ML20137M926

Monthly Indicator Rept

ML20137M926
Person / Time
Site:	Saint Lucie, Hope Creek, Turkey Point
Issue date:	10/31/1996
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML20137K821	List: ML20137K816 ML20137K910 ML20137K940 ML20137K961 ML20137K972 ML20137K998 ML20137L016 ML20137L023 ML20137L046 ML20137L065 ML20137L077 ML20137L081 ML20137L092 ML20137L116 ML20137L130 ML20137L141 ML20137L162 ML20137L191 ML20137L205 ML20137L226 ML20137L346 ML20137L359 ML20137L389 ML20137L786 ML20137M723 ML20137M926 ML20137N194 ML20137N205 ML20137N211 ML20137N220 ML20137N238 ML20137N278 ML20137N314 ML20137N327 ML20137N343 ML20137N366 ML20137N431 ML20137N791
References
FOIA-96-485 NUDOCS 9704080201
Download: ML20137M926 (55)

Text

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

FPL NUCLEAR DIVISION TURKEY PolNT NUCLEAR STATIOh ST. LUCIE NUCLEAR STATION MONTHLYINDICATOR REPORT OCTOBER 1996 gi Issued: November 19,199E l 40 1 970402 BINDER 96-485 PDR

4 ,

s l FPL NUCLEAR DIVISION TURKEY POINT NUCLEAR STATIOh l ST. LUCIE NUCLEAR STATION l

i 1'

l MONTHLY INDICATOR REPORT  !

, l l

1 OCTOBER 1996 i

i l

l l

l' yo

I pA

j. Issued: November 19,199E l

l j ENj4P8?22 *42 BINDER 96-485 PDR

l l

FPL NUCLEAR DIVISION i

l TURKEY PolNT NUCLEAR STATION j ST. LUCIE NUCLEAR STATION 1

! l l

l I

l MONTHLY INDICATOR l REPORT l i

OCTOBER 1996 I i

i gNi

issued

November 19,199E i

l gg4eegaoi97o4oa

,i BINDER 96-485 PDR

! FPL NUCLEAR DIVISION l

i

! TURKEY POINT NUCLEAR STATIOh i

ST. LUCIE NUCLEAR STATION i

l MONTHLY INDICATOR l REPORT OCTOBER 1996 i

4 ph issued: November 19,199E 40 1 970402 B N ER96-485 PDR

l i

i l TABLE OF CONTENTS Fo rewo rd.. . . . ... . . .. . .. ... .. .. I D. PERSONNEL INDlcATORS l Table of Contents ... .. . . . . . ... ii OSHA Recordables.. D-1

. Management Summary . .. . . . iii LostTime injuries - D-2 Nuclear Division Business Plan Indicator Overview.. v Regular Staffing... .D-3 j NRC Indicator Performance Overview Turkey Point.. vi NRC Indicator Performance Overview. St. Lucie . vii E. TRAINING INDICATORS l WANO Indicator Performance Overview... viii Operator Exam Performance Turkey Point. E-1 WANOIndicatorVariance Explanations . ix Operator Exam Performance - St Lucie= . . . .E-2

I i A. WANOINDICATORS F. NUCLEAR ASSURANCE & REGULATORYINDICATORS WANO Weighted Overall Performance A1 Overdue Condition Reports _. F1 Unit Capability Factor A2 OA Findings.- F-2 Unplanned Capability Loss Factor - A-3 NRC Violations

Cite and Non-Cited. F-3

, Unplanned Auto Trips Per7000 Hours Critical. ... . A-4 List of Notice of Violations F-4 High Pressure Safety injection System Performance A-5 Ucensee Event Reports (LERs) . F-5 Auxiliary Feedwabr System Performance. A-6 INPO Assessment Ratings- F-6 Emergency AC Power System Performance. A-7 NRC SALP Categor'y Ratings. .F.7 Thermal Performance-. -- A-8 Fuel Reliability... .. -- A-9 G. MATERIALSINDICATORS Chemistry Index. . . . . A-10 inventory... .. G-1 Radiation Exposure.- A-11 Low Leve! Waste. . A 12 H. TECHNICALIENGINEERINGINDICATORS Industrial Safety Performance -- . A-13 Open Plant Changes / Modifications.. h-1 Open Temporary System Alterations - ..H-2 B. OPERATIONSINDICATORS Equivalent Availability Factor B-1 1. RADIATION PROTECTION INDICATORS Capacity Factor (MDC Net). B2 Contaminated Floor Space- l-1 FuelUtilization(PTN) : B3 Dry Active Waste: Generated, Shipped Off-Site _ _ I-2 Fuel Utilization (PSL).- B-4 Personnel Contamination Events.. 1-3 Forced Outage Rate.... __ B5 Radiation Expovare(Y T-D) l-4 Unplanned Auto Trips - B-6 J. BUSINESSINDICATORS C. MAINTENANCE INDICATORS O&M Budget-Division J-1 Open PWO's C-1 Capital Budget- Division,_ J-2 PWO Aging Curve._ C-2 PWO's Greater Than 12 Months Old - C-3 Non-Outage PWO's . C-4 APPENDlX Control Room Instruments Out of Service.- C5 Distribution Ust 2-1 il

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

i i

n-i MNNAGEMENT

SUMMARY

OPERATING PERFORMANCE:

k 1

Equivalent Availability Factor performance in October was as follows:

4 Turkey Point Unit 3. Unit 3 operated at full power in October; Y-T-D EAF was 94.4% which is slightly

, below the Y-T-D target of 95.0%.

i Turkey Point Unit 4. Unit 4 operated at 88.2% for the month; unavailability was due to RPI Problems (0.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) and repairs to the SA Feedwater valve (11'.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />),4A SGFP Suction Relief Valve (2.5 j .. hours), and U4 Low Pressure Feedwater Heater Tube (73.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />). For the ye'ar, EAF was 85.2% which j  : is higher than the Y-T-D target of 79.7%.

1

! St. Lucie Unit 1. EAF for Unit 1 was 98.5%. Power losses were the result of: 4B LP Heater leak (0.6

hours) and a Condenser Tube leak (10.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />). EAF performance Y-T-D was 66.1% which is below the j 75.2% Y-T-D target.

i 4

. St. Lucie Unit 2. Unit 2 operated at full power in October; Y-T D EAF was 93.8% which is below the

- 95.0% Y-T-D target.

J 4 Nuclear Division. Equivalent Availability was 96.7% for the month and 84.9% Y-T-D which is below the

86.2% targeted Y-T-D. The year-end forecast for the Division is 86.5%.

l

! A Summary of key plant operating statistics is summarized below:

l No Unplanned Automatic Trips occurred in October. Year-to-date, one trip was experienced at Turkey -

i Point Unit 3in February.

PTN Unit 3 PTN Unit 4 PSL Unit 1 PSL Unit 2 i Month Y T-D Month Y-T-D Month Y T-D Month Y T-D i

! Gross Generation (MWh) 509,786 4,894,241 426,665 4,287,027 652,660 4,237,340 657,760 6,079,520 I. Net Generation (MWh) 486,755 4,659.874 404.897 4,075,415 619,473 3.990,520 623,933 5,752,922 I Net Heat Rate (Stu/KWh) 11042.6 11043.4 11199.5 11220.4 10924.2 11077.7 10986.8 10937.7 Equivalent Availability 100.0 % 94.4 % 88.2 % 85.2 % 98.5 % 66.1 % 100.0 % 93.8 %

Capacity Factor 104.9 % 96.2 % 87.2 % 84.2 % 99.1 % 65.0 % 99.8 % 93.7 %

• Auto Trips 0 1 0 0 0 0 0 0 1 Forced Outage Rate 0.0% 4.0% 0.0% 04% 0.0% 3.6% 0.0% 34%

i f i

l ikk l

4

f.

~

MANAGEMENT

SUMMARY

REGULATORY PERFORMANCE:

l l Turkey Point. One Notice of Violation (NOV) was reported in October.

1. 96-11 Fire Zones 64 and 143 not covered by exemption to Appendix R. Exit Meeting date: 9/27/96.

{

Year-to-date, three NOVs have been reported.

St. Lucie. Three NOVs were reported in October for the month of September:

1. 96-13 Failure to include some systems within the scope of the Maintenance Rule Program (Post Accident Sampling, Communications, Service Air, Radiation Monitors). Exit Meeting date: 9/20/96.

1. 96-13 Failure to follow procedures (multiple examples). Exit Meeting date: 9/20/96.

1. 96-13 Improper use of Most Probable Functional Failure (MPFF's) as indicators of reliability for safety l

significant systems. Exit Meeting date: 9/20/96.  !

l l* Year-to-date, St. Lucie has reported 23 confirmed and 11 potential NOVs. (See Page F-4 for list of confirmed NOVs).

I

$ 1 COST PERFORMANCE:

O&M Expenditures through October 1996 were $246.9 Million which represented a budget overrun

. overrun of $9.9 Million or (4.2%) again:t the revised budget. Variance is primarily due to St. Lucie Unit 1 outage l scope changes partially offset by transfer of the Turkey Point Thermal Uprate Project from O&M and by project and materials purchase cancellations.

Year-to-date, O&M budget performance variances are stratified as follows: .

i Turkey Point Site Specific $7.3 Million(or 7.4%) below budget j St. Lucie Site Specific $21.9 Million (or 23.2%) above budget i Other Nuclear Division $4.7 Million (or 10.7%) below budget Capital Expenditures through October 1996 were $21.5 Million which represented a budget underrun of $8.5 Million or (28.3%). Variance is primarily due to: plant projects cancelled / deferred /or reclassified as O&M; and, an underrun in the Steam Generator Replacement Project (SGRP).

Year-to-date, O&M budget performance variances are stratified as follows:

Turkey Point Site Specific $1.7 Million (or 69.9%) below budget St. Lucie Site Specific $3.8 Million (or 15.6%) below budget Other Nuclear Division $3.0 Million (or 90.9%) below budget iv

M.

NUCLEAR DIVISION BUSINESS PLAN INDICATOR OVERVIEW (Through October 31,1996) 1996 1996 1996  %

YE YTD YTD INDICATOR PLANT TARGET TARGET ACTUALS COMMENTS

Collective Radiation Exposure PTN 5 275.0 5 265.0 181.4*

Turkey Point and St. Lucie were below YTD Man-Rem targe7 PSL 5 485.0 5 468.0 381.5*

• Current month includes DRD count.

PTN 1.00 1.00 For the second consecutive time, PTN received supenor

NRC SALP Ratings ratings (1.00) in all areas for the SALP period ending 8/17/9s.

PSL 1.50 1.50 The next SALP period for PSL is scheduled for March 1997,

, PTN 57 3 PN reported one NOV in 10/96 for 9/96 for a total of 3 Y-T D.

NRC Violations PSL 57 -

23 PSL reponed three NOVs in 10/96 for the month of 9/96; Y-T D PSL has received 23 confirmed and 11 potential NOVs.

' ~

] PTN3 53 1

~

Unplanned Automatic PTN4 for -

0 No unplanned automatic trips were reported in October.

Trips PSL1 Division -

0 l j PSL2 0 Budget Performance Capital 39.2 30.1 21.5 Capital Y-T D actuals were below the Y T D target.

($ Millions) O&M 288.9 237.0 246.9 O&M actuals exceeded Y T-D target primarily as a Div. Total 328.1 267.1 268.4 result of PSL's outage scope changes.

PTN3 95.0 95.0 94.4 PTN Unit 4 performance Y T-D through October was

Equivalent Availability PTN4 82.0 79.7 85.2 higher than the Y-T-D target.

Factor (%) PSL1 78.5 75.2 66.1 For the Division, EAF Y-T-D was 84.9% which is below PSL2 95.0 95.0 93.8 the 86.2% Y-T D target.

l Division 88.0 86.2 84.9 M&S Inventory Levels PTN 5 38 34.5 PSL exceeded the Year-End target of $38.0 by 50.4M in

($ Millions) PSL 5 38 38.4 October. '

l Production Cost (O&M PTN 1.75 1.78 1.81 PTN and PSL Production Costs ( /KWh) were higher than E PSL 1.55 1.59 1.62 Y-T-D targets in October.

and Fuel)

Total Cost (O&M. Fue! & Division in October, Division Total Cost ( /KWh) was slightly higher Capital Carrying Costs) Total 4.56 4.65 4.68 that the Y-T-D target.

Nuclear Division FPL 2045.0 _. 1825.0 Total Nuclear Division Staffing Level was below the Staffing Levels LTC 463.0 331.0 Year-End target.

Total 2508.0 , 2156.0

_., l Refueling Outage PTN3 l  ; O Duration (Days) PTN4 45 ,.

35 Dates for future refueling outages are being revised and PSL1 63 3 88 should be availabe in next month's report.

PSL2 NA 0 Lost Time injuries per 200,000 PTN 0.30 0.28 No Lost Time injuries were reported in October.

Hrs. Worked (12 Mo. Running) PSL 0.30 0.26 y

v .

NRC INDICATOR PERFORMANCE OVERVIEW for Turk'ey Point (Data through Quarter Ending September 30,1995)

LEGEND PTN 3 g Plant Self Trend Deviatons From Peer PTN 4 g;gg Short Term Grouc Median Lono Term OPERATIONS Declined improved worse Better

~

nos Automatic Scrams While Critcal 10.0 022[@]

O0 0.0 Safety System Actuations 04 0.0 0.0 .o 45 g Significant Events OS 104 l

-o.30 I o.27 E Safety System Failures -0.30 Ioo CAUSE CODES (all LER's)

-o.u g o.06 m Administrative ControlProblem o.o .o.it y 0.0 0.18 g (

Ucensed Operator Problem o.o ieo O.0 0.72' ,

3 _,

vmer PersonnelError o.o i c.o l

1 o 14 g 0.42 ,

Maintenance Problem - .o 14 a 0.0  !

DesigrvConstructionlinstallation Fabrication Problem 00 M o40 0.0 0.0 Miscellaneous o.o 0.0 SHUTDOWN g 0.18 044 l l Sarry System Actuations o.q 0.7s M w?Ml l o.oi oo Significant Events s 40 o37' e 0.51 033 Safety System Failures 2.40 .o.37 CAUSE CODES (all LER's) u.u u.a Administrative ControlProblem 0.30 W wu 025 )

0.01 i 0.0 Licensed Operator Problem .o.30 W 0.0 oss_: )

-0.17 E l Other Personnel Error o.o a o.10 1025 0.12 E Maintenance Problem 320 a o.10 ch -o.03]

Design / Construction / installation Fabrication Problem .o 90 -o.0a E 0.0 0.0 i

i Miscellaneous oo oo FORCED OUTAGES 0.06 l 0.04 025 0.03 Forced Outage Rate *

]4 07 Equipment Forced Outages /1000 Commercial Hours

• 026 0.37 lvare 1.0 0.5 0.0 0.5 1.0 -1.0 0.5 0.0 0.5 1.0

• Not Calculated for Operational Cycle Performance Index Performance Index NOTES:

Plant Self-Tread Short Term: Based on the slope of a linear regression line plotted over each plants data. Time intervals used in the trends are 4 Quarters for *0perations' and ' Forced Outages' indicators and 6 Quaders for ' Shutdown' indicators.

Deviations from Peer Greue Median tono Term: Compansons are made of each plant to the performance of its peers over a 12 Quarter time interval.

Peer Greecs PTN 3&4 - O! der Westinghouse 3-Loop.

