Text

Performance Indicators,May 1992
	ML20101P212
Person / Time
Site:	Fort Calhoun
Issue date:	05/31/1992
From:	; OMAHA PUBLIC POWER DISTRICT
To:	;
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	NUDOCS 9207100341
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OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT Prepared By:

Production Engineering Division System Engineering Test and Performance Group MAY 1992

l l

ABSTRACT PURPOSE The

Performance indicators Program" is intended to provide selected Fort Calhoun plant perfor.

mance information to OPPD's personnel respcnsible 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 enrporate 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 inf ormation This inforri,ation can be used for comparison or as a means of promoting pride and motivation.

SCOPE The conditions, goals, and projections reflected within this report are current as of the end of the month being reported, unNss otherwise stated.

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

1) Data was selected which most effectively monitors Fon Celhoun's performance in key areas.

2) Established corporate goals and industry information were included for comparison.

3) Formal definitions were developed for each periormance parameter to ensure consistency in future reports and allow comparison with industry averages where appropriate.

Comments and input are encouraged to ensure that this program is tailored to address the areas f

which are most meaningful to the people using the report. Please refer comments to the Syste,n Engineering Department's Test and Periormance Group, To increase personnel awareness of Fort Calhoun Station's plant pettormance, it is suggested that this report be distributed throughout your respective departments.

~ REFERENCES INPO Good Practices OA 102, " Performance Monitoring - Management information" INPO Report Dated November 1984," Nuclear Power Plant Operational Data" NUMARC 87-00," Guidelines ar.d Technicd Bases for NUMARC Initiatives Addressing Station Black-out at Light Water Reactors", Revision 1, Appendix D,"EDG Reliability rogram", dated o

April 6,1990.

Table of Contents / Summary INPO INDUSTRY KEY PARAMETERS peg mJS T RY

,Q&2Q QCEQ unrrn m can TH!S te*m4 t AST TENTH m

UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7.000 CRITICAL HOURS...

.on o.

.1.

.0.

_NMA.

.3 SAFETY SYSTEM PERFORMANCE:

HIGH PRESSURE SAFETY INJECTION SYSTEM,

.00014.

. 0 000... O C00G9..

.NA.

m.NA.

_6 AUXILIARY FEEDWATER SYSTEM.

.0.0034

. 0.01.

.00094.

.. N A.

..NA.

.7 EMERGENCY AC POWER SYSTEM.

. 0.0065

.0.024.

. 0 0053.

.. N A..

.. N A.

.8 THERMAL PERFORMANCE..

. 99e%..

. 9' 3%... 99 6%.

.. N A..

..NA.

.10 UNIT CAPABILITY FACTOR.

. 841%..

. 69 2%... 69 9%.

. 0%..

l..

.12 UNPLANNED CAPABILITY LOSS FACTOR..

.187%.

.45%.

. 201%..

13 4 %.

. NA.

.13 FUEL RELIABILITY 'NDICATOR ewacw.g,.m NA.

. 7.5x 10-4. 7.07:10-4,

. N o.

..NA.

,.15 COLLECTIVE RADIAllON EXPOSURE.

118 5/YR.. 250!YR.. 226 5..

. 220 9.

..N A..

16 VOLUME CF LOW LEVEL SOLID RADIOACTIVE WASTE (cut >c f0.....

. 2,118 5'YR.. 3.000/YR.. 343 0..

.1970..

..N A...17 INDUSTRIAL SAFETY ACCIDENT RATE /0ISABLING INJURY /lLLNESS FREQUENCY RATE.

.. 0.16..

. 0 3.,

c.76.

. 0.90.

..N M A.. 18 CHEMISTRY INDiEX/ SECONDARY SYSTEM CHEMISTRY..

.. o.20..

..o 45..

..o 50.

.. O._

.. NMA.. 45 OPERATIONS PEiE maSTnY QEE2.

CDED UPfif R i fa4 g TH's LONTH t AST LONTH M

STATION NET GENERATION (10,000 Mwh)..

,. NA..

.. N A..

. 24 6.

.0.

.. N A..

.1 FORCED OUTAGF; RATE,

..-... 0.25%..

.24%.

. 7.31%..

. 7.1%.

.. N A..,. 2 UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7,000 CRITICAL HOURS.

.. 0 63.

. 0..

.1.

.. o.

..NMA.

.3 UNPLANNED SAFETY SYSTEM ACTUATIONS -(INPO DEFINITION)..

. 0..

.. o.

., l..

..4 UNPLANNED SAFETY SYSTEM ACTUATIONS. (NRC DEFINITION)..

. 0..

..).

.0,

.. D.

.5 GROSS HEAT RATE..

.. N A..

.. N A... 10.348.

.. N A..

.9 EQUIVALENT AVAILABILITY FACTOR.

.. NA..

.. NA.

. 74 6%.

. 0%..

. N A..

.11 UNIT CAPABILITY FACTOR.....

. 84.1%..

. 69.2%... 69 9%.

. 0%.

.. N A... 12 UNPLANNED CAPABILITY LOSS FACTOR..

. 1.87%..

. 4 5%... 20 ' %..

.13 4%.

. N A...13 PLANNED CAPABILITY LOSS FACTOR,

.. NA.

. 26.3%...10 0%..

. 86 6%.

.. N A...14

OPERA?lONS (Cont'd)

PAGE woustnv

.QEE2.

CPID urern m gQg TH!S LO*UH LAST AO*MH lpf,$Q FUEL RELIABILITY INDICATOR (rnicrocuries/ gram)....NA.

. 7.5x104. 7.07:104.

.. N A.

.. NA..15 DAILY THERMAL OUTPUT (Mwth).-..

... N A.

.1495.

.. N A.

.. N A..

. N A...19 EQUIPMENT FORCED OUTAGES PER 1,000 CR!TICA' HOURS..

......... N A..

. 0 2..

. 0.68.

NA.

..NMA... 20 OPERATIONS AND L

NTENANCE BUDGET..

.. NA.

.. N A..

.. NA..

.. N A..

. 21 DOCUMENT REVIEV,

.. N A..

.. N A.-

.. NA.

.. N A..

., NA,.. 22 MAINTENANCE PAGE moosTny

.QPI2.

CEEQ ugr m QQg TH!E A69UH LAST LO*RH 1E[,82 EMERGENCY DIESEL GENERATOR UNIT RELIABILITY...,.........

.. N A.

.. N A..

.. N A.

.. N A..

.. N A... 23 DIESEL GENERATOR RELIABILITY (25 DE MAN DS)....................

..... N A.

.. c4.

.. N A.

.. N A...

.. NA..... 24 DIESEL GENERATOR UNAVAILABILITY,..,,

... N A..

.. NA..

.. NA.

.. NA..

.. N A.... 25 AGE OF OUTSTANDING MAINTENANCE WORK ORDERS (GORRECTIVE NON OUTAGE)... NA..

.. N A...... N A..

}.4..

.. A.... 26 MAINTENANCE WORK ORDER BREAKDOWN (CORRECTIVE NON-OUTAGE).......NA.....

.. N A..

.. NA..

.. N A..

.. A,.... 27 CORRECTIVE MAINTENANCE BACKLOG GREATER THAN 3 MONTHS OLD (NON OUTAGE)

...... N A..

.... N A... 4 8 6%..

. 55.5%..

.. l... 2 8 RATIO OF PREVENTIVE TO TOTAL MAINTENANCE ;

.. NA..

.65%.

. 42 4%.

. 44.5%.

..NMA,. 29 PREVENTIVE MAINTENANCE TTEMS OVERDUE.............

....................NA.

. 0.5%... 0.72%.

.. N A.

..NMA.. 30 NUMBER OF OUT-OF SERVICE CONTROL ROOM INSTRUMENTS.....

.. N A..

< 13..

.,20.

. 22.

NMA.. 31

.. N A..

.10%.

. 8.6%..

. 39.7%.

.. l.... 32 MAINTENANCE OVERTIME._....,,..

PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)...

.. N A..

.. N A.

. 0..

. 2.-

.. 33 MAlh'.INANCE WORK ORDER BACKLOG (CORRECTIVE NON OUTAGE MAINTENANCE)......NA..

.. <350..... 432.

. 389..

.. A.. 34 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (ELECTRICAL MAINTENANCE).....

.. N A..

. 80%..

.. NA.

.. N A.,

.. N A.... 3 5 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (PRESSURE EQUIPMENT).........,.,....

...... NA..

.80%.

.. N A.... _.... N A..

. N A.... 36 li

MAINTENANCE (cont'd))

PAGE INDUSTRY p,fDfQ, QDfQ UD or p

E'N M TH'S M'WTH LA ST MNHH If,i,1Q PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (GENERAL MAINTENANCE).

.. NA..

. 80%..

..N A.

. N A..

.. N A... 37 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (MECHANICAL MAINTENANCE).

.. N A..

. 80%..

.. N A..

.. NA..

. NA... 38 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (INSTRUMENTATION & CONTROL)..

.. N A..

. 80%..

.. N A..

. N A... 39 NUMBER OF MISSED SURVEILLANCE TESTS RESULTING IN LICENSEE EVENT REPORTS...

.. N A.

.0..

.0.

1.

.40 COMPONENT FAILURE ANALYSIS REPORT (CFAR)

SUMMARY

.. N A..

.. N A.

.. NA.

.. N A... 41 NUMBER OF NPRDS MULTIPLE FAILURES.,

..NA.

.. N A..

.. NA.

.. N A..

.NA.

.42 MAINTENANCE EFFECTIVENESS.

.. N A..

.. N o.

. NA.....

.. N A..

.43 CHECK VALVE FAILURE RATE,...

.. N A.

. 2 00L.6.. 6 07E 7.. 6 07E 7.

.. N A.,. 44 CHEMISTRY AND RADIOLOGICAL PROTECTION PAGE IND'19 T RY

pff2, QffD UDPFR M M TH's k*3 NTH LAST t*"WTH IffQQ COLLECTIVE RADIATION EXPOSURE (CUMULAilVE)..

.1185YR.. 250/YR... 226.5..

. 220 9..

., N A...16 VOLUME OF LOW LEVEL SOLID RADIOACTIVE WASTE,

. 2.1185YR. 3.000YR... 343.0..

. 197.0..

.. N A.

.17 SECONDARY SYSTEM CHEMISTRY...

.. 0.34.

. 0 45..

.. U.50..

.. NA..

.. NMA.. 45 PRIMARY SYSTEM CHEHISTRY PERCENT OF HOURS OUT OF LIMIT..

.. N A..

. 2%..

.. N A.

.. N A..

.46 AUXILIARY SYSTEM (CCW) CHEMISTRY PERCENT OF HOURS OUTSIDE STATION LIMITS.....

.. N A..

. 2%..

.. N A.

.. N A..

.. NA.

.47 IN-L!NE CHEMISTRY INSTRUMENTS OUT OF-SERVICE.....

.....NA.

. 6..

. 20..

.. 18.

NMA.. 48 HAZARDOUS WASTE PRODUCED.

NA..

.. N A.

.. 0..

..o.

.. l..

.49 MAXIMUM INDIVIDUAL RADIATION EXPOSURE (mrem)..

.. N A..

.1.500.YR.. 232..

.610.

.. N A...50 TOTAL SKIN AND CLOTHING CONTAMINATIONS.

.. N A.

.144.

.213.

.203.

..NMA.. 51 lii

CHEMISTRY AND RADIOLOGIC AL PROTECTION (cont'd)

EAGE N'1?ST RY pff,1 CDf,Q UDDFR 1%

QQAL TH'S LONTH t_AST LO$lTH

]pflQ DECONTAMIN ATED RADIATION CONTROLLED AREA..

.. N A..

.88%.

. 86 2%..

. 85 9%.

..NMA.. 52 RADIOLOGICAL WORK PRACTICES PROGRAM.,.

.. N A.

.. NA.

.1.

. 39.

.. l...... b3 NUMBER OF HOT SPOTS.

...... N A.... resolve 1/mo.. 63.

. 64.

.. l..

. 54 GASEOUS RADIOACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT (curies)..

.. N A.

.. 340.. 358.5..

.. N A..

.. N A...55 LIQUID RADIOACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT (cuties)..

.. N A.

. 225... 176.1.

.. N A..

.. l..

. 56 e

SECURITY PA3E ikDL'5TRY QDfQ QEEQ UDPCR iM QQfL TH!S LO*fTH LAST ArWTH E LOGGABLE/ REPORTABLE

... NA..

... NA.

. 35...

. 59.

.. N A.

4. 57 INCIDENTS (SECURITY)..

SECURITY NON SYSTEM FAILURES.

.. NA..

.. N A..

.. NA.

.. NA..

.. N A... 58 SECURITY SYSTEM FAILURES..

.. N A........ NA..

.. N A..

.. N A...._.... N A... 59 MATERIALS AND OUTSIDE SERVICES EAGE N9MTRY QEEQ QEEQ UDDCR t%

CQfL TH'S LONTH t AST AFWTH Iff,1Q AMOUNT OF WORK ON HOLD AWAITING PARTS (NON OUTAGE)..

.. NA.

3 5%... 0.89%..

. 0.97%.

..l 60 SPARE PARTS INVENTORY VALUE ($ million)...... NA..... N A..

13.6.... 13.3..

.. N A,,. 61 SPARE PARTS ISSUED ($ thousands)..

..... NA..

NA.. 267.8

. 762.8...... NA... 61

__ NA - _

. 9 8%..

. 94%..

. 98%....... NMA.,. 62 INVENTORY ACCURACY,

.m__

STOCKOUT RATE

= NA

. 2%..

0.7%..

.. 9 8%..

..I 62 EXPEDITED PURCHASES..

..NA.

0.5%..

. 0.31%..

.1.79%.

..l 63 INVOICE BREAKDOWN.

_ NA NA...

.. N A N A......,.. N A.. 64 MATERIAL REQUEST PLANNING..

.. NA..

NA.

. 67.5%....... 73.9%.

..I 64 DESIGN ENGINEERING PAGE NorTRY QEER DEED UDDFD iM QQAL THis ArWTH t_AST AFWTH M

OUTSTANDING MODIFICATIONS.,

.. NA..

.. N A..

.172..

.179.

... N A... 65 iv

DESIGN ENGINEERING (cont'd)

EAGE 1*D_STRY QffQ QDfD UDDED 'N M TH'S kemi LAST wwtrH M TEMPORARY MODIFICATIONS (EXCLUDING SCAFFOLDING)..

.. N A.

.0.

. 21.

. 34.

. i... 66 i

ENGINEERING ASSISTANCE REQUEST (EAR) BREAKDOWN,

.. N A.

.166.

.. N A..

. NA

. 67 ENGINEERING CHANGE NOTICE STATUS.

.. NA.

.NA.

. 167..

.137.

.. N A.. 68 ENGINEERING CHANGE NOTICE BREAKDOWN... N A.

.. NA..

.. N A.

. NA..

.. N A... 69 INDUSTRI AL S AFETY EAgg l*DJS TRY QDfDQ QffQ UDDER'N M TH'S LOITH LA ST kO*lTH IfffQ DISABLING INJURY /lLLNESS FREQUENCY RATE.. 016.

03.

. 0.76.

. 0 90.

.NMA..18 RECORDABLE INJURY /lLLNESS CASES FREQUENCY RATE.

.. N A.

. 2.0..

. 2.27..

.1.81

..NMA.. 70 l

HUM AN RESOURCES EAGE PDJ9TRY QDfQ QDfQ D

Mff M M TH'S LOITH LAST LOAITH

}fffQ NUMBER OF PERSONNEL ERRORS REPORTED IN LERs.

.. NA.

. 0..

.1.

.. l.

. 71 LER ROOT CAUSE BREAKDOWN.

.. NA.

.. N A..

.. N A.. 72 STAFFING LEVEL.

.. N A..

. N A..

.. N A.

.. N A..

.NA.

.73 PERSONNEL TURNOVER RATE.

.. N A..

.. NA..

.. N A..

.. N A...73 TRAINING AND OUALIFICATION EAGE PDJSTRY QEEQ QEfD UDDDP1 M M TH's AOITH LAST LONTH IfftQ LICENSED OPERATOR REQUALIFICATION TRAINING..

.. N A.

.. N A..

. NA..

.. N A... 74 LICENSE CANDIDATE EXAMS.......

.. N A..

.. N A.

.. N A..

.. N A... 75 HOTLINE TRAINING MEMOS.

.. N A..

.. N A.

.. N A..

.. N A.. 76 TOTAL INSTRUCTION HOURS,

.. N A..

.. NA.

. 977..

.585.

.. N A... 77 TOTAL HOURS OF STUDENT TRAINING..

.. N A..

.. NA..

. 6.054.

. 3.652..

.. N A... 78 v

QUALITY ASSURANCE EAGE INDUSTRY QESQ QEEQ

- upern m QQg Tms wwmt uST MONTH M

. VIOLATIONS PER 1,000 INSPECTION HCURS......NA..

.1.5..... 2 80

. 1.85..

..NMA.. 79

' COMPARISON OF VIOLATONS -

AMONG REGION IV PLANTS......................NA -

.. N A..

.. NA...... N A...

.. N A.... 8 0 CUMULATIVE VIOLATIONS AND NCVs (TWELVE. MONTH RUNNING TOTAL).........

.... N A..

.. N A.... 14/3..

. 1 &'4.

.. A... 81 OUTSTANDING CORRECTIVE ACTON REPORTS.......

.... NA.

.. N A..

. 83....

.. 96.

.l 82 OVERDUE AND EXTENDED CORRECTIVE ACTION REPORTS..

...... N A..

. N A..

.. 37......-. 0/4..

.. D.. 83 CARS ISSUED vs. SIGNIF. CARS vs.

NRC VOLATIONS ISSUED vs.

LERs REPORTED....

......... N A

. N A..

.. NA..

..NA...84 l

PERFORMANCE INDICATOR DEFINITIONS.

...... 85 SAFETY ENHANCEMENT PROGRAM INDEX.........-...............

. 93 REPORT DISTRIBUTION LIST..............

.......... 9 5

SUMMARY

SECTION POSITIVE TREND REPORT..........

...... 96 ADVERSE TREND REPORT.........................

.......... 9 6 -

INDICATORS NEEDING INCREASED MANAGEMENT ATTENTION REPORT -

........ 9 6

- PERFORMANCE INDICATOR REPORT IMPROVEMENTS / CHANGES................

....,.... 97 r

TABLE OF CONTENTS /

SUMMARY

TREND SYMBOLS ~

A L ADVERSE TREND 1 - IMPROVED PERFORMANCE

. D - DECLINING PERFORMANCE NMA - NEEDS MANAGEMENT ATTENTON NA - NOT APPLICABLE /AVAILABLE.

Vi i

i Q Not Generation (10,000 Mw hours) 50 -

40-Cycle 14 y

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[43 i.

Q Jun91 Jul Aug

.Sep Oct hov Dec Jan Feb Mar Apr May92 STATION NET GENERATION This indicator shows the net generation of the Fort Calhoun Station for the reporting morth.

During the month of May 1992, a net total of 246,192 MWH was generated by the Fort Calhoun Station.

The station was returned to service after the Cycle 14 Refueling Outage when the reactor was taken critical on 5/1/92 at 1035 hours0.012 days 0.288 hours 0.00171 weeks 3.938175e-4 months and the generator was put on line on 5/3/92. A forced outage occurred on 5/14/92 when the turbine generator tripped on a false high level moisture separator trip signal which caused a simultaneous reactor trip.

The reactor was retumed to critical and the generator was put on-line on 5/15/92.

Unplanned energy losses for the month were: 1) the Cycle 14 Refueling Outage exten-sion; 2) the reduction to 58% power for the inoperable condenser valve: 3) the reactor trip;# the hold at 48% power for repair on a feedwater pump suction valve; and 5) the 5/31 dropped control rod caused by a faulty clutch coil.

The low net generation for the months of September and October 1991 was due to the following three forced outages: 1) the station batteries replacement outage from 9/12/91 at 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months through 10/6/91 at 1114 hours0.0129 days 0.309 hours 0.00184 weeks 4.23877e-4 months ; 2) a steam leak on the drain line from a turbine control valve was repaired from 10/18/91 at 0307 hours0.00355 days 0.0853 hours 5.076058e-4 weeks 1.168135e-4 months to 10/19/91 at 1116 hours0.0129 days 0.31 hours 0.00185 weeks 4.24638e-4 months ; and 3) a steam leak repair on a test pipe on the high pressure turbine shell from 10/25/91 at 2204 to 10/26/91 at 0810.

Data Source: Station Generation Report Accountability: Patterson Adverse Trend: None 1

i l

~

Forced Outtp Rab 20% -

l GOOD]

-O--

1991 & 1992 Fon Calhoun Goals

-O-1991 Industry Upper 10 Percentile (0.25%)

15% -

$ 9.3 10%-

-l

=

5%-

C O

O O

1,4 0%

0 O

O 9

'89

'90

'91 Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mct Apr MayD2 FORCED OUTAGE RATE The forced outage rate was reported as 7.31% for the twelve months from 6/1/91 to 5/

31/92.

A forced outage occurred on 5/14/92 at 1557 hours0.018 days 0.433 hours 0.00257 weeks 5.924385e-4 months when the tutine generator tripped on a false high level moisture separator trip signal which caused a simultaneous reactor trip. The reactor was returned to critical at 0537 on 5/15/92 and the generator was on-line at 1150 hours0.0133 days 0.319 hours 0.0019 weeks 4.37575e-4 months at 5/15/92.

