ML20137N194
| ML20137N194 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie, Turkey Point  |
| Issue date: | 10/17/1996 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20137K821 | List:
|
| References | |
| FOIA-96-485 NUDOCS 9704080287 | |
| Download: ML20137N194 (57) | |
Text
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l }/)VO/5 i
i l FPL NUCLEAR DMSION l
l TURKEY POINT NUCLEAR STATION i
ST. LUCIE NUCLEAR STATION j .
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MONTHLY INDICATOR l REPORT I '
, September 1996 1
s Y
(7))1 Issued: October 17,1996 g40eg2e797o4o2 Bm ER96-485 PDR j
t_ _ _ - - - , -
lJ)VD/S l
l FPL NUCLEAR DMSION i
TURKEY POINT NUCLEAR STATION I l ST. LUCIE NUCLEAR STATION i
I i
l MONTHLY INDICATOR REPORT i
l September 1996 i 1 l
D)l Issued: October 17,1996 gg40egae797o402
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TABLE OF CONTENTS '
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Foreword . . D. PERSONNELINDICATORS Table of Contents . -..... i?
OSHA Recordacies.. D* !
Management Summary; -.- ir Lost Time innnes.. . D-2 Nuclear Division Business Plan Indicator Overview. s Regular Staffing., _ . ..D-3 '
NRC indicator Performance Overview Turkey Point.. v.
NRC indicator Performance Overview St. Lucia - v.i : TRAINING INDICATORS WANO Indicator Performance Overview. viii Operator Exam Performance Turxey Poin.. . EA WANO indicator Vanance Explanations ix Operator Enm Performance St. Lucie.. . ... .. . E 2 -
A. WANO INDICATORS F. NUCLEAR ASSURANCE & REGULATORYINDICATORS WANO Weighted Overal; Performance.. A-1 Overdue Conditon Recons.. . . F'
. Unit Capabihty Factor. . . A-2 QA Findings.. . .F2
. Unplanned Capability Loss Factor.. A.3 NRC Violat.ons: Cite and Non-Cited.. . .F-3 l Unplanned Auto Tnps Per 7000 Hours Cntca!.. A-4 Ust of Nobce of Violatons.. I
.. F l.
High Pressure Safety injection System Performance A-5 Licensee Event Reports (LERs).. F5 l Auxiliary Feedwater System Performance._ A-6 INPO Assessment Ratngs., .F-5 Emergency AC Power System Performance.. A-7 NRC SALP Category Rabngs = .F.'
Thermal Performance.. .. . A-8 Fuel Reliability. A-9 G. MATER!ALSINDICATORS Chemistry index.. A 10 inventory- G-1 Radiation Exposure.. A 11 ;
Low Level Waste.. A-12 H. TECHNICAL / ENGINEERING INDICATORS l Industrial Safety Performance.. A-13 Open Plant Changes / Modifications.. . H-1 Open Temporary System Alterations.. .. .H-2 B. OPERATIONSINDICATORS Equivalent Availabihty Factor., B-1 1. RADIATION PROTECTION INDICATORS 1
Capacity Factor (MDC Net) B-2 Contaminated Floor Space.. I" l
Fuel Utikzation (PTNL. B-3 Dry Active Waste: Generated. Shipped Off-Site.. . . 1-2 l Fuel Udlization (PSL).. . .. B-4 Personnel Contaminabon Events-- l-3 Forced Outage Rate.. B5 Radiation Exposure (Y T-D) = . 14 Unplanned Auto Tnes.. BS J. BUSINESSINDICATORS l C. MAINTENANCEINDICATORS- O&M Budget- Division J-1 i Open PWO's.. .. C-1 CapitalBudget Division-. J-2 PWO Aging Curve = C-2 PWO's Greater Than 12 Months Old. C3 Non-Outage PWO's.- C-4 APPENDIX Control Room instruments Out of Service.. .. C-5 Distribution Ust-- . .Z-1 I i
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MANAGEMENT
SUMMARY
OPERATING PERFORMANCE:
Equivalent Availability Factor performance in September was as follows:
Turkey Point Unit 3. Unit 3 EAF for the month was 87.6%. Power losses resulted from Control Rod failure (89.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />). Y-T-D EAF was 93.8% which is below the Y-T-D target of 95.0%.
Turkey Point Unit 4. Unit 4 operated at 98.0%; unavailability was due to problems with Feedwater valves (14.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />). For the year, EAF was 84.9% which is higher than the Y-T-D target of 78.1%.
St. Lucie Unit 1. EAF for Unit 1 was 67.2%. Power losses were the result of: repair to 1B Main Transformer (221.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />); Chemistry Hold (9.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />); 181 Waterbox leak (2.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />); Circuit Breaker repair (1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />); and leak repair to Dump Valve at 0-nng (0.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />). EAF performance Y-T-D was 62.4% which is below the 73.0% Y-T-D target.
St. Lucie Unit 2. Unit 2 operated at 99 3% with power losses attributed to: Turbine Valve test (0.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) and repair to Waterbox (4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />). Y-T-D EAF was 93.1% which is below the 95.0% Y-T-D target.
Nuclear Division. Equivalent Availability was 88.0% for the month and 83.6% Y-T-D which is below the 85.3% targeted Y-T-D. The year-end forecast for the Division is 86.3%.
A Summary of key plant operating statistics is summarized below:
No Unplanned Automatic Trips occurred in September. Year-to-date, one trip was experienced at Turkey Point Unit 3 in February.
A summary of key plant operating statistics is summarized below:
PTN Unit 3 PTN Unit 4 PSL Unit 1 PSL Unit 2
, Month Y-T-D Month Y T-D Month Y-T-D Month Y-T-D Gross Generation (MWh) 438.277 4.384,455 487.947 3.860.362 428,500 3.584.680 628.870 5.421,760 Net Generation (MWh) 415.364 4.173,119 464.431 3.670.718 398.566 3.371.047 596.225 5,128,989 Net Heat Rate (Btu /KWn) 11397.1 11043.4 11371.1 11222.7 11390.2 11105.9 11051.3 10931.7 Equrvalent Availabilrty 67.6 % 93.8 % 98.0 % 84.9 % 67.2 % 62.4 % 99.3 % 93.1 %
Capacrty Factor 86.6 % 95.3 % 96.9 % 83.8 % 66.0 % 61.1 % 98.7 % 93.0%
Auto Tnps 0 1 0 0 0 0 0 0 Forced Outage Rate 12.3% 4.5% 0.0% 0.5% 16.5% 4.1 % 0.0% 3.7%
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MANAGEMENT
SUMMARY
REGULATORY PERFORMANCE:
Turkey Point. No Notice of Violations (NOVs) were reconed in Septemoer. ' tear-to-date, two NDVs have been reponec.
St. Lucie. No NOVs were reported for Sectember, however, four NOVs were recorted for orevious months. (See Pace F-4 for list of confirmed Notice of Violations).
In addition. three potential NOV s were reported:
- 96-13 Failure to include some SSC's within tne scoce of the Rule h tne Plant's Maintenance Ruls Program (PASS. Communicaaons. Service Air. Radianon Monitors). Exit Meeting date: 9/20!96.
- 96-13 Failure to follow procedures in actions recuired by ADM 17.08 (multiple examples). Exit Meeting date: 9/20/96
- 96-13 Improper use of MPFF's as indicators of re" ability for safety significant systems. Exit Meeting date: 9/20/96.
Year-to-date, St. Lucie has reported 20 Notice of Violations and three potentials which are pending investigation.
COST PERFORMANCE:
O&M Expenditures through September 1996 were $232.5 Million which represented a budget overrun l overrun of $12.5 Million or (5.7%). Variance is primarily due to St. Lucie Unit 1 outage scope changes l partially offset by underruns on the Turkey Point Thermal Uprate Project and by project and materials l purchase cancellations. ;
1 Year-to-date, O&M budget performance variances are stratified as follows:
Turkey Point Site Specific $7.2 Million(or 8.0%) below budget i
$23.2 Million (or 26.4%) above budget l St. Lucie Site Soecific
- Other Nuclear Division $3.5 Million (or 8.3%) below budget Capital Expenditures through September 1996 were S16.4 Million which represented a budget underrun of $11.4 Million or (40.9%). Variance is primarily due to:
Year-to-date, O&M budget performance variances are stratified as follows:
Turkey Point Site Specific $2.0 Million (or 85.6%) below budget St. Lucie Site Specific $6.8 Million (or 30.0%) below budget l l
Other Nuclear Division $2.6 Million (or 89.5%) below budget l
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NUCLEAR DIVISION BUSINESS PLAN INDICATOR OVERVIEW (Through September 30,1996) 1996 1996 1996 YE YTD YTD INDICATOR PLANT TARGP TARGET ACTUALs COMMENTS Collective Radiation Exposure PTN 52! ' 5 260.0 178.6* Turkey Point and St. Lu:ie were below YTD Man-Rem targets.
PSL 5 485.0 5 460.0 377.1* Current rnontn includes DRD count PTN 1.00 1.00 For the second consecutive time, PTN received supenor NRC SALP Ratings ratings (1.00) in all areas for tne SALP penod ending 8/17/96.
PSL 1.50 1.50 The SALP penod for PSL ending 1/6/96 was 1.50 PTN 57 2 PTN had no NOVs in Sept.: Y-T-D, two have been reported.
NRC Violations PSL 57 20 PSL reported four NDVs in September for July; Y-T-D,20 NDVs been received.
PTN3 53 1 Unplanned Automatic PTN4 for 0 No unplanned automatic tnps were reported in September.
Trips PSL1 Division 0 PSL2 0 Budget Performance Capital 39.2 27.8 16.4 Capital Y-T-D actuals were below the Y-T-D target.
($ Millions) O&M 288.9 220.1 232.5 O&M actuals exceeded Y-T-D target pnmanly as a Div. Total 328.1 247.9 248.9 result of PSL's outage scope changes.
PTN3 95.0 95.0 93.8 PTN Unit 4 performance Y T-D through September Equivalent Availability PTN4 82.0 78.1 84.9 was higher than the Y-T D target.
Facior(%) PSL1 78.5 73.0 62.4 For the Division, EAF Y-T-D was 83.6% which is below PSL2 95.0 95.0 93.1 the 85.3% Y-T-D target.
Division 88.0 85.3 83.6 M&S Inventory Levels PTN 5 38 34.9 PSL exceeded the Year-End targ<. C $38.0 (5 Millions) . PSL 5 38 40.5 $2.5M in Septernber.
Production Cost (O&M PTN 1.75 1.82 1.85 PTN and PSL Production Costs (#lKWh) were higher than b PSL 1.55 1.64 2.15 Y-T D targets in September.
and Fuel) l Tota! Cost (O&M, Fuel & Division In September, Division Total Cost (#/KWh) was higher Capital Carrying Costs) Total 4.56 4.80 4.99 that the Y T D target.
Nuclear Division FPL 2045.0 1818.0 Total Nuclear Division Staffing Level was below the Staffing Levels LTC 463.0 338.0 Year-End target.
Total 2508.0 J J, 2156.0 Refueling Outage Duration (Days)
PTN3 PTN4 NA 45 N[ 0 35 Future refueling outages are as follows:
PTN3 03/08/97 PSL102/03/98 PSL1 63 88 PTN4 09/15/97 PSL2 04/15/97 PSL2 NA M 0 Source: Fuel Cycle Length Operating Schedule of 2/8/96 Lost Time injunes per 200,000 PTN 0.30 0.14 No Lost Time injuries were reported in September.
Hrs. Worked (12 Mo. Running) PSL 0.30 0.25 v
NRC INDICATOR PERFORMANCE OVERVIEW for Turkey Point (Data thrcugh Quarter Ending Septemb::r 30,1995) l 7 m: Deviations From Peer j P: ant Serr. Trend FTN g Grogo Me1,7 Lea 1_TC Srmr' Te-PTN4 g improve: worse Sene-Decnned OPERATIONS c:
M c 72
- c
- .c;? P Automate Scrams While Cntca:
OC C2 M
Safery System Actuations 0L M 0#
I OC l Stanificant Events 4 as c27 E 0; i
Safety System Fanures 020 bl CAUSE CODES (all LER's) 4 12 [ .ocefl Administraave Control Problem c: .c 11 cc 418 N oe oo
'icensed Operator Problem "
05 .oo Other PersonnelError 4 14 g goc
, o.c 0 14 Maintenance Problem 409 E 0.2'~
i 0.0 R 0C Design /Constructon/Installacon Fabrication Problem 0.C o0 0.C 00 Miscellaneous l
SHUTDOWN _
0h4 l g kio 0.0 0.78 W sj Safety System Actuatons o.0 0.0 5 40 o.57 Significant Events 0 51 0.53 Safety System Failures _ _ _ es 2 40 ,
.n y gr; CAUSE CODES (an LER's) c;:-
iot
.o.30 IE"1
% 0 25 Administratve Control Problem 00i i 0.0 '
.o sc E cos Licensed Operator Problem 100 417El ioo [] c ic Other Personnel Error l 005 .o 12 Ei Maintenance Problerr # #a,,e 1 20 T C 1:
- i 0.0 -0.03J f' y . .a1erm %l -o go .o os y Design /Construccon/Instahation Fabncation Problem ~
iOO .CC ioe iee M:scellaneous ,
FORCED OUTAGES e.06 l o.04 o.05 4 03 Forced Outage Rate
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0 07 Eauipment Forced Outages /1000 Comrnercial Hours ' 026 4 37 i 1.0 05 00 05 1.0 10 0.5 00 05 10
- Not Calculated for Operational Cvde Performance index Performance inder NOTES:
Plant Se0 Trend Short Term: Based on the slope of a linear regression line plotted over eacn piants data Time intervais used in tne trends are 4 Quaners for ' Operations
- and ' Forced Outages' indicators and 6 Quaners br 'Shutsown' indicatos Deviations t'em Peer Groue Med;an Lono Term: Compensons are made of each plant to the im unaus af its pee:s over a 12 Quarter Dme interva!.
Peer Grous PTN 3&4. Older Westingnouse 34.000.
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NRC INDICATOR PERFORMANCE OVEitVIEW fer St. Lucie (Data through Quarter Ending September 30,1995)
_ LEGEND -
PSL 1 M Piant Self-Trend Deviat: ens From Pee-PSL2 c gno,; 7,,7, Grouc Meetan Lon: Tem OPERATIONS Declined imoroved worse Bette-c; Automatic Scrams While Cnaca
.c.56 g qou Safety System Actuabons cc ose lw, ,,
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0.C cc Significant Events oc oe 00 g c2:
Safety System Failures oe +,n - l c e CAUSE CODES Tall LER's)
Administrative Control Problem h 22 Ucensed Operator Problem o 0 68 t
0 64 <00
, Other Personnel Error 00 ,,pg ,_, 10 72 l
Maintenance Problem 0 48 E q 028 g o 14 ss 02s 025 0 40 l Design / Construction /Installaton Fabncaton Problem 10.0 a:n 04a Oc
-0.18 E Miscellaneous 0c ,
l 1045
, SHUTDOWN i Safety System Actuations 10.0 ME -0.15 x i
'00 03 Significant Events i o.0 ioo
}
n 0.22 ~El Safety System Failures 00 Muw4 1.34 CAUSE CODES (aH LER's) 4 5 011 -0.06 I Administrative Control Problem
!co wui 044 i 0.0 10.0 Licensed Operator Problem 10.0 0.30 non i
3 0.15 0.14 g i Other Personnel Error 10 0 1 0.08 4
Maintenance Problem 3m i00 020 g 1 0.12 g 020 .
- Design / Construction / installation Fabrication Problem i o.c e 027
- i 0.0
( 0.0
- Miscellaneous 10.0 100 i FORCED OUTAGES 4.10 g Forced Outage Rate - 60 W 049
{ M 0.82
- Ecurpment Forced Outages /1000 Commercial Hours
- i0 $ 013
, 10 -05 oO C.5 1.0 1.0 -0.5 00 05 to i
- Not Calculated for Operat onal Cycle Performance index Performance Index NOTES:
I
. Plant SeK. Trend Short Term Based on the slope of a knear regression hne plotted over each plant's data Time intervals used in the vends are 4
. Quarters for ' Operations' and ' Forced Outages' indicators and 6 Quarters for 'Snutoown* indicators.
! Dev:atons from Peer Group Median Lono Term: Compansons are made of each plant to the performance ofits pees over a 12 Quarter ome interval.
