ML20137N211
| ML20137N211 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie, Turkey Point  |
| Issue date: | 05/14/1996 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20137K821 | List:
|
| References | |
| FOIA-96-485 NUDOCS 9704080292 | |
| Download: ML20137N211 (56) | |
Text
{{#Wiki_filter:. - - - . - - - . - .. - - - - - - - - - - - i FPL NUCLEAR DIVISION TURKEY P0lNT NUCLEAR STATION ST. LUCIE NUCLEAR STATION l i ! MONTHLYINDICATOR ! REPORT l April 1996 i I I l
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Issued: May14,1996 40 2 970402 BINDER 96-485 PDR
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i ! FPL NUCLEAR DIVISION l l TURKEY POINT NUCLEAR STATION ! ST. LUCIE NUCLEAR STATION i i I ! MONTHLY INDICATOR i REPORT l April 1996
- I l 1 i
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d j h Issued: May14,1996 g40 egg 297o4oa BINDER 96-485 PDR
FOREWORD The Nuclear Division Monthly Indicator Report presents a compilation of performance indicators which provide a quantitative indication of performance. Specific areas of 1 focus include nuclear and personnel safety, plant reliability, and economic ' performance. 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 quarity control efforts, and of comparisons to other data sources. Each monthly report will reflect the best available data. 1 k i
l TABLE OF CONTENTS Foreward i D. PERSONNELINDICATORS OSHA Recordables.- - - - D-1 Table of Contents ii LostTimeinjuries .. - D-2 lii Regular Staffing.- -D3 Management Summary Nuclear Division Business Plan Indicator Overview v E.TRAININGINDICATORS NRC Indicator Performance Overview Turkey Point vi Operator Exam Perfortnance- Turkey Point .... . E 1 vii Operator Exam Performance St. Lucie= .. . E-2 NC Indicator Performance Overview St. Lucle WANO Indicator Performance Overview viii F. NUCLEAR ASSURANCE & REGULATORY INDICATORS WANO Indicator Variance Explanations ix Overdue Condition Reports. F-1 QA Findings.= = . . .. .. .. . . F 2 NRC Violatons: Cited and Non-Cited... .... F.3 A. WANO INDICATORS Ucensee Event Reports (LERs) - F4 WANO Weighted Overall Performance A-1 INPO Assessment Ratngs.. .. .. . .. ...F-5 NRC SALP Category Ratings.. .. F-6 Unit Capability Factor. = A-2 Unplanned Capabiltty Loss Factor-- = A-3 Unplanned Auto Trips Per 7000 Hours Critical- - .A4 High Pressure Safetyinjectionrs/.am Performance.. .A5 G. MATERIALS INDICATORS Auxiliary Feedwater System Pc t.r".ance .. .. A-6 inventory - G-1 Emergency AC Power System Performance . -.. ... . A-7 ThermalPerformance. - - .. A-8 Fuel Reliability. - -
- .. ... . A9 Chemistryindex - -... A-10 H. TECHNICAUENGINEERING INDIC ATORS Radation Exposure - . . .
A 11 Low Level Waste. - A 12 Open Plant Changes / Modifications = .. .. ... H-1 Open Temporary System Alteratons..- .. .. H-2 Industrial Safety Performance -.-.- - - - A.13 B. OPERATIONS INDICATORS L RADIATION PROTECTION INDICATORS l Contaminated Floor Space - i.1 Equivalent Availability Factor. - .. . . - - - B1 . . _ Capacity Factor (MDC Net) - B-2 Dry Active Waste: Generated, Shipped Off Site.... 1-2 B.3 PersonnelContamination Events - - ..~. 1-3 Fuel Utlization(PTN) . . . - .. Radiaton Exposure (Y-T D) - -la Fuel Utilization (PSL)- .... B4 Forced Outage Rate ; - - - - B-5 l l Unplanned Auto Trips .. ... . . . . . . . . . B-6 J. BUSINESS INDICATORS u@et @sion - . . . J-1 C. MAINTENANCEINDICATORS CapitalBudget -Division -;. .J-2 l Open PWO's.. .. .. -
. . . . . . . . - - C-1 l PWO Aging Curve. .- C-2 PWO's Greater Than 12 Montns Old.. -
.. . C-3 Appendix
( Non-Outage PWO's.: -C4 Control Room instruments Out of Service ..- .... ....- C-5 Distributon List... .. ... . Z-1 l 1 i l i il
MANAGEMENT
SUMMARY
OPERATING PERFORMANCE Turkey Point Unit 3. Unit 3 operated at 100.0% EAF in April. For the year, the EAF was 90.5% which is below the 95.0% Y-T-D target. Turkey Point Unit 4. Unit 4 retumed to service on April 8th after a scheduled refueling outage. Power d losses for the month were the result of: a refueling outage (178.6 hours); Turbine Overspeed testing (5.4 hours); a manual trip due to clogged orifice in the Main Turbine Govemor Control System (26.7 hours); repair 4 4 to 3A/4A Feedwater Heater (13.6 hours); and, repair to 4B Main Feedwater Pump Control Circuit (1.0 hour). The EAF for the month was 68.7% and 68.4% Y-T-D, which is higher than the Y-T-D target of 58.7%. St. Lucie Unit 1. For the month, Unit 1 EAF was 93.7%. Power reduction equating to 45.2 hours was the-result of downpowering for a scheduled refueling outage. For the year, the EAF was 94.6% which is slightly
- higher than the Y-T-D target of 94.0%.
St. Lucie Unit 2. Unit 2 EAF for the month was 92.3%. Power losses were attributed to repair to the Condenser Waterbox (32.3 hours), Turbine testing (19.0 hours), and Chemistry hold (4.1 hours). Year-to-date, EAF was 92.1% which is below the target of 95.0%. l Y-T-D Equivalent Availability for the Nuclear Division was 86.4% which is higher than the 85.7% targeted through the period. No Unplanned Automatic Trips occurred in April. Year-to-date, one trip was experienced at Turkey Point Unit 3 in February. A summary of key plant operating statistics is summarized below, [ h PTN Unit 3 PTN Unit 4 April YT-D April Y-T-D l Gross Generation (WMh) 518,671 1,891,703 293,734 1,375,028
~; Net Generation (MWh) 494,977 1,799,903 273,640 1,304,633 Net Heat Rate (Btu /KWh) 10865.1 10880 2 11613.6 10995.6 , Equivalent Avail. ability 100.0 % 90.5 % 68.7 % 68.4 %
- Capacity Factor 1032 % 93.1 % 57.1 % 67.5 %
Auto Trips 0 1 0 0 Forced Outage Rate 0.0% 7.0% 5.0% 1.3% PSL Unit 1 PSL Unit 2 April YTD April Y T-D Gross Generation (WMh) 598,390 2,422,760 586,380 2,370,080 Net Generation (MWh) 566,609 2,293,262 554,215 2,240,287 Net Heat Rate (Btu /KWh) 10975.7 11014.1 10984.9 10872.4 Equivalent Availability 93.7 % 94.6 % 92.3 % 92.1 % Capacity Factor 93.8 % 94.1 % 91.8 % 92.0 % Auto Trips 0 0 0 0 Forced Outage Rate 0.0% 2.2% 2.3% 2.2% iii
MANAGEMENT
SUMMARY
REGULATORY PERFORMANCE j Turkey Point reported no NRC Violations in April. One NRC Violation reported in March was reclassified to l an Unresolved issue (URI). No violations have been received year to-date. i St. Lucie reported four NRC Violations in April as follows:
#96-04 A containment gaseous monitor was rendered inoperable due to a failure to follow procedures, ,
combined with a lack of taking proper logs. Exit Meeting Date: 4/3/96.
#96 04 Failures to make required log entries for reactivity manipulations and.a main generator '
hydrogen addition. Exit Meeting Date: 4/3/96.
#96-04-03 -An EDG was rendered inoperable due to failure to follow procedures while placing the fuel oil tank on recirculation. Exit Meeting Date: 4/3/96. #96-04 Reviews of %torical data for CEA maintenance revealed that post-modification testing acceptance criteria for Uc;it 1 CEA power cables were not applied to post-modification test data. Exit Meeting Date: 4/3/96.
