ML20246A484

Performance Indicators

ML20246A484
Person / Time
Site:	Fort Calhoun
Issue date:	05/31/1989
From:	OMAHA PUBLIC POWER DISTRICT
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NUDOCS 8907070004
Download: ML20246A484 (87)

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FORT CALHOUN STATION PERFORMANCE INDICATORS l

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MAY, 1989 1

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1 Prepared by:

Production Engineering Division Special Services

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OMAHA PUBLIC POWER DISTRICT-FORT CALHOUN STATION PERFORMANCE INDICATORS i

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PREPARED BY:

PRODUCTION ENGINEERING DIVISION SPECIAL SERVICES MAY, 1989

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'l a,w F

. Pursuit of excellen c e is' a n attitude...

it in volves wis d o m and s o u n d j u dgm e n t...

'It is a lif e t im e, c a r e e r-lo n g commitment...

It isa w ay. of lif e... it is doing the job r i g h't th e fis t tim e, every tim e. It l 's in n e r-dir e e t e d, not th e res ult of ext e rn al pressure, it is our o w n s e lf w o r t h - w h o we are and th e y rid e and s atisf a ction th a t comes from b ein g the right kin d of person, not just in doing the righ t things.

James J.

O'Connor 1

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TABLE OF CONTENTS

_P129.

Distribution....................

iv Preface.....

1 Purpose......................

2 Scope.......................

3 Index to Perfo'mance Indicator Graphs.......

4 r

Performance Indicator Graphs............

8 Escalated Enforcement History........... 62 i

Significant Items of Interest........... 65 Definitions.................... 66 Basis for Establishing 1989 Performance Indicator Goals.................

76 Operating Cycles and. Refueling Outage Dates....

78 Production and Operation Records.......... 79 Data Source..................... 80 References..................... 82 a

DISTRIBUTION S. L. Anderson L. V. Goldberg J. T. O'Connor V. W. Anderson M. J. Guinn W. W. Orr R. L. Andrews R. H. Guy E. C. Pape W. R. Bateman M. C. Hendrickson T. L. Patterson K. L. Belek K. R. Henry F. M. Petersen A. D. Bilau K. C. Holthaus G. R. Peterson C. N. Bloyd L. G. Huliska S. M. Peterson J. P. Bobba R. L. Jaworski D. R. Pettit C. J. Brunnert R. A. Johansen R. L. Phelps M. W. Butt J. W. Johnson T. J. Pirruccello R. H. Cagle D. W. Jones W. R. Plowman i

C. A. Carlson W. C. Jones T. M. Reisdorff G. R. Chatfield J. D. Kecy A. W. Richard A. G. Christensen R. C. Kellogg G. M. Riva R. P. Clemens J. D. Keppler T. J. Sandene R. G. Conner D. D. Kloock F. C. Scofield G. M. Cook G. J. Krause L. G. Sealock S. R. Crites G. A. Krieser H. J. Sefick D. W. Dale L. J. Kripal R. W. Short R. C. DeMeulmeester J. B. Kuhr E. L. Skaggs W. D. Dermyer L. T. Kusek F. K. Smith R. D. DeYoung R. C. Learch R. L. So'renson D. E. Dirrim R. E. Lewis R. T. Spetman J. A. Drahota R. C. Liebentritt D. E. Spires M. O. Elzway B. R. Livingston K. E. Steele R. G. Eurich J. H. MacKinnon W.

Steele H. J. Faulhaber G. D. Mamoran C. J. Sterba K. S. Fieldin9 J. W. Marcil H. F. Sterba J. J. Fisicaro N. L. Marfice R. K. Stultz J. J. Fluehr D. J. Matthews G. A. Teeple J. J. Foley J. M. Mattice M. A. Tesar F. F. Franco T. J. McIvor J. W. Tills l

M. T. Frans M. L. Meador D. R. Trausch J. F. W. Friedrichsen R. F. Mehaffey C. F. Vanece'k R. M. Fussell K. A. Miller L. P. Walling S. K. Gambhir

k. A. Miser J. M. Waszak J. K. Gasper K. J. Morris W. O. Weber W. G. Gates D. C. Mueller G. R. Williams M. O. Gautier R. J. Mueller S. J. Willrett J. T. Gleason M. W. Nichols D. D. Wittke C. W. Norris

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t PREFACE PERFORMANCE INDICATORS REPORT IMPROVEMENTS Two indicators in the Performance Indicators Report have been changed in May. One change was made in the Maintenance Section and the other change was made in the Quality Assurance Section.

The Maintenance Section change was made to the Number of-

' Out-of-Service Control Room Instruments Indicator found on page 30.

- This indicator now includes the number of cut-of-service control room instruments corrected during the inonth and the number of out-of-service control room instruments added during the month.

The Quality Assurance Section _ change was made to the Outstanding Deficiency and - Ouality Reoorts Indicator found on page 60. This indicator now includes Deficiency and Quality Reports that are related to modifications.

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l PURPOSE This program titled " Performance Indicators" is intended to provide selected Fort Calhoun plant performance information to OPPD's personnel responsible for optimizing unit performance. The information is presented in a way that provides ready identification of trends and a means to track progress toward reaching corporate goals. The information can be used for assessing and monitoring Fort Calhoun's plant performance, with emphasis on safety and reliability. Some performance indicators show company goals or industry information. This information can be used for comparison or as a means of promoting pride and motivation.

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SCOPE' In order for the Performance Indicator Program to be effective, the following guidelines were followed while~ implementing this program:

Select the data which most effectively monitors Fort Calhoun's performance in key areas.

Present the data in a straight forward graphical format using averaging and smoothing techniques.

Include established corporate goals and industry information for comparison.

l Develop formal definitions for each performance parameter.

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This will ensure consistency in future reports and allow comparison with industry averages where appropriate.

1 Comments and input are encouraged to ensure that this program is tailored to address the areas which are most meaningful to j

the people using the report.

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i-PERFORMANCE INDICATORS INDEX TO GRAPHS INDUSTRY KEY PARAMETERS Forced Outage Rate.......................... 8

. Unplanned Automatic Reactor Scrams While Critical......... 9 Unplanned Safety System Actuations...............

10 Gross Heat Rate.........................

11 Equivalent Availability Factor....,............

12 Fuel Reliability Indicator....................

13 Personnel Radiation Exposure (Cumulative)............

14

. Volume of Low-level Solid Radioactive Waste...........

15 Disabling Injury Frequency Rate..................

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f PERFORMANCE INDICATORS I

INDEX TO GRAPHS l

(CONTINUED) 1 d

OPERATIONS Forced Outage Rate........................ 8 Unplanned Automatic Reactor Scrams While Critical.........

9 1

Unplanned Safety System Actuations...............

10 Gros s Heat Rate.........................

11 Equivalent Availability Factor.................

12 Fuel Reliability Indicator...................

13 Condenser Air Inleakage.....................

17 Daily Thermal Output......................

18 Equipment Forced Outages per 1000 Critical Hours........

19 Operations and Maintenance Budget................

20 Document Rev iew......'...................

21 MAINTEH_A.XQE Diesel Generator Reliability (100 Demands)...........

22 Diesel Generator Reliability (20 Demands)............

23 Age of Outstanding Maintenance Orders..............

24 Maintenance Order Breakdown'...................

25 Corrective Maintenance Backlog >3 Months Old..........

26 Ratio of Highest Priority M0s to Total M0s Completed......

27 Ratio of Preventive to Total Maintenance............

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Preventive Maintenance Items Overdue..............

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PERFORMANCE INDICATORS IhDEX TO GRAPHS (CONTINUED)

MAINTENANCE (CONTINUED)

Number of Out-of-Service Control Room Instruments........

30 Craft Work Activity.......................

31 Maintenance Overtime......................

32 Procedural Noncompliance Incidents (Maintenance)........

33 Number of Nuclear Plant Reliability Da+a System (NPROS)

Reportable Failures.......................

34 CHEMISTRY AND RADIOLOGICAL PROTECTION t

Personnel Radiation Exposure (Cumulative)............

14 i

Volume of Low-level Solid Radioactive Waste...........

15 Secondary System Chemistry...................

35 Primary System Chemistry - Percent of Hours Out of Limit....

36 Auxiliary Systems Chemistry Hours Outside Station Limits....

37 I

Maximum Individual Radiation Exposure..............

38 Total Skin and Clothing Contaminations.............

39 Decontaminated Auxiliary Building................

40 Gaseous Radioactive Waste Being Discharged to the Environment..

41 Liquid Radioactive Waste Being Discharged to the Environment..

42 MATERIALS AND OUTSIDE SERVICES Amount of Work On Hold Awaiting Parts..............

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Spare Parts Inventory Value...................

44 Spare Parts Issued.......................

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PERFORMANCE INDICATORS INDEX TO GRAPHS L

(CONTINUED)

DESIGN ENGINEERING f

Outstanding Modifications........-..............

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. Temporary Modifications.....................

47 INDUSTRIAL SAFETY' Disabling Injury Frequency Rate.................

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Recordable Injury Cases Frequency Rate.............

48 Minor Injury Cases per Month..................

49 HUMAN RESG'JRCES L

Number of Personnel Errors Reported in LERs...........

50 Personnel Turnover Rate..-.....

51 Staffing Level..........................

52 TRAINING AND QUALIFICATION SRO License Examination Pass Ratio...............

53 R0 License Examination Pass Ratio................

54 R0 Hot License Exams.......................

55 Hotlines............................

56 Classroom (Instructor) Hours..................

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Total Hours of Student Training.................

58 OUALITY ASSURANCE Number of Violations per 1000 Inspection Hours.........

59' Percent of DR/QR's Greater Than Six Months Old.........

60 DR/QR's Issued versus NRC Violations Issued versus LERs Reported. 61 -

- - - Forced Outage Rate 6

-e-Fort Calhoun Goal O Industry Upper 10 Percentile 5-GOOD c.

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FORCED OUTAGE RATE No Forced outage hours were logged for the Fort Calhoun Station during May, 1989. The

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present 12 month average forced outage rate j

is 0%.

J The last forced outage at Fort Calhoun occurred almost three years ago in August of 1986.