Peer Groucs- PSL 1&2 Combuston Engineenng witn core protecton calculator piants J, Vil j
. - ..- . . =._
WANO OVERALL INDICATOR PERFORMANCE OVERVIEW (September 30,1996) l l Industry Median Value: * '
Unit or Station Values l 3.Yr. Distribution l 2000 '
PERFORMANCE INDICATORS PTN 3 PTN 4 PSL1 i PSL 2 ! (1993 1995) Goals I I j Unit Capability Factor (Unit %. ,
3-Yr. Distribution End!ng Septemoer '96) 88.4% 89.5 % 77.0% 81.4% l 81.2 % i S7.0% l I
Unplanned Capability Loss Factor (Unit %.
3-Yr. Distribution Ending September 96) 3.7% 3.0% 15.3% 8.1% 5.25 l 3.0; i Unplanned Automatic Scrams Per 7000 Hours Critcal(Per Unit l 0.6 0.5 1.6 ! 0.6 0 :.0 3-Yr. Distribution Ending Septemoer'96)
High Pressure Safety injection ,
0.009 0.009 0.026 0.009 0.003 - 0.005 nc:
System (per Unit 3-Yr. Distribution f
s Ending Septemoer's ,,
available l 6
g Auxiliary Feedwater System l (per Unit. 3-Yr. Distnbution 0.013 0.010 0.009 0.013 0.004 - 0.009 not available fa Ending September'96)
Emergency AC Power system cer Unit,3-Yr. Distribution 0.006 0.003 0.019 0.013 0.007 - 0.012 not jending September'96) available Thermal Performance (Ratio of Design to Actual Gross Heat Rate,(1-Yr. 100.1 % 99.0% : 98.8% ~ .98.7% 99.5% "* 99.5%
Distribution Ending September'96)
Collective Radiation Exposure (Man-Rem per unit per year,3-Yr. running 149.0 149.0 ' ~217.7 > Y217.7 153.0 120.0 avg. ending September'96) l Volume of Low-level Solid Radioactive Waste (Cubic meters per unit per year, 31.0 31.0 -54.1 ' 54.1 47.0 45.0 l
l 3-Yr. avg. endtng September '96)
Chemistry index (12-mo. weighted average through Seotember'96) 1.03 1.05 1.17 1.17 1.18 " 1.10 l Industnal Safety Lost Time Accident l
Rate (Station rate per 200,000 man- 0.014 0.025 0.55 " 0.40 l -
hours worked ending September'96)
(
Fuel Reliability (Unit microcuries/g, Fuel Defect Reference not mtine endm September'96) 1.00E-06 4.48E-06 1.99E-06 7.71E-05 5.0E-04 "* available UTE: Shaded area cenotes FPL oerformance is unfavorable to actualindustry rned;an Source ofIndustry Data
- 1995 Year-End Report for Performance Indcators for the U. s. Nucear Utitty incastry (1993-1995 Detaduton;
" 1995 Year-Erid Report for Pertonnance inacators for tne u. s. Nuoear Utdity industry (1995 Detnbunony
"* 1995 Year-End Report for Pertormance inacators for the u. s M;oear untity inaustry (4.95495 Ostneubom Vili
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'WANO OVERALL INDICATOR PERFORMANCE OVERVIEW Discussion of FPL Performance Unfavorable to Industry Median
, (September 30,1996)
UNIT CAPABILITY FACTOR (3 Years Ending 9/30/96)
St. Lucie Unit 1. The 3-year running Capability Factor for the unit 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 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%); 1 A2 Reactor Coolant Pump seal repairs
, from 8/2/95 to 8/9/95 (0.7%); inoperable Power Operated Reu e f Valves from 8/9/95 to 8/17/95 (0.7%); and, 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 Factor loss.
UNPLANNED CAPABILITY LOSS FACTOR (3-Years Ending 9/30/96)
St. Lucie Unit 1. The Unplanned Capability Loss Factor for the three years ending 9/30/96 was 15.3% compared to an industry median of 5.2%. 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%); 1 A2 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%); 1A 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,1B Main Transformer repairs (0.8%). Other miscellaneous unplanned 4
outages and derates accounted for the remaining 3.5% Capability Loss.
St. Lucie Unit 2. The Unplanned Capability Loss Factor for the three years ending 9/30/96 was 8.1%. 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 for Hydrogen Cooling System Valve and 2C Auxiliary Feedwater Pump repairs from 6/6/% to 6/13/96 (0.7%). Other unplanned outages and power reductions accounted for the remaining 3.7% in Capabilrty Loss.
4 UNPLANNED AUTOMATIC SCRAMS PER 7000 HOURS CRITICAL (3-Years Ending 9/30/96)
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.
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- NRC INDICATOR PERFORMANCE OVERVIEW for Turkey Point (Data through Quarter Ending September 30,1995) uw I
i
. PTN3 Pl ant SeILirend Deviaucr.s Fro n Per
$aar Te- Group Messa Lea 9 Tr PTN4 [
i OPERATIONS De:nned imoroved worse sene-M7; c;
- Automate Scrams While Cnuca .0
- c;2 ['~~l 0.C Safety System Actuatons 0: c' 00 00 M 00 Sionificant Events .
l 4 33 g 427 g Satety System Failures -023 2*l C;
, CAUSE CODES (all LER's) 012[ o; -0 c6}i
! Administratrve Control Problem -c 1i 1 00 018 ll f Licensed Operator Problem 0t -
0c 0.0 0Tf
- Other Personnel Error 00 ~
0t 0 14 g -
oc
< Maintenance Problem 4 14 e _ 0.c Design /Construccon/Installation Fabrication Problem i o.0 R 0C a
0.0 0C Miscellaneous 00 0c
- SHUTDOWN ua sca l
' Safety System Actuatons 0.0 0.78 erdest2l 00 0.0
! Significant Events 5 40 457 ml
. 4 51 -0.53 Safety System Failures 2 40 m g CAUSE CODES (an LER's)
- 60.0 03 Administratve Control Problem 0.30 O Wo.25 10.0 0 01
~
Licensed Operater Problem -0.30 WE 4 06 :
10.0 017El Other Personnel Error 100 1 0.10 10.c5 012 t_ i Maintenance Probierr w " ,te 12c Dc1:
10.0 403J j Design!Construccon!)nstaliabon Fabncadon Problem W maa mml -0 90 -0 08 LI iOO '00 M:sceltaneous i0c ,
i00 1
FORCED OUTAGES 0.06 l 0.04 0.05 4 03 Forced Outage Rate . .
0 64 -007 Equipment Forced Outages!1000 Commercial Hours
- 026 4 37 i
-1.0 -0. 5 00 05 10 1o -0.5 00 05 1.0
' Not Calculated for Operational Cveie Performance index Performance index NOTES:
Plant Sek-Trend Short Terr Based on tne slope of a linear regression hne plotted over eacn plants data. Time intervats used in tne trends are 4 Quaners for ' Operations
- and ' Forced Outapes' indicators and 6 Ouaners for ' Shut:kwn* indicato's Deviat ons from Pear Groue Median Lono Term: Compansons are made of eadi plant to the performance of its peers over a 12 Ouarter tme interva!.
Peer G"JUDs PTN 3&4 - Older Westinanouse 34.ocn N
4
NRC INDICATOR PERFORMANCE OVEiRVIEW for St. Lucie (Data through Quarter Ending September 30,1995)
LEGEND PSL 1 P; ant Se!f-Trend Deviations From Pee-
- PS. 2 E Sho"t Terr, Group Mec:an Lone Ter OPERATIONS Declined imoroved Worse Bette' 01 0.56 Automatic Scrams While Cnaca' s 26.- l 0 54 _ I"" 01!
_ -0.36 El )rd 0.90 Safety System Actuatons OC 0.90 .< l 0.C 0C Significant Events 0C '? C 0c 3 0.22 Safety System Failures 0C se 1-10 67 CAUSE CODES Vall LER's)
O K-Administrative Control Problem _ gacg ..i o 3:
-or M 022 Licensed Operator Problem 0t ,
t 0 68
-064 0.0 Otner Personnel Error 00 c,::_s 10 72 Maintenance Problem 76 7 0.2e El.28 w 0 l 025 0C Design / Cons sction/ Installation Fabrication Problem i 0.0 c rc 0.0 i
' OC 0.18 M l Miscellaneous 00 I . r- l 0 45 i
l SHUTDOWN ,
Safety System Actuatons ! 0.0 ME -0.15 g I
- 0.0 0.0 i Sgnificant Events i00 10.0 i 0.22 4 01
, Safety System Failures 00 1.34 *stwr -s 1
CAUSE CODES (all LER's)
Eou 0.06 I 1 Administrative Control Problem i 0.0 w0a j 100 100 l' Licensed Operator Problem 100 0 30 le 3 0.15 0.14 g Other Personnel Error ' 0.0
_ r10.08 E C 09
- 00
-020 E Maintenance Problem R 012 3 020 o Design / Construction /Installaton Fabncation Problem too e or
! 0.0 600 Miscellaneous t 0.0 10.0 FORCED OUTAGES 410 g Forced Outage Rate
- io agral 049 l Eauipment Forced Outages /1000 Commercial Hours
- 10
'M -0.s2 I B 0.13 1
-1.0 -0.5 00 0.5 1.0 -10 -0.5 0.0 0.5 1.0
' Not Calculated for 0 eratonal Cycle Performance index Performance Index NOTES: 1 Ptant Self-Trend Short Ternt Based on the slope of a linear regression line plotted over each plant's data. Time intervals used in the trends are 4 Ouarters for ?Opetatons' and ' Forced Outages' inde.ators and 6 Quaners for
- Shutdown
- indicators.
Deviations from Peer Group Medten Lono Term: Compansons are made of each plant to the paiu nids of its peers over a 12 Quarter time interval.
Peer Grog [ PSL 1&2 - Combuston Engineenng witn core protec00n cacitator piants Vll
WANO OVERALL INDICATOR PERFORMANCE dVERVIEW (September 30,1996)
- ' l Industry Median Valuer. * '
Unit or Station Values l 3 Yr. Distribution l 2000 PERFORMANCE INDICATORS PTN 3 PTN 4 PSL1 i PSL2 ! (1993-19951 Goals 8 Un;t Capability Factor (Unit %. I I
, i 3-Yr. Distribution Ending Septemoer '96) 88.4 % 89.5 % 77.0 % 81.4% l 81.2 % i 87.0% l I Unplanned Cacability Loss Factor (Unit %. !
3-Yr. Distribution Ending Sectember '96) 3.7% 3.0% 15.3% 8.1% 5.2L l 3.05 ,
j
! i Unplanned Automatic Scrams Per , ,
7000 Hours Critical (Per Unit I 0.5 Of 1.6 ! 0.6 0.9 '0
.. 4 3-Yr. Distribution Ending Septemoer'96)
' i High Pressure Safety in.iection System (per Unit. 3-Yr. Distribution 0.009 0.009 0.026 0.009 0.003 - 0.005 nc:
i l Ending September'95) availaDie !
j Auxiliary Feedwater System iv (per Unit,3 Yr. DistnDution 0.013 0.010 0.009 0.013 0.004 - 0.009 not l
j Ending September'96) a Emergency AC Power system available i
'oer Unit,3-Yr. Distnbution 0.006 0.003 0.019 0.013 0.007 - 0.012 not lending September'96) available Thermal Performance (Ratio of Design '
to Actual Gross Heat Rate,(1 Yr. 100.1 % 99.0% ' 98.8% ~ .98.7% 99.5% ~ 99.5 %
Distribution Ending September'96)
Collective Radiation Exposure (Man-Rem per unit per year,3-Yr. running 149.0 149.0 117.7 ^ t217.7 - 153.0 120.0 avg. ending September'96)
- Volume of Low-level Solid Radioactive Waste (Cubic meters per unit per year, 31.0 31.0 - 54.1 '54.1 47.0 45.0 3-Yr. avg. ending September '96; Chemistry Index (12-mo. weightec average through Sectember'96) 1.03 1.05 1.17 1.17 1.18 " 1.10 industnal Safety Lost-Time Accident Rate (Station rate per 200,000 man- 0.014 0.025 0.55 " 0.40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> worked ending September'96)
Fuel Reliability (Unit microcuries/g, Fuel Defect Reference not month enCg September'96) 1.00E 06 4.48E-06 1.99E-06 7.71E-05 5.0E-04
- available i NOTE: Shaded area denotes FPL oerformance is unfavorable to actualindustry med:an Source of Industry Da'a
- 1995 Year End Report for Pettman Indcators for the U. s. Nuclear Uttr:y incusty (1993-1995 Distnbutoni "1995 Year-End Report for Pertorrnance indcators for the U. s humea" Utskty n1ustry (1995 ostnbunon).
'" 1995 Year.End Report for Perforrnance Inocators for the U. s Nuoear Uti.ty incustry (4!95495 ostnbuborn viii
1
~ WANO OVERALL INDICATOR PERFORMANCE OVERVIEW Discussion of FPL Performance Unfavorable to Industry Median (September 30,1996) 4 UNIT CAPABILITY FACTOR (3 Years Ending 9/30/96)
- St. Lucie Unit 1. The 3 year running Capability Factor for the unit was 77.0%. Capability loss is attributed to the i
following: 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%); Ouench Tank leak repairs from 2/27/95 to 3/8/95 (0.9%); 1A2 Reactor Coolant Pump seal repairs j 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%); and, 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 Factor loss.
UNPLANNED CAPABILITY LOSS FACTOR (3 Years Ending 9/30/96)
St. Lucie Unit 1. The Unplanned Capability Loss Factor for the three years ending 9/30/96 was 15.3% compared to an industry median of 5.2%. 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%); 1 A2 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%) 1B2 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,1B Main Transformer repairs (0.8%). Other miscellaneous unplanned outages and derates accounted for the remaining 3.5% Capability Loss.
St. Lucie Unit 2. The Unplanned Capability Loss Factor for the three years ending 9/30/96 was 8.1%. 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 for 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 3.7% in Capability Loss.
UNPLANNED AUTOMATIC SCRAMS PER 7G00 HOURS CRITICAL (3 Years Ending 9/30/96)
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.
ix e-.
HIGH PRESSURE SAFETY INJECTION SYSTEM i (3 Years Ending 9/30/96)
Turkey Point Unit 3 and 4. Average oenormance was afiecteo oue to tne on-iine rectacement of tne H3S: ourt motors following discovery ot cracKeo rotor cars. i l
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 23 HPSI oumo in tne 1st Quaner of 199E St. Lucie Unit 2. In the 1st Quaner of 1995, average performance was affected as a result of Component Cooling i Water (CCW) Heat Exchanger cleaning which placed the respective HPSI puma OOS due to lack of dedicated seal I cooling.
^
{
4 !
AUXILIARY FEEDWATER SYSTEM l
(3 Years Ending 9/30/96) j Turkey Peint. Units 3 & 4. Average performance for botn units was affected by the B AFW Turoine failure in tne 4tn Quarter of 1994 due to makunction of tne mechanical overspeed trip device; in tne 3rd Quaner of 1995, performance
, was affected by: Part 21 reoairs on the Trip and Trottle Valves, and Unit 3 outage work.
Note: Turkey Point's Auxiliary Feedwater System is configuratively unique because it is a snared system between two
- units. For example, dunng 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 affected by failure failure of the AFW PP 2C Steam Admission Valve MV-0813 to open, a mechanical trip linkage for AFW PP 20 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 Ending 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 nm which closed off fuel to the 12 cylinder engine in the 2nd Quarter of 1995,1B diesel 12 cylinder engine valve f ailure in the 3rd Quarter of 1995, and 1B diesel -
due to replacement of the cooling water valves in the 4th Quarter 1995.
l St. Lucie Unit 2.. Unit 2's average performance increased to .013 for the 3-years runing average as a result of failure of the governor Actuator Speed Changer during the cooldown idle period following monthly surveillance run.
4 COLLECTIVE RADIATION EXPOSURE - MAN-REM (3-Years Ending 9/30/96)
St. Lucie. Coliective Radiation Exposure three year running average level for St. Lucie was 217.7 Man-Rem per unit which was greater than tne industry median of 153 Man-Rem. Site performance was influenced by unplanned and scheduled outages.
VOLUME OF SOLID RADIOACTIVE WASTE (Annual Avg. for 3-Years Ending 9/30/96)
, St. Lucie. Volume of Solid Radioactive Waste for tne 3-year annual average was higher than industry median due to 1994 waste volume; tne 1995 value of 41.9 cubic meters was below the median value.
X
. . - . _ _ _ . . . = _ _ _ - _ . _ . . - .. . . . . . _ . - . - . . . _ - . . .. . . . - . _ _ .
WANO WEIGHTED OVERALL PERFORMANCE a
100 0 )
l s
y %. . . . w - - 4 e- ? - -
90 0 80 0 ,0, \ ;#
- g_*'"
O- 0 . . . o, . . .O O 7 ,.