During 2 o months of September and October 1991 a forced outage occurred when the station batteries were declared inoperable. The generator was taken off line on 9/12/91 and remained off line until 10/6 /91.

The generator was taken off line on October 18 & 19,1991 due to a steam leak on a turbine control valve before seat drain line. The generator was again taken off line on October 25 & 26 due to a steam leak from an instrument tap on the high pressure tur-blne.

A forced outage occurred during the month of August 1991 to replace a failed potential transformer (PT). This PT converted 345 KV to 120V for use in the breaker synchroniza-ton circuit.

The 1992 and 1991 Fort Calhoun goals for Forced Outage Rate are 2.4%.

Data Source: Monthly Ort is Report & NERC GAD Forms Accountability: Pnterson Adverse Trend: None 2

L:

3-O FCS Reactor Scrams

-O-1991 & 1992 Fort Calhoun Goals 1995INPOIndustryGoat

-O-Industry Upper 10% (0.63 per 7.000 Murs critical) I t

2-i I

1-4 A

A A

b-i C

D 0

D--D---C O

O O

O D-O ic.

P 0 0 0 0 0--c, 0 r-07-c, 0,-c, 0 r-c, 0 r-c, 0 ro, i

i i

i

'88 '89 '90 '91 Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7,000 HOURS CRITICAL There was one unplanned automatic reactor scram in May 1992. This scram occurred on May 14 at 1557 when the turbine generator tripped on a false high level moisture separator trip signal which caused a simultaneous reactor trip. The last unplanned

- automatic reactor scram prior to this occurred on July 2,1986.

The 1992 goal for unplanned automatic reactor scrams while critical has been set at zero. The 1995 INPO industry goalls one per 7,000 hours0 days 0 hours 0 weeks 0 months critical.

. The industry upper ten percentile value is approximately 0.63 scrams per 7,000 hours0 days 0 hours 0 weeks 0 months critical.

s L

l~

Data Source: Monthly Operations Report & Plant Licensee Event Reports (LERs)

E Accountability: Patterson l

L

Adverse Trend: None L

3 h.

3-O Safety System Actuations

-e--

1992 Fort Calhoun Goal c - Industry Upper 10 Percentile 2-i 1

1-0 oi icieioiaia,c,oioicic, i

i i

'89 90'91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 UNPLANNED SAFETY SYSTEM ACTUATIONS-(INPO DEFINITION)

There were no unplanned safety system actuations during the month of May 1992.

The 1992 goal for the number o! unplanned safety system actuations is zero.

The industry upper ten percentile value for the number of unplanned safety system actuations per year is zero. The Fort Calhoun Station is currently performing in the upper ten percentile of nuclear power plants for this indicator.

Drta Source: Monthly Operations Report & Plant Licensee Event Reports (LERs)

Act ountability: Jaworski/Foley/Ronning Adurse Trend: None 4

12 Month Running Total SSA 10-1000

-O--

Crdical Hours 900 E)

Safety System Actuations (SSA) 8-800 O

700 g

C' jj I 6-600 $

)

$$l E

E A

E 500 0 I

li j

$4-400 3 p

2 g

d 300 v\\

7 y% 2

)

200 7

2-100 i

i i i

0-

'M a

0

'89 '90 '91 JJASONDJFMAMJJASONDJFMAM 199n 1991 1992 UNPLANNED SAFETY SYSTEM ACTUATIONS-(NRC DEFINITION)

This indicator shows the number of unplanned safety system actuations (SSAs) which include 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.

An unplanned safety system actuation occurred on May 14,1992 when the turbine generator tripped on a false high level moisture separator trip signal which caused a simultaneous reactor trip and subsequent anticipatory start signal to both diesel genera-

tors, In June 1991 when 'here were two anticipatory signal starts for DG 2. The first start occurred after a control relay was bumped causing a momentary loss of power to safety bus 1 A4. DG 2 started a second time when a breaker trip occurred du ag DG 1 breaker synchronization. DG 2 was not required to provide power to the safety bus in either of these situations.

The 1992 Fort Calhoun goal for this indicatoris a maximum of three.

Data Source: Monthly Operations Report & Plant Licensee Event Reports (LERs)

Accountability: Jaworski/Foley/Ronning Adverss Trend: None 5

O 1992 Monthly High Pressure Safety injection System Unavailability Value 1992 High Pressure Safety injection Systern Unavailabihty Value Year to Date

-O-1991 & 1992 Fort Calhoun Goals

-H>-

1991 High Pressure Safety injection System Unavailability Value Year.to Date

-b-1995 INPO Industry Goal (0.02',

--O-Industry Upper 10% (0.0014) 0.025 -

0.02 -.A A

a a

a 0.015 -

Cyde14 Refueling 0.01 -

C O

O C

0 O

Outage 0

0.005 -

at

, k-@,-

0-

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the High Pressure Safety injection System unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for the report-ing month.

The High Pressure Safety injection System unavailability value for May 1992 was -

0.00069. There were 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months of planned unavailability for surveillance tests'in May.

The 1992 Fort Calhoun goal for this indicator is 0.008. The 1995 INPO Industry goal is 0.02 and the industry upper ten percent _ils value (for the threa year period from 1/89 -

through 12/91) is approximately 0.0014.

Data Source: Jaworski/Schaffer Accountability: Jaworski/Schaffer Adverse Trend: None 6

[]

1992 Monthly Auniliary Feodwater system unavellitwitty Value

-M-1992 Auxillary Feedwater system Ur.availabil:ty value Year to date

-O-1991 & 1992 Fort Calhoun Goals

-*')-

1991 Auxiliary Fes $ water syste.n Unavailability Value Year to-date 1995 INPO Industry Goal

-O-Industry Upper 10 % (0.0034) 0.025 -

A 4-- - 6 6

a 6-6 A

A o.02 -

O O

O

-C 1

l 0.015 -

Cycle 14 0.01 -

Refueling A

Outage e,

m 0.005 -

i O

O O

O O - --O O

O D:

0-Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May02 AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Auxiliary Foodwater System Unavailability value, as defined by INPO ln the Safety System Performance Indicator Definitions, for the reporting mor*".

The Auxiliary Feedwater System Unavailability Value for May 1992 was 0.0094. Preven-tive maintenance activities resulted in 2.67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months of planned unavailability and 10.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months of unplanned unavailablity on 5/27/92 due to corrective maintenance following the initial attempt to perform a PM,

The 1992 year to date AFW unavailability value was 0.0049 at the end of May.

The 1992 Fort Calhoun goal for this indicator is 0.01. The 1995 INPO industry goal is 0.025 and the industry upper ten percentile value (for the three year period from 1/89 through 12/91) is approximately 0.0034.

Data Source: Jaworski/Hilgenkamp Accountability: Jaworski/Hilgenkamp Adverse Trend: Nor.e 7

j

D 1992 Monthly Emergency AC Power UnavailabilRy Value

-M-1992 Emergency AC Power Unavailability Value Year to Date lGOODI

-O-1991 &1992 Fort Calhoun Goals (0.024)

+ 1991 Emergency AC Power Unavailability Value Year to Date 0.06-

.-6--

1995 INPO Industry Goal (0.025) 0.05 -

1 n

0.04 -

~e.

O.03 -

A A

g A

A A

A g

0.02 -

I O.01 -

0 0

0 j

0 i

i i

i i-i-

-. - i i

Jun91 Jul Aug Sep Oct Nov

-Dec Jan Feb Mar Apr May92 l

EMERGENCY AC POWER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Emergency AC Power System unavailability value, as defined by INPO ln the Safety System Perfonnance Indicator Definitions, for the reporting month.

I The Emergency AC Power System unavailability value for May 1992 is 0.0053. On May 26, there were 7.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months of planned unavailability for DG 1 to tighten the fan blades and repair a starting air solenoid valve.

The Emergency AC Power Systern unavailability velue year to4 ate is 0.0011.

The 1992 Fort Calhoun goal for this indicator is 0.024. The 1995 INPO industry goalls 0.025 and the Industry upper ten percentile value (for the three year period from 1/89 through 12/91) is approximately 0.0065.

Data Source: Jaworskl/Ronning.

- Accountability: Jaworski/Ronning Adverse Trend; None 8

1

-. =

13-D MonthlyGross HeatRate Year to Date Gross Heat Rate 12-m a

11-10520 10304

.1ll10023 Cyebi4 Refueling 10-Outage d

9=

i

.4 i

i i

i i-i i

i-i

- 89

'90

'91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Noi Dec92 GROSS HEAT RATE This indicator shows the Gross Heat Rate (GHR) for the reporting rnonth, the year to-date value, and the year end GHR for the previous 3 years.

The gross heat rate for the Fort Calhoun Station was reported as 10,348 BTU /KWH during the month of May 1992.

The year to date gross heat rate was reported as 10,225.4 BTU /KWH, Data Source: - Holthaus/ Gray (Manager / Source)

Accountability: Patterson-

Adverse Trends: None 9

i

O 1902 Monthly Thsrmal Performenos

+ 1992 Year to Date Avera9e Thermal Performance A

-O-1992 Fort Calhoun Goal (99.3%)

l GOOD l

. 1995 tNPO lndustry Gotal(99.5%)

--O-Industry Upper 10% (99.8%)

100% -

D D- < -O O

D-D D

D D

C A

o a

a T

A a

a a

a C

O O

O 99% -

Cycle 14 Refueling Outage 98% -

97%~

d; 90%

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 THERMAL PERFORMANCE This indicator shows the Thermal Performance value for the reporting month, the 1992 Fort Calhoun goal, the 1995 INPO industry goal and the industry median value.

The thermal performance value for the repirting month was 99.6%

The 1992 Fort Calhoun Gual for this indicator is 99.3%. The 1995 INPO Industry goal is 99.5% and the industry upper ten percentile value (for the one year period from 1/90 through 12/91) is approxiinately 99.8%

Data Souice: Jaworski/Popek Accountability: Jaworski/Popek Adverse Trend: None 10

~

O Monthly EAF M

Year to Date EAF n

80%- Iq 56.6 60%-

Cycle 14 g

Refueling i

IGOODI Outage

\\

40% -

o

/

20% -

e i

i i

1 0%

'89 90 m

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 EQUIV.ALENT AVAILABILITY FACTOR This indicator shows the plant monthly Equivalent Availability Factor (EAF), the year to-date EAF for 1992, and the EAF for the previous 3 years.

The EAF for May 1992 was reported as 74.6%.

The year-to-date EAF was reported as 31.5%

Data Source: Dietz/Parra (Manager / Source)

Accountability: Patterson Adverse Trond: None 11

O 1992 Mor.thly Unit Capability Factor 4

-ps-1992 Year to Date Average Unit Capability Factor j (;OOD I

+ 1991 Year to Date Average Unit Capabihty Factor

-O-1991 &1992 Fort Calhoun Goals 1995 INPO Industry Goal (80%)

O Indust >y Upper 10% (84.1% for a Three Year Avorage) 100 % -

90%-

b b

hP%Q_

O O

O 2

2 9

--9 M

9 hh 9

9 9

80%-

70%-

b O

pq c0%-

Cycle 14 50% -

Refueling 40%-

30%-

'M 20%~

10%~

0%-

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 UNIT CAPABILITY FACTOR This indicator shows the plant monthly Unit Capab;Iity (UCF) Factor and the 1995 INPO industry goal. UCF is defined as the ratio of the available energy generation over a given period of time to the reference energy generation (the energy that could be pro-duced if the unit were operated continuously at full power under reference ambient conditions) over the same time period, expressed as a percentage.

The UCF was reported as 69.9% for the month of May 1992.

The year to-date average unit capability factor was reported as 34%.

The 1995 INPO industry goalis 80% and the industry upper ten oercentile value (for the three year period from 1/89 through 12/91) is approximately 84.1%.

The 1992 Fort Calhoun goal for Unit Capability Factor is 69.2% The basis for this goal is 86 days for the Cycle 14 Refueling Outage,20 days rampup (10 full power equivalent days), unplanned loss of 11.5 full power equivalent days, and 10 day rampup (5 full power equivalent days).

Data Source: Generation Totals Report & Monthly Operating Report Accountability: Patterson Adverse Trend: None 12 E

_ _ _._. ~..

_.-.__-..-_-__.__m_.

O 1992 Monthly Unplanned Capabihty Loss Factor 90%-

. 1992 Year to Date Average Unplanned Capabihty Loss Factor 80%.

-+- 1991 Year to Date Average Unplanned Capabihty Factor 4

.-O--

1991 & 1992 Fort cathoun Goals

-s'r--

1995 !NPO Industry Goat (4.5%)

i Go%-

t-]

Industry Upper 10% (1.87% for a Three Year Average) 60%-

40% -

T Cycle 14 30%-

Refueling Outage 20%~

~

.rm i,

-4 10%-

6 a

6 6,6 6-B--8-1t-ed, o*-

Jun91 Jul --

Aug-Sep Oct Nov Dec Jan Feb Mar Apr May92 UNPLANNED CAPABILITY LOSS FACTOR f

This indicator shows the plant monthly Unplanned Capability Loss Factor (UCLF), the Fort Calhoun UCLF goal for 1992, and the 1995 INPO Industry goal. UCLF is defined as

' the ratio of the unplanned energy lossos during a given period of time, to the reference energy generation (the energy that could be produced if the unit were opera'ed continu-ously at full power under reference ambient conditions), expressed as a percentage.

The UCLF was reported as 20.1% for the month of May 1992. Unplanned energy losses for the month were: 1) the Cycle 14 Refueling Outage extension; 2) the reduction to 58% power for the inoperable condenser valve: 3)ihe reactor trip; 4) the hold at 48% -

power for repair on a feedwater pump suction valve; and 5) the dropped control rod caused by a faulty clutch coll.-

- The year-to-date average UCLF is 6.7%.

The 1995 INPO industry goalis 4.5% and the industry upper ten percentile value (for the three year period from 1/89 through 12/91)is approximately 1.87%.

- The Fort Calhoun goal for Unplanned Capability Loss Factor is 4.5%. The basis for this.

goalis an unplanned toss of 11.5 full power equivalent days and 10 day rampup (5 full-power equivalent days).

Data Source: Generation Totals Report & Monthly Operating Report Accountability: Patterson

- Adverse Trend: None -

13 y,-3y w

wv y,,.v w,,..

--w..-,-,.w.m m

,yy.,3r.v,_

_-w-m._--y.-

r_m,-wr.,.- - -,,.

s.,,-a,4---,,, - -.

,e

- +

-,--m 3-,

--rwe--ms,,.

O 1992 Monthly PL nn:d Captbility Lots Feetor

-N-1992 Year to Date Average PCLF

~

1991 Year to Date Average PCLF

-O--

1G91 & 1992 Fort Calhoun Goals

-O-Industry Median value (18.3% for a Three Year Averege)

Cycle 14 Refuehng Outage 100% -

90% -

I GCODI 80%-

T 4

70%-

g 60% -

/ : t-50%-

g 40% -

/--

l S

C C

C D

C C

C D

' 0% ~

C O

O O

og 7

O___

O

[~'""]

7 Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 PLANNED CAPABILITY LOSS FACTOR This indicator shows the plant monthly Planned Capability Loss Factor (PCLF), the PCLF year-to date average, and the Fort Calhoun yeat y average goals for 1991 and 1992. PCLF is defined as the ratio of the planned energy losses during a given period of time, to the reference energy generation (the energy that could be produced if the unit were operated continuously at full power under reference ambient conditions), ex-pressed as a percentage.

The PCLF was reported as 10.0% for the month of May 1992. Planned energy losses for the month were the rampup after the Cycle 14 Refueling outage, the hold at 30%

power for cherr;istry control and the hold at 65% power for instrument calibration and surveillance testing.

The year to-date average PCLF for 1992 is 59.3%.

The 1992 Fort Calhoun yearly average Planned Capability Loss Factor goalis 26.3%.

The basis for this goalis 86 days for the Cycle 14 Refueling Outege and 20 days rampup (10 full power equivalent days). The 1991 goal was 7%.

1

-The PCLF industry median value (for the three year pWiod from 1/89 through 12/91)is 18.3%.

l Data Source: Generation Totals Report & Monthly Operating Report Accountability: Patterson Adverse Trend: None 14 l

-M-Fuel Reliability indicator I 1995 INPO Industry Goal (0.5 X 10 3 Microcuries/ Gram)

-G-1992 Fort Calhoun Goal E

4-h3.5-g 3-2.5 -

2 2-Cycle 14 g

Refueling 1.5 -

Outage 1-O R

0.5 -

A A

A 0

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 FUEL RELIABILITY INDICATOR The Fuel Reliability indicator (FRI) was reported as 7.07 X 10 4 microcuries/ gram for the month of May 1992. During this month the plant was in the startup mode for the beginning of full power life for the Cycle 14 core.

The May FRI was calculated using the data from May 25 through May 31, in accor-dance with the INPO definition of steady state operation, the plant was at power levels above 85% during this time and the power levels did not vary more than + or 5% for at least 3 days. Only the lodine concentration values from the days that meet this steady state criteria can be factored into the INPO fuel reliability indicator.

The last detected fuel failure was during Cycle 13. The FRl values observed during the later months of Cycle 13 were in the 2.5 X 10-3 to 3.9 X 10 3 microcuries/ gram range.

Fuel;nspection/ reconstitution efforts during the last refueling outage replaced one defective rod in assembly N008 with a stainless steel pin. Fuoi assembly N008 is in the Cycle 14 core. NCR 92 029 includes the justification for fuel reconstitution and the use of assembly N008 in the core.

A Fort Calnoun goal of 7.5 X 10 4 microcuries/ gram will be utilized in 1992. Fort Cal-houn recognizes the INPO 1995 U.S. Industry goal of 5.0 X 10 4 microcuries/ gram and will revise the annual FRi goal accordingly.

The FRI was not applicable while the plant was shutdown for the refueling outage in February, March and April, and was not reported during those months.

j Data Source: 14olthaus/Guliani l

Accountability: Patterson/Spliker Adverse Trend: None l

15

O Monthly Personnel Radiation Exposure Personnel Cumulative Radiation Exposure (Man-Rem)

--O-ForiCalhoun AnnualGoal(250 Man Rem) 1995 INPO Industry Goal (185 Man Rom) 400-

-D-Industry Upper 10% (1163 Man Rem for a Three Year Average)

IGOODI 300-276 O---C C

a O

C C

C 200-A A

A A

93.4 100-52 b

L El A

O i

a i

i

'89

'90

'91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 COLLECTIVE RADIATION EXPOSURE During May 1992,5.584 man rem was recorded by TLDs worn by personnel while working at the Fort Calhoun Station. The year to date exposure is 226.458 man rom.

The Fort Calhoun goal for personnel radiation exposure (cumulative) during 1992 is 250 man rem. Cumulative radiation exposure for the Cycle 14 Refueling Outage was 216.899 man rem, whlen exceeds the outage goal of 210 man rem. The goal was not achieved because the outage was longer than anticipated and there was more expo-sure than expected due to the stuck reactor vessel stud and the thermal shield Inspec-tion.

The 1995 INPO industry goalis 185 man rem per year. The industry upper ten percen-i tile value (for the three year period from 1/89 through 12/91) is approximately 118.5 man rem per year. The three year average for Fort Calhoun Station from 1/89 through 12/91 is 140.4 man rem per year.

Data Source: Patterson/ Williams (Manager / Source)

Accountability: Patterson/Lovett Adverse Trend: None SEP 54 16 L

l

Curnuf ative Dry Active Waste Sent For Processing (in cubic feet) 25000-20000-15000-10000-5000-0-

Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 O

Radioactive Waste Buned Th's Month (in cubic feet)

- Curnulative Rad;oactive Waste Buried

-O-Fort Calhoun Goal For Waste Bi'riod (3,000 cubic feet)

--0--

1995 INPO Industry Goal (3,884 cubic f eet)

-O-Industry Upper 10% (2,118.5 cubic feet) 4310 4500 -

m a

a a

a

-o a

3000 -

O O

O

}---O O

O O---C O

O D---O O

33i.

1500 -

N bk 0

i i

i 10

'91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 Year end Total VOLUME OF LOW LEVEL SOLID RADIOACTIVE WASTE The upper graph shows the volume of radioactive oil and dry radioactive waste sent for processing. The lower graph shows the volun'e of the monthly radioactive waste bur-led, the cumulative annual total for radioactive waste buried, and the year end totals for radioactive waste buried the previous 2 years.

Cumulative amount of solid radwaste shipped oll site for processing (cubic f eet) 17,440.0 Amount of solid radwaste shipped oft cite for processing during May (cubic feet) 2,080 Volume of solid radioactive waste which was buried during May (cubic f eet) 140.4 Cumulative volume of solid radioactive waste buried in 1992 (cubic f eet) 343.4 Amount of solid radioactive waste in temporary storage (cubic feet) 240.6 The 1992 Fort Calhoun goal f or the volume of t.olid radioactive waste which has been buried is 3,000 cu'olc feet. The 1995 INPO industry goal is 110 cubic meters (3,884 cubic feet) per year, The industry upper ten percentile value is approximately 60 cubic meters (2,118.5 cubic feet) per year.

Data Source: Patterson/Breuer (Manager / Source)

Accountability: Patterson/Bilau Adverse Trend: None SEP54 17

-. - ~.. - - - - -.

. ~

1992 Disabling injury / Illness Frequency Rate

-H-- '1991 Disabic g injury /lliness Frequency Rate 1GOODI

- 1.4 -

y

-O-Fort Calhoun Goal (0.3) 1.2 -

-h-1995 INPO Industry Goal (0.5) 1-0.8

0'6 -

K N _.

