ML20137N205
| ML20137N205 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie, Turkey Point  |
| Issue date: | 06/14/1996 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20137K821 | List:
|
| References | |
| FOIA-96-485 NUDOCS 9704080290 | |
| Download: ML20137N205 (46) | |
Text
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i l FPL NUCLEAR DIVISION i
i TURKEY POINT NUCLEAR STATION ST. LUCIE NUCLEAR STATION l
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MONTHLYINDICATOR l REPORT ,l l l May 1996 I
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! Issued: June 14,199 j
40 0 970402 BINDER 96-485 PDR
l FPL NUCLEAR DIVISION TURKEY POINT NUCLEAR STATION ST. LUCIE NUCLEAR STATION i
l MONTHLYINDICATOR REPORT l i
! May 1996 ;
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issued: June 14,199 40 0 970402 BINDER 96-485 PDR
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FOREWORD The Nuclear Division Monthly Indicator Report presents a compilation of performance
- indicators which provide a quantitative indication of performance. Specific areas of focus include nuclear and personnel safety, plant reliability, and economic i
performance.
i The specific indicators included in this report have been selected by senior management as key indicators of operating performance. Summaries of NRC indicator and WANO indicator performance have been incorporated in this report.
Data contained herein will be refined on the basis of feedback from data providers, of continuing quality control efforts, and of comparisons to other data sources. Each
- monthly report will reflect the best available data.
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l TABLE OF CONTENTS Foreward i D. PERSONNEL INDICATORS Table of Contents ii OSHA Recordables.- - D-1 Lost Time injuries.. . .
..D-2 l Management Summary lii Regular Staffing-- .. D-3 i Nuclear Division Business Plan Indicator Overview v l E. TRAINING INDICATORS l NRC Indicator Performance Overview Turkey Point vi i Operator Exam Performance Turkey Point E.1 Operator Exam Performance- St. Lucie.= =E2 NRC Indicator Performance Overview St. Lucie vii WANO Indicator Performance Overview viii F. NUCLEAR ASSURANCE & REGULATORY INDILATORS WANO Indicator Variance Explanations ix Overdue Condition Reports.= F1 OA Findin0s... ..- F-2 A. WANOINDICATORS NRC Violatons: Cited and Non-Cited.= .. . F-3 Licensee Event Reports (LERs).- F-4 WANO Weighted Overall Performance - A1 INPO Assessment Ratings.- F-5 l I
Unit Capability Factor... A-2 NRC SALP Category Ratings- F-6 Unplanned Capability Loss Factor- -
-A3 Unplanned Auto Trips Per 7000 Hours. Critical A4 High Pressure Safety injection System Performance.. .A5 G. MATERIALS INDICATORS l Auxiliary Feedwater System Performance - A-6 Emergency AC Power System Performance.. : A.7 inventory- . G.t Thermal Perfarmance. .. A-8 Fuel Reliability . . . . - . A-9 Chemistry Index - . A 10 H. TECHNICAUENGINEEHING INDIC ATORS Radiation Exposure.: . . - - - . - A 11 Low Level Waste. ..-... A-12 Open Plant ChangesModifications - H-1 Industria! Safety Performance.- - A 13 OpenTemporarySystem Alterations.... H-2 B. OPERATIONS INDICATORS 1. RADIATION PROTECTION INDICATORS Equivalent Availability Factor. B-1 Contaminated Floor Space . 1-1 Capacity Factor (MDC Net). B-2 Dry Active Waste: Generated, Shipped Off Site:: 1-2 B-3 Personnel Contamination Events.. ; l-3 Fuel Utilization (PTN)....-:: .
Radiation Exposure (Y T D).. , 1-4 Fuel Utilization (PSL).. B.4 Forced Outage Rate . B-5 Unplanned Auto Tnps - -B-6 J. BUSINESS INDICATORS O&M Budget -Division -J-1 C. MAINTENANCEINDICATORS Capital Budget - Division = -J-2 Open PWO's - . . - - . C-1 PWO Aging Curve. C-2 PWO's Greater Than 12 Months Old = C-3 Appendix Non-Outage PWO's- C-4 Control Room Instruments Out of Service.... .. -C-5 Distribution List. Z1 ii
. MANAGEMENT
SUMMARY
OPERATING PERFORMANCE Turkey Point Unit 3. Unit 3 operated at 100.0% EAF in May. For the year, the EAF was 92.5% which is below the 95.0% Y-T-D target.
Turkey Point Unit 4. Unit 4 operated at full power for the month; EAF was 100.0%. Year-to-date, EAF was 74.8% Y-T-D, which is higher than the Y-T-D target of 65.8%.
St. Lucie Unit 1. Unit 1 was shutdown during May for a scheduled refueling outage. For the year, the EAF was 75.3% which is slightly higher than the Y-T D target of 74.9%.
St. Lucie Unit 2. Unit 2 EAF for the month was 98.8%. Power losses were attributed to problems with the B .
Start-up transformer (2.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />); Turbine Valve testing (0.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />); Waterbox inspection (4.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />); and, failure of a control fuse which caused isolation of heating steam to MSR's (1.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />). Year to-date, EAF was 93.5% which is below the target of 95.0%.
Equivalent Availability for the Nuclear Division year-to-date was 84.0% which is higher than the 82.7%
targeted through the period.
No Unplanned Automatic Trips occurred in May. 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 May Y T-D May Y-T-D Gross Generation (MWh) 529,560 2,421,263 518,780 1,893,808 Net Generation (MWh) 505,194 2,305,097 494,325 1,798,958 Net Heat Rate (Btu /KWh) 11027.5 n/a 11255.3 n/a Equivalent Availability 100.0 % 92.5 % 100.0 % 74.8 %
Capacity Factor 102.0 % 94.7 % 99.8 % 74.4 %
Auto Trips 0 1 0 0 Forced Outage Rate 0.0% 5.6% 0.0% 1.0%
PSL Unit 1 PSL Unit 2 May Y-T-D May YTD Gross Generation (MWh) 2,422,760 655,450 3,025,530
, Net Generation (MWh) 2,291,299 621,508 2,861,795 Net Heat Rate (Btu /KWh) & n/a 10895.7 n/a Equivalent Availability 3 75.3 % 98.8 % 93.5 %
Capacity Factor C) 75.2 % 99.6 % 93.6 %
l Auto Trips 0 0 0 Forced Outage Rate 2.2% 0.0% . 1.7%
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- MANAGEMENT
SUMMARY
l l REGULATORY PERFORMANCE l l
Turkey Point reported one NRC Violation in May-l
- 96-04 Failure to follow Chemical Volume Control System Operating Procedure during a Unit 4 blender flushing evolution. Exit Meeting date: 5/15/96.
Year-to-date, Turkey Point has reported one NRC Violation.
St Lucie reported no NRC Violations in May; however, one potential violation is pending investigation:
- 96-06-02 Fire brigade members not fully qualified. Exit Meeting date: 5/1/96. l l
Year to-date, St. Lucie has reported eight (8) NRC Violations. I l
l COST PERFORMANCE O&M expeditures through May 1996 were $128.5 million which represented a budget underrun of $1.1 million (or 0.9%). Significant contributors to the variance include: St Lucie Unit 1 outage schedule change; deferral of St. Lucie Spare Low Pressure Turbine Rotor refurbishment; and Turkey Point Thermal Uprate costs lagging budgeted cash flows.
~ Year to-date, O&M budget performance variances are stratified as follows:
Turkey Point Site Specific $0.7 million (or 1.2%) below budget St Lucie Site Specific $0.2 million (or 18.6%) above budget Other Nuclear Division $0.6 million (or 4.0%) below budget Capital expenditures for May Y T-D were 59.3 million. This represented a budget underrun of $8.5 million (or 47.7%). Significant contributors to the variance include: Plant projects cancelled / deferred /or reclassified as O&M; and, underrun in Steam Generator Replacement Project (SGRP) due to change in outage start date.
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Year-to-date, Capital budget performance variances are detailed as follows:
Turkey Point Site Specific $1.1 million (or 88.2%) below budget St Lucie Site Specific $6.2 million (or 40.8%) below budget Other Nuclear Division $1.2 million (or 83.3%) below budget iv
NUCLEAR DIVISION BUSINESS PLAN INDICATOR OVERVIEW I (DATA THROUGH MAY 31,1996) 1996 1996 1996 Indicator Plant YE YTD YTD Comments Target Target Actuals Collective Radiation Exposure PTN s 275.0 s 240.0 169.1 Turkey Point and St. Lucie were PSL below Y-T-D Man-Rem targets.
(Man-Rem) s 485.0 s 283.0 216.6 Current month includes DRD count. 4 NRC SALP Ratings g;4 1 The SALP for St. Lucie ending 1/6/96 was 1.50; for PTN, the period l
l gjyfa ends Aug. 31,1996.
PTN reported one NRC Violation in NRC Violations PTN s7 h 1
<7 F May; PSL reported one potential PSL - 8 f ,
violation: Y T D, has eight violations.
PTN3 iP% 1 Unplanned Automatic Trips PTN4 0 No unplanned automatic trips were
<3 PSL1 PSL2 h4
%p 0 0
reported in May.
l For .the year, O&M and Capital I' Capital 39.2 17.9 9.3 actuals were below Year End Budget Performance O&M 253.0 129.6 128.5 targets; underruns were mainly due
($ Millions) Div. Total 292.2 147.5 137.8 to schedule revisions and project undcauns.
PTN3 95.0 95.0 92.5 PTN4 and PSL1 exceeded Y-T-D l PTN4 82.0 65.8 74.8 EAF targets in May. Division EAF l Equivalent Availability Factor (%)
PSL1 78.5 74.9 75.3 Y-T D was 34.0%, which is higher PSL2 95.0 95.0 93.5 than the 82.7% Y-T-D target.
M&S Inventory Levels PTN s 38 bb! 34.9 PSL exceeded the Y-E target by
($ Millions) PSL s 38 M 43.6
$5.6M in May primarily due to the WM scheduled Unit 1 outage of 4/29/96.
$ Production Cost PTN 1.75 2.13 2.06 PSL Production Costs (c/KWh)
I (0&M and Fuel) PSL 1.55 1.77 1.85 were higher than the Y-T D target in 2 May.
'G r Total Cost (0&M, Fuel, and Div. Total 4.56 5.04 4.99 in May, Division Total Cost (c!KWh)
$ Capital Carrying Costs) was below the Y T D target. j
" FPL 2045.0 MW 1942.0 Total Nuclear Division Staffing n9 s LT Contr Total 463.0 2508.0 k%
Ts#h 425.0 Levels year-to-date was below the 2367.0 Y-E target.
,ypm PSL1 began a scheduled refueling PTN3 NA NhN O utage on 4/29. Future refueling Refueling Outage PTN4 45 bE3 35 l Duration (Days) PSL1 63 53 33 utage se .edules are: {
PSL2 NA #$$ 5 PTN3 03/08/97 PSL102/03/98 !
!$a!!.
m ;r PTN4 09/15/97 PSL2 04/15/97 i Lost Time injuries per 200,000 ked Month PTN 0.30 7 0.12 No Lost Time Injuries or Restricted (12 nn$ng) PSL 0.30 0.33 Duty Cases were reported in May.
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NRC INDICATOR PERFORMANCE OVERVIEW I for Turkey Point (Data through Quarter Ending September 30,1995) l LEGENo Plant Self-Trend Deviations From Peer l@ Short Term Deci ned improved Group Median L0na Term Worse Better OPERMIONS 0.72 0.0 Automatic Scrams While Critical 0.0 0.22 @
( .0 0.0 Safety System Actuations
'9 0.0 0.0 -0.45 Significant Events 0.0 0.0 !
0.30 -0.27 l Safety System Failures 0.30 g o.o Cause Codes (ALL LER's) M 0.12 0 Adminstrative Control Problem _
Lcensed Operator Problem '8M 0 u 0 0'72 Other Personnel Error Oh g l
0.42 Maintenance Problem 1j g
Desptonstructiordnstallation 0.25 0 Fabncation Problem 0.0 . .09l M 0.40 0
Mscellaneous 00 0 SHUTDOWN m 0.18 -0 Safety System Actuations 0.0 .04lk\\\\\\\\\1
- 0. 78 0.0 0.0 Significant Events k\\\\\%NNNNNNNN 5.40 -0.57BS MES
- 0.53 Safety System Failures
%\% _ j 2.40 0.37 N, Cause Codes (ALL LER's)
A.iministrative Contrc4 Problem 030 M 0$5 Lcensed Operator Problem 030 E 0.06 !
Other Personnel Erro, - 0.17El 0.10 0.12 Maintenanco Problem ,
0.0 .0.03]
Des @'ConstruClionAnstallation Fabncation Problem h%%%%W 0.90 0.08 E Mscellaneous N $j FORCED OUTAGES 0.06 l0.04 Forced Outage Rate
- 0.05 0.03 Equipment corced Outages .
0.64 0.07
/1000 Comn.ercial Hours y 0.26 ~
-0.37%
I i i l l i I I I i i l 1 1.0 0.5 0.0 0.5 1.0 1.0 0.5 0.0 0.5 1.0
- Net Catulates for Operabona! Cvele Performance Index Performance Index NOTES P ant Se'r Trend Shod Term: Based on the slope of a hnear regression kne plotted over each plant s data. Time intervals used in the trends are 4 Quarters for ' Operations' and Forced Outages
- indicators and 6 quarters for Shutdown' indicators.
Dev atens trem Peer Grouc Metan Lone Term: Compansons are rnade of each plant to the performance of its peers over a 12 Quarter tirne interval.
P.ter.Qsgr PTN 3&4 - Older Westinghouse 3 Loop. ,
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NRC INDICATOR PERFORMANCE OVERVIEW l
- for St. Lucie (Data through Quarter Ending September 30,1995)
LEGEND Plant Self Trend Deviations From Peer i Q Short Term Grou0 Median Lon0 Term !
OPERATIONS Automate Scrams WNie Critical
\\\\ll0.54 0.18 0.90 I
Safety System Actuatons 0.36 Significant Events i 00 0.0 0.22 Safety System Failures 0.0 0.67 Cause Codes (ALL LER's) mm
! Administra!we Control Problem 0.08 0.30 i
'. censed Operator Problem 0.0 0.68 Other Personnel Error O.0 \\\wxwN O.72 Maintenance Problem 0.48 M E 0.28 0.28 DesegrConstructioMnstaHation l 025 0.40 Fabncaten Problem l to 0.40 l y,scellaneous 0.0 - 0.18 E Safety System Actuatons
! Significant Ei/ents 00 0 0.22 0.0d Safety System Failures 4
0.0 1.34 Cause Codes (ALL LER's) 0.11 0.06 Admnstratwe Control Problem 0.44 Licensed Operator Problem 00 0.30 Oriw Personnel Error 0' 0.08 Maintenance Problem 09 020 DesgrvCotstructioMnstanation l @020 00 Fa.vicaten Problem l 10.0 0.27 Miscellaneous Oj j FORCED OUTAGES 0.83 0.10 Forced Outage Rate 0.0
%\\\\\10.49 Equipment Forced Outages
- 2.45 0.82
/1000 Commercial Hours 0.0 g 0.13 I I I i i i l I I I I I I I I
', 1.0 0.5 0.0 0.5 1.0 1.0 - 0.5 0.0 0.5 1.0
- Not Ca'cvwed W Otwa'ional Co Performance Index Performance Index NOTES:
Plant Self. Trend ShotTerr Based on the slope of a linear regression line plotted over each plant's data. Time interva!s used in the trends are 4 Ouaners for " Operations' and Forced Outages
- indicators and 6 quarters for Shutdown
- indicators.