- ~ ~ .c g ,,', ; , :, ..c o. . . o h . <
,$ 4 60.0
/ PTN 3 .
- . . + . . PTN 4 i 50 0 NOTE PTN Aug ca's sowste --O - PSL 1
' snowy cue to Raa,atso- . O = = PSL 2 l
- Exposure aw Raoweste Discosa. _. Industry Avg i 1
mustmeans 40 0 Unit 1991 1992 1993 1994 1996 it96 2/96 3/96 4/96 6/96 6/96 7/96 6/96 9/96 10/96 11/96 12/96 PTN 3 57 5 65 7 88 8 85 0 90 9 95 0 93 8 92.7 93 1 94 1 94 2 94 3 94 4 94 4 i PTN4 45 8 64 0 87 0 86 8 93 8 94 8 95 1 93 7 94 5 94 8 95 C 94 7 94 9 94 7 PSL1 52 6 75 0 82.7 76 3 63.3 67.1 67.7 70 5 69.3 67.1 65 8 64 4 64 4 66.7 PSL 2 71 6 30 9 70 9 67 5 74.0 71 8 73.5 75 5 80 0 79.1 77.9 77.9 78 1 78 1 andustryAvg n/a n/a 76.2 80.1 82 0 DEFINITION The WANO Overall Performance Index is a composite indicator utlized to trend nuclear station performance. The index is a weighted combinatier, of tne following 10 individual performance indicators over the time period noted: 4
- 1. Unit Capabihty Factor (16%) (2 yrs)* 5. Emergency AC Power (9%)(2 yrs)* 9. Thermal Performance (6%)(1 yr) j
- 2. Unplanned Capability Loss Ftr (12%)(2 yrs)* 6. Unplanned Auth(8%)(2 y s)* 10. Cherrustry indicator (6%)(1 yr) j
- 3. High Pressure Safety injection (9%)(2 yrs)* 7. Collective Radiation Exposure (8%)(2 yrs)* 11. Low-level Radwaste Volume (5%) (2 yrs)*
- 4. Auxikary Feeowater Systern (9%)(2 yrs)* 8. PWR Fuel Reliability (7%)(most recent atr) 12. Industnal Safety Accidents (5%)(1 yr)
- Calculated for a two y' ar penod instead of the normal three year penod to allow the index trend to be more responsive to changes in plant performance.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE WANO:
Through 4tn Quarter 1995. Industry Median: 82.0%
PERFORMANCE
SUMMARY
Data Provider Sha on Bilger 694-4255 A.1
UNIT CAPABILITY FACTOR
, (3 Year Running Average) 100c 94 C 90 0 . _ A. 4 w .9 vms-.s.t E rg
/.<
...5 - ..- .
85 c -
-# ~
0 - . c> M , . . . m . . . n . . .e
& 2l0 2. . . =' . [. . . = a p ,, ,
f 70.0 j o...c -
E 65 0 i p.* c
+ PTN 4 PTN 3 60.c -
/ --O-- PSL 1 55 o / **O*-Pe"
. IndustN Av- l 60 0 45.0 ,
e 40.0 Unit 1991 1992 1993 1994 1995 l 1/96 2/96 3/96 4/96 6/96 6/96 7/96 l 8/96 9/96 10/96 11/96 12/96 j PTN 3 47 9 52 7 64 6 85 0 88 9 ' 88 9 88 6 88 7 88 7 88 7 88 6 88 7 88 6 88 4 l PTN4 42 2 E18 E3 7 86 7 87.2 87 3 87 3 84 6 85 7 88 3 89 2 89 0 89 4 89 5 l Pst.1 77 5 78 4 82 7 84 6 77 9 78 0 77 8 77 s 83 5 80 5 79 4 77 1 77 1 77 0 l PSL2 81 4 81 3 8' 3 74 1 74 0 7! 1 77 7 83 5 80 4 81 0 80 3 80 6 80 9 81 4 industry Avg. 72 3 74 6 76 5 78 6 80 8 DEFINITION Unit Capability Factor is the ra30 cf tne available energy generation over a given bme penod to the reference energy generaton over the same time penod, expressed as a percentage with botn energy generation terms determined relative to reference ambient conditions. Available energy generation is the energy tnat could have been produced under reference ambtent conditions considering only hmitations within control of otant management, i e., plant eautoment and personnel performance, and work control. Reference energy generaton is the energy tnat could be produced if the unit were ooeratec continuously at full power under refe*ence ambient conditions throughout the period. Reference amoient conditions s'e environmenta! cons: tons represen:aave of the annua! mean (or typical) ambient condmons for the unit.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE I
g 5, 3.vr Runn+ Y.E Tarce WANC l 1993 1995 Median 81.2 %
PTN 3 27 E . 93 Bb 88.4 % 3 95.0 % 1995 Meoian 82.6 %
PTN 4 93 C5 64 Pe 89.5 % 2 82.0 % 1995 Average 79 4 %
PSL1 67.2 % E2 4% 77.0 % 1 78.5 % 1995 Goal 80.0 %
PSL 2 99.3 % 93 1% 81.4 % 3 95.0 %
PERFORMANCE
SUMMARY
See comments on Page ix.
Data Provioer. Snaron Br!ger 69L4255 A2
UNPLANNED CAPABILITY LOSS FACTOR (3-year Running Average) -
16 0 l 14 0 ,
p c PTN 12 0 ,'
f ,
, . + . PTN4 -
', --C>-- PSL *
.' Q - - C> PSL 2 10 0 , '., . Indys: v Avg -
O o. . . g . . O * - O . o . , g
..> y=
cE .x s",
6o ,
N 40
- V' '
, . . r - - a. . , ,s omsion Y E 3 2%
O' [ ' ' '
' *
- 4 e l 20 00 Unit 1991 1992 1993 1994 1996 1/96 2/96 3/96 4/06 5/96 5/96 7/96 8/96 9/96 10/96 11/96 12/96 (PTN 3 15 2 48 38 43 33 30 36 35 35 35 35 34 34 37 PTN 4 11 5 65 39 47 42 42 42 42 40 37 34 33 31 3c PSL1 51 59 44 57 13 0 13 0 133 13 2 12 7 12 1 12 5 14 ! 14 2 15 3 PSL2 31 55 11 6 13.2 14 8 13 1 107 84 83 81 87 85 83 81 JeudustyAvg. 82 7.6 64 55 49 DEFINITION Unplanned Capability Loss Factor is defined as the ratio of the unplanned energy losses dunng a given period of time to the reference enen;y generation, expressed as a percentage. Unplanned energy loss is energy that was not produced dunng tne penod because of unplanned shutdowns, outage extensions, or unplanned load reductions due to causes under plant management control. Causes of energy losses are considered to be unplanned if tney are not scheduled at least four weeks in advance. Reference energy generation is the energy tnat could be produced if tne unit were operated continuously at full power under reference ambient conditons throughout the period. Reference ambient conditons are environmental conditons representauve of the annual rnean (or typical) ambient conditions for the unit.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE 3-vr Runnino PTN 3 3.7% WANO PTN 4 3.0%
PSL1 15.3 % 1993 -1995 Med:an 5.2% l PSL2 8.1% 1995 Median 5.0%
l 1995 Goal 4.5%
1996 Tatget (all units): 13.2%
i PERFORMANCE
SUMMARY
See comments on Page ix.
I Dsta Source: John Pizzutelli 694-4245 A-3
UNPLANNED AUTG TRIPS PER 7000 HOURS CRITICAL t
(3-year Running Average) l 18 i + . I 1.6 q, O O O ',. O O O ; O l
. . \ '-
i D #
/1 l 5 14 1 ,^, n ,. -
f :
~'../ ',
I g .
"fj '. Div:sc- Y-E 51 De' uv, ,
3 j * .
- ' Na, 4...+....+...+...+....,...e I 0.8 .
E O-< O -O, '
{ 06 O ,' *
'O O O O O 'O O g O) '. : [
, 3 c4 m
$ d --O-- PSL " ,
- - O *
- Psl 9 1 i c.2 industry Avg oo .
Unit 1H1 1992 1993 1994 1995 1/96 2/96 3/96 4t94 5t94 6/96 7/96 8/96 9/96 10/96 11/96 12/96 PTN 3 16 1.0 00 03 03 03 06 06 06 06 06 06 06 06 PTN 4 17 14 09 13 09 09 09 09 09 09 09 09 06 06 PSL1 1.3 1C 09 15 16 16 16 16 16 16 16 16 16 16 PSL 2 06 06 03 07 07 07 07 06 06 06 06 06 06 06 IndustryAvg. 15 1.2 11 09 09 DEFINITION Unplanned Automate Scrams per 7000 Hours Cntical is defined as the number of unplanned automabc scrams tna: occur per 7000 hours0.081 days <br />1.944 hours <br />0.0116 weeks <br />0.00266 months <br /> of critical operation. Unplanned means that the scram was not an antiopated part of a planned test. Scram means the automatic snutdown of the reactor by a rapid inserbon of negatve reactivity (by control rods, licuid injection shutdown system, etc.) caused by actuation of t'ie reactor protection system.
The scram signal may have resulted from exceeding a setpoint or may have been sounous. Automatic means that the inital signal that caused actuaton of tne reactor protection system logic was provided from one of tne sensors rnonitanng plant parameters and conditions rather than from the manual scram switches or, in certain cases described in INPO 94 009. fmm manual turbine tnp switches provided in the main controi room.
Cntical means that dunng tne steady state conditon pnor to the scram, tne effective reactor muWicaton factor was essentially equal to one.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE
. Tnrough Septembef WAND 12-me 36-mo Division Tota:s 1993 - 1995 Mediar 0.9 1996 02 0.S 1995 Meoian 0 '-
1995 1.1 0.9 1995 Goa- 14 Division Target: 5 3.0 auto tnps PERFORMANCE
SUMMARY
See Pace ix for comments.
Data Providers: (PTN) Jim Knorr 2456757 and (PSL) Kelly Kortn 467-7054 l
A-4
i . .
- HIGH PRESSURE SAFETY INJECTION SYSTEM PERFORMANCE .
(3-yr Running Average) 0043 0 PIN :
q PTNt.
0035 - -O- Ps'
- - O - PS', ;
- - incast v Av; _
0 030 i _ _s L_
U '
] 0 025 Dmsion Y-E 50.025
'E h 0.020 D !
0.015 , ,
e' s o ,,, o. .
1
' " N'_, ,tj q).. ...
-O g J 0.005
~~
v 0.000 Unit 1991 1992 1993 1994 1995 3/96 8/96 9/96 12/96 l PTN 3 0 00' O 003 of,/ 0008 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 D C26 0017 C 011 0 025 0 026 0 027 0 026
'PSL2 0 01 e 0 006 0 018 0 007 0 010 0 009 0 009 0 009 Industry Avg. 0 008 0 008 0 010 0 00s 0006 DEFINITION l
This Safety System Performance indicator monitors the readiness of the Safety inlection (SI) System at Turkey Point and the Hign Pressure Safety )
injection (HDSI) System at St Lucie to respond to offmormal events or acocents. The ince,ator is determined from the unavailabilities, cue to all causes, of the components in the system dunng a time penod, divided by the number of trains in the system. The definition is further exptained.
comoonent unavailabik'y is the ratio of the hours the component was unavailable (unavailable hours) to the hours the system was reautred to be available for service Data is recorted on a cuarterly bas:s.
Unavailabihty = (Known Unavailable Hoursh (Estimated Unavailable Hours)
(Hours System Required)x(Numberof Trains)
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE 3rd Of 1cM 3-vr Ava Endina 996 PTN 3 0.000 0.009 WANO Unavailabihty PTN 4 0.001 0.009 PSL1 0.000 0.026 1993 1995 Medtan (PWR) 0.003 - 0.008 PSL2 0.004 0.009 1995 Goal 0.020 Targets: ETJt! EE 1995 Y-E Target 5 0.016 5 0.023 1996 Y.E Target 5 0.025 '5 0.025 PERFORMANCE
SUMMARY
See Page x for comments.
Data Provice's (PTN) Bnan Dunn 246-6173/Carlos Melchor 246-6964 (PSL) Chuck Wood 467-7034/Juri Krumins 467-7136 A.5
SAFETY SYSTEM (3-yearRunning PERFORMANCE Average) o AUXILIARY FEEDWATER
'l 04 0 . PTN 3
- + . PT N 4 PsL-
=* O PSL;
. mcust v AG e Omsion Y E 5 0 0:5 Il
- ! \ '.
0,.
0 020 e
0 .,
5 5. .
~~&
0 ..............****--7 0 --
u 0 010 ,
y ,
0 000 12/96 6/96 9/96 1994' 1995 3/96 '
Unit 1991 1992 1993 0 013 0 015 0 015 0 025 0 016 0 021 0 014 0 010 PD43 0 008 0 011 0 019 0 011 0 012 0 012 0 031 0 020 0 009 PU44 0 010 0 010 0 030 0 028 0 029 0 010 0 013 PSL1 0 012 0 014 0013 0 014 0.012 C 002 0 014 .
-PSL2 0 017
~
DEFINITION This Safety System Performance indicator monitors tne read f time period, divided by the number of trains in the system. This denniton is furtner explained _
hours tie component was unavailable (unavailable hours) to the hours the system was required to b AFW Unavailabihty = (Known Unavailable Hours) + IEstmated Unavailable Hours 1 (Hours System Required) x (Numoer of Trains)
INDUSTRY PERFORMANCE STATISTICAL
SUMMARY
3rd O'r 199 bvr Ava Endina 99 UnavailabM PTN 3 0.I- 0.013 EA!,Q 0 00- 0 010 PTN4 0.009 0.004 - 0.009 PSL1 0.004 1993 1995 Median (PWR)
O.013 O.025 PSL 2 0.0C. 1995 Goa' P7N PSL Targets:
1995 Y-E Target 1 0.020 1 0.021 1996 Y-E Target 1 0.025 5 0.025 PERFORMANCE
SUMMARY
Ese Page x for comments.
7 Data Provicers:
(PTN) Bnan Dunn 24%173/ woody Raasch 24M52 (PSL) Cnu0k WOOD 457-7034' Mark Wotaver 467 7083 A-6
SAFETY SYSTEM PERFORMANCE - EMERGENCY AC POWER SYSTEM (3-year Running Average) -
O PTN3
+ - PTN 4
--C)-- PSL 1
- 0025 O * *PSL 2 _.
Dmsten Y.E g C 00!,-,
--Incut,try Av; -
0020 -
0 0 C O o
. D. ~
^
m 0 015 o ', ,
O......,,,,,, ,,,,,......o 0.010 ', ', ,- ' , , ,
s b* ,,
, D he** i 0.000 '
j Unit 1991 1992 1993 1994 1v96 3/96 6/96 9196 12/96 I PTN 3 0 001 0 004 0 002 0 003 0 003 0 006 0 006 0 006 f sPTN4 0 015 0 001 0 002 0 003 0 003 0 003 0 003 0 003 j PSL1 0 013 0 019, 0 012 0 010 0019 0 019 0 019 0 019 I *PSL2 0 019 0 008 0 011 0 007 0 012 O 013 0 012 0 013 tedumbyAvg. 0017 0017 0 020 0.014 0 012
$ I
- l DEFINITION
}
j Emergency AC Power System is defined as the sum of the emergency diesel generator unavailabilities divided by the number j of emergency generators at a stabon. Data is collected at the train level. The emergency generator includes subsystems
- such as air start, lube oil, fue! oil, cooling water, etc. However, for this safety system performance indicator, unavailable hours j are counted only when the emergency generator is unavailable to start or load-run. For example, if a component fails in,one j train of a redundant support system the emergency generator is still operable, and no unavailable hours are counted.
i i STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE l 3rd Ott 1906 3-vr Av0 Endin0 9/96 PTN 3A&B 0.001 0.006
- PTN 4A&S 0.002 0.003 WANO UnavailaD#v i PSL1A&B 0.001 0.019 1 PSL 2A&B 0.015 0.013 1993 1995 Median (PWR) 0.007 0.012 1995 Goa! 0.025 i Tage
- s: ETJt! Eg l 1995 Y-E Taget 5 0.015 5 0.016 j 1 1996 Y-E Target s 0.025 5 0.025 :
j
- PERFORMANCE
SUMMARY
l l
1 See Page ix for comments.
4 1
Data Providers: (PTN) Bnan Dunn 246-6173/Jennifer Murpny 246 6827 (PSU Chuck Wood 467 7034/Ro0er Kutavich 467 7080 i
A7
t SAFETY SYSTEM PERFORMANCE - AUXILIARY FEEDWATER SYSTEM
. . (3-year Running Average)
)
0 040 .
l
- PTN2
. . 9. . . pts 4
--O- psi -
. O PS;. ;
-Incustw Aq 0.030 -
l 1
l
, ., o. vision Y-E $ 0.025 Il E b*
0.020 ', 0.