.-e.

c.

s'%

0.4 -

e e

o.

e o

e-o o

o- _o j

0.2 -

3 Jan92 ' Feb dier Apr May Jun Jul -

Aug Sep Oct Nov ' Doc 9 DISABLING INJURY /lLLNESS FREQUENCY RATE (LOST TIME ACCIDENT RATE) i This indicator shows the 1992 monthly disabling injury / illness frequency rate in column.

form. The 1991 disabling injury / illness frequency rate and the 5 year average (from 1987 through 1991) of the corresponding munthly disabling injuiy/ illness frequency

' rates are also shown.

The disabling injury / illness frequency rate for May was 0.76. There were no lost time 3

. accidents reported at the Fort Calhoun Station in May.1992. The total number of lost time accidents that have been reported during 1992 is 2. The 1992 disabling injury / -

Illness frequency

ate goal was set at 0.30. The 1995 lNPO Industry goalls 0.50.

The disabling injuy/ illness frequency rate for the past twelve months is 0.68.

The industry upper ten percentile disab!!ng injury / illness frequency rato is 0.16.

ygg Year-End Rate

.1989 0.4 1990.

'0.5 1991-0.4 Data Source: Sorenson/Skaggs (Manager / Source)

Accountabilityi Patterson/ Richard Adverse Trend: None SEP 25 & 26 18

O vnermai output

-O-Fort Calhoun 1495 MW Goal Tech Spec 1500 MW Um!t 1500 -

mu%

, y[ '. mi fN' Y

.r,

. L

f., ' '

, Q

' ;: jf-n n-;v. ;d;;}

,f g

- &m;x;+ -

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-O

< m

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qg# -

'M-1V /

z. f3d.M37ygsf;

'pa g 4 %...:

g r_.

. My6,wg gp g y+ r g3;y? g

n

~

- m%

3 m c --

k.

yl ' [g^; 4 x p a. x ;;: n a,

~ >

&~~

$?j

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\\

a in

1000 _

,ny m.-..;o gg,wm a

l g,.

y,0 kkk;y y,,y_

n f :p ?S;? %

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Q.,~.T % ;g<a S n

w

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. 1 d d W W W W @kif % p y g%g 1M i

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.. c-Y ' *, c NINS h

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q&lvtyM np:yy. r 4:..

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r

wnM <' %gsyltk 4[;4;;WWhlm.;gdgw yyr g ;<.

.wsyy<

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. pp, 3. o, qqw;py_%gy gQgg:t)Mbidf JL. -4 Y:

.9+3Qw y

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ut gg Q un,

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p,(klnl&a$$$gllk &Q&g$y..gw wMwpm(w$ FIN,g 5 W 6 %

l$n r

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< $b.m W 4 5 JW: S@WMA$SiMNgegd@p@e& <

w 0-1 3

5 7

9~

11 13 15 17 19 21 23 25 27 29 31 DAILY THErlMAL OUTPUT The above thermal output graph displays the daily operating power level during May 1992, the 1500 thermal megawatt average technical specification limit, and the 1495 thermal megawatt Fort Calhoun goal, The power level declined after rampup from the Cycle 14 Refueling Outage due to the automatic reactor scram which occurred on May 14 when the turblac generator tripped on a false high level moisture separator trip signal which auseo s simultaneous reacter trip. The power level began to decline on May 31 at 2255 when Contiol Element No. 35 dropped into the reactor core.

Data Source: Holthaus/ Gray (Manager / Source)

Accountability: Patterson/Trausch l

Adverse Trend: None I-l tL 19 l

.--.2.

,,c.

m_,-,,.._

-,e

..-_,m,-.--.,4,

.--,m,,,,.

..-.-,:.&vm

,i

. +.

l 2-Equipment Forced Outage Rate

- 1992 Fort Calhoun Gual 1.4 -

1.2 -

1-0.8 -

0.6 -

0.s3 o,5 0.4 -

o.13 0.2 - C O

O O

O j

o i

4 i

1

'89 - '90

'91 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS The equipment forced outage rate per 1,000 critical hours was 0.68 for the months from January through May 1992.

There was one equipment forced outage during May. This oquipment forced outege occurred on May 14 when the turbin9 generator tripped on a false high level moisture separator trip signal which caused a simultaneous reactor trip.

The station battenes were declared inoperable in September through October 1991, in addition, two forced outages occurred during the month of October 1991: on 10/18/91 the generator was taken off line due to a steam leak on a turbine control valve before seat dra!n lind; on 10/25/91 the generator was taken off line due to a steam leak from an instrument tap on the high pressure turbine.

One equioment forced outage occurred dur!ng the month of August 1991. The outage was required to replace a failed potential transformer (PT). This PT converted 345 KV to 120 V for use in the breaker synchronization circuit,

- One equipment forced outage occurred in the month of January 1991 due to the De-cembar CEDM housing leak which carried outage time into January.

The 1992 Fort Calhoun goal for this indicator is 0.2.

Data Source: Monthly Operations Report & Plant Licensee Event Reports (LERs)

Accountability: Patterson/ Jaworski Adverse Trond: None 20 l

l r

Operations 1992 Budget ($ Milhon) 80-

-M-1992 Cumulative Total ($ Milhon) 60 -

40-20-

/

0-Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 Maintenance 1992 Budget ($ Milhon) 40-30-

--W-1992 Cumulative Total ($ Milhon) 20-10-Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 OPERATIOt1S AtID Malt 1TEt4At1CE BUDbdT The Operations an 1 M aintenance Budget Indicator shows the budget year-to-date as well as the actual e. pe1dituros for operations and maintenance for the Fort Calhoun Station.

The budget year to date for Operations was 32,055,400 dollars for May 1992 while the actual cumulative expenditures through May totaled 29,221,612 dollars. The 1992 year.

end budget for operations has been revised to 66,560,800 dollars, which is a reduction of 100,000 dollars.

The budget year to date for Maintenance was 13,138,000 dollars for May 1992 while the actual cumulative expenditures through May totaled 12,318,630 dollars.

Data Source: Gleason/ Parent (Manager / Source)

Accountability: Scofield Adverse Trend: None 21

1 O Docum:nts Scherubd for R3vi:w 50; -

O Documents Reviewed D Overdue Documents 400 -

P 300 -

200 -

7 2

I s

'(:

100 -

h 7

d h

j':

5j

-?

3

$w:

~h h

f 9;

t t,

x e

y 2

p,,A L

m z

j 9) e c

y,

'x

.z e-U

~'

~

i i

i e

i i

i 1

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 DOCUMENT REVIEW This indicator shows the number of completed, scheduled, and overdue (greater than 6 months past the scheduled due date) blennial reviews for the reporting mo, i.These document reviews are performed in house and include Special Procedures, the Site Security Plan, Maintenance Procedures, Preventive Maintenance Procedures, and the Operating Manual.

During May 1992 there were 101 document reviews completed while 72 document reviews were scheduled. At the end of May, there were 42 document reviews overdue.

During the month of May there were 10 new or renamed documents reviewed. These new or renamed documents will need to be reviewed again in 1994.

Data Source: Patterson/Mehy (Manager / Source)

Accountability: Patterson/Jaworski Adverss Trend: None SEP 46 22

i O

Numb:r of Failures /20 D:m:rds

-N-Trigger Values for 20 Demands D

Number of Failures /50 Demands

--V - Trigger Values for 50 Demands O

Number of Failures /100 Demands Trigger Values for 100 Domands 8-C-

Yi-V E V

Y Y

Y y- -y v

v v

i i

i d

i i

p i

i 4_

Nr E

=

- -W

=

- - -E W

M b

b b

b 2-

'l i

i I

s 1

?

1 1

f 8

i

{__

i fl [

E [

0 0

0 O

L g_

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 EMERGENCY DIESEL GENERATOR UNIT RELIABILITY This bar graph shows three monthly indicators pertaining to the number of fallures that were reported during the last 20,50, and 100 emergency diesel generator demands at the Fort Calhoun Station. Also shown are trigger values which correspond to a high level of confidence that a unit's diesel generators have obtained a reliability of greater than or equa! to 95% when the failure values are below the corresponding trigger val-ues. These trigger values are the Fort Calhoun 1992 goal.

The demands counted for this indicator include the respective number of starts and the respective number of load runs for both Diesel Generators combined, The number of start demands includes all valid and inadvertent starts, including all start only demands and all start demands that are followed by load-run demands, whether by automatic or manualinitiation Load run demands must follow successful starts and meet at least one of the following criteria: a load run that is a result of a realload signal, a load run test expected to carry the plant's load and duration as stated in the test specifications, and a special test in which a diesel generator was expected to be operated for a mini-mum of one hour and to be loaded with at least 50% of design load (see exceptions and other demand criteria in the Definition Section).

The demand failure which occurred during the month of August for DG 2 was due to a seal failure on the Jacket water pump.

Data Source: Jaworski/Ronning (Manager / Source)

Accountability: Jaworski/Ronning Adverse Trend: None 23 l

l

O DG 1 Failures /25 Demands D

DG 2 Failures /25 Demands 5-

--s - Failure Trigget Value for 25 Demands / Fort Calhoun Goal 4-C O

O O

3-2 2

2 2

.<~

1 i

1 1

c 1

4 m

n 4

v 00 0 V 0 d 0

0 j!)

0 0

0 0 0

0 0

0 i

i i

i Jun91 Jul Aug Sep Oct No.

Dec Jan Feb Mar Apr May92 DIESEL GENERATOR RELIABILITY (25 DEMANDS)

This indicator shows the number of failures experienced by each emergency diesel generator during the last 25 start demands and the last 25 load run demands. A trigger value of 4 failures within the last 25 demands is alsn rhown. This trigger value of 4 failures within 25 demands is the Fort Calhoun goal for 1991, it must be emphasized that in accordance with NUMARC criteria, coitain actions will take place in the event that any one emergency diesel generator experiences 4 or more failures within the last 25 demands on the unit. Tnese actions are described in the Definition Section. A Standing Order has been drafted for the Fort Calhoun Station to institutionalize and formally approve /a*

the required NUMARC actions.

Diesel Generator DG 1 has not experienced any failures during the last 25 demands on the unit.

Diesel Generator DG 2 has experienced one failure during the last 25 demands on the unit. A ceal failed on a jacket water pump in August 1991.

Data Source: Jaworski/Ronning (Manager / Source)

Accountab;lity: Jaworski/Ronning Adverse Trend: None 24

O Planned Hours of Dissel Gsnarator No. 2 Unavailability

@ Unp.annW Hours of Diesel Generator No. 2 Unavailability O Estirnated Hours c Diesel Generator No. 2 Unavailability i

E Planned Hours of Diesel Genefator No.1 Unaval! ability O Unplanned Hours of Diesel Generator No.1 Unavailability

200-3 l

{150-

)

7

[100-f so-po a

r!

n.

6 i

e i

i i

i Jun91 Jul Aug sep Oct Nov Dec Jan Feb Mar Apr May92 O Cumulative Hours of DG-1 Unavailability for 1992 O Cumulative Heurs of DG 2 Unavailabitely for 1992 15-7,9 o'i i

/ /j k,vI/:

0 0

e i

i i

i Jan92 rob Mar Apr May92 DIESEL GENERATOR UNAVAILABILITY This indicator provides a monthly illustration of diesel generator unavailability. The top graph shows the diesel generator planned, unplanned, and estimated unavailable hours for DG 1 and DG 2 for each month. The lower graph shows the cumulative hours of unavailability for each diesel generator for each month.

On May 26, there were 7.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months of planned unavailability for DG 1 to tighton the fan blades and repair a starting air solenoid valve.

lhe 1992 Fort Calhoun goalls a maximum of 210.82 hours9.490741e-4 days 0.0228 hours 1.35582e-4 weeks 3.1201e-5 months of unavailability for each l

diesel geno Itor.

l l

Data Source: Jaworski/Ronning (Manager / Source) -

Accountability: Jaworski/Ronning Adverse frend: None 25

~

O February 1992 Outstanding MWOs O ' March 1992 Outstanding MWOs O April 1992 Outstanding MWOs 300-O May 1992 Outstanding MWOs

' Programmatic change to reflect change in non outage entena.

200-100-

.(

x e t 0

i i

i 0 3 Months 3 6 Months 6-9 Months 912 Months

>12 Months AGE OF OUTSTANDING M AINTENANCE WORK ORDERS (CORRECTIVE NON OUTAGE)

This indicator shows the age of corrective non outage maintenance work orders (MWOs) remaining open at the end of the reporting month.

Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/ Bobba Adverse Trend: An adverso trend is indicated based on increasing values for three consecutive months for outstanding MWOs 0 3 months old and

>12 months old. This trend is due to the Cycle 14 Refueling Outage during February, March, and April.

26 L-

O February 9992 T'

400 -

0 ' March 1992

'p; 350 -

Y:

O 19 2

- v.

300 -

'p!

Programmate change to ref 50t change n non outage cntena

'p 250 -

'/.

h' W

200-

'3!

3 150 -

- 'p;

p;

p e

100 -

- Z

//

'/,

/,-

s'it

3

~3:

M 50-V.

/,-

//.

v,

'/,

gi-

/p/.

0 i

TotalOpen MWOs Open MWOs>3 Total Open Safety Open Safety Open High Priority rnonths old Related iEWC; Re!sted MWOs > 3 MW0s Months Old MAINTENANCE WORK ORDER BREAKDOWN (CORRECTIVE NON OUTAGE)

This indicator shows the total number of corrective non outage MWOs remaining open at the end of the reporting month, along with a breakdown by severai key categories.

The number of open MWOs >3 months old increased during February, March, and April because on line activities had to be scheduled beyond the end of the Cycle 14 Refueling Outage.

Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/ Bobba Adverse Trend: An adverse trend is indicated based on increasing values for three consecutive months for total corrective non outage MWOs and open high priority MWOs. This trend is due to the Cycle 14 Refueling Outage during February, March, and April.

SEP 36 l

27 l

l i

IGOODI 80%, -

D Corre:tive Maintenance Backlog > 3 Months Old 60%-

..?

k

[n M

m 40% -

fj Q

1 g

(l 7

,g c-9

.g gi s4 S

.j yr

?%

e c!.

+)

m a

e!/

ht,

'+ ;

l

Wj A

5 T,

5:

'tj hi M1 43 ~

?.

t;;

b hi 7

l9 N

M

-;[U

%Y i

m m

e a

w 20*/. -

a n2 jlg 4(!

M,y ijh

@n]

%o s>

2 1

p-

,n-o, we.

y.

v ik

?

O$,. k th)

$b

$l1

?l b

b hk f

e

-0%

Jun91 Jul Aug Sep Oct Nov Doc Jan Feb

' Mar Apr May92

Programmate f.hange to refle:t change in nonoutage critena.

CORRECTIVE MAINTENANCE BACKl.CG GREATER THAN 3 MONTHS OLD (NON-OUTAGE)

This indicctor shows the percentage of open corrective non outage maintenance work orders that were greater than three months old at the end of the reporting month.

The percentage of open corrective non outage maintenance work orders that were greater than three months old at the end of May 1992 was reported as 48.6%.

Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/ Bobba Adverse Trend: None SEP 36 28

O Ratio of Proventive to Total MaLntonanco Cycle 14 90%.

-O-1991 & 1992 Fort Calhoun Non Outage Goals Refueling Outage 80%-

A 70%-

GOOD l D

0 60%-

C O

O O

O

[

^

~"~

50%-

y

,7 N

40%-

i

~

f; 30%-

f,'

h ly o

B g

20%

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 RATIO OF PREVENTIVE TO TOTAL MAINTENANCE This indicator shows the ratio of completed non outage preventive maintenance to total completed non outage maintenance.

The ratio of preventive to total maintenance was 42.4% in May 1992.

The 1992 Fort Calhoun goalis to attain a ratio of preventive to total maintenance non-outage greater than 65% The 1991 Fort Calhoun goal was to attain a ratio of preventive to total maintenance greater than 60%

Accountability: Patterson/ Bobba Data Source: Patterson/Schmitz (Mancger/ Source) l Adverse Trend: None SEP 41 29

-j Sg q

4%-

G Preventive Maintenance ! terns Overdue l GOOD l

-O-1991 & 1992 Fort Calhoun Goals Y

J

-3%-

Cycle 14 Refueling 2%-

Outage 1%-

C C

C O--

O--%

(j li 0%

Jun91 Jul

_Aug-Sep Oct Nov Dec Jan Feb Mar Apr May92 PREVENTIVE MAINTENANCE ITEMS OVERDUE The purpose of this indicator is to monitor progress in the administration and execution of preventive maintenance (PM) programs.' ~ A small percentage of preventive mainte-nance items overdue indicates a station commitment to the preventive maintenance program and an ability te plan, schedule, and perform preventive maintenance tasks as programs require.

During May 1992,559 PM ltems were completed. 4 PM items (0.72% of the total 559)

' were not complet9d within the allowsNe grace period.

The percentage of preventive malr.tenance items overdue was higher in November because of a seneauling problem resulting in a delay in completing PM task paperwork.

na 1992 Fort Calhoun goalis to have less than 0.5% per month of the preventive maint3 nance items overdue.The 1991 Fort Calhoun goal was to have less than 1% per month of the preventive maintenance items overdue.-

o

' Data Source: Patterson/Brady (Manager / Source)

Accountability: Patterson/ Bobba Adverse Trend: None SEP 41 h

30 I

Control Room Instruments Repairable On Line

['

U Total Number of Control Room Instruments Out-of Service 50-

- O -- 1991 & 1992 Fort Calhoun Goals For Total Out of Service instruments

~ 40-30-

_ l

[

q p3 g

h f-

_rd___p r._

~

a_c m

10-O-

3 Jun91 Jul - -Aug

. Sep_

Oct.

Nov-Dec Jan Feb Mar Apr-May92-

- NUMBER OF OUT-OF-SERVICE CONTROL ROOM INSTRUMENTS

. This indicator shows the number of out-of service control room instruments, the number

. of instruments repairable during plant operations (on-line), and the 1991 and 1992 Fort Calhoun goals.

There was a total of 20 out of-service' control room instruments at the end of May 1992.

.1 of these instruments requires a plant outage to repair.

The 1992 Fort Calhoun goalis to have less than 13 out-of service corNal room instru-ments. The'1991 Fort Calhoun goal was to have less than 14 out of service control room' instruments.

Data Source:. Patterson/Spilker (Manager / Source)

L-

- Accountability: Patterson/ Bobba

- Adverse Trend: None I

31 h

e

-4

O Maintenance Overtime 80%-

lGOODI X-12 Month Average Maintenance Owtime g

70%-

- O - 1991 & 1992 Fort Calhoun"On Line" Goals

]

60%-

Cycle 14 Refueling Ou+ age 50%-

40%-

30%-

4 C

O O

O 20% -

M X

A

{t X

X X

N

~

8

,(

o 0%

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 MAINTENANCE OVERTIME The Maintenance Overtime Indicator monitors the ability to perform the desired mainte-nance activities with the allotted resources. Excessive overtime indicates insufficient resource allocation and can lead to errors due to fatigue.

The percent of overtime hours with respect to normal hours was reported as 8.6%

during the month of May 1992. The 12 month average percentage of overtime hours with respect to normal hours was reported as 16.0 %.

The 1992 Fort Calhoun goal for the "on-line" percentage of maintenance overtime hours worked is 10%.

Data Source: Patterson/Schmitz (Manager / Source)

Accountability. Patterson/ Bobba Adverse Trend: None 32

n-0 Open irs Rslated to the Use of Procsdures (Maintsnzncs)

O Closed irs Related to the Use of Procedures (Maintenance) 15'-

g. Procedural Noncernpliance irs (Maintenance)-

Cycle 14 Refueling-Outage

- 9 5

5-4 4

l 3

s 2

2 2

s

'1 t

1 i,?-

1 11 5+

1 "y

}

-000 C C 0--000 0

I fn

~ /

0 f :,

0 0 0 0'

0-l-

0 ',.

00-

-0

-i a

i-a i

e i

i i

e i

i Jun91-Jut 1 Aug Sep

' Oct '

Nov Dec '

Jan Feb Mar Apr May92 PROCEDURAL NONCOMPLIANCE INCIDENTS (MAINTENANCE)

This indicator shows the number of open Maintenance incident Reports (irs) that are l~

related to the use'of procedures, the number of closed irs that are related to the use of i -

procedures, and the number of open and closed irs that received procedural noncom-

- pliance cause_ codes.

There wereino procedural noncompliance incidents for maintenance reported for the li month of May 19i)2.

l'l.i-

. Data Source: Patterson/McKay (Manager / Source) l l

l-Accountability: Pattorson/Bobba p

Positive Trend -

SEP 15,41 & 44 L

33

800-B Open MWOs

--O- - 1991 & 1992 Fort Calhoun Goals Cycle 14 600-Refueling Outage C

432 389 400

[

310 $

302 M

$ h

,266 261 250

/

I L

0 i

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 MAINTENANCE WORK ORDER BACKLOG (CORRECTIVE NON-OUTAGE MAINTEN ANCE)

This indicator shows the number of corrective non-outage Maintenance Work Orders (MWOs) that were open at the end of the reporting month.

The 1992 goal for this indicator is to have less than 350 corrective non-nutage mainte-nance work orders remaining open. The 1991 goal for this indicator was to have less than 450 corrective non-outage maintenance work orders remaining open.

Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/Bobba Adverse Trend: An adverse trend is indicated based on three consecubve months of increasing values for corrective non outage MWOs, SEP 36 l

l L

3

~

m B

Completed Scheduled Activities (EM)

O Fort Calhoun Goal 100 % -

90%-

80%-

O

]

[

- 70% -

-. 60Vo-Cycle 14 Refueling Outage

$c; w

50%-

~ ' ~

I 40%-

g 13 h

30% -

{ll_ j;;

20%-

10%-

g

{;7{

0%

3/7 3/14 3/21 3/28 4/4 4/11 4/184/255/2 5/9 5/16 EW 5/30 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (ELECTRICAL MAINTENANCE)

This indicator shows the percent of the number of completed maintenance activities as compared to the number of scheduled maintenance activities concerning Electrical Maintenance. Maintenance activities include MWRs, MWOs, STs, PMOs, calibrations, and miscellaneous maintenance activities.

Data for this indicator was not tracked during the Cycie 14 Refueling Outage.

The Fort Calhoun Station goal for this indicator is 80%.

Reoortina Month-Comoteted Scheduled Activities

-Week 3 87.8 %

Week 4 79.5 %

. Data' Source: Patterson/Schmitz (Manager / Source)

-- Accountability: Patterson/Bobba Adverso Trend: None-SEP 33 35

4 Q

Completed Scheduled Activities (PE)

--O-Fort Calhoun Goal 100% -

90%-

80%-

6 --h Cycle 14 Refueling Outage

^

70%-

u 60%-

(

J[

I 50%-

gg a

40%-

nf 4

30% -

si 20%-

9' f

10%-

fj[

~

0%

3/7 3/14 3/21 3/28 4/4 4/11 4/18 4/25 5/2 5/9 5/16 5/23 5/30 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (PRESSURE EQUIPMENT)

This indicator shows the percent of the number of completed maintenance activities as compared to the number of scheduled maintenance activities concerning Pressure Equipment Maintenance. Maintenance activities include MWRs, MWOs, STs, PMOs, calibrations, and miscellaneous maintenance activities.

Data for this indicator was not tracked during the Cycle 14 Refueling Outage.

The Fort Calhoun Station goal for this indicator is 80%.

Reoortino Month Comoteted Scheduled Activities Week 3 82.9 %

Week 4 84.7 %

Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/Bobba Adverse Trend: None SEP 33 36

O Completed Scheduled Activities (GM)

-O-Fort Calhoun Goal 100 % -

90% -

80%-

C O

70% -

E SO% -

R Cycle 14 Refueling Outage 50% -

y g

e 40% -

m$ g

~3

!#l 30% -

20% -

9 j

10%-

0%

3/7-3/14-3/21-3/28 4/4 4/11 4/18 4/25 5/2 5/9 5/16 5/23 5/30 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (GENERAL MAINTENANCE)

This indicator shows the percent of the number of completed maintenance activities as compared to the number of scheduled maintenance activities concerning General Main-tenance. Maintenance activities include MWRs; MWOs, STs, PMOs, calibrations, and miscellaneous maintenance activities.

Data for this~lndicator was not tracked during the Cycle 14 Refueling Outage.

The Fort Calhoun Station goal for this indicator is 80%

-Reoortina Month -

Comoleted Scheduled Activities i"

Week 4 52.6%.

Week 3 66.7%

Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/Bobba Adverse Trend: None SEP 33 l'

I 37 p-

O Completed Scheduled Activities (MM)

-O-Fort Calhoun Goal 100 % -

90% -

8 0*'* '

O

_Q E

b 70% -

Cycle 14 Refueling Outage 7

60%-

E M;

Q g;

50% -

Q gy c

eq E

Ek 40% -

$t S

[

30%-

y

$g

}$

20% -

e e

h fb 10%-

I2 ef, i 3/7 3/14 3/21 3/28 4/4 4!11 4/18 4/25 5/2 5/9 5/16 5/23 5/30 PERCENT OF COMPLETED SCHEDULED MAINTENANCE ACTIVITIES (MECHANICAL MAINTENANCE)

This indicator shows the percent of the number of completed maintenance activities as compared to the number of scheduled maintenanco activities concerning Mechanical Maintenance. Maintenance activities include MWRs, MWOs, STs, PMOs, calibrations, A

and miscellaneous maintenance activities.

Data for this indicator was not tracked during the Cycle 14 Refueling Outage.

The Fort Calhoun Station goal for this indicator is 80%.

Reoortina Month Comoteted Scheduled Activities Week 3 83.8%

Week 4 77.6%

Data Source: Patterson/Schmitz (Manager / Source)

Accountability: Patterson/Bobba Adverse Trend: None SEP 33 38

i i

O Completed Scheduled Activities (IC)

H">-

Fort Calhoun Goal 100% -

90%-

80%-

Cycle 14 Refueling Outage Y

r 70%-

!C 44 1[l 60%-

w 50%-

j l3; 40%-

[d!.'

aD us 30%-

$[s s

20% -

10%-

ge gt 0%

3/7 3/14 3/21 3/28 4/4 4/11 4/18 4/25 5/2 5/9 5/16 5/23 5/30 PERCENT OF COMPLETED SCHEDULED MA!NTENANCE ACTIVITIES (INSTRUMENTATION & CONTROL)

This indicator shows the percent of the number of completed maintenance activities as compared to the nurnber of scheduled maintenance activities concerning Instrumenta-tion & Control. Maintenance activities includo MWRs, MWOs, STs, PMOs, calibrations, and miscellaneous maintenance activities.

Data for this indicator was not track.ed dung the Cycle 14 Refueling Outage.

The Fort Calhoun Station gos; M ibis indicator is 80%.

Comoleted Scheduled Activities-Reoortina Month Week 3 91.1 %

Week 4 89.0 %

Data Source: Patterson/Schmit (Manager / Sot. ne)

Accountability: Patterson/Bobba Adverse Trend: None SEP 33 39

3-

@ Number of Missed STs Resulting in LERs 2-

)

1-0 0

0 0

i i

10-SO 31

=Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 NUMBER OF MISSED SURVEILLANCE TESTS RESULTING IN LICENSEE EVENT REPORTS This indicator shows the number of missed Surveillance Tests (STs) that result in Lic-ensee Event Reports (LERs) during the reporting month. The graph on the left shows the yearly totals for the indicated years, s

During the month of May 1992, there were no missed STs that resulted in LERs.

The 1991 & 1992 Fort Calhoun goals for this indicator are zero.

Data Source: Month!y Operating Report & Plant Ucensee Event Reports (LERs)

Accountability: Patterson/Jaworski Adverse Trend: None SEP 60 & 61 40

40-

-G-component

-+- Application

--*- Total 30-25-M' 8

$20-

^

n-

'd 5-D J91 F

M A

M J

J A

s O

N D J92 F

M A M92 63.0%

O WearOut/ Aging Q Other Devices s

@ Manufacturing Defect O Mainterance/ resting O Engineering / Design 0 arror 1_~ a w m ** # P** M MlisulOF F"

S.0%

~

11.0%

3.0% -

11.0%- '-p AO%

MAY 1992 COMPONENT F/ lLURE ANALYSIS REPORT (CFAR)

SUMMARY

This indicmor shows the number of items with high failure rates for the 18 months from December 1990 through May 1992. The top chart illustrates the component, application and total failures for each month in the 18 month time period. The lower chart depicts the breakdown by cause categories (see the " Definitions" section of this report for de-scriptions of these cause categories) for each type of failure for the reporting month.

The " component"_ portion of this indicator tracks the number of component categories (i.e. reciprocating pumps, feedwater pumps, motor operated valves, etc.) in which the Fort Calhoun Station has a higher failure rate than the rest of the industry. For the l

month of May, this value is 6.

1 The " application" portion of this indicstor tracks the number of application categories I

(i.e. charging pur ps, feedwater pump discharge valves, etc.)in which the Fort Calhoun Station has a higher failure rate than the rest of the industry. For the month of May this value is 7.

Data Source: Jaworski/ Dowdy (Manager / Source)

Accountability: Jaworski/ Dowdy Adverse Trend: None 41

d Greater Than One Failuro

'40-

--+- Greater Than Two Failures

- Greater Than Five Failures 35-30-25-7

=

20-15-10-5-

l '

Jul91 Aug-Sep Oct Nov Dec Jan Feb Mar Apr May92 NUMBER OF NPRDS MULTIPLE FAILURES This indicator shows the number of multiple NPRDS reportable failures over the preced-ing eighteen months sorted by component manufacturer and model number. The indica-tor is divided into three parts: manufacturer model numbers with more than one tailure in eighteen months, manufacturer model numbers with more than two failures in eigh-teen months, and manufacturer model numbers with more than five failures in eighteen months.-

During the past eighteon months,there were 21 model types that had more than one failure in eighteen months 10 of these had more than two failures. 4 component types, General Electric 50-570-01 power supplies, Gaulin P18 pumps, Byron Jackson 28RXL

. pumps and Jayco incorporated 150 valves haa more than five failures.The model types with more than two failures are: General Electric AK-2A-25 circuit breakers (3 failures),

the OSPDS (3 failures), Faulk Type Y couplings (3 failures), Byron Jackson 28RXL i

pumps (6 failures), Gaulin P18 pumps (11 failures), General Electric 50-570 power

< supplies (4 failures), General Electric 50 570-01 power supplies (8 failures), General L

Electric 12HEA61 relays (3 failures), Jayco incorporated 150 valves (6 failures) and the pressurizer (4 failures).

Data Gource: Jaworski/ Dowdy (Manager / Source)

Accountability: Jaworski/ Dowdy Adverse Trend: None l

42 L

i

Components With More Than One Failure lGOODI 20-X Components With More Than Two Failures 15-10-1 5-

[

v v

u o

u s

o m

n 0

h May91 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr92 MAINTENANCE EFFECTIVENESS The Maintenance Effectiveness indicator was developed following guidelines set forth by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Opera-tional Data (NRC/AEOD). The NRC/AEOD is currently developing and verifying a maintenance effectiveness indicator using the Nuclear Plant Reliability Data System (NPRDS) component failures.

This iridicator has been tevised to show the number of NPRDS components with more than one failure duiing the last eighteen months and the number of NPRDS compo-nents with more than two failures during the last eighteen months. The number of NPRDS components with more than two failures in an eighteen month period should indicate the effectiveness of plant maintenance. (This change applies only to the Sep-tember 1991 through May 1992 data. The data for June through August 1991 is based on a twelve month interval.)

During the last 18 reporting montns there were 13 NPRDS components with more thar 1 failure. 4 of the 13 had more than two failures. The tag numbers of the components with mc e than two failures are B/PQ-905, CH-1 A, CH-18, and RC-4.

Data Source: Jaworski/ Dowdy (Manager / Source)

Accountabliit/ Patterson/Bobba Adverse Trend: None 43

20-I

- Calculated Check Valve Failure Rats per Million Component Hours

- Industry Check Vatve Failure Rate per Million Component Hours 15-

--O-Fort Calhoun Goal

[GCODI v

10 e 10-g tT2 N's 5-e

[>

N[

i e

6----A A

1 1

O O

--O O

O O --- @

N N

0

'89 '90 '91 Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 Check Valva Failures CHECK VALVE FAILURE RATE This indicator shows the Fort Calhoun check valve failure rate, the Fort Calhoun goal and the industry check valve failure rate. This rate is based upon failures during the previous 18 months. The check valve failures at Fort Calhoun Station for the previous two years are shown on the left.

The data for the indust y check valve failure rate is three montns behind the reporting month due to the time involved in collecting and processing the data.

For February 1992, the Fort Calhoun Station reported an actual check valve failure rate of 6.09 E-7, while the industry reported an actual failure rate of 2.83 E-6. At the er.d of May 1992, the Fort Calhoun Station reported a calculated check valve failure rate of 6.07 E-7.

The 1992 Fort Calhoun goal for this indicator is a failure rate of 2.00 E-6.

y Data Source: Jaworski/ Dowdy (Manager / Source)

Accountability: Jaworski/Rollins Adverse Trend: None SEP43 6

I O

Sicondary Systom CPI

-O--

Fort Calhoun Goal (.45)

--6--

1995 INPO Industry Goal (0.30) 1.5 -

l Secondary System CPI Limit

-O--

Industry Upper 10% (0.33) 1-4 l

l l

+

Cycle 14 Refueling 05-O-O-U O-O-O-O Outage U

O -

o 38 oy

] 7

$Z8Z8Z8 dZ8Z8Z8 6

e iO i,#

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 5%-

O % of Hours Chemistry is Oi4%ide OG Guidelines 3%-

Cycle 14 Refueling Outage 0%

i i

i Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 SECONDARY SYSTEM CHEMISTRY The top graph, Secondary System Chemistry Performance Index (CPI), is calculated using the following three parameters: cation conductivity in steam generator blowdown, sodium in steam generator blowdown, and condensate pump discharge dissolved oxygen. The bottom graph shows the percent of total hours of 13 parameters exceed-ing the Owners Group (OG) guidelines during power operation.

The percent of hours outside the OG guidelines was reported as 0.31% for the month of May 1992. The CPI was reported as 0.505 for the month of May 1992.

The 1991 & 199'2 Fort Calhoun goals for the CPI ere 0.45. The INPO 1995 Industry goal is 0.30. The industry upper ten percentile value for this indicator was approxirr'tely 0.20 for 1991.

Data source: Franco /Glantz (Manager / Source)

Accountability: Patterson/Schmidt Adverse Trend: None 45 l

10%-

Primary Systom Chemistry Percent of Hours Out of Limit

--O-Fort Calhoun Goal BM 6%-

l 4 % --

Cycle 14

[

Refueling O

2%-

C O

O O

p Outage rN 0%

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb M

Apr Mays 3 PRIMARY SYSTEM CHEMISTRY PERCENT OF HOURS OUT OF LIMIT The Primcry System Chemistry - Percent of Hours Out of Limit indicator tracks the primary system chemistry performance by monitoring six key chemistry parameters.

Typically, lithium is the parameter that is out of limit.100% equates to all six parameters being out of limit for the month.

The Primary System Chemistry Percent of Hours Out of Umit was reported as 0.96% for the month of May 1992.

A plant outage in November and December 1990 resulted in a higher percentage of hours out of limit.

The 1992 Fort Calhoun goal for this indicator is 2%. The 1991 goal was 2%.

Data E'ource: Franco /Glantz (Manager / Source)

Accountability: Patterson/ Smith Adverse Trend: None 46 l

l-10% -

O

% of Hours Auxiliary System (CCW) Chemistry is Outside Station Umbs

- 1991 Industry Upper Quartite 8%-

6%-

4%-

Cycle 14 2%-

Refueling Outage E

O O

D--C C

C C

C D

i e

i i

i

'89 90 Jun91 Jul Aug Sep Oct N3v Dec Jan Feb Mar Apr May92 AUXILIARY SYSTEM (CCW) CHEMISTRY PERCENT OF HOURS OUTSIDE STATION LIMITS The Auxiliary System Chemistry Percent of Hours Outside Station Limits indicator tracks the monthly hours that the Component Cooling Water (CCW) system is outside the station chemistry limit.

The auxiliary system chemistry percent of hours outside station limits was reported as

~

0% for the month of May 1992. The last out of station limits condition occurred in June 1991 and was due to a low nitrite levelin CCW coolant.

The 1991 Fort Calhoun goal for this indicator was a maximum of 2%

Data Source: Franco /Glantz (Manager / Source)

Accountability: Patterson/ Smith Adverse Trend: None 47

i G

Number of In:trum:nts Out-7f.Servics 20 20,

--O--

Fort Calhoun Goal 18 g7

'/4<

-h 16-15 15 1s VA

///,A w

?/

'A 14-y,

'Al,,Xi

'~

W4 V/A Y/

f V4 12-f

',,f i

$hY l

M M

g

'gj io-

'/,k k

8-8-

C

, ---(5'~~~~, ^

O-~~

~

3;

?yfl

'A'A 4

4-W 3

//

n w,;

h l

Y/4

'f,YS

/,

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr MayD2 IN-LINE CHEMISTRY INSTRUMENTS OUT-OF SERVICE This indicator shows the total number of in-line chemistry system instruments that are out-of-service at the end of the reporting month. The chemistry systems involved in this-Indicator include the Secondary System and the Post Accident Sampling System (PASS).

At the end of May there was a total of 20 in-line chemistry instruments that were out of-service. Of these 20 instruments,18 were from the Secondary System and 2 were from

. PASS. Most of the cut-of service instruments are at the secondary sample panel due to a conibination of alarms not being operable and failure of two of the actualinstruments, The increase that occurred after November 1991 in the number of Secondary instru-ments out of service is due to a new method of determining if an instrument is out of service. The entire instrument channel is considered inoperative if: 1) the instrument is inoperative,2) the chart recorder associated with the instrument is inoperative,3) the alarm function associated with the instrument is inoperative. This change was made because if any of the functions named above cre not operational, then the instrument is not performing its intended function.

The 1992 Fort Calhoun goal for the number of in-line chemistry system instruments that are out-of-service has been set at 6. Six out-of-service chemistry instre' ents make no 10% of all the chemistry instruments that are counted for this indicator.

Data Source: Patterson/Renaud (Manager / Source)

Accountability: Patterson/Jaworski Adverse Trend: None 48

Total Waste Produced (Kilograms)

- Federal & State Monthly Limit (Kg) 1000 -

3 800 -

600 -

400-200-154.5 150 4.9 1 o

o o

o i

i i

6 i

i i

i Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 HAZARDOUS WASTE PRODUCED This indicator shows the total amount of hazardous waste produced by Fort Calhoun each month. This hazardous waste consists of non halogenated hazardous waste, halogenated hazardous waste, and other hazardous waste produced.

During the month of May 1992,0.0 kilograms of non halogenated hazardous waste was produced,0.0 kilograms of halogenated hazardous waste was produced, and 0.0 kilograms of other hazardous waste was produced, The amount of halogenated hazardous waste increased in December 1991 because of a change in the method of record keeping. Hazardous waste is no longer counted on a monthly basis. It is counted based upon a full drum of waste.

Date Source: Patterson/Henning (Manager / Source)

Accountability: Patterson/Henning Adverse Trend: None 49

O Highest Exposure for the Month (mrem)

D Highest Exposure for the Quarter (mrem)

E Highest Exposure for the Year (mP.em) 5000-OPPD 4500 mrem /yr. Limit 4000-3000 -

2000 -

1707 232 0-i May MAXIMUM INDIVIDUAL RADIATION EXPOSURE During May 1992, an individual accumulated 232 mrem which was the highest indi-vidual exposure for the month.

The maximum individual exposure to date for the second quarter of 1992 was 647 mrem.

The maximum individual exposure reported for the year 1992 was 1,707 mrem.

The OPPD limit for the maximum yearly individual radiation exposure is 4,500 mrem /

year.The 1992 Fort Calhoun goalis 1,500 mrem / year.

Date Source: Patterson/ Williams (Manager / Source)

Accountability: Patterson/Lovett Adverse Trond: None 50

300-O Montniy Personnei Contaminations Cumulative Personnel Contaminations 237

-O-Fort Calhoun Annual Goal (144) 200-

~

C O

O O

/

100-Z4 55 50 -

25 5/-

10 0 "",

~

t'~

i i

'90

'91 Jan92 Feb Mar Apr May Jun Ju; Aug Sep Oct Nov Dec92 TOTAL SKIN AND CLOTHING CONTAMINATIONS This indicator shows the number of skin and clothing contaminations for the reporting month. A total of 213 contaminations have occurred during 1992.

There was a total of 55 skin and clothing contaminations in 1991.

There was a total of 237 skin and clothing contaminations in 1990.

The 1992 goal for skin and clothing contaminations is 144.

Data Source: PattersonM/illiams (Manager / Source)

Accountability: Patterson/Lovett Adverss Trend: None SEP 15 & 54 51

D Decontaminated Radiation Centrolled Area 100% -

GOOD

-O-Fort Calhoun Goal (non-outage months)

Cycle 14 3

Refueling 9 0*' -

5,q m

m m

m n

Outage

?g sE G

V 1.

Q O

D 6

O M: 6 [

g s

y

@e gj jf 4

n' D

s s

^

/3ri w

4a 00 T

E

4 80%-

6%

W W

i W

is p

%y 5

W g

e w

+-

g yt;>-

4

%. i Q1

?

ty e

m

&.2

uce, 9

y sp m

n Hjy P &;

n %..

N'_'

"( g M%

.Q 3

-se 43d A;

s-;;

f;R fa 70%-

3..

4fs' s

4 e

a E

A L

m

~

h s

s

?t}

?

i-si:

h M

y;;

&{ad 3b d

w.

=

.M H.'

=

hic y

ca '

@[

nj

)4 1N

'y a

P

f)

%@s'a) 98 M

W X

.I d

d

-Q

%la'N ad

}$4 k

?gl M

y W

W M

Q L;

M C

N

%y k'if Qf 60%-

g Q@

m e

a&

>x R

et W.

m qf

p$a t

4<

qMn 16 9

~

a; g,.

V 3,

g cu

~g egr

%gg MJ m

~

T$j

?9

[d3 fN

@g?

m 9

e n

o w.

v

??

50 %

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 DECONTAMINATED RADIATION CONTROLLED AREA This indicator shows the percentage of the RCA that is decontaminated (clean) based on the total square footage, a 1991 Fort Calhoun goal of 85% decontaminated RCA for non-outage months and a 1992 goal of 88% decontaminated RCA for non-outage months.

At the end of the reporting month,86.2% of the total square footage of the RCA was decontaminated.