Vi

NRC INDICATOR PERFORMANCE OVERVIEW l for St. Lucie (Data through Quarter Ending September 30,1995) j I

LEGENO Plant Self Trend Deviations From Peer l PSL 1 Group Median Lono Term PSL 2 n Short Term OPERATIONS Declined improved Worse Better

- 10.o Automatic Scrams While Critica! 0.54  % o 18 0.90 Safety System Actuations I04 0.90 N32F#Ml 0.0 0.0 Significant Events oo Of

. 00 E 022 _ '

{ Safety System Failures 0.0 agggg22l0.67 CAUSE CODES (all LER's) i o.00 m 0.46 Administrative ControlProblem 0.0a w 0.30 Licensed Operator Problem M]0.90 0.0 E 022 ttJieraipi 0.68 0.64 0.0 Other PersonnelError ion react cl0.72 2

Maintenance Problem M TqElo.28 g o.14 iEU o.2s 025 0.43 Design / Construction / Installation Fabrication Problem oo wcw 0 40 0.0 -0.18 E Miscellaneous oo est o 45 SHUTDOWN 0.95 0.67 Safety System Actuations 0.0 0.15 o.0 0.0 Significant Events oo CD l 022 -0.01 :

Safety System Failures eo 1.s4 slWe%tMEM CAUSE CODES (all LER's) 5 0.11 0.06 I Administrative ControlProblem o.o mi o 44 0.0 0.0 Ucensed Operator Problem oo 0.30 lEliE 3 0.15 0.14 g Other PersonnelError io0 1 0.08 5DM 020 E Maintenance Problem ioo Eil o.12 3 020 fjt Design / Construction / Installation Fabrication Problem oo e,i o.27 i D.0 0.0 ,

Misce!!aneous 04 0.0 j FORCED OUTAGES l l

o.10 l Forced Gutage Rate

• IO EP"52l 0 #

Eauipment Forced Outages /1000 Commercial Hours

• M 0.82 10 il o.13 1.0 0.5 0.0 0.5 1.0 -1.0 -05 0.0 0.5 1.0

• Not Calculated for Operational Cycle Performance Index Performance Index NOTES:

Plant Se% Trend Short Tem 1: Based on the slope of a linear regression line plotted over each plant's data. Time intervals used in the trends are 4 j Ouaders for "Operatons* and Torced Outages

• indicators and 6 Quarters for

• Shutdown

• indicators. '

Deviations from Peer Group Mevian MT,ggr Compansons are made of each plant to the performance of its peers over a 12 Quaner tme interval.

Peer Groues: PSL 1&2 Combuston Engrneenng with core protecton calculator plants.

Vil

WANO OVERALL INDICATOR PERFORMANCE OVERVIEW (October 31,1996)

Industry Median Values

• l Unit or Station Values 3 Yr. Distribution 2000 PERFORMANCE INDICATORS PTN 3 PTN 4 PSL1 PSL 2 (7/93 6/96) Goals i Unit Capability Factor (Unit %, .-

l 3-Yr. Distribution Ending October '96) 89.2 % 89.4% a 77.0%.. 81.5 % 81.4 % 87.0 %  !

! Unplanned Capability Loss Factor (Unit %, ,. y _

l i ' 3-Yr. Distribution Ending October '96) 3.4% 3.4% $5?SYah L8 2)fo" 5.7% 3.0% i

'~

Unplanned Automatic Scrams Per 7000 Hours Critical (Per Unit, 0.6 0.6 f 0.6 0.9 1.0

N 1.6.' .

3-Yr. Distribution Ending October '96) /N High Pressure Safetyinjection N " '" M F.,.* '

c% wx :v. W.  :. a System (per Unit, 3-Yr. Distribution 60.009.,  :.~0.009 - ,00,265; .m .' 0.009. 0.003 - 0.008 not

. . .:w . ~ :.c.: -- .

j Ending September'96) D 9 c

1 '

~

available j

Auxiliary Feedwater System ,' g .

f . "[

7

] (per Unit,3 Yr. Distribution c0.0135 CO.010f 0.009 '0.013 0.004 - 0.009 not e.

" Ending September'96) ,- m:

• W. available f

I a Emergency AC Power system -

I (per Unit,3-Yr. Distribution 0.006 0.003 (0.019, 0.013 0.009 - 0.014 not v.

! ending September'96)  ? available l Thermal Performance (Ratio of Design l . "

to Actual Gross Heat Rate,(1 Yr. 100.0 % k59[dW 99.7 % 99.7 % 99.6% "" 99.5%

uww , l

, Distribution Ending October'96) ThEM I

Collective Radiation Exposure (Man- y-@

%..~gf.

Rem per unit per year,3-Yr. running 147.4 147.4 _;217.6) 2; 217.6 i 153.0 110.0 cm. ,to l avg. ending October'96) n.P %b  ;

Volume of Low-level Solid Radioactive

.Aw::. " ;' : , ,,.. .

l Waste (Cubic meters per unit per year, 31.5 31.5 .552.0 5 p52.0l 46.0 45.0 i "8 GNC; 3-Yr. avg. ending October'96) )

Chemistry Index (12-mo. weighted ,, f._ p- ;*., _ g .; '

average through October'96) 1.03 1.05  % 171: $1-184 1.16 " 1.10 l l

Industnal Safety Lost-Time Accident Rate (Station rate per 200,000 man- 0.28 0.26 0.44 " 0.40 l hours worked ending October'96)

Fuel Reliability (Unit microcuries/g, Fuel Defect Reference not month ending October'96) 1.00E-06 2.25E-05 1.00E-06 8.90E-05 5.0E-04 *" available NOTE: Shaded area denotes FPL performance is unfavorable to actualindustry rnedian.

Source ofindustry Data:

• 1996 Med. Year Report for Performana indcators for the u. s. Nudear Utihty Industry PS34S6 Distribubon). j

" 1996 MdYear Report for Performance Indicators for the u. S. Nudear Utikty industry US54S6 Distnbubon).

"' 1996 Md-Year Report for Performance ind cators for the u. s. Nudear Utihty industry (4S6696 Distnbution).

Viii

WANO OVERALL INDICATOR PERFORMANCE OVERVIEW Discussion of FPL Perforrnance Unfavorable to Industry Median (October 31,1996) 1 UNIT CAPABILITY FACTOR f3 Years Endina 10/31/96)

St. Lucie Unit 1. The 3-Year running Capability Factor through 10/31/96 was 77.0%. Capability loss is attributed to the following: Hot Leg Valve MV-3480 leak repairs from 3/29/94 to 4/2/94 (0.4%); Main Transforrner trip from 6/6/94

to 6/11/94 (0.4%); Quench Tank leak repairs from 2/27/95 to 3/8/95 (0.9%): 1 A2 Reactor Coolant Pump seal repairs i from 8/2/95 to 8/9/95 (0.7%); inoperable Power Operated Relief Valves from 8/9/95 to 8/17/95 (0.7%); inadvertent Containment Spray actuation and clean-up from 8/17/95 to 9/3/95 (1.3%); 182 Diesel Generator failure from 9/1/95 to 9/6/95 (0.5%); 1 A Diesel Generator Radiator leakage from 9/6/95 to 9/10/95 (0.4%); Code Safety Valve repairs

. and modifications from 9/11/95 to 10/13/95 (2.4%); a refueling outage from 4/29/96 to 7/25/96 (8.0%); and,1B Main Transformer repairs (0.8%). Other miscellaneous unplanned outages and derates accounted for the remaining 6.5%

Unit Capability Factorloss.

I UNPLANNED CAPABILITY LOSS FACTOR f3 Years Endina 10/31/96)

St. Lucie Unit 1. The Unplanned Capability Loss Factor for the three years ending 10/31/96 was 15.5% compared to an industry median of 5.7%. Unplanned outages and power reductions contributing to this performance included:

Hot Leg Valve MV-3480 leak repairs from 3/29/94 to 4/2/94 (0.4%); Main Transformer trip from 6/6/94 to 6/11/94 (0.4%); Quench Tank leak repairs from 2/27/95 to 3/8/95 (0.9%); 1A2 Reactor Coolant Pump seal repairs from 8/2/95 to 8/9/95 (0.7); inoperable Power Operated Relief Valves from 8/9/95 to 8/17/95 (0.7%); inadvertent Containment Spray actuation and clean-up from 8/17/95 to 9/1/95 (1.3%); 182 Diesel Generator Failure from 9/1/95 to 9/6/95 (0.5%); 1 A Diesel Generator Radiator leakage from 9/6/95 to 9/10/95 (0.4%); Code Safety Valve repairs and modifications from 9/11/95 to 10/31/95 (2.4%); dropped CEA's from 2/22/96 to 2/25/96 (0.2%); a refueling outage extension from 6/22/96 to 7/25/96 (3.1%); and,18 Main Transformer repairs (0.8%). Other miscellaneous unplanned outages and derates accounted for the remaining 3.7% Capability Loss.

St. Lucie Unit 2. The Unplanned Capability Loss Factor for the three years ending 10/31/96 for 8.0%. Major unplanned occurrences contributing to this performance included: shutdown for auto reactor trip investigation on 4/23/94 (0.3%); refueling outage extension from 12/1/95 to 1/5/96 (3.2%); and, Hydrogen System problems from 1/5/96 to 1/7/96 (0.2%); and, shutdown from Hydrogen Cooling System Valve and 2C Auxiliary Feedwater Pump repairs from 6/6/96 to 6/13/96 (0.7%). Other unplanned outages and power reductions accounted for the remaining 3.6% in Capability Loss. l l

UNPLANNED AUTOMATIC SCRAMS PER 7000 HOURS CRITICAL f3 Years Endina 10/31/96)

St. Lucie Unit 1. Increased rate for Unit 1 was the result of five auto trips occurring on 3/28/94,4/3/94,6/6/94, 10/26/94, and 7/8/95.

l l

i ix l

I

HIGH PRESSURE SAFETY INJECTION SYSTEM (3 Years Endina 9/30/96)

Turkey Point Units 3 & 4. Average performance was affected due to the on-line replacement of the HPSI pump motors following discovery of cracked rotor bars.

St. Lucie Unit 1. Average performance for the last three years was affected by on line Motor Operated Valve testing in the 3rd Quarter of 1994 and a breaker failure on 2B HPSI pump in the 1st Quarter of 1995.

St. Lucie Unit 2. In tne 1st Quarter of 1995, average performance was affected as a result of Component Cooling Water (CCW) Heat Exchangemaaning which placed the respective HPSI pump OOS due to lack of dedicated seal cooling.

AUXILIARY FEEDWATER SYSTEM (3 Years Endina 9/30/96)

Turkey Point Units 3 & 4. Average performance for both units was affected by the B AFW Turbine failure in the .4th Quarter of 1994 due to malfunction of the rrmhanical overspeed trip device; in the 3rd Quarter of 1995, performance was affected by:

Part 21 repairs on the Trip and Throttle Valves, and Unit 3 outage work.

NOTE: Turkey Point's Auxiliary Feedwater system is configuratively unique because it is a shared system between two units.

For example, during a refueling outage, the non-refueling unit will always be impacted with unavailable hours. Due to its uniqueness, it is unlikely Turkey Point will be within the Industry Median value (0.003 - 0.008).

St. Lucie Unit 2. Average performance for three-years was E.ucted by failure of the AFW PP 2C Steam Admission Valve MV-08-13 to open, a mechanical trip linkage for AFW PP 2C when the Electrical Overspeed Solenoid was energized, and a discrepancy between field wiring and plant wiring drawing for the AFW PP 28.

EMERGENCY DIESEL GENERATOR SYSTEM (3 Years Endina 9/30/96)

St. Lucie Unit 1. Unit 1's average performance for three years was the result of a high water Jacket temperature trip of 1 A EDG and failure of the govemor on 182 during monthly surveillance run which closed off fuel to the 12 cylinder engine in the 2nd Quarter of 1995,18 diesel 12 cylinder engine valve failure in the 3rd Quarter of 1995, and 1B diesel due to replacement of the cooling water valves in the 4th Quarter 1995.

COLLECTIVE RADIATION EXPOSURE MAN-REM (3-Years Endina 10/31/96)

St. Lucie. Collective Radiation Exposure three-year running average level for St. Lucie was 217.6 Man-Rem per unit which was greater than the industry median of 153 Man-Rem. Site perfoimance was influenced'by unplanned and scheduled outages.

VOLUME OF SOLID RADIOACTIVE WASTE (Annual Ava. for 3-Years Endina 10/31/96)

St. Lucie. Volume of Solid Radioactive Waste for the 3-year annual average was higher than industry median due to 1994 waste volume; the 1995 value of 41.9 cubic meters was below the median value.

CHEMISTRY PERFORMANCE (12-Mo.Weiahted Averaae Endina 10/31/96) .

St. Lucie. Performance at St. Lucie is affected by the elevated condensate dissolved oxygen.

X

WANO WElGHTED OVERALL PERFORMANCE 100.0 0 PTN 3

. . + PTN 4

.-t' .  :.s -d Fiu Industry Avg 90.0 ,-

. 4 80.0 . S. ,

. t y 0

..' l '. ,t >

o............o j 70.0 ,'

^

'W k

e C0.0 ,

s NOTL WANO reatnatred weighted percentages and

,# semoved lho Lawlevet Sohd Radioactive Weste sidcator.

50.0 , An- es proph have been earuswd Aimm graph has been redesegrwd to report data quartetty The 3rd 9' Quarter 1996 data WH fW be evadetMe unhl November.

40.0

' 3/96 . ;6/96 y .: .9/96 12/96 Unit 1991 1M2 1993 1994 1995 .

88 6 84.8 90.6 87.8 91.8 FIN 3 58 0 66.9 63 8 86.5 86.7 93.7 92.7 92.7 PTN4 46.3 i

74 4 82.7 75.8 62.1 62.2 58.2

' PsL'1 51.3 66.8' 73.6 72.5 73.2 PsL2 70.8 80.9 71.2 Industry Avg n/a n/a 76 2 80.1 i 82.0 DEFINITION I

The WAND Overall Performance index is a composite indicator utilized to trend nuclear station performance. The index is a weighted combination of the following 11 individual performance indicators over the time period noted:

1. Unit Capability Factor (16%)(2 yrs)* 5. Emergency AC Power (10%)(2 yrs)* 9. Thermal Performance (6%)(1 yr)

2. Unplanned Capability 1.oss Ftr (12%)(2 yrs)* 6. Unplanned Auto & rams (9%)(2 yrs)* 10. Chemistry Indicator (7%)(1 yr)

3. High Pressure Safety injection (10%)(2 yrs)* 7. Collective R:distion Expcue (8%) (2 yrs)* 11. Industrial Safety Accidents (5%)(1 yr)

4. Auxiliary Feedwater Systern (10%)(2 yrs)* 8. PWR Fuel Reliabity (8%) (most recent qtr)

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE WANO:

Through 4th Quarter 1995 Industry Median: 84.0%

l PERFORMANCE

SUMMARY

i t

St. Lucie Unit 1's decline from ist Quarter io 2nd Quarter is primarily the result of a decrease in Unit Capability Factor, increased Safety System performance rates, and increased Collective Radiaton Exposure.'

' See above for length of period used in weighted calculations.