Year to-date, St. Lucie has reported eight (8) NRC Violations. i COST PERFORMANCE O&M expeditures through April 1996 were $96.7 million which represented a budget underrun of $8.2 million (or 7.8%). This variance was primarily due to: a St. Lucie Unit 1 outage schedule change and the deferral of St. Lucie Spare Low Pressure Turbine Rotor refurbishment. Year to-date, O&M budget performance variances are stratified as follows: Turkey Point Site Specific $0.6 million (or 1.2%) above budget St. Lucie Site Specific $8.1 million (or 18.6%) below budget . Other Nuclear Division $0.7 million (or 5.5%) below budget Capital expenditures for April Y-T-D were $6.3 million. This represented a budget underrun of $9.3 million (or 59.7%). The favorable variance was primarily due to: an underrun in the Steam Generator Replacement Project (SGRP) reflecting a revision to the SGRP outage start date; the St. Lucie Unit #2 Reactor Head Seal Ring Replacement project determined to be O&M; and, during year cash flow revisions for various St. Lucie Plant projects. Year-to-date, Capital budget performance variances are detailed as follows: Turkey Point Site Specific $1.1 million (or 92.2%) below budget St. Lucie Site Specific $7.4 million (or 55.5%) below budget Other Nuclear Division $0.8 million (or 76.5%) below budget i
l NUCLEAR DIVISION BUSINESS PLAN INDICATOR OVERVIEW (DATA THROUGH APRIL 30,1996) 1996 1996 1996 Indicator Plant YE YT-D YTD Comments Target Target Actuals Collective Radiation Exposure PTN s 275.0 s 235.0 1782 Turkey Point and St. Lucie were PSL s 485.0 $ 86.0 21.2 below Y-T D Man-Rem targets. (Man-Rem) 4 The SALP for St. Lucie ending PTN 1.00 , 1.00 1/6/96 was 1.50; for PTN, the period NRC SALP Ratings PSL 1.50 1.50 ends Aug.31,1996. PTN had no NRC Violations in April; PTN s7 @Jjyj 0 PSL reported 4 NRC violations in NRC Violations PSL s7 fj,?itg 8 April and 8, year to-date. PTN3 ? 1 PTN4 3p 0 No unplanned automatic trips were Unplanned Automatic Trips s3 - 0 reportedin April. PSL1 PS12 t .. J 0 For the year, O&M and Capital Capital 39.2 15.7 6.3 actuals were below Year End Budget Performance O&M 253.0 104.8 96.7 ta.rgets; underruns were mainly due ($ Millions) Div. Total 292.2 120.5 103.0 to schedule revisions and project underruns. PTN3 95.0 95.0 90.5 PTN4 and PSL1 exceeded Y T D PTN4 82.0 58.7 68.4 EAF targets in April. Division EAF Equivalent Availability Factor (%) PSL1 78.5 94.0 94.6 Y T D was 86.4%, which is higher PSL2 95.0 95.0 92.1 than the 85.7% Y-T D target. PSL exceeded the Y E target by M&S inventory Levels PTN s 38 35.1
$4.9M in April primarily due to the PSL s 38 42.9
($ Millions) 4 scheduled Unit 1 outage of 4/29/96. 1.75 2.34 2.29 Production Costs (c/KWh) were
$ Production Cost PTN 1.55 1.59 1.45 below the Y T D target in April.
(0&M and Fuel) PSL Y In April, Division Total Cost (c/KWh) Total Cost (0&M, Fuel, and { Capital Carrying Costs) Div. Total 4.56 4.87 4.75 was below the Y T D target. 3 Total Nuclear Division Staffing Nuclear Division FPL 2045.0 ['$ 1948.0 LT Contr 463.0 i j 438.0 Levels yearto-date was below the Staffing Levels Total 2508.0 _, y 2386.0 Y-E target. PSL1 began a scheduled refueling PTN3 NA $g d 0 Refueling Outage PTN4 45 3; f 35 outage on 4/29. Future refueling utage schedules are: Duration (Days) PSL1 63 3# t 2 PTN3 03/08/97 PSL102/03/98 PSL2 NA 5 j,y $g PTN4 09/15/97 PSL2 04/15/97 Lost Time. Injuries per 200,000
'd I " PTN 0.30 0.30 h 0.11 0.31 No Lost Time injuries or Restricted Duty Caseswere reported in April.
PSL ng) I v
s NRC INDICATOR PERFORMANCE OVERVIEW { for Turkey Point (Data through Quarter Ending September 30,1995) i J mm Plant Self Trend Deviations Frorn Peer l
, [2 Short Term Grouc Mediar' LOna Term l OPERATIONS
" 'P i
0.72 0.0 Automatic Scrams While Critical 0.0 -0.22 @ i Safety System Actuatons 00 0.0 0.45 l Significant Events 0.0 0.0
-0.30 0.27 l l Safety System Failures 0.30 0.0 I Cause Codes (ALL LER's) N Adminstrative Control Problem O.0
- 11 Licensed Operator Pm l 0.0 0.18E
{ l 0.0 0.0 Other Personnel Error i 0.'0 00 l
. . Maintenance Problem oo Designtonstructioninstanaton 3 0.25 0.
Fabncation Problem I 0.0 . 09l M OA0 0 Mscellaneous loj 0 i SHUTDOWN J 0.18 0.04l SafetySystem Actuations 0.0 0.78 k\\\\\\\\\1 j 0.0 l 0.0 i Significant Events 5.40
- 0.57 E585888888
- 0.51 -0.53 Safety System Failures Cause Codes (ALL LER's) 0.0 2.40 0.37 g 0.29
' i Administratrve Control Problem 030 025 Licensed Operator Problem
; 030 - 0.06!
Other Personnel Error
.0 @ 0.10 Maritenance Problem E 0.05 0.12E h h h h w 120 E 0.10 Design / Construction /Instanation 0.01 0.03J Fabncaton Probiem hhhM 0$0 0.08 E Macema lj o c
FORCED OUTAGES MM 0.06 l 0.04 Forced Outage Rate - 0.03 0.05 0.64 0.07 Equipment Forced Outages. , /1000 Commercial Hours 0.26 -0.37@ 4 I i i i l I i i i l , I I I 1.0 0.5 0.0 0.5 1.0 1.0 0.5 0.0 0.5 1.0
- Not Calculated for Oceratonal Cycle Performance Index Performance index j
NOTES Plant Self-Trend Short Temi: Based on the slope of a linear regression line plotted over each plant's data. Time intervals used in the trends are 4 Quarters for "Operabons' and Forced Outages' indicators and 6 quarters for Shutdown' indicators. Deviations from Peer Grouc Med!an Lena Temt Compansons are rnade of each plant to the performance of its peers over a 12 Quarter time interval. PeerGroucs: PTN 3&4 OlderWestinghouse 3-Loop. Vi
NRC INDICATOR PERFORMANCE OVERVIEW for St. Lucie (Data through Quarter Ending September 30,1995) LEGENo Plant Self Trend Deviations Frorn Peer
- $I' Short Terrn Declined improved Grouo Median Lono Term Worse Better OPERATIONS Automatic Scrams While Critical
\\\ 0.54 0.18 0.90 0.36 Safety Syttem Actuations 0
Significant Events 9 0.0 0.22 ) Safety System Failures 0.0 0.67 1 Cause Codes (ALL LER's)
- 0.08 0.30 Licersed Operator Problem 0M 0.64 Other Personnel Error 0.48 Maartenance Problem 0.28 028 Leigr4cnstructiordnsta!'.ation M025 0.40 Fabrcation Problem Joo o 40 usmitaneous-0.0 0.18 M 0.0 0.45 Safety System Actuations ,
Significant Events o 0.22 - 0.01 l Safety System Failures 0.0 1.34 Cause Codes (ALL LER's) 0.11 0.06 Admrustratre Cortrol Problem 0.0 Licensed Operator Prcelem
~ '*
Other Personnel Error 0 o.oe 020 Martenance Problem Desgn/Constructicrdnstanation $020 00 Fabncation Problem 10.0 0.27 M5WPP2 FORCED OUTAGES Forced Outage Rate OO h\\\\\10.49
- 0.82 Equipment Forced Outages
- l 2.45 0.13
/1000 Commercial Hours l 0.0 I I I I i i i l 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 CaleWad for Oceratonaf Cvele Performance inder Performance Index TEES:
Plant Se'f-Trend Short Tem: . Based on the slope of a linear regression line plotted over each plant's data. Time intervals used in the trends are 4 Quarters for "Operatons' and Forced Outages' indicators and 6 quarters for Shutdown' indicators. Deviatrons from Peer Grouc Median Lena Term: Compansons are made of each plant to the performance of its peers over a 12 Quarter time interval. Peer Groue: PSL 1&2 - Combdion Engineenng w:th core protection calcutator plants. Vii
WANO OVERALLINDICATOR PERFORMANCE OVERVIEW
- (April 30,1996) i Unit or Station Values Industry MedianValues *l PerformanceIndicators s. year oistributioni I PTN 3 PTN 4 PSL1 PSL 2 (399339,5) ; 2000 Goals j j Unit Capability Factor (Unit %, 3-Yr.