Deviatons from Peer Grouo Median Lena Term: Compansons are rnade of each plant to the performance of its peers over a 12 Quarter time interval.
Peer Greue: PSL 1&2 Combustion Engineenng with core protection calculator plants.
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1 WANO OVERALLINDICATOR PERFORMANCE OVERVIEW (May 31,1996)
Unit or Station Values Industry MedianValues *l Performance Indicators 3. year oistributioni PTN 3 PTN 4 PSL1 PSL2 g3993,3993) 2000 Goals Unit Capability Factor (Unit %, 3-Yr.
88.7% 88.3% 80.5 % 81.0 % (:1.2% 87.0 %
Distribution Ending May,96)
Unplanned Capability Loss Factor (Unit 3.5% 3.7% 12.1 % 8.1% 5.2% 3.0%
%,3-Year Distr. Ending May 96)
Unplanned Automatic Scrams Per 7000 Hours Critical (Per Unit, 3-Year Distri- 0.6 0.9 1.6 0.6 0.9 1.0 bution Ending May '96) id High Pressure Safety injection System (Per Unit,3 Year Distribution not
$ 0.008 0.009 0.026 0.009 0.003- 0.008 r
j Ending March '96) available l Auxiliary Feedwater System (Per not j Unit, 3-Year Distribution Ending 0.015 0.012 0.010 0.013 0.004 - 0.009 available g, March '96) en 3
g Emergency AC Power System (Per not g Unit, 3-Year Distribution Ending 0.006 0.003 0.019 0.013 0.007 0.012 available i March '96)
Thermal Performance (Ratio of Design
- to Actual Gross Heat Rate, 1 Yr. 100.1 % 99.7 % - 98.9% 98.3% 99.5% " 99.5 %
Distribution Ending May '96)
Collective Radiation Exposure (Man-Rem per unit per year,3-year running 153 153 201 201 153 120 i ending May '96) atg.
Volume of Low-level Solid Radioactive I
. Waste (Cubic meters per unit per year, 32.0 32.0 55.5 55.5 47.0 45.0 3-year avg. ending May '96)
Chemistry Index (12-mo. weighted average through May ,96) 1.09 1.06 1.16 1.18 1.18 " 1.10 Industrial Safety Lost time Accident Rate (Station rate per 200,000 man-hours 0.12 0.33 0.55 " 0.40 worked ending May '96) llllEM
" 9' ay .I 1.00E-6 3.64E-5 Outage 4.06E-5 Refe e onth en ing 5.0E 04"*
NOTE: shaded area denotes FPL performance is unfavorable 'o actualindustry median.
source of Industry Data:
- 1995 Year End Report for Performance indicators for the U.s. Nuclear Utility industry (19931995 Distribution).
- 1995 Year End Report for Performance Indicators for the U.s. Nuclear Utility industry (1995 Distribution).
- 1995 Year-End Report for Performance indicators for the u.s. Nuclear Utility industry (4/954/95 Distribution).
yj; Rev. 4/15/96
WANO OVERALL INDICATOR PERFORMANCE OVERVIEW Discussion of FPL Performance Unfavorable to Industry Median (May 31,1996)
UNIT CAPABILITY FACTOR (3 Years Ending 5/31/96)
' St. Lucie Unit 1. The 3-year running Capability Factor for the unit was 80.5%. Capability loss is attributed to the following: Refueling Outage and extension from 3/29/93 to 6/17/93 (1.6%); 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 1
Operated Relief Valves from 8/9/95 to 8/17/95 (0.7%); and, inadvertent Containment Spray actuation and clean-u from 8/17/95 to 9/3/95 (1.3%) IB2 Diesel Genarator failure from 9/1/95 to 9/6/95 (0.5%); 1A Diesel Generator 2
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%); and, a refueling outage commencing 4/29/96 (3.0%). Other miscellaneous unplanned outages and derates accounted for the remaining 7.2% Unit Capability Factor loss.
St. Lucie Unit 2. Capability Factor for the three years ending 5/31/96 was 81.0%. Capability loss is attributed to the following: Condenser Tube leak repairs from 8/9/93 to 8/11/93 (0.2%); refueling outage from 2/13/94 to 4/22/94 (4.6%); shutdown for auto reactor trip investigation on 4/23/94 (0.3%); and, a refueling outage from 10/9/95 to 1/5/96 (7.9%). Other unplanned outages and power reductions accounted for the remaining 6.0% Unit Capab!!ity Factor loss.
UNPLANNED CAPABILITY LOSS FACTOR
, (3-Years Ending 5/31/96)
St. Lucie Unit 1. The Unplanned Capability Loss Factor for the three years ending 5/31/96 was 12.1% compared to an industry median of 5.2%. Unplanned outages and power reductions contributing to this performance included:
Refueling Outage extension from 6/1/93 to 6/17/93 (1.6%); Waterbox cleaning due to jelly fish intrus. ion from 9/18/93 to 9/29/93 (0.7%); Hot Leg Valve MV-3480 leak repairs from 3/29/94 to 4/2/94 (0.4%); Main Transformer trip from
- 6/6/94 to 6/11/94 (0.4%); Quench Tank leak repairs from 2/27/95 to 3/8/95 (0.9%); 1A2 Reactor Coolant Pump seal repairs from 8/2/95 to 8/9/95 (0.7%); inoperable Power Operated Relief Valves from 8/9/95 to 8/17/95 (0.7%);
inadvertent Containment Spray actuation and clean-up from 8/17/95 to 9/1/95 (1.3%) 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%); and, Code Safety Valve repairs and modifications from 9/11/95 to 10/31/95 (2.4%). Other miscellaneous unplanned outages and derates accounted for the remaining 2.1% Capability Loss.
St. Lucie Unit 2. The Unplanned Capability Loss Factor for the three years ending 5/31/96 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%). Other unplanned outages and power reductions accounted for the remaining 4.4% in Capability Loss.
UNPLANNED AUTOMATIC SCRAMS PER 7000 HOURS CRITICAL (3-Years Ending 5/31/96)
St. Lucie Unit 1. Increased rate for Unit 1 was the result of five auto trips occurring on 3/28/94,4/3/94,6/6/94, 10/26/94 and 7/8/95.
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HIGH PRESSURE SAFETY INJECTION SYSTEM (3 Years Ending 3/31/96)
Turkey Point Unit 4. Average performance was affected due to the on-line replacement of the HPSI pump motors following discovery of cracked rotor bars.
St. Lucie Unit 1. Average performance for the last three years was affected by on line Motor Operated Valve testing in the 3rd Quarter of 1994 and a breaker failure on 2B HPSI pump in the 1st Quarter of 1995.
St. Lucie Unit 2. In the 1st Quarter of 1995, average performance was affected as a result of Component Cooling Water (CCW) Heat Exchanger cleaning which placed the respective HPSI pump OOS due to lack of dedicated seal
- cooling.
AUXILIARY FEEDWATER SYSTEM (3 Years Ending 3/31/96) i Turkey Point. Average performance for both units was affected by the B AFW Turbine failure in the 4th Quarter of l i 1994 due to malfunction of the mechanical overspeed trip device; in the 3rd Quarter of 1995, performance was affected by: Part 21 repairs on the Trip and Trottle Valves, and Unit 3 outage work.
St. Lucie. Average performance for three-years was affected by f ailure in the 4th Quarter of 1994 of the 1C AFW '
! Pump Govemor. In the 3rd Quarter of 1995, performance was attributed to: failure e' the AFW PP 2C Steam i Admission Valve MV-08-13 to open, a mechanical trip linkage for AFW PP 20 when the Electrical Overspeed Solenoid j was energized, and a discrepancy between field wiring and plant wiring drawing for the AFW PP 28.
4 EMERGENCY DIESEL GENERATOR SYSTEM (3 Years Ending 3/31/96)
St. Lucie Unit 1. Unit 1's average performance for three-years was the result of a high water jacket temperature trip
- of 1 A EDG and failure of the govemor on 182 during monthly surveillance run which closed off fuel to the 12 cylinder engine in the 2nd Quarter of 1995,18 diesel 12 cylinder engine valve failure in the 3rd Quarter of 1995, and 18 diesel due to replacement of the cooling water valves in the 4th Quarter 1995.
j St. Lucie Unit 2. Unit 2's average performance for three-years was affected by a failure of the 2A EDG Govemor in
- the 4th Quarter of 1994.
4 COLLECTIVE RADIATION EXPOSURE - MAN-REM (3 Years Ending 5/31/96) s St. Lucie. Collective Radiation Exposure three-year running average level for St. Lucie was 201 Man-Rem per unit j which was greater than the 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 5/31/96) i St. Lucie. Volume of Solid Radioactive Waste for the 3-year annual average was higher than industry median due to 1994 waste volume; the 1995 value of 41.9 cubic meters was below the median value.
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.. . .._ . - .- - - . - ~ . - - - - ~ - - ~. . . - - - --
. - - - - ~
WANO WEIGHTED OVERALL PERFORMANCE 4
100.0
, , A 0 PTN 3
, 'j ,
- + PTN 4 4
.' + Psl1 h
0
.'~
l - O -
- PSL 2 80.0 , , 3; i
,.' ' ,' g/ . . .O . . o y o l '~ o. . . o
- 1 l .o-' g
, , Note: Adjustments have been I
. 60.0 / made to reconcile FPL data I l with WANO's records.
50.0 40.0 Unit 1 981 1992 1993 1994 1995 1/96 2/96 -3/96 4/96 $/96 8/96 7/96 9/96 9/96 -10f96 11/96 12/96 PTN 3 57.5 66.7 88.8 85.0 90.9 95.0 93.8 92.7 94.9 95.9 PTW 4 ' 46 8 64 0 87.0 86 8 93.8 94.8 95.1 93.7 94.2 94.5 PSL1' 52.6 75.0 82.7 76.3 63.3 67.1 67.7 70.5 65.4 68.6 PSL2' 71.6 80.9 70.9 67.5 74.0 71.8 73.5 75.5 77.3 76.5 Industry Avg rVa rva 76.2 80.1 82.0 DEFINITION The WANO Overall Performance Index is a composite indicator utilized to trend nuclear station performance.
The index is a weighted combination of the following 10 individual performance indicators:
- 1. Unit Capabiltty Factor (16%) 5. Emergency AC Power (9%) 9. Thermal Performance (6%)
- 2. Unplanned Capability Loss Factor (12%) 6. Unplanned Auto-Scrams (8%) 10. ChemistryIndicator(6%)
- 3. High Pressure Safety Injection (9%) 7. Collective Radiation Exposure (8%) 11. Low-level Radwaste Volume (5%)
- 4. Auxiliary Feedwater System (9%) 8. PWR FuelReliability(7%) 12. Industrial Safety Accidents (5%)
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE WANO:
Through 4th Quarter 1995 Industry Median: 82.0%
PERFORMANCE
SUMMARY
Turkey Point Units 3 and 4 overall performance through May exceeds WANO's industry median of 82.0%
l Data Provider: Shr.can 84er 694-4255 l A 1 e
(
l I-I UNIT CAPABILITY FACTOR l
- (3-Year Running Average) 1 100.o -
0 MN3 l l S5 o - . . + . . pru , p
,0.o
-o-est i L
,,k' 0 0 4 *
- O
- PSL 2 l
- * - 4',, Indttstry Avg 85.0 - I
~~
- 80 0 ' '
C 3- '[
Omsion Y-E: 87.5% u I p -o jo l
h 70.0 z
e 65.o
/
60.o
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$5.o i /
So.o
[ '
45.o
' 40.0 Unit 1991 1992 1993 1994 1995 1/96 2/96 .1/96 4/96 6/96 6/96 7/96 8/96 9/96 1o46 11/96 12/96 PTN 3 47.9 52.7 64.6 85.o 88 9 88.9 88.6 88.7 88.7 88.7 PTN 4 42.2 61.8 63.7 86.7 87.2 87.3 87.3 84.6 85.7 88.3 PSL1 77.5 78 4 82.7 84 6 e7.9 78 o 77.8 77.9 80 5 80.5 PSL2 81 4 81.3 81.3 74.1 74.o 75.1 77.7 8o.5 80 4 81.o f industry Avg. 72.3 74 s 7s 5 78.s 8o.8 DEFINITION Unit Capability Factor is the ratio of the available energy generation over a given time period to the reference energy generation over the same tirne penod. expressed as a percentage with both energy generation terms determined relabve to reference ambient conditions. Available energy generaton is the energy that could have been produced under reference ambient conditions considenng only limitations within control of plant management,i.e., plant equipment and personnel performance, and work control. Reference energy generation is the energy that could be produced .
if the unit were operated continuously at full power under reference arnbient conditions throughout the period. Reference ambient conditions are !
environmental conditions representative of the annual mean (or typical) arnbient conditons for the unit.
l STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE May 1-T-Q 3-vr Runnina Y-E Tarcet WANO 1993 1995 Median 81.2 %
PTN 3 100.0 % 92.5% 88.7 % 2950% 1995 Median 82.6 %
PTN 4 100.0 % 74.8% 88.3 % 2 82.0 % 1995 Average 79.4%
80.0 %
]
PSL1 0.0% 75.3 % 80.5 % 2 78.5% 1995 Goal PSL 2 98.8 % 93.5% 81.0 % 2 95.0%
PERFORMANCE
SUMMARY
Turkey Point Units 3 and 4 Capabihty Factor (3-yr. running average) performance through May 1996 was higher than WAN0's 3-yr. running industry median.
Data Provider: Sharon Bilger 694-4255 A-7
UNPLANNED CAPABILITY LOSS FACTOR i (3-year Running Ave. rage)
) 16.o
^ - PTN 3
,/' . 4 . . PTN 4
~
I I O - --O-- PSL 1
, M, >
O - PSL 2
' ' ' - Industry Avg. _
12.0 '
+ 9 .
'. l 'o 10.o l
g, . ,
S l 'O ..o..,n Note: Data for 1993-96 has g g ,._ -
l e ' A .' been analyzed and edited in i
$ '[\ order to reconcile with WANO's f
. 6.0 ~, ~' x records.
4.o
_ . .J.$
- h ....+..4....
r...
m .