Data Provider Shamn Bilger 694-4255 A1

I UNIT CAPABILITY FACTOR (3-Year Running Average) 100.0

' )

f 95.0 Dnnsen E j 9 .0 ..,,,.A j , ,,

e $y a

=

C f

85.0 qf. 4

,,, o-o.x7% . . . - . . . .. ...c...c...o 0 0 0 A ~

O--C

, l 70.0

' 65.0

• c PTN 3

, l*-4 PTN 4 ,

, 60.0 --O-- PSL 1

• ]

l *

• O

• PSL 2 _

l 55.0 * --c--Industryg I 50.0 45.0 ,

i e s 40.0 Unit 1991 ;1992 1993 1994 1995 -1196 12/96 W 4/96 '6/96 6/96 :7/96 8/96 9/96 10/96 11/96 12/96 88 9 88.9 88.6 88 7 88.7 88 7 88 6 88 7 88 6 88 4 89.2 PTN 3 47.9 52.7 64.6 85 0 87.2 87.3 87.3 64 6 85.7 88.3 89.2 89 0 89 4 89 5 89 4 PTN 4 42 2 61.8 63 7 86.7 77.9 78 0 77.8 77.9 80.5 80.5 794 77.1 77.1 77.0 77.0 PSL1 77.5 784 82.7 84 6 74.1 74 o 75 1 77.7 80 5 80 4 81.0 80.3 80 6 80 9 81 4 81.5 PSL2 81.4 81.3 81.3 industry Avg. 72.3 74.6 76.5 78 6 80 6 DEFINITION Unit Capability Factor is the ratio of the available energy generation over a given time period to the reference energy generation over the period, expressed as a percentage with both energy generation terms determined relative to reference ambient conditions. Available energy

. generation is the energy that could have been produced under reference ambient conditions considering only limitations within con management,i.e., pl ant equipment and personnel performance, and work control. Reference energy generation is the energy that coul if the unit were operated continuously at full power under reference ambient conditons throughout the period. Reference ambient con 6tions are environmental conditions representative of the annual rnean (or typical) ambient conditions for the unit.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE gg Y.T.D 3.vr Runnina Y.E Taroet WANO

' 7S3 6/96 Median 81.4 %

7SS 6S6 Median 84.2 %

PTN 3 100.0 % 94.4 % 89 2 % 1 95.0 %

89.4% 7S5 6S6 Average 79 8 %

• PTN 4 88.2% 85 2 % 1 82.0 %

77.0 % Year 2000 Goaf 87.0%

PSL1 98.5 % 66.1 % 1 78.5%

PSL2 100.0 % 93.8% 81.5 % 1 95.0 %

PERFORMANCE

SUMMARY

See comments on Page ix.

j Data Provider. Sharon Bilger 6944255 A-2

9

UNPLANNED CAPABILITY LOSS FACTOR

. , (3-year Running Average) i 16.0 14.0 ,

k (

i O PTN 3 e' / .

- . . .g. . . PT N 4 ~

12.0 .

• '. --- O-- PSL 1

- O - PSL 2

• / Q 1

.:. Industry Avg 10.0 ,

o.......o o...o...

g, o..

,_, c

6.0 , ,

N i .-

y kc .... ..... ___ , _

[

" ' ' v -e...$7.j W y.E: 1 I o' 3.2%

2.0 0.0 4/96- . 5/96 : -6/96 7/96 '. 8/96 ^9/96 10/96 11/96 *12/96' Unit 1991 1992 1993 :1994 :1995 '1/96i  :.2/06 + ?.3/96 3.0 3.8 3.5 3.5 3. 5 3.5 34 3.4 3.7 34 PTN 3 15.2 4.8 38 4.3 3.3 4.2 42 4.0 37 3.4 33 3.1 3.0 34 11.5 6.5 39 4.7 4.2 4.2 PTN 4 15.3 15.5 13.0 13.3 13.2 12.7 12.1 12.5 14.5 14.2 PSL1' 5.1 5.9 44 5.7 13.0 84 8.3 8.1 8.7 8.5 8.3 8.1 8.0 11.6 13.2 14.8 13.1 10.7

-PSL2 3.1 5.5 industry Avg. 8.2 7.8 64 5.5 4.9 DEFINITION Unplanned Capability Loss Factor is defined as the ratio of the unplanned energy losses during a given period of time generation, expressed as a percentage. Unplanned energy loss is energy that was not produced during the per shutdowns, outage extensions, or unplanned load reductions due to causes under plant ird-pK&it control. Causes of energ considered to be unplanned if they are not scheduled at least four weeks in advance. Reference energy generation is the ene produced if the unit were operated continuously at full power under reference ambient conditions throughout the pe conditions are environmental conditions representative of the annual mean (or typical) ambient conditions for the utst.

STAflSTICAL

SUMMARY

INDUSTRY PERFORMANCE 3-vr Runnino PTN 3 3.4% WANO 3.4% 7/93 6/96 Median 5.7%

PTN 4 15.5% 7/95 6/96 Median 5.0%

PSLi 8.0% Year 2000 Goal 3.0%

PSL 2 1996 Target (all units): 53.2%

PERFORMANCE

SUMMARY

See comments on Pageix.

Data Source: John Pizzutelli 6944245 s.t

UNPLANNED AUTO TRIPS PER 7000 HOURS CRITICAL

~

(3-year Running Average) j 16 5

O O O O O O O O O O

, 1.6 ^ '. '

I l 31.4 5 b *

• f

] 1.2

%\\.', ,-

~

• s

• Onnsion Y E:11 per unrt ,

gg .

% :4 2 .... .......+....... ... ,

l -

e 0.8 l N 0-< O- O,' '.

^ ' ^

'O O O O O 'O O O

{

^

i 0.6 >

y .  :

' PTN 3 , _

i 'i5 04 -

- - 4 * - PTN 4 l

Z 6 .*

O

/

e --O -PSL 1 O PSL 2

, 0.2 4 Industry Avg. ,

I I 00 .

2/96 3/96 4/96' 5/96 6/96 7/96 9/96 9/96 10/96 11/96 12/96 Unit - 1991 1992 1993 1994 1995 1/96 03 0.3 0.3 06 06 0.6 06 06 06 0.6 0.6 06

'PTN 3 - 1.6 1.0 0.0 I 1.7 14 09 1.3 09 0.9 09 09 0.9 0.9 09 09 06 06 06 PTN4 <:

1.6 1.6 1.6 1.6 1.6 1.6 1.6 i PSL1,'= 1.3 1.0 09 1.5 16 1.6 1.6 1.6 07 0.6 0.6 06 06 06 06 06 0.6 PSL2 06 06 03 07 0.7 0.7 Industry Avg.- 1.5 1.2 1.1 09 0.9 i

DEFINITION Unplanned Automate Scrams per 7000 Hours Cntcalis defined as the nurnber of unplanned automatic scrams that occur per 7000 ho operation. Unplanned rneans that the scram was not an anticipated part of a planned test. Scram means the automatic shutdown of th a rapid insertion of negative reactivity (by control rods, liquid injection shutdown system, etc.) caused by actuation Of the reactor protection sys i The scram signal may have resulted from exceeding a setpoint or may have been spurious. Automatic means that the initial signal that ca actuation of the reactor protection system logic was provided from one of the sensors monitoring plant pararneters and conditions rather th the mamtat scram switches or, in certain cases described in tNPO 94009, from manual turbine trip switches provided in the main control room.

Critical means that during the steady-state condition N.ior to the scram, the effective reactor multiplication factor was essentiaffy equal to one.

STATISTICAL

SUMMARY

- INDUSTRY PERFORMANCE s 1 Through October WANO 12-mo 36 e 7/93 6/96 Median 0.9%

Division Totals: 7/95 6/96 Median 0.8%

08 Year 2000 Goal 1.0% j f g 9 Division Target: 13.0 auto trips l

. PERFORMANCE

SUMMARY

1 I See Pageix for comments.

?

Data Providers: (PTN) Jim Knorr 246-6757 and (PSL) Kelly Korth 467-7054 A-4

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

j HIGH PRESSURE SAFETY INJECTION SYSTEM PERFORMANCE (3-yr Running Average)

OW c PTN 3 j

- - +- - PTN 4

]

0035 ---O-- PSL 1 -

j

- O PSL 2

4. Industry Avg 0.030 l

.x k 0 - '

@ 0.02s DnnsaiY-E: < 0.025 8

h 0.02o D

0.015 ,' ,

0 010 .,

/

^

g

~ ' ~ ~

s'

~~~

O.000 Unit 1991 1992 1993 1994 1995 2

t. 3/96 5/94 9/96 12/96 PTN 3 0.007 0.003 0.007 0.00s 0.006 0.008 0.009 0.009 PTN 4 0 001 0.001 0.006 0.006 0 009 0.009 0.009 0 009 PSL1 0 091 0.026 0 017 0 011 0 025 0.026 0.027 0.026 PSL2 0.011 0 00s 0.01a 0.007 0.010 0.009 0 009 0.009 andustry Avg. 0.006 0.000 0.010 0 006 0.008 ,

DEFINITION This Safety System Performance indicator monitors the readiness of the Safety injection (SI) System at Turkey Point and the High Pressure Safety l Injection (HPSI) System at St Lucie to respond to Offmormal events or accidents. The indicator is determined from the unavailabilities, due to all I causes, of the components in the system during a time penod, divided by the number of trains in the system. The definition is further explained:  !

component unavailability is the ratio of the hours the component was unavailable (unavailable hours) to the hours the system was required to be l available for service. Data is reported on a quarterly basis.  !

.j Unavailability = fKnown Unavailable Hours) + fEstimated Unavailable Hours)

(Hours System Required) x (Number of Trains)

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE l 3rd Otr 1996 3-vr Ava Endino 9S6 Pm3 0.000 0.009 PTN 4 WANO Unavailability 0.001 0.009 l PSL1 0.000 0.026 7S3 6/96Medan(PWR) 0.003 - 0.008 PSL 2 0.004 0.009 2000 Goal 0.020 Targets- ETN PSk 1995 Y-E Target 5 0.016 5 0.023 i 1996 Y-E Target 5 0.025 5 0.025 l PERFORMANCE

SUMMARY

!l See Page x for comments.

I

)

i I

Data Providers: (PTN) Blian Dunn 246-6173/Carlos Melchor 2466964 (PSL) Chuck Wood 467-7034/Juri Krumins 467-7136 A-5  !

I

~

i SAFETY SYSTEM PERFORMANCE - AUXILIARY FEEDWATER SYSTEU

! (3-year Running Average) l 0.040 f

j 0 PTN 3

' + PTN 4

--O-= PSL 1 O -PSL2

industry Avg .

0.030 A

I Divis4on Y-E: 50.02s I 0.020 '0 . .

h O 's, g . . . . . . . . . . . 6.%

g

, /  ;-n--....

t

0 000 3/96 6/96- 9/96 - 1 2/96 r Unit ' -1991 1992 1993 1994

1995 -

0 016 0 021 0 014 0015 0 015 0.013 PTN 3 0.008 0.025 0.019 0.011 0.012 0.011 0 010

' PTN 4 -- 0.012 0.031 0.020 0.010 0.010 0 009 PSL'1 + 0.012 0.030 0.028 0029 0 010 0 008 0.014 0.013 0.014 0 013 PSL'2 0.017 0.014 0 012 4

i DEFINITION i This Safety System Performance indicator monitors the readiness of the Auxiliary Feedwater (AFW) System to respond to off-norm

events or accidents. The indicator is determined from the unavailabilities, due to all causes, of the components in the system during a time period, divided by the number of trains in the system. This definition is further explained

comoonent unavailability is the r hours the component was unavailable (unavailable hours) to the hours the system was required to be available for service.

AFW Unavailability = (Known Unavailable Hours) + (Estimated Unavailable Hours)

• (Hours System Required) x (Number of Trains)

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE 3rd Otr 1996 3-vr Av0 Endino 9/96 PTN 3 0.004 0.013 WANO Unavailability l 0.004 0.010

• PTN 4 PSL1 0.004 0.009 0.004 0.009 j 0.013 7/93 6/96 Median (PWR) 0.020 PSL2 0.003 2000 Goal Targets: EE! ESL l 1995 Y E Target 5 0.020 5 0.021 1 1996 Y-E Target 5 0.025 5 0.025 PERFORMANCE

SUMMARY

See Page x for comments.

I t

I i

4 Data Providers: (PTN) Brian Dunn 2464173/ Woody Raasch 246-6527 (PSL) Chuck Wood 467 7034/ Mark W0 laver 467-7083 A6

I SAFETY SYSTEM PERFORMANCE - EMERGENCY AC POWER SYSTEM (3-year Running Average) ~

l 0.030

PTN 3

• 4 = PTN 4 l i

0.025 - *

• O PsL 2 onnsion Y.E: 5 0 025 5! i e

Industry Avg 0.020 O C O O w . l 1

rg 0.015 5 [0. , . ,

A

=,

0 ---........ ,......... c ,

. l 0.010

,- p' , , ,,

b' '

'. D 1 0.00s ,

+............+...........+ i

,.* I 0.000

Unit ' 1M1 -1992 1993 '1994 A996 e r"; f3tH ' :St96 ' -

• 9/96 12/96

. PTN 3 .' O001 0.004 0 002 0 003 0.003 0 006 0.006 0.006 I

- PTN 4 o . 0.015 0.001 0.002 0 003 0 003 0.003 0.003 0.003 PSL1 0 013 0.019 0 012 0.010 0.019 0.019 0.019 0.019  ;

'PSL2 0019 0.008 0 011 0 007 0.012 0.013 0 012 0.013 )

6rulustry Avg. 0.017 0.017 0.020 0 014 0 012 .

DEFINITION Emergency AC Power System is defined as the sum of the emergency diesel generator unavailabilities divided by the number of emergency generators at a station. Data is collected at the train level. The emergency generator includes subsystems such as air start, lube oil, fuel oil, cooling water, etc. However, for this safety system performance indicator, unavailable hours are counted only when the emergency generator is unavailable to start or load-run. For example, if a component fails in one train of a redundant support system the emergency generator is still operable, and no unavailable hours are counted.

~

STATISTICAL

SUMMARY

- INDUSTRY PERFORMANCE 3rd Otr 1996 3-vr Ava Ench g@f PTN 3A&B 0.001 0.006 PTN 4A&B 0.002 0.003 WANO Unavailability PSL1A&B 0.001 0.019 PSL 2A&B 0.015 0.013 7S3 6/96 Median (PWR) 0.009 0.014 2000 Goal 0.025 Targets: PT_H E$1 1995 Y-E Target 5 0.015 1 0.016 1996 Y-E Target 1 0.025 5 0.025 PERFORMANCE

SUMMARY

See Pageix for comments.

Data Providers: (PTN) Brian Dunn 246-6173/Jennifer Murphy 246-6827 (PSL) Chuck WO0d 467-7034/ Roger Kulavich 467-7080 A7

I

. l

.' THERMAL PERFORMANCE (12. Month Running Average) 101.0 l

l I o .... ..... .

, 100.0 -

? G &W=. = = = *

&nnson Y.E: 99.57.

j

,/

,l I . D II i O*. s .

s. . .O * " 43'.

'**. .o*

l 5 / t) O **

~~~ ~~

99.0 - ,.

I f,

• ,.- , f 1;;

l, .

I Note: PSL numbers have t '. / been adjusted for 1995

. / and 1996 to reflect an pyg 3 _

' 96.0 average of best plant . . .e. . .PTN 4 I D, + pst1 performance. This is in l g

line with PTN's reporting. - O Psl2 j i t., Industry Avg i

[ 97.0 i 6/96 '7/96 8/96 9/96- 10/96 1 1/96 12/96 .

t 2. Unit - 1991 1992' 1993 1994 1 995 119 6 J/96 ' 3/96 ' 4/96 ' 5/96 '.