88.7 % 85.7 % 80.5 % 80.4 % 81.2 % 87.0% Distribution Ending April,96) l , Unplanned Capability Loss Factor (Unit I l ' 3.1% 4.4% 11 1.0 %, 6.8% 5.2% 3.0%
%,3-Year Distr. Ending April'96) l 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 April'96) i g High Pressure Safety injection '
riot a, System (Per Unit,3-Year Distribution 0.008 0.009' O.026= 0.009 0.003 - 0.008 available l s v l Ending March '96)
$ Auxiliary Feedwater System (Per j j Unit, 3-Year Distribution Ending 0.015 .0.012 0.010 _0.013 0.004 - 0.009 s gL v>
March '96) ava able l b Emergency AC Power System (Per
~
not j Unit, 3-Year Distribution Ending 0.006 0.003 0.019 0.013 0.007- 0.012 available March 96) Thermal Performance (Ratio of Design _ to Actual Gross Heat Rate,1-Yr. 100.0 % 99.9 % .98.9%$ 198.3 % 99.5% " 99.5% Distribution Ending April'96) Collective Radiation Exposure (Man- .
. Rem per unit per year,3-year running 166 ~ 166l' 187- 153 120 avg.ending April'96) ] 87 1 Volume of Low-level Solid Radioactive . _
Waste (Cubic meters per unit per year, 33.2 33.2 {55.91 55.9 47.0 45.0 3-year avg. ending April'96) ~ j Chemistry Index (12-mo. weighted 1.11 1.08 1.16 1.17 1.18 " 1.10 average through April 96) ) Industrial Safety Lost time Accident Rate (Station rate per 200,000 man-hours 0.11 0.31 0.55 " 0.40 worked ending April'96) Fuel Reliability (Unit microcuries/g' 1.00E-6 1.00E-6 1.89E 5 1.04E-4 Refe e e month ending April 96) 5.0E-04"' l NOTE: shaded area denotes FPL performance is unfavorable to actualindustry rnedian. 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 (4/95-6/95 Distribution).
y;; Rev. 4/15/96 ! i
\
l l WANO OVERALL INDICATOR PERFORMANCE OVERVIEW Discussion of FPL Performance Unfavorable to industry Median (April 30,1996) UNIT CAPABILITY FACTOR (3-Years Ending 4/30/96) 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 (7.4%); Hot Leg Valve MV-3480 leak repairs from 3/29/94 to 4/2/94 (0.4%); Main Transformer trip from 6/6/94 to 6/11/94 (0.4%); Quench Tank leak repairs from 2/27/95 to 3/8/95 (0.9%); 1 A2 Reactor Coolant Pump seal repairs from 8/2/95 to 8/9/95 (0.7%); inoperable Power Operated Relief Valves from 8/9/95 to 8/17/95 (0.7%); and, inadvertent Containment Spray actuation and clean-up from 8/17/95 to 9/3/95 (1.3%) 182 Diesel Generator failure from 9/1/95 to 9/6/95 (0.5%); 1A Diesel Generator Radiator leakage from 9/6/95 to 9/10/95 (0.4%); Code Safety Valve repairs and modifications from 9/11/95 to 10/13/95 (2.4%); and, a refueling outage commencing 4/29/96 (0.2%). Other miscellaneous unplanned outages and derates accounted for the remaining 4.2% Unit Capability Factor loss. 1 St. Lucie Unit 2. Capability Factor for the three years ending 4/30/96 was 80.4%. Capability loss is attributed to the following: dropped CEA's on 5/21/93 (0.5%); 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 Capability Factor loss. UNPLANNED CAPABILITY LOSS FACTOR (3-Years Ending 4/30/96) St. Lucie Unit 1. The Unplanned Capability Loss Factor for the three years ending 4/30/96 was 11.0% compared to an industry median of 5.2%. Unplanned outages and power reductions contributing to this performa_nce included: Refueling Outage extension from 6/1/93 to 6/17/93 (1.6%); Waterbox cleaning due to jelly fish intrusion 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%); 1 A2 Reactor Coolant Pump seal repairs from 8/2/95 to 8/9/95 (0.7%); inoperable Power Operated Relief Valves from 8/9/95 to 8/17/95 (0.7%); inadvertent Containment Spray actuation and clean-up from 8/17/95 to 9/1/95 (1.3%) 182 Diesel Generator failure from 9/1/95 to 9/6/95 (0.5%); 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 1.0% Capability Loss. St. Lucie Unit 2. The Unplanned Capability Loss Factor for the three years ending 4/30/96 was 6.8%. Major unplanned occurrences contributing to this performance included: dropped CEA's on 5/21/93 (0.5%); shutdown for auto reactor trip investigation on 4/23/94 (0.3%); and, refueling outage extension from 12/1/95 to 1/5/96 (3.2%). Other unplanned outages and power reductions accounted for the remaining 2.8% in Capability Loss. UNPLANNED AUTOMATIC SCRAMS PER 7000 HOURS CRITICAL (3 Years Ending 4/30/96) St. Lucie Unit 1. Increased rate for Unit 1 was the result of five auto trips occurring on 3/18/94,4/3/94,6/6/94, 10/26/94 and 7/8/95. IX
i l ! 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 28 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. l AUXILIARY FEEDWATER SYSTEM (3 Years Ending 3/31/96) Turkey Point. Average performance for both units was affected by the B AFW Turbine failure in the 4th Quarter of 1994 due to malfunction of the mechanical overspeed trip device; in the 3rd Quarter of 1995, performance was affected I 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 failure in the 4th Quarter of 1994 of the 1C AFW Pump Govemor. In the 3rd Quarter. of 1995, performance was attributed to: failure of the AFW PP 2C Steam Admission Valve MV-0813 to open, a mechanical trip linkage for AFW PP 20 when the Electrical Overspeed Solenoid was energized, and a discrepancy between field wiring and plant wiring drawing for the AFW PP 28. EMERGENCY DIESEL GENERATOR SYSTEM (3-Years Ending 3/31/96) St. Lucie Unit 1. Unit I's average performance for three-years was tt.e result of a high water jacket temperature trip of 1 A EDG and failure of the govemor on 1B2 during monthly surveillance run which closed off fuel to the 12 cylinder engine in the 2nd Quarter of 1995,18 diesel 12 cylinder engine valve failure in the 3rd Quarter of 1995. and 1B diesel - due to replacement of the cooling water valves in the 4th Quarter 1995. 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. COLLECTIVE RADIATION EXPOSURE MAN-REM (3-Years Ending 4/30/96) Turkey Point. The three-year running average Collective Radiation Exposure level for Turkey Point was 166 Man-Rem per unit which was greater tnan the industry medea of 153 Man-Rem. Site performance was influenced by , scheduled refueling outages. J
' St. Lucie. ' Collective Radiation Exposure three-year running average level for St. Lucie was 187 Man-Rem per unit 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 4/30/96) St. Lucie. Volume of Solid Radioactive Waste for the 3 year annual average was higher than industry median due to 1994 waste volume; the 1995 value of 41.9 cubic meters was below the median value. X
. . _ . .- _ . - . . . . . . .. . . - . . - . - - . .. . . - -- - - ~ . , . . . - . - - . , - . . 1 i WANO WEIGHTED OVERALL PERFORMANCE 100.0 90.0
.?
,.'f ' '
W . . : . .;?
- pgL,
* ** . . o . . PSL 2
..' E 80 0 0 -
.- g...v
,.~ ,
l s L .
* \
k 70.0
- o' l 'g ,
Note: Adjustments were v made to reconcile data with
- 'O' WANO's records.