Date Source: Patterson/Gundal (Manag er/ Source)

Accountability: Patterson/Lovett Adverse Trend: None SEP 54 52

80-

@ Number of identified PRWPs Cycle 14 Refueling 70-Outage 60-59 50-39 40-30-20-15 10-4 4

0 I-I i

i i

i I

i l

i I

l Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 RADIOLOGICAL WORK PRACTICES PROGRAM The Radiological Work Practices Program Indicator shows the number of Poor Radio-logical Work Practices (PRWPs) which were identified during the reporting month. The PRWPs are identified through a review of the monthly Radiological Occurrence Reports and Personnel Contamination Reports.

l-The number of PRWPs which are identified each month shouldindirectly provide a means to qualitatively assess supervisor accountability for their workers' radiological performance.

Duri_ng.the month of May 1992,1 PRWP was identified. The numbers of PRWPs for the months of February, March and April are higher than the numbers reported for previous

- months due to the Cycle 14 Refueling Outage.

Data Source: Patterson/ Williams (Manager / Source)

Accountability: Patterson/Lovett Positive Trend SEP 52 53

O Total Numt:or of Hot Spots O

Number of Additional Hot Spots identified Cumulative Hot Spots Removed O

Removal Planned 7s -

-O - 1992 Fort Calhoun Goal for Hot Spots Removed

]

1 9

i i

50 -

t; l

l 25-."

1 i

m 0

4 i

i i

Jan92 Feb Mar Apr May June July Aug sept Oct Nov Dec92 NUMBER OF HOT SPOTS This indicator shows the total number of hot spots.yhich have been identified to exist in the Fort Calhoun Station and have been documented through the use of a hot spot identification sheet. A hot spot is defined as a smalllocalized source of high radiation. A hot spot occurs when the contact dose rate of an item or piece of equipment is at least 5 times the General Area dose rate and the item or piece of equipment's dose rate is equal to or greater than 100 mrem / hour.

At the end of May, there were 63 hot spots identified. 33 of these hot Jpots were consid-ered permanent, i.e. hot spots which are not significant dose contributors or are cost prohibitive for removal.1 hot spot was removed in the boric acid storage tank area and no new hot spots were identified during the month.

Removalis planned for 18 hot spots.12 hot spots are stiii under evaluation.

The 1992 Fort Calhoun goalis to remove one hot spot per month.

Data Source: Patterson/ Williams (Manager / Source)

Accountability: Patterson/Lovett Adverse Trend: Nt,no 54

Monthly Radioactive Gas Discharged (Curies)

+

800-Cumulative Radioactive Gas Discharged (Curies)

-O-Cumulative Annua 1 Goal (Curies) 600 -

465 Ym b

'I 400 -

7059 8 j$s?!

C O

O O

O

'W

@e r

200 -

164

[

N(k 4d gh

" - ^ '

0 i

i 3

i i

'89 50 Jan91 Feb Mar Apr May Jun Jul Aug Sept Oct Nov Dec91 GASEOUS RADIOACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT.

The gaseous radioactive waste being discharged to the environment is shown for Janu-ary 1,1991 through December 31,1991. A total of 358.5 curies have been released to the environment during this time, i

in September,238.236 curies of gaseous radioactive waste was released to the envi-ronment due to containment purges required during the unscheduled maintenance outage. Most of the radioactive waste was released in the form of Xenon 133.

The Fort Calhoun Station cumulative annual goal for 1991 was 340 curies for this indi-l cator.

The gaseous radioactive waste being discharged to the environment is calculated every six months.

Data Source: Franco /Krist (Manager / Source)

Accountability: Patterson/Trausch Adverse Trend: None 55

Monthly Radioactive liquid Discharged -

--- Cumulative Radioactive liquid Discharged V

-O-Cumulative AnnualGoal 300-231 228 C

0 0

0 P

j 200-ya

@p-175 e

@n

'IN B -j w

c, N h b:

o g2

^2 M@ k 100-kh k t

~,

h 18.2 22.7 28 4 33.9 28.2 Id 354 s gi y@

8.4 9.1 5.3-6.3 4.8

_8.3 2.3 m

0 m.

I i

6 I

4.

I I

i i

I i

I

- '88 '89 '90

Jan91 Feb M o,-

Apr May Jun Jul Aug Sept Oct Nov Dec91 LIQUID RADIOACTIVE WASTE BEING DISCHARGED TO THE ENVIRONMENT

- The liquid radioactive waste being dischar'ged to the environment is shown for January 1,1991 through December 31,1991. The liquid radioactive waste that was dlscharged to the environment from all sources totaled 176.1 curies during this time. The Fort Calhoun Station cumulative ennual goal for 1991 was 225 curies.

The liquid radioactive waste being discharged to the environment is calculated every six months.

Data Source: Franco /Krist (Manager / Source)

Accountability: Patterson/Lovett Adverse Trend: None 56

D Non-System Faitures lGOODI 30-h 25-20-17 15-p h 2

0 i

i Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 lGOODI h

80-73

'~~

70 -

60-56 52 50-43 40-l

[

33 30-20-10-0 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec92 LOGG ABLE/ REPORTABLE INCIDENTS (SECURITY)

The Loggable/ Reportable incidents (Security) Indicator is depicted in two separate l

graphs. The first graph depicts the total number of loggable/reporiable non-system failures concerning Security Badges, Access Control and Authorization, and Security Force Error, and Unsecured Doors. The bottom graph showc the total number of loggable/ reportable incidents concerning system failures which occurred during the reporting month.

During the month of May 1992, there were 35 loggable/ reportable incidents identified.

System failures accoun;ed for 33 (94%) of the loggable/ reportable incidents, and 8 (24%) of these were environmental failures. Of the 12 microwave alarm failures identi-fied,10 were attributed to one zone. The problem was caused by a faulty transmitter which has been identified and repaired. Of significance were door hardware incidents which declined dramatically during May (from 16 to 4).

Data Source: Sefick/Woerner (Manager / Source)

Accountability: Sefick Adverse Trend: None SEP 58 57

O _ rebru ry 92 0 March 52 O April 92 0 May 52 20~

15~

_7_

7 5

5-4 2

2 l'$'?

hk

'O O

l l

i 0

0 i

0-Badges Accesa Control

' Security Force Error Unsecured Doore SECURITY NON SYSTEM FAILURES This indicator shows the number of loggablahnp able non system failures for the reporting month. Tnese items include: Secunty Badges, Access Control and Authoriza-tion, Security Force Error, and Unsecured Doors.

{

Non System Failure.g,

Number of Incidents May.'E2 Aor. '92 Security Badges' 2

1 Access Control and Authorization 0

0 Security Force Error.

O.

1 Unsecured Doors Q

E Total 2

7 r

Data Source: Selick/Woerner(Manager / Source)

Accountability: Sefick =

Adverse. Trend:LNone SEP 58 4

/

.4

~_,.;..

O Environmentai O Failuro I b@D I

+

20 -

15-10-6-

4 3

~

l 0

0 O

o Atarms CCTV C omputer Soarch Equipment Doors C 1901 System Failuros D 1992 System Felivros

!b UI

+

100 -

i 00-73 71 79 C,

00-DO b

53 53 50 S2

[4 3

43

?'M 42

~

40-g j) p h.j 33 h

k f

jj

]

20-d a

e Jan roo ' uar A

Ma Jun Jul Aug Sep Oct Nov Dec

(

SECURITY SYSTEM FAILURES This indicator shows the numbet v toggable/ reportable system failures for the reporting month. These items include: Alarm System ailures, CCTV failures, Security Computer r

Failures, Search Equipment Failures and Door Hardware Failures Alarm systems and CCTV failures will be divided into two categories: environmental failures and failures as defined in the performance indicator definitions. Also, the 1991 and 1992 System Fail-ures will be compared on a monthly basis.

Syrtem Number of incidents May '92 ADIiL*22 Environs failures Enp us Failures Alarms 4

12 12 10 CCTV 4

3 1

2 Computer N/A 5

N/A 6

Search Equipment N/A 1

N/A 5

Door Hardware

(('A f

((IA 3

Totals 8

25 13 39 Data Source: Sefick/Woerner (Manager / Source)

Accountabi;ity: Sefick/Pattarson Adverse Trend: None SEP 58 59

10*/. -

O Amount of Work On Hold Awalting Parts 9%-

--O-1991 & 1992 Fort Calhoun Goals 8%-

7%-

6% -

Cycle 14 Refueling 5%-

Outage

~~

4%-

C O

C C

O 3%-

g M

f Q

g

~

y

.f:Aj (g

n n

n 4

1%-

fi

~}

,?

fp 7

f lii i

i 5

P b

2

{

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 AMOUNT OF WORK ON HOLD AWAITING PARTS (NON OUTAGE)

This procurement indicator displays the percentage of open, non outage maintenance itams that are on hold awaiting parts, to the total amount of open, non outage mainte-nance items.

There was a tota! of 902 open, non outage maintenance work orders (MWOs) with 8 (0.89%) of thee MWOs on hold awaiting parts at the end of the reporting month.

The 1991 and 1992 Fort Calhoun Goals for this indicator are 3.5% of the total number of open, non outage MWOs awaiting parts.

Data Source: Willrett/ CHAMPS (Manager / Source)

Accountability: Willrett/Fraser Positive Trend l

o

20-

-m Spue Pads Inventory Value ($ Million)

I 15-i 1

j 10-5-

0-7 i

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 l

l-SPARE PARTS INVENTORY VALUE The spare parts inventory value at the Fort Calhoun Station at the end of May 1992 was reported as $13,646,008.

Data Source: Steele/Huliska (Manager / Source)

Accountability: Willrett/McCormick Adverse Trend: None

==== Spare Parts issued ($ Thousands) l 800-000-400-200-0 i.

i i

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 SPARE PARTS ISSUED The value of the spare parts issued during May 1992 totaled $267,822,47. The value of

- the spare parts issued for November and December 1991 was not available due to a printer problem.

l Data Source: Steele/ Miser (Manager / Source)

Accountability: Willrett/McCormick

- Adverse Trend: None 61

i O

inventory Accuracy

-O-Fort Calhoun Goal (98%)

100%q r.q m

m n

Q O

O -O-9-U-Q-Q Q ---O O

Q M(! R1 7

d 95%- M b

N N

2

,fj n

a 9

G 14 R

ty T

rq Jun41 Jul Aug Sep Oct Nov Doc Jan Feb Mar Apr May92 ItWENTORY ACCURACY This indicator shows the accuracy of the actual parts count for the warehouse compared to the counts contained in the MMIS computer system for ihe reporting month.

During May,1,178 different line items were counted in the warehouse. Of the 1,178 line items counted,74 items needed count adjustments. The inventory accuracy for the month of May was reported as 94% The Fort Calhoun 1991 & 1992 goals for this indi-I cator are 98%

Data Source: Willrett/McCormick (Manager / Source)

Accountability: Willrett/McCormick Adverse Trend: None

% of Pick Tickets Generated When Parts U

are not Available, etc.

7%-

6%-

5

-- O - Fort Caboun Goal M

5%-

4%-

g m$

O O

O

( p a

ga e

it 8

v n

a m

rm

~

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 STOCKOUT RATE This indicator shows the percentage of the number of Pick Tickets generated when the amount of parts requested is equal to or less than the minimum stocking level and parts are not available.

I During May 1992, a total of 986 Pick Tickets were generated. Of the 986 Pick Tickets generated, 7 Pick Tickcis (0.7 %) were generated when the amount of parts requested l

was equal to or lesr than the minimum stocking level and parts were not available. The l

Fort Calhoun 1992 goal for this indicator is 2.6% and the 1991 goal was 2.0%

Data Source: Willrett/McCormick (Manager / Source)

Accountability: Willrett/McCormick Adverse Trend: None 62

~

% of Total Purchases that are Expedited 4%-

Cycle 14

-O-1991 & 1992 Fort Calhoun Goals (0.5%)

Refueling Outage a

3%-

[9 7

1,c

?

2%-

R m

k-d.

t o, 1

r/-

1%-

Y A

[A

w

.:n m.

n MJ Sin FC o-o o

o--o--c 0

o-o--o-o N

6 i%

o% %

0%

i i=

i i

Jun91 Jul Aug Sep Oct Nov - Dec Jan Feb Mar Apr May92 L

i EXPEDITED PURCHASES L

. This indicator shows the percentage of expedited purchases compared to the total number of purchase orders generated during the reporting month.-

l During May, there was a total of 321 purchase orders generated.'Of the 321 purchase L-

- orders generated,1 (0.31%) was an Lxpedited purchase. The expedited purchase was L

for radiation protection sources.

- The 1992 Fort Calhoun goal for this indicator is 0.5%. The 1991 goal was 0.5%'.

l The' number of expedited' purchases was above the Fort Calhoun goal during the months of February, March and April 1992 due to the ordering of items related to the Cycle 14 Refueling Outage.

- Date Source: Wilfrett/Fraser (Manager / Source)

Accountability: Willrett/Fraser Adverse Trend: None to e

G v*-

e ar-.J i

m-,

c.-,,%_+--.

,,,,,,g-,,,--;-

..-me,--,,c.-.,,,

.,r,w+r-vmm wa v----

m v ewwb w g m' S-r-m-w a-m a r -

m-*

5"o

100-80 -

so-40-19 20-12 0-i i

Service invoices COE Invoices Miscellaneous INVOICE BREAKDOWN This indicator shows the number of service invoices, COE invoices, and miscellaneous invoices for the month of May 1992.

Date Source: Willrett/Fraser (Manager / Source)

Accountability: Willrett/Fraser i

Adverse Trend: None 1

- Percentage of Material Requests for issue with the 100% -

E Request Date the same as the Need Date

-O-1991 Fort Cathoun Goal 80%-

T

~

~~~

60%-

C O- -

-C O

O O

O

(

[:

[

s y$;.

l$f}

l l$?

40%-

pi..

pg L

gg m

j

k y

{

pg gf e,3 s

(

's g

r i

..c.

e;.

.e q

gy;

[N;;

g 9

27 g

,d 20%-

q*

~'

i..

N k/8 k-4 Lr '

j i

0%

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 MATERIAL REQUEST PLANNING This indicator shows the percentage of material requests (MRs) for issue with their E

request date the same as their need date compared to the total number of MRs for issue for the reporting month. The 1991 goal of 60% is also shown.

During the month of May, a total of 986 MRs were received by the warehouse. Of the 986 total MRs received by the _vearehouse,- 67.5% of the MRs (666 ) were for issue with their request date the same as their need date.

Data Source: Willrett/McCormick (Manager / Source)

Accou ntability: Willrett/McCormick Adverse Trend: None L

64

~.

500-O Total Modhcation Packages Open 1

l 1

425 426 I

400 3

337

~

301 300- m ras ro7 T T$'N 270 tst w

gj 7;

9 m

251

, f f/

)

']

r y

e r

s e

f

'!?

q tQ g

200-6 k

1 t

i H

189 "8

y y

ii, Q

J p

i.

k 4

8 i.

p in p

d M

}

N 51 R

k'[lN k

Eh

[!d h

kh

?

W w

tv

v b

I I

I i

1 1

i i

i l

i I

I

'88

'89

'90 Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 OUTSTANDING MODIFICATIONS This indicator shows the total number of outstanding modifications (excludino outstand-inc modifications which are orocosed to be cancelled).

I Cateaorv Reoortina Montt1 Form FC 1133 Backlog /in Progress 16 Mod. Requests Be!ng Reviewed 14 Design Engr. Backlog /In Progress 70 Construction Backlog /in Progress 52 i

Deslan Enar. Uodate Backloc/In Proaress 20 TotaI 172 At the end of May,25 additional rnodification requests had been issued this year and 10 modification requests had been cancelled. The Nuclear T'rojects Review Committee (NPRC) had completed 95 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) had completed 65 backlog modification request reviews this year.

Data Source: Jaworski/ Turner (Manager / Source)

Scofield/Lounsbery (Manager / Source)

Accountability: Scofield/Phelps AdverseTrend: None 65

L 5

Temporary Modifications >1 cycle old (RFO required for Removal)

Q Temporary Modifications >6 months old (Rernovable on line)

--G-Fort Calhoun Goal for Temporary Modifications >1 cycle old (0) 6-5-

4-3-

2-

-. f

ffff}G 1

I

$$$$;hI:

s ss:M 0

0 0-0----

0"'

March '92 April'92 May '92 TEMPORARY MODIFICATIONS (EXCLUDING SCAFFOLDING)

This indicator provides information on the number of temporary modificailons greater than one fuel cycle ol) icquiring a refueling outage (RFO) for removal and the riumber of temporary modi'ications removable on line that are greater than six months old Also provided is the Fort Calhoun goal for temporary modifications.

There are currently no temporary modifications that are greater than one fuel cycle old requiring a refueling outage to remove. In addition, at the end of May there were 2 temporary modifications installed that were greater than six months oki that can be

- removed on-line. These were: handjack close of CCW/RW valves,in which OPS is reviewing a system engineering suggestion for closure; and potable water supply piping temporary repair, which is awaiting completion of MWOs 921203,921204, and 921205

- currently not scheduled.

At the end of May, there was a total of 21 TMs installed in the Fort Calhoun Station.- 5 of -

the 21 installed TMs require an outage for removal and 16 are removablo on line, in 1992 a total of 39 temporary modifications have been installed.

Data Source: Jaworski/ Turner (Manager /Sou ue)

Accountability: Jaworski/Gorence -

Adverse Trend: None -

SEP 62 & 71 66

-l

00-O March '92 so-O April'92 40-O May '92 30-20 20 20 20-Seyv 10-lRi':,

ggy,$

a 3

2 3

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0 i

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0 3 months 3 G months

>G months System Engineering 00-D March '92 50 -

47 O April'92 45 44 39 38 40-O May '92 w#se 33 hh!!h I

30-0 26 gg 3

M'M 20-

~~~ ' '

hhhh

'o-373 J

0 0 3 months 3-G months

>G months Design Engineering ENGINEERING ASSISTANCE REQUEST (EAR) BREAKDOWN This indicator shows a breakdown of the number of EARS assigned to Design Engineer-ing and System Engineering awaiting a technical response from engineering.

At the end of May 1992,32 EARS had beeti resolved and were going through the close-out process. There were 3 EARS awaiting a technical response from Nuclear Projects.

Total EAR breakdown is as follows:

EARS opened during the month 16 EARS closed during the month 7

Total EARS open as of the end of the month 166 Data Source: JaworskiNan Osdel(Manager / Source)

Accountability: Jaworski/Phelps Adverse Trend: None SEP 62 67

O ECNs BacMogged in DEN 350 -

O ECNs Opened During the Month Q ECNs Completed During the Month 300 -

Cycle 14 250-Refueling Outage 200 '

T f

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0 Jun91 - Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 ENGINEERING CHANGE NOTICE STATUS This indicator shows the number of Engineering Change Notices (ECNs) awaiting completion by DEN, the. number of ECNs opened during the reporting month, and the number of ECNs completed by DEN during the reporting month.

At the end of May 1992, there was a total of 167 DEN backlogged open ECNs, There weic 40 ECNs opened, and 33 ECNs completed during the month.

Although the number of open ECNs is currently high, activitias are in progress to reduce the backlog of open ECNs. It is expected that the number of open ECNs will continue to decrease.

Data Source: Phelps/Pulverenti(Manager / Source)

~ Accountability: Phelps/Jaworski Adverse Trend: None SEP 62

- -. -.=_ - - - =__

O DEN. Engineering not compi:13 O System Engineering Engineering complete, response under review Q Maintenance. MWO scheduled, but work not complete D Maintenance MWO complete, awaiting closoout C2

~

31 29 29 4

7-Y~

j 19 j'3h 'h-7 7

-{

3 1

0 1

1 3

3 0 3 months 3 6 months

> G months ECN FACILITY CHAT {QES_QEElg O DEN. Engineering not complete O sysism Engineering. Engin.oring complete, response under ieview G Maintenance. MWO scheduled, but work not complete O Maintenance. MWO complete, awaiting closeout a4 I

E 4*

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12 16 11 13 3

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> 6 months EQN SUBSTITUTE REPLACEMEfjT ITEtG_QEEN D DEN Engineering not complete O System Er.gineering. Walkdov,n or confirmation not complete 70 -

57 60-60-40-31 30-

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14 31 20 08$h[

1

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> 6 months ECN DOCUMENT CHANGES OPEN ENGINEERING CHANGE NOTICE BREAKDOWN l

This indicator shows a breakdown of the number of Engineering Change Nutices l

(ECNs) that are assigned to Design Engineering Nuclear (DEN), System Engineering, and Maintenance for the reporting month. The graphs provide data on ECN Facility Changes Open, ECN Substitute Replacement items Open, and ECN Document i.

Changes Open.

l Data Source: Phelps/Pulverenti(Manager / Source)

Accountability: Phelps/Jaworski Adverse Trend: None SEP 62-69

. -. - = - _ - - -.. ~. -..... ~....

1992 Recordable injury / Illness Frequ:ncy Rats 5-IGOODi

--M - 1991 Recordable injury / illness Frequency Rate y

4.5 -

--O - 1992 Fort Calhoun Goal (2.0) 4_

3.5 -

3-2.5 -

-C O

O O-O O

O O

2-

- 1.5 -

1-o.5 -

o Jan92 Feb Mar Apr May Jun Jul Aug

-Sep Oct Nov Dec92 RECORDABLE INJURY /lLLNESS CASES FREQUENCY RATE This indicator shows the 1992 monthly recordab!e injury / illness cases frequency rate in i

coluran form. The 1991 recordable injury / illness cases frequency rate and the Fort

.Calhoun Station 5 year average (from 1987 through 1991) recordable injury / illness cases frequency rates are also shown.