I O' 3 '
[
Dnnsion Y E. 3.2t. I 2.0 o.o 1/96 :2/96 4/96 $/96 8/96 T/96 8/96 9/96 top 96 11/96 12/96
' ' Unit ' luf 1982 1983 1984 1983 2P96
' PTN 3 - 152 4.8 3.8 4.3 3.3 3.0 3.6 35 35 3.5 PTN4 11.5 6.5 3.9 47 42 4.2 4.2 4.2 4.0 3.7 PSL1- 5.1 5.9 44 5.7 13.0 13.0 13.3 13.2 12.7 12.1 PSL2 - 31 5.5 11.6 13.2 14.8 13.1 10.7 84 8.3 8.1 i
F Avg.; 8.2 7.6 64 5.5 4.9 DEFINITION Unplanned Capability Loss Factor is defined as the ratio of the unplanned energy lo68es dunng a given penod of time to the reference energy generation, expressed as a percentage. Unplanned energy loss is energy that was not produced during the period 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 they are not scheduled at least four weeks in advance. Reference energy generation is the energy that could be produced if the untt were operated continuously at full power under reference ambient conditions throughout the period. Reference ambient j condrtions are environmental conditions representatrve of the annual mean (or typical) ambient conditions for the unit.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE 3-vr Runnino Ava YLAUQ PTN 3 3.5%
3.7% 1993 1995 Median 5.2%
PTN 4 12.1 % 1995 Median 5.0%
PSL1 1995 Goal 4.5%
- - PSL 2 8.1%
1996 Target (all units); s 3.2%
PERFORMANCE
SUMMARY
i
" St Lucie Units 1 and 2's Unplanned Capability Loss Factor performance for 3-yr running through May 1996 was higher than the WANO's 3 year running industry median.
T Data Source: John Pizzutelli 694-4245 A.1
UNPLANNED AUTO TRIPS PER 7000 HOURS CRITICAL (3-year Running Average) 1.8
., o PTN 3 1.6
^' '
O O O O O +
- PTN 4 _
'. --0-- PSL 1 4 ',
' = O * = PsL 2 f- ,4 i . Industry Avg. j
. 1.2 , ,
y %:
- Omn M s 1 m unn g ,
j 1.0
~ .................
, 0.8 h ^' '
Q---( O -O, '
'^ ^ ^
^
b
^
0.6 0.4 z
0.2
\. . r j 00 .
- Unit 1991 1992 1993 1994 1996 1/96 2/96 3/96 4/96 5/96 6/96 7/96 8/96 S/96 10f96 11/96 12/96 PTN 3 16 1.0 0.0 0.3 03 0.3 0.6 o.6 0.6 06 PTN 4 1.7 14 0.9 1.3 0.9 09 0.9 09 0.9 0.9 PSL1 1.3 1.0 0.9 1.5 1.6 1.6 1.6 1.6 1.6 1.6 PSL2- 0.6 06 0.3 07 0.7 07 0.7 06 0.6 06 Industry Avg. 15 1.2 1.1 00 0.9 DEFINITION Unplanned Automatic Scrams per 7000 Hours Cnticalis defined as the number of unplanned automatic scrams that 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 anticipated part of a planned test. Scram means the automatic shutdown of the reactor by a rapid insertion of negative reactivity (by control rods, liquid injection shutdown system, etc.) caused by actuation of the reactor protection system.
The scram signal may have resulted from exceeding a setpoint or may have been spurious. Automatic means that the initial signal that caused actuation of the reactor protection system logic was provided from one of the sensors monitonng plant parameters and conditions rather than from the manual scram setches or, in certain cases desenbed in INPO 94409, from manual turbine trip switches provided in the main control room.
Critical means that dunng the steady state condition pnor to the scram, the effective reactor multiplication factor was essentially equal to one.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE Through May WANO 12st 36-mo Division Totals: 1993 1995 Median 0.9 1996 05 0.9 1995 Median 0.9 1995 1.3 0.9 1995 Goa! 1.0 Dmsion Tarcet. s 3.0 auto tnps PERFORMANCE
SUMMARY
. No unplanned automatic trips were reported in May.
. Turkey Point Unit 3 expenenced an automatic tnp on February 9th. The "B" Steam Generator Feed Pump was stopped to monitor its discharge check valve closing stroke which did not strike closed as expected. The resulting feed flow transient caused the "C" Steam Generator level to increase resutting in a turbine trip which tripped the reactor. Unit 3's 3-year running average of 0.6 was below the industry median.
. St. Lucie Unit 1's 3-year running average of 1.6 exceeded WANO's 3-year running average of 0.9 as a result of four trips occurring in 1994 and one in 1995.
Data Providers: (PTN) Jim Knorr 246-6757 and (PSL) Kelly Korth 467 7054 A4
HIGH PRESSURE SAFETY INJECTION SYSTEM PERFORMANCE l
, (3 yr Running Average) l o.o40 l l
O PTN 3 0.035 -+ PTN 4 _
===O--- PsL 1
- O - PSL 2 l -- z-Industry Avg. f E o.025 9 , O Divison Y E: s0.025 ,
i ,
h !
j o.02o i
7
, o.015 ,.' . ,
/ '.
o.010
, */ .."**-r..
l o.000 I d
i g Unit < -1991 '1992 1903 :.1994 '1996 3/96 8/96 '9/96 12/96 PTN 3 0.007 0.003 0 007 0.008 0.006 0.008 PTN 4 0.001 0.001 0.008 0.008 0.009 0.009 PSt1 0.001 0.028 0.017 0.011 0.025 0.026
'PSL2 0.011 0.008 0 018 0 007 0 010 0.009 l industry Avg. 0008 0 008 0 010 0.008 0.008 DEFINITION This Safety System Performance indicator monitors the readiness of the Safety inje : bon (SI) System at Turkey Point and the High Pressure Safety Injection (HPSI) System at St. Lucie to respond to Off-normal events or acadents. The indicator is determined from the unavailabilities, due to all causes, of the components in the system during a time period, divided by the number of trains in the system. The definition is further explained:
comconent unavailabihtv is the ratio of the hours the component was unavailable (unavailable hours) to the hours the system was required to be available for service. Data is reported on a quarterty basis.
Unavailability = (Known Unavailable Hours) + (Estimated Unavailable Hours)
(Hours System Required) x (Number of Trains)
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE ist O'r 1996 3-vr Ava Endina 3/96 PTN 3 0.006 0.008 Unavailability y/MQ PTN 4 0.005 0.009 PSL1 0.015 0.026 1993 1995 Median (PWR) 0.003 0.008 PSL2 0,000 0.009 1995 Goal 0.020 Targets: EIN ESL 1995 Y E Ta*get s 0.016 5 0.023 1996 Y E Target s 0.025 s 0.025 i PERFORMANCE
SUMMARY
. Turkey Point Unit 3's 3-year running average for Safety injection System performance through the 1st Quarter 1996 was below the year-end target and industry median. Unit 4's performance for 3-years was below the year end target and slightly higher than industry average.
. St. Lucie Units 1 and 2's High Pressure injection System average performance for 3 years running was higher than the industry median through the 1st Quarter 1996; Unit 2's performance was below the year-end target.
Data Providers: (PTN) Ed Lyons 246-6967/Carlos Melchor 246-6964 (PSL) Chuck Wood 467-7034/ Bob Young 467-7063 A-5
4 SAFETY SYSTEM PERFORMANCE - AUXILIARY FEEDWATER SYSTEM l l
(3-year Running Average) l 1
, 0.040 c PTN 3 l
- t- - at PTN 4
-H>-- Psl 1
- - O - -PsL 2
- Industry Avg .
0.030 , , j
'. Dmsion Y-E: s 0.025 E I F '
b 0 020 E . **
2
- 5 O /. '
. ~. . e
., ~ - .......
0.010
~. ,
O
'O l
l 0.000 Unit 1991 1992 -1993 1994 1995 3/96 6/96 9/96 12/96 PTN3 0.008 0.025 0.016 0.021 0.014 0.015 PTN 4 s 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 I PSL2 0.017 0.014 0.012 0.00e 0.014 0.013 j
DEFINm0N
. This Safety System Performance indicator monitors the readiness of the Auxiliary Feedwater (AFW) System to respond to off-normal
, events or accidents. The indicator is determined from the unavailabilities, due to all causes, of the components in the system during a time period, divided by the number of trains in the system. This definition is further explained: comoonent unavailabilev is the ratio of hours the component was unavailable (unavailable hours) to the hours the system was required to be available for service.
AFW Unavailability = (Known Unavailable Hours) + (Estimated Unavailable Hours)
(Hours System Required) x (Number of Trains)
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE 1st Otr 199,5 3-vr Ave Endino 3S6 PTN 3 0.008 0.015 WANQ Unavailability 1
PTN 4 0.007 0.012 PSL1 0.005 0.010 PSL2 0.008 0.013 1993-1995 Median (PWR) 0.004 0.009 1995 G0a! 0.025 Targets: EIN ESL 1995 Y-E Target 5 0.020 s 0.021 1996 Y E Target s 0.025 s 0.025
- PERFORMANCE
SUMMARY
e Turkey Point Units 3 & 4 Auxiliary Feedwater System performance for 3-years running through the 1st Quarter 1996 was lower than the year-end target and higher than the industry med!an.
- St. Lucie Units 1 & 2 Auxiliary Feedwater System performance for 3-years running through the 1st Quarter 1996 was below the year end target and higher than the industry median.
Data Providers: (PTN) Jose Donis 246-6008/ Woody Raasch 246-6527 (PSL) Chuck Wood 467-7034/ Mark Wolaver 467 7083 A-6
SAFETY SYSTEM PERFORMANCE - EMERGENCY AC POWER SYSTEM (3-year Running Average) 0.030 Dnnsion Y-E: s 0.025 1 0 PTN 3 0.020 . - + PTN 4 U
9 / ---0-- PSL 1 f - a 0
- PSL 2
- . wustqr A4
= 0.015 0 ,
. ,,..........O
,.* o '
0.010 ,
', O '.,'
. 0 0.005
/...........
0.000 l ,
1 Unit 1991 1992 1993 1994 1995 3/96 6/96 W96 12/96 j PTN 3 0.001 0.004 0.002 0.003 0.003 0.006 l PTN4 0.015 0.001 0,002 0.003 0.003 0.003 l l
PSL1- 0.013 0.019 0.012 0.010 0.019 0.019 PSL2- 0.019 0.008 0.011 0.M7 0.012 0.013 Industry Avg.- 0.017 0 017 0.020 or 8 0.012
- J DEFINITION Emergency AC Power System is definet 2 the sum of the emergency diesel generator unavailabilities divided by the number of emergency generators at a station. Data is collected at the train level. The emergency generator includes subsystems such as air start, lube oil, fuel oil, cooling water, etc. However, for this safety system performance indicator, unavailable hours are counted only when the emergency generator is unavailable to start or load-run. For example, if a component fails in one train of a redundant support system the emergency generator is still operable, and no unavailable hours are counted.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE ist Ott 1996 3-vr Ava Endino 3/96 PTN 3A&B 0.029 0.006 PTN 4A&B 0.000 0.003 YLA.NQ Unavailability PSL1A&B 0.006 0.019 PSL 2A&B 0.005 0.013 1993 1995 Median (PWR) 0.007 -0.012 1995 G0a! 0.025 Targets: EIB ESL 1995 Y E Target 's 0.015 5 0.016 1996 Y-E Target 5 0.025 s 0.025 PERFORMANCE
SUMMARY
. Turkey Point Ur..ts 3 & 4 Emergency AC Power performance for 3-years running ending 1st Quarter 1996 was below the year-end target and industry median.
. St. Lucie Units 1 & 2 Emergency AC Power performance for 3-years running through the 1st Quarter 1996 was below the year-end target and higher than the industry median for 3 years running.
Data Providers: (PTN) Jose Donis 246-6008/ Jim Freyre 246-6539 (PSL) Chuck Wood 467-7034/ Roger Kulavich 467 7080 A-7
e THERMAL PERFORMANCE (12-Month Running Average) 101.0 l 0 PTN 3
+ PTN 4 I --O-- PSL 1 1 ; > + + - . s . . o . .pst a
,og, e -4,
') >
0 I industry Avg.
- p, Division Y E: 99.5% II i C ,
89 4 - , 0^. - I ;
, e ; ; 3 a2 + .
. ,0 (
o...o...O"
98.0 -
, D 97.0 Unit 1991 1992 1983 1984 1995 '1/96 ,2/96 3/96 4/96 5/96 8/96 7/96 8/96 9/96 10/96 11/96 12/96
.. PTN 3 99.3 99 2 100 4 100.: 99 8 99 8 99.9 99 9 100 0 100.1 PTN4 98.7 99.0 99.7 Fb.7 100.1 .100.1 100.1 100.1 99 9 99.7 PSL1 99.0 99.3 99.2 99 0 99 0 98 9 98.9 98.9 98.9 98.9 PSL2 99.6 99 3 97.8 98.5 98 1 982 98.2 98 2 98.3 98.3 )
Industry Avg. 99.2 99.3 99 4 99 4 99.5 DEFINITION I Thermal Performance is the ratio of the design gross heat rate (corrected) to the adjusted actual gross heat rate. Gross heat rate is dehned as the ratio of total thermal energy produced by the reactor core to the total gross electrical energy produced by the generator during a given time period. Design gross heat rate (corrected) is the minimum theoretical heat rate that can be attained at design operating conddions for 100 percent power, expressed in British thermal units (BTVs) per kilowatt-hour (electric).
Adjusted actual gross heat rate is the gross heat rate attained in the normal ect.,.,msnt lineup during one 24-hour period each month, expressed in BTUs per kilowatt-hour (electric) power level should be greater than 80 percent.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE May 12 Mo Averaae WANO PTN 3 100.0 % 100.1 %
PTN 4 98.3 % 99.7 % 1995 Median 99.5 %
PSL1 0.0% 98.9 % 1995 Goal 99.5 %
PSL 2 99.2 % 98.3 %
1996 Target (all units): 99.5%
PERFORMANCE
SUMMARY
. For the 12 mo. running average, Turkey Point Units 3 and 4 performance was higher tnan WANO's 12-mo. running industry average.
. . St. Lucie Units 1& 2 Thermal Performance for 12 mo. running was below % ANO's 12-mo. running average.
Data Provicers: (PTN) Manuel Martinez 246-6523 and (PSL) Marty Smd 467-7079 A-8
4 FUEL RELIABILITY j (Fuel Cycle / Monthly)
}
1.coE+oo e PTN 3 l
+ - PTN 4
! 1.ooE of
-- PSL 1
- O - PSL 2 1.
- "" A'9
? ooE42 m
b' y*. .
h1.ooE-o3
~
\
- .5 1.ooE od ,0, Fuel Defect Reference E OE44 1 I w 'n -
'9 O' ,' I I
1.coE45 , ,
e,- ,
^ ^ ^
1.coE46 -
1.coE o7 UrWt > Previous Cycles 1186 2/96 3/96 4/96 . 5/96 '6/96 7/96 a/96 Of96 10/06 11/96 12/96 PTN3 4 4M4 t us.: a rosa i rssa a ssE4 t ocs4 t oos4 1.cos4 1.coE4 1.coE4 PTN4 SJas4 t ossa 74ssa i cos4 s.sss4 i sis 4 t oos4 s s4E4 PSL t .. a sas.r, 54184 s t 7:4 s cos4 4:2s4 t assa s ais.s i sst.s PSL2 a 01:4 s 71s4 s sas4 e sos 4 s s2s4 1 coE4 1.cos4 i ses.s 104 4 4 oss-s industry Avg. s cosa DERNmON This indicator is defined as the steady-state pnmary coolant iodine-131 activity (microcunes/ gram) corrected for the tramp contnbution and power level, and normalized to a common purification rate and average linear heat generation rate. The indicator value is calculated based on the average of the three monthly values for the most recent quarter of steady-state operation above 85 percent power, Steady state is defined as continuous operation for at least three days at a power level that does not vary rnore than 5 percent.
