the reporting month. The security organization continues to focus on security forca errors. For the year 1997, total failures declined 21% System failures declined 18%
. while non-system failures declined 31%
This indicator provides information on security performance for Safety Enhancement Program (SEP) Item No. 58.
Data Source: Sefick/Woemer (Manager / Source)
Accountability: Sefick Trend: None SEP 58 47 m
, . Temporary M:difications >1-cycle cid (RFO rcquircd f:r rcm: val) g:;gg Tcmporary M:dificctions >6 mtnths cid (R:m vable en lin2) .
Fort Calh un Goals f:r >1 cycle cnd >6 m:nths cid !
3 3 l 3 ~ *'
T l i 2 2 2 2 22 2 2 2 2 2 2 21 4 q - _ -
l 1.51 3 3 3 3 f 3 3 3 3 3 3 3 h
(
Ek +5 $ d M ap l 9
- b. s + m > l l-7
- S 4 2
= a 4 2 e e e 4 m e g i 2
e o
4 3 TEMPORARY MODIFICATIONS ,
This indicator provides information on the number of Temporary Modifications (TMs) greater than one fuel cycle old requiring a refueling outage (RFO) for removal and the nuraber of temporary modifications removable on-line that are greater than six monthc old. The 19S7 Fort Calhoun monthly goals for this ladicater are zero.
There are currently two (2) temporary modifications that are greater than one-fuel cycle old requiring an outage for removal. TM 96-014, Reactor Cociant Gas Vent Line Pressure High Alarm. was installed April 22,1996. Repairs for this TM were completed during the 1996 RFO, but the reactor coolant gas vent line pressure is still high. MR-FC-97-011 was initiated to solve this problem and currently DEN is planning the modification. MR-FC-97-011 is expected to be completed during the 1998 RFO. TM 96-018, Equipment Drain Header Soft Rubber Patch was installed June 16,1996.
MWO 963468 has been written to replace the piping and is currently scheduled for the 1998 RFO.
At the end of December 1997, there was one (1) TM installed that was greater than six months old that could be removed on-line. TM 96-039, Railroad Siding / Corridor 26 Deor, was installed November 1,1996. EAR 97-219 will close this TM. EAR 97-219 requires System Engineering review and approval. EAR 97-219 is expected to be completed by May 1,1998.
At the end of December 1997, there was a total of 14 TMs installed in the Fort Calhoun Station. Ten (10) of the 14 installed TMs require an outage for removal anc' 4 are removable on-line. In 1997, a total of 18 TMs have been installed. At the end of -
December 1997, there were three (3) procedural or maintenance configuration alterations (PMCAs)(a special classification of TM) installed in the Fort Calhoun Station using PRC approved procedures which are controlled by Standing Order O-25.
Data Source: Phelps/ Frank (Manager / Source)
Accountability: Phrlps/ Core Trend: None SEP 62&71 48 1
i i ThalNbd5ceianPaclopsOpen RrtCalhounYeared(bal(68) 80 . n ;
n ,
n n <
{ ~ ~ ~
75 1 M - "
n <
70 . "
85 .
- 00 I f 55 _ - , I .
' : y 96 Jan F% Mar Apr inry Jun Jid Aug Sep Oct Ptw Dec l
OUTSTAND!NG MODIFICATIONS This indicator shows the total number of Outstanding Modifications (excludina outstandina modifications which are orocosed to be cancelled).
Reporting Cateaorv '90 '94 .'96 '91 Month
'.a5 'QB .'89 Form FC-1133 Backlog /In Progress 0 0 0 0 0 0 0 i
Mod. Requests Being Reviewed 0 0 0 0 0 8 8 Design Engr. Backlog /In Progress 0 0 0 0 6 5 11 Construction Backlog /in Progress 1 0 4 5 13 0 23 Design Engr. Update Backlog /In Progress _5 5 _f .2 _Q _Q . 18
Totals 6 5 10 7 19 13 60 (Outage + OnUne) (2+4) (3+2) (8+2) (2+5) (15+4) (10+3)
At the end of December 1997,28 modification requests have been issued this year and 8 modification requests have been cancelled. The Nuclear Projects Review Committee (NPRC) has conducted 76 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) has completed 22 backlog modification request reviews this y:ar.
The 1997 yee:-end Fort Calhoun goal for this indicator is a maximum of 68 outstanding modifications.
Data Source: Jaworski/ Walling (Manager / Source)
Lounsberry/Betek (Manager / Source)
Accountability: Lounsberry/Jaworski Trend: Positive 49
98 , I A A s A c e s tela s l o g in e e rin g C lo s e e s t . N e t ta C te s s e e t O 3E O OfN
'8
- 31 II "
14 14 gg
, '__A__; e !. 2 ; .a a 1 B O ct Nov D ec O ct Nov D ec O ct New Dec Oct N ew Dec
- c. W e n tn a 3 6 W e a th e 6 13 W e a th s att Wentas O Engineering Response a Closecut(SE) 30 23 sol '
10 d 1 2 0 1 1 3 1 3 1 0 0 0
I
" I I Priority 0 Priority i Priority 2 Priority 3 Priority 4 Priority 5 Priority 6 6 6 E A R's 41 Closeout on o ve rd u e 9 S c he d ule Reponses 56.9 % 35.3%
w g
Response
h s.
107 9 O ve rd ue Clo s e cuts 7.8%
ENGINEERING ASSISTANCE REQUEST BREAKDOWN This indicator shows a breakdown of the number of EARS assigned to Design Engineering and System Engineering. The 1997 year-end goal for this indicator is a maximum of -
140 outstanding EARS.
The Total EAR breakdown is as follows: -
EARS opened during the month 19 EARS closed during the month 35 Total EARS open at the end of the month 116 Data Source: Jaworski/Livingston (Manager / Source)
Accountability: Phelps/Jaworski Trend: None SEP 62 50 I
3' 237 ter 67 CONST. OUT
, DEN >6 ne O'3 M0"D8
$1% y 23% 74 in 's 14 %
q
,%,. ^<
s .[
,. W5iN5'~~~
, e lECN STATUS - CVERALL BACKLOG a Backlogged O Re ceive d a Com pleted 0 3 Months 3 6 Months Seu 46 33% 22%
960 H8 118 M7 08 112 102
~
17 "4.; ,,"
.0 11 a w t
,"- Su,.
n
, a w D, , ,1.
+ ,.