A recordable injury / illness case is reported if Nuclear Operations Division personnel are injured on the job and require corrective medical treatment beyond first aid. The record-l able cases frequency rate is computed on a year to-date basis.

The recordable injury / illness _ rate for May was reported as 2.27. There were 2 record-

'able injury / illness cases, a back injury and tendinitus of the wrist, reported during the month of May 1992. There has been a total of 6 recordable injury / illness cases in 1992.

The 1992 goal for this indicator is 2.0.

-Year Recordable Cases Year-End Rete 1989-11 2.2 L

1990.

11 2.1 1991 18 3.3 l

Data Source: Soronson/Skaggs (Manager / Source)

Accountabil!ty: Richard Adverse Trend: None.

SEP 15,25 & 26 70

l

~

G Licensee Event Reports O

Personnel Errore ".aponed in LERs Cumulative Licensee Event Rep ns K

-+- Cumulative Personnel Errors Reported in LERs N

30~

p i 3

j) 2 20-h:

14

'f-12 9

10-1

? m

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4 i

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'88

'89

'90 11 Jan92 Feb Mar Apr May Jun Jul Aug Sep Oct Nov De:92 NUMBER OF PERSONNEL ERRORS REPORTED IN LERS This indicator shows the number of Licensee Event Repons (LERs) submitted during each month of 1992, the LERs attributed to personnel errors for each month, and the cumulative totals of both. The year-end totals for the four previous years are also shown.

In May, there was a total of 5 LERs reported, none of which were attributed to personnel error.

Data Source: Short/Eid (ManagenSource)

Accountability: Patterson Adverse Trend: None SEP 15 m

O Administrative Control Problem 5-l O Licensed Operator Error

@ Other Personnel Error 4-y Maintenance Problem G Design /Constructior./ Installation / Fabrication Problem Q Equiptnent Failures 3-2-

1-i q

y i

2 1

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4 a

?

i 0-Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 LICENSEE EVENT REPORT (LER) ROOT CAUSE BREAKDOWN This indicator shows the LERs by report date broken down by Root Cause Code for each of the past twelve months from June 1,1991 through May 31,1992.

The cause codes are intended to identify possible programmatic deficiencies, in order to be consistent with industry reporting, the Root Cause Codes have been revised to reflect the NRC's sequence coding. For detailed descriptions of these codes, see the

' Performance Indicator Definitions" section of this report.

Data Source: Short/Howman (Manager / Source)

Accountability: Patterson Adverse Trend: None 72

b Actual Division StattinD 600-643 553 C Authorized Dvision Stating 00 -

200 N

200 50 51 I

I 1

0 q

Nuclear Operations Production Engineering Nuclear Services STAFFING LEVEL The authorized and actual staffing levels are shown for the three Nuclear Divisions.

Data Source: Sorenson/ Burke (Manager / Source)

Accountability: Waszak Adverse Trend: None SEP 24

-C}- Nuclear Operations Divis:an Turnover Rate

-e-Production Engheering Division Turno'.er Rate 10% -

-O-Nuclear Services Division Turnover Rate ry10 A

v v

2% - C O

O O-0-O-:-

-D-"--O 0*/.

J91 F91 M91 A91 M91 J91 J91 A91 S91 091 N91 D91 J92 F92 M92 A92 M92 PERSONNEL TURNOVER R ATE The tumover rates for the three Divisions are calculated usir.g enly resignations from OPPD.

Division Turnover Ratt NOD 2.2%

PED 3.5%

NSD 2.0%

Currently, the OPPD corporate turnover rate is being reported as approximately 2.5%.

This OPPD corporate turnover rate is based on the turnover rate over the last four years.

Data Source: Snrenson/ Burke (Manager / Source)

Accountability: Waszak Adverse Trend; None 73

60-O Total Roqualification Training Hours O Simulator Training Hours D Non Requalification Training Hours G Numberof Exam Failures 41 4o-36 36 36 3o-24 24 22 20-is e

14 14

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Z 72 0

Cycle 914 Cycle 915 Crcle 916 Cycle 917 Cycle 901 Cycle 92 2 Cycle 92 3 LICENSED OPERATOR REQUALIFICATION TRAINING This indicator provides information on the total number of hours of training given to each crew during each cycle. The Simulator training hours shown on the graph are a subset of the total training hours. Non Requalification Training' Hours are used for 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 Perf;tmance Measures (JPMs) segments of the Licensed Operator Requalification Training l

The 2 exam failures in Cycle 92 3 were during a simulator evaluation. The individuals who failed the scenario were remediated and returned to shift by the end of the requalification week.

Data Source: Gasper /Guliani (Manager / Source) l Accountability: Gasper /Guliani Adversa Trend: None SEP 68 74 1

--r m.

50-O SRO Exams Administered O SRO Exams Passed D RO Exams Administered O RO Exams Passed 30-20-r 10-b 0-Jen91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 LICENSE CANDIDATE EXAMS This indicator shows !ae number of Senior Reactor Operator (SRO) and Reactor Opera-tor (RO) quizzes and exams taken and passed each month. These internally adminis-tered quizzes and exams are used to plot the SRO and RO candidates' monthly progress.

During the month of May 1992, there were 11 internally administered SRO exams taken and 6 of these exams were passed. The 5 who failed were given remedial training and all 5 passed the exams.

Also during May, there were 15 internally administered RO exams given and 14 of these exams were passed. One individual did not pass the exam and has not yet taken the

remedial, There were no NRC administered SRO or RO exems during Cycle 92 3.

Data Source: Gasper / Herman (Manager / Source)

Accountability: Gasper /Guliani Adverse Trend: None SEP 68 75

l l

4 O Hotlinesinitiated 35 -

B HotlinesClosed 8

30-

@ Hotlines Overdue > 4 Weeks 25 -

20-Il 15 -

i

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i Jun91 Jul Aug Sep Oc4 Nov Dec Jan Feb Mar Apr May92 HOTLINE TRAINING MEMOS This indicator shows the number of Hotline Training Memos that were initiated, returned for close out, overdue less than four weeks, and overdue greater than four weeks for the reporting month.

May 1992 initiated Hotlines 10 Closed Hotlines 11 Hotlines Overdue < 4 wks.

5 Hotlines Overdue > 4 wks.

0

. Data Source: Gasper /Newhouse (Manager / Source)

Accountability: Gasper Adverse Trend: None 76

... _ _ - _ _ _ _ _ - _ _. - _ _. -. _. - - - - - - - - - -. _ _. - _ - - -. _ ~ - _. - _ -. -. _ -... _ - _ _ _ _ - - _ _ _ _ -. _.. - _ - - -. _.. -.

O Other Training (1000 Hrs.)

@ Geneial Employee Training (1000 hrs.)

O TechnicalGuppert(1000 Hrs)

O Chemistry and Radiation Protection (1000 Hrs.)

4-O Maintenance (1000 Hrs.)

@ Operations (1000 Hrs.)

r E 2-E m

E E

5 5

g 1

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=

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=

E E

Z 5

E

=

E M

i 4

I i

i 4

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May91 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr92 TOTAL INSTRUCTION HOURS This indicator displays the training instruction hours administered to the listed depart-ments for the month of December 1991.

This indicator is normally one month behind the reporting month due to the time re-quired for data collection and processing.

DEPARTMENT M ARCH '92 APRIL '92 Operations 295 613 Maintenance 43 3

CherrQtry and Radiation Protection 9

10 Technical Support 4

4 General Employee Training 168 106 Other 66 241 Total 585 977 Data Source: Gasper /Newhouse (Manager / Source)

Accountability: Gasper Adverse Trend: None 77

. -. ~.. - - - -

D Other Training (1000 Hrs.)

@ General Employec Training (1000 hrs.)

@ Technical Support (1000 Hrs.)

5 Chemistry and Radiation Protection (1000 Hrs.)

30-O Maintenance (1000 Hrs.)

25-5 Opera 11ons (1000 Hrs.)

z~ 20-

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x

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i i

i i-May91 Jun Jul' Aug Sep Oct Nov Dec Jan Feb Mar Apr92 TOTAL HOURS OF STUDENT TRAINING This indicator shows the total number of student hours for Operations, Maintenance, Chemistry and Radiation Protection, Technical Support, General Employee Training, and Other Training conducted for the Fort Calhoun Station.

This indicator is normally one month behind the reporting month due to the time needed to collect and evaluate the data.

DEP.ARTMENT MARCH 92 APRIL 'o2 Operations 2,295 4,918 Maintenance 150 200 Chemistry and Radiation Protection 7

10 Technical Support 4

32 Ger,eral Employee Training 944 439 Other 252 455-

- Total.

3,652 6,054 Data Source: Guper/Newhouse (Manager / Source)

Accountability: Gasper Adverse Trend: None.

Violations per 1,000 inspection Hours 9-

-O-Fort Calhoun Goal IGOODI b

+

.b s _

h 5s s

3.7 2.6 D-7E C

C O

O o

A_

h, -- i 0l i

'8B '89 '90 May91 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr92 VIOLATIONS PER 1,000 INSPECTION HOURS This indicator displays the number of NRC violations cited in inspection reports per 1,000 NRC inspection hours. This indicator is one month behind the reporting month due to the time involved with collecting and processing the data.

The violations per 1,000 inspection hours indicator was reported as 2.80 for the twelve months from May 1,1991 through April 30,1992. This increase, which exceeds the Fort Calhoun goal, is due to the large number of inspection hours (2,000 hours0 days 0 hours 0 weeks 0 months ) from the EDSF inspection which were removed this month in calculating the violations per 1,000 inspection hours, as well as the increase in the number of violations issued (i.e., IER 92-07 reported 6 violations and 1 additional violation was issued in IER 92-09).

The 1992 Fort Calhoun goalis 1.5 violations per 1,000 inspection hours for 1992. The goal was 1.6 violations per 1,000 inspection hours for 1991.

Data Source: Short/Eid (Manager / Source)

Accountability: Short Adverse Trend: None 79

Fort Calhoun x

fi 2.8 Cooper 0.21 River Bend 2.21 Commanche Peak 1.34 Wolf Creek 3.77 Arkansas One 1.7 South Texas 1.78 Wateriord 3.91 0

0.5 1

1.5 2

2.5 3

3.5 d

Violations per 1,000 Inspection Hours COMPARISON OF VIOLATIONS AMONG REGION IV PLANTS This indicator provides a cornparison of violations per 1,000 inspection hours among Region IV nuclear power plants. The data is compiled for a twelve month period from May 1,1991 through April 30,1992.

The Fort Calhoun goal for 1992 is 1.5 violations per 1,000 inspection hours. The goal for 1991 was 1.6 violations per 1,000 inspection hours.

Data Source: Short/Eid (Manager / Source)

Accountability: Short Adverse Trend: None 80

25-

-+-- Number of Violations During the Last 12 Months

-o--

Number of NCVs During the last 12 Months 20-15-34 13 10-8 5-4

.,2

_2

_2 2

2 0

May91 Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr92 CUMULATIVE VIOLATIONS AND NCVs (TWELVE-MONTH RUNNING TOTAL)

The Cumulative Violations and Non Cited Violations (NCVs) indicator shows the cumu-lative number of violations and the cumulative number of NCVs for the last twelve months.

This it!dicator is one month behind the reporting month due to the time involved with collecting and procassing the data for this indicator.

Data Source: Short/Eid (Manager / Source)

Accountability: Short Adverse Trend: An adversc trend is indicated based on three consecutive months of increasing values for the number of cumulative violations (twelve months running total).

81

Q TotalOutstanding CARS O Outstanding CARS > Six Months Old

@ Outstanding CARS That Are Modification Related 150 -

7 100-U t

7 s

9 n

7 1

t

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50-

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1 g

4

)

O h

f,A b

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+

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 OUTSTANDING CORRECTIVE ACflON REPORTS This indicator shows the total number of outstanding Corrective Action Reports (CARS),

the number of oatstanding CARS that are greater than six months old, and the number of outstanding CARS that are modification related.

At the end of May 1992, there were 83 outstanding CARS,35 CARS that were greater than six months old, and 2 CARS that were modification related.

Data Source: Orr/Gurtis (Manager / Source)

Accountability: Andrews/Gambhir/ Gates Adverse Trend: None 82 l

l 0-

-O-NOD Overdue CARS

~ -

NOD CARS Wah Extensions Granted 10-h 0

O m

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92

~

-O-PED Overdue CARS

--6--

PED CARS With Extensions Granted 10 --

j

WAc, 5

}

O m

n m

m m

m Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 20 -

-O-Other Overdue CARS 15-Other CARS With Extensions Granted 5-O, O

7--G-T--C 5~

i i

Jun91 Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May92 OVERDUE AND EXTENDED CORRECTIVE ACTION REPORTS o.f.

This indicator shows the number of overdue CARS and the number of CARS which received extensions broken down by organization.

Overdue CARS Overdue CARS March '92 Apnl'92 May 92 NOD 0

0 0

PED 0

0 2

Others 0

0 1

Total 0

0 3

Extended CA~

Extended CARS March '92 April '92 May 92

~

NOD 3

1 1

PED 0

3 5

Others 0

0 1

Total 3

4 7

Data Source: Orr/Gurtis (Manager / Source)

Accountability: Andrews/Gambhir/ Gates Adverse Trend: None 83

1991 SALP Funct.

Area CARS Signif. C ARs NRC Viola.

LERs A) Plant Operations 30 1

1 6

B) Radiolog. Controls 12 0

3 0

C) Maint/Survell.

66 0

2 9

D) Emergency 16 0

0 0

Preparedness E) Security 5

0 1

3 F) Engr / Tech Suppon 93 3

1 12 G) Safety Assess' 27 1

1 2

Oual. Verit, H) Other 0

0 0

0 Total 249 5

9 32 1992 SALP Funct.

Area CARS Signif. CARS NRC Viola.

LER$

A) Plant Operations 9

0 0

4 B) Radiolog. Controls 7 (1) 0 6

0 C) Maint/ Surveil.

82(8) 1 2 (1) 5 (2)

D) Emergency 4

1 1

0 Preparedness E) Security 1

0 0

0 F) Engerrech Suppon 13 0

0 10(3)

G) Safety Assess; 15(2) 0 0

0 Qual. Verit.

H) Other 0

0 0

0 Total 131 (11) 2 9 (1) 19 (5)

Note:() Indicate values for the reporting month.

CARS ISSUED vs. SIGNIFICANT CARS vs NRC VIOLATIONS ISSUED vs. LERs REPORTED The above matrix shows the number of Corrective Action Reports (CARS) issued by the Nuclear Services Division (NSD) vs. the number of Significant CARS issued by NSD vs.

the number of violations issued by the NRC for the Fort Calhoun Station in 1991 and 1992, included in this table is the number of Licensee Event Reports (LERs) identified by the Station each year. The number of NRC violations reported is one month behind the reporting month due to the time involved in collecting and processing the violations.

Data Source: Orr/Gurtis (Manager / Source)

Short/Eid (Manager / Source)

Accountability: Andrews/Gambhir/Gutes Adverse Trend: None SEP 15,20,21 84 1

ERFORMAIJCE ltJDICATOR DEFl!41TIOt4S AGE OF OUTSTANDING MAINTENANCE WORK OR.

COMPONENT FAILURE ANALYSIS REPORT (CFAR)

DERS

SUMMARY

The number of tems for Fort Calhoun Station with higher This indicator tracks the total number of outstanding cor-i rectrve non-outage Maintenance Work Orders at the Fort f ailure rates than the rest of the industry for an eighteen Calhoun Staton versus their age in months.

montn time perod. Failures are repo"ed as component (Lo. rectprocating pumps, motor operated vanes, etc.)

AMOUNT OF WORK ON HOLD AWAITING PARTS and appleat on (i e. charging pumps, feedwater pump,,

This indcator is dehnod as the percentage of open, non-discharge pumps, etc.) categories, outage, maintenance work orders that are on hold awart-Failure Cause Categones are:

ing parts, to the total number of open, non outage, main-Wear Out/ Aging a failure thought to be the conse-tenance work orders.

quence of expeded wear or aging.

Manuf actunng Def ect a f ailure attrit stable to inad-AUXlLIARY FEEDWATER SYSTEM SAFETY SYSTEM equate assembly or inttial quaMy of the responsible com.

PERFORMANCE ponent or system.

The sum of the known (planned and unplanned) unavail-Engineering' Design a f ailure attributable to the inad-able hours and the estimated unavailable hours for the ecuate design of the responsible component or system.

aunihary feedwater system for the reporting period di.

Other Devees. a f ailure atthbutable to a failure or vided by the critcal hours for the reporting pered multi-misoperaton of arcther component or system, including plied by the number of trams in the auxihary feedwater associated devces, system.

Maintenance / Testing a f ailure that is a result of im-proper maintenance or terting, lack of maintenance, or AUXIUARY SYSTEMS CHEMISTRY PERCENT OF personnel errors that occur during maintenance or test.

HOURS OUTSIDE STATION LIMITS ing activities periormed on the responsible component or The cumulative hours that the Ccmponent Cooling Water system, including f ailure to f ollow procedures.

system is outside the station chemistry limit. The hours Errors failures attributable to incorrect procedures that are accumulated from the first sample exceeding the limit were followed as written, improper installation of equip-until additional sampling shows the parameter to be back ment, and personnel errors (including f ailure to follow within limits.

procedures property). Also included in this category are failures for which the cause is unknown or cannot be as-C ARs ISSUED vs. SIGNIFICANT CARS vs. NRC VIO-signed to any of the preceding categories.

LATIONS vs. Lens REPORTED Provides a comparison of CARS issued, NRC violat ons, CORRECTIVE MAINTENANCE D ACKLOG GREATER and LERs reported. This indcator tracks periormance for TdAN 3 MONTHS OLD SEP #15,20, & 21.

The percentage of totaloutstanding corrective mainte-nance items, not requiring an outage, that are greater CHECK VALVE FAILURE RATE than three months old at the end of the period reported.

Compares the Fort Calhoun check valve f ailure rate to the industry check valve f ailure rate (failures pe,1 milton CUMULATIVE VIOLATIONS & NON CITED VIOLA.

component hours). The data for the industry f ailure rate T10NS (12 MONTH RUNNING TOTAL) is three months behind the Pl Report reporting month.

The cumulative number of volatons and Non-Cited Vo-This indicator tracks performance for SEP #43.

latons for the last 12 months.

COLLECTIVE RADI ATION EXPOSURE DAILY THERMAL OUTPUT Collective radiation exposure is the total external whole-This indicator shows the daily core thermal output as body dose received by all on site personnel (including measured from computer point XC105 jn 'hermal mega-contractors and visitors) during a time period, as mea-watts). The 1500 MW Tech Spec limit, c,d the unmet sured by the thermoluminescent dosimeter (TLD). Col-portion of the 1495 MW FCS daily goal for the reporting lective radiation exposure is reported in units of man-month are also shown, rem. This indicator tracks radiological work perf ormance for SEP #54, DIESEL GENERATOR RELIABILITY (25 DEMANDS)

This indicator shows the number of f ailures occurring for COMPARISON OF VIOLATIONS AMONG REGION IV each emergency diesel generator during the last 25 start PLANTS demands and the last 25 load run demands.

Provides data on violations per 1,000 inspection hours for Region IV nuclear power plants.

DIESEL CENERATOR UNAVAILABILITY This iWatcr provides monthly data on the number of hour + c),iesel generator ptanned and unplanned un-availability. The Fort Calhoun goalfor the second half of 1991 for the number of unavailable hours per dieselgen-erator has been established based upon the 1990 indus-try median value provided by INPO.

85 I

l

PERFORMANCE INDICATOR DEFINITIONS (Cont'd)

DECONTAMINATED RADIATION CONTROLLED GEA A) A load run of hay duration that results from a real au-ihe percentage of the Radiation Controlled Area, which tomatic or manualinitiction.

includes the auxihary building, the radwaste building, and B) A load run test to satisfy the plant's load and duration areas of the C/RP building, that is decontaminated based as stated in Sach test's specifcations, on the total square footagc. This indicator tracks perfor-C) Other special tests in which the emergency generator mance for SEP # 54.

is expected to be operated for at least one hour while loaded with at least 50% A ps design load.

)

DISABLING INJUr1Y FREOUENCY RATE (LOST TIME

4) Number of Load-Run Failures: A load run f allure ACCIDENT RATE) should be counted for any reason ir. which the emer-This indicator,is defined as the number of acx:idents for gency generator 'oes not pick uoluo and run as pro-all utiltty personnel permanently assigned to th: s'ation, dicted. Failures s counted during any valid load run (ing days away from work per 200 000 man-hours demands.

ed (100 mar, years). This does no; include contrac-

5) Exceptions 'Jnsuccessful ahompts to start or load run w rsonnel. This indicator tracks personnel perfor-should not be counted as va!id demands or fJlures when l

1 see for SEP #2S & 26 they can be attributed tu any of the follow:ng:

A) Spurious trips that wn. J Ne hypassed in the event of DOCUMENTREVIEW(Bl NNIAl.)

an emergency.

'ha Document Review Indcator shows the numbar of B) Malfunction of equipment thet is not required during

, xrnents reviewed, the number of documents sched-an emergency.

..wd fc: review, and the numoer of Acument reviews C)Intantionaltermination of a test because of sbnormal i

s,st are overdue for the reporting month. A document conditions that would not have resulted in major diesel l

review is considored overdue if the review is not com-generator damage or repair.

plete within 6 months of the assigned due date. This indi-D) Ma!!unctionr, or operating errors which woub have not cator tracks performance for SEP #46.

prevented the emergency generator from being resterted and brought to load within a f ew rrf.nutes.