100.1 100.1 100 1 100.2 100.1 100 0 l 99.2 100 4 100.3 99 8 99 8 99 9 99.9 100.0 PTN3. 99.3 99 0 99 0 j 100.1 100.1 100.1 99 9 99.7 99 4 99.3 99 1

2. PTN 4 98.7 99.0 99.7 99 7 100.1

99.7 99 7 99.7 99.7 99 0 99.8 99 7 99.7 99.7 99.7 99 7 99.7 i '.PSL1 99 0 99 3 99.2 99 2 99.2 99.3 99 4 99.5 99 6 99 7 99 8 PSL2 99 6 99 3 97.8 98.5 99.1 29 1 99.2 f 99.3 99 4 99 4 99.5 a industry Avg. . 99 2 1

DEFINITION Thermal Performance is the ratio of the desgn gross heat rate (corrected) to the adjusted actual gross heat rate. Gross heat rate is defined as the ratio of total thermal energy produced by me reactor core to the total gross electrical energy produced by the t

generator during a given time MM. Design gross heat rate (corrected) is the minimum theoretical heat rate that c i at design operating conditions for 100 percent power, expressed in British thermal units (BTUs) per kilowatt-hour (e I Adjusted actual gross heat rate is the gross heat rate attained in the normal equipment hneup during one 24-hour month, expressed in BTVs per kilowatt-hour (electric) power level should be greater than 80 percent.

3 STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE g 12-Mo Avera0e WANO PTN 3 99.3 % 100.0%

99.0 % 99.0 % 7/95 6/96 Median 99.6 %

PTN 4 100.0 % 99.7 % 2000 God 99.5 %

PSL1 l PSL 2 99.6 % 99.8% l 1996 Target (all units): 99.5%

PERFORMANCE

SUMMARY

l l

i I

l 4

Data Providers: (PTN) Jose Donis 2466008 and (PSL) Marty Senit 467-7079 l f

A-8

FUEL RELIABILITY (Fuel Cycle / Monthly) 1.00E+00 0 PTN 3

. . 0 PTN 4

--O--PSL 1 _

1.00E 01 =

• O PSL 2

.:. Industry Avg 1.00E 02 hm D* -

E 1.00E 03 4 -. '

3 . ' <$ Fuel Defect Reference 5.0E-04 EI 1.00E od ', O. .

• O " * " E

W.7..<:'O...

1 -

,~ .

y >

x. . *

' ^

'^ ^

1.00E 06 1.00E.07 c Cycles c 1/96 :2/96 - '3/96 4/96 5/96 ' 6/96: '7/96 '8/96: 9/96 10/96 11/96 .12/96

- . Unit Previous .

t.7saa ims4 ima smt4 tmE4 t eoE4 t eos4 t oca4 1.cos 4 tme4 t ooe4 PYN 3 4 4sa.s sme4 s 70s-s s. tea 4 ima4 f asa4 sme4 s esa4 e.sse4 s.sta4 tme4 a s4a4 s ese4 t.7ss.s t ona4 4 4as4 22s44 ePTN4 3J4a.s a ses4 s ataa s.t7s4 t eie4 a.s s s t. sea 4 s.stt4 t seos s ete.s t ass 4 ime4

.PSL1s em4 s aas.s n ece4 ims4 issos t oes4 4 csa4 2 4sa.s f o0E4 s ceE4 7.7tE.s s ecE4

<PSL2 a s18 2 a 71s s a sas.s 8ndustry Avg; s.cead DEFINITION This indicator is defined as the steady-state primary coolant iodine-131 activity (microcuries/ gram) corrected for the tramp contribution and power level, and normalized to a common purification rate and average linear heat generation rate. The indicator value is calculated based on the average of the three monthly values for the most recent quarter of steady-state operation above 85 percent power. Steady state is defined as continuous operation for at least three days at a power level that does not vary more than 15 percent.

Note: If a calculated monthly value for a unit is less than 1.0E4 microcuries per gram, the value is replaced by 1.0E-6 microcuries per gram.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Qg Cycle No WANO PTN 3 1.00E46 15 l PTN 4 2.25E 05 16 7/96-6/96FuelDefectReferenceThrc .old(PWR) 5.00 E44 PSL1 1.00E 06 14 1994 Median 7.36 E45 PSL2 8.90E 05 9 1994 Best Quartile 3.00 E-06 Division Target for each unit 14.50E 03 I

1 PERFORMANCE

SUMMARY

Preliminary review of the Reactor Coolant System radioisotopic data for all units indicates zero defects.

1 1

Data Provider. Modesto Jimenez 694-3323 l

A9

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

. 1s CHEMISTRY INDEX 1

> . (12-Months Ending Weighted Average) 1.40 -

PTN 3 4 PTN 4

--O-- PSL 1 '

1.35 O PSL2 l .:. Industry Avg 1.30

(&

Desion Y-E: < 1.20 g , ,

n.

g o

5... .

...go;o p

,p 1.15 O

:  : -m % . ,

i 1.10 ' "

m- -

g_*

e+*4..,

\ ,

e e ........ . -3 1.00 )

3/96 4/96 5/96 6/96 7/96 8/96 9/96 10/96 11/96 12/96 l 1992 1993 1994 1995 119 6 . 2/96 Unit 1991  !

1 11 1.11 1.11 1.09 1.09 1.09 1.08 1.08 1.03 1.10 1 11 PTN 3 1.05 1.04 1.03 1.08 1.06 1.06 1.07 1.05 1.05 1.04 1.04 PTN 4 i +

1.24 1.20 1.20 1.18 1.16 1.16 1.16 1.16 1.17 1.17 1.17 )

.PSL1- 4 1.18 1.17 1.18 l 1.17 1.19 1.19 1.19 1.17 1.18 1.19 1 18

. PSL'2 .'s industry Avg.. 1.18 DEFINITION The Chemistry index compares the concentration of selected impurities to the limiting values for those irpurities. Eac

.I impurity value is divided by the limiting value for the impurity, and the sum of these ratios is normalized to 1.0. Th values are the ' achievable values' defined by intemational industry-accelf.ed values.

i i STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE l 12 Mo. Endino Weichted Ava Qgt 1.00 1.03 WANO

! PTN 3 (PWR's with Recirculating Steam Geaarators without Molar

! PTN 4 1.01 1.05 1.17 Ratio Contr01) l PSL1 1.19 1.16 1.18 7/95 6/96 Median PSL 2 1.25 1.00 1995 Lowest Chemistry Index Value Attainable Year 2000 Goal 1.10 1996 Targetfor each unit: s 1.20 PERFORMANCE

SUMMARY

f See Page x for comments.

l t

Data Providers: (PTN) R Steinke 24%118/ Jim Berg 24H953 1

(PSL) R Frechette 465-3213/ Dave Faulkner 465-3393 1

a.in

Q '

RADIATION EXPOSURE

!* (3-year Running Average) 400

,! ' -+- PTN

--O- PSL 350 + + Industry Avg. i

)

sm I

b 250 yau a-yr Avf g T rget. I229.2 EI

=

200 Target 5,1 8 r

t 100 Note: 1996 numbers are adjusted each monm to renect l

, T1.D data '

So i I

i 0 0 Plant ' 1991' 1992 1993 1994 1995 .1/96 ' 2/96 . 3/96 ' 4/96 ' 5/96 iG/96 7/96 8/96' 9/96' 10/96 11/96 12/96 )

PTN. 350 332 257 181 162 162 161 185 164 153 152 151 150 149 147

PSL> 274 238 193 202 230 229 227 219 187 200 210 218 218 218 218 j tuluspy Aug. 189 193 193 ]

144 153 DEFINm0N .

Collective Radiation Exposure is the total extemal whole-body dose received by all personnel (including contractors and  !

coming on site during a time period, as measured by the primary dosimeter, thermoluminescent dosimeter (TLD) or film badgel Exposure measured by direct reading dosimeters should be included only for those periods or situations when more accurate data j is not available to the utility f/om TLD's or film badges. In order to correlate this indicator with the rew 10 CFR 20 reportingj guidelines, U.S. utilities report deep dose equivalent (DDE) and the total effective dose equivalent (TEDE).

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE 3-yr Runnino oer Unit Man-Reni PTN 147.4* WANO (per Unit)

PSL 217.6*

(PWR's ) Median 3-yr Distribution (7S3 6S6) 153 Division Targets: 3-vr. Avo 7S3 -6S6 Median 136 PTN: Y-E thru 1996 5 170.8 2000 Goal 110 PSL Y-E thru 1996 5 229.2 PERFORMANCE

SUMMARY

J i

See Page x for comments.

~

Current monm data is DRD; TLD was not available at time of pubr<ston.

Data Providers:(PTN) John Lindsay 2464548 and (PSL) H. M. Mercer 467 7302 A-11

_ _ _ . _ _ . _ _ - . _ _ _ _ . . _ _ . - . _ . . _ . . _ _ _ _ _ _ _ . . . _ . . _ . . _ . _ _ .__ __ .-_ _~ _____.

!l -

. LOW LEVEL SOLID RADIOACTIVE WASTE

• l (Cubic Meters per unit per year. 3 year Running Average)

)

4 i  ;

+

140 a f j --+-- PTN i

--O- PS L l

120

-is-Industry Avg -

i l

f l

1x .

i.

I e

$ 80 d

PSL Y.E: 67.5 I l

a f .e-60

\i C O 4

40

- r -

4 4 '

W,- ,

:  :  :  : 0 t

! 20 i

a

. O

'1993 :1994 1996 .1/96 ;2/96 -3/96 4/96 .4/96 6/96 ;7/96 .8/96  :$/96 10/96 '11/96 12/96 J Plant '1991 ' :1992 125 3 102.3 81.2 63 4 37 4 36.7 36.2 33.1 33.2 32.0 31.1 31.1 30.8 31.0 31.5 PTN 121.1 103.8 80.7 75 4 53.7 63.3 53.0 54 6 57.2 57.0 56 4 54.7 54.2 54 1 52.0 i ~PSL' I Mustry Avgc 85.0 87.0 45.0 46 0 47.0 t I

f f

i DEFINITION This indicator is defined as the volume of low-level solid radioactive waste that has been processed and is in final form (for example, l

compacted or solidified) ready' for disposal during a given period. It is calculated using the amount of waste in final form, including l

the container, actually shipped for disposal from both on-site and off-site facilities, plus the change in inventory of final-form waste in l

i storage at both on-site and oft site facilities.

i .

l i

• in transitto or at disposal site for disposal STATISTICAL

SUMMARY

-lNDUSTRY PERFORMANCE l

i 3-vr Runnino thru Oct foer unit)

WANO MontNy Cu. Ft.

(per uniti PTN 31.5 PSL 52.0 3-yr Distribution Median (7S3-6S6) 46.0 755 6S6 Median 32.0 Division Ta gets:

2000 Goal 45.0 PTN 1996 Y-E 55.6 cu. mtr.per unit

• PSL 1996 Y-E 67.5 cu. mir. pe unit PERFORMANCE

SUMMARY

See Page x for comments.

Data Providers: (PTN) Bob Schuber 2467220 and(PSL) Bruce Somers 467-7305 A-12

f 4 - INDUSTRIAL SAFETY ACCIDENT RATE (12-Month Running Average) 1.00 0 -PTN l l 4 -C>- PSL

\

$ +lndustry Avg l u0 0.80 2

}" 0.60 - -

xg y 2 / l

\ , $.'

" 0.50 l a.

f 0.40

/ & '

PTN/PSL Y-E: 10.30 ,

• h" i \ ,

y 0 0 2 0.10 0.00

.8/96 9/96' 10/96 11/96 12/96 3/96 .4/96 ' 5/94 J . 6/96 7/96 1993 '1994 '1995 A196 4 /96 Plant i 1991 1992 0 12 0.13 0.14 0.28 0.22 0 11 0 11 0.12 0.12 0 67 0.36 0.50 0.22 0.22 0.26 PTN 0.25 0.33 0.34 0 33 0.36 0.25 0 40 0 40 0 41 0.32 0 32 0.75 0.61 0.50 0.51 PSL l 0.97 0.77 OJ7 0.64 0.55 -

industry Aug. .

DEFINITION Industrial Safety Accident Rate is defined as the number of accidents per 20,000 ma permanently assigned to the station that result in any of the following: (1) one the accident);(2) one or more days away from work (excluding the day of the accide notincluded for thisindicator, incustrial Safety Accident Rate = fnumber of restricted-time + lost-time accidents + fatatifie (number of station man-hours worked) t INDUSTRY PERFORMANCE STATISTICAL

SUMMARY

1?Mo-Endino(Oct)

WANO PTN 0.28 0.44 PSL 0 26 7/95 6/96 Median 0.40 2000 Goal DivisionTargets:

PTN 1996 Year-End 0.30 PSL1996 Year Ena 0.30 I

PERFORMANCE

SUMMARY

l l

No Lost Time injuries were reported in October.

l I

Data Providers: J. Sambito (PTN) 245-7372 and T. Mo

r.

,. L l .- EQUIVALENT AVAILABILITY FACTOR

! (Yee.r-to-Date) 100.0

-O' 'O j k .' - .,i_,,h. b Division

. r

,g ~

,,, kt.W .

Y\ . ....

i 70.0 .

'e. . . . e ' ' 1 1

k e

=

, y  ;

2 e 50.0 ./

. l 40.0 30.0

/ ,

)

' c PTN 3 l 1 - + PTN 4 _ (

20.0 * --O-- - PSL 1

'! + O PSL2

.t ind Avg __

10.0 i i

{ , 0.0 Unit 1991 1992 1993 1994 1995 ' fit 96 ? ;2/96) M 4/96; 5/96 4/96- ,7 M 8/96 9/964 10/96 11/96 12/96 j 66.3 94.6 83.5 88 7 99 9 83.3 87.4 90.5 92.5 93.3 94.3 94 6 93.8 94 4 1 PTN 3 22.3 PTN 4 13 9 85.5 81.1 83.1 97.4 100.0 100.0 68.3 68.4 74 8 78.9 80.9 83.3 84.9 85.2 1

74 0 64.5 75.3 99 6 94 5 94 9 94.6 75.3 62 9 55 6 61.8 62.4 66 1 PSL-1 78.5 95 4 71.8 77.4 72 9 76 8 87.9 92.0 92.1 93.5 99.8 91.3 92.4 93.1 93 8

- PSL 2 98 5 73.2 Ind Avg - 72.2 72 8 75 3 77 4

]

DEFINITION Equivalent Availability Factor (EAF) is the ratio of the actual energy production capability to the energy that would be produced f

j operating at full power for the same period expressed as a percent. Equivalent Availability provides an indication of the effectiveness

! of plant programs and practices in maximizing electrical generation.

EAF% = Available Hours - (Ecuivalent Unit Derated Hours) x 100%

Period Hours l 1

i STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE l l

Oct YT-D Y-T-D Taroet 3-vr Run. Ava l l  !

PTN 3 100.0 % 94.4 % 95.0% 89.2%

, 88.2% 79.7% 89.4 %

1995(ms) 75.7% i f PTN 4 85.2 %

77.0 %

1993-1995(Alltypes) 72.7% l l PSL1 98.5% 66.1 % 75.2%

PSL 2 100.0 % 93.8% 95.0% 81.5 %

WO Division 96.7 % 84.9 % 86.2% 84.3 %

7/95 6/96 Median 82.3%  ;

7/95 6/96 Average 77.3%

1996 Division Y E Target: 88.0 %

1996 Year End Forecast 86.5%

l PERFORMANCE

SUMMARY

h 1 Equivalent Availability Factor performance in October was as follows:

• PTN Unit 3 operated at full power in October; EAF Y T-D was 94.4% which is slightly below the Y T-D target of 95.0%.

. PTN Unit 4 EAF for the month was 88.2%; power losses were attributed to RPI problems (0.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) and repairs to the SA Feedwater Heater Tube Side Relief Valve (11.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />),4A SGFP Suction Relief Valve (2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />), and 2A Low Pressure Feedwater r8.ater Tube (73.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />). EAF Y-T D was 85.2% which is higher than the Y-T-D target of 79.7%.

• PSL Unit 1 EAF was 98.5% Power losses were the result of leaks to the 4B LP Heater (0.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />) and Condenser Tube hours). Y T D Performance of 66.1% was below the Y T-D target of 75.2%.