50 J- J u ly Aug
- , .nvm Sep Oct New Det SW&
250 ,. 7 200 7 3 4 Months 70
,,,g ,,u,,,n, 150 ; , stas 100 1.85 et 84 77 86 74 o.s u onine i w1 2 10 mio - - 1.2 %
50 4 12 N 13 s s.c 1716 $ 1613 ?3, 0 an m .J:cs lm _.:.; i . ' % .,
July Aug Sep Oct Nov Dec SYSit-MEN 3N HN3 l00 .
ISO 1211 217 213 220 227 10 ga 204 t00 I r 207 3 Months 3 6 Months l50 1 !' ~
me M onths dd%
4.4 %
91.2 %
1001 A13 +
5 16 13 3
h; 50 1 4 128 6 ,
8 5 g 2 3 0 L 6 x- ,: m - + . - --
--- h-July Aug Sep Oct Nov Dec PROCURENENT/OONSTUGTION 250 '
O.3 M onths 3 6 Months 300 1 15.8% 23.7 %
150 4 >6 M onths 100 HM \
4, 26 2631 33 443 ,17 M 1934 g SO b7 @ 22 OT1 011 fb, fi-n o
i
~
July AuS Sep Oct Nov Dec -
lD R A FTIN G /C LO S E O U Tl ENGINEERING CHANGE NOTICE STATUS Data Source: Jaworski/Livingston (Manager / Source)
Accountability: Jaworski/Phelps Trend: None SEP62 51
=
1
_. 1
es 9e !
s$ P riorley P 'Y l in,
/'
&h w j_ k J 24 Y * 'Y
$klTYPt Total Open ECNs a 441 3"4 Total Open ECNs = 441
$7%
o DE N Cieseovi or Draftsa0 N61 Com plete E
g O$(*'7e*EI"n'oIni N
- Ee pieetting koi Com 7M'".*N$"i[$NE*c*oIUin$tdNo'tEINI'i plete 24 14e , or Pnanty1&2 82 $ n, ny 10
" ' f. p le F 24 2' n
"4 2.
c7 4
22.4 % prientysas m
ll: e , . ..
7 " n ;n u Qn*
40 4
- I 20 i ?! Il 48 52 44 45
"* '""u. u, !I!... C.%e, "" "
300 , " ,,
350 { _2p 2M N 249 P r' '"
P rio eity
$46 200 . Il 3 15%
29 150 4' 1 E! i d by US E2 E5 141
, M er i l'? *i P rio rity 33 i 30 28 27 as g %& Q 4.'
h 42 39 35 34 k Jul97 Aug t' Sep97 Oct 97 Nov-97 Dec-97 SubsttJe 5trplacement item ECNs Open i D B6 1 '
85 4, a 4, 80 76
- 7
[]37 9
,g u
10 16 a u'#
s '" us " .'Y,8'd
.. s a s2 -
"I 3 46 so k, ~'
I ! '
,,{E
OL 26 27 L
3s 33
</ MGLD#
~
July Aug Sep Oct Nov Dec Document Change ECNs Open ENGINEERING CHANGE NOTICES OPEN Data Source: Jaworski/Livingston (Manager Source)
Accouritability: Phelps/Jaworski Trend: None SEP 62 52
. . startup
{
m s hutdsw n m Operations
. .o .. Industry Average Trend 2
T 1.s
- o o ,6 O -.o o...~o..
...o.... .. .a oo ....o.ona."".o.....a 9 , .1 93 2 93 3 93 4 94 1 94 2 94 3 94 4 t s.1 96 2 96 3 95 4 Ye a r.Q u a rte r t
SAFETY SYSTEM FAILURES This indicator illustrates the number of NRC Safety Systen: Failures as reported by the Nuclear Regulatory -
Commission's Office for Analysis and Evaluation of Operational Data in the annual" Performance indicators for Operating Commercial Nuclear Power Reactors" report. .
The following safety system failures occurred between the 2nd quarter of 1992 and the 1st quarter of 1995:
1st Quarter 1993: The SG low pressure scram signal block reset values, for all 4 channels of both SGs, were greater than the allowed limits. This rendered the scram input inoperab!e at certain operating conditions.
2nd Quarter 1903: A section of the piping configuration for the borated water source of the safety injection system was not seismically qualified. This could ' nave resulted in a failure of the system to meet design requirements during a seismic event.
4th Quarter 1991: 1) During surveillance testing, both PORVs for the LTOP system failed to open during multiple attempts / The fa lures were a result of differential expansion caused by a loop seal. excessive venting line back pressure, and cracked valve disks; 2) Calibration errors of the offsite power low signal relays could have prevented nffsite power from tripping and the EDGs from starting in the required amount ef *k:ie during a degraded voltage condition: 3) P,oth AFW pumps were inoperable when one was removed from service for testing and the control switch for the othe, pump's steam supply valve was out of the auto position.4) Only one train of control room ventuation was placed in recirc when both toxic gas monitors became inoperable. Later during surveillance testing,
, the other train auto. started and brought outside air into the control room for & .'y-minute period.
1st Quarter 1994: A design basis review determined that an ESF relay could result in loss of safety injection and
_ spray flow, due to premature actuation of recirculation flow.
4th Quarter 1994: An accident scenario was identified that could result in the inoperability of both control room air conditioning units. Following certain accident conditions, CCW temperature could rise causing compressor rupture '
disc failure and a release of freon.
There were no safety system failures since the 4th quarter of 1995.
Data Source: Nuclear Regulatory Commission Accountability: Chase Trend: None 53
O Total Nqualif 6cition Trcining Hours !
g Simulator Training H:urs g Non-Requalif6 cation Training Hours O Number of Exam Failures 33 33 32 32 30 .
25 22 20 qg 15 4 4 14 7 4 12 12 10 8 g g 6 66 8 5
3 0 0 0 0 0 0 0 9 i , _ ~ - ,- +
Cycle Cp e Cycle Cycle Cycle Cycle Cycle Cycle Cycle
$8 5 96 7 97 1 97 2 97 3 97 4 97 5 97 6 97-7 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 grapn are a subset of the total training hours. Non-Requalification Training Hours are used for AOP/EOP verification & validation, INPO commitments, GET, Fire Brigade, Safety _
Meetings, and Division Manager lunches.
Exam failures are defined as failures in the written, simulator, and Job Performance Measures (JPMs) segments of the Licensed Operator Requalification Training.
Note: Rotation 97-6 was the Annual Licensed Operator Requalification Examination ,
rotation for 1997. There were Three (3) individual and one (1) crew simulator exam failures during rotation 97-6. All remediations were c:)mpleted prior to the end of the exam week. .
Conceming Reactor Operator and Senior Reactor Operator Candidate exams:
Currently, there is no Initial Licensed Operator training class in session.