g [ 60.0 / 50.0 4 40.0
- f Unit /.L ;1901 1982' 1983 '1904 1985 ' 1/96 . 2 'al56 W36 Sf56 St96 :7196 .S/36 9f96 10/96 11/96 12/96 PTN 3 ' 57.5 66.7 88.8 85.0 90.9 94.6 94.5 93.0 95.0 r PTN 4 - 46.8 64 0 87.0 86.8 93.8 94 0 94.0 92.4 92.7
; PSt;1
- 52.6 75.0 82.7 76.3 63.3 70.5 70.9 73.7 73.8 PSL2 ; 71.6 80.9 70.9 67.5 74.0 69.6 74.1 78.3 79.7 Induciry Avg' n/a n/a 762 80.1 82.0 DEFINmON s
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 Capability Factor (16%) 5. Emergency AC Power (9%) 9.ThermalPerformance (6%)
- 2. Unplanned Capability Loss Factor (12%) 6. Unplanned Auto-Scrams (8%) 10.ChemistryIndicator(6%)
- 3. High Pressure Safety injecton (9%) 7. Collective Radiation Exposure (8%) 11. Low-level Radwaste Volume (5%)
- 4. Auxiliary Feedwater System (9%) 8. PWR Fuel Reliability (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 April exceeds WANO's industry median of 82.0%. Data Provider: Sharon Bilger 694-4255 A-1
i UNIT CAPABILITY FACTOR (3-Year Running Average) j 100.0 i 95.0 ~
. . + . . PTN 4 90.0 ---O--- PSL 1 0 - O
- PSL 2
- h. . . { ,
- 0 4 l 85.0 i Industry Avg o -W, o
,o_, N...n C ,O*
[ DMston Y-E' 87.5% a D-O g 70.o 65.0 60.0
+ *f 55.0 i/
50.0 [ ' 45.0 40.0
)e J Unit ~ /1est' :1982 1e03 1994 1995 11/96 2f96 '346 '4#56 '546 6/96 7/96 ~ -8/96 9/96 10/96 ~11/96 12/96
- PTN 3 - 47.9 52.7 64.6 85.0 88.9 88.9 88.6 88 7 88.7
- PTN 4 < - 42.2 61.8 63.7 86.7 87.2 87.3 87.3 84.6 85.7 PSL1F 77.5 78.4 82.7 84.6 77.9 78.0 77.8 77.9 8o.5 PSL2' 81.4 81.3 81.3 74.1 74.0 75.1 77.7 80.5 80 4 kWhsstry Ave. 72.3 74 6 76.5 78 6 8o.6 DEFINITION-Unit Capability Factor is the rato of the available energy generation over a given time period to the referena energy generation over the same bme period, expressed as a perceit s rath e both energy generaton terms determined relative to reference ambient conditions. Available energy generation is the energy tnat . , . ildve been M&ced under reference ambient conditions mnsidering only limitations within control of plant management, Le., 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 ambient conditions throughout the period. Reference ambient conditions are environmental conditions representative of the annual mean (or typical) ambient conditions for the unit.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE fg H-Q 3-vr Runnina Y-E Taraet WANQ 1993 1995 Median 81.2 % PTN 3 100.0 % 90.5 % 88.7% 2 95.0% 1995 Median 82.6 % PTN 4 68TA 684% 85.7 % 2 82.0 % 1995 Average 79.4 % PSL1 9374 94.6 % 80.5% 2 78.0 % 1995 Goal 80.0 % PSL2 92.3 % 92.1 % 80.4 % 295.0% PERFORMANCE
SUMMARY
Turkey Point Units 3 and 4 Capability Factor (3-yr. running average) performance through April 1996 was higher than WANO's 3-yr. running industry median. Data Provider. Sharon Bilger 694-4255 A2
2 1 UNPLANNED CAPABILITY LOSS FACTOR l l (3-year Running Average) l 1 I i 16.0 O PTN 3 l i . . + . . PTN 4
--H:)-- PSL 1 C' O - -PSL 2 12.0 i industry Avg. .
=
4 ,
- 's l 6
& C 3 i 10.0 l '
i g, '
.' D, Note: This data is i
j c l '. currently being 4 g ' 4; ., analyzed in order . cf = ,N - to reconcile with ! WANO's records. 6.o , ..
Nl 4...+..4...+
.i O - 0 0 onnsion y.E: 3.2% l l 2.0 l l o.o 1 Unit . '1991 1992 1983 1994 1986 1/96 2P86 3/96 4/96 5/96 6/96 7/96 8/96 9/96 10/96 11/96 12/96 MN3 15.2 4.8 3.7 3.7 2.7 2.1 2.9 3.1 3.1
. PTN 4 - 11.5 6.5 3.6 5.o 44 4.4 4.3 43 4.4 PSL1 5.1 59 2.6 4.2 10.8 10.8 11.o 11.o 11.0 PSL2 3.1 5.5 11.9 12.5 13.0 11.9 94 6.6 6.8 Industry Avg. 8.2 7.6 6.4 5.5 4.9 DEFINITION '
Unplanned Capability Loss Factor is defined as the ratio of the unplanned energy losses during a given period of ttrne to the reference energy generation, expressed as a percentage. Unplanned energy loss is energy that was not produced dunng the period because of unplanned shutdowns, outage extensions, or unplanned load reductions due to causes under plant rnanagement control. Causes of energy losses are considered to be unplanned if they are not scheduled at least four weeks in advance. Refererve energy generation is the energy that could be produced if the unit were operated continuously at full power under reference ambient cc iditions throughout the period. Reference ambient conditions are environmental ec,nditions representative of the annual mean (or typical) ambie it conditions for the unit. STATISTICAL
SUMMARY
. IUOUSTRY PERFORMANCE 3-vrRunnina Avo WANO PTN 3 3.1% PTN 4 4.4% 1993 1995 Median 5.2% PSL1 11.0 % 1995 Median 5.0% PSL2 6.8% 1995 Goal 4.5'/. 1996 Target (all units): s 3.2% PERFORMANCE
SUMMARY
St. Lucie UniL,1 and 2's Unplanned Capability Loss Factor performance for 3-yr running through April 1996 was higher than the WANO's 3-year running industry median. Data Source: John Pizzctelli 6944245 A-3
- UNPLANNED AUTO TRIPS PER 7000 HOURS CRITICAL (3-year Running Average)
I 1.8
., o PTN 3
^'
1.6 , C O O O * * +
- PTN 4 ,__
'. + PSL1
] 3,4 k . O PSL 2 j g '. l . Industry Avg.
h 1.2
.\a's e h. e' i*
.g
" Dmson Y E:51perunit , ,
g t o.a N.......... E p...c, o. . . o 06 O O ^
'O O ,
a g o.4
.\ ':
- z. .. ,
o.2 \* r j o.o . * -
< t unita 1991 19ea 1900 1904 1906 1/96 246 af06 4706' '5/96 6/96 7/96 4/96 St96 10f96 11/96 12M l PTN 3 = 1.6 1.o o.o o.3 o.3 o.3 o.6 o6 o6 PTM 4 - 1.7 1.4 0.9 1.3 o.9 o.9 o.9 o.9 o.9
. PSL'1 1.3 1.o o.9 1.5 1.6 1.6 1.6 1.6 1.6
' PSL 2 0.6 o.6 o.3 o.7 o.7 o.7 o.7 o.6 o.6 i industry Avg. 1.5 1.2 1.1 o.9 o.9 l
DEFINITION 1 Unplanned Automatic Scrams per 7000 Hours Criticalis defined as the number of unplanned automatic scrams that occur per 7000 hours of entical
)'
operation. Unplanned means that tne scram was not an anticipated part of a planned test. Scram means the automatic shutdown of the reactor by a rapid inserton of negative reactivity (by control rods, liquid injection shutdown system, etc.) caused by actuation of the reactor protection system. l The scram signal may have resulted from exceeding a setpoint or may have been spurious. Automatic means that the initial signal that caused l actuation of the reactor protection system logic was provided from one of the sensors monitoring plant parameters and conditions rather than from the manual scram switches or, in certain cases described in INPO 94409, from manual turbine trip switches provided in the main control room. j Critcal rneans that dunng the steady-state condrtion pnor to the scram, the effective reactor multiplication factor was essentially equal to nne. i STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE Through April g 12 s . Lin Division Totals: 1993 1995 Median 0.9 19 % 0.5 0.9 1995 Median 0.9 1995 1.3 0.9 1995 Goal 1.0 Division Target: s 3.0 auto trips PERFORMANCE
SUMMARY
e No unplanned automatic trips were reported in April.
- Turkey Point Unit 3 experienced an automatic trip on February 9th. The 'B' Steam Generator Feed Pump was stopped to monitor its discharge check valve closing stroke which did not strike closed as expected. The resulting feed flow transient caused the 'C' Steam Generator level to increase resulting in a turbine tnp which tripped the reactor. Unit 3's 3-year running average of 0.6 was below the industry median. -
e St. Lucie Unit 1's 3-year running average of 1.6 exceeded WAN0'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 s .s
i HIGH PRESSURE SAFETY INJECTION SYSTEM PERFORMANCE I (3-yr Running Average)
- o.04o e PTN 3 i o.o35 $- PTN 4 _
---{>-- Psl 1 O a
- PSL 2 industry Avg. !
i l O h o.025 Q , Desion Y E: s o.o25 4 o.o2o ~ o.015 0 010 O'.,
; ; .- - - . . , . . 9
( ' [Q '_ ,,j ? o.co5 4--6
- UnN , ^1991 -1982 1983 -1e84 1906 ?i" 2P96 8/96 9/96 1 arts PTN 3 . - 0.007 0.003 0.007 0.006 0.008 0.008
+ PTN 4 0.001 0.001 0.006 0.000 0.000 o.009 4 PSL1
- 0.091 0.026 0.017 0.011 0.025 0.026
- PSL21 0.011 0.006 0.018 0.007 0.010 0.009 kiegatry Aug. 0.006 0.006 0.010 0.008 0.006
' DEFINITION i This Safety System Performance indicator monitors the readiness of the Safety injection (SI) System at Turkey Point and the High Pressure Safety injection (HPSI) System at St. Lucie to respond to off normal events or accidents. The indicator is determined from the unavailabil: ties, due to all causet,, of the components in the system during a time period, divided by the number of trains in the system. The definition is further explained:
-ucM unavailability is the ratio of the hours the component was unavailable (unavailable hours) to the hours the system was required to be available for sennce. Data is reported on a quarterly basis.