Note: If a calculated monthly value for a unit is less than 1.0E-6 microcuries per gram, the value is replaced by 1.0E 6 microcuries per gram.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE May Cvde No.
WANO PTN 3 1.00E 06 15 PTN 4 3.64E-05 16 1995 Fuel Delect Reference Threshold (PWR) 5.00 E 04 PSL 1 Outage 1994 Median 7.36 E 05 PSL2 4.06E 05 9 1994 Best Quartile 3.00 E-06 Division Target for each unit. 54.50E 03 PERFORMANCE
SUMMARY
. Unit 3's Fuel Reliability continues to indicate zero fuel defects in Cycle 15.
. Und 4 began Cycle 16 operation on April 8th. Preliminary review of radioisotopic data indicates zero defects.
- Unit 1 remained shutdown in May for a scheduled refueling outage.
. Prehminary review of the Reactor Coolant System radioisotopic data for Unit 2 indicates zero defects.
Data Provider: ModestoJimenez 694-3323 Ao
CHEMISTRY INDEX (12-Months Ending Weighted Average) 1.40 I
1.35 0 PTN 3
+ - PTN 4 1.30 + PSL1 O PSL 2 Industry Avg.
y , , Dmsion Y.E: s 120 , ,
- n. g... '
$ h
-O 1.15 i
1.1o
- : : A
,.9. .,
.os , , ,,,,,,,,,,
1.00 Unit 1991 1992 1993 1994 1995 "1/96 - 2/96 M 4/96 5/96 6/96 736 '9/96 Sf96 10f96 1146 12/96 PTN3 1.10 1.11 1.11 1.11 1 11 1.09 j PTN 4 1 04 1.04 1.04 1.03 1.08 1.06 i PSL1- 1.24 1.20 120 1.18 1.16 1.16 f PSL2 1 17 1.19 1.19 1.19 1.17 1.18
- industry Avg.' 1.18 DEFINITION i
4 The Chemistry Index compares the concentration of selected impurities to the limiting values for those impurities. Each
- impur!y value is divided by the limiting value for the impurity, and the sum of these ratios is normalized to 1.0. The limiting 4
values are the " achievable values
- defined by intemational industry-accepted values.
i STATISTICAL
SUMMARY
- INDUSTRY PERFORMANCE i l May 12.Mo Endino Weiahted Avg j WAtQ PTN 3 1.01 1.09 (PWR's with Reorculating Steam Generators without Molar PTN 4 1.02 1.06 Ratio Control)
Outage 1.16 1995 Median 1.18 PSL 1 1,18 1995 Lowest Chemistry Index Value Attarnable 1.00 PSL 2 1.13 1996 Target for each unit: 5 1.20 PERFORMANCE
SUMMARY
l
- Chemistry Index performance for all units for 12-mo. ending weighted average was below the year-end target and industry l median. !
l l
Data Providers: (PTN) R. Steinke 246-6118/ Randy Woodard 246-6810 (PSL) R. Frechette 465-3213/ Dave Faulkner 465-3393 A-10
d i
RADIATION EXPOSURE
- (3-year Running Average) 400 4
+ PTN 350 . -O- PSL _
! - Industry Avg.
300 4
3 25o (N Note: 1996 numbers are adjusted each month to reflect TLD data N O PSL 3-yr Avg g l
@ Target s229.2 a
4 2M ^
} F- k "~ [
PTN: 3-yr Avg g ,
Target 5.170.8 y -- -
l .
, 100 So I
(
' Plant :1991 1992 1993 1994 1995 1/96 2/96 3/96 4/96 5/96 646 T/96 8/96 9/96 10/96 11/96 12/96 1
PTN. 350 332 257 181 162 162 161 185 164 153 PSL' '
274 238 193 202 230 229 227 219 187 201 l DEFINITION Collective Radiation Exposure is the total extemal whole-body dose received by all personnel (including contractors and visitors) coming on site during a time period, as measured by the primary dosimeter, thermoluminescent dosimeter (TLD) or film badge.
Exposure measured by direct reading dosimeters sho'dd be included only for those penods or situations when more accurate data is not available to the utility from TLD's or film badges. In order to entrelate this indicator with te new 10 CFR 20 reporting j
guidelines, U.S. utilities report deep dose equivalent (DDE) and the totd effective dose equivalent (TEDE).
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE 3-vr Runnina cer Unit Man-Rem PTN 153.3 EANQ (oer Unit)
PSL 200.8' (PWR's ) Median 3-yr Distnbuton (1993 1995) 163 Division Targets: 3-vt. Ayg 1995 Median 153 PTN: Y E thru 1996 s 170.8 1995 G0a! 185 PSL: Y E thru 1996 s 229.2 PERFORMANCE
SUMMARY
. Turkey Point Collective Radiation Exposure for 3-years running through May 1996 was 153.3*; performance was below WANO's 3-yr. running median of 163.
. SL Lucie's Collective Radiation Exposure for 3-years running through the month of 200.8* was higher than WANO's 3-yr.
running median.
, May data e 080;TLD w- . e. t u tune of pubicaten.
Data Providers:(PTN) John Lindsay 246-6548 and (PSL) H. M. Mercer 467-7302 A-11
LOW-LEVEL SOLID RADIOACTIVE WASTE (Cubic Meters per unit per year,3-year Running Average) 140 i --+-- PTN 120 g --0-- PSL
--d-Industry Avg. F f 100 l
N $ =
>?,
i e \
G.
e \
.g PslY-E 67.5 I 60 g 3 PTN Y-E: 55.6 I A -*-
do O
so -
o
' Plant 1991 -1992 1993 1994 1996 '1/96 2/96 3/06 4/96 5/96 6/96 7/96 9/96 9/96 10/96 1UB6 12/96 PTN 125.3 102.3 81.2 63.4 37.4 36.7 36.2 33 1 33.2 32.0 PSL 121.1 103 8 80 7 75 4 53 7 53.3 53.0 54.6 55 9 55.5 Industry Avg. 85.0 87.0 45.0 46 0 47.0 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, compacted or solidified) ready' for disposal during a given period. It is calculated using the amount of waste in final form, including the contaner, actually shipped for disposal from both on-site and off-site facilities, plus the change in inventory of final-form waste in l storage at both on-site and off site facilities.
- in transit to or at disposal site for disposal STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE 3-vr Runnina thru May (oer t. ,M (2 Unh Me)
PTN 32.0 3 yr Distribution Median (1993 1995) 47.0 1995 Median 30.0 bon Targets.
1995 W 110.0 PTN 1996 Y E 55.6 cu. mtr. per unit PSL 1996 Y E 67.5 cu. mtr. per unit PERFORMANCE
SUMMARY
. Turkey Point's Solid Waste Disposal performance for 3-yrs. running was below the year-end target and WANO's 3-yr.
industry median.
- St. Lucie's performance was below the year-end target and higher than WANO's 3-yr. industry median.
Data Providers: (PTN) Bob Schuber 246-7227 and (PSL) Bruce Somers 467 7305 A-12
1 INDUSTRIAL SAFETY ACCIDENT RATE j (12 Month Running Average) 1.00 k \
+ PTN g gg + PsL _
l Industry Avg
\
0.80
'8 x p 0.70 0.60 NOTE: An ryury at PSL in 1/96
[ was dassified as a Lost Trne j
/ Injuryin May! Numbers have 2
O.50 been adjusted from 1/96 te 4/96.
0.40 --C j
a 0.30
/ 'V \, \ PTN/Psl Y-E: s 0.30 ,
i j
0.20 W
~*
0.10 - I "
0.00 Plant : 1W1 1992 1993 1 994 1995 1/96 2/96' 3/96 4/96 5/96 6/96 7/96 9/96 9996 10/96 11/96 12/96 PTN- 0.25 0 67 0.36 0 50 0.22 022 0.22 0.11 0.11 0.12 PSL 0.75 0.61 0.50 0 51 0.40 0 40 0 41 0.32 0.32 0.33 9tdustry Avg. , 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 restricted work (excluding the day of the accident); (2) one or more days away from work (excluding the day of the accident); and, (3) fatalities. Contractor personnel are notincluded for this indicator.
Industrial Safety Accident Rate = (number of restricted-time + lost-time accidents + fatalities) x 200.000 (number of .tation man-hours worked)
STATISTICAL
SUMMARY
lhTUSTRY PERFORMANCE 12-Mo -Endina (Mavi PTN 0.12 SL . 02 1995 Median 0.55 5 Goat 0.50 Division Targets:
PTN 1996 Year End 0.30 PSL 1996 Year End 0.30 PERFORMANCE
SUMMARY
. Turkey Point's Industrial Safety Accident Rate for 12-mo. running through May 1996 was below the year-end target and industry median.
- St. Lucie's Industrial Safety Accident Rate of 0.33 for 12-mo. running through May 1996 was higher than the year-end target and below tne industry median.
Data Providers: J. Sambito (PTN) 246-7372 and W. Alfera (PSL) 467-7171 A-13
EQUIVALENT AVAILABILITY FACTOR (Year-to Date) k ,-
,h... h '
Dmsion Target- 88.0% I I
, ; PTN 3 70.0
, , , , , - . , . . PTN 4
. ---O-- PSL 1 O - PSL 2 60 .0 g ,f Ind Avg!
E
- 50.0 '/
40.0 30.0
/
20.0 ,
b 10.0 l I
0.0 Unit 1991 1992 1993 1994 1995 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 22.3 66.3 94.6 83.5 88.7 99.9 83 3 87.4 90.5 92.5
' PTN 4 13.9 85.5 81.1 83.1 97 4 100.0 100 0 68.3 68 4 74.8 PSL1 78.5 95.4 74 0 84.5 75.3 99 6 94 5 94.9 94 6 75.3 i PSL 2 - 98.5 73.2 71.8 77.4 72.9 76.8 87.9 92.0 92 1 93.5 Ind Avg 72.2 72 8 75.3 77.4 DEFINITION Equivalent Availability Factor (EAF) is the ratio of the actual energy production capability to the energy that would be produced operating at full power for the same period expressed as a percent. Equivalent Availability provides an indication of the effectiveness i of plant programs and practices in maximizing electrical generation.
EAF% = Available Hours - (Eauivalent Unit Derated Hours) x 100% l Period Hours STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE May Y-T-D Y T D Taraet 3-vr Run. Ava NERC/ GADS PTN 3 100.0 % 92.5 % 95.0 % 88.7 % 77.8 %
1994 (PWR's)
PTN 4 100.0 % 74.8 % 65.8 % 88.3 % 1994 (Alltypes) 74.1 %
PSL1 0.0% 75.3 % 74.9 % 80.5 % 74.4 %
1990-1994 (PWR's)
PSL2 98.8 % 93.5 % 95.0 % 81.0 % 1990-1994(Alltypes) 71.2 %
Division 74.7 % 84.0 % 82.7 % 84.6 %
WANO 1995 Median 80.7 %
1996 Division Y E Target: 88.0 % 1995 Average 77.4 %
1996 Year End Forecast: 88.4 %
PERFORMANCE
SUMMARY
Equivalent Availability Factor performance in May was as follows:
- PTN Units 3 and 4 operated at 100.0%.
- PSL Unit 1 was shutdown all of May for a scheduled refueling outage.
- PSL Und 2: Power losses were attributed to problems with the B-Start-up transformer (2.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />); Turbine Valve testing (0.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />); Waterbox inspection (4.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />); and. failure of a control fuse which caused isolation of heating steam to MSR's (1.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />).
For the Division, Y-T D Equivalent Availability was 74.7% for the month and 84.0% Y-T-D which is higher than the 82.7% targeted through the period. Data Provider: Sharon Bilger 694-4255 B-1
CAPACITY FACTOR (MDC NET) l (Year-to-Date) ;
110.0
-+ PTN 3 100.0 0
l
+c PTN 4 -
,,., iAA <
h = ;u A Y ... Y N
= ~^*
,,., \ !
70.0
- r .,cr.- .s-g,
.a 60.0 l/
- j
- 7 s 1 g 50.0 40.0 ll
/
30.0 ,
l 20.0 .
+
10.0 0.0
-- Unit ~ 1991 1992 1993 1994 '1996 1/96 2/96 3/96 4/06 5/96 6/96 7/96 8/96 S/96 10/06 11/96 12/96 sPTN3 22.5 58 4 97.0 84.8 89.5 103.9 857 90.0 93.1 94.7 PTN 4 13.7 79 3 81.4 83.0 99.5 104.5 104.2 71.0 87.5 74.4 PSL1 78.8 96.9 73.9 84.1 75.0 98.8 93.3 94.2 94.1 75.2 PSL 2 101.1 73.7 64.1 76.3 71.9 74.1 87.0 92.0 92.0 93.6 ImJ Avg 71.2 72.3 75 4 77.9 DEFINITION Capacity Factor (CF) is the index of the actual electrical energy produced by the unit with respect to its potential.
Capacity Factor = Net ElectricalGeneration X 100 Maximum Dependable Capacity (839 or 666) X Period Hours STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE NERC/ GADS May Y-T-D 12-mo. end.in 1994 Avg PWR's 76.7 %
PTN 3 102.0% 94.7 % 86.8 %
1994 Avg AllTypes 72.8 %
PTN 4 99.8% 74.4 % 89.6 %
1990-1994 PWR's 72.8 %
PSL1 0.0% 75.2 % 67.2*/.
1990-1994 All Types 69.5 %
PSL2 99.6% 93.6 % 70.9%
WANO Division 75.3 % 84.5 % 78.6 %
1995 Median 81.1 %
1995 Average 77.9 %
PERFORMANCE
SUMMARY
a Turkey Point Units 3 & 4's Capacity Factor Rate for 12-mo. ending in May was higher than the industry average.
- St. Lucie Units 1 and 2's Capacity Factor Rate for 12-mo. ending through the month was below industry average.
Data Provider: Sharon Bilger 694-4255 B-2
4 i PTN FUEL UTILIZATION FACTOR
! Turkey Point Unit #3, Cycle 15 Turkey Point Unit #4, Cycle 15 55o Soo. ,:
- A 450 , Planned Refuehng Date
- March 8,1997 g[p. 500 - Planned Refuehng Date: September 15.1997 /(
MN 400 -
'l f]'
f q/E bb
==~
s .W7w g4oo - glg.Slg 1 {u. 350 - My;g n,@b a, 4;, g g j E
$5ihMd f k350-v-p [&&e fh%,
}u 300 e$5#55W.gw{$ h 3m - ik? s ME?l E 250 - M E [ k ,( S E M $hb i $ g$$ E 25o - ).' $h$$bNW N y 200 -
D O&bfh.fNA OcQjn's? w 4yqh hf%
yd2k%.
/T
$1 U 5 200 -
g (WN$VG$f!$$W :I w ,s .% ,k 3 &.
4 W,1,p3;.r .
~
A W. Aw%g'N;p%M.y
, 2 i b150- O!p MB%' y < v.pp"&r"[L dM~ C
'm' ?'O # IDdO* 7 g rb v4M' %m*I w 150 -
YQM N P-m % Dm;ub :
100 -
[ [h:+co:m**%m e-'h"kNO . .$@'Ye
- N *
- WTM@!?dSN! "+.j p
- Y, ld".M IM '
i TV[U ' dIMMY .
5 50 - Q. , so -- .
k .
j, 4
y . ,, l b 3;
%:OMM%&MM5yW9;-pg
,emW gyj r.) q -h?Vyf1?