Data Source: Conner /Guliani(Manager / Source)
Accountability: Conner /Guliani s Trend: None SEP 68 54 l
. =
r o SRO Ex ms Administersd D SRO Exrms Pcas:d O RO Exams Administered a RO Exams Passed 10 7
l i
77 77 77 77 l
- l l i i I !
I
$l l i
l 0000 00 00 00 00 0000 0000 0000 0000 0000 0000 0000 0
Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec LICENSE CANDIDATE EXAMS - 1997 This indicator shows the number of Senior Reactor Operator (SRO) and Reactor Operator (RO) quizzes and exams taken and passed each month. These internally administered quizzes and exams are used to plot the SRO and RO candidates' monthly progress.
During the month of December 1997, there were no (SRO) or (RO) training classes in
, session. The next license class is scheduled to begin in July,1998.
Data Source: Conner /Guliani(Manager / Source)
Accountability: Conner /Guliani Trend: None SEP 68 55 9
+ l
% TotalOb Fbady to(bse 3500 .
3000 +
2500.
M
- *+
1500.
f .
1ooo k .: : ,
SM- _ _ _
{' y ~N o!
N., : .= =
k k B a k u a u a u k h b $ $k hhE hh CONDITION REPORTS BY LEVEL This indicator shows the total number of Condition Reports which are Closed, Ready to Close, Open and the Total Number of Condition Reports to date.
Level 1 Level 2 Level 3 Level 4 Level 5 Level 6 Total Open 20 15 101 612 20 210 980 Closed 22 15 164 1641 558 460 2860 212 condition Reports are classified as READY to CLOSE.
Data Source: Tesar/Burggraf (Manager / Source)
Accountability: Chase /Gambhir/ Bishop Trend: None 56 l
1
0T*8 0*** M W D HOLDS c%dy to wat System Ungineering Parts 1880
, $m Planner 7*/.
in 4 10%
'" 30%
Seen j
$= ,4 "j,-
?
N- w M ECNs d%
[3 3 "
T2] 7 n m7 eoe.7 % ,7 o247 %.7 o.oer MWD PLANNING STATUS (CYCLE 18 REFUELING OUTAGE)
This indicator shows the total number of Maintenance Work Requests (MWRs) and Maintenance Work Documents (MWDs) that have been approved for inclusion in the Cycle 18 Refueling Outage. This graph indicates:
Parts Holds - Planning Complete, Awaiting Parts System Engineering Holds - Awaiting System Engineering input to Planning 3 l
Planner Holds - Maintenance Planner has not completed planning the work j package.
ECN Hold Awaiting Substitute Replacement items ECN from DEN.
In Review Planning Complete awating SE, ISI and QC review.
Data Source: Chase / Johnson (Manager / Source)
Accountability: Chase / Herman Trend: None SEP 31 57
I gLAST aTHis DFOR SCHEDULE 90 80 a 70 g E z
l ,o 3 3 S S S S S S SS S I
" l1 !! ! ! !! 3"! ! I! [
gi 1 j -
"" " ^'S""" "S
"""""SA"GMi#w"alFJPa#T 1998 OUTAGE PROJECTS STATUS REPORT c ountabIty: el /BI o ter Trend: None SEP 31 58 j
12/27/97 '
ks' Cb 5 " h 11/27/97 h g g 10/28/97 + N "
t' :, t : : -
7/3 & 97 E $ s s s 6/30,7 + $ 5 g
, Actualr4CDate 4/1/97 j u W NM
, 3/2/97 1/31/97 .
-1/1/97 .
I PROGRESS OF 1998 REFUELING OUTAGE MODIFICATIONS CYCLE 18 This indicator shows the status of Modifications approved for installation '.. ing the Cycle 18 Refueling Outage (March 1998).
The goal for this indicator is to have all modification packages which were identified prior to March 20,1997, PRC approved by September 15,1997.
December 1997 Modifications added: 0 Deleted = 0 O
Data Sour:e: Jaworski/ Walling (Manager / Source)
Accountability: Gambhir/Jaworski Trend: None SEP 31 59 0
. Actual PRC Date , Target PRC Date 2/5/98 , s 12/17/97 .. e- e imaS7 . .
n'as7 .
7/20/97 "lsl 7
5/31/97 h .
4/11/97 moS7 ,
1/1S7 .
$E$$
!hbh mm i PROGRESS OF CYCLE 18 0UTAGE MODS AND ECN'S ADDED TO '98 REFUELING OUTAGE AFTER FREEZE DATE This indicator will show the status of Modifications and ECN's approved for installation during the Cycle 18 Refueling Outage. The goal for this indicator is to have all modification pr.ckages PRC approved by their target date.
December 1997 e
Modifications /ECN's Added = 0 Deleted = 0 Data Source: Jaworski/ Walling (Manager / Source)
Accountability: Gambhir/Jaworski Trend: None SEP 33 60 l
,,.,-m--,r...,------ . , - - , - - - , , - - - .
No 1997 On Line Modifications Currantly Approved
. PROGRESS OF 1997 ON-LINE MODIFICATION PLANNING This indicator shows the status of modifications approved or in review for approval for on line installation during 1997.
The goal for this indicator is to have all modification packages PRC approved by their scheduled date, December 1997 Modifications Added: 0 Deeted: 0 4 Data Source: Jaworski/ Walling (Manager / Source)
- Accountability- Gambhir/Jaworski Trend
- None SEP 31 61 1
-J
l 9
5 ACTION PLANS Y
62
- h. .
ACTION PLANS l
This section lists action plans that have been developed for the perfomiance indicators cited as Adverse Trends during the month preceding this report. Also included are Action Plans for indicators that have been cited in the preceding month's report as Needing increased Management Attention for three (3) consecutive months.
In accordance with Revision 5 of NOD-QP-37, the following performance indicators would require action plana based on three (3) consecutive months of performance cited as "Needing increased Management Attention":
Fuel Reliability Indicator (page 9) \
Based on the current number of predicted fuel failures and expectation that future fuel failures will be identified, Fuel Performance functional area performance is considered to be POOR for 4th quarter of1997. The plant is currently in " Action Level 4" in accordance with Standing Order O-43," Fuel Reliability Action Plan," based on the increase in the number of core average power failed rods (24) which is considered conservative for entering Action Level 4.
Ratio of Preventive to Total Maintenance Preventive Maintenance Items Overdue (page38)
Standing Order M-2, " Preventive Maintenance," requirements are being revised to provide additional guidance on " Overdue" PM tasks. Reports are being issued to all '
responsible work groups that have "Past Due" PM tasks. In addition, a two week forecast report is being issued weekly to project PM tasks that are approaching the scheduled
" Late Finish Date."