Unavailability = (Known Unavailable Hours) + (Estimated UnavaRable Hours) (Hours System Required) x (Number of Trains) STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE 1st Otr 1996 3-vr Ave Endino 3/96 PTN 3 0.006 0.008 Unavaitability WANO PTN 4 0.005 0.009 PSL1 0.015 0.026 1993 1995 Median (PWR) 0.003 0.008 PSL 2 0.000 0.009 1995 Goal 0.020 Targets: , EIN ESL 1995 Y E Target 5 0.016 s 0.023 1996 Y-E Target 5 0.025 s 0.025 PERFORMANCE
SUMMARY
e 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. I . St. Lucie' Units 1 and 2's High Pressure injection System average perfomiance 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.4
SAFETY SYSTEM PERFORMANCE - AUXlLIARY FEEDWATER SYSTEM l (3-year Running Average) 0.040 e PTN 3
+ - PTN 4 I
---O-- PSL 1
- O PsL2 g .: Industry Avg.
0.030 , Divisa Y-E: s0.025 I I ( 0.02o i
'O . .
- = o ,
' ~'
! & .' . . . . . .' .' .' .' .' : : S 0.010 ', O i 0.000
' Unit. In :1901 1982 1983 1994 '1995 % :3f56 -
8/96 . af96 5 12/06
.PTNS* 0.008 0.025 0.018 0.021 0.014 0.015
- PTN 4 ~. ~ 0.012 0.031 0.020 0.019 0.011 0 012 2 988.1 ' O.012 0.03c 0.028 0.029 0.010 0.010
.: PSt.2 -- 0.017 0 014 0.012 0.008 0.014 0.013 Industry Avg. 0.014 0 014 0.012 0.012 0.009 I
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 unavailabihties, due to all causes, of the cm.tients in the system during a time period, divided by the number of trains in the system. This definition is further explained: comoonent unavailability is the 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 S@sMARY' INDUSTRY PERFORMANCE 1st Otr 1996 3-vr Avg Endino 3/96 ' PTN 3 0.008 0.015 PTN 4 0.007 0.012 EMQ Unavailabihtv l 3 PSL1 0.005 0.010 PSL2 0.008 0.013 1993 1995 Median (PWR) 0.004 0.009 i 1995 Goal 0.025 Targets: EIN ESL 1995 Y E Target s 0.020 s 0.021 1996 Y E Target 5 0.025 s 0.025 l PERFORMANCE
SUMMARY
. 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 median.
. 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-7
i l SAFETY SYSTEM PERFORMANCE - EMERGENCY AC POWER SYSTEM (3-year Running Average) 0.o30 4 Dmsion Y E: s 0.025
^
PTN 3 o.o2o * * + "
- PTN 4 O
[, 3 o__.pst i j . -
- - O - PSL 2 j r@
o.o15 0, sW4
, ............O o ,
o.oto ,
. 0 '. .'
1
- O
'. /
l , d .... , g..- i o.oco i n Urtit - 1991 '1992 :1993 1994 .1995 .i- 2 M 6/96 S/98 _ 12/96 I ' PTN 3 0.001 0.004 0.002 0.003 0.003 0.006 } ' PTN 4 ' O015 0.001 0.002 0.003 0.003 0.003 4 PSL 1 - 0.013 0.019 0.012 0.010 ' O.019 0.019 PSL 2 0.019 0.008 0.011 0.007 0.012 0.013 Int.geFY AWO. 0.017 0.017 0.020 0.014 0.012 DEFINITION . Emergency AC Power System is defined as the sum of the emergency diesel generator unavailabilities divided by the number of emergency generators at a station. Data is collected at the train level. The emergency generator includes subsystems such as air start, lube oil, fuel oil, cooling water, etc. However, for this safety system performance indicator, unavailable hours are counted only when the emsrgency 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 1st O'r 1996 3-vr Ava Endina 3S6 PTN 3A&B 0.029 0.006 PTN 4AaB 0.000 0.003 ggg Unavailabihty PSL 1 A&B 0.006 0.019 PSL 2A&B 0.005 0.013 0.007 0.012 1993 1995 Median (PWR) 1995 Goal 0.025 Targets: EIN ES.L i 1995 Y E Target 5 0.015 5 0.016 1996 Y E Target 5 0.025 s 0.025 PERFORMANCE
SUMMARY
l
. Turkey Point Unas 3 & 4 Emergency AC Power performance for 3-years running ending 1st Quarter 1996 was below the year-end target andindustry median.
. St. Lucie Units 1 & 2 Ernergency 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 (PSU Chuck Wood 467-7034/ Roger Kulavich 467 7080 A-7
THERMAL PERFORMANCE (12-Month Running Average) , 101.0 0 PTN 3
+
- PTN 4 l f + PSL1
+ +- +. ..
s
,co., ; >
. . o . .Pst s !
> (0 0 I . Industry Avg. ,
, 0, . !
'., Oneon Y E: 99.5% 1 I g <
99.0 . , f, . C O O O
+' {
l m '. ! '. A O . . . o . . .O . *
- O 98.0 ,
4 ) 97.0 I (Jnk .1981 1982 1983 1984 '1995 !1/96 2f96 3/96 > 4/96 ' 5/96 8/96
~7/96 8/96 :9f96 1046 '11/96 12/96
' PTN 3 . 99.3 90.2 100.4 100.3 99.8 99.8 99.9 99.9 100.0 FIN 4 98.7 99.0 99.7 99.7 100.1 100.1 100.1 100.1 99.9
. PSL 1 99.0 99.3 99.2 99.0 99 0 98.9 98.9 98.9 98.9
; PSL2 - 99.6 99.3 97.8 98.5 98.1 98 2 98 2 98.2 98.3 M :., Avg. 99.2 99.3 99 4 99 4 99.5 i
DEFINITION Thermal Performance is the ratio of the bsign gross heat rate (corrected) to the adjusted actual gross he is defined as the ratio of total thermal energy produced by the reactor core to the total gross electncal 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 conditions for 100 percent power, expressed in British thermal units (BTUs) per kilowatt-hour (electric). Adjusted actual gross heat rate is the gross heat rate attained in the normal equipment 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 Ap.t 12-Mo. Avernoe WANO PTN 3 100.3 % 100.0 % PTN 4 98.6 % 99.9 % 1995 Median 99.5% PSL1 98.9 % 98.9% 1995 Goal 99.5 % PSL2 99.3 % 98.3 % 1996 Target (all unrts): 99.5% PERFORMANCE
SUMMARY
For the 12-mo. running average, Turkey Point Units 3 and 4 performance was higher than WANO's 12-mo. running industry average. St. Lucie Units la 2 Thermal Performance for 12-mo. running was below WANO's 12-mo. running average. Data Providers: (PTN) Jennifer Murphy 246-6827 and(PSL) Marty Smit 467 7079 A.9
FUEL RELIABILITY (Fuel Cycle / Monthly) 1.coE@ i 0 PTN 3 1 * + = PTN 4 1.coE o1 p _ 4 <>
- PSL 2 1.ooE-o2 i 'N %
, y. . u . s
- h 1.coE43 \,
i " + s., ). 1.coE44 ,0 Fue! Defect Reference E.0E 04 I I j w 1) )i 1.ooE o5 ,- , D' ! / , i 1.00E-o6 1
- l 1.coE-o7 l an u Unki=r Prov6osas # : Cycles 6 o
. ~1/96 a246 L3S$ 4/96 al56 s6/96 '7ta6 -8/96 -:SdB6 10/96 11/06 12/06 j . : PTN 3 - 44ss4 i 44s4 a rosa i.7ssa s ies4 isos4 s.cos4 1.cos4 1 oos4
" PTN 4 - 324s4 i cas4 74asa 14oe4 s.ssa4 isis 4 i cos4 1 PSLin e s4E4 s41s4 s i7ta 1.coE4 4ms4 i ses4 s ats4 i nes4 f~
i ' PsL2 o saise 37t:4 s us4 e sos 4 s ass 4 i.cos4 i cos4 i nes4 s o4:4 Industry Aug.' s cos4 i DEFINITION This indicator is defined as the steady-state primary coolant iodine-131 activity (microcunes/ gram) corrected for the tramp contribution and power i 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 rnonthly values for the most recent quarter of steady state operation above 85 percent power. Steady state is defined as conbnuous operation for at least three days at a power level that does not vary more than 2 5 percent. 4 l 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 microcunes per gram. 1 STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE l And[ Cvde No. WANQ PTN 3 1.00E 06 15 ! PTN 4 1.00E 06 16 1995 Fuel Defect Reference Threshold (PWR) 5.00 E 04 i PSL1 1.89E 05 13 1994 Median 7.36 E-05 PSL2 1.04E-04 9 1994 Best Quartile 3.00 E 06 Division Target for each unit s 4.50E 03
- PERFORMANCE
SUMMARY
.