The industry up.ner ten percentile value for the forced outage rate is 0.0%. The Fort Calhoun Station is currently in the upper ten percentile of nuclear plant performance 1

in this area.

i The 1989 goal for forced outage rate is 2.1%

and is based on seven days of forced outage time. The basis for establishing the 1989 performance goals can be found on page 76.

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48 Reactor Scram j

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1988 1989 1

UNPLANNED AUTOMATIC REACTOR SCRAMS WHILE CRITICAL There were no unplanned automatic reactor scrams in May. It has been 1,064 days since the last unplanned automatic reactor scram l

which occurred on July 2, 1986.

l The 1989 goal for unplanned automatic reactor scrams while critical has been set at 1.

1 The industry upper ten percentile value is zero scrams per unit on an annual basis. The Fort Calhoun Station is currently in the upper ten percentile of nuclear plant i

performance in this area.

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6 Safety System Actuations e-Fort Calhoun Goal O Industry Upper 10 Percentile 3-

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'86 '87 '88 Jun Jul Aug Sep.0ct Nov Dec Jan Feb Mar Apr May 1988 1989 UNPLANNED SAFETY SYSTEM ACTUATIONS There were no unplanned safety system actuations in May, 1989.

The 1989 goal for the number of unplanned safety system actuations is zero. This goal is based on past performance at the Fort Calhoun Station.

The industry upper ten percentile value for the number of unplanned safety system actuations

)er year is zero. The Fort I

Calhoun Stat on is currently in the up>er L

ten percentile of nuclear plants for t11s indicator.

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- Year to Date Gross Heat Rate

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'88 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1989 GROSS HEAT RATE The gross heat rate for the Fort Calhoun Station during May, 1989 was 10,678 BTU /KWH. This gross heat value was high due to two startups that took place during May.

The gross heat rate values for this cycle of operation will be increased due to the removal of the first stage of the high pressure turbine.

The 1989 year to date gross heat rate value

'i is 10,499 BTU /KWH. The 1989 goal is 10,500 BTV/KWH.

l The gross heat rate industry upper ten percentile value is 9,989 BTU /KWH. -

I IMonthly EAF

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- 12 Month Average EAF G-Fort Calhoun Goal GOOD C Industry Upper 10 Percentile 100-85 e...__g..__ e =

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l 66 es P 60-plh c N h e n 40-j t y ~ 17 20-t:i l n 0 '86 '87 '88 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1988 1989 E0VIVALENT AVAILABILITY FACTOR The Equivalent Availability Factor (EAF) was reported as 47.7% for the month of May. The 1989 EAF goal is 84.4% while the present 12 month average EAF for Fort Calhoun is 50.3%. The EAF industry upper ten percentile value is 83.5%. _ _ _.......... _.....

5" X Fuel Reliability Indicator -e-Fort Calhoun Goal O Industry Upper 10 Percentile 4-n a n 16 GOOD i + e 2-r a m I-O----&--- O---G----G----&--- G---G---@ O---G---O i; O O B' C/ m n '86 '87 '88 fu'n 51 A'u'g Sep Oct Nov Dec Jan Fe'b Mar Apr May 1988 1989 FUEL RELIABILITY INDICATOR The Fuel Reliability Indicator (FRI) was reported as.395 nanocuries/ gram for the month of May. This indicates that there have 7 been no fuel failures since startup in January, 1989. l The hich FRI figures resulted from a change in the rev that the FRI is calculated. The FRI was ' pres;ously celculated using a constant letdown flow rate for the entire month, but the actual letdown flow rate is l now used. 1 The 1989 fuel reliability goal has been set at 1.0 nanocuries/ gram. The fuel reliability indicator industry upper ten percentile value is 0.07 nanocuries/ gram. _ _ _ _ _ _. _ _.........

Personnel Radiation Exposure 388 400 -e-Fort Calhoun Goal O Industry Upper 10 Percentile 9$ 300-GOOD pg 272 4 4 0 O -E R \\ { E 200- 'N M d O O O O O O O O 129 c' ~ y @ g __.e. - & ~~O 9 -& ~~e -O J fita 100-gg ? g2j p,,,9 -O pg isq J / m 00 '86 '87 '88 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1989 PERSONNEL RADIATION EXPOSURE (CUMULATIVE) During May, 1989, 8.6 man-rem was recorded by l pencil dosimeters worn by personnel while working at the Fort Calhoun Station. The monthly cumulative exposure goal for April was 72.5 man-rem while the actual recorded l exposure through April was 60.5 man-rem. The personnel radiation exposure industry upper ten percentile is 175 man-rem per unit per year. _ _ ___ - _ _________ -___ -____ __.

gi; Monthly Radioactive Waste Shipped 12500- - Cumulative Radioactive Waste Shipped -G-Fort Calhoun Goal O Industry Upper 10 Percentile 10000-C u b GOOD c 7500-4 F e O---- G----G---- G----&---G-- O---G----&---G---- O ---O e 4096 C C O / I 1722 1 N l C C C O O O O 8 O 2500-l 4 l E E O 86 '87 '88 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1989 VOLUME OF LOW-LEVEL SOLID RADI0 ACTIVE WASTE The above graph shows the amount of low-level radioactive waste shipped off-site for disposal. The table below lists the amount of waste actually ship >ed off-site for disposal plus the change in inventory of waste in on-site storage in final form ready for burial. The volume of solid radioactive waste is (cubic feet): Amount Shipped in May 540.5 Amount in Temporary Stor3ge 0.0 1989 Cumulative Amount Shipped 4624.0 1989 Goal 6000.0 i There are two reasons for the very high amount of low-level solid radioactive waste that was shipped in January,1989. One reason is that the 1988 refueling outage produced a large volume of radioactive waste. Also, shipping of low-level solid radioactive waste stopped in October, 1988, due to samples being sent off-site for isotope analysis that could not be completed at the Fort Calhoun Station. The industry upper ten percentile value is 2,895.5 cubic feet per unit per year. The Fort Calhoun Station was in the upper ten percentile of nuclear plants for this indicator in 1986, 1987 and 1988.

p -++ Disabling Injury Frequency Rate G-Fort Calhoun Goal 3 O Industry Upper 10 Percentile 2-GOOD R 4 a ~ t e 1.1 1- .6 i g e.---s --O----C - 0----O--- G--- C O---G--- G----O 9 '86 '87 '88 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Rates for 1986, 1989 1987, and 1988 are shown for the month of May DISABLING INJURY FRE0VENCY RATE (LOST TIME ACCIDENT RATE) There were zero disabling injuries reported at the Fort Calhoun Station in May. The total number of disabling injuries in 1989 is one. The 1989 disabling injury frequency rate 1 goal was set at 0.31% and was based on one disabling injury occurring in 1989. The industry upper ten percentile disabling injury frequency rate is 0%. 1 , U--___-___-_--________----_-___-___

g4 - Condenser Air Inleakage 9.5 8.1 5.9 ~ S lM ~ C F 4-2 GOOD Y 0 '86 '87 '88 Jun Jul, Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1988 1989 CONDENSER AIR INLEAKAGE In May, the condenser air inleakage value was rep (orted as 9.2 Standard Cubic feet per Minute SCFM). The industry upper quartile value for condenser air inleakage is no longer available. This indicator was discontinued for 1989 by INPO. 'l l C

-*- Thermal Output - Technical Specification Limit -e Fort Calhoun Goal 1 50 0 ^ ^ ^ ^ ^ - ^ ^ ^ ^ ^ - - - ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ 12 / 600 300 / 0' ,z,,,, 1 7 14 21 28 DAILY THERMAL OUTPUT The above thermal output graph displays the daily operating power level, the 1500 thermal megawatt average technical specification limit, and the 1495 thermal megawatt Fort Calhoun goal. The cross hatched area represents the difference between the maximum allowable operation and the actual plant operat'on. The percent power operation of the Fort Calhoun Station was approximately 52.1% for the month of May. This low value for percent power operation-was due to power reductions for a turbine overspeed trip test and a main feedwater check valve leak. e, --~ ma

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' Equipment Forced Outage Rate

.12 GOOD R a o,1 4 ejg '~. i,: 1 bl$h,

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l ';ffi?! r.;w !-) 0 0 '86 '87 '88 Jun Jul A'ug Sep Oct Nov Dec Jan Fe'b M'ar A'pr May 1988 1989 E0VIPMENT FORCED OUTAGES PER 1000 CRITICAL HOURS There were zero forced outage hours reported for the Fort Calhoun Station during'the month of May, 1989. The last equipment forced outage occurred ~ in 1986 and was due to a failed electrical instrument inverter. $[F - Actual Operations Expenditures 80-X Operations Budget o M f 60-s i 1d l40-ol s na s r 20-s j 0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1989 15- - Actual Maintenance Expenditures 12

Maintenance Budget M

i 1d 9 lo ilol 6-na s r 3-s O Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1989 OPERATIONS AND MAINTENANCE BUDGET The Operations and Maintenance Budget Indicator shows the budget year to date as well as the actual expenditures for operations and maintenance for the Fort Calhoun Station. This indicator is one month behind the reporting month due to the time for collecting and processing the data. The budget year to date for operations was 23.2 million dollars for April while the actual cumulative expenditures for April totaled 26.7 million dollars. The budget year to date for maintenance was 3.7 million dollars for April while the actual cumulative expenditures for April totaled 5.5 million dollars.