Maintenance Workload Backlogs (page39)
The Rams project is currently in progress. The purpose of this project is to stream line
- he maintenance process at Fort Calhoun Station. This will significantly improve our
" WRENCH TIME" by removing inefficiencies and related hurdles that prevent work from being accomplished in a timely manner. In addition, it is expected that schedule
.npliance will also increase and our maintenance backlog will decrease. This project is svneduled to be fully implemented by September 1998.
63 l
PERFORMANCE INDICATOR DEFINITIONS PERFORMANCE INDICATOR INDEX manual scram sv4tches or, manual turbine trip switches (or push-buttons) provided in the main This ind4cator index 4 calculated from a welghted control room.
combinabon of eleven performance indicator values, which indude the fonowing: Unit Capability Factor, Unplanned 4) Crtucal means that during the steady-state Capability Loss Factor, HPSI, AFW, Emergency AC Power conditon of the reactor prior to the scram, the System, Unplanned Automate Scrams, Collectve Radi tion effectve multiplication (k , ) was essentally equal Exposure, Fuel Rehabihty, Thermal Performance, Seconchry to one.( Page 4 )
System Chemistry, and industrial Safety Acddent Rate. ,
( Page vi)
HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE UNIT CAPAtslLITY FACTOR <
The sum of the known (planned and unplanned) unavailable The rabo of the avaltable energy geneObon over a given hours and the estimated unavaitat le hours for the high bme penod to the reference energy gensration (the energy pressure safety injecbon system for the reportng period that could be produced if the unit were operated divided by the enhcal hours for the reportng period continuously at full power under reference ambient muthplied by the number of trains in the high pressure safety condibons) over the same trne period, expressed as a injecton system.
percentage. ( Page2 )
INDUSTRIAL SAFETY ACCIDENT RATE . INPO UNPLANNED CAPABILITY LOS$ FACTOR This indicator is defined as the number of accidents per 200,000 man-hours worked for all utihty personnel The rano of the unplanned energy losses dunng a gnren penod of permanently assigned to the station that result in any of the time, to the teference energy generauon (the energy that could be following:
produced if the unit were operated continuously at full power under reference ambient condiCons) over the same time penod, 1) One or more days of restricted work (excluding expressed as a percentage. ( Page 3 ) the day of the accident);
- 2) One or more days away from work (exduding the day of the accident); and UNPLANNED AUTOMATIC REACTOR SCRAMS PER 3) Fatalities.
T,000 CRITICAL HOURS Contractor personnel are not included for this indicator.
(Page 5 )
This indicator is defined as the number of unplanned automatic scrams (RPS logic actuatons) that occur per 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of cntiert operabon. AUXILtARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE The value for this indicator is calculated by multiplying the total number of unplanned automatic reactor scrams in a The sum of the known (planned and unplanteed) unavailable ,
specific hme pened by 7,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, then dividing that hours and the eshmated unavailable hours for the auxiliary number by the total number of hours criticalin the same feedwater system for the reportng penod divided by the time period. The indicator is further defined as follows: critical hours for the reportng period muttplied by the number of trains in the auxiliary feedwater system.( Page 6 ) -
- 1) Unplanned means that the scram was not an antcipated part of a planned test. EMERGENCY AC POWER SYSTEM SAFETY SYSTEM PERFORMANCE
- 2) Scram means the automatic shutdown of the reactor by a rapid inserton of negative reactivity The sum of the known (planned and unplanned) unavailable (e.g , by control rods, liquid injection system, etc.) and the estimated unavailable hoursfor the emergency AC that is caused by actuation of the reactor power system for the reporting penod divided by the number protection system. The signal may have resulted of hours in the reportng period multiplied by the number of from exceeding a set point o$ spurious. trains in the emergency AC power system.( Page 7 )
- 3) Automatic means that the inital signal that caused actuation of the reactor protection system logic was provided from one of the sensor's monitoring plant parameters and conditions, rather than the 64
PERFORMANCE INDICATOR DEFINITIONS THERMAL PERFORMANCE COLLECTIVE RADIATION EXPOSURE The rabo of the design gross heat rate (corrected) to the Collective radiation exposure is the total extemal whole-adjusted actual gross heat rate, expressed as a percentage. body dose received by all on-site personnel (including
( Page 8 ) contractors and visitors) during a time period, as measured by the thermoluminescent dosimeter (TLD). Collective FUEL RELIABILITY INDICATOR radiaton exposure is reported in units of peison-rem. This indicator tracks radrological work performance for SEP #54.
TNs indicator is defined as the steady-state primary coolant ( Page 11 )
M31 activity, corrected for the tramp uranium contributon and normalized to a corrvnon purification rate. Tramp uranium is fuel which has been deposited on reactor core INDUSTRIAL SAFETY ACCIDENT RATE intamals from previous defechve fuel or is present on the surface of fuel elements from the manufacturing process. The purpose of tNs indicator is to monitor progress in
, Stesdy state is defined as con *inuous operation for at least improving industrial safety performance for utility personnel three days et a power level tha1does not vary rnore than + permanently assigned to the station. Contractor work-hours or 5%. Plants should collect lata for this indcator at a are not included in this indicator. (Page 12 )
, power level above 85%, when possible. Plants that did not Failure Cause Categories are:
l operate at steady state power above 85% should collect j data for this indicator at the highest steady-state power levet j attained during the month.
VOLUME OF LOW LEVEL SOLID RADIOACTIVE WASTE The density correchon factor is the ratio of the specific This indicator is defined as the volume of low-level solid volume of coolant at the RCS operatng temperature (540 radioactive waste actually shipped for burtal, This indicator degrees F., Vf = 0.0217) divided by the spedfic volume of also shows the volume of low-level radioactive waste wNch coolant at normal letoown temperature (120* F at outlet of is in temporary storage, the amount of radioaceve oil that he letdown cooling heat exchanger, Vf = 0.0163), which has been sNpped off-site for processing, and the volume of resutts in a density correcton factor for FCS equal to 1.33 solid dry radioactve waste wNch has been shipped off-site
( Page g ) for processing. Low-level solid radioactive waste consists of dry active waste, sludges, resins, and avaporator bottoms generated as a result of nuclear power plant operation and SECONDARY SYSTEM CHEMISTRY PERFORMANCE maintenance, Dry radioactive waste includes contaminated INDEX rags, cleaning materials, disposable protective clotN99, plastic containers, and any other material to be disposed of The Chemistry Performance Index (CPI)is a calculation at a low-level radioachve waste disposal site, except resin, based on the concentra bon of key impuribes in the sludge, or evaporator bottoms. Low-level refers to all secondary side of the plant. These key impurities are the radioactive waste that is not spent fuel or a by product of most likely cause of deterioration of the steam generators. spent fuel processing. TNs indicator tracks radeological Criterta for calculahng the CPI are: work performance for SEP #54. ( Page 13 )
- 1) The plant is at greater than 30 percent power, and
- 2) the power is changing less than 5% per day.