. pyf. &.ar-j,q h W ;G.M"l'We; h?dtkh;*m y ?! A yAW WW o o Ost Nov m Fat anr Apr w Jun Joe Aug map Dos saw Das Jan Fe Iew Apr easy Jun Jul aos esp PTN83 Dee Pionned - 5 35 66 98 127 158 188 219 249 281 312 342 373 do3 435 466 494 5o1
- Aetiaal 18 47 78 109 128 157 187 218 vertence W4 - 13 12 12 11 1 1 -1 1 PTN #4 Ptsened 6 37 67 98 129 159 190 220 251 282 310 341 371 do2 432 463 494 509 18 49
- Vertones N-) 12 12 6
DEFINITION
, Fuel utilization plots the amount of nuclear energy used during the current fuel cycle. The amount of nuclear energy loaded into the 4
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 at PSL) for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. Planned energy is compared to actual energy used during the cycle. Fuel utilization is directly related to plant performance. The significance of variance EFPD(+/-) is the difference between planned and i actual energy consumption. Fuel utilization can be used to project longer or shorter operating fuel cycles.
Actual Energy / Calendar Days = Fuel Utilization Factor
!4 Fuel Cycle Operating Assumptions PTN 3: In accordance with the April 26,1995 Approved Operating Schedule (AOS), Unit 3, Cycle 15 is scheduled to run 498 calendar days (October 27,1995 to March 8,1997) with design 9nergy to run 501 (EFPD) days. NQIE: Due to the 34-day outage, startup began on October 7,1995,20 days earlier than plNnad.
PTN 4: In accordance with the February 8,19% AOS, Unit 4 Cycle 16 was scheduled to startup on April 25,1996. Due to a 35-day refueling outage, the unit actually star 1ed up on April 8,1995,17 days earlier than planned. Note that the unit has a design
, energyof 507 EFPD.
PERFORMANCE
SUMMARY
e Unit 3 achieved a Fuel Utilization Factor of 99.8% and operated for 743 effective full power hours in the month of May. For the penod October 27,1995 to May 31,1996, the Fuel Utilization Factor was 100.0%.
. Unit 4 achieved a Fuel Utilization Factor of 99.6% and operated for 741 effective full power hours in the month of May, For the penod April 8,1996 to May 31,1996, the Fuel Utilization Factor was 131.1%.
Data provider. Jimmie Perryman 694 3330 B-3
. , . ..._~ .-__ . . - . , - . -.-.-n .. . -- ..n. - - , _
.___,_4 .-
e-PSL FUEL UTILIZATION FACTOR St. Lucie Unit #1, Cycle 14 St. Lucie Unit #2, Cycle 9 600 500 p-.; 4 550 - Planned Refuehng: February 3,1998 ^%
jq 450 . Planned Refuehng Date: Apnl 15,1997
/~
7,y 5x - p& . 4%'
n5
/ ?'l, %
_ 450 - n/ @&;;p.
.. m p , m m;
/;gn@ d 350 - / bhN*h b R $ /?ihdVMjf i 3m - $%g$@$ hd? G 3* - j%iQg%$
l %# % hut ,a
! "~ djh kd $N d (25 ! ' f., .w[n,%.s hNNhMy 8 g,o . g '" ~ g; _;;%
a t 200 p/ p$ Uih.3jjqM%g - gw LW g$y w q.v. gDy m 43MT'M $g;q;;
j; L qW.m946.NxN ? ibG 0
i l$q ' f 0, $r y 150 - DUMQ
? ql @ +d;Rp i ! ff A YdDtT Y$n'b& OY 100' l~l,;:w; uM &p2 m
- y m% OM? 8 w? N $ pJ.:
?.m ., :.::
%*,R:L m, 100 - , ::w;wn, . , . . . .. sg n.gW;QlMsh} @.f ^, m'.%b
/ i :+ S c M 3 ,fi W 3 4 b " y W;;$: 4 g-pgg y 50 - gj ; 4L g} ...mp.4 g73 '.n,g%g g7yg 50 - ,
g ( q @ Q, yggjg [ 6 2.G f ; q @q . .gyy g"' ' ' 3 ny.,,yQ 0 'f : > 0: .
' '~ '~
PSL81 h M due esp ht Inow One h Fat har Apr eley Jun M Aug Sep Cet peuw pas M Fee seer Apr Planned 9 39 69 98 129 158 188 218 246 276 305 335 365 395 425 454 485 514 544 573 575 Actual verinnee p)
'PSL92 Planned 5 36 67 95 126 155 186 215 247 276 306 336 366 397 427 455 485 500 Actual 0 0 23 52 83 111 141 Variance M) -5 -36 44 43 -43 -44 -45 DEFINm0N Fuel utilization 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 at PSL) for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. Planned energy is compared to actual energy used during the cycle. Fuel utilization is directly related to plant performance. The significance of variance EFPD(+/-) is the difference between planned and actual energy consumption. Fuel utilization can be used to project longer or shorter operating fuel cycles.
Actual Energy / Calendar Days = Fuel Utilization Factor Fuel Cycle Operating Assumptions ESL1: In accordance with the February 8,19% Approved Operating Schedule (AOS), Unit 1, Cycle 14 is scheduled to begin operation June 22,1996. This provides for a cycle of 591 calendar days with design energy to run 575 effective full power days (EFPD).
EEL 2: In accordance with the April 26,1995 AOS, Unit 2, Cycle 9 was scheduled to begin operation 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 was in a schedu!ed refueling outage during the month of May.
- Unit 2 achieved a Fuel Utilization Factor ol 97.5% and operated at 725 effective full power hours in the month of May. For the period of November 24,1995 through May 31,1996, the Fuel Utilization Factor was 75.8%
Data orovider: Ruben Rodnouez 694 3345 B-4
_ _ -- _ - ---_. . _ _ _ . _ . - . - . . . . - -._. . _ - - _ . - . ~ . . - . - - . . . . -
FORCED OUTAGE RATE
, (Year to-Date) 30.0 c PTN 3 1
.. + ..PTN4 1
--O-- PSL 1 j 25.o - - O PSL 2 ,._
. Ind Avg i 9 1
. 1 20.o
)
e :
15.0
- l* k
. .: \
k j
' 0-lh k
- O'% 1 o,
l . .
s.O -
l , ,
. : .y . .
4
,,.+....
o.0 .
i Unit -1991 1992 '1993 1 994 1995 1/96 ' 2f90
. ' 3 96 4/96 SfD6 8/96 7/96 8/96 9/96 10/96 11/96 12/96 l PTN 3 1.2 15.6 1.8 1.9 0.5 0.0 11.8 9.3 7.0 56 PTN 4 1.8 13 2 2.0 3.9 1.5 0.0 0.0 0.0 1.3 1.0 PSL1 1.2 35 21 39 21 8 00 44 29 2.2 2.2 PSL 2 0.0 81 23.5 2.3 2.4 7.0 34 2.2 2.2 1.7 Ind Avg 6.8 8.8 8.1 DEFINITION l l
Forced Outage Rate is the percentage of time that the unit was unavailable due to forced events compared to the time planned for full power operation. 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 /electricathydraulic controls systems and operator-intbated trips in response to unit alarms.
Forced Outage Rate Forced Outaae Hours x 100%
Forced Outage Hours + Service Hours STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE May Y T-D 12 Mo. Endina NERC/ GADS 1994 (PWR's) 8.1%
PTN 3 0.0% 5.6% 2.6%
1994 (Alltypes) 10.6%
PTN 4 0.0% 1.0% 0.3%
1990-1994 (PWR's) 7.6%
PSL1 0.0% 2.2% 24.0 %
1990 - 1994 (All types) 10.8%
PSL 2 0.0% 1.7% 2.2%
PERFORMANCE
SUMMARY
No forced outages occurred in May.
. Turkey Point Units 3 and 4 and St. Lucie Unit 2's 12 mo. ending performance was below industry average.
. St. Lucie Unit 1's 12-mo, ending performance was higher than industry average. -
Data Provider. Sharon Bilger 6945255 B-5
- .- -~ _ .- -.
}
UNPLANNED AUTOMATIC TRIPS WHILE CRITICAL (Year-to-Date) s
- O PTN3
+ PTN4 4
C)- PSL1
.. o ..pst2
^
4 - Ind Avg
,3 Division Target: s3 , ,
H I
o g a 1 . * '
I h -j ' ^ ^ ^
.' "'t .
. I O W
~.1) nit '1991 .1992 '1993 1994 '1996 1/06 ; 219 6 :3/96 4/96 S/96 6/96 7/96 '8/96 9/96 10/96 11/96 12/96
-PTN1 0 0 0 1 0 0 1 1 1 1 !
-PTN4 0 1 1 2 0 0 0 0 0 0 PSL1 - 2 1 0 4 1 0 0 0 0 0 PSL2 0 1 0 1 1 0 0 0 0 0 Ind Avg ' 1.3 1.1 0.9 0.8 0.9 DEFINITION An Unplanned Automatic Scram is a non-manual actuation of the reactor protection system that results in a scram signal any time the unit is entical. Scrams that are planned as part of special evaluations or tests are not included in this definition. This indicator provides an indication of success in improving plant safety by reducing the number of undesirable and unplanned thermal-hydraulic and reactivdy transients requiring reactor scrams.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE May Y-T-D 12-Month Endino WANO Trios oer unit PTN 3 0 1 1 Trips per 7000 CriticalHours PTN 4 0 0 0 3-yr Distribution Median (1993-95) 0.9 PSL1 0 0 1 1995 Median 0.9 PSL2 0 0 0 1995 Goal 1.0 Division Total: 0 1 2 .N.Fi (1995 3rd Otr Performance Indicator Rpt)
QuarterlyTrips Annuahzed 1.0 1996 Division Target: 's 3 Quarterly Trips per 7000 Cntical Hours 1.2 PERFORMANCE
SUMMARY
No automatic trips occurred in May 1996. Year to< late, one automatic trip has been experienced:
. Turkey Point Unit 3 experienced an automatic tnp on February 9th; the 'B' Steam Generator Feed Pump was stopped to monitor its discharge check valve closing stroke which did not strike closed as expected. The. resulting feed flow trcnsient caused the "C" Steam Generator level to increase resulting in a turbine trip which tnpped the reactor.
Da'a Providers: (PTN) J. Knorr 246-6757 (PSL) K. Korth 467-7054 B-6
4 i _
i OPEN PWO'S 2.Soo
--+- PTN
< --CH- PSL
- 2.oco -
l
V i c i.ooo -
l
}
l M
l 1
j l o I Unit 1991 1992 1943 1994 1995 1/96 2f96 3/96 4/96 sP96 S/96 -7/96 S/96 ' 9/96 1Qf96 11/96 12/96
- * * *
- 1Mt 1.31o PTN 1.466 1.589 1.422 d * *
- 2.166
-PSL. *
- 1.608 1.920 2.030 2.086 i DEFINITION i
This indicator includes Work Type 1 (Planned Miscellaneous), Work Type 3 (Projects), WorkType 5 (Trouble & Breakdown) and includes all hold codes, status 22 through 48.
- Historic data not meaningful. Prior to 1996, each site was counting Open PWO's differently. St. Lucie was counting only Work Type 5 non-outage corrective and Turkey Point was counting Work Types 1 and 5. Each site now agrees to report per the above l
j dehnition.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE l
i i PERFORMANCE
SUMMARY
1 1
4 Data Providers:(PTN) Greg Heisterman 246-6796 and (PSL) Joe Marchese 467 7107 i
C-1
PWO AGING CURVE woo O PTN Actualj 900 <> PTN Goal ;
--*--- PSL Actual!
800 - O PSL Goal !
700
$ 600 Note: The data in this graph and the PWO's g Greater Than 12 Months graph on Page C-2 reflect g reported Cata discrepancies. Plans are in progress g O to reconcile data reported on these two graphs.
A O'.
400 *',
300 '.
.N 200 u .. .,
.o,,
a.,*
100 .
0 0 'i Y Unit . TOTALS 04 h - --44 Mo. - 7 0 Mo. :10-12 Mo. , - Over 12 Mo.
MN Actual - 949 508 225 106 33 33 PTN Goal - 475 238 119 0 0 P8t. Actual ' 890 378 317 97 45 53, _
PSL Goal ' 445 189 158 48 23 DEFINITION PWO Aging curves includes Work Type 1 (Planned Misc) Work Type 3 (Projects) and Work Type 5 (Trouble & Breakdown),
and excludes short notice outages (SNO), HC2 Startup HC3-Hot Standby, HC4-Ho't Shutdown, HC5-Cold Shutdown, and HC6-Refueling. This only includes status 22 through 48.
Goal: To nalve the backlog every three months.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE 9
PERFORMANCE
SUMMARY
Data Providers: (PTN) Greg Heisterman 246-6796 Bnd (PSL) Joe Marchese 467 7107 C-2
f 1
1 PWO'S GREATER THAN 12 MONTHS (GOLDEN OLDIES) I TURKEY POWT
, REF PWOs PWO TITLE Orig. Date Date on List
) 1 95007509 HAGAN CONTROLLER 35V REG MEAUSRES 30.7 031395 5/1/96 2 95007506 HAGAN CONTROL.LER BOW IN OUTPUT 031395 6h 2 95007506 HAGAN COMROLLER. BOW IN OUTPUT (TST HOLD) 031395 6W 3 95LO6285 RCDT LEVEL LOOP L 51003. VERIFY MAING OF RCDT LEVEL LOOP L 1003 (ENG HOLD) 037t95 ST96 4 95008271 RCDT LEVEL LOOP L 1003. VERIFY WIRING OF RCDT LEVEL LOOP L 1003 (ENG HOLD) 0321/95 51 S6 5 95009033 FLUX MAPNG SYS. CERL PANEL. RPLC FLUX MAP NIXIE TUBES /PWR SPLYIHTAAWP HOLDSi 032&95 5/1/96 6 95009032 FLUX MAPPING SYS , REPLACE FLUX MAP NIXIE TUBES /PWR SUPPLY (HTAAWP HOLDS) 037&t5 5/1/96 7 95009320 FLUX MAPPING SYS RECRDRS R 1420,1421,1422. RPLC FLUX MAPPER RECS W/1 RECRDR 03W95 51/96 i 8 95010755 MEDIAN SIGNAL SELECT MODULE MODEL #1966E57G02. OUTPLIT JUMPS 04/17/95 6396 l 9 95012597 HAGAN SUMMATOR MODEL 0411106&C03. UNIT TRIP 042&95 6396 10 95012596 HAGAN SUMMATOR MODEL #4111084-003. OUTPtfT DRIFTING 47&95 6396 I
11 95013019 CBC GROUP 1/ STEP COUNTER 'C' GROUP. COUNTER REPLACEMENT 5395 6396 12 95013013 S8B GROUP 1/ STEP COUNTER 'B* GROUP / COUNTER REPLACEMENT 5395 6396 13 95013014 $8A GROUP 2/ STEP COUNTER 'A' GROUP / COUNTER REPLACEMENT 5395 6396 14 95013015 SBA GROUP 1/ STEP COUNTER *A' GROUP /COUWER REPLACEMENT 5395 6396 15 95013016 CBD GROUP 2/ STEP COUNTER 'D' GROUP / COUNTER REPLACEMENT 5/3/95 6G96 16 95013018 CBC GROUP 2/ STEP COUNTER "C" GROUP / COUNTER REPLACEMENT 5595 6G96 17 95013020 CBB GROUP 2/ STEP COUNTER 'B" GROUP / COUNTER REPLACEMENT 5G95 6/3/96
] 95013021 CBA GROUP 1/ STEP COUNTER A" GROUP / COUNTER REPLACEMENT 5/3/95 6G96 19 95013022 CBA GROUP 2' STEP COUNTER 'A' GROUP / COUNTER REPLACEMENT 5G95 6596
, 20 95013023 CBB GROUP 1/ STEP / COUNTER "B" GROUPCOUNTER REPLACEMENT 5595 6 4/96 21 95013012 SBB GROUP 2/ STEP COUNTER T* GROUP / COUNTER REPLACEMENT 5/3/95 6/3/96 22 95013017 CBD GROUP 1/ STEP COUNTER 'D' GROUP /CONTER REPLACEMENT 5G95 6G96 23 95013372 1/P42836/ CHARGING PP B TRANSDUCER./GUAGE GLASS MISSING (ENG HOLD) 5/5/95 6596 e 24 95013533 SGB-4-041/lSO VLV FOR S/G A BLOWDOWN TEST CONNECTION / REPAIR 5/BS5 6/3/96 l 26 95013550 HAGAN SUMMATOR MOOEL #4111084 004 /OLTTPUT LOCKED UP 5/8/95 6/3S6 !