500- .. Documents Scheduled for Review -X-Documents Reviewed

Overdue Documents 400-ND 300-

-r e " 200-ot fs /'~.. -s 100- / /

• --- 2'%

j XN-x-X N 0 Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct 1988 1989 DOCUMENT REVIEW The Document Review Indicator was changed for January, 1989. The Document Review Indicator now takes into account a 25% grace period (6 months) for overdue document reviews. This indicator shows the number of documents reviewed for the reporting month, scheduled for review, and the document reviews that are overdue. These document reviews are performed in house and include Special Procedures, the Site Security Plan, Maintenance Procedures, Preventive Maintenance, and the Operating Manual. The documents included in the Operating Manual are Standing Orders, the Technical Data Book, the Radiological Emergency Response Plan, Emergency Plan Implementing Procedures, Operating Procedures, Emergency Operating Procedures, Abnormal Operating Procedures, Operating Instructions, the Radiological Protection Manual, the Chemistry Manual, the Fuel Management Manual, Surveillance Tests, and Calibration Procedures. During May there were 45 document reviews completed while 24 document reviews were scheduled. At the end of May, there were 260 document reviews overdue.

ct 100-l Diesel Generator No. 1 -M-Diesel Generator No. 2 98- -e-Fort Calhoun Goal 96-G---G----O-----&----C - e---e----G= -Of = G-----O 94-l l l l X X X X m X'y X X X X X X 92, p e 90-r c e 88 n n t 86-GOOD 84-82-80 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1988 1989 DG RELIABILITY LAST IQO DEMANDS Diesel generator D-1 has a 95 percent reliability factor over the last 100 valid demands. Diesel generator 0-2 has a 94 percent reliability factor over the last 100 valid demands. The Fort Calhoun goal for the diesel generator reliability is 95%. Assuming that no failures occur to the diesels, D-2 should reach the 95% goal in 1990. _ T

l' j Diesel Generator No. 1 l -X-Diesel Generator No. 2 -e-Fort Calhoun Goal 100-l l 95-w -- G----&-- O-G- O-- - -0 =- G-S G-----O P / e r ," 90-X X X X X X X M i n t ^ 85-GOOD 80' Jun Jul Aug Sep Oct Nov Dec Jan-Feb Mar Apr May 1988 1989 DG RELIABILITY LAST 20 DEMANDS Diesel generator D-1 has not had a failure in the last 20 demands on the unit. The present reliability factor for D-1 is 100% over the last 20 demands. Diesel generator D-2 has had 1 failure in the last 20 demands. D-2 has a 95% reliability factor over the last 20 demands. 4 The Fort Calhoun goal for the diesel generator reliability for the last 20 demands is set at 95%. Diesel D-1 and D-2 presently meet this goal. 1 ) 1 u

l 800-March 1989 April 1989 I IMay 1989 0 600- 't k Fort Calhoun Goal a (zero M0's > 12 months old) \\ i 400-n 9 0 d E 200-l a s-p:j . i E e, a 0-5li- h-- ) 0-3 3-6 6-9 9-12 >12 Age in Months AGE OF OUTSTANDING MAINTENANCE ORDERS (NON-0UTAGE) As of May 31, 1989, there were a total of 1,497 outstanding non-outage maintenance orders. The above bar chart breaks down the maintenance orders by their age in months and trends each category over the previous three months. The Fort Calhoun goal is to have zero outstanding maintenance orders greater than 12 months old. As of May 31, the Fort Calhoun Station had 202 maintenance orders greater than 12 months old. l > l L_---___----

4 2000-3 March 1989 April 1989 1600 I 1May 1989 ) 1200-Fort Calhoun Goal 800- '400-E!!E""'-~- E ~ 0-Total Open Total Open Open Open MOs Open Safet/ High M0s > 3 Months Safety Related Priority Old Related MOs M0s M0s > 3 Months Old i MAINTENANCE ORDER BREAKOOWN (NON-00TAGE) A new goal was established for the Maintenance Order Breakdown indicator in March. The goal is to have zero M0's older than the average age of M0's that are greater than three months old. There is presently 1,497 total M0's with 807 open M0's greater than three months old. The May goal is to have less than 473 open M0's that are greater than three months old. The total number of open non-outage maintenance orders as of May 31, 1989, is shown, along with a breakdown by several l key categories.

rc o e .c - Corrective Maintenance Backlog > 3 Months Old 4-Industry Upper Quartile 60- ~ ii O O O O O O O +- -- - - O OM O 40-

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C e i n MD 20- + 0-- Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1988 1989 CORRECTIVE MAINTENANCE BACKLOG GREATER THAN 3 MONTHS OLD (NON-0UTAGE) The Fort Calhoun Station enrrective maintenance backlog greater than 3 months old increased in May to 53.9%. The total number of outstanding maintenance orders increased from 1,478 in April to 1,497 in May. The number of outstanding maintenance orders greater than 3 months increased from 766 in April to 807 in May. The industry upper cuartile value for corrective maintenance backlog greater than 3 months old is 44.1%. _ -___-____

l. / - Ratio of Highest Priority MOs to Total M0s Completed

30-p;.

i r c-20 e n 't-GOOD 3 + 10-i ' \\ k 0 Jun Jul .Aug Sep Oct Nov Dec Jan Feb Mar Apr May 19 1988-1989 j l l RATIO OF HIGHEST PRIORITY M0'S TO TOTAL M0'S COMPLETED (NON-0UlAGE) The purpose -of this indicator is to monitor the ability to effectively prioritize, lan, and schedule corrective maintenance. A hi her ratio indicates that a comparatively greater number of emergency type maintenance' activities have been required to support plant operation. In May, the ratio of highest priority M0's to total M0's completed decreased to 10.7%. The reason for this decrease was that there were a total of 365 M0's completed during the month with only 39 of these being of highest priority. 1 The industry upper quartile for the ratio of highest priority M0's to total M0's completed is no longer available This indicator was discontinued for 1989 by.INP0. l L' 27

1 l - Ratio of Preventive to Total Maintenance 1 + Industry Upper Quartile i 90 -e-Fort Calhoun Goal L l 80-70-P 60-

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~ / e n 50-0 0 0 O. O O O O O O' t A 40-GOOD 30-20 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1988 1989 RATIO 0F PREVENTIVE TO TOTAL MAINTENANCE (NON-0UTAGE) The ratio of preventive to total maintenance indicator shows the ratio of completed non-outage preventive maintenance to total completed non-ortage maintenance. The ratio of preventive to total maintenance at the Fort Calhoun Station increased to 64.9% in May. The Fort Calhoun goal is to have a ratio of I preventive to total maintenance greater than 60%. The industry upper quartile value for the ratio of preventive to total maintenance is 57.4%. The Fort Calhoun Station is currently in the upper quartile of nuclear plant performance in this area. l I - Preventive Maintenance Items Overdue f. 4- -<>- Industry Upper Quartile -e-Fort Calhoun Goal l I 3-P e GMD

r c.

2- + e .n t ~/c o ^ ^ ^ ^ ^ ^ ^ ^ ^ c ---e 1-j l l l l 0 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May i 1988 1989 9 EREVENTIVE MAINTENANCE ITEMS OVERDUE The purpose of this indicator is to monitor progrest in the administration and execution of preventive maintenance programs. A small percentage of preventive maintenance items overdue indicates a station commitment to the i preventive maintenance program and an ability to plan, schedule, and perform preventive maintenance tasks as programs require. The preventive maintenance items overdue value remained at 0.0% for the month of May. There were a total of 781 preventive maintenance items completed during the month with zero preventive maintenance items not completed within the allowable grace period. j 1 The Fort Calhoun goal is to have less than 1.2% preventive maintenance items overdue. The industry upper quartile for preventive maintenance items overdue is 1.5%. The Fort Calhoun Station is currently in the upper quartile for this indicator.

1 i >#v Total Control Room Instruments Out-of-Service Fas Out-of-Service Instruments Added During the Month l lOut-of Service Instruments Corrected During the Month + Industry Upper Quartile For Total Out-of-Service Instruments 35- -G-Fort Calhoun Goal For Total Out-of-Service Instruments 30-GOOD 25-4 20-15-l b L l =g; d 10- S ' s 3 ) r 1 g s s p r p__ 3-- _ ) 5-j [ i l = 0 l' Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1988 1989 NUMBER OF OUT-OF-SERVICE I CONTROL ROOM INSTRUMENTS j The Number of Out-of-Service Control Room Instruments Indicator has been changed for the month of May, 1989. In addition to the previously shown total number of control room instruments out-of-service, this indicator now shows the number of out-of-service control room instruments that were corrected during the reporting month and the number of control room instruments that were added to the l out-of-service control room instruments list during the reporting i month. This change is due to the Control Room Instruments Project established on April 18, 1989 to prioritize and expedite the i resolution of out-of-service control room instruments. There was a total 23 out-of-service control room instruments at the end of May. During the month of May, 9 out-of-service instruments were l corrected and 12 instruments were added to the out-of-service I instruments list. The Fort Calhoun goal is to have less than 7 out-of-service control room instruments. 4 The industry upper quartile value for the number of out-of-service, control room instruments is 9. i l

EM GM IN { ', f A ji9 igg / g g1-s "*V' &Tf46WA> Itf =::: / PE I&C - %,_cy #$r [ % WorkOrders(WO) l l Maintenance Orders (MO) { pf E Unestimated (UNE) PreventiveMaintenance(PM) f Training (TRA) l t S Calibration Procedures (CP) f R Surveillance Tests (ST) .(RAFT WORK ACTIVITY l The Craft Work Activity Indicator shows the percentage of a type of work each craft performed during the month. The crafts that are represented i in this indicator are Electrical Maintenance (EM), General Maintenance (GM), Mechanical Maintenance (MM), Pressure Equipment (PE), and Instrumentation and Control (I&C). Data for this indicator was not available for the month of May,1989. This indicator currently shows the data for the month of April, 1939. WORK ACTIVITY (IN PERCENT) CRAFT WO MO UNE,. PM TRA CP ST EM 64.02 12.54 5.13 7.98 7.69 0.00 2.64 ) 1 GM 0.00 64.88 30.63 0.00 4.49 0.00 0.00 { MM 0.00 55.50 24.61 14.61 5.28 0.00 0.00 PE 13.46 53.47 6.44 3.98 22.65 0.00 0.00 1 I&C 3.94 34.00 11.65 10.36 14.12 16.70 9.23 . i

- Maintenance Overtime 80 L 60-GOOD P + e r c 40-e n t 20- / 0 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 1988 1989 MAINTENANCE OVERTIME The Maintenance Overtime Indicator monitors the ability to perform the desired maintenance activities with the allotted resources. Excessive overtime indicates insufficient resource allocation and can lead to errors due to fatigue. The percent of overtime hours with respect to normal hours was 17.2% during the month of May, 1989. e -

l k-100-1 IIdentified Incidents R$ Incident Reports Opened Incident Reports Closed a b e r 60-o f I i n 40-s d i o l l n j t 20-s ._a l. i O Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1989 I PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE) The Procedural Noncompliance Incidents Involving Maintenance Indicator was added to the Fort Calhoun Station Performance Indicators Report for the month of March, 1989. This indicator shows the number of incidents identified (not yet written as an IR) each month involving maintenance, the number of incident reports opened each month involving maintenance, and the number of incident reports closed each month involving maintenance. .. Total Description March April May Year to date Incidents identified 11 1 1 115 Incident Reports Opened 41 7 9 119 Incident Reports Closed 6 13 6 51