EMERGENCY AC POWER SYSTEM SAFETY SYSTEM E) A f ailure to start because a portion of the starting sys-PERFORMANCE tem was disabled for test purpose, if followed by a suc-The sum of tne known (planned and unplanned) unmil-cessful start with the starting system in its normal align-abb and the estimated unavailable hours for the emer-ment.

gen, y AC power system for the reporting period divided Each emergency generator 'ailure that results in the gen-by the numk of hours in the reporting period multiplied orator being declared inoperable should oe counted as by the nu' 4.

tr' m in the emergency AC po'ver sys-one demand and one fai!ure. Exploratory tests during um.

corrective maintenance und the successf ul test that fol-lows repair to verify operabihty should not be countcd as EMERGENCY DIESEL GENER ATOR UNIT RELIABIL-demands or failures when the EDG ha not been de-IT" clared operable again.

This indicator shows the ruinber of failures that were reported during the last 20,50, and 100 emergency die-ENGINEERING ASSISTiNCE REC"3ST(EAR) sel generator demands at the Fort Calhoun Station. Also BEAKDOWN shown are trigger values which correlate to a high level This indicator shows a breakdown, by age of the EAR, of of confidence that a unit's diesel generators have ob-the number of EARS assigned to Design Engineering tained a reliability of greater than or equal to 95% when Nue'sar and System Engineering. This indicator tracks the demand f ailures sre kss than the trigger values performance for SEP #62.

1) Number of Start Demands: All vand and inadvertent start demands. including all start.only demands and all.

ENGINEERING CHANGE NOTICE (ECN) BREILK-start demands 1%t are followed by icad run domands, DOWN whether by automatic or manualinitiation. A start-only This indicator break; down the nurnber of Engineering demand is a demand in wh ch the emergency generator Change Notices (ECNs) that are atsignM to Design is started, but no attempt imade to load tha generator.

Engineering Nuclest (DEN), System E.gineering, and

2) Number of Start Falures. Any feb within the emer-Maintenance. The graphs provide data on ECN Facility gency generator system that preveats the generator from Changes open, EON Substitute Replacement Parts achieving specified f requency and voltage is classified as open, and ECN Document Changes open. This indicator a valid start f ailure. This includes any condition identified tracks performance for SEP #62.

in the course of maintenance inspections (with the emer-gency generator in standby mode) that defirJtely would ENGINEERING CHANGE NOTICE (ECN) STATUS have resulted in a start fr ure if a demand had occurred.

The number of ECNs that were opened, ECNs that were u

3) Number of Load-Run Demands: For a valid load run completed, and open backlog ECNs awaiting completion demand to be counted the load run attempt must meet by DEN for the reporting rr.onth. This indicator tracks per-one or more of the following enteria:

formance for SEP #6'L 86

PERFORMANCE INDICATOR DEFINITIONS (Cont'd)

(

EQUIPMENT FORCED OUTAGES PER 1,000 CRITI-GROSS HEAT RATE CAL HOURS Gross heat rate is defined as the ratio of total thermal Equipment forced outages per 1000 entir at hours is the energy in Bntish Therma! Units (BTU) produced by the inverse of the mean time between forced outages reactor to the total gross electrical energy produced by caused by equipment f ailures. The mean time is equal to the generator in kilowatt hours (KWH).

the number of hours the reactor is critical in a period (1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months ) divided by the number of forced outages HN'.AHDOUS WASTE PRODUCED caused by equipment f ailures in that penod.

The N amount (in Kilograms) of non halogenated ha2-ardou' ste, halogenated hazardous waste, and other EQUIVALENT AVAILABILITY FACTOR hazardous waste proheed by FCS each month.

This indicator is det ned as the ratio or gross available generaton to gross maximum generaton, expressed as HIGH PRESSURE SAFETY INJECTION SYSTEM a percentage. Available generaton is the energy that can SAFETY SYSTEM PERFORMANCE be produced il the un;t is operated at the maximum The aum of the known (planned and unplanned) unavail-power level permitted by equpment and regulatory limi-able hours and the estimated unavailable hours for the tatons. Maximum generaton is the energy that can be high pressure safety injection system for the reporting produced by a ur.it in a given perod if operated continu-period divided by the crnical hours for the reporting pe-cus'y at maximum capacity.

nod multiplied by the number of 1.ains in the high pre e sure safety injection system.

EXPdr'ITED PURCHASES The percentagc of expedded purchases occurnng during HOTUNE TRAIN!NG MEMOS the reporting mordh compared tee total number of pur-The number of Hotline Training Memos (HTM) that are chaSt orders generated, initiated, closed, r.,nd overdue less or greater than 4 weeks for the indicated month. A HTM is a training docu-FORCED OUTAGE RATE ment sent out for immediate res v. The HTM should be This indicator la defined as the percentage of time that reviewed t.nd signed within 5 days of receipt of the HTM.

the unit was unavailable due to forced events compared to the time planned for electrical generation. r creed IN UNE CHEMISTRY INSTRUMENTS OUT OF SER-events are f ailures or other unplanned conditions that VZE require removing the unit from service before the end of Total number of in-line chemistry instruments that are the next wenkend. Forced events include start up fail-out-of service in the Secondary System and the Post ures and events initiated while the unit is in reserve shut.

Accident Sampling Systsm FA?.S?

down (i.e., the unit is available but not in service).

LNVENTORY ACCURACY FUEL REUABluTY INDICATOR The percentage of line items that are counted each Thit indicator is defined as the steady state primary cool-month by the warehouse which need count adjustments.

ant 1131 activity, corrected for the tramp uranium contri.

buton and normalized to a common purification rate.

INVOICE BREAKDOWN Tramp uranium is fuel which has been depositsd on re-The number of invoices that are on hold due to shelf life, actor core internals f rom previous defective f uel or is COE, and miscellaneous reasons, present on the surf ace of fuel elements from the manu-f acturing process. Steady state is defined as continuous UCENSE CANDIDATE EXAMS operation for at least three days at a power level that This ir,dicator ghows the number of SRO and/or RO quiz-does not vary more than + or - 5%. Plants should collect zes and exams that are administered and passed each data for this indicator at a power level above 85%, when month. This indicator tracks training performance for possible. Plants that did not operate at steady state SEP #68.

3 power above 85% stauld collect data for this indicator at the highest steady state power level attained during the UCENSED OPERATOR REQUAUFICATION TP.AIN-month.

ING The density correction f actor is the ratio of tho specific The total numb 6 af hours of training given to each crew volume of coolant at the RCS operating temperature during each cycle. Also provided are the simulator train-

- (540 degrees F, Vf = 0.02146) divided by the specific ing hours (which are a subset of the total training hours),

volume of coolant at ermalletdown temperature (120 the number of non requalification training hours and the degrees F at outlet of..ie letdown cooling heat ex-number of exam f ailures. This indicator tracks training changer, Vf = 0.016204), which results in a density cor-performance for SEP #68.

rection f actor for FCS equal to 1.32.

GASEOUS RADIOACTIVE WASTE BEING 3 CHARGED TO THE ENVIRONMENT This indicator displays the total numbet of Curies of all gaseous radioactive nuclides released from FCS.

87 I

I

_m.w_ _ _ - _ _ _ _ - - - - _ _ _ - _ _ - - - - - _ - - - _ _ - _ _ - - - - - - - _ _ - - _ _ _ _ - _. - _ - - _ _ _ - _ _ _ _ - - - - _ _ _ _ _ _ - - _ - _ _ _ _ _ _ _ _ _ - - _. - _ _ _ _ _ _ _

_ _ _ _, - _ - ~ _ _ _

PERFORMANCE INDICATOR DEFINITIONS (cont'd)

LICENSEE EVENT REPCRT (LER) ROOT CAUSE MAINTENANCE WORK ORDER FFEAKDOWN BREAKDOWN This indicator is a breakdown of corretive non outage This indicator shows the number and root cause code for maintenance work o ders by several categories that re.

Licensee Event Reports. The root cause codes are as main open at the end of the reporting month. This indica-follows:

tor tracks maintenance performance for SEP #36.

1) Administrative Control Problem Management and supervisory deficienchs that affect p! ant programs or MAINTENANCE OVERTlME activities (i.e., poor planning, breakdown or tack of ad.

The % of overtime hours compared to normal hours for equate management or supervisory control, incorrect maintenance. This includes OPPD personnel as well as procedures, etc.)

contract personnel.

2) Licensed Operator Error This cause code captures errors of omission / commission by licensed reactor opera-MATERIAL REOUEST PLANN!WG tors curing plant activities.

The percent of ma:er:al requests (MRs) for issues with

3) Other Forsonnel Error Errors of omiss sn/commis-their tw wt date the same as their need date compared sion committed by non-licensed personnelinvoiN,4 to the L wmber of MRs.

plant activities.

4) Maintenance Problem The intent of this cause MAXIMUM INDIVIDUAL RADIATION EXPOSURE code is to capture the ful! range of problems which can The total maximum amount of radiation received by an be attributed in any way to programmatic defciencies in individual person working at FCS on a monthly, quartarly, the maintenance functional organization. Activities in-and annual basis.

cluded in this category are maintenance, testing, surveil-lance, calibration and radiatiori phon.

NUMBER OF HOT SPOTS

5) Design / Construction / installation / Fabrication Problem The number of radiological hot spots which have been This cause code covers a full range of programmatic identified and documented to exist at FCS at the end of deficiencies in the areas of design, construction, installa-the reporting month. A hot spot is a small localized tion, anc f abrication (i.e., loss of control power due to source of radiation. A het spot occurs when the contact underrated fuse, squipment not quaYied for the environ-dose rate of an item is at least 5 times the Ger eral Area ment, etc.).

dose rate and the item's dose rate is equal to or greater

6) Equipment Failures (Electronic Piece Parts or Envi-than 100 mrem / hour.

ronmental-Related Failures) This code is used for spuri-ous failures of electronic pieco-parts and f ailures due to NUMBER OF NPROS MULTIPLE FAILURES meteorologkal conditions such es lightning, ice, high Ti e number of NPRDS reportable f ailures over the pre-winds, etc. Genorally, it includes spurious or one me coding eighteen months sorted by component manufac-1ailures. Electric components included in this category turer as model riumber, are circuit cards, rectifiers, bistables, fuses, capacitors,

- diodes, resistors, etc.

NUMBER OF OUT OF SERVICE CONTROL ROOM INSTRUMENTS LlOUID RADIOACTIVE WASTE BEING DISCHARGED A control room instrument that cannot perform its dasign TO THE FNVIRON1.ENT function is considered as out of service. A contro: room This indicator dispy 9 the total number of curies from all instrument which has had a Maintenance Work Order liquid releases from FCS toihe Missouri River.

(MWO) wrrtten for it and has not been repaired by the 9nd of the reporting period is considered out of-service LOGG ABLE/ REPORTABLE INCIDENTS (SECURITY) and will be counted. The duration of the out-of-service The total number of security incidents for the reporting condition is not considered. Computer CRTs are not con-month depictef in two graphs. This indicator tracks secu. sidered as contrei room instruments.

rity performance for SEP #58.

NUMBER OF PERSONNEL ERRCRS REPORTED IN MAINTENANCE EFFECTIVENESS LERS The number of Nuclear Plant Reliability Data System The number of Licensee Event Repoas (LERs) attributed (NPRDS; components with more than 1 tailure and the to personnel error on the original LER submittal, This number of NPRDS components with more than 2 failures indicator trends personnel periormance for SEP #15.

for the last eighteen months.

NUMBER OF MISSED SURVEILLANCE TESTS RE-MAINTENANCE WORK ORDER B ACKLOG SULTING IN LICENSEE EVENT REPORTS Tho number of corrective non-outage maintenance work The number of Surveillance Tests (STs) that result in o.ders that remain open at the end of the reporting Licensee Event Reports (LERs) during the reporting month. This indicator was added to the Pl Report to month. This indicator tracks missed STs for SEP #60 &

trend cpen corrective non-outage maintenan% wLrk or-61.

dets as stated in SEP #36.

88

PERFORMANCE INDICATOR DEFINITIONS (cont'd)

OPERATIONS AND MAINTENANCE BUDGET PERCENT OF COMPLETED SCHEDULED MAINTE-The year to date budget compared to the actual wpen-NANCE ACTIVITIES ditures for Operations and Maintenance departmon:s.

The % of the number of completed maintenance activi-ties as compared to the number of scheduled mainte-OUTSTANDING CORRECTIVE ACTION REPORTS nance activities each week. This % is shown for each This indicator displays the total number of outstinding maintenance craft. Maintenance activities include MWRs, Corrective Action Reports (CARS), the number of CARS MWOs, STs, PMOS, cahbrations, and other miscella-that are older than six months and the number of moddi-neous activit;es. These indicators track Maintenance per-cation related CARS.

formance for SEP #33.

OUTSTANDING MODIFICATIONS PERSONNEL TURNOVER RATE The number of Modi! cation Requests (MRs)in any state The rato of the number of tLrnovers to average employ-between the issuance c! a Modifcation Number and the ment. A tumover is a vacancy created by voluntary resig-completion of the drasing update, naton from the company. Retirement, death, termination,

1) Form FC-1133 Backlog /In Progress. This number rep-transfers within the company, and part time employees resents modifcation requests that have not been plant are not considered in tumover.

approved during the reporting month, r

2) Modtfcation Requests Being Reviewed. This category PLANNED CAPABILITY LOSS FACTOR includes:

The ratio of the planned energy losses during a given A.) Modification Requests that are not yet reviewed.

pew.,J of time, to the reference energy goneration (the B.) Modification Requests being reviewed by the Nuclear energy that could be produced if the unit were operated Projects Review Committee (NPRC).

continuously at full power under reference ambient con-C.) Modifcation Requests being reviewed by the Nuclear ditions), expressed as a percentage.

Projects Committee (NPC)

These Modification Requests may be reviewed several PREVENTIVE MAINTENANCE ITEMS OVERDUE times before they are approved for accomplishment or This indicator is defined as the % of preventive mainte-cancelled. Some of these Modification Requests are re-nance items in the month that were not comploted by the tumed to Engineering for more information, some ap-scheduled date plus a grace period equal to 25 % of the proved for evaluation, some approved for study, and scheduled interval. This indcator tracks preventive main-some approved for planning. Once planning is completed tenance actreities for SEP #41, and the scope cf the work is clearly defined, these Modi-fication Roquests may be approved for ao:omplishment PRIMARY SYSTEM CHEMISTRY % OF HOURS OUT with a year assigned for construction or they may be can-OF U MIT celled. Alloi these different phases require review.

The % of hours out of limd are for six primary chemistry

3) Design Engineering Backlog /in Progress. Nuclear parameters divided by the total number of hours possible Planning has assigned a year in which construction will for the month. The key parameters used are: Lithium, be comphad arvi design work may be in progre,.s.

Chloride, Hydrogen, Dissolved Oxygen, Fluonde, and

4) Construction Backlogrin Progress. The Construction Suspended Solids. EPRIlimits are used.

r Package has been issued or construction has begun but the me.dification has not been accepted by the System PROCEDURAL NONCOMPLIANCE INCIDENTS Acceptance Committee (SAC).

(MAINTENANCE)

5) Design Engineenng Update Backlog /In Progress. PED The number of identified incidents concerning mainte-has recerved the Modificaton Completion Report but the nance procedural problems, the number of closed irs drawings have not been updated.

related to the use of procedures (includes the number of The above mentioned outstanding modificatiors do not closed irs caused by procedural noncompliance), and include modifications which are proposed for cancella-ths number of closed procedural noncompliance irs.

tion.

This indicator trends personnel performance for SEP

15,41 & 44.

OVERDUE AND EXTENDED CORRECTIVE ACTION REPORTS RADIOLOGICAL WORK PRACTICES PROGRAM The number of overdue Corrective Action Reports The nunibor of identified poor radiological work practices (CARS) and the number of CARS which received erten-(PRWP) for the reporting month. This indicator tracks sions broken down by organization for the last 6 months.

radiological work performance for SEP #52.

89

~

PERFORMANCE INDICATOR DEFINITIONS (Cont'd)

RATIO OF PREVENTIVE TO TOTAL MAINTENANCE SECURITY SYSTEM FAILURES The ratio of preventive maintenance (including surveil-The following components are the types of loggable/re-lance testing and caabration procedures) to the sum of portable SECURITY SYSTEM FAILURES represented in noneutage corrective maintenance and preventive main-this indicator, incidents in this category include alarm tenance completed over the reperting period. The ratio, system f ailures, CCTV f ailures, security computer f aih expressed as a percentage, is calculated based on man-ures, search equipment f ailures, and door hardware f aib hours. THs indicator tracks preventive maintenance ac-ures. These system failures are further categonzed as l

livities for SEP #41.

follows:

1) Alarm System Fa'ure Detection system events in-RECORDABLE INJURY /lLLNESS CASES FRE-volving f alse/ nuisance alarmx and mechanical f ailures.

QUENOY RATE

2) Alarm System Environs Degradations to detecten The number of injuries requiring more than normal first system performance as a result of environmental conde aid per 200,000 man-hours worked. This ind cator trends tions (i.e., rain, snow, liost).

personnel performance for SEP #15,25 & 26.

3) CCTV Failures - Mechanical failures to all CCTV hard-ware components.

SECONDARY SYSTEM CHEMISTRY PERFORMANCE

4) CCTV Environs Degradations to CCTV performance INDEX as a result of environmental conditions (i.e., rain, snow, The Chemistry Performance index (CPI) is a calculation frost, fog, sunsputs, shade).

based on the mncentration of key impurities in the sec-

5) Security Computer Failures Failure of the multi-ondary side of the plant. These key impursties are the plexer, central processing unit, and other computer hard-most likely cause of deterioration of the steam genera-wrar and software. This category does not include soft-tors. The chemistry par. meters are reported only for the ware problems caused by operator error in using the period of time greater than 30 percent power, softw.ve.

The CPlis calculated using the following equation: CPI-

6) Sea'ch Equipment Failures Failures of x ray, metal, (KWO.8) + (Na/20) + (0,/10)) / 3 where the following are or explosive detectors and other equipment used to monthly averages of: Ka - average blowdown cation search tor contraband. This also includes incidents mnductivity, Na - average blowdown sodium concen-where the search equipment is found to be defective or tration O, - ave age condensate pump discharge dis-did not function properly during testing.

solved oxygen concentration.

7) Door Hardware Failures Failure of the door alarm and other door hardware such as latches, electric strikes, SECURITY NON-SYSTEM FAILURES doorknoes, locks, etc.

The following components are the types of loggable/re-

8) 1991 versus 1992 System Failures Statistics from portable non-system f ailures represented in this indica-19g will be compared on a monthly basis with 1992 l

tor, incidents in this cr28 gory include security badges, loggable/ reportable system f ailures.

l access control and authorization, security force error, This indicator tracks secunty performance for SEP #58.

and unsecured doors.

1) Security Badges - Incidents associated with improper SPARE PARTS INVENTORY VALUE uss and handling of security badges, incidents include The collar value of the spare parts inventory for FCS dur-security badges that are lost, taken out of the prctected ing the reporting period, area, out of control on site, or inadvertently destroyed or broken.

SPARE PARTS ISSUED

2) Access Contr and Authorizaticn Administrative and The dollar value of the spare parts issued for FCS during pecedural errorc associated with the use of the card-the reporting period.

access systern such as tailgating, incorrect security badge issued, and improper escort procedures. This also STAFFING LEVEL includes incidents that were caused by incorrect access The actual staffing level and the authorized staffing level authorization information entered into the security sys-for the Nuclear Operations Division, the Production Engi-tem computer.

neenng Division, and the Nuclear Services Division, This

3) Security Force Error Events caused by members of indicater tracks performance for SEP #24.

the secunty force that a'e founo to be inattentive to their duties or who neglected to properly perform assigned S1 ATION NET GENERATION functions (e.g., required search procedure or patrol).

The not generation (sum) produced by the FCS during

4) Unsecured Doors - Doors which are found to be unse-the reporting month.

cured with no compensatory of'icer posted or where tne individual causing the alarm did not remain at the STOCKOLT" AATE alarmed door until a security officer resoondad. Events The total number of Pck Tickets that were generated where an unsecured door is caused by air crossure are during the reporting month and the total number of Pick included in this category unless there is an indicatior. that Tickets that were generated during the reporting month an adjustment was made to the door.

when the amount of parts requested is equalto or less This indicator trarfs security periormance for SEP #58.

than the minimum stocking level and parts are not avail-able.

90

PERFORMANCE INDICATOR DEFINITIONS (Cont'd)

TEMPORARY MODIFICATIONS UNPLANNED AUTOMATIC REACTOR SCRAMS The number of ter orary mechanical and electr' cal con-WHILE CRITICAL figurations to the plant's systems.

This indicator is defined as the number of unplanned av.

1) Temporary configurations are defined as electrical tomate scrams (reactor protection system logic actua-jumpers, elect k.al blocks, mechanical jumpers, or me" tions) that occur while the reactor is critical. The inocator che 91 blocks whch are installed in the plant opvatin9 is further defined as follows:

sy'.t 'ns and are not shown on the latest revision of the

1) Unplanned means that the scram was not part of e P&id, schemate, connecton, w ring, or flow diagrams.

planned test or evolution.