• PSL Unit 2 operated at 100.0% for the month; Y T-D EAF was 93.8% which is slightly below the Y-T-D target of 95.0%.

i Data Provider. Sharon Bilger 694-4255

+

p.1

_ ___ ______ _ _ _ . . __ __m - . _ . _ . _ _ . . - _ _ _ . . . _ . . _ _ _ _ _ _ = _ . . ~ . . - - ._.. ___.

4 CAPACfrY FACTOR (MDC NET)

(Year-to-Date) 110.0

.. 4 0

100.0 i AA / h . 2 _.t..:.. 6...a i

K M..X W \ "

,, 0 m/ .

, y.

,,, ~

4

!/ v \ , s i

1,,, y v

. t 50.0

~  :

• /,

40.0 0 PTN 3 j . . .e. . . PTN 4 -

30.0 --o-- PSL 1

• 0 PSL 2 _

20.0  ; Ind Avg

! 10.0 0.0 Ut96 ' 8/96 ' ' Site ? 10/96 -11/96 12/96

,1992 "1993' 1994 ~l1995 1 /96'

• 2/96. ~3196

• 4/96 - 'St96.' '. 6/96

• Unit 'l s1991 95.3 96.2 103 9 85.7 90.0 93.1 94 9 95.5 95 9 96 4

'P7N 3 - 22 5 58.4 97.0 84 8 89.5 f

71.0 67.5 74 1 78 1 79 3 82 2 83.8 84 2 13.7 79.3 81.4 83 0 99.5 104.5 104.2 PTN 4 60.5 61.1 65.0 75 0 98 8 93.3 94.2 94.1 74 9 62.5 55 2

- PS!.1 s 78 8 96.9 73 9 84.1 87.0 92.0 92.0 93 5 89 5 91.2 92.3 93.0 93.7

' PSL2' 101.1 73.7 64.1 76 3 71.9 74.1 ind Avg 71.2 72.3 75 4 77.9 j

f DEFINITION Capacity Factor (CF) is the index of the actual electrical energy produced by the unit with respect to its potent Net Electrical Generation X 100 CapacityFactor =

Maximum Dependable Capacity (839 or 666) X Period Hours STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE NERC/ GADS Qc[ Y T-D 12-mo. endina 1995 A:1 Types 75.2%

PTN 3 104.9 % 96.2 % 97.0%

19911995 AllTypes 71.3%

PTN 4 E7.2% 84.2 % 87.0 %

PSLi 99.1 % 65.0 % 70.2%

78.0%

WANO PSL 2 99.8% 93.7 % 81.1 %

7/95 6/96 Median Division 97.7 % 82.1 % 83.0 %

7/95-6/96 Average 77.9 %

PERFORMANCE

SUMMARY

Capacity Factor performance in October was affected by-

. PTN Unit 4 - RPI problems and repairs to the SA Feedwater Heater Tube Side Relief Valve,4A SGFP Suctio  ;

l Valve, and 2A Low Pressure Feedwater Heater Tube.

= PSL Unit 1 - 4B LP Heater and Condenser Tube leaks.

1 i

Data Pr.vider. Sharon Bilger 6944255 1

1 Q .-)

P I.

I PTN FUEL UTILIZATION FACTOR  !

. Turkey Point Unit #3, Cycle 15 Turkey Point Unit #4, Cycle 16 I I I 550 jl 500 - )

l

< g Planned Refuedg Date: March 8.1997 500 - Planned Refueling Date- September 15,1997 l l 453 450 - .2 O 3400- . 'ein i k 350 - c. MM f k350 - ,M e e 30o - g & n-y %

4 4 l

cet New Das Men F.4 tear Apr meer M .Jwt Aug asp Oct Nov Des Jan fee test Apr tesy Jun M Aug See

! PTN s3 Planned . 5 35 66 98 127 158 188 219 249 281 312 342 373 403 435 466 494 501

" - ' 18 47 78 109 128 157 167 218 248 278 308 333 365 Variance 91.)

• 13 12 12 11 1 -1 1 1 1 3 4 9 8 i

) - PTN 94 6 37 67 98 129 159 190 220 251 282 310 341 371 402 432 463 4 94 509 Planned 4 - " = ' ~ 18 49 79 106 137 166 194 VA 12 12 12 8 8 7 4 j ,

Hi-)

i DEFINITION l'

2

! Fuel utilization plots the amount of nudear energy used during the current fuel cyde. The amount of nudear energy loaded into the j core is expressed in effective full power days (EFPD). One EFPD is the equivalent of operating the reactor at maximum thermal i I ra'ing (2200 at PTN or 2700 at PSL) for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. Planned energy is compared to actual energy used during the cyde. Fuel lj 1 utilization is directly related to plant performance. The significance of variance EFPD(+/-) is the difference between planned and actual energy consumption. Fuel utilization can be used to project longer or shorter operating fuel cydes.

Actual Energy I Calendar Days = Fuel Utilization Factor

! ;i i Fuel Cycle Operating Assumptions -

i PTN 3: In accordance with the April 26,1995 Approved Operating Schedule (AOS), Unit 3, Cyde 15 is scheduled to run 498 calendar days (October 27,1995 to March 8,1997) with design energy to run 501 (EFPD) days. NOTE: Due to the 34-day outage, startup began on October 7,1995,20 days earlier than planned.

PTN 4: In accordance with the February 8,1996 AOS, Unit 4 Cyde 16 was scheduled to startup on April 25,1996. Due to a 35-day refueling outage, the unit actually started up on April 8,19%,17 days earlier than planned. Note that the unit has a design i energy of 507 EFPD.

PERFORMANCE

SUMMARY

. Unit 3 achieved a Fuel Utilization Factor of 103.1% and operated for 767 effective full power hours in the month of October.

' For the period October 27,1995 to October 31,1996, the Fuel Utilization Factor was 99.4%. Power uprate occurred on 10/11/96.

. . Unit 4 achieved a Fuel Utilization Factor of 90.6% and operated for 674 effective full power hours in the month ofOctober.

For the period Apnl 8,1996 to October 31,1996, the Fuel Utilization Factor was 102.0%. Power uprate occurred on t

10/28/96.

Data provider. Jimmie Perryman 694-3330 B.3

e.

PSL FUEL UTILIZATION FACTOR St. Lucie Unit #1, Cycle 14 St. Lucie Unit #2, Cycle 9 500 600 Planned Refuehng: February 3.1998 Planned Refuehng Date: April 15.1991 550 - 450 500 -

_ 450- -- --

k o O 350-400 -

_ _ _ , ~-

w"--- - - -

0; .

0; u s., om seev .c.c Jan p.e aner .aer o.: one, oss Jan pe emir a,, eney su. Aue PSL#1 Jun u a.,e s.,

335 365 395 425 454 485 514 544 573 575 39 69 98 129 158 188 218 246 276 305 Planned 9 Actual O 5 35 56 87 variance eq .9 34 34 .42 42 PSL#2 336 366 397 427 455 485 500 <

67 95 126 155 186 215 247 276 306 5 36 Planned 254 285 0 23 52 83 111 141 162 193 224 Actual 0 44 .43 43 44 -45 53 54 52 52 51 Vartance MM 5 36 DEFINITION Fuel utilization plots the amount of nuclear energy used during the current fuel cycle. The amount of nuclear energ core is expressed in effective full power days (EFPD). One EFPD is the equivalent of operating the reactor at m rating (2200 at PTN or 2700 at PSL) for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. Planned energy is compared to actual energy utilization is directly related to plant performance. The significance of variance EFPD(+/-) is the difference betw actual energy consumption. Fuel utilization can be used to project longer or shorter operating fuel cycles.

Actual Energy 1 Calendar Days = Fuel Utilization Factor l

Fuel Cycle Operating Assumptions PSI.1: In accordance with the February 8,1996 Approved Operating Schedule (AOS), Unit 1, Cycle 14 was scheduled ta operation June 22,1996. This provided for a cycle of 591 calendar days with design energy to run 575 effec (EFPD). Unit 1, Cycle 14 actually began operation July 25,1996 and is currently scheduled to refuel Febr PSL 2: In accordance with the April 26,1995 AOS, Unit 2, Cycle 9 was scheduled to begin operation November 24,199 i provided for a cycle of 508 calendar days with design energy to run 500 EFPD Unit 2, Cycle 9 actually 1996 and is currently scheduled to refuel April 15,1997.

PERFORMANCE

SUMMARY

e Unit 1 achieved a Fuel Utilization Factor of 98.7% and operated at 734 effective full power hours in the month of O the period of June 22,1996 through October 31,1996, the Fuel Utilization Factor was 67.4%.

e Unit 2 achieved a Fuel Utilization Factor of 100.0% and operated at 744 effective full power hours in the rnonth of Octob For the period of November 24,1995 through October 31,1996, the Fuel Utilization Factor was 84.8%.

Data provider Ruben Rodriguez 694-3345 ru

] -

F~

ai

'E - FORCED OUTAGE RATE 12 (Year to-Date) 0 250 --

PTN 3 h' g + PTN 4

., --C>- PSL 1

*. O PSL2 l ** i. Ind Avg ;__

4.,

20 0 -- ,

g ,

4 ,. l\ .

a')

15.0 ,

E * '.

; e

.

Y s l '. '.

?  ?

10 0 --

.. =-k l, ,

T.

6

.  : . -o .

', ,0 . . _

50 --

v...,,

, , ~~~

., O., l l ,

%.{ *o.. ,,

O -

. A -  :  :'

.. ~ -

• • 0.0

-3/96 ' :4/96 ' 5/96. > 6/96 . 7196 8/96 9/96 10/96 '11/96 12/96 gun 1991 1992 '1993 1994 '.1995 '1/96  : 2/96 -

0.5 00 11.8 9.3 7.0 56 47 40 35 45 40 pyy 3 1.2 15 6 1.8 1.9 1.5 0.0 0.0 0.0 1.3 1.0 0.8 06 0.5 0.5 04 1.8 13.2 2.0 39 PTN4 2.2 2.1 18 4.1 36 1.2 35 2.1 39 21.8 00 44 29 2.2 22

- pstt 3.4 2.2 2.2 1.7 5.7 4.8 4.2 3.7 3.4

~ pst2 0.0 81 23.5 2.3 2.4 7.0 ind Avg 12.1 10 9 10.3 10.6 9.0

• DEFINITION 4

Forced Outage Rate is the percentage of time that the unit was unavailable due to forced events compared to the time p full power operation. A forced outage exists when the unit requires immediate removal from service,i.e. the unit is not

• to the grid. This type of outage usually results from immediate mechanical / electrical / hydraulic controls systems and opera initiated trips in response to unit ala:Tns.

Forced Outage Rate Forced Outaae Hours x 100%

Forced Outage Hours + Service Hours STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Oct Y-T-D 12 Mo Endino NERC/ GADS 1995(Alltypes) 9.0%

PTN 3 0.0% 4.0% 3.3% 10.6%

0.3%

1991- 1995 ( @ s)

PTN 4 0.0% 0.4% .

PSL 1 0.0% 3.6% 3.2%

PSL 2 0.0% 3.4% 3.4%

4 PERFORMANCE

SUMMARY

. No forced outages occurred in October.

Data Provider. Sharon Bilger 6944255 )

4 B-5 l

.- l UNPLANNED AUTOMATIC TRIPS WHILE CRITICAL (Year-to-Date) s,-

0 PTN3

+ PTN4

--0-- PSL1 O PSL2 l

^ /. lnd Avg!

4 Division Target: 5 3 ,

s

^  ;

2-l ',

o 0 I  : . . . O O O O O O O O O M/965 r2/96 ' : 3/96 - 4/96- 25/96 -6/96 i :7/96- -8/96 9/96' 10/96 11/96 *12/96 Unit -1991 1992 '1 993' *1994 :1995 1 1 1 1 PTN3 0 0 0 1 0 0 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0

-PTN44 0 1 1 2 4 0 0 0 0 0 0 0 0 0 0

. PSL1 2 1 0 1 0 0 0 0 0 0 0 0 0 0

PSL2 .- 0 1 0 1 1 ind Avg - 1.3 1.1 0.9 0.8 09 DEFINITION An Unplanned Automatic Scram is a non-manual actuation of the reactor protection system that results in a scram signal any tl the unit is critica!. Scrams that are planned as part of special evaluations or tests are not included in this definition. This indicator l provides an indication of success in improving plant safety by reducing the number of undesirable and unplanned thermal-hyd and reactivity transients requiring reactor scrams.

STATISTICAL

SUMMARY

~ INDUSTRY PERFORMANCE WANO Trios per unit Oct Y-T-D 12-Month Endino 0 1 Trips per 7000 Critical Hours PTN 3 1 0 3-yr Distribution Median (1993 95) 0.9 PTN 4 0 0 0 1995 Median 0.9 PSL1 0 0 0 1995 Goal 1.0 PSL 2 0 0 0 1 1 NRC (19953rd Qtr Performance Indicator Rpt)

Division Total:

Quarterly Trips Annualized 1.0 Quarterly Trips per 7000 Critical Hours 1.2 1996 Division Target 53 PERFORMANCE

SUMMARY

7_

No automatic tnps occurred in October 1996. Year-to< late, one automatic trip has been experienced:

• Turkey Point Unit 3 experienced an automatic trip on February 9th; the 'B' Steam Generator Feed Pump was stopped to monitor its discharge check valve closing stroke which did not strike closed as expected. The resulting feed flow transient caused the 'C' Steam Generator level to increase resulting in a turbine trip which tripped the reactor.

Data Providers: (PTN) J. Knorr 246-6757 (PSL) Kelly Korth 467-7054 B-6

OPEN PWO'S 2,500

--+- PTN

-O- PSL 2,000 1,500 y A

c.

5 ,

i CL O 1,000 )

l  !

I l 500 0

1991 '1992 1993 1994 :1996 s1M s .M - ".3/96 6 . 6/96 : $/96, 7/96 :8/96 9/96 '.10/96 11/96 .12,96 e Unit -

• * *

• 1.422 1.310 1.330 1.544 1.536 1.608 1.553

'PTN

• 1.466 1.589 1.441 1.60s 1.920 2 03c 2.086 2.166 2.056 1.697 1.782 1.644 1.762 PSL-DEFINITION This indicator includes Woi Type 1 (Planned Miscellaneous), Work Type 3 (Projects), WorkType 5 (Trouble & Breakdown), Status 17 through 48, and all hold coces.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE PERFORMANCE

SUMMARY

pa.ta a Providers:(PTN) Greg Heisterman 246-6796 and (PSL) Joe Marchese 467-7107 C-1

l PWO AGING CURVE  !

-1000 j 0 PTN Actual 900  ! * * + - PTN Goal i--0--PSL Actual 800 l O PSL Goal "

's o 700 .

e . .

!~o 500  %'- -

400 -

300 200 100 Unit -

0

. TOTALS- :3 Mo. & gruster c -- '",8 Mo;& grooter '

s Mo. & greater - 12 Mo. & greater-PTN Actual * . c- 988 464 237 96 i PTN Goal t *

• 908 494 247 124 0 PSL' Actual -- 862 311 156 58 23 PSLGoal ' 862 431 216 108 0 DEFINITION PWO Aging curves includes Work Type 1 (Pianned Miscellaneous) Work Type 3 (Projects), WorkType 5 (Trouble &

Breakdown), status 17 through 48, and excludes HC2 through HC6 and SNO. INPO definition is to be used for the graph.

Goal: To halve the backlog every three months.