- Unit 3's Fuel Reliability continues to indicate zero fuel defects in Cycle 15.
i
= Unit 4 began Cycle 16 operation on April 8th. Preliminary review of radioisotopic data indicates zero defects.
; e For Unit 1, Reactor Coolant System radioisotopic data and spiking iodine following shutdowns indicate the presence of one third-cycle failed fuel rod in the current Cycle 13.
. Unit 2 Fuel Reliability continues to indicate zero fuel defects in Cycle 9.
e Data Provider: Modesto Jimenez 694 3323 A-9
3 l. CHEMISTRY INDEX (12-Months Ending Weighted Average) l 1.40 i J 1.35
- O PTN 3
+ PTN4 l 1.30 --H>--- Psl 1 l
- -O PSL 2 g 4 industry Avg.
! l k 120 ^ 0--
. Omsson Y E: s 1.20 ,
i n . u h 1 1.15 1 6 , 1.10 1 1.05 o + + .. , ,.'
- 1.00 I
f l t - Unit - 1991 1992 1993 $1994 '1995 .1/96 219 6 .3f96 '4/36 -4/96 ; W96 IW96 7196 af96 10/96 '11/96 12/96 PTN 3 - 1.10 1.11 1.11 1.11 1.11
- PTN 4 1.04 1.04 1.04 1.03 1.08 PSL1 1.24 1.20 120 1.18 1.16
' PSL 2 1.17 1.19 1.19 1.19 1.17 j industry AE 1.18 a
DEFINITION I The Chemistry Index compares the concentration of selected impurities to the limiting values for those impurities. Each impurity value is divided by the limiting value for the impurity, and the sum of these ratios is normalized to 1.0. The limiting values are the ' achievable values
- defined by intemationalindustry-accepted values.
, STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE i Ag! 12-Mo. Endino Weichted Ava WANO PTN 3 1.00 1.11 (PWR's with Recirculating Steam Generators without Molar PTN 4 1.43 1.08 Rato Contr00 PSL 1 1.10 1.16 1995 Median 1.18 PSL ? 1.25 1.17 1995 Lowest Chemistry index Value Attainable 1.00 1996 Target for each unit: s 1.20
~
PERFORMANCE
SUMMARY
Chemistry index perfoimance for all units for 12-rno, ending weighted average was below the year-end target and industry median. Data ProMers: (PTN) R. Steinke 246-6118/ Randy Woodard 246-6810 (PSL) R. Frechette 465-3213/ Dave Faulkner 465-3393 A-10
1 4 RADIATION EXPOSURE l
, (3-year Running Average) j 400
)
- +- PTN
~
l
< 35o
^ --O- PSL L_
. Industry Avg. l 30o Note: 1996 numbers are adjusted 250 k each month to reflect TLD data j ,,, _ / % :.* : W l X" ~h
~
# ;';n,*:e u 15o g_ -- -
4 too so j o-Plant 1991 1992 1993 1994 1995 '1/96 2/96' :3/96 4/96 - 5f96 6/96 7/96 8/96 s t/96 1of96 11/96 12/96
' PTN ' 3So 332 257 181 162 161 161 185 166 P8L " 274 238 193 2o2 23o 229 227 219 187 Industry Aug, . 189 193 193 144 153 DEFINITION Collective Radiation Exposure is the total extemal whole-body dose received by all personnel (rncluding 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 should be included only for those periods or situations when more accurate data l is not available to the utility from TLD's or film badges. In order to correlate this indicator with the new 10 CFR 20 reporting guidelines, U.S. utiltties report deep dose equivalent (DDE) and the total effective dose equivalent (TEDE). . 1 I STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE ) 3-vr Runnino eer Unit Man Rem 165.8* Witi2 (oer Und PTN i PSL 187.1 163 (PWR's ) Median 3-yr Distribution (1993 - 1995) i 1995 Median 153 Division Targets: 3-vr. Ava ' 185 1995 Goal PTN: Y-E thru 1996 s 170.8 PSL: Y E thru 1996 s 229.2
' April data is DRD; TLD was not available at tirne of pubreation.
PERFORMANCE
SUMMARY
. Turkey Point ^ollective Radiation Exposure for 3-years running through April 1996 was 165.8; performance was slightly higher than WArw s 3-yr. running median of 163.
. St. Lucie's Collective Radiation Exposure for 3-years running through April 1996 of 187.1 was higher than WANO's 3-yr.
running median. Data Providers:(PTN) John Lindsay 246-6548 and (PSL) H. M. Mercer 467 7302 A 11
.- . _. - -- . _- - _ _ . - . ~ - -- - . -. . ._. - _ _ _ - _ _ - _ .
iM LOW-LEVEL SOLID RADIOACTIVE WASTE (Cubic Meters per unit per year,3-year Running Average) 140
-+- PTN 120 g -O-- PSL
~
l Industry Avg. ,' 100 80
\
m
! A 4 i \
j , PsLY E: 67.5 1 1 g 60 C PTN Y E: 55.6 1 40 i 4 ! 20 $ l 1 1 o Plant 1991 19P2 '1953 :1994 1996 1/96 246 ~ 3f96 4/96 546 6/06 "7/96 9/96 :9/96 10/96 11/96 12/96 JPTN: s - 125.3 102.3 81.2 63 4 37.4 36.7 36.2 33.1 33 2 PSL 121.1 103.8 80.7 75 4 53.7 53.3 53.0 54 6 55.9 industy Ass. : 85.0 87.0 45.0 46.0 47.0 t . DEFINITION f' 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 calcu!ated using the amount of waste in final form, including
; the container, actually shipped for disposal from both on-site and off-site facilities, plus the change in inventory of final-form waste in ! storage at both on-site and off-s'te : facilities.
1
- in transit to or at disposal site for disposal STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE I j 3-vr Runnine thru Acril(eer unit) WA.HQ MontNy Cu. Ft. (2 Unit Site) FTN 33 2 , 3-yr Distribution Median (1993 1995) 47.0 1995 Median 30.0 Mion Target 1995 Goal 110.0 j PTN 1996 Y-E 55.6 cu. mtr. per unit PSL 1996 Y-E 67.5 cu. mtr. per unit i ) PERFORMANCE
SUMMARY
e Turkey Point's Solid Waste Disposal performance for 3-yrs, running was below the year-end target and WANO' 's 3 yr. industry median. j = St. Lucie's performance was below the year-end target and higher than WANO's 3-yr. industry median.
,1 i Data Providers: (PTN) Bob Schuber 246-7227 and (PSL) Bruce Somers 467-7305 A-12
f a INDUSTRIAL SAFETY ACCIDENT RATE (12 Month Running Average) 1.00 l --$-- PTN
\, --O-- PSL 0.80
^- #@ #9' _
L a 7 g 0.70
\. \
m 0.60
\
s , ,, / KN 0 40 a 0.30
,/
V
\ 0 PTN/PSL Y-E: s 0.30 ,
020 0.10 1 0.00 Plant '1991 1992 1993 1994 1996 1/96 2/96 W 4/96 5/96 6/96 7/96 '8/96 Of96 10tW6 11/96 12/96 PTN' O.25 0.67 0.36 0.50 022 0.22 0.22 0.11 0.11 1 PSL- 0.75 0.61 0.50 0.51 0.40 0.30 0.30 0.32 0.31 I bulustyAvg. 1 0.97 0.77 0.77 0.64 0.55 DERNm0N Industrial Safety Accident Rate is defined as the number of accidents per 200,000 man 4.ours worked for all utility personnel permanently assigned to the station that result in any of the fcllowing:(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 station man-hours worked) STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE-12-Mo -Endino (A0r) PTN 0.11 0.31 1995 Median 0.55 al 0.50 Division Targets: PTN 1996 Year-End 0.30 PSL 19% Year End 0.30 PERFORMANCE
SUMMARY
= Turkey Point's Industrial Safety Accident Rate for 12-mo. running through April 1996 was below the year +nd target and industry median.
- St. Lucie's Industrial Safety Accident Rate of 0.31 for 12-mo. running through April 1996 was slightly higher than the year-end target and below the industry median.