8 o j' .
'. ~
'x - 9...... ...-.G %
.$l .
] 0.010 [ . "s '
0 " ^
--5
, d 'Cf i 4
0 000 4
1991 1992 1993 1994' 1995 3/96 6/96 9796 12/96 i Urdt PTN 3 0 008 0 025 0 016 0 021 0 014 0 015 0 015 0 013 l 0 011 0 010 PTN4 0 012 0 031 0 020 0 019 0 011 0 012 PSL1 0 012 0 030 0 028 0 029 0 010 0 010 0 010 0 009 j
JPSL2 0.017 0 014 0 012 0 000 0 014 0 013 0 014 0 013 ,
4 DEFINITION i
This Safety System Performance indicator monitors tne readiness of the Auxiliary Feedwater (AFW) System to respond to off-norma!
events or accidents. The indicator is determined from tne unavailabilites, due to all causes, of the components in the system dunng a tme period, divided by the number of trains in the system. This definiton is further explained: component unavailability is the rato of j
hours the component was unavailable (anavailable hours) to tne hours the system was required to be available for service.
, AFW Unavailability = (Known Unavailable Hours) + (Estmated Unavailable Hours) l (Hours System Required) x (Numoer of Trains) l STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE 3rd O'r icc? 3-vr Ava Endina 9%
PTN 3 0.00- 0.013 WANO UnavaifabFr'i PTN4 0.00- 0 010 PSL1 0.0C.: 0.009 1993 1995 Median (PWR) 0.004 0.009 PSL 2 0.00,- 0.013 1995 Goa' O.025 Targets: S S l 1995 Y-E Target 5 0.020 5 0.021 i 1996 Y-E Target 5 0.025 's 0.025 I
PERFORMANCE
SUMMARY
l i
Set Page x for comments. i Data Provcers- (PTN) Bnan Dunn 24M173rWo0cy Raasch 24M527 (PSU Cnu0k Wo0d 467 7034/ Mark Wotaver 457 7083 A-6
SAFETY SYSTEM PERFORMANCE - EMERGENCY AC POWER SYSTEM !
(3. year Running Average) i
- PTN 3 j . 4. . . PTN 4 l --O-- PSL 1 O PSL Omsten M $ C 025 g, C 025 l
- -Industry Avg i
I 0 020 l O C O O L m rg 0 015 0 ,
', O.......,,,,, ,,,,,.....;O
=
0.010 ',
_Q' , . , '
b'
- O . . .
0005 ,
. e............+...........4 0.000 Unit 1991 1992 1993 1994 1996 3/96 6/96 9/96 12/96
. PTN 3 0 001 0.004 0 002 0 003 0 003 0 006 0 006 0 006
' PTN 4 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
' PSL 2 0 019 0 008 0 011 0 007 0 012 0 013 0 012 0 013 tuluulryAvg. 0017 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 tnis 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 Ott 1906 3-vr Ava Endino 956 PTN 3A&B 0.001 0.006 i PTN 4A&B 0.002 0.003 WANO Unavaita@'y PSL 1A&B 0.001 0.019 l 1
PSL 2A&B 0.015 0.013 1993 1995 Median (PWR) 0.007 0.012 1995 Goal 0.025 Targets: ETN ES(
1995 Y.E Ta get 5 0.015 1 0.016 1996 Y.E Target 5 0.025 1 0.025 PERFORMANCE
SUMMARY
l See Page ix for comments.
Data Providers: (PTN) Bnan Dunn 246-6173lJennifer Mugny 24%827 (PSL) Chuck Wood 467 7034/Ro0er Kulavich 467 7080 A7
4 l
THERMAL PERFORMANCE !
(12-Month Running Average) l 1010 .
l 4
f f
' / <> + 4 -- 9. : Ob
- .$ > Y: # ,
0* ,',
Divister Y E 9915 II s -,p ,4 ..
l a
I _
y 99 0 , , 0' ' .'*--
- 8 .-
~ ' ' ' ~ ~
p
/ '.
j O - C> O'..O---o*O
I 98 0 : PTN? ---
l 6' 4 -PTN4
--O-- P SL -
, <> - PSL 2
- Inaustry Avg i 97,0
.4Jnit ^ ^ 1991 1992 1993 1994 1995 1J56 12t96 M 4t96 r ' 5F96 S/96 *7/96 8/96 ' 9/96 10/96 11/96 12/96
-Pill 3 99 3 99.2 1004 100 3 99 8 99 8 99 9 99 9 100 0 100 1 100 1 100 1 100 2 100 1 M984 - 98.7 99 0 99 7 99 7 100 1 100 1 1C01 100 1 99 9 99 7 99 4 99 3 99 1 99 0 1 PSL'1 99 0 99.3 99 2 99 0 99 0 98 9 98.9 98 9 98 9 98 9 98 9 98 9 98 9 98 8 PSL 2 99 6 99 3 97 8 98 5 98 1 98 2 98.2 98.2 98 3 98 3 98 4 98 4 98 6 98 7 f
andustyAvg. 99 2 99 3 99 4 99 4 99 5 DEFINITION j Thermal Performance is the rabo of the desgn gross heat rate (corrected) to the adjusted actual gross heat rate. Gross heat rate
, is defined as the ratio of tota! thermal energy produced by the reactor core to the total gross electrical energy produced by the
} generator during a given tme penod. Design gross heat rate (corrected) is the minimum theoretical heat rate tnat can be attained I at design operatng conditons for 100 percent power, expressed in British thermal units (BTUs) per kilowatt-hour (electnc).
2 Adjusted actual gross heat rate is the gross heat rate attained in the normal equipment lineup dunng one 24-hour pened each month, expressed in BTUs per kilowatt-hour (electnc) power level should be greater than 80 percent.
, STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE 1
g 12-Mo Averace WANO i PTN 3 .
99 5 % 100.1?
- PTN 4 98.7% 99.0% 1995 Med;an 99 5 %
j PSL1 93 4 % 98.8% 1995 Goa, 99 5 %
d PSL2 95J% 98.7 %
1996 TargeHall units): 99.5 %
PERFORMANCE'
SUMMARY
Data Proveers- (PTN) Jose 00nis 2466008 and (PSL) Many Smit 467 7075 A-8
FUEL RELIABILITY (Fuel Cycle / Monthly) 100E +0C 0 PTh ;
4 -PTN4 1.00E 01 --O-- P S' *
- O PS;;
. Industry Aq ,
100E.C2 h:s D- -
- t
',\'
{ 1.00E-03 .
4 = ' Fuel Defect Reference 5 OE 04 gI 1.00E-o4 - ', -
O-
.. 0 1
"w.:.m. e : c) . . .
'y -
r.
1.00E-oe
',. ^ "
^ '., - ,' ^ ^ ^
s,
^'
1.00E 07 Unit Previous Cycles 1/96 2/96 3/96 4/96 5tDS 6/96 7/96 8/96 9/96 10/96 11/96 12 _/96 PTN3 a sea-2 1 esta a 7cEd 17sa-a a 1sE4 100E4 1 COE4 1 coE 4 1 OoE4 100E4 1DoF4 1 coE4 1mE4 100E4 PTN 4 sJ4a.s i osa.s 7 assa e cos4 s see4 e ses4 i sia.s : coe4 s s4a.s i sea.s t 7sa.s 5 coe4 4 asE4 PSL1 e sas. s sina s 17s4 s.coe4 4 a2E4 i see s a sia4 i see s a sis.s t see4
.: PSL 2 2.oia.s : 7tta a s2E4 e sos.s a asa4 imE4 i oce4 i sea-s s.cas4 4 assa a asa4 7 cos.s a osa4 7 vida enshastry Avg. s 00E4 DEFINITION This indicator is defined as the steady-state primary coolant iodine 131 activity (mcrocunes/ gram) corrected for the tramp contribution and power level, and normahzed to a common punfication rate and average knear heat generation rate. The indicator value is calculated based on the average of the three montnly values for the most recent quarter of steady state operation above 85 percent power. Steady state is defined as continuous operation for at least tnree days at a power level that does not vary rnore than 25 percent.
l Note: If a calculated monthly value for a unit is less tnan 1.0E4 microcuries per gram, the value is replaced by 1.0E4 microcuries per gram STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE laat CYele No.
PTN 3 1.00E-06 15 PTN 4 4 48E-06 16 1995 Fuel Defect Reference Threshold (PWR) 5,00 E44 PSL1 1.99E-06 14 1994 Median 7.35 E 05 PSL2 7.71E-05 9 1994 Best Quartile 3.00 E46 l 1
Division Target for each unit: 5 4.50E-03 PERFORMANCE
SUMMARY
Preliminary review of the Reactor Coolant System radioisotopic data for all units indicates zero defects.
Data Provider. Modesto Jimenez 694-3323 3.o
CHEMISTRY INDEX !
(12-Months Ending Weichted Averagei ,
) l I' 1 40
^
DTP:
+ -
- pTN 4 q ,33
--C>- D s'. '
=
- Q *
- P$', ,
1 30 -- ini. sty As;
(>
D Dvsren Y E e 11:
, h . . . h4 . . o ~ ~ (, O
! y c, i h 1.15
- o 1.10 % .
O. ' '
, ,...$.* 4.,,
4 $*4.., .
1.00 Unit 1991 1992 1993 1994 1996 1/96 2/96 3/96 4/96 5/96 6/96 7/96 8/96 9/96 10/96 11/96 12/96 PTN 3 1 10 1 11 1 11 1 11 1 11 1 09 1 09 1 09 1 08 1 08 PTN 4 1 04 1 04 1 04 1 03 1 08 1 06 1 06 1 07 1 05 1 05 PSL1 1.24 1.20 1.20 1.18 1 16 1 16 1.16 1 16 1 17 1 17 PSL2 1.17 1 19 1 19 1 19 1 17 1 18 1 19 1 18 1.18 1 17 industry Avg. 1 18 DEFINITION The Cnemistry index compares the concentrabon of selected impurites to the limiting values for those impurites. Each impurity value is divided by tne limitng value for the impunty, and the sum of tnese ratos is normalized to 1.0. Tne limitng values are the " achievable values
- defined by intematonal industry-accepted values.
STATISTIC AL
SUMMARY
INDUSTRY PERFORMANCE Sepj 12-Mo Endino Weichted g WANO PTN 3 t 1.01 (PWR s with Rec:rculating Steam Generators uthout Mata-1.0; Rato Contr0!,
PTN 4 1.00 1.it 1995 Med;a , 1.18 PSLi 1 11 PSL2 1.19 1.17 1995 Lowest Cnemistry index Vaiue Attainable 1E 1996 Target for eacn unit: 5 1.20 PERFORMANCE
SUMMARY
e Chemistry index performance for all units for 12-mo. ending weighted average was below the year-end target and ind'stry average.
Da'a Providers: (PTN)R. Steinke 2464118/ Jim Berg 2464953 (PSL) R. Freenette 465-3213/ Dave Fautxner 465-33s's -
A 10
1
. l l RADIATION EXPOSURE (3-year Running Average) -
400 1 + PTN 8
35o -c>- PS L
- -industry Av; 300 .-
I
- s 250 O 3 Ta get 229 2 p s. ,
Targ i 1708 4
- l
! 100 Note 1996 numoers are l adjusted eacn month to rehe:' I TLo cata 50 i
$ Plant 1991 1992 1993 1994 1996 1/96 2/96 3/96 4/94 5/96 6/96 7/96 8/96 9/96 10/96 11/96 12/96 I
PTN 350 332 257 181 162 162 161 185 164 153 152 151 150 149 PSL 274 238 193 202 230 229 227 219 187 200 210 218 218 218
{ M Asg. 189 193 193 144 153
- DEFINITION 1 i i
! Collective Radiabon Exposure is the total extemal whole-body dose received by all personnel (including contractors and visitors) coming on site during a bme period, as measured by tne pnmary dosimeter, tnermoluminescent dosimeter (TLD) or film badge. j 4 Exposure measured by direcf. reading dosimeters should be included only for those periods or situabons when more accurate data -
is not available to the utility from TLD's or film badges. In order to correlate this indicator with the new 10 CFR 20 reportng ;
- guidelines U.S. utilibes report deep dose equivalent (DDE) and the total effectve dose equivalent (TEDE).
< l STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE 3-vr Runninc cer Unit i Man-Rem l PTN 149.0* WANO (per Unit l PSL 217,7*
(PWR's ) Median 3-yr Distnbution (1993 1995) 163 Division Targets: 3-vr Ave 1995 Median 153 PTN: Y-E thru 1996 1995 Goal 185 5 170.8 PSL Y-E thru 1996 5 229.2 PERFORMANCE
SUMMARY
See Page x for comments.
Data Providers:(PTN) John Lindsay 24M548 and (PSL) H. M. Mercer 467-7302 A.11
j .
l LOW LEVEL SOLID RADIOACTIVE WASTE
, (Cubic Meters per unit per year. 3-year Running Average) 140 3
--+- PTt, l
! , -o- p:.
120 - - Incustry Av:: -
100 I
1 7N 6 8/96 ca:a aausted SC ',
j g 80 o>scesa, caiculate er o-
- C l
' 85L - 7% acosies n: va .- l uses esieae o's te .a..+
a> p3 y,g g g 2 60 O- PTN Y-E 55 6 l O
7 l 3 -m -
40 l'
i
%m- .
I l
l 20 4
i g l Plant 1991 1992 1993 1994 1995 1/96 2/96 3/96 4/96 5/96 5/96 7/96 8/96 9/96 l 10/96 11/96 12/96
- PTN 125 3 102 3 81.2 63 4 37 4 36 7 35 2 33 1 33.2 32 0 31 1 31 1 30 8 31 0 PSL 121.1 103 8 80 7 75 4 53 7 53.3 53 0 54 6 57.2 57 0 56 4 54 7 54 2 54 1 1 4
tidusby Auf. > 85 0 87.0 450 46 0 47 0 l 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, i compacted or solidified) ready
- for d:sposal during a given penod. It is calculated using the amount of waste in final form, includ:ng the container, actually shipped for disposal from both on-site and off-site facilites, plus the change in inventory of final form waste in
- storage at both on4ite and off-site facilites.
j
- in transit to or at disposa! site for disposa!
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE 3-vr Runnin0 tnn; Seat (Dar unjtj WANO Monthly Cc. R.
PTN 31I (2 it S m p"e 3-yr Dstnbution Med:an (1993 - 1995t 47.0 l
1995 Med:an 30.0 Dvison Targe's 1995 & a! 110.0 PTN 1996 Y-E 55 6 cu. mtr. cer unit PSL 1996 Y E 67.5 cu. mtr. per unit PERFORMANCE
SUMMARY
See Page x br comnunts.
Da:a ProvceT (PTN) Bob Senuber 246-7220 and(PSL) Bruce somers 467 7305 A 12
INDUSTRIAL SAFETY ACCIDENT RATE (12-Month Running Average) 1 00
- +- P T N
--O-- P S . _
0 90 y -incastw Av; 0 80 I
- 0 70 k
) 0 60 '
4 2 0 50 1 00 / \A -
=hx 0 2
\ FTN'PSL Y-E S C 30 g-,
s 0.20 3'
- 4 0 10 0 00 1994 1995 1/96 2/96 3/96 4/96 5/96 6/96 7/96 8/96 919 6 10/96 11/96 12/96 Plant 1991 1992 1993 PTN 0 25 0 67 0.36 0 50 0.22 0 22 0.22 0 11 0 11 0 12 0 12 0 12 0 13 0 14 PSL 0.75 0 61 0.50 0 51 0 40 0 40 0 41 0 32 0 32 0 33 0.34 0 33 0 36 0 25 In6meWyAvg. 0 97 0.77 0.77 0 64 0.55 DEFINITION Industrial Safety Accident Rate is defined as the number of accidents per 200.000 man-hours worked for all utility personnel permanently assigned to the station that result in any of the following: (1) one or more days of restncted work (excluding tne day of the accident); (2) one or more days away from work (excluding tne day of the accident); and, (3) fatalities. Contractor personnel are ra!Wuded for this indicator.
Industrial Safety Accident Rate = (number of restricted-time + lost-time accidents + fatalites) x 200.000 (number of station man-hours worked)
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE 12-Mo -Endina (Seon PTN 0.14 PSL 0.25 1995 Median 0.55 Dmsion Targets:
PTN 1996 Year-End 0.30 PSL 1996 Year.End 0.30 PERFORMANCE
SUMMARY
No Lost Time injunes were reported in September.