STATISTICAL

SUMMARY

- INDUSTRY PERFORMANCE PERFORMANCE

SUMMARY

l I

Data Providers: (PTN) Greg Heisterman 24%796 and (PSL) J0e Marchese 467-7107 c.9

PWO'S GREATER THAN 12 MONTHS (GOLDEN OLDIES) l 1

TURKEY POINT ,

PWO# PWO TrrLE Ong. Date Date on Lst l TtEF CONMUL BLDG ROUP MULLEi BEAM,iN5i ALL TROLLEY EEAM 10/30s55 lie 1Tro

--i 95V A 606 ST.LUCIE PWO# PWO TITLE Ong. Date Date on Ust

~REF 9401/403 SUPPORT PCM442 289 (H2 iSOL VLVS) 7/13/94 07/13/95 1

95003699 U 2 OSG 2A ANN. 6.2 ALARM 2/5/95 02/05/96 2

VLV LEAKS BY SEAT 2/12/95 02/12/96

~3 95004362 CHECK THE LIMITS ON SOLENOIO. 2/22/95 02/22/96

~4 95005523 95013260 REPAIR REPLACE CONOUlT SUPPORTS 5/4/95 05/03/96 5

95013570 WILL NOT CAllBRATE REPAIR 5/8/95 05/07/96

-6 95014709 SW1TCH CAUSES RELAYS TO CHATTER 5/19/95 05/18/96 7

95017293 MECH. SEAL LEAK ANO FITTINGS LEAKING 6/14/95 06/13/96 8

95018290 ENG MOUNTED ELAPSED HOUR METER INCORREC 6/22/95 06/21/96 9

95020079 ALARMS WILL NOT ADJUST. REPAIR / REPLACE 7/13/95 07/12/96

~10 95020533 IMPLEMENT PCM-152-994 7/25/95 07/24/96 i 11 '

95022001 REPLACE FH-1 A AND FH-1 DOORS 8/9/95 08/08/96

~ 12 95024572 REPLACE TEMP CONNECTIONS TO CALGON TIME 8/9/95 08/08/96 13 08/30/96 l 14 95024538 WATER LEAK 8/31/95 95030685 U/2 OVERHAUL SPARE HVE.218 MOTOR 9/29/95 09/28/96 t5 16 95029229 NEED TO BE CALIBRATED FOR LOCAL READING 10/16/95 10/15/96 17 95029289 OSCILATING AND NOT CONTROLING 10/16/95 10/15/96 95029430 PLEASE REPA!R VLV. LEAKS BY SEAT 10/17/95 10/16/96

~ 18 95030905 U/2 4KV BKR 2AB-1 PARTS REPLACE 10/22/95 10/21/96 19 95031853 PUMP CASING DEGRADED-REPAIR OF REPLACE 10/23/95 10/22/96 20 95030597 REPAIR CRACKS ON A/C BASE NE CORNER 10/23/95 10/22/96 l 21 10/28/95 10/27/96 22 95030690 U/2 REPLACE ARC CHLfTE RETAINER f 95030795 REPAIR AS REOUIRED 10/30/95 10/29/96 j 23 1

1 PWO Greater than 12 month's, includes Work Type 1 (Planned Miscellaneous), Work Type 3 (Projects), WorkType 5 (Trouble &

Breakdown), status 17 through 48, and excludes HC2 through HC6 and SNO. j l

l l

l l

Da'a Providet (PTN) Greg Heistennan 246-6796 (PSL) Joe Marchese 467 7107 C-3

! NON 0UTAGE PWO'S f

I 1400

-+- PTN _

1200

-O- PSL 2

, "\

u 1000 W/

o l 800 f

S y soo e

4oo too o

1M2 '1M3 1994 iM5 ' 1M :2f96 3I96 4/96. SI96. .6/96, ~7/96 .BM 9f96 10M 11/96 12/96 Unt 1M1 1024 1091 1118 1166 949 936 1081 1035 1049 993 1PTN 1247 1103 1016 961 890 889 1102 1101 902 922 PSL'.

DEFINITION ~

Non-Outage PWO's includes Work Type 1 (Planned Misce!!aneous), Work Type 3 (Projects), WorkType 5 (Trouble & Breakdowl status 17 through 48, and excludes HC2 through HC6 and SNO.

l STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE l

i I

l PERFORMANCE

SUMMARY

Data Providers: (PTN) Greg Heistennan 246-6796 and (PSL) Joe Marchese 467-7107 r.s j

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

F CONTROL ROOM INSTRUMENTS OUT OFoSERVICE 60

-+- PTN C -O- PSL

$0 8

Ie Y

40 .

s i h Outage tags j PTN: 38 g so PSL: 8 E \

• t I0 '

l

{ $ 20 v

~

I _& '

l e 1 10 0

Unit 1991 -1992 1993 1994 1996 146 2 96 '3/96 456 656 6/96- 7/96 8/96 946 10/96 1146 12/96 PTN : 39 40 42 12 30 16 43 41 52 47 49

.PSL. 54 46 25 20 28 27 27 33 22 12 11

! DEFINITION l This indicator defines the number of control room instruments for each unit that cannot perform their design function, regardless of the reason. Instruments on the control room back panels are readily available for use by the control room crews and are included; however, instruments in adjoining areas where operators are not normally stationed (such as computer rooms) are not included. Count deficiency tags that are in status 05 to 48.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE l

PERFORMANCE

SUMMARY

Data Providers: (PTN) Greg Heisterman 2466796 and (PSL) Joe Marchese 457-7107 C-5

i OSHA RECORDABLES (Year-to-Date) 50

--*- P TN '

--C>- PSL 40 2 30 3 e E

20 a O

10 C . .

0 6/96 :7/96. 's/96 -1/96 1 0/96 '11/96 12/96 M196. ;226. ' 3/96

• 14/96'; : 6/96

Unit ., ~ 1991 '1992 !1993' '1994 1998 2 2 4 4 5 6 6 35 39 29 27 20 0 1 2

. : . PTN a ,

17 18 19 20 41 26 3 3 4 5 10 14 PSL 20 22 23 DEFINITION The definition by Occupational Safety Health Administration (OSHA) is an injury occuning on the job that requ treatment beyond first aid as defined by 29 CFR 1904. This graph shows OSHA Recordables reported at the sites STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE

, Month Y T-D PTN 0 6 PSL 0 20 Nuclear Division Y-E Target 1,75 per 200,000 Hours Worked 3.75 per 200,000 Hours Worked l Corporate Y E Target 1 i

PERFORMANCE

SUMMARY

I St. Lucie reported one OSHA Recordable injury in October as a result of an employee treated for carpel tunnell I

A total of 26 OSHA Recordables have been received year-tchdate.

Data providers: J. Sambito (PTN) 246-7372 and T. Moser (PSL) 457 7171 n.1

f '

k.

l LOST TIME INJURIES

(Year-to-Date) 5 8

f d

^ -+- PTN l

--O- PSL ;

' l ga t

?

E 1 i: i

$2

.a

" ^

0 0 0 1

i

! I 1 0 0 0 0 0  :  :  :  :

j 0  :  : . .  :  :  :  : .

l Unit 1ssi 19s2 1993 1994 1995 .1/ss :2tes sies -  :*ss ' w.  : stes ; viss . s/ss '- 9/96 10/ss 11/ss 12/ss l

! PW 0 0 0 1 0 0 0 0 0 0 1 1 1 1 1

PSL 2 4 3 1 2 1 1 1 1 1 1 2 2 2 2 i

DEFINITION .

!- A Lost Time injury as defined by Occupational Safety Health Administration (OSHA) is an occupationalinjury that requires an

! employee to miss a full day (8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shift) beyond the day of injury, d

STATISTICAL SIJMMARY INDUSTRY PERFORMANCE Month Y-T-D PTN 0 1 PSL 0 2 i

l PERFORMANCE

SUMMARY

l 4

No Lost Time injuries were reported in October. l 1

Data providers: J. Sambito (PTN) 24S7372 and T. Moser (PSL) 467-7171 D-2

REGULAR STAFFING FPL Employees and Long-Term Contractors by Department Turkey Point 1200 l O Actual

] --O- Planned i 1100- M M c  ; g g C c g f3 1000 900- - est e43 asT ,7, g g g , ,

8I8 sis sie g 800-700 St. Lucie 1200 1100- 1.054 1.oso 19 1.o2o 1.o11 1.oi s 1.o11 m , m  ;

1000- ,,g, , ,,7, ,,,g, , ,q, ,,dQ C a 3 900 - e3I s2i e j f g 800-700 Engineering l 500

• M3 343 333 aos 400 - _ Ml M1 ses 3os 0 0 -

~

= l 300 - Sie 316 314 312 311 3co 293 278 296 30o ,

, 200-g 100 -

)

0 Nuclear Assurance 120

• tos ios toe a 1os tos vos 110 w w w C 0 0 0 0 C 100 - scT 104 104 #5 104

• ic%3 Si C

i O

5 s4" go .

-E 80 Licensing & Special Programs 10

• a 8- e a 6- ,C p p l 4- l f

g 2-0 Nuclear Business Services 50 I 43 O

= p ,2 43 43 43 43 4 42 42 45 43 c  : = = = c a g 40 - 41 4i ,

, y 4o 4 w M f g 35 -

30 Nuclear Division Total 2600 - 2.493 2.493 2.493 2.4S3 2.489 2.489 2.co C C g C C C 2.372 2.372 2.372 2400 - = Q 2.4I3 2.43 1 2.4Ts 25 d7% -

2 2T*~ 2.2ss

' 2200 - 2. tie 2.iTe 2.13 6 f

2000

[ ins l .2ns l 3as -l atos J l . stes l . .eles- l 7/es - l ass l . siss .. j .1056 ' l .11/es - l 1246 l Data Provider. Laurie Hertdin 6944631

i l .

l OPERATOR EXAMINATION PERFORMANCE f' 100.0 %

Turkey Point Units 3 & 4 f 5RO/SRO Pass % l O Oper Reg Pass % l i

F

~

l j G$.0% . -; l l

l b -

l  !

l

' 8,

[ . '. hl  !

1

g a0% _: g S

l ik .

I

' E ( j

a. .

; l

(  !

t l l

1 l

85.0 % -' -

l  ;

' ' y I i  ;

' I ,

l a 8 =

p*

e3 e.4 Exams: -1991 -1992 t1993 1994 *1996

.1196 ; .2/96 ' 3/96' .4/96 5/96 6/96 7/96. 8/96 .' ' 9/96 . 10/96 11/96 12/96 1 d

RO/SRO Taken 39 5 . 8 13 . . . . . . . .

Pas. sed 39 5 - 8 13 . . . . . . . .

ROISRO Pass % 100 0% 100 0% 100 0% 100 0%

Ope < Reg Taken 47 78 69 63 68 . 64 . . . 19 . . . -

Passed 44 75 66 60 56 . 64 . - 18 . . - -

Oper Reg Pass % 94 0 % 96 0 % 96 0% 95 0% 96 5% 100 0% 95 0%

)

DEFINm0N ___

l l

Initial License Examination (RO/SRO) results are reported for all candidates taking an initial License Exam as conducted by the NRC.

Operator Requalification Examination results are reported for both RO's and SRO's. This examination is administered annually by the utility and may be jointly administered by the NRC. Retests of operators who failed examinations are not included.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Initial RO/SRO License Exams The NRC at their last Regional Training Managers Meeting No. Taken No. Passed Pass Rate %

0.0% (for fiscal year 1994) provided the following data:

YTD 1996 0 0 YTD 1995 13 13 100.0 %

Inital NRC Erams NRC Recual Exams RO's Pass Rate 94.6 % RO's Pass Rate 91.0%

Operator Requal Exams instant SRO's Pass Rate 94.4 % SRO's Pass Rate 85.0%

No Taken Pass Rate % Upgrade SROs Pass Rate 94.7% Average Overall 88.0 %

@. Passed Average Overan 94.6 %

YTD 1996 83 82 98.8 %

YTD 1995 58 56 96.5 %

PERFORMANCE

SUMMARY

l No exams were given at Turkey Point in October.

Data Provider. Maria Lacal(PTN) 2464476 E.1

OPERATOR EXAMINATION PERFORMANCE St. Lucie Units 1 & 2 100 0% -

. SRO/SRO Pass %

u Oper Rea Pass %

j e50%

j o iI I 99 0*4 Exams:

- RothRO Taken

'a ROI5RO nos %

T Oper Reg Taken 1991 100 S4 15 llbl 65 1992 100 87 6

69 1993. -1994 100 100 10 68 100 91 11 75

.1995 73

- 67 5%

~1/96. . :2/96 -

'3/95 100 4

'456 5/96 ' 6/96 7/96 ' ;B/96

.9/96 ' 10/96 11/96 l 12r36 OperReg ens %

DEFINITION d by the Initial Licence Examination (RO/SRO) results are reported for all candidates takin ll b NRC.

Operator Requalification Examination results are reported ldd for both RO'c and the utility and may be jointly administered by the NRC. Retests of operators who fail INDUSTRY PERFORMANCE STATISTICAL

SUMMARY

The NRC at their last Regional Training Managers Meeting Initial RO/SRO Ucense Exams (for fiscal year 1994) provided the following data:

100.0'4 YTD 1996 4 NRC Recual Exams 0 0.0% !nW NRC Exams 91.0%

YTD 1996 0 94.6 % RO's Pass Rate RO's Pass Rate 85.0 %

SRO's Pass Rate instant SRO's Pass Rate 94 4 % Average Overaa 88.0 %

Operator RequalExams UpgradeSRO'sPassRate 94.7%

-Pass Rate % Amage Oman s4.6%

No Taken No Passed 0 0.0%

YTD 1996 0 71 97.5 %

YTD 1995 73 PERFORMANCE

SUMMARY

No exams were given in October at St. Lucie.

l DataProvider. Mike Allen (PSL)467 4161 F .")

I l I

OVERDUE CONDITION REPORTS 100

--+-- PTN I I

90

-O- PSL _

Juno 90 g 70

\

8. 1 gE 60

.I E 50 \ O e

$ 40 \ /\

1

" \/ \

W

\ / \

O

. \M - %

0

\.. .

~1 Unit - :1991 1992 _1993 1994 1995 .1/96 ' .2/96 3/96 ~4/96 8/96' 6/96 7/96 9/96- . 9/96 10/96 11/96 12/96 PTN- 6 0 0 12 0 1 3 0 2 7 0 PSL- 95 25 51 0 8 19 29 29 13 15 Jimo u+ / 11 19 9 12 5 3 1 DEFINITION This graph shows Condition Reports that exceed assigned priority timeframe. This indicator takes a snapshot the last day of each month. Record the number of overdue condition reports the last day of each month.

Severity Levels are as follows: A = 3 working days B = 10 calendar days C = 30 calendar days STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE i

PERFORMANCE

SUMMARY

Data ProvideT (PTN) Ed Lyons 2464967,(PSL) J. Voorhees 467-7587, and Bob Symes (Juno) 6944287 F-1

l l

! QA FINDINGS 12 l

PTN k\ + Psl

• • • • "J""

10 -

i 8

) 4

, 1 a

j z6 4

i * .,

3 2

. ..4 ,

.. 4 . .

1 .

o 1

Unt -0 30 days . -[ 3140 days . - $140 days - "91-120 days - 121450 days - 1151-180 days . > 180 days .

- PTN 0 0 2 0 0 0 1

, PS6 ~ 11 5 0 0 2 0 2 A 0

.Jmo. 3 0 3 1 3 1 i

DEFINITION i

1 j The indicator represents the age of audit Fndings open as of the last day of the month. The clock starts on the day of the audit report transmittal and continues until Quality Assurance (QA) verifies that implementation has occurred.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE PERFORMANCE

SUMMARY

Data Providers: T. Abbabello (PTN) 246 6581 W Bladow (PSL) 467-7111. and R. A. Symes (June) 694-4287 F.7' l

i NRC VIOLATIONS Cited and Non-Cited (Year-to-Date) .