Data Provider W.Korte 6944 235 A 13
_ - _ _ _ _ _ _ _ _ _ _ . . . . - . . - . . -- , _ _ . - _ ~ . - . - - _ . - - _ - , .- . . . . - . 1 EQUIVALENT AVAILABibTY FACTOR (Year-to-Date) I l \ A ,
,M Division Target 87.6% ll
,, ; c PTN 3 70.o 4,, - + - P (N 4
! l
-O- PSL 1 Go .o
*
- O -PSL 2
, t h 50.o
'll
[ do.o ! l 3o.0 4 1 i 1 2o.o , e b , 1o.o 0.0
**Unt-e 4 901 19B2 1803 1994 c1996 '1/96
. ;2f8E ' 3 06 .4/96 : StBE 18/96. ~7/96 . 8/96 79/96 10/96 11/96 12/06
. PTN 3 " 22.3 66.3 94.6 83.5 88.7 99.9 03.3 87.4 90.5 i < P7N 4 L. 13.9 85.5 81.1 83.1 97.4 100.0 100.0 68.3 68.4 l
' PSL 1 ' 78.5 95.4 74.0 84.5 75.3 99.6 94.5 94.9 94.6
'PSL2 98.5 73 2 71.8 77.4 72.9 76.8 87.9 92.0 92.1
]
2
- , 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 of plant programs and practices in maximizing electncal generation.
EAF% = Available Hours - Eauivalent Unit Derated Hours) x 100% Period Hours
- STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE g Y T-D Y T-D Taraet 3-vr Run. Ava NERC/ GADS PTN 3 100.0% 90.5 % 95.0 % 88.7 % ! 1994 (PWR's) 77.8% PTN 4 68.7% 68.4 % 58.7 % 85.7% 1994(Alltypes) 74.1 % PSL1 93.7 % 94.6 % 94.0 % 80.5 % PSL 2 19901994 (PWR's) 74.4 % 92.3% 92.1 % 95.0 % 80.4 % 1990 1994 (Alltypes) 71.2 % Division 88.7 % 86.4 % 85.7% 83.8 % WANO 1995 Median 80.7% 1996 Division Y-E Target 87.6% 1995 Average 77.4 % 1996 Year End Forecast 87.9 % PERFORMANCE
SUMMARY
. Major contributors to April 1996 Equivalent Availability loss for the Division was as follows:
PTN Unit 4: Refueling outage (178.6 hours); Turbine test (5.4 hours); manual trip due to clogged orifice in Main Turbine 4 Govemor Control System (26.7 hours); repair to the 3A/4A Feedwater Heater (13.6 hours); and, repair to 4B Main Feedwater 4 Pump Control Circuit (1.0 hour).
. PSL Unit 1: Downpowering for scheduled refueling outage (452 hours).
- e PSL Unit 2
- Repair to Condenser Waterbox (32.3 hours); Turbine testing (19.0 hours); and, Chemistry hold (4.1 hours).
l For the Division, Y T-D Equivalent Availability was 86.4% which is higher than the 85.7% targeted through the period. Data Provider: Sharon Bilger 694-4255 R.1
... . _ _ _ _ _ _ .._.m.. _ . . . ._ . . _ . _ _ _ . _ _ _ _ . . ?
l l 1 CAPACITY FACTOR (MDC NET) l (Year to Date) 110.0 100.0 m ,
%-+ c PTN 3!
- + - PTN 4' --- l l
,0.o
- b *
$$ 1 80.0 70.0 ,,
- A :/,e q 60.0 .
s l l 50.0 i 40.0 t 30.0
/
I 20.0 , b i 10.0 l 0.0 i 4 fiUnR ; c1991 1992 -1983 1994 '1995 i1/58' M' W 4fBS 18/96 56fB6 7/96 af96 : St96 10fDE :11/96 12/96 i . PTN 3 22.5 58 4 97.0 84.8 89.5 103.9 85.7 90.0 93.1
- > FTN 4 13.7 79.3 81.4 83.0 99.5 104.5 1042 71.0 67.5 1 PSL1 78.8 96 9 73.9 84.1 75.0 98.8 93.3 942 94.1 I
PSL2 101.1 73 7 64.1 76.3 71.9 74.1 87.0 92.0 92.0 l ]
~ DEFINmON Capacity Factor (CF) is the index of the actual electncal energy produced by the unit with respect to its potential.
CapacityFactor = Net ElectncalGeneration X 100 Maximum Dependable Capacity (839 or 666) X Period Hours STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE , 1 NERC/ GADS 1
& Y-T-D 12-mo end.ina 39 pg.s 76.7 % l PTN 3 103.2 % 93.1 % 86.9 %
1994 Avg AllTypes 72.8 % PTN 4 57.1 % 67.5 % 89.6 % 1990-1994 PWR's 72.8 % PSL1 93.8 % 94.1 % 75.5 % 19901994 AllTypes 69.5 % 70.5 % PSL2 91.8 % 92.0 % g ' Division 86.5% 86.6 % 80.6 % 1995 Median 81.1 % 1995 Average 77.9 % PERFORMANCE
SUMMARY
. Turkey Point Units 3 & 4's Capacity Factor Rate for 12-mo. ending through April 1996 was higher than the industry average.
- St. Lucie Units 1 and 2's Capacity Factor Rate for 12-mo. ending through the month was below industry average.'
Data Provider Sharon Bilger 694-4255 B-2
PTN FUEL UTILIZATION FACTOR Turkey Point Unit #3, Cycle 15 Turkey Point Unit #4, Cycle 15 500 55o
$$,~
4$o . Planned Refueling Date: March 8.1997 Wg 500 - Planned Refuehng Date: Septemoer 15.1997 . 450-400 - 4r-#! .q[ftx1 350- 3+ g, j u h 2 n g 200 - af M'"~ KIN 4b h
~ RE4j %
$200 5 # hph,. f g E i
150 - .
$5h "~ jhbkh W 8, E;It3
,oo .
y2 3'
^})ffA+sIQ pp '**'
M3Jd y$ Ab?AQGWh@.Y - , 50 - h[y Q% WM So - Mmm%%B%Mk
,m M@dSm&&n .
1 Fru es . = = o . m = = n., a m w a., o. m- c .a. e inr = m., .ai. .u = l Masumed ~ 5 35 66 98 127 158 188 219 249 281 312 342 373 403 435 466 494 501 I i Actust: 18 47 78 109 128 157 187 VertonesW-) < 13 12 12 11 1 1 -1
'FFN 64
- Manned 6 37 67 98 129 159 190 220 251 282 310 341 371 402 432 463 494 509 l
- /Asmael * *v 18 I vartunne W-) - 12 DEFIN. TION Fuel utilization plots the amount of nuclear energy used during the current fuel cycle. The amount of nuclear energy loaded into the l 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 hour 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 PTN 3: In accordance with the AprH 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 energy to run 501 (EFPD) days. N_QIE: Due to the 34-day outage, startup began on October 7,1995,20 days earlier than planned. PTN 4: In accordance with the February 8,1996 AOS, Unit 4 Cycle 16 was scheduled to startup on April 25,1996. Due to a 35-day refueling outage, the unit actually started up on April 8,1996,17 days earlier than planned. Note that the unit has a design energy of 507 EFPD. PERFORMANCE
SUMMARY
e Unit 3 achieved a Fuel Utilization Factor of 99.5% and operated for 717 effective full power hours in the month of April. For the period October 27,1995 to April 30,1996, the Fuel Utilization Factor was 100.7%.
. Unit 4 achieved a Fuel Utilization Factor of 294.0% (the unit started up 17 days earlier than planned due to a shorter refueling outage) and cperated for 423 effective full power hours in the month of April Data provider. Jimmie Perryman 694-3330 B-3
'I PSL FUEL UTILIZATION FACTOR St. Lucie Unit #1, Cycle 13 St. Lucie Unit #2, Cycle 9 l 500 450- Ong nal Planned Refueimg: April 8,1996 450 Planned Refuelmg Date: Apnl 15,1997 i 4oo . Revised Date: April 29.1996 j[ 2 p q{
.p#4 400-g 35 -
3 ps j,Mq' g 35, ' ype
& dli ; ~ M 5
& g'M@:fk
$ gog .
3 g 4 000
& 0 1 250 - g,p p
- f' g 4 e 250-
[# Ipf i a p" ( 20o . g g g ,,, .