L I u Confirmed'HPRDS Failures l ISuspected NPRDS Failures - Average CE Plant Confirmed NPRDS Failures 80-I i _- 60-a i 1 ~ u 40-p ' O. s 20-f l ..s m,a ~ 0-Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1988; 1989 NUMBER OF NUCLEAR PLANT RELIABILITY DATA SYSTEMS (NPRDS) REPORTABLE FAILURES The suspected NPRDS reportable fcilures are identified by possible equipment failures on the applicable Maintenance Order (MO). Only after the M0 has been completed can the determination be made whether the equipment has failed or not. The entire 12 month gra)h is updated on a monthly basis to reflect comp:eted M0's. In May, 1989 there were 0 confirmed NPRDS re?ortable failures and 75 suspected NPRDS failures. The average value for confirmed reportable equipment failures at similar Combustion Engineering (CE) designed plants is 7.7 failures per unit. The Fort Calhoun Station has a 12 month average value of 5.2 confirmed NPRDS failures. e _ _ _ _ - _ - _ _ _ _

e - Secondary System CPI 1.5- ~ * " "## # -s-Industry Upper Quartile j ~ l I 1- + - - - - + --+=-l---+ ---+---l + - - - - + g GOOD .36 I .5-E0 '87 '88 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 1988 1989 300- - Hours Chemistry is Outside OG Guidelines l 200-H GOOD 0 + { 100-31 m 0 0 '87 '88 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mer Apr 1988 1989 SECONDARY SYSTEM CHEMISTRY The top graph, Secondary System Chemistry Performance Index (CPI), is a calculation based on the concentration of key impurities in the secondary side of the plant. These key impurities are the most likely cause of deterioration of the steam generators. The monthly CPI is plotted relative to the EPRI chemistry limit for CPI. The CPI was reported as 0.38 for the month of April. The industry upper quartile value for this indicator is 0.20 The bottom - graph, Hours Chemistry is Outside Owners Guidelines, tracks the total hours of 13 parameters exceeding guidelines during power operation. In April, 1989, 'there ' were zero hours outside owners group guidelines. The industry upper quartile value for this indicator 8- - Primary System Chemistry Out of Limit 6-P e r c 4 3.0 E I2. G000 + 0 '87 '88 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 1988 1989 i PRIMARY SYSTEM CHEMISTRY PERCENT OF HOURS OUT OF LIMIT The primary System Chemistry - Percent of Hours Out of Limit indicator tracks the primary system chemistry performance by monitoring six key chemistry parameters. The Primary System Chemistry Percent of Hours Out of Limit was reported as 2.5% for the month of April.100% equates to all six parameters being out of limit for the I month. l 1 i l ! 3 i I 1

+ Auxiliary System Chemistry Out Of Limit + Industry Upper Quartile 40-GOOD + 30- ~ H o u 20-r s ' O O O O O O O O O O O \\ 10- 'N \\ \\ \\0 0 0 0 L .s .s '87 '88 May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr 1988 1989 AUXILIARY SYSTEM (CCW) CHEMISTRY HOURS OUTSIDE STATION LIMITS The Auxiliary System Chemistry Hours Outside Station Limits indicator tracks the monthly hours that the Component Cooling Water (CCW) system is outside the station chemistry limit. The above chemistry indicator is one month behind the reporting period due to the time needed for data collection and evaluation of the chemistry data for the station. The auxiliary system chemistry hours outside station limits for the month of April,1989 was reported as zero. l The industry upper quartile value for l auxiliary systems chemistry hours outside station limits is 2,. 6 hours. The Fort l-Calhoun Station is currently performing in the industry upper quartile.for this area. I l 1. _ _ - _. - - _ _ - _ _ _ - - _ -

5000-1 IMonth j E Quarter OPPD Limit [ Year 4000-3000-m R E 2000-1000-0 April 1989 MAXIMUM INDIVIDUAL RADIATION EXPOSURE The Maximum Individual Radiation Exposure graph is one month behind the reporting period due to the lag time involved with collecting and calculating the radiation exposure for the station. During April, 1989 an individual accumulated 204 mrem which was the highest individual exposure at the Fort Calhoun Station for the month. The maximum individual exposure so far for the second quarter of 1989 was 204 mrem. The maximum individual exposure for the year so far was 887 mrem. The maximum accumulated 1988 individual exposure was 2,371 mrem, received by a visiting contractor during the refueling outage. The OPPD limit for the maximum yearly individual radi,ation exposure is 4,500 mrem / year.

rf4 Monthly Contaminations 500i - Cumulative Contaminations -e-Fort Calhoun Goal + Industry upper Quartile 400 357 P l R e i r GOOD I n 4 n e 200-161 I l-0 ^ A C C C C C C C O g 100- O O ,..q -&

• g.-O v

v ^ ~ -e -O_,.4 '87 '88 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1989 TOTAL SKIN AND CLOTHING CONTAMINATIONS There was a total of 10 skin and clothing contaminations reported for the Fort Calhoun Station during May, 1989. These contaminations consisted of 7 skin ~ contaminations and 3 clothing contaminations. j There have been a total of 82 skin and I clothing contaminations so far in 1989. The l 1989 goal for skin and clothing is 110 contaminations. i l The industry upper quartile value for total skin and clothing contaminations is 129 per unit annually. i _ _ - _ _

l i - Decontaminated Auxiliary Building ) i 100-I 1 80-P 60-e n. t 40-A l j GOOD 20-O Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1988 1989 DECONTAMINATED AUXILIARY BUILDING This graph shows the percentage of the auxiliary building which is decontaminated (clean)basedonthetotalsquarefootage. As of May 31, 1989, 71.0% of the total square footage of the auxiliary building was decontaminated. . 7

L' j l l l Monthly Radioactive Gas Discharged l - Cumulative Radioactive Gas Discharged h -G-Cumulative Gosi 800-I GOOD 576 C 600-u r G---O--C 0 -- - G - 0 0--- -O - - O I--C O----O f 432 i Is ~ ' 400-200-1 0 '86 '87 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1988 GASEOUS RADIOACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT The gaseous radioactive waste being discharged to the environment is shown for 1988. A total of 785.0 curies have been released to the environment from January through December of 1988. The Fort Calhoun Station goal was 450 curies for this indicator. The high amount of gaseous radioactive waste released to the environment in October was caused by the purging of containment in preparation for the 1988 refueling outage. The gaseous radioactive waste being discharged to the environment is calculated every six months. I IMonthly Radioactive Liquid Discharged - Cumulative Radioactive Liquid Discharged -G-Cumulative Goal l 228 250-C O --G---G---O---G -- O-0 0 ~ - u--- v u r 150-Goop i e 100- + i s 50- 'I I' 'I I-87 0 '85 '86 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 192 200-i 1l132 B o I I 144 1G 150-1aE iif o1 f 100-no1 j snu i 50-se o n i H 'I I' f t 0 '85 '86 '87 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1988 1 1 ) LIOVID RADI0 ACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT The liquid radioactive waste being discharged to the environment is shown for 1988. The liquid radioactive waste that was discharged to the environment totaled 231 curies and 147.6 billions of gallons of liquid effluent (radioactive liquid waste plus dilution water) from January through December 1988. The Fort Calhoun Station goal for 1988 was 225 curies. The liquid radioactive waste being discharged to the environment is calculated every six months. I 10- - Amount of Work On Hold Awaiting Parts 8-GOOD P '6- + l e c o E 4-2- ^ 0 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1988 1989 AMOUNT OF WORK ON HOLD AWAITING PARTS (NON-0UTAGE) This. procurement indicator displays the amount of open, non-outage, maintenance ' items that are on hold awaiting parts, to the total amount of open, non-outage, maintenance items, expressed as a percentage. The percentage of work on hold awaiting parts increased to 4.7% in May. This increase is due to parts ordering during the outage to perform a turbine overspeed trip test. As of May 31, 1989, there were 6 total of 1,497 open, non-outage, maintenance items with 71 of these items on hold awaiting parts. The April, 1989, Performance Indicators Report stated that a total of 127 maintenance items were on hold awaiting parts at the end of April. The actual number of maintenance items on hold awaiting parts at the end of April was 36. This change in the number of maintenance items awaiting parts also changed the. ratio of maintenance items awaiting parts from 8.6% reported in the April, 1989, Performance Indicators Report to an actual value of 2.4% for April, 1989. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -

1 - Spare Parts Inventory Value M. i' 1 o 7 n s y N D o I 6- .j. ar s ~ 5 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1988 1989 SPARE PARTS INVENTGRY VALVE The spare parts inventory value at the Fort Calhoun Station at the end of May, 1989 was reported as $6,759,606. I i i 44

400- '{ - Spare Parts Issued O u s 300-a n. d' s 200-o. f 1 i 0 O 1 100-1 a r s -0 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1988 1989 l SPARE PARTS ISSUED The value of the spare parts ' issued for the Fort Calhoun Station during May, 1989 totaled $114,526. l 4 i j. LE--

1 700- - Total Modification Packages Open 640 600-1 500-J 425 f 384 400- ~ 300-y a gi i E E 200 '86 287 '88 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1988 1989 OUTSTANDING MODIFICATIONS The total number of outstanding modifications decreased by one in May. CATEGORY MAR 82APR 81 MAY 89 Form FC-1133 Backlog /In Progress 120 117 106 Mod Requests Being Reviewed 150 168 185 Design Engr. Backlog 3 0 0 l Design Engr. In Progress 57 59 55 Construction Backlog /In Progress 46 45 45 Desion Enor, Vodate Backloo/In Prooress 52 45 42 Total 428 434 433 i i

l 1 i l. Temporary Electrical Modifications M 80- -e-Temporary Mechanical Modifications 1 L o-L Nd u i 60-N' af c 40-ra , e- ----g -b-----b-----A Kg4 g, -e { oj 20- 's fo l 0 I n i 5 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May 1988 1989 March 1989 l M