1 24 __--

1 a 22

..h.. 'PS NOVs r-20 ,

Vs for t o

/ / _ mi- ~

i . .

I ( . .w * ~  ;

i ,, .

l ." h* ~

1 ,,, s. +

..../.

.o '/ .-

1, \\ .

'l ! ..-

/ .i

) .:

\

1 ,,, .

J 4. -

• ~

i + ,/ [,/ ,'," 1996 Y E Target: 5 7 E 4

f , .+ f* 4 '

O ==C>==*

= = O\ _ f

\ -

Cd , y O'-

• Ci 0- . . , .

l

Unit 1991 1992 1993 1994 1996 1/96 2/96 -3/96 4/96 5/96 -6/96 ~7/96 a/96 9/96i 10/96 11/96 12/96 PTN NOV's 13 8 4 4 1 0 0 0 0 1 2 2 2 3 3 l

cPTNNCVs- 21 7 13 12 15 0 1 3 3 5 8 11 14 14 15 PSL NOV's - 8 8 7 9 21 1 4 4 8 9 0 17 20 23 23 PSL NCVs : 3 3 3 3 12 1 1 1 5 10 13 15 17 18 18 DEFINITION Notice of Violations (NOVs) c.re categorized in terms of five levels of severity to show their relative importance. Seventy Levels I and 11 are violations that involve actual or high potential impact on the public. Severity Level 111 Violations are causefor significant concem. Severity Level IV violations are less serious, but are of more than minor concem; i.e., if left uncorrected, could lead to a more serious concem. Violations are counted on the date of the inspection exit meeting. Violations are now counted with respect to the date of occurrence (using the date of the inspection exit meeting)instead of the date of the inspection report, as was done in the past.

Non-cited Violations (NCVs) are violations of NRC regulations for which no citation will be issued.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Oct YTD Year End Taroet NRC Violations PTN Cited 0 3 7 1995 IBG Group Mean 9.4 PTN Non-Cited 0 15 1995 Region 11Mean 10.5 PSL Cited 0 23 7 1995 IBG Top Quartile Mean 3.8 PSL Non-Cited 0 18 1995 IBG Top Quartile Entry 6.0 1995 Region 11 Top Quartile Entry 7.0 PERFORMANCE

SUMMARY

Turkey Point reported one Notice of Violation (NOV) in October for September. Year to-date, three NOVs have been reported.

St. Lucie reported three NOVs in October for September; eleven potential NOVs are pending investigation. Year-to-date, the total confirmed is 23.

See next page for details.

Data Providers- (PTN) Gary Holknger 2466078 Snd (PSL) Ed Weinka n 467-7162 F-3

NOTICE OF VIOLATIONS - 1996 TURKEY POIRT:

1 #E06-02 Preconditioning of EDG fuel system prior to surveillance test. Exit Mtg date: 6/14S6.

2 #9644-02 Fplure to follow Chemical Volume Control System Operating Procedure during a Unit 4 blender flushing evolution. Exit Mtg date:

5/15S6.

3#51103 Fire Zones 64 and 143 not covered by exemption to Appendix R. Exit Mtg date: 9/27S6.

ST. LUCfE:

1 #96-01 01 Temporary Changes to Procedures improperly Changed intent of Procedura. Exit Mtg Date: 1/26S6.

2 #96-03-01 Operators failed to follow procedures with four examples. Exit kig Date: 2/BS6.

3 #%03-02 Inadequate design controlof RCS boron dilution procedure. Exit Mtg Date: ?>8/96.

4 #96-03-03 A10CFR50.59safetyevaluationwasinadequate. ExitMtgDate: 2/%6.

5 #%0441 A containment gaseous /particulateliodine monitor was. rendered inoperable due to a failure to follow procedures, cambined with a lack of proper follow through on the part of non-licensed operators taking logs. Exit Mtg Date: 4/356.

6 #%04-02 Failures to make required log entries for reactivity manipulations and a main generator hydrogen addition. Exit Mtg Date: 413S6.

7 #E04-03 An EDG was rendered inoperable due to a failure to follow procedures whili placing the fuel oil tank on recirculation. Exit Mtg Date:

4/3/96.

8 #9644 04 Reviews of historical data for CEA maintenance revealed that post-modification testing acceptance enteria for Unit 1 CEA power cables were not applied to post-modification test data. Exit Mtg Date: 4/3SS.

9 #960645 An audit of fire brigade member qualifications resulted in a violation for failure to maintain current physica!s. Exit Mtg date: 5/1766.

10 #9649-01 Failure to control overtime. Exit Mtg date: 7/8S6.

11 #9609-02 inadequate procedure for managing overtime. Exit Mtg date: 7/8SS.

12 #%09-03 Failure to test the Reactor Cavity Pressure Relief Dampers in Accordance with the Vendor's Technical Manual. Exit Mtg date: 7/8S6.

13 #96 09 04 Failure to perforrn adequate testing on the Reactor Cavity Pressure Relief Dampers. Exit Mtg date: 7/8S6.

14 #96 09-06 Failure to control contaminated tools in acx:ordance with licensee procedures. Exit Mtg date: 7/8S6.

15 #%1104 Pre <x)nditioning of valves prior to surveillance. Exit Mtg date: 8/6/96.

16 #512-02 Failure to perform safety evaluation as required by 10CFR 50.59 for failure to recognize an unreviewed safety question in the development of a safety evaluation for an EDG fuel oil transfer line valve lineup change (Level 111). Exit Mtg date: 7/12S6.

17 #%12-03 Failure to coordinate design changes with the necessary changes to operating procedures as evidenced by three examples. Exit Mtg date:7/12/96.

18 #%12-04 Failure to assure that the design of the Circulating and intake Cooling Water System was correct!y translated into plant drawings.

Exit Mtg date: 7/12S6.

19 #%16-01 Failure to rnake a i hour security event notification to the NRC in iMaace with 10 CFR 73.71 and plant procedure 0006125 for the July 26,1996, tampering event. Exit Mtg date: 8/23S6 20 f961604 Failure to follow procedures for key control for the Unit 1 PORV key lexk switches. 5xit Mtg date: 8/23S6.

21 #96-13 01 Failure to indude some SSC's within the scope of the Rule in the Plant's Maintenance Rule Program (PASS, Communications, Service Air, Radiation Monitors). Exit Mtg date: 9/20S6 2' #51302 Failure to follow procedures in actions required by ADM 17.08 (multiple examples). Exit Mtg date: 9/20/96.

23 #96-13-03 Improper use of MPFFs as indicator of reliability for safety significant systems. hit Mtg cate: 9/20S6.

Potential Notice of Violations at St. Lucie for October were reported as follows:

1 #%15-04 Failure to follow procedure for the use of M&TE during Ni system work. Exit Mtg date: 10/12SS.

2 #96-1508 Failure to use or follow procedure resulting in the operability of the containment PIG radiation monitor (repeat violation). Exit Mtg date: 10/12S6.

3 #96-17 01 Violation of 10CFR Part 50, Appendix B related to implementation of PC/M's for nudear instrumentation and BEACON (3 examples).

Exit Mtg date: 10/13S6.

4 #%17 02 Failure of !&C personnel to write a Condition Report to address a discrepant condition related to implementation of a nudear instrumentation of a nudear instrumentation replacement PC/M. Exit Mtg date: 10/25SS.

5 #96-1801 Failure to maintain adequate provisions to implement staff augmentation rneasures for the emergency response organization. Exit Mtg date:10/28S6 6 #96-18-02 Failure to meet 10 CFR Appendix E in providing adequate training to identified members of the emergency response organization.

Exit Mtg date: 10/28S6.

7 #96-18-03 Lack of instruction in EPIPs for relocating to an attemate OSC, as identified in the E Plan. Exit Mtg date: 10/28S6.

8 #96-1804 Failure to e'fect timely corrective actions for Hurricane Erin. Exit Mtg date: 10/28S6.

9 #96-1941 Unauthorized access to the protected area and potential access to vital areas by a terminated employee. Exit Mtg date: 10/25S6.

~

10 #519-02 Events resulting in unauthorized access to the plant were not reported in accordance with 10 CFR 73.71/10 CFR Part 73 Appe G. Exit Mtg date: 10!25S6 11 #519-03 Procedures were inadequate in that unauthonzed individuals may have gained access to the plant. Exit Mtg.date: 10/25S6.

Data Providers: (PTN) Gary Holling* 246-6078 and (PSL) Ed Weinkam 467 7162 F.A

d i

i LICENSEE EVENT REPORTS (Year-to-Date)

< 25

-+- PTN '

1

-O- PSL 20 .

2

e.

i j 15 i

i, /,

l 3, 3 f

N 1

3 -

1 5 ^

1 0

Unit - 1991 *1992 1993 :1994 1995 :1/96 :2/96 ;3/96- ,4/96 5/96. .8/96 '7/96 9/96 9/96 10/96 11/96 12/96

. PTN 20 24 9 12 7 1 5 5 7 8 9 9 10 10 10 j PSL: 9 10 8 15 18 1 1 5 6 7 11 11 13 16 16 1

1 1

DEFINITION 1

l License Event Reports (LER) are submitted to the NRC by the licensee to report unusual occurrences prescribed by 10CFR50.73.

2 i STATISTICAL

SUMMARY

' INDUSTRY PERFORMANCE 4 Od WD j PTN 0 10 i '

PSL 2 18 i

J q PERFORMANCE

SUMMARY

1 i

i Data ProvideT (PTN) Gary Holknger 246-6078 8nd (PSL) Ed Weinkam 467 7162 F.S

O INPO ASSESSMENT RATINGS I

4 80 UT2 b 1

DPst 3 50 -

1 3 00 -

2.50

= .

f 2.00 - - .-

l E l 1 s0 _

I

- =- ===-

1.00 - -

0 50 - -

{

0.00 1987 - 1984 - 71989 '1990 ~1991 - 1992.- 1993 1994 1995 1996 UM: 1986 4 00 3.00 4 00 3 00 2.C0 2 00 . 1.00 l PTN 4 00 1m im 12 - 1m

.PSL .

INPO ASSESSMENT PROGRAM DESCRIPTION The Institute of Nudear Power Operations (INPO) conducts periodic evaluations of site activities to make an overall determinatinn of plant safety, to evaluate management systems and controls, and to identify areas needing improvement. Information is assembled from discussions, interviews, observations, and teviews of documentation.

l Eva!uation Frequency INPO's goalis to visit each plant on an average of every 18 months. However, this frequency may vary depending upon the previous assessment ratings. For instance, if a plant is rated a '1' or '2', the interval between assessments is usually 20-24 months; if a plant is rated a *4' or a '5', the assessment interval isj 18 months.

Performance Cateoory Ratinos:

Category 1: Overall performance is excellent. Industry standards of excellence are met in most areas. No sigrdficant weaknesses noted.

Category 2: Overall performance is exemplary Industry standards of excellence are met in most areas. No significant weaknesses noted.

Category 3: Overall performance is generally in keeping with the high standards required in nudear power. However, improvements are needed in a number of areas. A few significant weaknesses may exist.

Category 4: Overall performance is acceptable, but improvements are needed in a wide range of areas. Significant weaknesses are noted in several areas.

Category 5: Overall performance does not meet the industry standard of acceptable performance. The margin of nuclear safety is measurably reduced. Strong and immediate management action to correct deficiencies is required. Special attention, assistance, and follow up ane required.

NOTE: If a plant is found to be operating without an adequate margin of nudear safety, INPO will request that the plant be shutdown, or not l started up.

l PERFORMANCE

SUMMARY

I l

Turkey Point and St. Lucie received an INPO category rating of *1'in 1995. l The next evaluations for Turkey Point and St. Lucie are expected in the last quarter of 1996 and first quarter of 1997, j respectively.

Data Providem (PTN) Gary Holhnger 246-6078 and (PSL) Ed Weinkam 467-7162 F-6

i i

s i

i i i NRC SALP CATEGORY RATINGS

( 2.50 f

i e PTN Rating l 2.00 - - -

O PSL Rating 4

l

! En 1.50 - -

1 5 i e

! b M 1.00 - - = --

0.50 - - - ------

0.00 - --

4

-1986 t1987 .-19884 A1989 , 5.1990- s1991 -1992.. -1993e c;1994 s n19952 r1996 .

j PTN Rating - 2.27 2.18 2.25 2.14 1.86 1.38 1.29 1.00 - 1.00 Period Ending - 440/86 5/31/87 600/88 741/89 741/90 9/28/91 100/93 8/27/94 l - - 8/17/96 PSL Ranno " ' 1.55 1.20 - 1.29 1.14 - 1.00 - 1.00 - 1.50 Pedad Ending 4/30/86 10/31/87 - 4/30/89 10/31/90 5/2/92 1/1/94

- - - 1/6/96 1

SALP PROGRAM DESCRIPTION i

l

it is lhe polcy of tie NRC lo use the Systemabe Assessment of Ucensee Pertrmance (SALP) process e arnculate the agency's observabons and esghts on licensee safety performance The SALP report communcates those otearvabons and insghts.

Eviuluanon Freener The NRO will normdy review and evaluate each power rarer licensee Siat possesses an operattg license at least every 18 months. When the NRO determmes that I

the pertrmance warrants a rnore frequent evaluabon, tie normal SALP taturcy may be kicreased. The assessment pencd may be extenced e a rmumum of 24 montns when a plant j receives a Category 1 ranng m all four functonal areas.

Funceonal hear Pertrmance e generapy evaluated in bcr (4) hmcsond arer

1. Plaat Ocericons This funcnonal area consats chiefty of the o'mtrol and em # actnntes direc9y retaled b operseng a kant it meludes actvibes such as plant startup. imwer ogersbons, pant shutdown, and system imeups. It also includes iniha sid requalN termig of Econsed operators.

l' 2. Ereance The kmenonal area includes all achvibes associand wiin other 6 agnostic., y=rfcsve, preventve or correc6ve maintensice of plant structures, systems, and components, or mantenance of the physcal condiban or the plant i 1 Fweem This funcnonal area addresses the acequry of schncal and engmeenng support br all plant a:nvibes. It eicludes d Ecensee acevibes associated with design control; the j oesgn, mstallabon and tes6ng of plant moddicabons; engmeanng and schncs support for operatons, cutages, mantenance, testng, survedlance, and procurement acevtbes; i corifiguraban numagement cesgrubass informanon and its retnevat, and support for konsmg a2 vibes.

4. Ptant Succort The functwnd area covers all rtrr'tes felmed to plant support kmetons, sicludmg rahabgcal controts, emergency preparedness, secunty, chemistry, sid 6te protectun Housekeepmg controts are atso included in tus rea Pe6"1ance Ca'ewv P#nes: bcensee performance in each functonal area ' maassed s by assignmg a camgory raeng as docussed beloat

, Category 1. Lmensee attenton and mvoNement have been property ta:used cr' safety and resuhed in a supenor level cf safety performance j Camgary 2. Ucensee ettenbon aid mvolvement are normally well bcused and resumed in a good level of safety pertrmance.

Category 1 Ocensee attenton and involvement have resulted in an axwtable level of performance. However, performance rnay exhibit one or rnore of the followmg chara

tensbes:

l ineffeceve programs and sgni5 cant issues, lack cf conectve accan thoroughness, and deficiencies in root cause ar,alysis. Because the magm to unacceptable performance in important aspects a small, mcreased NRO and hcensee stienbon is requesd.