Data Providers. J. Samtxto (PTN) 246 7372 and T. Moser (PSL) 467 7171 3.i
I EQUIVALENT AVAILABILITY FACTOR
. (Year-to-Date) 100 0
"** ~~ ~
90 6 \
hL..'W V' \ .....
5"'"'" '
h/M% . .'(
~
\ +..4' 60 ~0
!/ Y c -
g s0 0 l/
g .I 40 0 30.0 /
- PTN 3 20.0
- + . PTN 4 _
--O-- PSL 1 0 O -PSL 2 10 0 m-ind Avg-00 Unit 1991 1992 1993 1994 1996 1/96 2/96 3/96 4/96 Sits . 6/96 7/96 8/96 $/96 10/96 11/96 12/96 PTN 3 22 3 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 PTN 4 13 9 85 f 81 1 83 1 97 4 100 0 100 0 68 3 68 4 74 6 78 9 80 9 833 84 9 PSL1 78 5 95 4 74 0 84 5 75 3 99 6 94 5 94 9 94 6 75 3 62 9 56 6 61.8 62 4 PSt.;2 ;- 98 5 73 2 71 8 77 4 72 9 76 8 87.9 92 0 92 1 93.5 89 8 91.3 92 4 93.1 N Agg - 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 operating at full power for tne same penod expressed as a percent. Equivalent Availability provides an indication of the effectiveness of plant programs and practces in maximizing electncal generation.
EAF% = Available Hours -(Eouivalent Unit Derated Hours) x 100%
Period Hours STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE o
seo_t
%T-D WT-D Taraet 3-yr Run Avo PTN 3 87.6% 93 8% 95.0% 88.4 % NERC/ GADS 1995 (All types) 75.7%
PTN 4 9804 M 9S 78.1% 89.5%
73.0% 77.0 % 1993-1995 (All types) 72.7%
PSL 1 67.2% 62 4%
PSL 2 99.3% 93 i5 95.0% 81.4 % WANO 1 80.7 % !
Division 88.0% 836% 85.3% 84.1 % 1995 Med:an 1995 Average 77.4 % ;
l 1996 Division Y E Target 88.0%
1996 Year End Forecast 86.3%
PERFORMANCE
SUMMARY
I Equivalent Availability Factor penormance in September was as follows:
e PTN 3 EAF for the month was 87.6%. Power losses resulted from Control Rod failure (89.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />).
e PTN Unit 4 operated at 98.0%: unavailability was due to problems with Feedwater valves (14.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />).
e PSL 1 EAF was 67.2%. Power losses were tne result of: repair to 1B Main Transformer (221.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />); Chemistry Hold (9.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />): 1B1 Wateroox leak (2.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />); Circuit Breaker recair (1.8 nours): and leak repair to Dump Valve at 0-nng (0.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) e PSL 2 operated at 99.3% w:tn power losses attributed to: Turbine Vane test (0.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) and repair to Waterbox (4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />).
I For the Division, Equivalent Availability was 88.0% for the month and 83.6% Y T-D which is below the 85.3% targeted Y-T-D. 1 Data Provioer. Snaron Bager 694-4255 B-1 l
_ . _ . . - - - . - . . . . - _ _ - - . . - . . . _ . . _ . - . . . . - - ~ . . - _ . . _ . .. - . . . . - .
~ .-_ . _...--
CAPACITY FACTOR (MDC NET)
. (Year-to-Date) -
3 110 0 0
100.0 i A lx .- he . . J"., ......8 W W \
,0 ,
,00 / ...-
., O ,
W O ', ,
- q' c
\
8, l l 2 600 -
L>-- n l l
l t 50 0 J l I 40 0 f'/, : PTN 3 I
30.0 -s PTN 4 - '
--O-- PS:.1 l l 20.0 - 0 *PSt.2 _
j . -- Ind Av; j 10.0 i :
1 00 1
! Amt . -1991 19s2 1ses 1ss4 1ses ties 2/es 3ms dies site ses 7/ss ass ses 10ms 11/96 12/ss l PTN3 22 5 58 4 97.0 84 8 89 5 103 9 85.7 90 0 93 1 94 9 95 5 95 9 96 4 95.3 l
PTN 4 13.7 79 3 81 4 83 0 93 5 104 5 104.2 71.0 67.5 74 1 78 1 79 3 82 2 83 8
- PSLT. 78 8 96 9 73 9 84 1 75 0 98.8 93 3 94.2 94.1 74 9 62.5 55.2 60 5 61.1
. stE.,1. 101.1 73.7 64 1 76.3 71.9 74.1 87.0 92 0 92.0 93.5 89 5 91.2 92.3 93 0 tudEsg 71.2 72 3 75.5 77.9 ,
1 1
DEFINITION Capacity Factor (CF) is the index of the actual electrical energy produced by tne unit wittnespect to its potential.
Capacity Factor = Net Electrical Generabon X 100 Maximum Dependable Capacity (839 or 666) X Period Hours STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE NERC/ GADS Se,pt Y-T-D 12-mo. endn.ia 1995 M Types 75.2%
PTN 3 86.6% 95.3% 93.1 %
1991-1995 M Types 71.3%
PTN 4 96.9 % 83.8% 88.2 %
WANO PSL 1 66.0% 61.1 % 66.3 %
1995 Median 81.1 %
PSL 2 98.7 % 93.0 % 71.5 %
1995 Average 77.9%
Division 87.0% 83.3 % 79.8%
PERFORMANCE
SUMMARY
Capacity Factor performance in September was affected by:
. PTN 3-Control Rod failure
. PTN 4 - problems with Feedwater valves e PSL 1 repair to 1B Main Transformer; a 181 Waterbox leak; Circuit Breaker repair; and a leak repair to tne Dump Valve at 0-nng.
. PSL 2 Turbine Valve test and repair to Waterbox.
Data Pn:mder. Snaron Bilger 6944255 B-2
PTN FUEL UTILIZATION FACTOR 4
! , Turkey Point Unit #3, Cycle 15 Turkey Point Unit #4, Cycle 16 j 500 - ,
000
/-
4 453 hanned Ret,se1ng pa'e Ma ch 3 195' C ;/., 5;;
g g,, g ,
999 400- 450
..Y.
- ng;y y .
j;Me ;- !"
@ 0* '
t '
6 400 7 C4 t b -
k ge, 300 - '
w 350 - -;
fD Rf.y,g.g[
e y e d A ::a 7
- 250- N
- o l / ,, <
c 250 - - -"$rf,N " ' ""
$ 200-g / 4 f ;
L:n200 4 g.Qy sg4A.; m ' - ' ' -
7, . J 100 -
150 j g. $
f... n 100 ,
i 50 - 4.i ... (N, so f .,.
5 Y k ,
8 1
n .
n I $5hk . l J Y-hY PTNf3 oss how Dee ! Jan Fee saar Aer aser Jun -M Ag see oss new pee Des 1 Jan aamr l Aar assy M u . Aue See Pimined 5 35 66 98 127 158 188 219 249 281 312 342 373 403 435 466 494 501 Actisal 18 47 78 109 128 157 187 218 248 278 308 333
, Vartance W 13 12 12 11 1 1 1 .i 1 3 4 9 j PTN84 Planned 6 37 67 96 129 159 193 220 251 282 310 34 1 371 432 432 463 4 94 509 Asensal 18 49 79 106 137 166 Wartaans M 12 12 12 8 8 7 4
DEFINITION Fuel utilizabon plots the amount of nudear energy used during the current fuel cycle. The amount of nuclear energy loaded into the core is expressed in effectve full power days (EFPD). One EFPD is the equivale'it of operatng tne reactor at maximum thermal rabng (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 /> penod. Planned energy is compared to actual energy used dunng the cycle. Fuel utikzabon is directly related to plant performance. The significance of variance EFPD(+/-) is the difference between planned and actual energy consumption. Fuel utilizabon can be used to project longer or shorter operatng fuel cycles Actual Energy 1 Calendar Days = Fuel Utilization Factor Fuel Cycle Operating Assumptions PTN 3: In accordance with tne April 26,1995 Approved Operating. Schedule (AOS). Unit 3, Cyde 15 is seneduled to run 493 calendar days (Octooer 27 1995 to March 8,1997) with design energy to run 501 (EFPD) oays. NOTE: Due to tne 34-cay outage, startup began on October 7,1995,20 days earlier than planned.
PTN 4: In accordance witn the February 8,'1996 AOS, Unit 4 Cycle 16 was scheduled to startup on April 25,1996. Due to a 35-day refueling outage, the unit actually started up on April 8,1996,17 days earher tnan planned. Note that the unit has a design energyof 507 EFPD.
PERFORMANCE
SUMMARY
e Unit 3 achieved a Fuel Utilizabon Factor of 84.2% and operated for 606 effeebve full power hours in tne montn of Septemoer.
For the period October 27,1995 to September 30,1996, the Fuel Utikzabon Factor was 98.0%.
Unit 4 achieved a Fuel Uthzation Factor of 94.4% and operated for 679 effectve full power hours in the month of Septemoer l For the pened Aoni 8,1996 to September 30.1996, tne Fuel Utihzaton Factor was 104.2k '
1 Data previoer Jirnmte Perryman 694-3330 l
BJ
PSL FUEL UTILIZATION FACTOR St. Lucie Unit #1, Cycle 14 St. Lucie Unit #2, Cycle 9 '
00 500 550 - Planned Retvehng Feorua'y 3,1993 ,h 45c . Pianned ReNeung Date Apnj 1$ 1957 500 -
d
(
C 400-
- f. ..g u&kb f'm 44 4
?_
300-
] 350- ,. y ;
300- 250 .
^,
o o o 250 - A ?
o 200- Aa m ~m C 200 - "
150 ,.'
150- _
[
~
100 - I 30 4 g
'. 50 -
3 S.W . l gg. 7'
,OPSL91 Jun see, 1 aus Aus ese om oss .Jun een eser mer eser .nsi u aos see on ans, ces Jun een anse mer l Planned 5 39 69 98 129 158 188 218 246 276 305 335 365 395 425 4 54 485 514 544 573 575 wActasel 0 5 35 56 Netence 4 >A) -9 -34 -34 42 l
PSL#2 j
Planned 5 36 67 95 126 155 186 215 247 276 306 336 366 397 427 455 485 500 j
.. i.2Actaael 0 0 23 52 83 111 141 162 193 224 254 8Wtenoe (+A) 5 -36 44 -43 43 -44 -45 -53 -54 -52 -52
)
j DEFINITION l Fuel utilizaton plots the amount of nuclear energy used during the current fuel cycle. The amount of nuclear energy loaded into the core is expressed in effective full power days (EFPD). One EFPD is the equivalent of operating the reactor at maximum thermal rating (2200 at PTN or 2700 st 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 energyis compared to actual energy used dunng the cycle. Fuel utilization is directly related to plant performance. The significance of variance EFPD(+/-) is the difference between planned and actual energy consumpton Fuel utilization can be used to project longer or shorter operating fuel cycles.
Actual Energy / Calendar Days = Fuel Utilization Factor Fuel Cycle Operating Assumptions PSL 1: -In accordance with the February 8,1996 Approved Operating Schedule (AOS), Unit 1, Cycle 14 was scheduled to begin operabon June 22.1996 This provided for a cycle of 591 calendar days with design energy to run 575 effectve full power days (EFPD). Un:t 1, Cycle 14 actually began operabon July 25,1996 and is currently scheduled to refuel February 3,1998.
PSL 2: In accordance witn tne April 26,1995 AOS, Unit 2, Cycle 9 was scheduled to begin operahon November 24,1995. This provided for a cycle of 508 calendar days with design energy to run 500 EFPD. Unit 2, Cycle 9 actually began operation January 5, 1996 and is currently scheduled to refuel April 15,1997.
PERFORMANCE
SUMMARY
e Unit 1 achieved a Fuel Utilization Factor of 68.5% and operated at 493 effective full power hours in the month of September.
For the penod of June 22,1996 through September 30,1996, the Fuel Utilization Factor was 57.1%.
. Unit 2 achieved a Fuel Utilizaton Factor of 99.3% and operated at 715 effechve full power hours in the montn of September.
For the period of November 24,1995 through Se;". ember 30,1996, the Fuel Utilizaton Factor was 83.0%.
Data provider: Ruben Rodnguez 694 3345 n.s
_ _ - _ . - . - - - - _ . - - - . . .- .- . . - . , - . ~ . . . . . .~ . _ - - . . . _ . - ~ . . - . - . . - . . . . . . _ - . . ~ _ _ .
FORCED OUTAGE RATE (Year-to-Date) 25 0 CTN ."
n' . + PTN',
'. ---O--- P S L
- l.
- O -PSL 2
, . Ind Av; _
l '.
l '
, 15 0 .
g 9\ *;
c c .
$ . . l' .
10~0
- ^ :\ . , b l f .} .
/ i o. /
1
< e.
SD O...,,
,. ., / _
- . . O. l
[
. . s,( **g.. ,,
O
^
,. **"+***-$...+... ,...., .
00 C .
1996 1/96 2/96 3/96 4/96 6/96 6/96 7/96 j 8/96 9/96 10/96 11/96 12/96 Unit ' -1991 1992 1993 1994 PTN 3 12 15 6 18 19 05 00 11 8 93 70 56 47 40 35 45 PTN4 18 13.2 20 39 1.5 00 00 00 1.3 1.0 08 06 05 05
-PSL1 12 35 21 39 21 8 00 44 29 22 22 22 21 18 41 PSL1/.7 0.0 81 23.5 2.3 2.4 7.0 34 2.2 2.2 1.7 5.7 48 4.2 3.7
- and Aug - 12.1 10 9 10.3 10 6 90 DEFINITION l
Forced Outage Rate is the percentage of tme tnat tne unit was unavailable due to forced events compared to the time planned for full power operaton. A forced outage exists when the unit requires immediate removal from service, i.e. the unit is not synchronized to the grid. This type of outage usually results from immediate mechanical /electncal/ hydraulic controls systems and operator.
initiated trips in response to unit alarms.
Forced Outage Rate Forced Outace hourt x 100%
Forced Outage Hours + Service Hours l
1 STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE l
f Sect Y-T-D 12 Mo. Endrno NERC/ GADS 1995(Alltyoes) 9.0%
PTN 3 12.3% 4.5% 3.4%
1991 - 1995 W types) 10.6%
PTN 4 0.0% 0.5% 0.3%
PSLi 16.5% 4.1% 7.8%
PSL 2 0.0% 3.7% 3.6%
PERFORMANCE
SUMMARY
. Turkey Point Unit 3's Forced Outage Rate for September was 12.3% as a result of Control Rod fai!ure.
- St. Lucie Unit 1's Forced Outage Rate of 16.5% was attributed to repair to tne 1B Main Transformer.
Data Prowder. Sharon Bilger 694-4255 B!
l
UNPLANNED AUTOMATIC TRIPS WHILE CRITICAL (Year-to-Date) -
5 L
PTN2
+ - - PTN4
--O-- PSL1 4 - - o psL2
- - ind Avg
,3 D#vrsion Targe: 5: ,
t
^
2 ^
e
- 'w s , .
1
%I #
^
0 0 0 0 0 0 0 o' -l. $*
o ^' ^
' ^ ' ^ ^ ^ ^ ^
{ Unit 1991 1992 1993 1994 1995 1/96 '2/96 3/96 4/96 6/96 6/96 7/96 8/96 9/96 10/96 11/96 12/96 PTN3 0 0 0 1 0 0 1 1 1 1 1 1 i 1 j
4 PTN4 0
- 1 : C 0 0 0 C 0 C C C C PR1 2 1 0 4 1 0 0 0 0 0 0 0 0 0
, 'PSL2 0 1 0 1 1 0 0 0 0 0 0 0 0 0 f -Ind Avg 13 1.1 0.9 08 0.9 4
DEFINITION An Unplanned Automade Scram is a non-manual actuabon of the reactor protection system that results in a scram signal any tme
{ the unit is cnbcal. Scrams that are planned as part of special evaluabons or tests are not included in this definition. This indicator
- provides an indicabon of success in improving plant safety by reducing the number of undesirable and unplanned thermal-hydraulic
- and reactivity transients requiring reactor scrams.
j j STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE
- Sep{ Y-T-D 12-Month Endino WANO Trios per unit
- j. PTN 3 0 1 1 Tnps per 7000 Critical Hours PTN 4 0 0 0 3-yr Distribubon Median (1993-95) 0.9 i PSL1 0 0 0 1995 Median 0.9
- PSL 2 0 0 0 1995 Goal 1.0 Division Total: 0 1 1 NRC (1995 3rd Otr Performance indicator Rpt)
Quarterly Trips Annualized 1.0 j 19% Division Target 5 3 Quarterly Trips per 7000 Critical Hour. 1.2 i PERFORMANCE
SUMMARY
- No automatic tnps occurred in September 1996. Year-tcKlate, one automabc trip has been expenenced
l
- Turkey Point Unit 3 experienced an automatic tnp on February 9th; the 'B' Steam Generator Feed Pump was stopped to 2
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 resulung in a turbine tnp which tnpped the reactor.