95013652 SSS5 6G96 l 26 LCV 4 6265A/ACTR/BLWDWN HX LEVEL CNTRL VLV/ GAGES NEED REPLACING 27 95013675 FTT 4-114/PRI WTR TO BLENDER FLOW TRANS/SEALTIGHT SPLIT 5/9/95 6/3/96 28 95013648 LCV 4-6265A/ACTR BLWDWN HX LEVEL CNTRL VLV/ GAUGE NOT READABLE 5/9/95 6G96 29 95013876 HAGAN OPTIMAC LEAD / LAG CONTROLLER /OUTPt/T NOISY $/10/95 6G96 l 30 95014020 3T25A/ MOISTURE SEPARATOR & REHEATER A/PCM 95-005 5/11/95 6G96 I
31 95014469 HANGERS ON TPCS PIPING TO 3B HTR DRAIN PP/NEED REPLACEMENT 5/17/95 6!3/96 1 32 95014599 SV 12836 INST AIR DRYER PURGE CNTL SOL VLV/ AIR LEAK 5/18/95 6/3/96 l 33 95015302 LT 31544/ LEVEL TRANS FOR CONDENSATE STORAGE TANK / GAUGE RUSTED 5/23/95 6G96 34 W O15456 HAGAN SINGLE COMPARATOR MODEL 4111082-001 5/24/96 BG96 35 95015455 HAG AN CONTROLLER MODEL 411088-001/FAlLED CAL E!24/95 6/3/96 36 95015457 HAGAN SINGLE COMPARATOR MODEL 4111082-001/HIGH AC 5/24/95 6/3/96 37 95015511 RV 3-210B/3B DIESEL GEN AAIR START AIR TANK /NEED TO REPL VLV 5/2595 6G96 38 95015504 RV 3 210A/3A DIESEL GEN AIR START AIR TANK /NEED TO REPL VLV 5/25/95 EG96 39 95015505 RV 3-211 A/3A DIESEL GEN AIR START AIR TANK B RELIEF VLV/NEED TO REPL VLV 5/25/95 6/3/96 40 95015506 RV 3 212A/3A DIESEL GEN AIR START AIR TANK C RELIEF VLV/NEED TO REPL VLV 5/25/95 6596 41 95015510 AV-3-211B/3B DIESEL GEN AIR START AIR TANK B RELIEF VLV! MEED TO REPL VLV 5/25/95 6496 42 95015507 RV 3-213A!3A DIESEL GEN AIR START AIR TANK D REUEF VLV/NEED TO REPL VLV 5/25/95 6/3/96 43 95015787 BTV-11524/ ACTUATOR / AIR OPERATOR FOR TRIP VLV/ AIR BLOWING BY 5/31/95 6/3/96
- 4 95015932 FT-4-1464' FLOW TRANS FOR CCW RTN FROM EMERG CNTMT COOLER / INSTALL VOL 6/1/95 6/3/96 45 95016014 5/G Bt S AMPLE TUBING UMT 3/4 - DETERIORATED TUBING /REPL 6/2/95 6G96 ST. LUCIE REF PWO# PWO TITLE Or69. Date Date on List 1 92352114 SCREEN CORRODED FALUNG APART SAFE'1Y 10/1592 N/A 2 93032089 COMPLETE UPGRADE OF COMPUTER SYSTEM 1291/93 NA 3 94025253 METER MOVEMENT STICKY AND OUT OF CAL 10f0594 4/1/96 4 95001003 INSTALL LEVEL INDICATOR FOR POOL LEVEL 01/11/95 41/96 8 950udO53 REPAIR VALVE LEAK REMOVE DRIPPAN 029995 41/96 6 93034478 OVERHAUL SPARE HVS 1 A MOTOR 021W95 21/96 7 95004389 SUPPORT MN IN ACTUATOR REMOVAL 021395 4/1/96 8 95004447 REBAR is RUSTED AND CONCRETE IS CRACKW 02/1495 2 1/96 9 93034478 OVERHAUL SPARE HVS 1 A MOTOR 0377.95 3 1 /96 PWO Greater than 12 month'S, Work Types 1 throug*l 5, exCludng outage hold Codes (SNO, SNW, HC2, HC3, HC4, HC5, HC6) Status 22-48.
Data Pmndeer (PTN) Greg Heisterman 246-6796 (PSL) Joe Marchese 467 7107 C-3
i NON-OUTAGE PWO'S 1400 i
1 1200 I --+- PTN _
--O-- PSL 1000 O
s 600 e
400 200 o
Unit : 1991 1992 1993 1994 1995 1/96 '2/96 2/96 - 4/96 5/96 6/96 7/96 9/96 9f96 10/96 11/96 12/96 PTN * *
- 1024 1091 1118 1166 949
'PSL *
- 1247 1103 1016 961 890 DEFINITION Non-Outage PWO's includes Work Type 1 (Planned Mise) Work Type 3 (Projects) and Work Type 5 (Trouble & Breakdown), and excludes all outage hold codes. Short notice outages (SNO), HC2 Startup, HC3-Hot Standby, HC4-Hot Shutdown, HC5-Cold Shutdown, HC6-Refueling and includes status 22-48.
- Historic data not meaningful. Prior to 1996, each site was counting Open PWO's differently. St. Lucie was counting only Work Type 5 nonautage corrective and Turkey Point was counting Work Types 1 and 5. Each site now agrees to report per the above riefinitinn.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE PERFORMANCE
SUMMARY
Data Providers: (PTN) Greg Heisterman 246-6796 and (PSL) Joe Marchese 467 7107 C-4
t :
CONTROL ROOM INSTRUMENTS OUT-OF-SERVICE a 1 l
--+-- PTN C
-O- PSL__
so -
0 40 3
O h 30 i-c
.E E /
8 /
$ 20 0
{o May Outage Tags PTN 14 o PSL 12 10 o
Unit 1991 -1992 1993 1994 1995 1/96 2f96 3/96 -4/96 5/96 SP96 7/96 9/96 IW96 10/96 11/96 12/96 PTN 39 40 42 12 30 16 PSL' 54 46 25 20 28 27 DEFINITION This indicator defines the number of control room instruments for each unit that cannot perform their design function, regardless of the reason. Instruments on the control room back panels are readily available for use by the control room crews and are included; however, instruments in adjoining areas where operators are not normally stationed (such as' computer rooms) are not included. Count deficiency tags that are in status 05 to 48.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE PERFORMANCE
SUMMARY
t Data Providers: (PTN) Greg Heisterman 246-6796 and (PSL) Joe Marchese 467-7107 C-5
- . .- - . - .- -~. . ~ - _ . . . . . _ - - _ - - - . . .
e l
l OSHA RECORDABLES (Year-to-Date)
So I
40
--+-- PTN
- -O-- PSL I z
, m 20 . ,
l 10 a i Note: PTN and l PSL 1992 95 data l adiusted in 5/96. C l 0
' Unit 1991 1992 1993 1994- 1906 c1/96 2f96 3fB6 4/B0 5/96 446 7/96 896 '996 10/96 11/96 12/96 ,
PTN 35 39 29 27 20 0 1 2 2 2 !
'PSL 20 22 23 41 46 3 3 4 5 10 )
DEFINITION The definition by Occup".ional Safety Health Adrninistration (OSHA) is an injury occurring on the job that requires medical treatment beyond first aid as defined by 29 CFR 1904.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE Month .Y-T-Q PTN O 2 PSL 5 10 Nuclear Division Y-E Target 1.75 Corporate Y-ETarget 3.75 PERFORMANCE
SUMMARY
Five OSHA Recordable injuries were reported at St. Lucie in May as a result of:
. a lacerated hand cut on a hasp
. a fractured foot, caught between trolly and stop
. a foreign object in an eye while cleaning bolts e a fractured finger struck against a drain line e a hip strain A total of 12 OSHA Recordables have been received year to-date.
Data providers: J. Sarnbito (PTN) 246-7372 and W. Ajfera (PSL) 467-7171 ni
. .. - = . . _ . -. . . _ . - - _ - . . . - . ..
f i
LOST TIME INJURIES (Year-to-Date) 5 l l --+-- PTN l -O- PSL i
3 s
.E l
2 a
Note: An injury at PSL d
occurred m January but l was not reported until May.
f 1 O h'C O O o ; . .
Unit 1991 1992 1993 1994 1996 1/96 246 2/96 4/96 546 -6/96 7/96 846 W96 10/96 11/96 '12/96
, PTN O O O 1 0 0 0 0 0 0 l PSL 2 4 3 1 2 1 1 1 1 1 k l l
l DEFINITION 1 A Lost Time injury as defined by Occupational Safety Health Administration (OSHA) is an occupational injury that requires an employee to miss a full day (8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shift) beyond the day of injury.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE Month _Y.-T-Q PTN 0 O PSL 0 1 PERFORMANCE
SUMMARY
One Lost Time injury was reported at St. Lucie in May for the month of January:
. A F. ant operator injured his knee while performing fire brigade training at the Fire House in January. Surgery on his knee was performed in April.
Data providers: J, Sambito (PTN) 246 7372 and W. Affera (PSL) 467 7171 D-?
'O REGULAR STAFFING FPL Employees and Long-Term Contractors by Department l
Turkey Point 1100 1050- -*- Actual 986 9e ,s 96 ,6 9es - Planned 1000 Se_6 C - - - 3 950 - C -
I 957 g 1 g
900 8 '"*
1100 i 1050 -
~
1f 1.03o 1.o22 i,qo 3 1,o o 1,o o 1.01 1.oY1 1. t f 950 -
900 Engineering & Licensing 348 348 347 347 400 - 343 C C C C D Sig 316 314 312 311 3 200 -
$ 100 - ,
0 Nuclear Assurance 50 106 106 106 106 106 103 104 104 ton los 5 50 -
f 0
Nuclear Operations 40
= 32 32 32
~
M M
[ M. C C C U 31 31 30
-[ 29 29 E 20 -
D g 10 -
0 Nuclear Business Services 15 1 11 11 11 11 11
.[ 10 -
C C C = 3 i to io io 9 9
y 5-0 Nuclear Division Total 2.493 2,493 2.493 2,493 2.489 2500 - 3- g 2,4u 2400- ,,,,, ,'g, ._
D 2,366 2.3s7 g 2300 2200 l 1/96 l 2196 l 3/96 l 4/96 l 6/96 l 6/s6 l 7/96 l stes l s/96 l 10/e6 l 11/96 l tales l Data Providor: Alicia Simpson 694-3275 Data Source: ND Staffing Report p.1
.t :
i l l
OPERATOR EXAMINATION PERFORMANCE I Turkey P0 int Units 3 & 4 100 o %
i E E RO/SRO Pass %
[j D Oper Reg Pass %
_ g 1 c . ::' :i i 95.0% -
! 4 I
h % -
D t f I h f e.
+
a 5 p
- e s ,
90.o% - - -
4 a :: t ,it ! !
! : r .
e ;
4 f f5.o% $ -
.g )i j l
U '
.; L 3 W i h %
h ,
h g .:
h $ k l { $ e >
80.0 %
i Exame: 1991 .1992 1993 1994 1995 1/96 2/96 3/96 4/96 5/96 6/06 7/96 8/96 9/96 10/96 11/96 12/96 RO/SMO Teken 39 5 - 8 13 -
Poseed 39 5 - 8 13 - - - -
RO/SRO Pues % 100 0 % 100 0% 100 0 % 100 0%
Oper Reg Token 47 78 69 63 58 64 - - -
i i Possed 44 75 66 60 56 64 -
Opet Req Pese % 94 0 % 96 0 % 96 0 % 95 0 % 96 5 % 100 0%
j DEFINITION
) Initial License Examination (RO/SRO) results are reported for all candidates taking an Initial License Exam as conducted by the
-! ! NRC.
j Operator Requalification Examination results are reported for both RO's and SRO's. This examination is administered annually by the utility and may be jointly administered by the NRC. Retests of operators who failed examinations are not included.
! STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE
! i Initial RO/SRO License Exams No Taken No. Passed Pass Rate % The NRC at their last Regional Training Managers Meeting 0 0.0% (for fiscal year 1994) provided the following data:
I YTD 1996 0 YTD 1995 13 13 100.0 %
inmal NAC Erams NAC AaaualErams RO's Pass Rate 94 E% RO's Pass Rate 91.0 %
Operator RequalExams Instant SRO's Pass Rate 94 4 SRO's Pass Rate t!5.0%
No Taken No Passed Pass Rate % Upgrade SRO's Pass Rate 94.7% Average Overall B8.0%
YTD 1996 64 64 100.0 % Average Overall 94.6 %
YTD 1995 58 56 96.5 %
1 PERFORMANCE
SUMMARY
i No Initial RO/SRO License or Operator Requalification Exams were given in May 1996 at Turkey Point.
1 i
Data Providers: Mana Lacal (PTN) 24%476 and Pat Fincher (PSL) 467-4161 E-1
- OPERATOR EXAMINATION PERFORMANCE l' St. LuCle Units 1 & 2 100 0 % ,
a.
i h 3 -
E RO/SRO Pass %
- ,{ D Oper Req Pass %
95.0% f y
]
a .
$.2 b I g, , t'
) i MS -
ij -
[
e .
E k ?e
< g-l .% 4 j ,' b i 85.0% g i
! : I
. . : 7 :
f
- i j; ,;
80 0%
E.soms: 1991 ~1992 1993 1994 :1995 1/96 '2/96 3/96 '4/96 5/96 6/96 7/96 8/96 9/96 1 0/96 11/96 12/96 ROrSRO Taken 15 8 10 11 - 4 - -
- Passed 15 8 10 11 - 4 - -
RO/SRO Pass % 100 0% 100 0% 100 0% 100 0% 100 0%
i OperReqTaken 65 69 68 75 73 - - - - -
Possed 61 60 68 68 71 - - -
Oper Reg Pass % 94 0 % 87 0% 100 0% 91 0% 97 5 %
DEFINm0N Initial Ucense Examination (RO/SRO) results are reported for all candidates taking an initial License Exam as conducteo by the j NRC.