)

PERFORMANCE

SUMMARY

The Nuclear Regulatory Commissen issued its Systemate Assessment of Limnsee Performance (SALP) report for the Turkey Point plant for

, August 28,1994 through August 17,1996. For the second consecutive tme, the plant remived Category 1 (superior) ratngs in all four j functonal areas rated by the NRC ,

} Turkey Point St Lu:ie 4 Prior Most Recent Prior Most Recent i Functonal Area:

Plant Operatons 1 1 1 2

Maintenance 1 1 1 2 i Engineenng 1 1 1 1

{ Plant Support 1 1 1 1

Overa!t 1.00 1.00 1.00 1.50 j Data Prrmders: (PTN) Gary Holknger 2464078 and (PSL) Ed Weinkam 457-7162 F-7

INVENTORY VALUE ACCOUNT 154.300 60 70 --+- PTN

--O- PSL 60

?

h 60 5

C 1996 Y.E

7. N .

'N:  :

N Inget l 338tsu) l 2

E 30 E

to 10 o

Unit * : ;1991 1992 .1993 1994 1 996 :1/96 '2/96 ' 3/96 ' 4% '386 '646- J7/96 ' 8/96 9/96 10/96 11/96 12/96

• PTN " 791 74.7 54 6 42 4 37 4 37 4 37.2 36 0 35.1 34.9 35,1 35.3 35 1 34.9 34 5 PSL 58 6 65.2 60.2 43.7 33 4 42.0 42.3 43.5 42.9 43.6 41.3 42.7 41.3. 40.5 38 4 DEFINITION This indicator reflects the valve of Account 154.300. This account reflects materials needed to keep operational the physical equipment and facilities of the plant (e.g., spare parts, consumables, commodities, tools). The information is pulled from SAR 1 Report #G0009R72-501. The Passport system utilizes SAR for system data reporting.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE 3,taj End  % Chance YE Taroet IBG(Year 1995) ' Total Average $39.2 Million PTN Monthly 34.9 34.5 -1.1% . Top Quartile Entry $35.0 Million YTD 37.4 34.5 -7.8% $38M Top Quartile Average 129.0 Million PSL Monthly 40.5 38.4 -5.2%

YT-D 39.4 38.4 2.5% 538M 'Value does not include Capital as defined by PRUC PERFORMANCE

SUMMARY

. Turkey Point Regular inventory decreased by 50.4M in October, e St. Lucie's Regular Inventory decreased by $2.1M for the month.

Data Providers: (PTN) Dick Rose 246-6692 and (PSL) Gil B0asy 467 7582 G-1

r e

if OPEN PLANT CHANGES / MODIFICATIONS (PC/Ms)  !

l 350 I i

-*-- PTN '

-O-- PSL l l l 300 ' A i

250 y200 '

, 2 e

^

150 ~

l j i

100 EI!f EE

, Desgn: 24 40 i Re m 12 17 Working: 53 61 l 50 Update: 63 105 Total 152 223 l

l}

a O l

. Unit 1991 1992 1993 1994 1996 1/96. 12/96! 43/96, 4/96' :5/96 :6/96- 7/96 8/96 9/96 . 10/96 11/96 12.16 PTN- 240 242 230 219 170 170 155 153 157 152

-PSL' 31E 326 269 274 285 282 303 295 227 223

DEFINITION s

1

This indicator tracks the total number of PCM.s in the modification cycle. The purpose is to provide management a snapshot i of the number of PCMs. Include all PCMs in design (not issued to the plants) review (issued to the plants for review), and )

implementation or drawing update phases. The PCM is considered open until drawing update is complete.

J l l

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE j

1 4

i PERFORMANCE

SUMMARY

l 1

1 i

Data Providers: (PTN) Isidro Rioseco 2466184 and (PSL) David Brown 467-7048 TJ 1

.. . _ _ . _ . - ._. .___ -._ . ~ . _ . . . . . . _ _ _ . _ _ _ . _ _ .m.__.. . _ _ . _ _ _ _ s _ . - - _..___ _ _ ._ ~ . - _ . .

~

OPEN TEMPORARY SYSTEM ALTERATIONS 30

-*- PTN !

-O- PSL I 2s

^

g 20 e

C 4 O E 15 - -

2 5 E

0 10

^

0 .

- Unit - -1991 1992 1993' 1994 1995 dits t2f96  ; 3/96, 4/96 .8#96 ' 6/96 17tH, ;8/96 9/96 10/96 11/96 12/96

.' ' PTN .'.

S 5 2 3 6 3 3 J 0 0 0 PSL* 17 15 16 21 24 27 19 20 19 16 16 DEFINITION ,

A temporary system alteration is a modification made to plant equipment, components, or systems that does not conform with approved drawings or other design documents; a modification that is necessary for continued safe plant operation; a i modification that will remove a nuisance or distraction to the Plant Operators; a modification necessary to enable the plant to start upin a safe manner,  ;

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE g Year End Goal PTN 0 5 PSL 16 10 PERFORMANCE

SUMMARY

~

l l

l Data Providers: (PTN) Julio Balaguero 246-6971 and (PSL) Kns Mohindroo 467-7482 l H-2

- .. . _ . . . - - . __ _ ._ .. .- . . . - _ ~ .-...c.. - --

CONTAMINATED FLOOR SPACE 6000

--*- PTN

--O- PSL 5000 4000 i

3000 f

l 2000 ,

I 1000 0 __

Unit :1H1 ' 1992 1H3 1994 1995 1196 Mr ;3/96 *4/96: 25/96

. 6/96 '7/96 8/96 :9/96 10.96 11/96 12/96 PTN 1750 50 330 700 3748 32 559 77 1048 250 489 312 PSL 5610 4351 4600 2848 1480 250 200 12 12 4354 2725 800 50r. 242 540 DEFINITION This indicator, designed to measure contaminated floor space with removable activity 21000 dpm/100cm sq. beta / gamma or 2 20 dpm/100cm sq. alpha, is counted against the base. Areas that can be specifically exempted from the base include: reactor containment building, chemical volume control system demineralizer room and long term process areas such as the decontamination facility. Contaminated components such as charging pumps, evaporators, etc. are not included as part of ' recoverable" floor space (i.e. not considered floor area you can walk or step on).

PTN: Totaf Base (117,746 sq. ft) Exemoted Area (6,110 sq. ft)

PSL: Total Base (112,422 sq. ft) Exemoted Area (7,722 sq. ft)

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE

_Qc1 Taraet PTN 312 50 .

PSL 540 50 PERFORMANCE

SUMMARY

Turkey Point and St Lucie's Contaminated Floor Space was higher than the year-end target Data Providers: (PTN) John Undsay 246-6548 and (PSL) Hank Buchanan 467 7300 11

DRY ACTIVE WASTE: GENERATED, SHIPPED OFFSITE (Year-to-Date) 16000

. O PTN Guierated 16000 - * * + *

• PTN Shipped 0

---

o- PSL Generated

- - o- - PSL Shipped 1 o' 12000 ,

,,. _g-._g j /

u. 1000o sO 8000 ' /'.?'

o'

, .__- = - -4 4 n,- ,4 - $ = =

• W 0 - - ,

' Unit ' 1991 1992 1993 1994 :1995 *1/96 .2/DS ' '-3/96 4/96 '5/96 6/96- 7/96 .8/96 9/96 10/96 11/96 1 2/96

=TN oenerated 8100 425 515 3925 4115 4355 4675 5285 5415 5655 5775 P7N sNpped 2560 0 0 0 0 0 2560 2560 2560 4368 4368 PsL Generened 11740 0 820 1845 2595 7595 13040 14950 16060 16310 17470 rsL sNpped 13003 0 2030 3120 5314 7508 9702 11896 11896 11896 16284 DEFINITION Generated - Is an estimate based on the number of ' yellow bags' initially generated prior to surveying for free release or shipment as radwaste.

Calculation: Number of yellow bags x 5 cubic feet = Estimated Monthly Generated Waste figure.

Shipped offsite - The amount of dry active radioactive waste that FPL ships to either Scientific Ecology Group Inc. (SEG) or American Ecology Recycle Center (AERC) for processing.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE PSL made 6 shipments to SEGin 1995.

PTN made 3 shipments to SEG in 1995.

l PERFORMANCE

SUMMARY

SL Lucie shipped 4.388 Cubic Feet of Dry Active Waste in October.

Data Providers: (PTN) John Undsay 246-6548 and (PSL) Hank Buchanan 467 7300 1-2

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

_ . _ . . . . . _ . - . - . - , _ . . ___ . . _ _ . ._m_, __ . _ . .

PERSONNEL CONTAMINATION EVENTS (Year-to-Date) 180 160

--O-- PSL 140

, 120 1

v '

$ 100

^

O O ii 80 . l 8 l 1

0 60 l

40 l

20 0 .

-1992 1994 -1995. *1/96 '2/96 3/96- .4196 *5/96 i6/96- '7t96 ' 8/96. 9/96 10/96 11/96 1 2/96

C Unit.;' F '1991

.1993 95 100 73 4 9 23 32 36 38 43 47 52 54 163 85

.'cPSL-PTN 87 76 84 82 0 2 2 5 83 92 93 95 95 95 DEFINITION l

This indicator is designed to monitor personnel contamination. A personnel contamination exists when 5000 dpm per 100cm2 on skin or personal clothing as detected by Personal Contamination Monitor and >100 counts per minute (net) using the Friskeris observed.

1 STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE l 1

M Y-T-D PTN 2 54 PSL 0 95 l

PERFORMANCE

SUMMARY

i i

l l

Data Providers:(PTN) John Undsay 246-6548 and (PSL) Hank Buchanan 467-7300

! I-3

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

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

RADIATION EXPOSURE (Year to-Date) 1000 i -+-- PTN Y T D_

,gn

--0--PSL Y-T D 800

g 700

\

i tr.

I e

• y 600 e *

, y Ncte Sept 1996 numbers y sciusted to renect TLD data

= = -o a

aa .

1. PTN Y-E Target 275 ll N j 3 200 '  :  :  :  : e a

100

-/ a /:

o e s

/ --

'9196 10/96 11/96 12.96 Unit .- 1991 1992 1993 1996' ;1995 it96 ~ ' 2/96. .3196 " 8 4/96- t 5/96 ~ ' 6/96 ' '7/96 - --8/96 9.5 1592 165 5 1687 171.0 172 8 175 4 178.6 181 4

. PTN Y-T4 ' 938 0 324.9 281.8 476.2 214.6 6.3 3.0 90 13 0 21.9 209.2 321.9 371.3 374 6 377.4 381.5

• PSL Y-T D . 451.3 244 5 459 9 504.7 412 8 J

DEFINITION l

1 Collective Radiation Exposure is the total effective dose equivalent received by all on-site personnel (including contractors and

visitors), it includes extemal deep dose as measured by the thermoluminescent dosimeters (TLD's) plus intemal dose. It is l

' reported in man-rem for the station. Current month readings may be taken from the direct reading dosimeters (DRD's).

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE

.Qc1 31Q YTD Taroet Man-Rem 3.4* 181.4 265.0 WANO (PWR's) (two units)

PTN PSL 4.0* 381.5 468.0 1995 Median 306 1995 Goal 370 Year End Targets:

PTN: 275.0 PSL: 485.0 PERFORMANCE

SUMMARY

l

. Turkey Point and St. Lucie's Y T-D Collective Radiation Exposure totals were below Y-T-D targets.

1 l

l Data Providers: (PTN) John Lindsay 246-6548 and (PSL) Hank Buchanan 467 7300

• Includes DRD count T 4

i 1

l

, 'j. O&M BUDGET- DMSION (Year-to-Date) 350.0 l

---+--- Actual

,I

. . . . . . Budget 300 0 l ,

1

250.0 , l

..- 1

..- l E 200.0 j

, E

• 2 ..**,* \

y '

I

$ 150.0 ,, )

i

,e'

100.0 ,.

a' l 1

50.0 ,

, 00 l 7/96. .8/96 11/96 .12/96 1991 1992 '1993 :1994 '1995 .1/96 2196 - .t3/96 - + 4t96 : ' 619 6 . '6196 ' 9/96 - .10/96

. Actual - - 342.4 295.2 290.6 285.2 269.5 13.4 31.2 67.4 96.7 128.5 162.2 181.9 195 8 232.5 245.9 Sudget > . 333.3 314 6 326 4 302.0 279.2 17.8 36.7 75.8 104 8 129.6 147 4 1640 179 6 220.1 237.0 264.0 291.1 l l 1 vertence (%) < 2.7 6.2 t 1.0 -5.6 3.5 -24.9 -14.9 11.1 7.8 09 10.1 11.1 90 5.7 4.2 l DEFINITION Operating and Maintenance Expenditures indude Nuclear Division operation and rrdtanance expenses associated with  !

direct employees, contractors and consultants, equipment, tools, design, engineering and other items / activities required to I i sustain the electrical generation of the plants and to provide required support Fuel costs, corporate administrative and  !

general expenses, and charges from other departments outside the Nuclear Division are excluded. (

Y-T-D Actual Expenses - Y T-D Budaeted Expenses x 100% = O&M Variance % j 1

I Y T-D Budgeted Expenses STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Oct Y T-D Actual ($M) Y-T-D Variance ($M)  %

O&M Budget 1996 9.9 ($M) 4.2% IBG Actual 1995 Average $334.1M 246.9 ($M) 1995 -16.1 ($M) 7.1% IBG Top Quartile Entry $2T/.6M i 4 211.3 ($M) i IBG Top Quartile Average $234.2M 1996 Y-E Budget 291.1 ($M)

PERFORMANCE

SUMMARY

! O&M Expenditures through October 1996 were $246.9 million which represented a budget overrun of $9.9 million (or 4.2%).

l 3

Significant contributors to the variance include: St. Lucie Unit 1 outage scope changes partially offset by transfer of the Turkey Point Termal Uprate Project from O&M and by project and material purchase cancellations.

Data provider: Laurie Hertzlin 694-4631 J.1

_ _m. ._ _ _ _

6 l

l

, CAPITAL BUDGET - DIVISION (Year-to-Date) l 180.0 160.0 ', f --+--- Actual i

, l**- Budget l 140.0 ,

120.0 U

• k 100.0

=

8 80.0 . ..K .

60.0 40.0 ,,

20 0 ,,, ...- ,

O.0

• • • • f -

1991. .1992 '1993 1994 199s '1/96 72/96 :3/96 ^ 4/96 '5/96 6/96 7/96 8/96 9/96 10/96 11/96 12/96 Actual 150.7 68 4 90.3 76 6 47.2 1.5 2.5 2.9 6.3 9.3 12.1 12.9 15 7 164 21.5 Budget 179 6 75.1 101 4 87.7 64 7 48 7.1 11.1 15.7 17.9 19 8 22.6 26.3 17.8 30 1 33.1 39 2 Variance (*/.) 16.1 -90 11.0 12.7 -27.0 -67.6 -65 0 -73 7 -59 7 -47.7 38 6 42 8 -40 4 -40 9 28.3 I DEFINITION Capital Expenditures are those directly incurred / budgeted by the Nuclear Division for the construction of new utility plant

. additions and improvements made to increase efficiency, reliability or safety. Capital fuel costs are excluded.

, Y T-D Actual Expenses -Y-T D Budaeted Exoenses x 100% = CapitalVariance %

Y-T-D Budgeted Expenses l

l STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE i Oct Y-T-D Actual ($M) Y-T-D Variance ($M) $

Capital Budaet 1996 -28.3% IBG Actual 1995 Average $75.8M 21.5 ($M) 8.5 ($M)

-38.6% IBG Top Quartile Entry $42.6M 1995 31.4 ($M) 19.7 ($M)

IBG Top Quartile Average 327.2M 1995 Y-E Budget 39.2 ($M)

PERFORMANCE

SUMMARY

Capital Expenditures through October 1996 were $21.5 million which represented a budget underrun of $8.5 million (or 28.3%). Significant contributors to the variance include: Plant projects cancelled / deferred /or reclassified as O&M; and, underrun in the Steam Generator Replacement Project (SGRP).

Dataprovider LaurieHertzlin694-4631 32