4 l
- Data Provideni: (PTN) J. Knorr 246-67T' (PSU Kelly K0rth 467-7054 B-6
OPEN PWO'S v 2.500
-+- PTN l
- -O-- PSL 2.0C0 l
r 1 500 h
a k E CL O 3,non
}
t
?
! 500 i
i j Urdt 1991 1H2 1H3 itM 1H6 119 6 2/96 3/96 4/96 6/96 6/96 7/96 6/96 9/96 10/96 11196 12/96 j PTN * * * *
- 1 466 1.589 1 441 1 422 1 310 1 330 1 544 1 536 1 608 PSL * * *
- 1 608 1 920 2 030 2 066 2 166 2 056 1.69 1.782 1644 i
! DEFINITION i
This indicator includes Work Type 1 (Planned Miscellaneous), Work Type 3 (Projects). WorkType 5 (Trouble & Breakdown), Status i 17 through 48, and all hold codes.
a i
i STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE i
4 I
PERFORMANCE
SUMMARY
1 1
i 4
i i Data Prowers:(PTN) Greg Heisterrnan 24%796 and (PSL) Joe Marchese 467 7107
, C-1
PWO AGING CURVE )
. \
1200
- PTN A :ua
+ PTN Goal
---O- PSL Actua!
1000 . o - -PSL Goat i
.e b .
b .
n '. ~
o 600 - ',
}e '. '
3 400 200
, . . . . . . .: ~ g .. ..,,,...
l o
~
"k Unit TOTALS 3 Mo.& greater 6 Mo. & greater 9 Mo. & greater - 12 Mo. A greater PTN Actual 1045 423 205 43 1 l l
PTN Goal 1045 523 262 131 0 l PSL Actual 862 349 185 67 33 PSLGoal . 862 431 216 108 0 l DEFINITION PWO Aging curves includes Work Type .1 (Planned Miscellaneous), Work Type 3 (Projects), WorkType 5 (Trouble &
Breakdown), status 17 through 48, and excludes HC2 inrough HC6 and SNO. INPO definition is to be useu for the graph.
l l Goal: To halve the backlog every three months.
l I
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE PERFORMANCE
SUMMARY
Da*a Prowders:(PTN) Greg Heisterman 246-6796 and (PSL) Joe Mar 0hese 467-7107 cp
PWO'S GREATER THAN 12 MONTHS (GOLDEN OLDIES)
TURKEY P0lNT REF PWO* PWo TITLE Ong Date i Date on List 1 W5024551 vN I 3 FER50NNEL NAIGn AGGt55 AREA rov - LEAA: b 1195 i . W-ST. LUCIE 4 REF PWO3 PWo TITLE I Ong. Date i Date on List h 41316 .Gh Fe 26 RcFJGt MGiUn niAicRe. ces s. c.a N i 4 WJ0J2059 GOMFLEic VPORADE OF GOMPViER 51aity 141 sc 14144 I 3 9401027D FG'v 06 ois GUEo NCI CONTRDL FRc56URi 6 429- i2rd5 4 940174G3 5bFFMT FGf,W42 25s th4 650; v'LG '
..c W I ~ 1345 940165t1 PUfEF CEGRAD6NU.U. crna-5 i.i5 M i . . .:3d :
o WDUUJobs 0-2 G53 J ANN. 5.2 ALARM bis: 1 0.56_
W5004362 VLV LEAR 5 5Y 5 EAT 2 13,95 113<W o 95005523 ;nEGA Tnd Lit /..I5 QN 5DdNU.; ;; e c2Jm s 95010734 TAPE REAG5 53 VvniN Lu i5 3V2. 4 17e = , l 4.16dc 10 950132tia HtFAiR REPLAGt GUNOV.i bu e FVaio a.4.s 5 e 5,3 Ed 11 95014570 Viia NGi GALi5mAic. RtFaR 5 5.k: 5745 12 95014501 nic J6 RELAi 264.545 REFLACEMENi s. ii.so be lo<n 13 95014512 HV5-4A RhLA) is505 RthAGcMtNT i 17.h i16M 14 95014511 HV5-25 RELA) 26452J RcFLAGcMcNi il7!sa 5164o
?6 35014709 5WIIGH CAU5c5 RELAY 5 IU GHA i i c" 5. ls :s 515/y6 lo S5015354 GiSGnARU: AGGVMJ Ai06 LEAMNU bLIGniLi 524.95 5235d il 95015453 FGM-115-234 5259: 524:35 16 350172M MECH. SEAL LEAK ANU rsi ItNG5 LEAMN5 6 15!s5 61446 19 95015290 ENG MUJNicD ELAF5c0 hJUR Mc i c8 INGvRRt; ci2695 62546 20 UN W0lb ALARM 5 WILL NOT ADJJ5T,REFAiRiRtPLAGE Til5Sa 7.17ho 21 9302054J IMPLEMENT PCM-152-994 li2565 7i24,W 22 WOUzv/W2 GHEM UMBLE TO MAKE GRAB 5AMPLINU GncG li25.M i.27h6 23 WJU21755 RtPAJR LEAKJNG Rh0VLAIOR - 5/5S5 575o 24 UNZ1914 iMPLEMENI PGhW53195 BS.M &&W 25 WDv44wl MtFLAGE FH-1A AND Fn-1 DOOR 5 &1065 &S/W 2t WN44cto LGV 1132D. HANDWMEtL dicM air LEAA 5,2155 620fn
. WN22553 LGV 1115A. Alm LcA6 AT HANDNnEEL A551 62145 62005 2s W 2455o DidRBRQnEN 6.21/95 620so 29 S5024077 JGni WIRE 5 HANG.NG ON DOOR 5/3.M 5.2/%
M 95024536 'u AIcR LEAA s/5.M Sil55 31 d5024572 MtFLAGE TEMF GUNNtGI60Nb IQ CALGUN IIMi 9.li35 5 i/h 32 W W24 bob McFAiR OR REPLACi S. la.5 5 s. li so 3a WN20564 NJ PU5ifiUN INDIGAIUM W.27.% 5 Zih ;
i PWO Greater than 12 months. includes Work Type 1 (Planned Miscellaneous). Work Type 3 (Projectst WorkType 5 (Trouble &
Breakaown). status 17 Intougn 45. and ecuces HC2 inrough HC6 and SNC.
Das ProvvjeT PTN) Greg Heisterman 246-6796 (PSL) Joe Ma@ese 467 7107 l
.A C-3 1
__ ._ _ _ _ _ _ _ _ _ _ _ _______._______._._______u
I NONo0VTAGE PWO'S
! 1400 1
1200 -+-- PTN _
! -O- PS L
! 1000 l , 'v/ \
l 800
- i j 600 .-
E i
l 400 1
1 1
200 4
0
- Unit 1991 1992 1993 1994 1995' if96 2196 3/96 4/96 556 6/96 7196 856 946 10/96 11/96 12/96
, PTN 1024 1091 1118 1166 949 935 1081 1035 1049 1247 1103 1016 961 690 889 1102 1101 902
) f PSL-1 1 DEFINITION
! Non-Outage PWO's includes Woa. Type 1 (Planned Misce ianeous), Work Type 3 (Projects), WorkType 5 (Trouble & Breakdown),
status 17 through 48, and excludes HC2 through HC6 and SNO.
t l
i l STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE i
l i
I PERFORMANCE
SUMMARY
a Data Pr:moers- (PTN) Greg Heesterman 246 6796 and (PFQ Joe Marchese 467 7107 r-.t
l
)..
i CONTROL ROOM INSTRUMENTS OUT OF SERVICE
- 4 f 60 l
- -*-- PTN l j C -o- PSL j
$0 '
8 !
}* O
{
NOTE PTN numoers <
nave Deen adiuste:
q trom 6 8/96 to refie:t - i
) o tne 'totar number :' !
4 g tags instead o' E C " outage ~ tags or , i E
^
N C / O i
' O E
8 O l Outage tags 4
tt 20 '
PTN 3E -
j C [' [ PSL 7 e
! O 10 o
4 i o l Unit 1M1 1992 1M3 1994 1M6 1/96 2/96 3/96 4/H 5/96 6/96 7/96 8/96 9/96 10/96 11/96 12/96 PTN 39 40 42 12 30 16 43 41 52 47
- PSL' 54 46 25 20 28 27 27 33 22 12 i
DEFINITION This indicator defines the number of control room instruments for each unit that cannot perform their design function, j
regardless of the reason. Instruments on the control room back panels are readily available for use by the control room crews j .
and are included; however, instruments in adjoining areas where operators are not normally stationed (such as computer j rooms) are not included. Count deficiency tags that are in status 05 to 48.
t i 1
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE i
i
, PERFORMANCE
SUMMARY
J j
]
i Data Procoers- (PTN) Greg Heisterman 2456796 and (PSL) Joe Marchese 467-7107 l
i C4
j I, OSHA RECORDABLES j (Year-to-Date) .
4 50 1
--+- PT N l
-O- P SL 40 1
.,I 30 l
L i$
\
n: '
1 (
@ 20 w , f
{ ;
j O u
' The numoerof osha l 10 - Recorcabees m 1995 at
- PsL ns mconectly
- reported at the begmneg
! of this year (46). The . .
conect number is 26 C . .
f f a :#' _
i .uen 1eet 1esa sees 1ess toes vos zies sies ases sees sies 7ses sies eres seres itses 12iss
- PTN 35 39 29 27 20 0 1 2 2 2 4 4 5 6
- 'PSL 20 22 23 41 26 3 3 4 5 10 14 17 18 19 4
! DEFINITION
! The definition by Occupational Safety Health Administraton (OSHA) is an injury occurnng on the job that requires medical 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 19 i
i Nuclear Division Y-E Target 1.75 per 200,000 Hours Worked l Corporate Y-E Target 3.75 per 200,000 Hours Worked
- PERFORMANCE
SUMMARY
} Two OSHA Recordabk injunes were reported in September. The injuries occurred in August.
P.EL laceratontothumb S-hydroblasterinju y toleg i
i A total of 25 OSHA Recordables have been received year-to date.
Data pronders: J. Sambito (PTN) 2467372 and T Moser (PSL) 467-7171 D-1
LOST TIME INJURIES (Year-to-Date)
I
-+- DTN d
--O- PSL .
3 Ei 7 E
' ^
2 v O O a \
1 --
O O O O O 0 0 0 o : : . . : : : : .
(JnN 1991 1992 1993 1994 1995 1/96 2/96 3/96 N96 5/96 6/96 7/96 8/96- 9/96 10/96 11M 12/96 PTN O O O 1 C C 0 0 0 0 1 1 1 1 PSL 2 4 3 1 2 1 1 1 1 1 '
2 2 2 DEFINITION A Lost Time injury as defined by Occupabonal Safety Health Administraton (OSHA)is an occupatonalinjury that reautres 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 tne day of injury.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE Momt Y-T-D PTN 0- 1 PSL 0 :
PERFORMANCE
SUMMARY
No Lost Time injuries were reported in September.
Das govcers: J. Sambito (PTN) 246-7372 and T. Moser (PSL) 467-7171 D-:
REGULAR STAFFING FPL Employees and Long Term Contractors '
by Department 1200 Turkey Point
{w 1100 966 988 ges 964 se{ 984 gec
-i 1000- c .
- - 64: 64: Actua' 900 s? s2 sN 5 5 I C -O- Pianned t 6- 6.: sri gN .
- 800 -
,7; .-
700 1200 St. Lucie 1100- 1 034 i c3: ,c2 , e7 , , , ,g,, ,e,, ,
3 f 900 -
1 0 10 10 1 1C1 1 00 b
935 93- g"4 w
j BQQ - ee" 700 - <
"9'"""9
$00 E
- 400 - 3's 348 34' 34' 343 343 333 3*
C C C C C Sc =
-} 300- 3, , 3ie 33, 3' C & M h y 200 31 af 2s' g 29s g 100-0 Nuclear Assurance
'20 I
ggS is 5x 1x 12 1M 1M 'M k C E N g 100 - tc7 16 1A *M 1" '"
U 10 \3 99 99 2
90 -
80 Licensing & Special Programs 0~
s s i
t F P E 2 0
gg Nuclear Business Services E 43 43 43 43 r 45 - 43 43 43 42 42 R g cm,
, ; 4, 4, 3 ,,
4=
a a 30 Nuclear Division Total 2600 - 2 493 2 493 2 493 2 493 2 4a9 2 489 2 47s 2400 - 2 453 2.et U 5 2.41s 5
2.3A 2'mW' 2re E
2200 2.2s %e 2.t se 2.1x 2000 L*I=I = l= I = I = I 7'" I 8'" I *** l "a* ~ I $ $'" I $2'" I Data Provioer. Laune Hertzlin 6944631 n.
1 1
OPERATOP EXAMINATION PERFORMANCE
. . 1arkey Point Units 3 & 4
) 1000% ,
I
OOce* Re: Pass 4
- y
- s. y %
! 95 0% g --f -
p -.
1 ,
i [ "4 i .
[
1 3 h l a i 't i s l t 90 0%
k-
- ~
j j y g j ! i E
$ h l l' 1 '
w ,
h 4 , 8 85 0 % h - -
$. Y 5
r
' 'f kl
- a .
l l
[
ti i i h ) , S D e h I m.,, .
Emune: l1991 1992 1993 1994 1995 1!94 2/96 3/96 . /96 5/96 6/96 7/96 8/96 9/96 10/96 11/96 12/96
- nrAC TEM 39 6 . 6 13 Paesed 39 6 . 8 13 . . .
ROfS8tO Peas % 100 0% 100 0% 100 0% 100 0%
OperAegGaken d~ 78 69 6' $8 . 64 . . 19 . .
Passed de 76 66 60 66 . 64 18 . .
Oper Reg mens % 94 0% k; 0% 96 0 % 95 0% 96 5 % 100 0% 95 0 %
DEFINITION I . ital License Examination (RO/SRO) results are reported for all candidates taking an Initial License Exam as conducted by the NRC Operator Requahficaton Examination results are reported for both RO's and SRO s This examination is administered annually by the utility and may be p.nlly aoministered by the NRO. Retests of operators who failed examinations are not included.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE initiaf RO/SRO License Exams The NRC at their last Regional Trarning Managers Meetn; No Taven No Passed Pass Rate %
0.0% (for fiscal year 1994) provided tne following data.
YTD 1996 C 0 YTD 1995 13 13 100.0 %
RO s Pass Rate 94 6 % RO's Pass Rate 91.0%
Ctperator Requal Exams instant SRO's Pass Rate 94 4 % SRO's Pass Rate 85.0%
No Taken No Passed Pass Rate % Upgrade SRO's Pass Rate 94.7% Average Overall 68.0%
Average overali 94.6 %
VTD 1996 83 82 93.8 %
YTD 1995 58 56 96.5 %
PERFORMANCE
SUMMARY
l l
No exams were given at Turkey Point in September.
Data Provider. Mana Lacal (PTN) 246 647E E.,
\.
l OPERATOR EXAMINATION PERFORMANCE
- St. Lucie Units 1 & 2 100 0 %
a
' W RO/SRO Pass %
g D Oper Rea Pass %
9 95 0 % - N w
1 j
90 0 % -
5 ( N e !
[ '
850% } - -
0 f
l s 3 a
i , F ff m I i 1 b h Emmes: l 1991 1992 1993 1994 1995 1/96 2/96 3/96 4/96 6/96 6/96 7/96 8/96 9/96 10/96 11/96 12/96 RotSRO Taken i 16 8 10 11 - - 4 - - . .
Pommed i 16 8 10 11 . . 4 - . .
RorsRD Pass % i 100 0% 100 os too os 100 c% 100 os eh i- -1 65 69 68 75 7s . - - - - . .
- Pummed i 61 60 68 68 71 - - - - - -
-c v n s t 64os e7 os im os ei os e7 ss DEFINITION initia! Ucense Examination (RO/SRO) results are reported for sti candidates taking an Inital Ucense Exam as conducted by the NRC.