The CPI is calculated using the following equation:
CPI = ((sodium /0.79) + (CNortde/1.52) + (Sulfate /1.44) +
- (Iron /3.30) + (Copper /0.30)+(Condensate 02/2.90)yB Where: Sodium, sulfate, chloride and condensate dissolveu oxygen are the montNy average blowdown concentrations in ppb, tron and copper are montNy time wwighted average feedwater concentrations in ppb. The denominator for eaof the five factors is the INPO median value. If the monthly average for a specific parameter is less than the INPO median value, the median value is used in the calculahon.
( Page 10 )
65 l
_ _ _ = - _ _ . .. . . .
1 PERFORMANCE INDICATOR DEFINITIONS DISABLING INJURYALLNESS FREQUENCY RATE LICENSEE EVENT REPORT (LER) ROOT CAUSE (LOSS TIME ACCIDENT RATE) BREAKDOWN This irdcator is defined as the number of accidents or all This ir@cator shows the number and root cause code for utihty personnel permanently assigned to the station, Licensee Event Reports. The root cause codes are as involv6nt days away frorn work per 200,000 man-hours follows:
worked (100 man-years). This does not include contractor personnel This irdcator tracks personnel performance for t) Administrative Control Problem .
SEP #25,26 & 27, (Page 15 ) Management and supervisory deficiencies mat affect plant programs or activities (i.e.,
poor planning, breakdown or lack of -
RECORDA8LE INJURYALLNESS CASES FREQUENCY adequate management or supervisory RATE control, incorrect procedures, etc).
The number of injunes requ6 ring more than normal first aid 2) Licensed Operator Error . This cause code per 200.000 man-hours worked. This indicator trends captures errors of omission / commission by personrel performance for SEP #15,25 and 26, licensed reactor operators during plant
( Page 16 ) activities.
- 3) Other Personnel Error Errors of CLEAN CONTROLLED AREA CONTAMINATIONS 21,000 omission / commission committed by non. ,
DISINTEGRATIONS / MINUTE PER PROSE AREA he nsed personnet involved in plant activities.
The personnel contaminabon events in the clean controlled area. This indicator tracks personnel performance for SEP 4) Maintenance Problem .The intent of this
- t 5 & 54. ( Page 17 ) cause code is to capture the full range of problems which can be attributed in any way to programmatic defidendes in the PREVENTABLElPERSONNEL ERROR LERs maintenance functional organization.
Activites included in this category are This indicator is a breakdown of LERs. For purposes of maintenance, teshng, surveillance, LER event classificabon, a ' Preventable LER* is defined as: calibrabon and radiation protection.
An event for wtuch the root cause is personnel ettf (i e., 5) Design / Construction / installation /Fabricati inappropriate action by ono or more individuals), on Problem . This cause code covers a full inadequate administrahve controls, a design constmction, range of programmatic deficiencies in the installabon, installation, fabrication problem (involving areas of design, construction, installation, work completed by er supervised by OPPD personnel) or and fabrication (i.e., loss of control power a maintenance problem (attributed to inadequate or due to underrated fuse, equipment not 6mproper upkneokepair of plant equipment). Also, the qualified for the erMronment, etc.).
cause of the event must have occurred within approximately two years of the " Event Date* specified in 6) Equipment Failures (Electron!c Piece. -
the LER (e.g., an event for which the cause is attributed Parts or Environmental-Ra'.ated Failures)-
tc a problem with the original design of the plant would This cooe is used for spunous failures of not be mnsidered preventable). electronic piece-parts and failures due to meteorological conditions such as hghtning.
For purposes of LER event dassification, a ' Personnel ice, high winds, etc. Generalty, it indudes Error
- LER is defined as follows: spurious or one-time failures. Electric components induded in this category are An event for which the root cause is inappropriate action circuit cards, techfiers, bistables fuses, on the part of one or more individuals (as opposed to capadtors, diodes, resistors, etc.
being attributed to a department or a general group). I:, addibon this indicator reports SEP # 60 &
Also, the inappropriate action must have occurred within 61. (Page 19 )
approximately two years of the " Event Date* specified in the LER. Additionally, each event dassified as a
- Personnel Error" should also be dassified as
" Preventable? This indicator trends personnel performance for SEP ltem #15. ( Page 18 )
66 l
PERFORMANCE INDICATOR DEFINITIONS VIOLATION TREND UNPLANNED SAFETY SYSTEM ACTUATIONS .(INPO
+ DEFINITION)
This indicator is defined as Fort Calhoun Station Cited Violations and Non-Cited Violations trended over 12 months. This indicator is defined as the sum of the following safety Additionally, Cited Veolations for the top quartile Region IV system actuations:
plant is trended over 12 months (lagging the Fort Calhoun Stabon trend by 2 3 months). It is the Fort Calhoun Stabon 1) The number of unplanned Emergene) Core goal to be at or below the oted vlotabon trend for the top Coohng System (ECCS) actuations that quart le Region IV plant. ( Page 20 ) result from reaching an ECCS actuation set point or from a spurious / inadvertent ECCS signal.
MAXIMUM INDIVIOUAL RADIATION EXPOSURE
- 2) Tne number of unplanned emergency AC This indicator shows the highest exposure for an individual powur rystem actuations that result from a dunng the year, ( Page 21 ) loss of power to a safeguards bus. An unplanned safety system actuation occurs when an actuation set point for a safety STATION NET GENERATION system is reached or when a spurious or inadvertent signal is generated (ECCS only),
The net generation (sum) produced by the FCS during the and major equipment in the system is reporting month. ( Page 23 ) actuated. Unplanned means that the system actuaton was not part of a planned test or evolution The ECCS actuations to be
. FORCED OUTAGE RATE counted are actuations of the high pressure injection system, the low pressu e injection This indicator is defir'ed as the percentage of time that the system, or the safety injecton tanks.
unit was unavailable due to forced events compared to the (Page 27) time planned for electrica! generation, Forced events are failures or other unplanned conditions that require removing the unit from service before the end of the next weekend. UNPLANNED SAFETY SYSTEM ACTUATIONS .(NRC Forced events indude start-up failures and events initiated DEFINITION) while the unit is in reserve shutdown (i.e., the unit i.)