Operator Requalification Examination results are reported for both RO's and SRO's. This examination is administered annually by the utility and may be jointly administered by the NRC. Retests of operators who failed examinations are not included.
l STATIET'CA!. EUMMARY INDUSTRY PERFORMANCE Initial RO/SRO bconse Exams Pass Rate *,,c The NRC at their last Regional Training Managers Meeting No Taken No. Passed (for fiscal year 1994) provided the following data:
YTD 1995 0 0 0.0% ,n,,, yqe go,, gne q,,y,, g,,,,,
, RO's Pass Rate 94.6 % RO's Pass Rate 91.0%
No Taken No. Passed Pass Rate % Upgrade SRO's Pass Rate 91.7% Average Overall 88.0 %
0.0% Average Overall 94.6 %
YTD 1996 0 0
- 97.5%
YTD 1995 73 71
$ PERFORMANCE
SUMMARY
No exams were given in May 1996 at St. Lucie.
Data Providers: Mana Lacal (PTN) 2464476 and Pat Fincher (PSL) 467 4161 i
F-7
OVERDUE CONDITION REPORTS ;
- {,
l 100 l -+-- PTN I k-O--PSL F l
80 -
)
, a 70
\ :
)
1 g 60 \
! i
- O '
- ISO j 40
\ /\
v t.
\/a \
20
\
i a
' e \
UnN' O
1991 1992 1993 1994 1996 1/96 246
/Nu 3/96 4/96 EPD6 646 726 9/96 9f96 1046 1156 12/96 PTN 6 0 0 12 0 1 PSL 95 25 51 0 8 l
l DEFINITION i
- Currently, the Nuclear Division is transitioning to a consistent Conddion Report. The project is scheduled to be completed by May 1, 1996 at all locations. This graph shows Condition Reports that exceed assigned priority timeframe.
- Severity Levels are as follows:
! A = 3 working days B = 10 calendar days C = 30 calendar days l
! STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE 1
l
\
j i
PERFORMANCE
SUMMARY
I Data Provdere, (PTN) Juho Balaguero 246-6971 and (PSL) B2 Dawson 467 7154 c.i
- . - - - _ _ - - - -- - - .. . . . . .. . ~ . - . - . _ _ - _ _ - _ . . , ~ . -, ~.
OA FINDINGS 20
-+- PTN PSL
- d!r-Juno 1$
l 1
E g 10 B
z 6
)
0 .- _ . . .
Unit 0 30 days 3140 days - . 41-90 days ?91-120 days 121150 days 151-100 days 101-210 days PTN 1 0 0 1 0 0 0 PSL 6 3 0 1 0 2 0 Juno 6 5 0 0 0 1 7 DEFINm0N The indicator represents the age of audit findings open as of the last day of the month. The clock starts on the day of the 1 audit report transmhtal and continues until Quality Assurance (OA) verifies that implementation has occurred. l STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE PERFORMANCE
SUMMARY
Data Provder. R. A. Symes 694-4287 F-2
NRC VIOLATIONS Cited and Non-Cited (Year to-Date) 22 20 4
7 f l 0 PTN NOVs!
i ! I / ;. . +- .PSL l--o . PTN NOVs NCVsl;
- O PSL NCVsl 16 l en .A E 14 12 j :
to
\'. . .
- ' ' 0l
- n' _ \l }:
4 4 [ 1996 Y E Target: s7 I
, a
\! J .a . :o O . . . . . . .O. . . ox g .
\ >
O* , : O' = -C'
]
o Urdt 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 12f96
- PTN NOV's 13 8 4 4 1 o o 0 o 1 PTN NCV's ' 21 7 13 12 #5 o 1 3 3 $
PSL NOV's 8 8 7 9 21 o o 4 8 8 PSL NCV's 3 3 3 3 12 1 1 1 5 5 DEFINITION Violations are categonnd in terms of five levels of seventy to show their relative rnportance. Seventy Levels I and 11 are violations that mvolve actual or high potental impact on the public. Seventy Level lli Violatons are cause for significant concem. Seventy Level IV violations are less senous, but are of more than moor concem; i.e., if left uncorrected, could lead to a more senous correm. Seventy Level V vdatons are moor safety or environmental concem. Vdatons are counted on the date of the mspecton exit meeting. Violatons are now counted with respect to the date of occunence (usmg the date of the mspection exit meebng) mstead of the date of the inspection report, as was done m the past.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE Ma,y .YIQ YeatEnd Target NRC Violations PTN Cited 1 1 7 1994 IBG Group Mean 16.2 PTN Non-Cited 2 5 1994 Region 11 Mean 13.1 PSL Cited 0 8 7 1994 IBG Top Quartile Mean 9.0 PSL Non-Cited 0 5 1994 Region ilTop Quartile Entry 8.0 PERFORMANCE
SUMMARY
] Turkey Point reponed one NRC Violations in May-
- #%M02
- Failure to follow Chemical Volume Control System Operatng Procedure dunng a Unit 4 blender flushing evoluton. Exit Meetng date: 5/15S6.
St. Lucie reported one potential NRC Violation for the month:
- 96 06 Fra bngade members not fully qualified. Exit Meetng date: 5/1/96.
4
- 964101: Temporary Procedure changes were made which involved changes of mtent, without pnor FRG revew as required by Tecnnical Specifications Exit Meeting Date: 2/20/96.
- 96 03-01: Operators failed to follow procedures for boron dilution. Exit Meeting Date: 2S96.
- 96-03 03: Inadequate 50.59 safety evaluaton of change to boron dilution procedure. Exit Meeting Date: 2496.
l
- e96M01: A containment gaseous monitor was rendered inoperable due to a failure to follow procedures, combined with a lack of taking proper logs. Exit Meeting l
Date:4396.
- 96 04-02: Failures to make required log entnes for reactivtty manipulatons and a main generator hydrogen additort Exit Meetng Date: 4396.
t96-04 03: An EDG rendered operable due to a failure to follow procedures while placog the fuel oil tank on recirculaton. Exit Meetng Date: 4!396.
- 96-04-04:Revews of histoncal data for CEA maintenance revealed that post-modification testing acceptance entena for Unit 1 CEA power cabies were not applied to post modification test data. Exit Meeting Date: 4/396.
Year to date, Turkey Point has reported one NRC Violaton and St. Lucie has reported 8 and one potental violation.
Data Providers: (PTN) Gary Hollinger 246-6078 and (PSL) Ed Weinkatn 467 7162 i F-3
_ _ .. . _ . _ _ . _ . .. . . _ _ .- ._..m __m . _ _ _ . _ _ . _ ._ . . . _ . . . _ . _ _ , _ . . .
d LICENSEE EVENT REPORTS (Year to-Date) 1 25 i
'4 --+- PTN l ,
to -
-O-PSL i 7
b i =L i E 15 E
c w -
4
! J
^
5- ~
i, j
i o I
}
j ' Unit 1991 1992 1993 1994 1996 1/96 2/96 3/96 4/96 6/96 8/96 7/96 8/96 9/96 10/96. 11/96 12/96
- 'PTN 20 24 9 12 7 1 5 5 7 8
' PSL 9 10 8 15 18 1 5 5 5 5 f
i DERNITION 1 1 1 ;
j License Event Reports (LER) are submitted to the NRC by the licensee to report unusual occurrences prescribed by 10CFR50.73.
i i
~
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE i
) MU IIQ t
1 PTN 1 8 4
PSL 0 5 1
- PERFORMANCE
SUMMARY
i No LER's were reported in May 1996 by St. Lucie.
- Turkey Point reported one LER for the month
i i #96 manual reactor trip occurred due to a turbine govemor control oil perturbation.
i Data Providers. (PTN) Gary Hollriger 2464078 and (PSL) Ed Weinkam 467 7162 F4
l l i
, ! INPO ASSESSMENT RATINGS 1
i ,
- 2 4 00 l
l'P l l 330 - - - - - - - - - - ' O Pst ' l l
3 00 -
2 50 - - - -
) E
] [ s.00
- i30 _ _ _ _ _
i 00 _ __ - - -
l
- 1. 0 s0 _ _ _ _ _
0.00 -
1 Unit 1986 1987 1988 1980 1990 1991 i 1992 1993 1994 1995 ifs 6 PTH 4 00 4 00 3 03 4 00 3 00 2.00 2 00 1.00 Psl 2.00 1.00 1 00 1.00 INPO ASSESSMENT PROGRAM DESCRIPTION The Inst;tute of Nuclear Power Operations (INPO) conducts penodic evaluations of site activities to make an overall determination of plant safety, to evaluate management systems and controls, ano to identify areas need:ng improvement. Information is assembled from discussions, interviews, observations, and reviews of documentation.
Evaluation Frequency: INPO's goal is to visit each plant on an average cf every 18 months. However, this frequency may vary depending upon the previous assessment ratings. For instance, if a plant is rated a "1* or *2*, the interval between assessments is usually 20-24 months; if a plant is rated a '4" or a '5*, the assessment interval is s 18 months.
Performance Cateaory Rat!ncs:
Category 1: Ovarall performance is excellent. Industry standards of excelience are met in most areas. No significant weaknesses noted.
Category 2: Overall performance is exemplary. Industry standards of excellence are met in most areas. No significant weaknesses noted.
Category 3: Overall performance is generally in keeping with the high standards required in nuclear power. However, improvements are needed in a number of amas. A few significant weaknesses may erst.
Category 4: Overall performance is acceptable, but improvements are needed in a wide range of areas. Significant weaknesses are noted in several areas.
Category 5: Overall performance does not meet the industry standard of acceptable performance. The margin of nuclear safety is measurably reduced. Strong and immediate management action to correct deficiencies h, required. Special attention, assistance, and follow up are required.
N2T.E: If a plant is found to be operating without an adequate margin of nuclear safety, INPO will request that the plant be shutdown, or not started up.
PERFORMANCE
SUMMARY
Turkey Point and St. Lucie received an INPO category rating of *1' in 1995. The next evaluations for Turkey Point and St.
Lucie are expected in the last quarter of 1996 and first quarter of 1997, respectively.
i, 5
Dra Premdes (PTN) Gary Hollinger 246-6078 and (PSt.) Ed Weinkam 467 7162 F-5
_ _ _ _ _ _ _ _ _ . _ _ - - . - - , - - . . . - -. -.- . -~ . -.
NRC SALP CATEGORY RATINGS f 2.50 l
E PTN Rating l 2m -
f O PSL Rat;ng ;
l i E 1.50 -
i 5 e
b
$ im .. . . _ _ _
0.50 -
t 0.00 -'
1 1986 1987 1988' 1989 ' 1990 : 1991 1992 1993 1994 1995 1996 PTN Rating 2.27 2.18 2.25 2.14 1.86 1.38 1.38 1.29 1.00 - -
Parlod Eneng 4/30/86 5/31/87 6/30/88 7/31/89 7/31/90 9/2&91 1/3093 8/27/94 -
j PSL Ratino 1.55 1.20 - 1.29 1.14 1.00 1.00 1.50 Period Ending 4/30/86 10/31/87 - 4/30/89 10/31/90 -
5292 - 1/1/04 - 1/696 SALP PROGRAM DESCRIPTION tt a the pohcy el the NRC to use the Systemanc Assessment of Lcensee Performance (SALP) process n) arnculate the agency's cosentanons and msgnts on bcensee salety pefformance.
The SALP report commumcates those observanons and maights.
Evabanan Frememv The NRC wil normally review and evaluate each power reactor kcensee that possesses an operanng beense at least every 18 months. When the NRC detemunes that the performance warrants a rnore frequent evaluanon, the norma! SALP troquency may be mersased The assessment penod rimy be extended to a rnarrmum of 24 months when a plant receives a Category I ranng m all leur lunctonal areas.
Fec*enal Amas Performance a generally evabated miour(4) funcnonal areas:
- 1. Ptam Oce- TNs funcnonal area consats cNelly of Ihe contrd and execunon of acovmes erectly related to operanng a piant it meludes acnymes such as piant startup power operanons, plant shutdown, and system kneups.11 also mducles rN and requaldcaton trammg of bcensed morators.
- 2. Ma atenance TNs funcnonal area mciudes all acavees assow : uth erther dagnostc, pre $ cave, prevereve, or corrective mantenance of plant structures, systems, and components, or rnamtenance of the physca! condnon of the plant
- 3. Ewaeems TNs functional area addresses the adequacy d techrucal and engmeenng s@ port lor alt plant ac6 vees.11 nduces all bcensee activmes assocated w@ desgn contr$; the desgn, mstanabon. and testmg of plant mod 6 canes; engneenng and techrscal support for operatons. outages, mantenance, tesung, surveihance, and procurement activees:
configuranon management desgn-bass olormanon and ns remeval; and support for hcenang scavees
- 4. P.rt Suceer' TNs functiorW area covers all acnvmes retared to plant support funchons, mdudng radological controts emergency prepareoness. seeinty, chemistry, and 6re protecnon.
Houseteepmg controls are also induced m ins area.
Peamanca Cyrv Aam Ocensee performance m each luncnonal area is assessed by assgnmg a category ratmg as dscussed below-Category 1. Ucenses anenten and mvorvement have teen property focused on safety and resulted m a supenor level of utety periormance Category 2. bcensee attermon and involvement are normally welllocused and resutted in a good level of safety performance.
Category 3 beensee anewon and mvo#vement have resulted m an acceptable level of perfomunce. However, pertermance rnay exNbd one or more of the folloung charactenstcs:
meffectve programs and significant asues, lack of corrective accan 1horoughness, and deficiences m root cause analVss Because the m&96 to unacceptabe performance m important aspects a sfrt ncreased NRC and hcense ' attennon a requesd.
PERFORMANCE
SUMMARY
Turkey Point SL Luoe Pnor Most Aeeggt Pnor Most Aecertt Functonal Area:
Plant Operations 1 1 1 2 Maintenance Iimproving 1 1 2 Engineenng 2 Improving 1 1 1 Plartt Support n/a 1 1 1 Emergency Preparedness 1 n/a n/a n/a Radiological Controls 1 n/a n/a n/a Secunty i n/a n/a n/a Self Assessment / Ouakty Venfication 1 Id D3 Dla Overall: 1.29 1.00 1.00 1.50 Data Prowders- (PTN) Gary Hollinger 246 6078 and (PSL) Ed Weinkam 467 7162 p.6
I INVENTORY VALUE ACCOUNT 154.300 Bo 4
70 --+- PTN
-C>-- PSL 0
Y So a
e e C 2 40 3 -
"Nm .