2) Jumpers and blocks whch are installed for Surveil-

2) Scram means the automatic shutdown of the reactor lance Tests, Maintenance Procedures, Calibration Pro-by a rapid insertion of all control rods that is caused by cedures, Special Proceduret, or Operating Procedures actuaton cf the reactor protection system. The scram are not considered as temporary modifcations unless the signal may have resulted from exceediry a utpoint or jumper or block remains in place after the test or proce-may have been sputous, dure is complete. Jumpers and blocks installed in test or

3) Automatic means that the initial signal that caused lab instruments are not considered as temporary modifi-actuaton of the reactor protecton system logic was p o-cations.

vided from one of the sensors monitoring plant param-

3) Scaffolding is not considered a tempc.ary mod.fca-eters and condttions, rather than the manual scram tion. Jumpers and blocks which are insta!Ied and for switches (or push buttons)in the main control room.

wnich MRs have been submitted will be considered as

4) Critcal rneans that during the steady-state concttion of temporary modifcations until final resolution of the MR the reactor pror to the scram, the effective mutplication and the jumper or block is removed or 11 permanently f actor (k,) was equal to one.

recorded on the drawings. This indicator tracks tempo-tary modifications for SEP #62 & 71.

UNPLANNED CAPABluTY LOSS FACTOR The ratio of the unplanned energy losses during a given THERMAL PERFORMANCE period of time, to the reference energy generaton (the The rato of me design gross heat rate (corrected) to the ensrgy tnat could be produced if the unit were operated aojusted actual gross heat rate, expressed as a percent-continuously at full power under reference ambient con-age.

ditons) over the same time perod, expressed as a per-TOTAL HOURS OF STUDENT TRAINING The total number of studant hours of training for Opera-UNPLANNED SAFETY SYSTEM ACTUATIONS-tions, Maintenance, Chemistry / Radiation Protection-(INPO DEFINITION)

Technical Support, General Employee Training, and This indicator is defined as the sum of the fo!!owing Other Training conducted for FCS.

safety system actuations:

11 The number of unplanned Emergency Core Cooling TOTAllNSTRUCTION ilOURS System (ECCS) actuations that result frem reaching an The total number and department breakdown of training ECCS actuaton setpoint or f rom a spurous4nadvertent instruction hours administered by the Training Center.

ECCS signal.

2) The number of unplanned emergency AC power sys-TOTAL FKIN AND CLOTHING COffTAMINAT10NS tem actuations that result from a loss of power to a safe-Reportable skin and clothing contaminations above guards bus. An unplanned safety system actuation oc-background levels greater than 5000 dpm/100 cm cuts when an actuaton setpoint for a safety systera is squared. This indicator trends personnel perf ormance fu' reached or when a spurious er inadvenent signal is gen.

SEP #15 & 54.

erated (ECCS only), and major equipment in the system is actuated. Unplanned means that the system actuation UNIT CAFADILITY FACTOR was not part of a planned test or evolution. The ECCS The rato of the available energy generation over a given actua*cns to be counted are actuations of the high pres-time pericd to the reference energy generation (the en-sure injecten system, the low pressure injection system, ergy that could be produced if the unit were or>erated or the safety injecton tanks.

continuously at full power under reference ambient con.

drtions) over the same time period, expressed as a per-UNPLANNED SAFETY SYSTEM ACTUATiONS(NRC centage.

DEFINITION)

The number of safety system actuations which include (2&) the High Pressure Saf ety injection System, the Low Pressure Safety injec' ion System, the Safety injec-tion Tanks. and the Emergency Diesel Generators. The NRC classifcaton of saiety system actuatons includes actuations when major equipment is operated gg when the logc systems for the above safety systems are chal-lenged.

91 l

PERFORMANCE INDICATOR DEFINITIONS (cont'd)

' VIOLATIONS PER 1,000 INSPECTION HOURS This indicator is defined as the number of violations sited i

in NRC inspection reports for FCS per 1,000 NRC in.

spection hours. The violations are reported in the year j

that the inspection was actual!y performed and not based on when the inspection report is received. The hours re-4 ported for each inspection report are used as the inspec-tion hours.

VOLUME OF LOW LEVEL SOLID RADIOACTIVE WAS1F.

This indicator is defined as the volume of low-level sohd radioactive waste actually shipoed for burial. This indica-2 tor also shows the volume of low-level radioactive waste I

which is in temporary storage, the amount of radioactive oil tnat has been shipped off site for processing, and the volume of solid dry radbactive waste which has been shipped off site for processing. Low-level solid radioac-tive waste consists of dry active waste, sludges, resins, and evaporator bottoms generated as a result of nuclear power plant operation and maintenance. Dry radioactive waste includes contaminatod rags, cleaning materials, disposable protective clothing, plastic containers, and any rthat material to be disposed of at a low level radio-l active va.w disposal site, except resin, sludge, or wcporator bottoms. Low-level refers to all radioactive waste that is not spent fuel or a byproduct of spent fuel processing. This indicator tracks radiological work perfor-mance for SEP #54, l

l l

I 92

..~... - - -

_--....... ~

1 SAFETY ENHANCEMENT PROGRAM INDEX The purpose of the Safety Enhancement Prog.am (SEP) Performance Indicators Index is to list perfor.

mance indicators related to SEP ltems with parameters that can be trended, SEP Reference Number if Eglg

' increase HPES and IR Accountability Through Use of Performance Indicators Procedural Noncompliance incidents (Maintenance)................................................... 33

, Total Skin and Clothing Contaminatlens........................................................... 51 Recordable injury /lliness Cases Frequency Rate............-..................

. 70 Num!er of Personnel Errors Reported in LERs.........

.... 71 CARS issued vs Significant CARS issued vs NRC Violations issued vs LERs Reported.......... 84 SEP Reference Number 20 Ouality Audits and Surveillance Programs are Evaluated, improved in Depth are "trengthened CARS issued vs Significant CARS issued vs NRC Violations issued vs Leas Reported....

... 84 SEP Reference Number 21 Develop and Conduct Safety System Functional inspections

- CARS issued vs Significant CARS issued vs NRC Violations issued vs LERs Reported........ 84

$EP Reference Number 24 Complete Staff Studies -

Staffing Level-73 SEP Reference Number 2[

- Training Program 1or Managers and Supervisors implemented Disabling injury / Illness Frequency Rate............................................

18 Recordable in;ury/lliness Cases Frequency Rate.............

... 70 SEP Refere. ice Number 26 Evaluate and. implement Station Standards for Safe Work Practice Requirements Disabling injury / Illness Frequency Rate..... -...............

.. 18 Recordable injury / Illness Cases Frequency Rate..................................................... 70

' SEP Reference Number 33 Develop On-Line Maintenance and Modification Schedule

' Percent of Completed Scheduled Maintenance Activities

' ( Electrical M alnte nance)................................................

.,............................................ 35

.- (Pre ssu re Equipme nt)...................................................................................

....'. 3 6 -

(General Maint enanc e)........................... _.......................................................

37'

( M echanical M ainte n a nce)..................................................................................................... 38 -

(Inst rume ntabon & Cont rol)......................................................................................... 3 9 SEP Reference Number 36

[

_ Reduce Corrective Non-Outage Backlog L

Maintenance Work Order (MWO) Breakdown (Corrective Non. Outage Maintenance)......... 27

Corrective Maintenance Backlog Greater than 3 Months Old (Non-Outage)......................... 28 ~.

l Maintenance Work Order Backlog (Corrective Non-Outage Maintenance)................... 34 -

L SEP Reference Number 41 Develop and Implement a Preventive Maintenance Schedule Ratio of Freventive to Total Maintenance................................................

.. 29 L

Preventive Maintenance items Overdue,..............................................

.. 30 u

S3 p

e

,,ry.----

w w-, me

(.-W+v,-...--.,

%,,r-e,.--ew-e..a

-+w,w,

,ww.-

, A.e 4,,

. 33 Procedural Noncompliance incidents.........,...

SEP Reference Number 43 Implement the Check Valve Test Program

.. 44 Check Valve Failure Rate........

SEP Reference Number 44 Compliance With and Use of Procedures

.... 33 Procedural Norcompliance incidents (Maintenar.ce).

SEP Reference NumberE Design a Procedurcs Control and Administrative Program

. 22 Document Review...

SEP Reference Number 52 Establish Supervisory Accountability for Workers Radiological Practices

... 53 Radiological Work Practices Program..

SEP Reference Number 54 Complete Implementation of Radiological Enhancement Program

.. 16 Collective Radiation Exposure (Curnulative).....

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

.. 51 Total Skin and Clothing Contaminations.....

. 52 Decontaminated Radiation Controlled Area.....

SEP Ref erence Number 58 Revise Physical Security Training and Procedure Program

... 57 Loggable/ Reportable incidents (Security).

.. 58 Security Non-System Failures...........

.... 59 Security System Failures,.....

SEP Reference Number 60 Improve Controls Over Surveillance Test Program

.40 Number of Missed Surveillance Tests Resulting in Licensee Event Reports.

SEP Ref erence NumbetEl Modify Computer Program to Correctly Schedule Surveillance Tests

...40 Number of Missed Surveillance Tests Resulting in Licensee Event Reports.

SEP Reference Numbar 82 Establish Interim System Engineers

... 66 Temporary Modifications...............................

. 67 Engineering Assistance Request (EAR) Breakdown........

. 68 Engineering Change Notice Status..........

.... 69 Engineering Change Notice Breakdown...

SEP Reference Numbe.,63 Assess Root Cause of Poor Operator Training and Establish Means to Monitor Operator Training. 74 Licensed Operator Requalification Training..

.75 License Candidate Exams...

SEP Reference Numbar 71 Improve Controls over Temporary Modifications

. 66 Temporary Modifications...

94

REPORT DISTRIBUTION LIST R. L. Andrews K. B. Guliani L. L Parent G. L Anglehart E. R. Gundal T. L. Patterson W. R. Bateman R. H. Guy R. T. Pearce K. L. Delek R. M. Hawkins R. L. Phelps A. D. Bilau M. C. Hendrickson W.J.Ponec B. H. Biome R. R. Henning L. M. Pulverenti C. N. Bloyd K. R. Henry T. M. Reisdorfi J.P.Bobba J. B. Herman A W. Richard C. E. Boughter G. J. Hill D. G. Ried M. A. Breuer K. C. Holthaus G. K. Samide C. J. Brunnert L G. Huiiska T. J. Sandene M. W. Butt C. J. Husk B. A. Schmidt C. A.Carlson R. L. Jaworski S. T. Schmitz J. W. Chase R. A. Johansen F. C. Scofield G. R. Chatfield W. C. Jones L. G. Sealock A. G. Christensen J, D. Kecy H. J. Selick A. J. Clark J. D. Keppler J. W. Shannon O. J. Clayton D. D. Kloock R. W. Short R. P. Clemens J. C. Knight C. F. Simmons J. L Connolley D. M. Kobunski E.L.Skaggs G. M. Cook G. J. Krause J. L. Skiles M. R. Core L J. Kripa'.

F. K. Smith S. R. Crttes J. G. Krist R. L. Sorenson D. W. Dale J. B. Kuhr J. A. Spilker R. C. DeMeulmeester L T. Kusek K. E. Steele R. D. DeYoung L E. Labs W. Steele D. C. Dict 2 M. P. Lazar H. F. Sterba K.S. Dowdy R. C. Learch G. A. Teeple J. A. Drahota R. E. Lewis M. A. Tesar T. R. Dukarski.

R. C. Liebentritt T. G. Therkildsen D. L Eid B. Lisowyj J. W. Tills R. G. Eurich B. R. Livingston D. R. Trausch H. J. Faulhaber J. H. MacKinnon P. R. Tumer M. A. Ferdig G. D. Manoran J. M. Uhland V. H. Frahm J. W. Marcil C. F. Vanecek l

F. F. Franco N. L. Martice J. M. Waszak M. T. Frans D. J. Matthews G. R. Williams H. K. Fraser J. M. Mattice S. J. Williett J. F. W. Friedrichsen T. J. Mcivor W. C. Woerner S. K. Gambhlt K. S. McCormick J. K. Gasper R. F. Mehaffey W. G. Gates K. G. Melstad M. O. Gautier K. J. Morris S. W. Gcbers D. C. Mueller J. M. Giant 2 R..'. Mue!!ec J. T. Gleason J. B. Newhouse L V. Goldberg M. W. Nichok D. J. Golden C. W. No; tis D. C. Gorence Nuclear Liceasing R. E. Gray

& Industr, Affairs M. J. Guinn J. T. O'Connor G. E. Guliani W. W. Orr 95 i

_~

POSITIVE TREND REPORT The Positive Trend Report highlights sevaral Perfor-y,;ntenance Work Order Backfoo (Corredive Non Out-mance Indcators with data representing continued per-ace Msnttnance) 1 formance above the stated goal and indicators with data (Page 34) representing signthcant improvement in recent months.

The nurnber of corrective non outage MWOs increased

{

for three consecutive months. This trend is due to the Tha following indicators have i,een selected as exhibiting Cycle 14 Ref uehng Outage during February, March and positive trends:

April.

Cumulative Vstatic2s and NCVs (Twelve Month Runnino Proceduraf Noncomo!iance Incidents (Maintenannt) g (Page 33)

(Page 81)

The nu nber of 9tocedural noncomphance incidents has The nurnber of cumulative violations (twelve-menth run-decreased for.wo mnsecutive months.

ning total) has increated for three consecutive months.

1 Racioloeical Work Pradices Procreen I

(Page $3)

End of Adverse Ttand Report.

The number of coor radiological work practices has de-creased from a he of 59 during the Cycle 14 Refue;ing Outage to 1 for May.

INDICATORS NEEDING INCREASED Amount of Work on Hold Awaitino Parts MANAGEMENT ATTENTION REPORT The amount of work on hold awaiting parts has de-creased for three consecutive montns.

This section lists tha indicators which show inadequacies as compared to the OPPD goal and indicators which show inadequacies as compared to the industry upper

- End of Positive Trcnd Report ten percentile. The indcators will be compared to the industry upper ten percentile as reisvant to that indicator.

ADVERSE TREND REPORT Unofanned AutomMc Reactor Scrams Per 7.000 Hours Crrtical A Performance Indicator which has data represeniing (Page 3) three (3) cor secutive months of declining performance The number of unplanned automatic reactor scrams per constitutes an adverse trend.The Adverse Trond Report 7,000 hours0 days 0 hours 0 weeks 0 months critca' for 1992 (one) has exceed.d the Fort explains the conditions under which certain indicators are Calhoun goalof zero, showing adverse trends. An explan. tion will be provided for indicators with data representing three months of de-Djipblir.a iniurvt! ness Frecuency Rate (Lost Time Acci-clining performance that have been labeled as adverse dont Rcte)

- trends.

(Page 18)

The following indica.e= :re c.*ia v adverse trends for The disabling injury / illness frequency rate at the end of the reporting month:

the reporting month (0.76) exceeds the Fort Calhoun goal of 0.3. -

Ecuinment Forced Outaces Per 1.000 CrMica! Hours Ace of Outstandino Maintenance Work OrerGrree tive Non.Outace)

(Page 20)

The equipment fomed outage rate per 1,000 critical (Page 26)

The number of outstanding MWOs 0-3 months old and hours at the end of the reporting month (0.69) exceeds

>12 months old has increased for three consecutive the Fort Calhoun goal of 0.2.

months. This trend is due to the Cycle 14 Refueling Out-Ratio of Preventive to Total Mainigpance (Non-Outaae) age during February, March and April.

(Page 29)

Maintenance Work Order Breakdown (Corrective Non.

The ratio of preventive to total maintenance for the re-porting month (42.4%)is lower than the Fort Calhoun gg (Page 27) goalof 65%.

The number of total corrective non-outage MWOs and open high priority MWOs has increased for three con-secutive months. This trend is due to the Cycle 14 Refueling Outage during February, March and April.

96

L INDICATORS NEEDING INCREASED PERFORMANCE INDIC/. TOR REPORT MANAGEMENT ATTENTION REPORT IMPROVEMENTS / CHANGES (contiriued)

This secton lists significant changes made to the report Preventive Maintenarce hems Overdgg and to specific indicato's within the report since the pre-

.yous month.

(Page 30)

The percentage of preventive maintenance items over-due for the reporting month (0.72%) exceeds the Fort f0'ced Outaae Ra+e Calhoun goalof 0.5%.

(Page 2)

Out of Service Control Room Instruments The 1992 Fort Calhoun goal was incorrectly repor1ed as (Page 31) 4.5% in the January 1992 repor'. The indica'or has been The number of out-of service control room instruments revised to show the correct goal of 2.4%,

for 16.) reporting month (20) exceeds the Fort Calhoun Fuel RefiabifPv fndicator goal of 13.

(Page 15)

Secondarv oystem Chemistry To follow INPO practtes, this :ndicator is now repnrted in (Page 45)

Ursits of microcuiles/ gram rather than ranocuries/ gram.

The secondary system chemist y perfortnance index value for the reporting month (0.505) is above the FM Co.!!ecib.e Radiation Excesure Calhoun goalof 0.45.

(Page 16)

Columns have been added to the graph to represent the in-Line Chemistrv instruments Out-of Servito monthly values for this indict. tor.

(Page 48)

The number of in-line chemistry instruments cut-of-ser.

Comoonent Faitum Ana!vsis Reogy,f,CFAR) Summarv vice for the reporting mnnth (20) exceeds the Fort Cal.

(Page 41) houn goal of 6.

This indicator repla. css the " Number of NPRDS Report-able Fai'm es* indicator.

Total Skin and Clq1bino Contamination (Page 51)

Licensee Event Recort (LER) RooTause Breakdown The cumLJative skin and ciothing cantaminations at the (Page 72)

The LtiR root cauce codes have been revised to reflect end of the r9 porting month (213) exceeds the Fort Cai.

houn got : af 144, the NRC sequecce coding.

Decontaminated Radi.Elj9D Controlled Area Comoarison of Violations Amone Recion IV P' gig (Page 52)

(Page 80)

The percentage of the RCA thaiis decontaminateo for The column graph has been changed to a bar graph to the reporting month (86.2%)is less than the Fort Caj.

be consistent with the performance indicators standard houn goalof 88%.

of usin columns to represent monthly data.

Cumulative Violations and NCVs (Twelve-Month Runnino Inventerv Accuracy (Page 62)

ID1id The inventory accuracy for the reporting month (94%) is (Page 81) less than the Fort Calhoun goal t f 98%.

Data for the past twelve months has been revised.

Recordable Iniurv'Ifiness Caces Frecuenev Rate Emercent MWOc Acoroved for inclusion in the Cvcie 14 Refuelino Outace (Page 70)

This indicator has been deleted. Indicators to track out-The recordable injury / illness cases frequency rate for the rsporting month (2.27)is above the Fort Calhoun goal of age planning will again be reported in the June 1992 2.0.

Performance Indicators Report.

Violatons Per 1.000 insoection Hours iPage 79)

End of Indicator improvement / Changes Report.

The violations per 1,000 inspection hours reported this month (2.80) exceeds the Fort Calhoun goal of 1.5.

End of Management Attention Report.

97

FORT CALHOUN STATION i

OPERATING CYCLES AND REFUELING OUTAGE DATES l

Ev:nt Data Range Production (MWH)

Cumulative (MWH)

Cycit 1 09/26/73-02/010 5 3,299,639 3,299,639 1st Refueling 02/0145-05/0995

. Cycle 2 05/09&S 10/01U6 3,853,322 7,152,961 2nd Refueling 10/0196 12/1378 Cycle 3 12/13/76 9/30/77 2,805,927 9,958,888 3rd Refueling 09/30N7 12/0977 Cycle 4 12/09/77 10/14/78 3,026,832 12,985,720 4th Refueling 10/1478 12/24/78 Cycle 5 12/2498 01/18/B0 3,882,734 16,868,454 Sth Refueling 01/18/80 - 06/11/80 Cycle 6 06/11/80 09/18/81 3,899,714 20,768,168 6th Refueling 09/18/81 12/21/81 Cycle 7 12/21/81 -12/06/82 3,561,866 24,330,034 71h Refueling 12/06/82 - 04/07/83 Cycle 8 04/07/83 - 03/03/84 3,4005,371 27,736,405 8th Refueling

-03/03/84 07/12/84 Cycle 9 07/12/84 09/28/85 4,741,488 32,4 71,893 9th Refueling 09/28/85- 01/16/86 Cycle 10 01/16/86-03/07/87 4,356,753 36,834,646 10th Refueling 03'07/87 - 06/08/87 Cycle 11 06/08/87 - 09/27/60 4,936,859 41,771,505 11th Refueling 09/27/88 - 01/31/89 Cycle 12 01/31/89 02/17/90 3,817,954 45,589,459 12th Refuelitin 02/17/90-05/29/90

. Cycle 13 05/29/90 -02 01/92 5,451,069 51,040,528 13th Refueling 02/01/92 05l03/92 Cycle 14#

05/03/92-09/18/93 (Planned Dates) 14th Refueling 09/18/93-11/13/93 Cycle 15 11/13/93-03/11/95 15th Refueling

- 03/11/95- 05/06/95 FORT CALHOUN STATION CURRENI' PRODUCTION AND OPERATIONS " RECORDS" First Sustained 3eaction August 5,1973 (5:47 p.m.)

First Electricity Cupplied to the System August 25,1973 Commercial Operation (180,000 KWH)

September 26,1973

. Achieved Full Power (100%)

May 4,1974 Longest Run (477 days)

June 8,1987 Sept. 27,1988 Highest Monthly Net Generation (364,468,800 l(WH)

October 1987 Most Productive Fuel Cycle (f,,451,069 MWH)(Cycle 13)

May 29,1990-Feb.1,1992

-

ML20101P212

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