available but not in service ( Page 24 ) The number of safety system actuations which include (goty) the High Pressure Safety injection System, the Low Pressure Safety injection System, the Safety injechon UNIT CAPACITY FACTOR Tanks, and the Emergency Oiesel Generators. The NRC classification of safety system actuabons includes The net electrical energy generated (MWH) divided by the actuations when major equiprnent is operated 3Dd when the product of maximum dependable capaoty (net MWE) times logic systems for the above safety systems are challenged, the gross hours in the reporbng period expressed as a ( Page 28 )
percent. Net electrical energy generated is the gross electrical output of the unit measured at the output terminals of the turbine generator minus the normal station service GROSS HEAT RATE
,. loads during the gross hours of the reporting period, cxpressed in megawatt hours, ( Page 25 ) Gross heat rate is defined as the rabo of total thermal ene~gy in British Thermal Units (BTU) produced by the reactor to the total gross electrical energy produced by the EQUIVALENT AVAILABILITY FACTOR generator in kilowatt-hours (KWH). ( Page 29 )
This indicator is defined as the ratio of gross available generaton to gross maximum generrion, expressed as a DAILY THERMAL OUTPUT percentage. Available generabon is the energy that can be produced if the unit is operated at the maximum power level This indicator shows the daily core thermal output as permitted by equipment and regulatory limitations, measured from computer point XC105 (in thermal Maximum generation is the energy that can be produced by megawatts). The 1500 MW Tech Spec limit, and the unmet a unit in a given period if operated continuously at maximum porton of the 1495 MW FCS daily goal for the reporting capacity. ( Page 26 ) month are also shown. ( Page 30 )
67
[ ..
PERFORMANCE INDICATOR DEFINITIONS SOUIPMENT FORCED OUTAGES PER 1,000 CRITICAL Maintenance Work Priorities are defined as-HOURS Emergency . Condsbons which significantly degrade Equipment forced outages per 1,000 cribcal hours is the station safety or availability, inverse of the mean time between forced outages caused by equipment failuros. The mean bme is equa! to the number immediate Action . Equipment deficiencies which of hours the reactor is criticalin a period (1,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />) significantly degrade station rehability Potential for unit dtvided by the number o forced outages caused by shutdown or power reduction.
equipment failures in that penod. ( Page 31 )
Operations Concern . Equipment deficiencies which hinder station operation.
CHEMISM ACTION LEVELS EXCEEDED. EVENT DAYS Essential . Routine corrective maintenance on essential stabon systems and equipment. ,
Chemistry Achon Levels Exceeded indicator tracks the aumber of days in which chemistry parameters exceeded a Non-Essential . Routne correchve maintenance on non-corresponding acbon level for tne reporting month. essenhal stabon systems and equipment.
( Page 32 )
Plant Improvement . Non-corrective maintenance and plant improvements.
PRIMARY SYSTEM LITHlUM % OF HOURS OUT OF LIMIT This indicator tracks maintenance performance for SEP
- 36. ( Page 37 )
The percent of hours out o'let ere for hthium divided by the total number of hors pass t4 for the month ( Page 33 )
RATIO OF PREVENTIVE TO TOTAL MAINTENANCE &
PREVENTIVE MAINTENANCE ITEMS OVERDUE CENTS PER KILOWATT r40VR The ratio of prevenhve maintenance (Induding surveillance D The purpose of this mc catar is t0 Quantify the economical tesbng and calibration procedures) to the sum of norkoutage (
operabon of Fort Ca hour Straon The cents per kilowatt corrective maintenance and preventive maintenance hour indicator represents tv t+dget and actual cents per completed over the reporting period. The ratio, expressed kilowatt hour on a twei.e monts average for the current as a percentage,is calculated based on man-hours. Also year, The basis fo* tne ta:ac! carve is the approved year 1y displayed are the percent of preventive maintenance items budget. The basis fy the a:Na' curve is the Financial and in the month that were not completed or administratively Operating Report ( Page 35 ) closed by the scheduled date plus a grace penod equal to 25% of the scheduled interval. This indicator tracks preventive maintenance activibes for SEP 841, ( Page 38 )
MAINTENANCE WORKLOAD BACKLOGS This indicator shows the backlog of non-outage PERCENTAGE OF TOTAL MWDs COMPLETED PER Maintenance Work Documents remaining open at the end of MONTH IDENTIFIED AS REWORK the reporting month. Maintenance classificabons are defined as follows: The percentage of total MWDs completed per month identfied as rework. Rework activities are idenbfied by ,
Corrective Repair and restorabon of equipment or maintenance planrang and craft. Rework is: Any additioral components that have failed or are malfunctioning and work required to correct deficiencies discovered dunng a are not performing their intended function. failed Post Maintenance Test to ensure the component / system passes subsequent Post Maintenanco Preventive . Actions taken to maintain a piece of Test. ( Page 39 )
equipment within design operating conditions, prevent equipment failure, and extend its hfe and are performed pnor to equipment failure. MAINTENANCE OVERTIME Non4crrective/ Plant improvements Maintenance The percent of overtme hours compared to normal hours for activibes performed to irnplement station improvements or maintenance. This includes OPPD personnel as well as to repair non-plant equipment, contract personnel. ( Page 40 )
68
PERFORMANCE INDICATOR DEFINITIONS i
PROCEDURAL NONCOMPLIANCE INCIDENTS TEMPORARY MOOlFICATIONS (MAINTENANCE) l .
The number of temporary rnechanical and electrical The number of identthed incidents conceming maintenance configurabons to the plants systems, procedural problems, the number of closed irs related to the use of procedures (includes the number of closed irs 1) Temporary configurations are defined as caused by procedural noncompliance), and the number of electrical jumpers, electrical blocks, closed procedural noncomphance irs. This indicator trends mechanical jumpers, or mechanical blocks personnel performanm for SEP #15, 41 and 44. ( Page 41 ) . which are installed in the plant operahng systems rd are not shown on the ta'est revision of the PalD. schematic, connecbon, IN LINE CHEMISTRY INSTRUMENTS OUT OF SERVICE wiring, or flow diagrant Total number of in-line chemistry instruments that are out+f- 2) Jumpers and blocks which are installed for
, service in the Secondary System and the ,51 Accident Surveillance Tests, Maintenance Procedures.