• April 1989

) 25 N I IMay 1989 l ui 20-l 0 f-l b i 15-Oc r a ' 10 u e = t yf 5-l- j n l 5 0-3 3-6 6-9 9-12 > 12 Age in Months TEMPORARY MODIF! CATIONS (EXCLUDING SCAFFOLDING) The top graph, Number of Temporary Modifications, displays a monthly trend of installed electrical and mechanicai temporary modifications. There was a l total of 30 electrical jumpers and 27 temporary meciierical jumpers existing in the Fort Calhoun Station at the end of May, 1989. The bottom graph, Ace of Temocrary Modifications, displays the age of all electrical and mechanical temporary modifications by months installed in the plant. B. I 12 - Recordable' Injury Cases Frequency Rate 10-F ~ r e 8-q ?, u e-" 6-GOOD y R 4 a 4-t 2.5 2.6 e 106-2- 0 '86 '87 .88 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1989 RECORDABLE INJURY CASES FRE00ENCY RATE A recordable injury case is reported if Nuclear Production Division personnel are injured on the job and require corrective medical treatment. The recordable cases freq9ency rate is computed on a year-to-date basis. l There was one recordable injury case reported for the month of May. There have been a total of two recordable injury cases so far in 1989. There were eleven recordable cases reported in 1988, eight reported in 1987, and four reported in 1986. - _ _ _ _ -. _ _ _ _ _ - _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ -

- Minor Injury Reports Filed Per Month ~25-M- i 20-n 0 r 15-7 n j u 10-r- i 5-0' Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug 1988 1989 H13QR INJURY CASES PER MONTH The Minor Injury Cases per Month indicator shows the number of minor injury cases each month involving OPPD employees. During the month of May,1989 there were a total of 5 minor injury cases reported. i.- There have been a total of 42 minor injury cases reported in 1989. $ f' __ l

i .. Licensee Event Reports l l Personnel Errors Reported in LERs - Cumulative Licensee Event Reports j Cumulative Personnel Errors Reported.in LERs 50-46 39 40 ] l 30-26 20-g 10-1 5 1 - 0 '86 '87 '88 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1989 NUMBER OF PERSONNEL ERRORS REPORTED IN LER'S The Licensee Event Reports (LERs) are reported for the month that they are submitted to the NRC. In May, 1989 there were 4 LERs submitted with one attributable to personnel error. There have been 15 LERs re)orted so far in 1989 with only 4 attributable to personnel errors. t w I INuclear Divisions Turnover Rate ) - OPPD Corporate Turnover Rate i p 5-l T ~ 4-f 'u t r n. o 3-y .e. r ,,l" 2-R a .t~ e-1- O H-Nuclear Operations Production Engineering Quality Division Division and Environmental Affairs PERSONNEL TURNOVER RATE The turnover rate for three Nuclear Divisions is shown for the last nine months. j The personnel turnover rate is plotted against the OPPD corporate turnover rate of 4.0%. This OPPD corporate turnover rate is based on the turnover rate over the last three years.

t 500-488 @ Actual Staffing i IAuthorized Staffing j 440 1 p 1 l w@pg; 400-W:@j hk - nu p ri 21:4, 'M c

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(:~ \\ftf .. c. \\ \\ l U. 'b. glggsll1 y d' )$k ih h N; .j ...>..,.b. l 77% ypj 1: ;. 100-ydgjpegi r y y _al_;;;N= W iddl iMW4p@% 38 45 Q fij 0 'hh] Elifl8dB RPJirM@ ~ ~ ' ' " " ' " " Nuclear Operations Production Engineering Quality Division Division and Environmental ~ Affairs STAFFING LEVEL The authorized and actual staffing levels are shown for the three Nuclear Divisions. ) l I 1SR0 Initial Exam Eff SRO Requalification Exam i 100- 'ldih$ M& V 8~ WE L1 ( ) wmm m::hf?W1 m ;a g 9 1 ? :;?l^XT'f31 (( p v ypgy

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+gw 60-y;f'60$i ..f;;;;) ll j s @f'N pyyf(Q il, s R . >..s . mg,;;- i sg a se.n w p j 40-ll { 2 k 20-No Initial Exams j Taken 1 0 1987 1988 1989 1 SRO LICENSE EXAMINATION PASS RATIO There were five Senior Reactor Operator (SRO) exams taken in May. These five exams were OPPD administered requalification exams. ) OPPD ADMINISTERED i4RC ADMINISTERED Initial Exam Requal Exam Initial Exam Requal Exam 'DATE % PASS RATIO % PASS RATIO % PASS RATIO % PASS RATIO 100 100 March 87 June 87 100 February 88 80 100 100 67 March 88 100 i April 88 ) 100 July 88 67 April 89 100 May 89

l l IRG Initial Exam ) 4 R0 Aequalification Exam I l 100-80-1 p j 60-s R $i 40-O l 20-NO Requal Exams Taken 1987 1988 1989 RO LICENSE EXAMINATION PASS RATIO There were five Reactor Operator (RO) exims taken in May. These five exams were OPPD administered requalification examinations. OPPD ADMINISTERED NRC ADMINISTERED Initial Exam Requal Exam Initial Exam Requal Exam DATE % PASS RATIO % PASS RATill % PASS RATIO % PASS RATIO June 87 100 February 88 100 March 88 100 100 100 July 08 100 April 89 100 100 May 89 100

4-iW fi0 Hot License Exams Administered I'l R0 Hot License Exams Passed N u 3-m b I e I 'l I i o.2 - 1 g! E h {n 1[ x j a l m '1 ll ~l s l 0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1989 EO HOT LICENSE EXAMS The R0 Hot uicense Exams indicator shows the number of R0 Hot License exams or quizzes taken and passes each month. During the mo;tth of April,1939, two exams were adminis'.ered and all three candidates passed the e::am. This indicator is one month behind due to the time needed to collect and process the data. l 55

f Hotlines Initiated M Hotlines Closed 30- !!!! Hotlines Overdue M Hotlines Remaining Open 25-m b 20 r o ip I 15-hi H l o 10-i f, t I 1 i E : ':I ! k II lll l ll l l 5-l ll l l l ll !!l 8 l ! ll 5i 0 Jan Feb Mar. Apr May Jun Jul Aug Sep Oct Nov Dec 1989 l HOTLINES This indicator shows the number of issues of Hotlines that are initiated, the number of issues closed, the number of issues overdue, and the number of issues that remain open. i l During the month of May, 1989, there were 10 l Hotlines initiated, 4 Hotlines closed, 11 Ho,tlines overdue, and 14 Hotlines remaining g open. P '

R$ Planned Classroom Hours [ l l l Actual Classroom Hours T h 3-o u a ~ n l l d l l h(l ~ s 2 o 4 f f l h H o u l-r Jr s O Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1989 CLASSROOM (INSTRUCTOR) HOURS The Classroom (Instructor) Hours indicator was added to the Fort Calhoun Station Performance Indicators Report for the month of March, 1989. This indicator displays the number of planned classroom hours and the number of actual classroom hours for the Fort Calhoun Station. The planned classroom hours for January and February l are low because Maintenance and General Employee Training were not figured into the ' schedule for these months. l The April data for this indicator is not available i due to the inadvertent deletion of the computer program that processes this information. This indicator is one month behind the reporting month due to the time to collect and process the needed information. _ _ -

20-l 1 Operations L 19-M Maintenance p 18-Chemistry and Radiation Protection 7 E Tecnnical Support h M General Er7 oyee Training 1 13 ner 14-5 13-12-L d 11-5 10-o 9-f 8-l' H l o 6-BR u 5-n- 4- [ s 3-g 2-1- l 0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1989 TOTAL HOURS OF STUDENT TRAINING This indicator shows the total number of student hours for Operations, Maintenance, Chemistry and Radiation Protection, Technical Support, General Employee Training, and Other training conducted for the Fort Calhoun Station. The hpril data for this indicator is not available due to the inadvertent deletion of the computer program that processes this information. This indicator is one month behind the reporting month due to the time needed to collect and evaluate the data. Total Hours TRAINING FEBRUARY 1989 MARCH 1989 Operations 2,517 3,387 Maintenance 740 2,023 Chemistry and 290 1,771 Radiation Protection Technical Support 1,568 2,428 General Employee Training 2,524 1,805 pther 1,176 1.142 Total 8,815 12,556 - - _ _ - _ _ _ _ _ _ _ _ _

l - violations per 1000 Inspection Hours -e-Fort Calhoun Goal 14 15-l 'G000 L M. 6 "

• E 9-3___

_ ___e o.___e.___o = e____e _ 3 __e ___o l. 6-3- 1. 0 '86 '87 '88 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 1989 l VIOLATIONS PER 1000 INSPECTION HOURS This indicator displays the number of NRC violations cited in inspection reports per 1000 NRC inspection hours. This indicator was calculated using the number of violations and the number of inspection hours from the months of December, 1988, through May, 1989. The violations per 1000 inspection hours indicator was reported as 8.0 for the month of May, 1989. There were two violations cited in three inspection reports for the month of April. There have been a total of fourteen violations cited with 1,348 inspection hours in 1989. The goal for the number of violations per 1000 inspection hours is less than 8.6. - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

l 1: - Total Outstanding DR/QR's "J Outstanding DR/QR's > Six Months Old M Outstanding DR/QR's That Are Modification Related 1 200-r i 150-D- R l 0 R 100-s. ,s,s 50-V &,.x :. S.,,,,N, ' *: #V A" ..4.. c s,... ~. '.,;' k f ':':' A '[ .k .':, ? _ p _ ' ' ' ' j;, _ ; ':' D,h, k 7 C j' ';. : ;,. e.'. .1 !.lh?:,'j ,,4,

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g. y s yp.:7. _. ,..Aa , _.y>. gy if,? ..s: y... _ ' ~ s j ; 3, + ' " ' " " " ' 0-Jun Jul Aug Sep-Oct Nov Dec Jan Feb Mar Apr May 1988 1989 OUTSTANDING DEFICIENCY AND OUALITY REPORTS The Outstanding Deficiency and Quality Reports Indicator has been changed for the month of May, 1989. This indicator now shows outstanding Deficiency and Quality reports that are associated with modifications. I As of the end of May, 1989 there were 193 l outstanding DR/QR's reports, 41 DR/QR's that are greater thar six months old, and 9 DR/QR's that are m3dification related. l l _ _____- _ _ - _ _

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ESCALATED ENFORCEMENT HISTORY L Escalated enforcement includes level III, II, and I violations issued by the Nuclear Regulatory Commission for deficiencies discovered at the Fort Calhoun Station. Escalated enforcement also includes civil penalties which are usually assessed with level III and higher violations. Listed below is the escalated enforcement history for the Fort Calhoun Station. ESCALATED ENFORCEMENT

1. February 1985 Site Security Multiple Level IV and V Violations that were escalated to a Level III.

A civil penalty of $21,425 was assessed.