Operator Requalificaton Examinaton results are reported for both RO's and SR0c This examinabon is administered annually by the utihty and may be jointly administered by the NRC. Retests of operators who failed examinatons are not included. l STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE inital RO/SRO Ucense Exams The NRC at their last Regional Training Manacers Meetng No Taken No Passed Pass Rate 'm, ~
(for fiscal year 1994) provided the following data:
YTD 1995 0 0 0.0% in,,,, gne g,,,, gne p,,y,, Exams RO's Pass Rate 94.6 % RC's Pass Rate 91.0 %
Operator RequalExamS Instant SROs Pass Rate 94 4 % SRO's Pass Rate 85.0 %
Upgrade SRC's Pass Rate 94.7% Average Overall 88.0%
No Taken No Passed Pass Rate %
^**9'" 8%
YTD 1996 0 0 0.0%
YTD 1995 73 71 97.5%
PERFORMANCE
SUMMARY
No exams were gwen in September at St. Lucie.
Data Provider Mike Allen (PSL) 467 4161 I
C.*
J i .
OVERDUE CONDITION REPORTS 100 1 -+ P Tf ,
90 - -
+ Junc j B0 g 70
\,
- s
- g 60 \
2 5 I 2
% so . I n 1 5 \
! U \
d e 4g i i i$ 30 \/\
k'
\ / \
10
\ /'
M%
Lhaft 1991 1992 l . 993 1994 1996 1196 2/96 3/96 4/96 5/96 6/96 7/96 8/96 9/96 10/96 11/96 l 12/96 PTN 6 0 0 12 C 1 : C : 7 PSL 95 25 51 0 8 19 29 29 13 Juno- 11 19 9 12 5 3 DEFINITION This graph shows Condition Reports that exceed assigned pnonty timeframe. This indicator takes a snapshot the last day of each month. Record the number of overdue condition reports the last day of each montn.
Severity Levels are as follows: A = 3 working cays B = 10 calendar days C = 30 calendar days ,
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE l
PERFORMANCE
SUMMARY
Data Pmves- (PTN) Ed Lyons 2464967,(PSL) J. Voomees 467-7587, and Bob Symes (Juno) 694-42B7 F-1
4 i QA FINDINGS i
i f P Tts
--O - PS. ,
e
- dr *
- June )
4- - -
1 ,
1 I I i T i a d s
- i '4 l j j ,
., '., l
? !
2
- l . \
.: 2 , S- ,
3 .
i .
,.. ~
O Unit 040 days 3140 days 61-00 days 91120 days 121150 days 151180 days > 180 days PTN O 2 0 0 0 0 1 PSL 5 3 4 4 1 0 3 Juno 0 3 1 0 3 0 2 DEFINITION The indicator represents the age of audit findings open a of the last day of the month. The cic.:k starts on the day of the 1
audit report transmittal and continues until Quality Assurance (QA) venfies that implementation has occurred.
'l i
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE l PERFORMANCE
SUMMARY
1 Data Prtmders T. Abombeho (PTN) 246-6581. W Bladow (PSL) 467 7111, and R. A. Symes (Juno) 69442S7 F2
NRC VIOLATIONS Cited and Non Cited (Year-to-Date) 24
~~
- pTENOV;
- 2 - + - DTN NCVs
, ek --C- PSL NOVs 20
) O PSL NCVs j .
/
' .s.~o<. m.* /
g
. i
/ _-.= m2m eu u un;
..-.m r...,:. , <
g ,o...o g ,, . J ., - .- m ,v.,,,
/
s, s. .+. . ./~ _ .o /
} ,;, y.. .
'l ! ..-
/ .. '
l , ,! Y ,! '
h.'
/ *,' 1995 Y-E Target 5 7 E 6 -
, \ J . J i '. ..-
0O--bO\ [ , ,h : 5 + ' , , ,
\ C h :: O "== O' f 0
Unit ' 1991 1992 1993 1994 11996 -1196 l 2/96 3/96 4#95 6/96 6/96 719 6 8/96 9/96 10/96 11/96 12/96 PTM NOVs 13 8 4 4 1 0 0 0 0 1 2 2 2 2 PTDI NCVs 21 7 13 12 ' 15 0 1 3 3 5 8 11 14 14 PSL NOVs e 8 7 6 21 1 4 4 e 9 9 17 20 23 PSL NCVs 3 3 3 3 12 1 1 1 5 10 13 14 17 17 DEFINITION Notice of Violabons (NOVs) are categonzed in terms of five levels of severity to show their reladve importance. Sewnty Levels I and ll are violatons that involve actual or high potential impact on the public. Seventy Level lli Molabons are causefor significant concern. Seventy Level IV violabons are less senous, but are of more than minor concem: i.e., if left t 'icorrected, could lead to a more serious concem. Violatons are counted on the date of the inspecton exit meebng. Molations are nveunted with respect to the date of occurrence (using tne date of the inspection exit meeting)instead of the date of the inspecbon rep .. as was done in the past.
Non-cited Molations (NCVs) are violabons of NRC regulabons for which no citaton will be issued.
STATISTICAL
SUMMARY
INDUSTR/ PERFORMANCE Sept M Year End Taroet NRC Violations PTN Cited 0 2 7 1995 IBG Group Mean 9.4 PTN Non-Cited 0 14 1995 Region 11 Mean 10.5 PSL Cited 0 20 7 1995 IBG Top Quartile Mean 3.6 PSL Non-Cited 0 17 1995 IBG Top Quartile Entry 6.0 1995 Region 11 Top Quarble Entry 7.0 PERFORMANCE
SUMMARY
Turkey Point received no Nobce of Molabons in September. Year-to-date, two violabons have been reported.
St. Lucie reported four Notee of Molatons in September for previous months; tnree potental Nobce of Molabons are pending investgaton. Year-to-date. the total confirmed is 20 See next page for details Data Proveers- (PTN) Gary Honrnger 2466078 and (PSL) Ed Weinum 467-7162 I
F-3
NOTICE OF VIOLATIONS - 1996 .
TURKEY POINT:
1 #96-06-02 Precondiconing of EDG fuel system pnor to surveillance test. Exit Meeting date. 6/14/96 2 #96-04-02 Failure to follow Chemical Volume Control System Operaung Proceoute cunny a Un:t 4 blender fiushing evolution. Exit Meeting date: 5/15/96.
ST. LUCIE:
1 #96-01-01 Temporary Changes to Procedures improperly Changed Intent of Procedures. Exit Meeting Date 1/26/96 2 #E03-01 Operators failed to follow procedures with four examples. Exit Meehng Date: 2/8/96.
3 #96-03-02 Inadequate design control of RCS boron dilubon procedure. Exit Meeting Date: 2/8/96 4 #E03-03 A 10 CFR 50.59 safety evaluaton was inadequate. Exit Meetng Date: 2/8/96.
5 #96-04-01 A containment gaseous /parbculate/ iodine monitor was rendered inoperable due to a fa: lure to follow procedures combined with a lack of proper follow through on the part of non-hcensed operators taking logs. Exit Meeung Date: 4/3/96.
4 6 #96-04-02 Failures to make required log entnes for reacDvity manipulations and a main generator hydrogen addition. Ex t i Meebng Date: 4/3/96.
] 7 #96-04-03 An EDG was rendered inoperable due to a failure to follow procedures while placing the fuel oil tank on recirculation. Exit Meebng Date: 4/3/96.
8 #96-04-04 Reviews of historical data for CEA maintenance revealed that post-modification tesung acceptance entena for Unit 1 CEA power cables were not apphed to post modification test data. Exit Meeting Date: 4/3/96.
9 #9 & O6-05 An audit of fire bngade member qualifications resulted in a violaton for failure to maintain current physicals. Exit Meebng date: 5/17/96.
10 #96-09-01 Failure to control overtime. Exit Meebng date: 7/8/96.
11 #96-09-02 Inadequate procedure for managing overnme. Exit Meeting date: 7/8/96.
12 #96-09-03 Failure to test tne Reactor Cavity Pressure Relief Dampers in Accoroance with tne Vendor's Technica! Manual Exit Meeting date: 7/8/96.
13 #96-09-04 Failure to perform adequate testing on the Reactor Cavity Pressure Relief Dampers. Exit Meebng date: 7/8/96.
14 #96-09-06 Failure to control contaminated tools in accordance with licensee procedures. Exit Meeting date: 7/8/96.
15 #96,11-04 Preconditioning of valves prior to surveillance. Exit Meeting date: 8/6/96.
16 # % 12-02 Failure to pedorm safety evaluation as required by 10CFR 50.59 for failure to recognize an unreviewed safety quesbon in the development of a safety evaluation for an EDG fuel oil transfer line valve lineup change (Level 111). Exit Meebng date: 7/12/96.
17 #96-12-03 Failure to coordinate design changes with the necessary changes to operating procedures as evidenced by three examples. Exit Meeting date: 7/12/96.
18 #96-12-04 Failure to assure that the design of the Circulating and intake Cookng Water System was correctly translated into plant arawings. Exit Meebng date: 7/12/96 i 19 #96-16-01 Failure to make a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> security event notfication to the NRC in accordance with 10 CFR 73.71 and plant procedure 0006125 for the July 26,1996, tampenng event. Exit Meeting date: 8/23/96.
20 # % 16-04 Failure to follow procedures for key control for the Unit 1 PORV key lock switches. Exit Meeting date: 8/23/96.
Potenbal Notce of Violations at St. Lucie for September were reported as follows:
1 #96-13-01 Failure to include some SSC's within the scope c' the Rule in the Plant's Maintenance Rule Program (PASS, Communicabons., Service Air, Radiation Monitors. Exit Meebng date: 9/20/96 2 #96-13-02 Failure to follow promdures in acbons required by ADM 17.08 (multiple examples). Exit Meeting date: 9/20/96.
3 #96 13 03 Improper use of MPFFs as indicator of rehability for safety significant systems. Exit Meeting date: 9/20/96.
Note: The above list of has been slightly revised to align with St. Lucie's NRC Violatic 1 descriptions.
Data Providers- (PTN) Gary Holknger 2464078 and (PSL) Ed Wemkam 4ti7-7162 F4
. _ , . _ - ...__._.._.-__---_-_.m_-. . . _ . - _ . . . - - . _ . . - - - . - - - - . - . . - - . . ~ , . - . - - - - - 4._.--- - - --
4 1 .
l LICENSEE EVENT REPORTS g, 25 (Year-to-Date) l I
' /
[ --+- PTN
-C- A S.,
- 20 0
/
7 I &
4 s
z 15 ;
8.
E Een 10 -
C
}
j 5 ^
i 1'
O Unit 1991 1992 1993 1994 1996 1/96 2/96 3/96 4/96 8/96 8/96 9/96 10/96 6/96 l 7/96 11/96 12/96
>PTN 20 24 a 12 7 1 5 5 7 8 9 i 9 10 10
' i* SISt. 9 10 8 15 18 1 1 5 5 7 11 l 11 13 16 DErlNITION License Event Reports (LER) are submitted to the NRC by tne licensee to report unusual occurrences prescribed by 10CFR50.73.
1 i
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE l l
Sept M PTN 0 10 PSL 3 16 PERFORMANCE
SUMMARY
Data Providem- (PTN) Gary Hohnger 246-6078 and (PSL) Ed Wemkarn 467 7162 F-5
1 ,
4 i
INPO ASSESSMENT RATINGS o
4 Sf, j 4 00 s :TN 1
U I S- --
3 50 3 00 - -
l I
j I:o E
g 200 - - - - - - - - - - - . - - - -
a 1 60
- - ===== - .
1 00 l -
- 02 -
1 - -
~ --
0 00
]
1987 1988 1989 1990 1991 1992 1993 } 1994 1995 l 1996 Unit 1986 } l l 4 c; 3 00 4 0t 3 oc j 2 0t 21 j 10c l PTN a ct ! (
2 00 10c t ot 10t l
! PsL } l } l
}
INPO ASSESSMENT PROGRAM DESCRIPTION The Institute of Nuclear Power Operations (INDO) conducts periodic evcluations of site activities to make an overall determrnation of et safety, to evaluate managernent systems and controts. and to identify areas needing improvement informat:or' is assemb>ed t.m dist'ussions. interviews ocse*vations. and reviews of documentation Evaluation Frequency: INPO's goa' is to visit ea:n plant on an average of every 18 months. However, this frequency may vary depending upon tne previous assessment ratings. For instance,if a plant is rated a *1' or *2', the interval between assessments is usuahy 20-24 montns.
If a plant is rated a '4' or a '5', the assessment interval is318 months.
Performance Cateoorv Ratncs Category 1: Overali perderma ice is excellent. Industry standards of excellence are met in most areas. No signrncant weaknesses notec Category 2: Overall performance is exemplary. Industry standards of excellence are met in most areas. No significant weaknesses noted Category 3. Overall oedorma,ca is generally in keeping with the high standards required in nuclear power. However, irnprovements are needed in a numoer of areas. A few significant weaknesses may exist.
i Category 4: Overall performance is acceptable, but improvements are needed in a wide range of areas. Signrficant weaknesses are noted n severa: areas Category 5: Overall perfo rnance does not rneet the industry standard of acceptable performance. The ma gtn of nuclear safety is measuraciy reduced Strong and immediate management action to correct deficencies is required. Speoal attention.
assistance anc follow-up are required NOT.E: If a plant is found to be operating without an adequate margin of nuclear safety. INPO will request that the plant be snutdown. or not staned up PERFORMANCE
SUMMARY
Turkey Point and St Luce rece:ved an INPO category rating of *1'in 1995.
The next evaluations for Turkey Point and St Luce are expected in the last quarter of 1996 and first quarter of 1997, respectively.
Data Droveeni (PTN) Gary Hollinger 2464078 and (PSL) Ed Weinkam 467 7162 F-6
- i. .
! NRC SALP CATEGORY RATINGS i
2 50 i
j W PTN Ratin; 2 00 - -
O PSL Ratin;
}
4 1 $ 1.50 - - -
.s
} %
, a:
$ 1.00 - - - - - -
}
0 50 - - - - - - -
0 00 -
l 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1
PTN Ranno 2.2? 2 te 2 25 2 14 1 86 1.38 1 38 1.29 1.00 1 00
]
Pened Endng 4/30/85 5/31/87 6130/88 7/31/89 7/31/90 9/28/91 1/30M 8/27/94 8/17/96 1 55 1.20 1.29 1 14 . 1.00 1 00 - 1 50
- PSL Ranno Penod Enchng 4/30/86 10/31/8' 4/30'89 10/31C 5T92 - 1/1/94 ' . 1 @ 96 l
SALP PROGRAM DESCRIFb d
}
l it a N pahey W Ine NRO t use the Systemane Assessment of Lxansee Performa,ce (SALP) process e a1culate the agency's coselyabor:s and msgnts on beensee stety performa1ce l The SALP report comnineses those observanons and esgnis Evauabon Ffoouener Ihe NRO wdl normaly review and evauste eacn poner reater Icensee that possesses an opec: ting bcense a lemt every 18 montns When the NRO oetermmes tha'
{
Ine pef 1ormance wiltraits a fnore frecuent evauanon, the normd SALP troquency raay be erremad Tne asessment pened may be exlonoed e a maomum of 24 rnonins wnen a pant l
receives a Category 1 ranng m all four funcnona areas Functonal Areas Performance a genera *y evausted a tour {41 funcnona arez 1 Ralt Operaners The functona area conssts enielly W the control sia exacunon of actv'nes diracey related e oce anng a pant it ecluoes a hvities suen as plant startup, parer l
operalons. Want snutoowit and system kneups. It aso meluoes Irutal aid reoualifiction tranang of hcenseo oDerators 1
2 Maatensice The functons area mctuces at acevites Esccized we emer diagnostc. predcave. preventrve, or cor'ecove rnantenaice of pa1t structures. systems and components.