Sampl6ng System (PASS). ( Page 42 ) Calibrabon Procedures, Special Procedures or Operahng Procedures are not considered as temporary modifications unless the jumper HAZARI)OUS WASTE PRODUCED or block remains in place after the test or procedure is complete. Jumpers and blocks The total amount (in Kilograms)of non.halogenated installed in test or lab instruments are not hazardous waste, halogenated hazardous waste, and other considered as temporary modifications, hazardous waste produced by FCS each month. ( Page 43 )
- 3) Scaffold is not considered a temporary modification. Jumpers and blocks which are CONTAMINATED RADIATION CONTROLLED AREA installed and for which Mrs have been submitted will be considered as temporary i The percentage of the Radiation Controlled Area, which modificahons until final resolution of the MR includes the auxiliary building, the radweste building, and and the jumper or block is removed or is
. areas of the C/RP buildirm, that is mntaminated trased on permanently recorded on the drawings. This the total square footage. TNs indicator tracks performance indicator tracks temporary modificabons for for SEP #54. ( Page 44 ) SEP #62 and 71, ( Page 48 )
RADIOLOGICAL WORK PRACTICES PROGRAM OUTSTANDING MODIFICATIONS The number of identfied poor radiological work practices The numoet of Modificabon Requests (MRs)in any state (PRWPs) for the reporting month. TNs indicator tracks between the issuance of a Modification Number and the radiological work performance for SFP #52. ( Page 45 ) completion of the drawing update.
- 1) Form FC 1133 Backlog /In Progress, This DOCUMENT REVIEW (BIENNIAL) number represents modtficabon requests that have not been plant approved during the The Document Review Indicator shows the number of reportng month, documents reviewed, the number of documents scheduled s for review, and the number of document reviews that are 2) Modification Requests Being Reviewed.
overdue for the reporting month. A document review is This category includes:
consklered overdue if the review is not complete within six months of the assigned due date. This indicator tracks A) Modification Requests that performance for CEP #46 ( Page 46 ) are not yet reviewed.
LOGGABLElREPORTABLE INCIDENTS (SECURITY)
The total number of security incidents for the reporbng . B) Modification Requests being month depicted in two graphs. This indicator tracks security reviewed by the Nuclear performance for SEP 158. ( Page 47 ) Projects Review Committee (NPRC).
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PERFORMANCE INDICATOR DEFINITIONS C) Modification Requests being and ECN Docurr snt Changes open. This Indicator tracks reviewed by the Nudear performance for bEP #62. ( Page $2 )
Projs ets Committee (NPC).
These Modification Requests may be reviewed several SAFETY SYSTEM FAILURES times before they are approved for accomplishment or canceled. Some of these Modification Requests are Safety system failures are any events or conditions that retumed to 8'ngineenng for more informahon, some could prevent the fulfillment of the safety funcuena of approved for evaluabon, some approved for study, and structures or systems. If a system consists of multiple some approved for planning. Once planning is completed redundant subsystems or tra ns, failure of all trains and the scope of tr.e work is deafty defined, then constitutes a safety system failure. FaNre of one of two or Modification Rowests may be approved wr accomphshment more trains is not counted as a u fety system failure. The -
with a year atsigned for construction or they may be definibon for the indicator paratiets NRC reporting canceled All of these different phases require review. requirements in 10 CFR 60.72 and 10 CFR 50.73. The following is a list of the major safety systems, sub-systems,
- 3) Design Engineering Backlogrin Progress. and components monitored for this indiewtor; Nuclear Planning has assigned a year in which construebon will be completed and Acc6 dent Monitoring Instrumentation, Auxlhary (and design work may be in progress, Etnergency) Feedwater System, Combustible Gas Control, Component Coohng Water System, Containment
() Construction Backlogfin Progress. The and Containment Isoit On, Containment Coolant Construction Package has been issued or Systems, Control Room Emergency Ventilation System, construction hbs begun but the (nodification E:.iergency Core Coon.,g Systems, Engineered Safety has not been accepted by the System Featuresinstrumentation EssenbalCompressed Air Acceptance Committee (SAC).
b) Design Engineering Update Backlog /in Prgtress. PED has received the Systems, Essential or Emergency Service Water, F6te MoWication Completion Report but the Detechon or Suppression Systems, isolation Condenser,
- iravm;s have not been updated.The 1bove Low Temperature Overpressure Protec+ ion, Main Steam menboned outstanding modifications do not Line Isolation Valves, Onsite Emerger.vy AC & DC Power IN lude modifications which are proposed 'or w! Distribution, Radiation Monitonng instrumentabon, u loWlabon, t Page 49 ) Reactor Coolant System, Reactor Core Isola,lon Cookng System, Reactor Tnp System and instrumentation, Recirculation Pump Trip Actuation Instrumentation, Residual ENGINEERING AS$lSTANCE REQUEST (EAR) Heat Removat Systems, I afety Valves, Spent Fuel SREAK30WN Systems, Standby Liquiu Control System and Ultimate Heat Sink ( Page 53 )
TNs indicator s'iows a breakdown, by age and pnority of the EAR, of the number of EARS assigned to Design Engineering Nuclear a,d System Engineenng. This LICENSED OPERATOR REQUALIFICATION TRAINING indicator tracks performance for SEP #62. ( Page 50 )
The total r. umber of hours of training given e eadi crew '
during each cycle. Also provided are the * 'utator training ENGIAEERING CHANGE NOTICE (ECN) STATUS hours (wtilch are a subset of the total training hours), the number of non-REQUALIFICATION training hours and the ,
The number of ECNs that were opened ECNs that were number of exam failures. This indicator tracks training completed, and open backlog ECNs awaibng completicn by performance for SEP # 68. ( Page 54 )
DEN for the reporting month. This indicator tracks performance for SEP #62. ( Page 51 )
LICENSE CANDIDATE EXANS ENGINEERING CHANGE NOTICEr. OPEN This indicator shows the number of SRO and/or RO quizzes and exams that are administered and passed each month.
This indicator breaks down the number of Engineenng This indicator tracks training performance for SEP #S8.