2. April 1986 Qualification of Electrical Penetrations - Level III Viol,1 tion.

No civil penalty was assessed.

3. May 1986 Radiological Protection Level III Violation.

No civil penalty was assessed. (

4. December 1986 Physical Security - Level IV Violation.

A civil penalty of $15,000 was assessed.

5. January 1987 Lack of Adequate Safety Evaluation for Emergency Modification - Level III Violation.

A civil penalty of $50,000 was assessed.

6. January 1988 Unlocked High Radiation Doors and Lack of Health Physics Coverage to Very High Radiation Areas Level III Violation.

A civil penalty of $75,000 was assessed.

7. February 1988 Design Evaluation, Design Implementation and Classification / Reporting, and Corrective Action of l

Water Intrusion into the Instrument Air System - 3 l Level III Violations. A civil penalty of $175,000 was assessed. l

8. May 1988 Unlocked Very High Radiation Door and deficiencies identified in the Radiological Protection Program - 2 Level III Violations.

A civil penalty of $112,500 was assessed. __

e ESCALATEDENFORCEMENTHISTORY(CONTINUED) ESCALATED ENFORCEMENT

9. October 1988 A missing cap on a 3/8 inch containment line, SIRWT check valve test failures, and Safety l

Analysis for Operability - tavel III violation. l A civil penalty of $50,000 was assessed. l

10. October 1988 Errors in Cycle 11 Setpoint Analysis and incorrect information submitted in a response.

l No civil penalty was assessed. l - _ _ _ - - _ _ _ _ - _ _ _

ENFORCEMENT CONFERENCES AND MANAGEMENT MEETINGS Enforcement conferences are held with the NRC on potential higher level violations. Listed below are the recent enforcement conferences and management meetings held with the NRC. s RECENT ENFORCEMENT CONFERENCES AND MANAGEMENT MEETINGS

1. August 1988 Two management meetings were held with the NRC

~ in August. One meeting was held to discuss the security program while another meeting was held on the OPPD independent appraisal results.

2. October 1988 Two management meetings were held with the NRC v

in October. One meeting was held concerning the security program while another meeting was held to discuss the training program and the radiation protection program.

3. November 1988 Two management meetings were held with the NRC in November. One meeting was held concerning the Safety i

Enhancement Program while another was -held to discuss Decay Heat Removal.

4. January 1989 One management meeting was held with the NRC in January. This meeting was held concerning the new Site Security Plan.

5. February 1989 One Enforcement Conference was held with the NRC in February. This Enforcement Conference was held concerning the Radiological Protection Program.

6. February 1989 One management meeting was held with the NRC in February. This management meeting was held concerning the Safety Enhancement Program.

7. April 1989 One management meeting was held with the NRC in A)ril. This management meeting was held concerning tie Safety Enhancement Program.

8. May 1989 One management meeting was held with the NRC in May.

This management meeting was held concerning the Safety Enhancement Program.

SIGNIFICANT ITEMS OF INTEREST This section is intended to provide information on events which are significant to the Fort Calhoun Station and will give a " heads-up" look at what is scheduled in the coming months. The Fort Calhoun Station went critical on January 29, 1989 et 9:27 a.m. The Fort Calhoun Station went on-line on January 31, 1989 at 4:46 p.m. The 1990 refueling outage is scheduled for February, 15, 1990. Significant Emergency Preparedness Drills are scheduled for June 7 and June 28, 1989. The next Safety Audit and Review Committee (SARC) . Meeting is scheduled for July 12, 1989. The next Quarterly Safety Enhancement Program (SEP) Update Meeting with the NRC is tentatively scheduled for sometime during the first week in August, 1989. The Graded Annual Emergency Exercise for the Fort 'Calhoun Station is scheduled for July 19,1989. NRC Region IV and the states of Nebraska and Iowa will be participating. Emergency Preparedness Accountability Drills will be held June 21 and June 23, 1989. These drills will require assembly of personnel to account for all personnel in the protected area. Site evacuation is not planned. - - _ _ - - - - _

FORT CALHOUN PERFORMANCE PARAMETER DEFIN!TIONS AGE OF OUTSTANDING MAINTENANCE ORDERS This indicator tracks the total number of outstanding Maintenance Orders at the Fort Calhoun Station versus their age in months. r AMOUNT OF WORK ON HOLD AWAITING PARTS This indicator is defined as the percentage of open, non-outage, maintenance orders that are on hold awaiting purts, to the total number of open, non-outage, maintenance orders. AUXILIARY SYSTEMS CHEMISTRY HOURS OUTSIDE STATION LIMITS The cumulative hours that the Component Cooling Water system is outside the station chemistry limit. The hours are accumulated from the first sample exceeding the limit until additional sampling shows the parameter to be back within limits. CLASSROOM (INSTRUCTOR) HOURS The number of planned classroom hours and the number of actual classroom hours for the Fort Calhoun Station. CONDENSER AIR INLEAKAGE The typical volumetric flow rate of air leakage into the' secondary system, measured in Standard Cubic Feet per Minute (SCFM) during stable, full-power operation with two condenser evacuation pumps operating. CORRECTIVE MAINTENANCE BACKLOG GREATER THAN 3 MONTHS OLD The percentage of total outstanding maintenance work requests, not requiring an outage, that are greater than three months old at the end of the period reported. CRAFT WORK ACTIVITY The percentage of a type of work performed by each craft during the reported month. DAILY THERMAL OUTPUT The daily core thermal output as measured from computer point XC105 in thermal megawatts. m.

FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) l DIESEL GENERATOR RELIABILITY A Diesel Generator (DG) unit consists of the engine, generator, combustion air system, cooling water system, fuel supply system, lubricatin controls, g oil system, starting air system, autostart controls, manual and diesel generator breaker. Reliability of each DG unit will be reported for two situations, one for the last 20 demands and one for the last 100 demands. Reliability is the ratio of the number of successful runs to the number of demands, for each individual DG unit. A successful run is defined as a start of a DG unit and the loading of this unit to a minimur. of 50% rated load (1250 KW) for a minimum time period of 60 minutes. A failure is defined as the failure to start, accelerate, and assume the design rated load for the given time period as specified for an emergency or a valid test. The total number of demands (or valid tests) will be equal to the sum of the failures and the successful runs. This definition of DG Reliability was taken from the U.S. Nuclear Regulatory Commission " Regulatory Guide 1.108, Revision 1". This is the definition being applied in calculating the diesel generator reliability at the Fort Calhoun Station. DISABLING INJURY FAE00ENCY RATE (LOST TIME ACCIDENT RATE) This indicator is defined as the number of accidents for all utility personnel permanently assigned to the station, invviving days away from work per 200,000 man-hours worked (100 man-years). This does not include cor, tractor personnel. DOCUMENT REVIEW The Document Review Indicator shows the number of documents reviewed during the reporting month, the number of documents scheduled for review during the reporting month, and the number of document reviews that are overdue. EOUIPMENT FORCED OUTAGES PER 1000 CRITICAL HOURS Equipment forced outages per 1000 critical hours is the inverse of the mean time between forced outages caused by equipment failures. The mean time is equal to the number of hours the reactcr is critical in a period (1000 hours) divided by the number of forced outages caused by equipment failures in that period. FORTCALHOUNPERFORMANCEPARAMETERDEFINITIONS(CONTINUED) E0VIVALENT AVAILABILITY FACTOR This indicator is defined as the ratio of gross available generation to gross maximum generation, expressed as a percentage. Available generation is the energy that can be produced if the unit is operated at the maximum power level permitted by equipment and regulatory limitations. Maximum generation is the energy that can be produced by a unit in a given period if operated continuously at maximum capacity. FORCED OUTAGE RATE This indicator is defined as the percentage of time that the unit was unavailable due to forced events compared to the time planned for electrical generation. Forced events are failures or other unplanned conditions that require removing the unit from service before the end of the next weekend. Forced events include startup failures and events initiated while the unit is in reserve shutdown (i.e., the unit is available but not in service. FUEL RELIABILITY INDICATOR This indicator is defined as the steady-state primary coolant I-131 activity, corrected for the tramp uranium contribution and normalized to a common purification rate. Tramp uranium is fuel which has been deposited on reactor core internals from previous defective fuel or is present on the surface of fuel elements from the manufacturing process. Steady state is defined as continuous operations above 85 percent power for at least seven days. GASEOUS RADI0 ACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT This indicator displays the total number of Curies of all gaseous radioactive nuclides released from the Fort Calhoun Station. GROSS HEAT RATE Gross heat rate is defined as the ratio of total thermal energy in British Thermal Units (BTV) produced by the reactor to the total gross electrical energy produced by the generator in kilowatt-hours (KWH). HOTLINES The number of Hotlines that are initiated, closed, overdue, and open for a given month. A Hotline is a training document sent out for immediate review. The Hotline should be reviewed and signed within 5 days of l receipt of the Hotline. f

FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) HOURS CHEMISTRY IS OUTSIDE OWNERS GROUP GUIDELINES Total hours for 13 secondary side chemistry parameters exceeding guidelines during power operation. Power operation is defined as greater than 30% power. The 13 parameters tracked are steam generator pH, cation conductivity, boron silica, chloride, sulfate, sodium, feed water pH, dissolved oxygen, hydrazine, iron, copper, and condensate pump discharge dissolved oxygen. LIOUID RADIOACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT This indicator displays both the total volume of liquid effluent (radioactive liquid waste plus dilution water) and the associated Curies. discharged from the Fort Calhoun Station to the Missouri River. MAINTENANCE ORDER BREAKOOWN This indicator is a breakdown of all open non-outage maintenance orders by several categories. MAINTENANCE OVERTIME The percentage of overtime hours compared to normal hours for maintenance. This includes OPPD personnel as well as contract personnel. MAXIMUM INDIVIDUAI. RADIATION EXPOSURE The total maximum amount of Gamma and Neutron (Whole Bbdy) radiation received by an individual person working at the Fort Calhoun Station on a monthly, quarterly, and annual basis. MINOR INJURY CASES PER MONTH The number of minor injury cases (short-form cases) involving OPPD employees. NUMBER OF NUCLEAR PLANT RELIABILITY DATA SYSTEM (NPRDS) FAILURE REPORTS SUBMITTED L-The data plotted is the number of suspected and confirmed NPRDS component failures. The suspected NPRDS failures are designated as such on the l applicable equipment Maintenance Order. NPRDS is the Nuclear Plant Reliability Data System, and is a utility industry users group program which has been outlined by INP0 and implemented at the Fort Calhoun Station. 1 m - 7 L

FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) NUMBER OF OUT-OF-SERVICE CONTROL ROOM INSTRUMENTS A control room instrument that cannot perform its design function is considered as out-of-service. A control room instrument which has had a Maintenance Order (MO) written for it and has not been repaired by the end of the reporting period is considered out-of-service and will be counted. The duration of the out-of-service condition is not considered. b Computer CRTs are not considered as control room instruments. NUMBER OF PERSONNEL ERRORS REPORTED IN LER'T The number of Licensee Event Reports (LERs) attributed to personnel error on the original LER submittal. NUMBER OF VIOLATIONS PER 1000 INSPECTION HOURS L This indicator is defined as the number of violations sited in NRC inspection reports for the Fort Calhoun Station per 1000 NRC ins)ection hours. The violations are reported in the year that the inspect on was actually performed and not based on when the inspection report is received. The hours reported for each inspection report are used as the inspection hours. OPERATIONS AND MAINTENANCE BUDGET The year to date budget compared to the actual expenditures for operations and maintenance. OUTSTANDING MODIFICATIONS The number of Engineering Evaluation'and Assistance Requests (EEAR'S) and authorized Modification Requests (MR'S) in any state between Division Manager approval of an EEAR and the completion of the drawing update. Form 'B' Backlog /In Progress The Form ' A' has been approved but the Form 'B' has not been signed off. Minor Modification Backlog /In Progress Minor modifications that GSE has approved but the plant has not issued a Construction Package. Modification Requests Being Reviewed The plant is reviewing these Modification Requests and will assign a year for construction to be completed or will submit an approval for cancellation. -

FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) OUTSTANDING MODIFICATIONS (CONTINUED) GSE Design Backlog The plant has assigned a year in which construction will be completed but GSE has not started design work. GSE Design In Progress The plant has assigned a year in which construction will be completed and GSE design work is in progress. This also includes minor modifications for which the Form 'B' has been issued and GSE has not returned the Form 'D' to the plant. Construction Backlog /In Progress The Construction Package has been issued or construction has begun but the modification has not been accepted by the System AcceptanceCommittee(SAC). GSE Update Backlog /In Progress GSE has received the Modification Completion Report but the drawings have not been updated. PERCENT OF OR/0R'S GREATER THAN SIX MONTHS OLD This indicator displa Quality Reports (QR's)ys the percentage of Deficiency Reports (DR's) and that are greater than six months old. PERSONNEL RADIATION EXPOSURE (CUMULATIVE) Collective radiation exposure is the total external whole-body dose received by all on-site personnel (including contractors and visitors) during a time period, as measured by the thermoluminescent dosimeter (TLD). Collective radiation exposure is reported in units of man-rem. PERSONNEL TURNOVER RAH The ratio of the number of turnovers to average employment. A turnover is a vacancy created by voluntary resignation from the company Retirement, death, termination, transfers within the company, and part-chae employees are not considered in turnover. PREVENTIVE MAINTENANCE ITEMS OVERDUE This indicator is defined as the percentage of preventiu maintenance items in the month that were not completed by the scheduled date plus a grace period equal to 25 percent of the scheduled interval. _

FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) PRIMARY SYSTEM CHEMISTRY - PERCENT OF HOURS OUT OF LIMIT The percent of hours out of limit are for six primary chemistry parameters divided by the total number of hours possible for the month. The key parameters used are: Lithium, Chloride, Hydrogen, Dissolved Oxygen, Fluoride, and Suspended Solids. EPRI limits are used. PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE) The number of identified incidents, the number of opened incidents, and the number of closed incidents each month involving maintenance. RATIO 0F HIGHEST PRIORITY M0'S TO TOTAL M0'S COMPLETED This indicator is defined as the ratio of the number of highest priority, non-outage, corrective maintenance orders (priority 4 or 5) to the total number of non-outage, corrective maintenance orders completed, expressed as a percentage. RATIO OF PREVENTIVE TO TOTAL MAINTENANCE The ratio of preventive maintenance (including surveillance testing and calibration procedures) to the sum of non-outage corrective maintenance and preventive maintenance completed over the reporting period. The ratio, expressed as a percentage, is calculated based on man-hours. RECORDABLE INJURY CASES FRE00ENCY RATE (RECORDABLE INJURY RATE) The number of injuries requiring more than normal first aid per 200,000 manhours worked. R0 HOT LICENSE EXAMS This indicator shows the number of R0 Hot License exams or quizzes taken and passed for the month they were taken. R0 LICENSE EXAMINATION PASS RATIO The ratio of station candidates passing both the oral and written NRC Reactor Operator (RO) license examination to the total number of candidates taking examinations. SECONDARY SYSTEM CHEMISTRY PERFORMANCE INDEX The Chemistry Performance Index (CPI) is a calculation based on the concentration of key impurities in the secondary side of the plant. These key impurities are the most likely cause of deterioration of the steam generators. The chemistry parameters are reported only for the period of time greater.than 30 percent power.

FORTCALHOUNPERFORMANCEPARAMETERDEFINIT!0NS(CONT!NUED) SECONDARY SYSTEM CHEMISTRY PERFORMANCE INDEX (CONTINUED) The following equation is how the CPI is calculated: CPI = ((Ka/1.2) + (Na/20) + (Cl/20) + (S0 /20) + (0 /10)) / 5 4 2 Where the following parameters are monthly averages of; Ka = Steam Generator Blowdown Cation Conductivity Na = Steam Generator Blowdown Sodium Concentration C1 = Steam Generator Blowdown Chloride Concentration Steam Generator Blowdown Sulfate Concentration SO 4 = Condensate Pump Discharge Dissolved Oxygen Concentration 02 = SPARE PARTS INVENTORY V'ALUE, The dollar value of the spare parts inventory at the end of the reporting period. SPARE PARTS ISSUED The dollar value of the s)are parts issued for the Fort Calhoun Station during the reporting perioc. SRO OPERATOR LICENSE EXAMINATION PASS RATIO The ratio of station candidates passing both the oral and written NRC Senior Reactor Operator (SRO) license examination to the total number of candidates taking examinations. TEMPORARY MODIFICATIONS The number of temporary mechanical and electrical configurations to the plant's systems. Temporary configurations are defined as electrical jumpers, electrical blocks, mechanical jumpers, or mechanical blocks which are installed in the plant operating systems and are not shown on the latest revision of l the P&ID, schematic, connection, wiring, or flow diagrams. Jumpers and blocks which are installed for Surveillance Tests, Maintenance Procedures, Calibration Procedures, Special Procedures, or l 0)erating Procedures are not considered as temporary modifications unless tie jumper or block remains in place after the test or procedure is complete. Jumpers and blocks installed in test or lab instruments are not considered as temporary modifications. Scaffolding is not considered a temporary modification. FORTCALHOUNPERFORMANCEPARAMETERDEFINITIONS(CONTINUED) TEMPORARY MODIFICATIONS (CONTINUED) t Jumpers and blocks which are installed and for which EEAR's have been submitted, will be considered as a temporary modifications until final resolution of the EEAR and the jumper or block is removed or is permanently recorded on the drawings. TOTAL HOURS OF STUDENT TRAINING The total number of student hours of training for Operations, Maintenance, Chemistry and Radiation Protection, Technical Support, General Employee Training, and Other training conducted for the Fort Calhoun Station. TOTAL SKIN AND CLOTHING CONTAMINATIONS Reportable skin and clothing contaminations above background levels greater than 5000 dpm/100 cm squared. UNPLANNED AUTOMATIC REACTOR SCRAMS WHILE CRITICAL This indicator is defined as the number of unplanned automatic scrams (reactor protection system logic actuations) that occur while the reactor is critical. The indicator is further defined as follows: Unplanned means that the scram was not part of a planned test or evolution. Scram means the automatic shutdown of the reactor by a rapid insertion of all control rods that is caused by actuation of the reactor protection system. The scram signal may have resulted from exceeding a setpoint or may have been spurious. Automatic means that the initial signal that caused actuation of the reactor protection system logic was provided from one of the sensors monitoring plant parameters and conditions, rather than the manual scram switches (or pushbuttons) in the main control room. Critical means that during the steady-state condition of the f reactor prior to the scram, the effective multiplication factor (keff) was equal to one. UNPLANNED SAFETY SYSTEM ACTUATIONS This indicator is defined as the sum of the following safety system actuations: the number of unplanned Emergency Core Cooling System (ECCS) actuations that result from reaching an ECCS actuation setpoint or from a spurious / inadvertent ECCS signal

FORT CALHOUN PERFORMANCE PARAMETER DEFINITIONS (CONTINUED) UNPLANNED SAFETY SYSTEM ACTUATIONS (CONTINUED) the number of unplanned emergency AC power system actuations that result from a loss of power to a safeguards bus An unplanned safety system actuation occurs when an actuation setpoint for a safety (system is reached or when a spurious or inadvertent signal is generated ECCS only), and major equipment in the system is actuated. Unplanned means that the system actuation was not part of a planned test or evolution. The ECCS actuations to be counted are actuations of the high pressure injection system, the low pressure injection system, or the safety injection tanks. VOLUME OF LOW-LEVEL SOLID RADIOACTIVE WASTE This indicator is defined as the volume of low-level solid radioactive waste produced, in final form ready for burial, during a given period. It is calculated using the amount of waste actually shipped for disaosal, plus the change in inventory of waste in on-site storage in final form ready for burial. The volume of radioactive waste that is not yet in final form ready for shipment is not included. Low-level solid radioactive waste consists of dry active waste, sludges, resins, and evaporator bottoms generated as a result of nuclear power plant operation l l and maintenance. Dry active waste includes contaminated rags, cleaning materials, disposable protective clothing, plastic containers, and any other material to be disposed of at a low-level radioactive waste disposal site, except resin, sludge, or evaporator bottoms. Low-level refers to all radioactive waste that is not spent fuel or a by-product of l spent fuel processing. 1 l l