1996 Y-E Target: s 38 ($M) l l o .
2 to 4 i io -
i 0
Unit 1991 '1992 '19e3 1994 1995 1/96 2/96 3/96 4/96 5/96 '6/96 7/96
) S/96 9/96 10/96 11/96 12/96 j PTN 79 1 74 7 54 6 42 4 37 4 G7.4 37.2 36 0 35.1 34.9 PSL 58 6 65.2 60.2 437 39 4 42.0 42.3 43.5 42.9 43.6 DEFINITION This indicator reflects the valve of Account 154.300. This account reflects materials needed to keep operational the physical equipment and facilities of the plant (e.g., spare parts, consumables, commodities, tools). The information is pulled from SAR Report #G0009R72-501. The Passport system utilizes SAR for system data reporting.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE l EliLrt End % Chance YE Taroet IBG (Year 1994)
- Total Average $43.6 Million PTN Monthly 35.1 34.9 -2.5% Top Quartile Entry $34.7 Million f
j Y-T-D 37.4 34.9 ?.7% $38M Top Quartile Average $28.9 Million j PSL Monthly 42.9 43.6 4.2% i Y-T-D 39.4 43.6 10.7% $38M 'Value does not include Cap'rtal as defined by PRUC
~
n PERFORMANCE
SUMMARY
. Turkey Point Regular inventory decreased by $0.2M in May.
i . St. Lucie's Regular Inventory increased by $0.7M for the month due to receipts for outage materials.
l .
i 1
Data Prowders: (PTN) Dick Rose 246-6692 and (PSL) Tom Kreinberg 4654183 '
l
- n. , l 1
- - = _. _.
OPEN PLANT CHANGES / MODIFICATIONS (PC/MS) 350
- +- PTN
-O- PSL NOTE:
There are 29 additional PCMs not counted in this total for the steam generator replacement 250 Also, this number wdl decrease once Unit 1 outace is completed g200 2
e 150 m m Design: 25 35 Review: 13 34 100 Wortung- 48 107 Update: 84 109 Total: 170 285 50 o
3 96 4/96 5/96 6/96 7/96 B/96 :9/96 10/96 11/96 12f96 Un6t - ,3 1 '1992 1993 1994 1995 1/96 2/96 240 242 230 219 170 PTN 6 316 326 269 274 285
-PSL DEFINmON This indicator tracks the total number of PCMs in the engineering department. The purpose is to provide management a snapshot of the number of PCMs. Includes all jobs that have been approved by plant management, and are in design, operability review, or implementation phases. The PC/M is considered open until System Acceptance Tumov and drawing updateis complete.
STATISTICAL SUMMAPY INDUSTRY PERFORMANCE PERFORMANCE
SUMMARY
Data Providers: (PTN) Jim Reed 246 6903 and (PSL) Kns M0hindroo 467 7482 Yf 9
OPEN TEMPORARY SYSTEM ALTERATIONS so NOTE. This number will l -+-- PTNI .
decrease once Unit 1 outage is completed.
25 I
e to 8
( >
n g 15 -
i m
c 10
^
5 N
i o j 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 5 5 2 3 6 3 PSL 17 15 16 21 24 27 DEFINITION A temporary system alteration is a modification made to plant equipment, components, or systems that does not conform with approved drawings or other design documents; a modification that is necessary for continued safe plant operation; a modification that will remove a nuisance or distraction to the Plant Operators; a modification necessary to enable the plant to start upin a safe manner.
t l STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE May Year End Goal PTN 3 5 PSL 27 10 PERFORMANCE
SUMMARY
Data Providers: (PTN) Julic Balaguero 2464971 and (PSL) Kris Mohindroo 467 7482 u.9
- CONTAMINATED FLOOR SPACE ww
--+- PTN '
-O- PSL 1
4000 '
i l
is.
! 3000 5
- E 2000 d
4 l 1000 i
f O _ _
Unit - 1991 1992 1993 1994 1995 1/96 2/96 3/96 4/96 5/96 6/96 '7/96 4/96 9/96 10/96 11/96 12/96 PTN 1750 50 330 700 3748 32 559
, PSL 5610 4351 4600 2848 1480 250 280 12 12 4354 I
l DEFINITION This indicator, designed to measure contaminated floor space with removable activity 21000 dpm/100cm sq. beta / gamma or 2 20
, dpm/100cm sq. alpha, is counted against the base. Areas that can be specifically exempted from the base include: reactor j containment building, chemical volume control system demineralizer room and long term process areas such as the decontamination
- faciltty. Contaminated components such as charging pumps, evaporators, etc. are not included as part of " recoverable" floor space j (i.e. not considered ficor area you can walk or step on).
! PTN: Total Base (117,746 sq. ft.) Exemoted Area (6,110 sq. ft.)
PSL Total Base (112,422 sq. ft.) Exemoted Area (7,722 sq. ft.)
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE i Mu IEQd PTN 559 50
- PSL 4354 50
- PERFORMANCE
SUMMARY
Turkey Point and St. Lucie's Contaminated Floor Space was higher than the year end target.
j ,
Data Providers: (PTN) John Undsay 246-6546 and (PSL) Hank Buchannon 467 7300 T.1
't
I DRY ACTIVE WASTE: GENERATED, SHIPPED OFFSITE l t
(Year-to Date) 14000 C l c PTN Generated' 12000 . . + . . PTN Shipped g ,
l
--o- PSL Generated 4 O PSL Shipped l 10000 i
8000 U
6000 g NOTE PTN. 4955 cu.
ft actually onsite whech 4000 ^
neludes 600 cu. ft.
carryover from 1995.
'O g- .o 4
0 0 e c c !
e Unit 1991 1992 1993 1994 1995 1>96 2/96 3 96 4/96 SID6 6fD6 '7/96 8/96 IW96 1Gf96 11/96 12/96 i PTN Generated 8100 425 515 3925 4115 4355 PTH Shipped 2560 0 0 0 0 0
- PtL Generseed 11740 rVa 820 1845 750 5000
- PSL Shepped 13003 0 2080 3322 2396 2194 DEFINITION Generated Is an estimate based on the number of " yellow bags
- initially generated prior to surveying for free release or shipment as radwaste.
I Calculation: Number of yellow bags x 5 cubic feet = Estimated Monthly Generated Waste figure.
Shicoed offsite - The amount of dry active radioactive waste that FPL ships to either Scientific Ecology Group Inc. (SEG) or American Ecology Recycle Center (AERC) for processing.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE PSL made 6 shipments to SEG in 1995.
PTN made 3 shipments to SEG in 1995.
- PERFORMANCE
SUMMARY
e PTN projects to ship 5,120 cubic feet in 1996.
St. Lucie shipped 2,194 cubit feet of Dry Active Waste in May.
Data Providers: (PTN) John Lindsay 246-6548 and (PSL) Hank Buchannon 467 7300
- s. ,
)
l l
PERSONNEL CONTAMINATION EVENTS '
(Year to-Date) i 180
- , --+- PTN 160
, & pg(
i 140 1
120 I
^
. 100 8
i ic !
p -
h Y ) .
, 8 m
40 20 <
l l
0 .
1 Unit 1991 '1992 1993 ~1994 1995 '1/96 -296 3/96 4796 5#96 6/96' ~7/96 8/96 ef96 10/96 11/96 12/96
'PTN 183 85 95 100 73 4 9 23 32 36 l
, PSL 87 76 84 82 0 2 2 5 83
- DEFINITION This indicator is designed to monitor personnel contamination. A personnel contamination exists wtien 5000 dpm per 100cm2 on skin or personal clothing as detected by Personal Contamination Monitor and 2100 counts per minute (net) using the j Frisker is observed.
1
, STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE
- Mn YiED 1 PTN 4 36 PSL 78 83 P
PERFORMANCE
SUMMARY
Data Providers: (PTN) John Lindsay 246-6548 and (PSL) Hank BuchannOn 467 7300 1A i
RADIATION EXPOSURE (Year-to-Date) 1000
$ - +-- PTN Y T D _
--O-- PSL Y-T D g rw
\
\
i*
e
\
500
{ ^
PSL Y-E Target: 485 l l 400 I
N PTN Y E Target: 275 l l 200 Note: April 1996 numbers
- ' adjusted to reflect TLD data 0 C
. Unit - 1991 1992 1993 1994 '1996 ~ 1/96 2fB6 3/96 4/06' Sit 6 $#96 7/96 9/96 9/96 10/90 11/96 '12/06 PTN Y T-D 9380 3240 281.8 476.2 214.6 5.3 9. 5 159.2 165 5 169.1 PSt.Y T-D 451.3 244.5 459 9 504 7 412.8 30 9.0 13.0 21 9 2166 l DEFINITION Collective Radiation Exposure is the total effective dose equivalent received by all on-site personnel (including contractors and visitors), it includes extemal deep dose as measured by the thermoluminescent dosimeters (TLD's) plus intemal dose. It is reported in man-rem for the station. Current month readings may be taken from the direct reading dosimeters (DRD's).
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE a
M_ay HQ YTD Taraet 12-Mo. Endina Man-Rem PTN 3.6* 169.1 240.0 306.6 WANO (PWR's) (two units)
PSL 194.8* 216.6 283.0 401.6 1995 Median 306 Year End Targets: 1995 Goal 370 PTN: 275.0 PSL : 485.0 PERFORMANCE
SUMMARY
e Turkey Point's performance Y-T D was below the Y-T-D target; performance for 12-mo.'s ending of 306.6 is slightly higher than the industry median in May.
. St. Lucie's performance Y-T-D was below the Y T-D target; performance for 12-mo.'s ending totaled 401.6 which is higher than the industry median.
Data Providers: (PTN) John Lindsay 246-6548 and (PSL) Hank Buchannon 467 7300
- Includes DRD count l
p
- O&M BUDGET - DIVISION (Year-to-Date)
. 350.0 1 .
i .
. l -e-- Actual
., l . . . . . Budget 250.o
- _i
- 3^ 200.0 *
- t. ,.
l E
=
$ 150.o ,.
f 100.o f
50.o ,-
0.0 1991 '1992 1993 1994 1995 1/96 '2f96 3/96 W96 5/96 6/96 '7/96 8/96 Sf96 10/96 11/96 12f96 s Actual 342.4 295.2 290.6 285.2 269.5 13 4 31.2 67.4 96.7 128.5 Budget
- 333.3 314 6 326 4 302.o 779.2 17.8 36 7 75 8 104.8 129 6 147.4 164.0 180.0 201.2 218 0 233.9 252.8 Verlance (%) 2.7 6.2 11 0 -56 35 -24 9 14 9 11.1 7.8 0.9 DEFINITION Operating and Maintenance Expenditures include Nuclear Division operation and maintenance expenses associated with direct employees, contractors and consultants, equipment, tools, design, engineenng and other items / activities required to sustain the electrical generation of the plants and to provide required support. Fuel costs, corporate administrative and general expenses, and charges from other departments outside the Nuclear Division are excluded.
Y-T-D Actual Excenses - Y-T-D Budoeted Excenses x 100% = O&M Variance %
Y T D Budgeted Expenses STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE O&M Budoet May Y-T-D Actual ($M) Y-T-D Variance ($M) '/2 $297.0M IBG Actual 1994 Avg _
IBG Top Quartile Entry $270.0M 1996 128.5 ($M) 1.1 ($M) 0.9% IBG Top Quartile Avg. $213.2M 1995 80.3 ($M) -13.5 ($M) 14.5% IBG Projected 1995 Avg. $284.0M 1996 Y-E Budget: 252.8 ($M) Projection (per dual unit site) derived by trending 1986-94 Actual dau and 1995 Budgeted data for IBG Group.
PERFORMANCE
SUMMARY
(.,&M Expenddures through May 1996 were $128.5 million which represented a budget underrun of $1.1 million (or 0.9%).
Significant contributors to the variance include: St. Lucie Unit 1 outage schedule change; deferral of St. Lucie Spare Low Pressure Turbine Rotor refurbishment; and Turkey Point Thermal Uprate costs lagging budgeted cash flows.
Data provider. T. O. Nasby 694-4188
- 1. I j
- I
CAPITAL BUDGET- DIVISION (Year to-Date) 180 0
. l + Actual
=
l -Budget 140 0
\,\
120.0 ',
E .
1", .
$ 100.0
\jf,f,
=: .
8 .
80.0 60 0 1
40.0 ,,
'"***~
~'
20.0 ,,,....--
0.0 w
1991 1992 1993 '1 994 ~1996 1f96 2f96 3/96 4/96 6/96 6796 17/96 8/96 9/96 10/96 11/96 12/96 Actual 150.7 68 4 90.3 76.5 47.2 1.5 2.5 2.9 6.3 9.3 101 4 87 7 64.7 4.8 . 7.1 11.1 15.7 17.9 19.8 22.6 26.3 27.8 30.1 33.1 39.2
'T 179 6 75.1 Vertence (%) -16 1 90 11.0 12.7 -27.0 67.6 45.0 -73 7 59.7 -47.7 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 c6sts are excluded.
Y-T-D Actual Exoenses - Y-T-D Budaeted Excenses x 100% = CapitalVariance %
Y T-D Budgeted Expenses STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE CaoitalBudael May Y-T-D ActuaH$M) Y T-D Variance ($M) $ IBG Actual 1994 Avg. $63.1M IBGTop Quartile Entry $28.3M 1996 9.3 ($M) B.5 ($M) -47.7% IBG Top Ouartile Avg. $21.1M 1995 9.5 ($M) -8.2 ($M) -46.4% IBG Projected 1995 Avg. $58.5M 19% Y E Budget: 39.2 ($M). Projection (per dual unit site) derived by trending 1986-94 Actual data and 1995 Budgeted data for IBG Group.
PERFORMANCE
SUMMARY
Capital E):penditure., .. rough May 1996 were $9.3 nuhan which represented a budget underrun of $8.5 million (or 47.7%).
Significant contributors to the variance include: Plant rojects cancelled / deferred /or reclassified as O&M; and underrun in Steam Generator Replacement Project (SGRP) due to che nge in outage start date.
Data provider: T. O. Nasby 694-4188 J- 2
INTERNAL DISTRIBUTION:
R. J. Acosta JNA/JB D. E. Jemigan PTN/ PLT T. V. Abbatiello PTN/ PLT H. H. Johnson PSUPLT L W. Bladow PSUPLT V. A. Kaminskas PTN/ PLT W. H. Bohlke JPN/JB T. Kreinberg PSUPLT J. B. Brady CC/JB J. T. Luke PTN/ PLT J. L. Broadhead JEX/JB R. D. Mothena JNE/JB C. L Burton PSUPLT H. N. Paduano JPN/JB R. L Castro JDC/JB J. G. Pizzutelli JNE/JB J. Clay PSUPLT T. E. Roberts JPN/JB K. R. Craig JPN/JB R. E. Rose PTN/ PLT R. E. Dawson PSUPLT D. Samil FNG/JB D. J. Denver PSUPLT J. Scarola PSUPLT M. S. Dryden JNUJB C. H. Shotwell JHR/JB P. L Fincher 'PSUPLT R. Sipos PSUPLT J. C. Hampp ETS/JB J. A. Stall PSUPLT J. R. Hartzog PTN/ PLT R. A. Symes JNA/JB R. G. Heisterman PTN/ PLT C. Villard JPN/JB G. Hollinger PTN/ PLT E. Weinkam PSUPLT R. J. Hovey PTN/ PLT D. H. West PSUPLT 4 R. West PTN/ PLT EXTERNAL DISTRIBUTION:
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 D. B. Miller, Jr.
Supervisor Nuclear Safety & 0/ Sight Kerry D.Landis, Region 11 NEU Services Company Nuclear Regulatory Commission P. O. Box 270 101 Marietta Street N.W., Suite 2900 Hartford, CT 06141-0270 Atlanta,GA 30323 T. P. Johnson NRC Senior Resident Inspector PTN/ PLT Z-1