Change Nobces (EC1) that are assigned to Design ( Page 55 )
Engineenng Nuclear (DEN), System Engineenng. and Maintenance. The graphs provide data on ECN Facihty Changes open. ECts dubshtute Pentacement Items open, 70
PERFORMANCE INDICATOR DEFINITIONS CONDITION REPORTS SY LEVEL P90GRESS OF .A REFUELING OUTAGE fAODIFICATIONS CYCLE 18 This indicator shows the total numter of Condition Reports which are Closed, Ready to Close, Open and the Total this indicator shows the status of Modifications approved for numter of Condition Reports to date. Iratallation during the Cycle 18 Refueling Outage
( Page 66 ) ( March 1998). This indicator tracks performance for SF# #
31 ( Pinge 99 )
WWD PLANNilvG STATUS (CYCLE 10 REFUELING OUTAGE) PROGRESS OF CYCLE 18 OUT'.3E MODS AND ECN'S ADDED TO 48 REFUELING OJTAGE AFTER FREEZE
, This Indicator shs wa the total number of Maintenance Work DATE Requests (MWRs) and Maintenance Work Documents (MWDs) that have been approved for inclusion in the Cycle This indicator will show the status of Modificauons and 18 Refueling OutaDe. This indicator tracks performance #31 ECN's approved for installation during the Cycle 18
( Page 67) Refueling Outage. This indicator tracks performance for SEP #33. ( Page 60 )
SPECIALSERVICES ENGINEERING 1998 OUTAGE NO 1997 ON LINE MODIFICATIONS CURREN11.Y PROJECTS ETATUS REPORT APPROVED This indicator tracks performance for SEP # 31. This indicator shows the status of modifications approved or
( Page 68 )
in review for approvst for on line installation during 1997 T his indicator tracks performance for SFP # 31. ( Page 61 )
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SAFETY ENHANCEMENT PROGRAM INDEX The purpose of the Safety Enhancement Program (SEP) Performance Indicators index is to list performance indicators related to SEP ltem with parameters that can be trended.
SEP Refetsnee Numbetil East
. Increase HPES and IR Accounta5lIlty through use of Performance Indicators Procedural Noncompliance incidents (Maintenance) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 Recordable injury / Illness Cases Frequency Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 Clean Controlled Area Contaminations 11,000 Disintegrations / Minute Per Probe Area . . . . . . . . . . 17 ,
Preventable / Personnel Error L.ERs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 SEE_Befattac1 Numbers 25. 26. & 27 e Training Program for Managers and Supervisors implemented
. Evaluate and implement Station Standards for Safe Work Practice Requirements
. Implement Supervisory Enforcomsnt of Industrial Safety Standards Disabling injury / Illness Frequency Rate . ............................. .............. 15 Recordable injury / Illness Cases Frequency Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 SEP Reference Number 31
- . Develop Outage and Maintenance Planning Manual and Conduct Projact Management Training MWD Planning St.aus (Cycle *
- Refueling Outage) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 Component Testing Department. Special Services Engineering Department 1998 Outage Projects . . , 58 Progress of i9" ifueling Outage Modifications Cycle 18 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 59 Progress of 1L i A ' % Modification Planning ......... ............................. 61 SEP Reference Numar 33
. Develop On-Line Maintenance and Modification Schedule Progress of Cycle 18 Outage MODS and ECN's Added to '98 Refueling Outage After Freeze Date . . 60 EEP Reference Number 36
. Roduce Corrective Non Outage Backlog Maintenance Workload Backlogs (Corrective Non Outage) ...... ....... . .............. 37 SEP Refertr&g_thimbers 41 & 44
. Develop and implement a Preventive Maintenance Schedule
. Compliance With and Use of Procedures
- Ratio of Preventive to Total Maintenance & Preventive Mrintenance items Overdue . . . . . ... 38 Procedural Noncomplianco incidents (Maintenance) . . .. .. .. .. .. . ...... . ....4' SER Reference Number 46 Design a Plocedures Control and Administrative Program Document Review . . . . . . . . . . . . . . . . . . . . . . . . . . .. ...... ...... ..... . ...... 46 72
SAFETY ENHANCEMENT PROGRAM INDEX SEP_Reletence Number 52 P_ ann
- Establish Supervisory Accountability for Workers Radiological Practices Radiological Work Practices Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 5
. SEP Rafflence3umbE14
+ Complete in pieriientation of Radiological Enhancement Program Collective Radiation Exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . 11 Volume of Low-Level Solid Radioactive Waste ......... ...........,................... 13 Clean Controlled Area Disintogrations 21,000 Counts / Minute Por Probe Area . . . . . . . . . . , , , . . . 17 Contaminated Radiation Controlled Area . . . . . . . . . . . . . . . . . . . . . . . . . . , , . . . . . . . . . . . . . . . . 44 EEP Referance Number 58
+ Revise Physical Security Tralning and Proceduro Program Loggable/ Reportable inclJents (Security) , ... ...................... ................ 47 EEP ReferencA3umhtra 60 & 6.1
. Improve Controls Over Surveillance Test Program e Modify Computer Program to Correctly Schedule Surveillance Tests licensee Report LER Root Cause Breakdown Number of Missed Surveillance Tests resulting in Licensee Event Reports . . . . . . . . . . . . . . . . . . . . ig SEP Reference Number 62
. Establish interim System Engineers Temporary Modification s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 Engineering Assistance Request (EAR) Breakdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 Engineering Change Notice Status ........ ...... ..... .. . ............. ......... 51 Engineering Change Notices Open . . . . . . . . . . . . . . . . . . . . . . . . . ... ............. .... 52 r '
SEP _ Reference Number 68
. Assess Root Ca Jse of Poor Operator Training and establish means to monitor Operator Training License Operator Requalification Training . . . . . . . . ....... .. ... ............... 54 License Candidate Exams . . . ........... ... . . ... ... ... .... ....... 55 SEP Reference Number 71
- Improve Controls over Temporary Modifications Temporary Modifications . . . . . . . . . . . . . . . . . . . . ... .. .., ., ..... ......../9 73 q .) . i
REPORT DISTRIBUTION LIST R. L. Andrews J. B. Kuhr (9 Copies)
K.L.Belck L. T.Kusek G.C. Bishop C. J. Linden (10 Coples)
C. E. Boughter S. A. Lindquist C. J. Brunnert B. R. Livingston J. W. Chase E. R. Lounsberry R. G. Conner T. J. McIvor .
M.R. Core K. A. Miller T. R. Dukarski P. A. Mruz M. L. Ellis R. J. Mueller >
H. J. Faulhaber R. L. Phelps S. K. Gambhir R. L. Plott J. K. Gaspe, W.J.Ponec W. G. Gates D. G. Ried S. W. Gobers M. J. Sandhoefner M. J. Guinn F. C. Scofield R. H. Guy H. J. Sefick l A. L. Hale R. W. Short l B. R. Hansher J. L. Skiles l
K. R. Henry R. D. Spies (2 Copies)
J. B. Herman K. E. Steele R. P. Hodgson D. E. Spires C.K. Huang M. A. Tesar J. K. Kellams J. J. Tesarek R. L. Jaworski J. W. Tills J. W. Johnson D. R. Trausch D.D. Kloock L. P. Walling G. R. Williams
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