! or manamarce or ine pnyses condioon of ine aant 3 Enocieeano Tns funcuana sea a$oresses tne aoeauacy of incnnca aid engmeenng supcon lor all pant a:tvities it actuces ali tcensee acevmes assec.ated witn aesgn conirct tv oesyn. mstalianon. and lesDng of piant rnodificabons; engmeenng and t!cnnca suppJrt for operaDons, outapes,inantenance, tesang. survedlance. 31d procurement actvines j Clifigursion management; oes:g4 basis informaDon and its retnevat and UplX)rt for licensmg actvees 4 Ptz't Suacort Tha functons area cove's ah acevities retmed e pant support kmchans. ecluomg raficiogca contnys. emergercy precareoness. secunty, chemistry. and tre protecto."
l Houseuecing contras ne aso aciuoed m inis au j Pe@maice Cawwr Rannes Lcensee penormance m ucn funchonal sea a assessed by asgning a caegory ratng as docussed been 4 Category 1. Lcenses attenoon and evolvement nave Deen propery focusec on s#ety and resulted m a sucenar leve, of safety per1ormaice Category 2 Licensee attennon and ev v 'ernent are normally men locused and resaltec iri a goos ievel of smery performaice Caegory 3 Lcensee attenton av! mvorvement nave resuned m an a:ceptaue levei of certormance kweve , penormance may ecot one or more of ine tonowmg cnaractenstes mettecove proo av rd igneca,t asuesaack of ccrectrve acnon incrougnness. and oerciencies m root cause anayss Because ine magm e una:ceotame pe termance r imDottimi EDeCtb a smah. mereased hRC and licensee aftenDon a reQulfed PEhPORMANCE
SUMMARY
The Nuclear Regutatory Cornmason asued its Systematic Amessment of Licensee Performance (SALP) report br the Turkey Portt plant for August 28.1994 through August 17,1996. For the secono correcutnre time, the plant remvved Category 1 (superor) ratings in all four funcbonal areas rated by the NRO Turkey Point St. Luoe i Pnor Most Recent Pnor Most Recent Funceonal Area
" 1 2 Plant Operations 1 1 i 1 1 2 Mamtenance 1
! 1 1 Engineenng 1 i
Plant Support 1 i i
O eran 1.00 1.00 LOO 1.50 Data Previoers' (PTN) Gary Hollinger 246-6078 and (PSL) Ed Weinxarn 457 7162 F"
1
. l l lNVENTORY VALUE ACCOUNT 154e300 l l
, l
- 80 l I
l 70 -+-- PTN l i --O- PSL 1
CT 2
! $ 50 j d
E I I ~ 40
' II g ] .
'N:
1996 Y-E Target: $ 38 (SM.i l e : : : : :
i s
} l 30 s
j 20 i l l
l
$ 10 i
i s
i 6.-
! v ent , 1ssi tssa 1ssa tissa asss- ctses. arms sees 4 Ass .stes , sies ,7tes ases. . stos . 1oins 1 ties 12/ss
/ 'M9i - 79 1 74 7 54 6 424 37 4 37 4 37.2 36 0 35 1 34 9 35 1 35 3 35 1 34 9
" "TSL' - 58 6 65 2 60.2 43 7 39 4 42.0 42 3 43 5 42 9 43 6 41.3 42 7 41 3 40 5 I DEFINITION This indicator reflects tne valve of Account 154.300. This account reflects materials needed to keep operational the physical I l
equipment and facilites of the plant (e.g., spare parts, consumables, commodities, tools). The information is pulled from SAR Report #G0009R72 501. The Passport system utiltzes SAR for system data reporbng.
l l
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE l St,a.j g.nd n % Chanae YE Taroet IBG (Year 1995}- ' Total Average $39.2 Million PTN Monthly 351 34.9 -0.6% Top Quartile Entry $35.0 cc.,
Y T-D 37.4 34.9 -6.7% $38M Top Quartile Average $29 3 Million l PSL Monthly 41.3 40.5 1.9% i YT-D 39.4 40.5 2.8% 538M Nalue does not include Capital as defined by PRut, 1 PERFORMANCE
SUMMARY
l
. Turkey Poirr Regular Invencry decreased by $0.2M in Sepumber. l
. St. Lucie's Regular inventory decreased by $0.8M for the month. ,
1 l
Data Providers: (PTN) Dick Rose 246-6692 and (PCL) Sil Boessy 467-7582 G-1
. . _ _ _ _ . . _ . -_ .-_ _ _ . ._____._._._..._._,m.___-. _ . . . . _ . . . . . . . _ _ . _ _ _ . _ . . _ _ - _ . . _ . . . _ _
i OPEN PLANT CHANGES / MODIFICATIONS (PCIMs) 35c
- --+- PT5 300 --
i \ ^N
- \
i 250 4
i .* 200 5
c.
C
^ A 150 100 P_Th &
Desiga 26 2' Review 10 16 Working $2 71 50 UMaw 69 113
' Tota' 15? 227 0
Unit 1991 1992 1993 1H4 1995 1796 2/96 3/96 4/96 5/96 l 6/96 7/96 8/96 Sit $ 10/96 11196 12/96 i PT91 - 240 242 230 219 170 170 155 153 157
'PSL 316 326 269 274 285 132 303 295 227 DEFINITION l This indicator tracks the total number of PCMs in the modification cycle. Tne pu. ose is to provide management a snapshot of the number of PC/M s. Include all PC/M s in design (not issued to the piants) review (issued to the plants for review). and implementation or drawing update phases. The PC/M is considered oper, until drawing update is complete.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE PERFORMANCE
SUMMARY
Data ProvideT (PTN) Isidr0 fboseco 246-6184 and (PSL) David Brown 457-704E H1
, , . - - - - . , . - . . . . . . . . . . . . . . . - _ . - _ . . . . _ . ~ . . . . _ _ . , . .. . . . _ _ . . - . . ,- .--.-..
~
i .
j OPEN TEMPORARY SYSTEM ALTERATIONS
~
i
^
30 ._
+ PTN
- --O- P S L 25 l
l 1 E 2a i E C
a i E 15 l h l I
t l C i
- 8. l
, O to l 1 1 i
^
5 c l
. 0-Unit 1991 1992 1993 1994 1996 1J56 2/96 3/96 4/96 8/96 6/96 7/96 8796 9/96 10/96 11/96 12/96 1
'PTN 5 5 2 3 6 3 3 2 0 0
. h.. 17 15 16 21 24 27 19 20 19 16 l DEFINITION
? A temporary system alteration is a modificaton made to plant equipment, components, or systems that does not conform with l approved drawings or otner design documents; a modificaton that is necessary for contnued safe plant operaton; a modificabon that will remove a nuisance or distracton to the Plant Operators; a modificaton necessary to enable the plant to start up in a safe manner.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE l Ee2t Year End Goal PTN 0 5 PSL 16 10 PERFORMANCE
SUMMARY
t 7
4 Data Providers: (PTN) Julio Balaguero 2464971 and (PSL) Kns Mohindroo 467-7482 H-2
___...._._.__..._.._.__.m. ._. . . . . . . _ . _ ._ _ . . . . __.._._._... ._._ _ _ _ . . . _ . . _ _ . _ . . . . . _
CONTAMINATED FLOOR SPACE 6000 I
+ PT*,
i o
\ --C DS.
4 50C0 \
d 4000
\
. T
- a \ li\
m 3000 i B 1 E l 1
I
, 2x0 i
J l
l i 1000 I i
a 0 _ _~
i 1992 1993 19M 1996 1/96 2/96 3/96 4/96 5/96 6/96 7/96 6/96 Sf96 10/96 11/96 12/96
. Unit 1991 4
1750 50 330 700 3748 32 559 77 1048 250 489 j V PTDI i 4600 2848 1480 250 280 12 12 4354 2725 800 505 242 l j .PSL 561C 4351 l
DEFINITION l j This indicator, designec to measure contaminated floor space with removable activity 11000 dpm/100cm sq beta / gamma or 2 20 j dpm/100cm sa sipna. is counted against the base. Areas that can be specifically exempted from the base include: reactor a
containment building enemica' volume control system deminerahzer room and long term process areas such as the decontamination l facihty. Contaminatec components such as charging pumps, evaporators. etc. are not incluoed as part of ' recoverable
- f!oor space I
(i.e. not considered ficor area you can walk or step on).
1 PTN: Total Base (117,746 sq. ft.) Exempted Area (6,110 sq ft.)
' PSL Total Base (112,422 sq. ft.) Exempted Area (7,722 sq. ft)
^
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE M Tamet 4 PTN 489 50 PSL 242 50
- PERFORMANCE
SUMMARY
i Turkey Point and St Lucie's Contaminated Floor Space was higher than the year-end target i
1 Data Providers: (PTN) John Undsay 2466548 and (PSL) Hank Buenanan 467 7300 i
11
DRY ACTIVE WASTE: GENERATED, SHIPPED OFFSITE
, (Year to-Date) , l 18000 0 PTN Generatei 16000 - * * +
- PTN Shipped
--o--- PSL Generated
-O PSL Shipped 14000 -
12000 g _g. .g i 10000 0
4 0 8%0 '
6000 O -
f 4000 - #
. 4 , e...$..4' UnM 1991 1992 1993 1994 1996 1/96 2/96 3/96 4/96 6/96 6/96 7/96 8/96 9/96 10/96 11/96 12/96 PTN Generseed 8100 425 515 3925 4115 4355 4675 5285 5415 5655 PTN SNpped 2560 0 C 0 0 0 2560 2560 2560 4368 I PSL Generosed 11740 0 820 1845 2595 7595 13040 14350 16060 16310 PSL SNpped 13003 0 2080 3120 5314 7508 9702 11896 11896 11896 DEFINITION Generated is an estimate based on the number of " yellow bags" initially generated prior to surveying for free release or ;
shipment as radwaste.
Calculabon: Number of yellow bags x 5 cubic feet = Esbmated Monthly Genmssd Waste figure.
Shicoed o'fsite - The amount of dry active radioactive waste that FPL ships to eitner Soentfic Ecology Group inc. (SEG) or Amencan Ecology Recycie Center (AERC) for processing STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE PSL made 6 shipments to SEGin 1995.
PTN made 3 shipments to SEG in 1995.
PERFORMANCE
SUMMARY
Turkey Point shipped 1,802 Cubic Feet of Dry Achve Waste in September.
Data Providers: (PTN) Jonn Lindsay 24%548 and (PSL) Hank Buenanan 467-7300 1-2
r . 1 PERSONNEL CONTAMINATION EVENTS
- . (Year-to-Date) l 180
+ CTh. l
$ 16C c- p 3, --
1 140 l
120 E
N O
8C I
$ h 8
60 40 1
20 o ;- -
1993 1964 1996 1/96 2/96 3/96 4/96 8/96 6/96 7/96 9/96 9/96 10/96 11/96 12/96 Unk 1991 1992 4 9 23 36 38 43 47 52
- etPTN 163 85 95 100 73 32 87 76 84 82 0 2 2 5 83 92 93 95 95 sPSL DEFINITION l I
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 Frisker is observed.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE Sept Y-T-D PTN 5 52 PSL 0 95 PERFORMANCE
SUMMARY
l Data Providers:(PTN) Jonn Undsay 2464548 and (PSL) Hank Buenanan 457-7300 l l
1-3
) .
!' RADIATION EXPOSURE (Year-to-Date) .
1000 i e I !
900 . _. --+-- CTN Y-T-C _
-O- PSL YJ-;
j 800 l
4 y 7C0 g a $
600 -g
- \l
, e s F5'. 6'E'T5M3eI43Ql
. f s NO:t 4.;: 1995 erra :
\ { / / k,h aciuste: to rebe:: TLD ca:4 i E l = 0
- i /
1 0: 300 i PTN Y-E Target. 275 ll I 200
/: : 0 0 100 0 t UnN 1991 1992 1993 1994 1996 1/96 2/96 3/96 4/96 6/96 6/96 7/96 8/96 9/96 10/96 11/96 12/96
- PTN Y-T-D 9380 324 9 281.8 476.2 214 6 53 9.5 159 2 165 5 168 7 171 0 172 8 175 4 178 6 PSL Y 7-0 451.3 2445 459 9 504.7 412 8 30 90 13 0 21 9 209.2 321.9 371 3 374 6 3771 DEFINITION Collective Radiation Exposure is tne total effecove 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 reported in man-rem for tne station. Current month readings may be taken from the direct reading dosimeters (DRD's).
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE Sect ),7,Q YTD Taroet Man-Rem PTN 3.2' 178.6 260.0 WANO (PWR's) (two units)
PSL 2.5' 377.1 460.0 1995 Median 306 Year-End Targets: 1995 Goal 370 PTN: 275.0 PSL ; 485.0 PERFORMANCE
SUMMARY
. Turkey Point and St Luce's Y-T-D Collectve Radiaton Exposure was below Y T-D targets.
Data Provdem (PTN) John Unasay 246-6548 and (PSL) Hank Buchanan 457 7300
' includes DRD count I-4
. -- _. .. , . . - . _. . - - - . . . - . . - , . .. _ - . ~ . . . - -
! e O&M BUDGET - DIVISION
- , (Year-to-Date) 350 0 i ---4-- Actual
. . - - . . Budget 300 0 i ,.
250 0 I
4
.f 200.0 ,'
i t' ..'
- E '
! $ 150 0 ,.
100 0 i ,
,'^
- 50 0 on 1991 1992 1993 1994 1996 it96 2/96 3/96 4/96 6/96 St96 7/96 Sit 6 9/96 10/96 11/96 12/96 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 Budget 333 3 314 6 326 4 3C2 0 279 2 17 8 36 7 75 8 104 8 129 6 147 4 164 0 179 6 220 1 243 0 265 9 288 9 Verlance (*/ ) 27 -62 .11.0 -56 -35 -24 9 -14 9 11 1 -78 -09 10 1 11 1 90 57 DEFINITION Coerating and Maintenance Expenditures include Nuclear Division operation and maintenance exoenses associated with direct employees, contractors and consultants, equipment, toois, design, engineenng and other items / activities required to sustain the electncal generation of the plants and to provide required support. Fuel costs, corporate aoministrative and general expenses, and charges from other departments outside the Nuclear Division are excluded.
Y T-D Actual Exoenses . Y T-D Budoeted Exoenses x 100% = O&M Variance %
Y-T-D Budgeted Expenses STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE Sect Y T-D Actual (SM) Y T-D Variance ($M) $
O&M Buccet 1993 :32.5 (SM) 12.5 (SM) 5.7% IBG Actual 1995 Average $334.1M 995 '.64.7 (SM) u.8 ($M) -8.2% IBG Top Quartile Entry S277.6M IBG Too Quartile Average S234.2M 1996 Y-E Buoget: 288 9 (SM)
PERFORMANCE
SUMMARY
O&M Expenditures tnrough September 1996 were 5232.5 milhon which reoresented a budget overrun of $12.5 million (or 5.7%) Sign:ficant contntutors to the vanance include: St. Lucie Unit 1 cutage scoce changes pantally of' set Dy underruns on the Turkey Point Termal Ucrate Project and by project and matenal purenase cancellations.
Da:a provioer: Laurie Hertzlin 6944631 t
1- 1
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e CAPITAL BUDGET - DIVISION l
l ,
(Year-to-Date) l 180 0 160 0
'. Budget -
e !
140 0 ,
'. l 120 0 5 '.
l k 100 0 ,
= .
~,
80 0 l
60 0
> 4
'I 40 0 20.0 _ _
,....... ... y ,,,..... -
00 1991 1992 1993 1994 1996 itto 2/96 3/96 4/96 SID6 6/96 - 7/96 8/96 9/96 10/96 11796 12/96 Actuar 15C7 68 4 90 3 76 5 47.2 15 25 29 63 93 12.1 12 9 15 7 16 4 Budget 179 6 75 1 101 4 87.7 64 7 48 71 11 1 15.7 17.9 19 8 22 6 26 3 27 8 33 1 33 1 39 2 Vertence (%) - -16 1 90 11 0 -12.7 -27 0 67.6 650 -73 7 59 7 -47 7 38 6 42.8 -40 4 -40 9 DEFINITION Capital Expenditures are those directly incurred! budgeted by the Nuclear Division for the construction of new utility plant additions and improvements made to increase efficiency, reliability or safety. Capital fuel costs are excluded.
%T-D Actual Expenses - Y-T-D Budaeted Excenses x 100% = Capital Vanance %
Y-T-D Budgeted Expenses STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE Sect Y T-D Actue ($',4 *' T-D Vanance ($M)%-
Capital Budaet 1996 16 4 (SMi -40.9% IBG Actual 1995 Average $75.8M 11.4 ($M)
-42.8% IBG Too Quartile Entry $42.6M 1995 24.0 ISM) -18.0 ($M)
IBG Too Quartile Average $27.2M 1996 Y E Sudget: 29 2 ISM)
PERFORMANCE
SUMMARY
Oapital Expenditures tnrougn Septemoer 1996 were $16.4 million which represented a budget underrun of $11.4 million (or 10 9%). Significant centncutors to the vanance include: Plant pro}ects cancelled / deferred /or reclassified as O&M, and, uncerrun in tne Steam Generator Replacement Project (SGRP).
Data provider. Laune Hertzhn 694-4631 J- 2
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W. R. Corcoran W. Kleinsorg 21 Broadleaf Circle Nuclear Regulatory Commission Windsor, CT 06095 101 Marietta Street N. W., Suite 2900 Atlanta. GA 30323-0199 T.P. Johnson NRC Senior Resident !nspector Kerry D. Landis, Region 11 PTN/ PLT Nuclear Regulatory Commission 101 Marietta Street N. W., Suite 2900 Atlanta. GA 30323-0199 Z-1