BASfS FOR ESTABLISHING 1989 PERFORMANCE XNDICATOR GOALS This section will explain the basis used in establishing the 1989 performance goals. FORCED OUTAGE RATE AND EOUIVALENT AVAILABILITY FACTOR The Forced Outage Rate (FOR) and Equivalent Availability Factor (EAF) goals have been established from 1989 to 1992. The following table is a breakdown of the hours allotted for each category over the next five years. STARTUP GENERATOR FORCED OUTAGE PLANNED ON LINE OUTAGE TIME OUTAGE PERIOD EAF FOR YEAR (HOURS) (HOURS) (HOURS) (HOURS) (HOURS) ,(3,), (%) 1989(**) 7783 168 172 737 8760 84.4 2.1 1990(*) 7036 168 172 1464 8760 75.9 2.3 1991(*) 7036 168 172 1464 8760 75.9 2.3 1992 8520 240 0 0 8760 92.9 2.7 l l l (**)The1988RefuelingOutagecontinuedintoJanuary,1989 (*) Refueling Outage Years UNPLANNED AUTOMATIC REACTOR SCRAMS WHILE CRITICAL l The 1989 goal for Unplanned Automatic Reactor Scrams While Crf tical has l been set at one. The Fort Calhoun Station has had one urplanned automatic l reactor scram in the past three years of operation. 1 UNPLANNED SAFETY SYSTEM ACTUATIONS The Unplanned Safety System Actuations goal for 1989 has been established at zero. The Fort Calhoun Station has not had an unplanned safety system actuation in the last five years. GROSS HEAT RATE The 1989 Gross Heat Rate goal for the Fort Calhoun Station has been set at 10,500 BTU /KWH. This heat rate goal is based on the 1988 goal of 10,075 BTU /KWH less 20.6 MW(e) stated in memo TS-FC-83-233H, written on July 17, 1983. This states that operation without the governing stage of the turbine results in a gross electrical output loss of 20.6 MW(e).

BASIS FOR ESTABLISHING 1989 PERFORMANCE !NDICATOR GOALS (CONTIhbED) l FUEL RELIABILITY INDICATOR The 1989 Fuel Reliability Indicator (FRI) goal has been set at 1.0 nanocuries/ gram. This level allows for approximately one to two fuel pin failures. Although Cycle 11 was completed without any apparent fuel pin failures, there are a number of ANF assemblies entering into a third or fourth cycle of operation. When a fuel pin has been used for three or four fuel cycles there is an increased probability of fuel failure. The Failed Fuel Action Plan, Standing Order 0-43, allows for approximately four fuel pin failures prior to implementing any increased action levels. PERSONNEL RADIATION EXPOSURE (CUMULATIVE) The 1989 Personnel Radiation Exposure (Cumulative) goal is 130 man-rem. This goal was based on 50 man-rem of cumulative exposure for the month of January,1989, and approximately 7.5 man-rem of cumulative exposure for the months of February, 1989, through December, 1989. VOLUME OF LOW-LEVEL SOLID RADIOACTIVE WASTE The 1989 Volume of Lew-Level Solid Radioactive Waste goal is 6,000 cubic feet. This goal was based on a recommendation made by the Fort Calhoun ALARA Committee and approved by the Division Manager of the Nuclear i Production Division. DISABLING INJURY FRE0VENCY RATE The Disabling Injury Frequency Rate 1989 goal has been set at 0.31. This goal allows for one lost time accident in the Nuclear Production Division during 1989. I a

FORT CALHOUN STAT 10N OPERATING CYCLES AND REFUELING OUTAGE DATES PRODUCTION CUMULATIVE T0 (MWH) (MWH) EVENT FROM Cycle 1 09/26/73 - 02/01/75 3,299,639 3,299,639 First Refueling 02/01/75 - 05/09/75 Cycle 2 05/09/75 - 10/01/76 3,853,322 7,152,961 Second Refueling 10/01/76 - 12/13/76 Cycle 3 12/13/76 - 09/30/77 2,805,927 9,958,888 Third Refueling 09/30/77 - 12/09/77 Cycle 4 12/09/77 - 10/14/78 3,026,832 12,985,720 Fourth Refueling 10/14/78 - 12/24/78 Cycle 5 12/24/78 - 01/18/80 3,882,734 16,868,454 Fifth Refueling 01/18/80 - 06/11/80 Cycle 6 06/11/80 - 09/18/81 3,899,714 20,768,168 Sixth Refueling 09/18/81 - 12/21/81 Cycle 7 12/21/81 - 12/06/82 3,561,866 24,330,034 Seventh Refueling 12/06/82 - 04/07/83 Cycle 8 04/07/83 - 03/03/84 3,406,371 27,736,405 Eighth Refueling 03/03/84 - 07/12/84 Cycle 9 07/12/84 - 09/28/85 4,741,488 32,47),893 Ninth Refueling 09/28/85 - 01/16/86 Cycle 10 01/16/86 - 03/07/87 4,356,753 36,834,646 Tenth Refueling 03/07/87 - 06/08/87 Cycle 11 06/08/87 - 09/27/88 4,936,859 41,771,505 Eleventh Refueling 09/27/88 - 01/31/89 Cycle 12 01/31/89 - 02/15/90* Twelfth Refueling 02/15/90*- 05/11/90* Cycle 13 05/11/90*- 09/01/91*

• - Planned Dates.

FORT CALHOUN STATION PRODUCTION AND OPERATION RECORDS The following seven items are the current production and operation " records" for the Fort Calhoun Station.

1. First Sustained Reaction..........

.. August 5,1973(5:47p.m.)

2. First Electricity Supplied to the System..... August 25, 1973

3. Commercial Operation (180,000 KWH)........ September 26, 1973

4. Achieved Full Power (100%)............May 4, 1974 5.LongestRun(477 days).............. June 8,1987-Sept.27.,1988 6.HighestMonthlyNetGeneration(364,468,800KWH).0ctober1987 7.MostProductiveFuelCycle(4,936,859 MWH).... June 8,1987-Sept.27,1988 (Cycle 11) 8 o

PERFORMANCE INDICATOR DATA SOURCES PERFORMANCE INDICATOR MANAGER / INDIVIDUAL Age of Outstanding Maintenance Orders CHAMPS Amount of Work On Hold Awaiting Parts CHAMPS Auxiliary Systems Chemistry Hours Outside Station Limits Jaworski/Stultz Classroom (Instructor) Hours Gasper /Kobunski Condenser Air Inleakage Turbine Building Log Corrective Maintenance Backlog > 3 Months Old CHAMPS Craft Work Activity Peterson/Shrum Daily Thermal Output Holthaus/ Gray Decontaminated Auxiliary Building Peterson/Christensen Diesel Generator Reliability DG Log Disabling Injury Frequency Rate Willrett/ Plowman Document Review Peterson/McKay DR/QRs Issued Versus NRC Violations Issued Richard /Krieser Equipment Forced Outages per 1000 Critical Hours Holthaus/ Gray Equivalent Availability Factor Dietz/Kulisek Forced Outage Rate Holthaus/ Gray Fuel Reliability indicator Holthaus/Lofshult l Gaseous Radioactive Waste Discharged to the Environment Jaworski/Stultz Gross Heat Rate Holthaus/ Gray Hotlines Gasper /Kobunski Liquid Radioactive Waste Discharged to the Environment Jaworski/Stultz Maintenance Order Breakdown CHAMPS Maintenance Overtime Peterson/Shrum Maximum Individual Radiation Exposure Peterson/Mattice Minor Injury Cases per Month Willrett/ Plowman Number of NPRDS Reportable Failures Fisicaro/Riva. _ _ _ _ _ _ _ _. _ o

h PERFORMANCE INDICATOR DATA SOURCE l (CONTINUED) Number of Out-of-Service Control Room Instruments CHAMPS l Number of Personnel Errors Reported in LFP.s LER File Number of Violations per 1000 Inspection Hours Orr/Krieser Operations and Maintenance Budget Gleason/ Parent Outstanding Modifications Jaworski/ Turner Percent of DR/QR's Greater Than Six Months Old Orr/Krieser PersonnelRadiationExposure(Cumulative) Peterson/Mattice Personnel Turnover Rate Jaworski/Yager Preverttive Maintenance Items Overdue Peterson/Cagle Primary System Chemistry - Percent Hours Out of Limits Jaworski/Stultz Procedural Noncompliance Incidents (Maintenance) CHAMPS Ratio of Highest Priority M0s to Total MOs Completed CHAMPS Ratio of Preventive to Total Maintenance Peterson/Shrum Recordable Injury Cases Frequency Rate Willrett/ Plowman R0 Hot License Exams Gasper /Kobunski R0 License Examination Pass Ratio Gasper /Fleuhr Secondary System Chemistry Jaworski/Stultz Spare Parts Inventory Turnover Ratio Steele/ Miser I Spare Parts Inventory Value Steele/Huliska SR0 License Examination Pass Ratio Gasper /Fleuhr Staffing Level Jaworski/Yager Temporary Modifications Jumper Log Total Hours of Student Training Kobunski/newhouse Total Skin and Clothing Contaminations Peterson/Christensen Unplanned Automatic Reactor Scrams While Critical Holthaus/ Gray Unplanned Safety System Actuations Holthaus/ Gray Volume of Low-level Solid Radioactive Waste Peterson/Bilau -

REFERENCES i INP0 Good Practices OA-102, " Performance Monitoring - Management Information" IEEE Standard 762, "lEEE Trial Use Standard Definitions for Use in l Reporting Generating Unit Reliability, Availability and Productivity" INP0 Report Dated November 1984, " Nuclear Power Plant Operational Data" .o U.S. Nuclear Regulatory Commission " Regulatory Guide 1.108 / 4 9 L' - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - .}}