- s, : {yq eqs s'5 ' h %wu ! j $ tz- iF o M _,.g 100 -
4N h , pf 100-Am yd
- An%gg;h46 %r%m tm ~ K EP88.816 Nov Dec Jan 'Feb Mer Apr May Jun - Jul Aug Sep Oct - Nov Dec .Jan Feb ' Mer Apr
' Planned - 11 41 68 98 127 158 187 217 247 276 306 335 366 396 423 453 461 Actual 29 60 86 109 139 170 199 227 227 227 244 271 302 331 357 387 415
' Vertence N-) - 18 19 18 11 12 12 12 10 20 -49 -62 -64 44 65 -66 66 46
-PSL92' Planned 5 36 67 95 126 155 186 215 247 276 306 336 366 397 427 455 485 500 4 Actual - 0 0 23 52 83 111
' Vertence W-)' -5 -36 44 43 -43 44 DEFINITION 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 ratog (2200 at PTN or 2700 at PSL) for a 24 hour 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 cor.sumption. Fuel utilization can be used to project longer or shorter operating fuel cycles. Actual Energy / Calendar Days = Fuel Utilizabon Factor Fuel Cycle Operating Assumptions ESL.1: In accordance with the October 28,1994 Approved Operating Schedule (AOS), Unit 1, Cycle 13 was scheduled to begin operation December 20,1994. This provided for a cycle of 475 calendar days with design energy to run 461 effective full power days (EFPD). Unit 1, Cycle 13 actually began operation November 29,1994 and commenced to refuel on April 29,19%. N.QTE: Per the revised AOS dated February 8,1996, the unit was shutdown 21 days later than previously scheduled. ESL2: 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 daya with design energy to run 500 EFPD. Unit 2, Cycle 9 actually began operation January 5, 1996 and is currently scheduled to refuel April 15,1997. PERFORMANCE
SUMMARY
e Unit 1 achieved a Fuel Utilization Factor of 93.8% and operated at 675 effective full power hours in the month of April. For the penod of December 20,1994 through April 29,1996, the Fuel Utilization Factor was 84.0%.
- Unit 2 achieved a Fuel Utilization Factor of 91.7% and operated at 661 effective full power hours in the month of April. For the period of November 24,1995 through April 30,1996, the Fuel Utilization Factor was 71.6%.
Data provider: Ruben Rodriguez 694 3345 B-4
- FORCED OUTAGE RATE
! (Year to-Date) , 30.0 i 0 PTN 3 ! -+ PTN 4
--O--- PSL 1 l
$ 25.0 i O PSL 2I 9
;; p
'. I 20.0 .
! l1 l f, l \ f 15.0 l $
- .. I .
10.0 [ ). k b
' o '. *
; 0, 5.0 l ,
.:.3 **- ,,
r..* d o.o O .
^
Unit - 1991 1982 1993 1984 1996 :146 '2/96 : .:2ft$ ' .4 36. 8/96 ^ 8/96 7/96 8/96 9f90 10f96 11s96 12/96
" PTN 3 + 12 15.6 1.8 1.9 0.5 0.0 11.8 9.3 7.0 PTN4* 1.8 13.2 2.0 3.9 1.5 0.0 0.0 0.0 1.3
' P58 1 - 1.2 35 2.1 3.9 21.8 0.0 44 2.9 2.2 P8t.T 4 0.0 8.1 23.5 2.3 2.4 7.0 3.4 2.2 2.2 DEFINITION 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 / electrical, hydraulic controls systems and operator-initiated trips in response to unit alarms.
Forced Outage Rate Forced Outaae Hours x 100% Forced Outage Hours + Service Hours STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE M Y-I-Q 12 Mo. Endina NERC/ GADS PTN 3 0.0% 7.0% 2.6% 1994 (PWR's) 8.1% PTN 4 5.0% 1.3% 0.3% 194 (Alltypes) 10.6% PSL1 0.0% 2.2% 22.0 % 1990-1994 (PWR's) 7.6% PSL 2 2.3% 2.2% 2.2% 1990 1994 (Alltypes) 10.8% PERFORMANCE
SUMMARY
Turkey Point Unit 4 Forced Outage Rate of 5.0% was the result of a manual reactor trip on April 9th as a result of a clogged orifce in the Govemor Control System for the Main Turbine.
. St. Lucie Unit 2 experienced a Forced Outage Rate of 2.3% as the result of Turbine testing problems.
Data Provider: Sharon Bilger 694-4255 B-5
UNPLANNED AUTOMATIC TRIPS WHILE CRITICAL (Year to-Date) 1 I l 5 c PTN3
.. + ..PTN4
--O-- PS L1 4 ^
- O - PSL2 l
3 Division Target: s3 I b-o 2 p ' 1 0 , 0 0 - l ', p % 0
^ ^
. . W
~ Unit 1 1961 1982 1993 '1994 1995 '1/96 . W96 a396 *4/96 S/96 '6/96 7/96 SP96 ' 9996 10P96 11/96 12/96
~PTN3 0 0 0 1 0 0 1 1 1
- PTN41 0 1 1 2 0 0 0 0 0
" PSL1 ? 2 1 0 4 1 0 0 0 0
'PSL2 0 1 0 1 1 0 0 0 0 DEFINm0N An Unplanned Automatic Scram is a non manual actuation of the reactor protection system that re,ults in a scram signal any time the unit is critical. Scrams that are planned as part of special evaluations or tests are not included vi this definition. This indicator provides an indication of success in improving plant safety by reducing the number of undesirable and unplanned thermal-hydraulic and reactivity transients requiring reactor scrams.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE
.Am E-Q 12-Month Endino WANO Trios cer unit PTN 3 0 1 1 Trips per 7000 CriticalHours PTN 4 0 0 0 3-yr Distribution Median (7/92 6/95) 1.0 PSL1 0 0 1 . 1994 Median 0.8 PSL2 0 0 0 1995 Goal 1.0 Division Total: 0 1 2 HBQ (1995 3rd Ott Performance indicator Rpt)
QuarterlyTrips Annualized 1.0 1996 Division Target 53 Quarterly Trips per 7000 Critical Hours 1.2 PERFORMANCE
SUMMARY
No automatic trips occurred in April 1996. Year-tcxfate, one automatic trip has been experienced:
- Turkey Point Unit 3 experienced an automatic trip on February 9th; the 'B' Steam Generator Feed Pump was stopped to monttor its discharge check valve closing stroke which did not strike closed as expected. The resulting feed flow transient caused the "C" Steam Generator level to increase resulting in a turbine trip which tripped the reactor.
Data Providers: (PTN) J. Knorr 246-6757 (PSL) K Korth 467 7054 B6
OPEN PWO'S
\
2.500 I
- --+- PTN k --O- PSL 2.000
} l 3 1 500
- w '
l 3
- Q.
c
- 1.000 500 l
i o _ Unit ' 1991 1992 1983 '1994 1995 :1/88 :2PBS 3788 ; 4fBS 5196 ; ' SfBS 7/96 S/36 9f96 10/96 11196 12/06 j PTN - s 1 466 1589 1 441 1.422
- - est. 1. sos i n2e 2.ose 2.oes I
t l i DEFINITION 4 l This indicator includes Work Type 1 (Planned Mscellaneous), Work Type 3 (Projects), WorkType 5 (Trouble & Breakdown) and includes all hold codes, status 22 through 48. i
- Historic data not meaningful. Prior to 19%, each site was counting Open PWO's differently. St. Lucie was counting only Work Type 5 non-outage corrective and TJrkey Point was counting Work Types 1 and 5. Each site now agrees to report per the above definition.
s STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE PERFORMANCE
SUMMARY
Data Providers: (PTN) Greg Heisterman 246-6796 and (PSL) Joe Marchese 467 7107 r-1
. - -.. . . _ . . . .. - . . . _ - . . _ - . . . - _ . _ - . - . _ . - . . _ _ . . _ - _ ~ - - - . - . _ . - .
l l
! PWO AGING CURVE J
i 1200 1 j ; PTN Actual i - <> PTN Goal 1000 _e_.PSL Actual O PSL Goal i 4 800 4 m n. j 'o 600 9 3 ., f O, 4x .,'., i i . j . l 200 .',",.,,
... '~
j ., -
. Unit . TOTALS ., . 0 3 Mo. , ' 4-6 Mo. - 7-9 Mo.- ~1012 Mo. c Over12 Mo. .
i PTN Actual 1166 529 271 124 24 0 PTN Goal '- 583 292 146 0 O l
- PSt. Actual 961 541 234 95 51 40 )
PSLGael - 481 240 120 60 30 i l i . DEFINITION ! l ! PWO Aging curves includes Work Type 1 (Planned Misc) Work Type 3 (Projects) and Work Type 5 (Trouble & Breakdown), l and excludes short notice outages (SNO), HC2-Startup, HC3-Hot Standby, HC4-Hot Shutdown, HC5-Cold Shutdown, and HC6-Refueling. This only includes status 22 through 48. j ) Goal: To halve the backlog every three r. 3nths. STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE { i 2 i i ! PERFORMANCE
SUMMARY
f 1 - j Data Providers: (PTN) Greg Heisterrnan 246-6796 and (PSL) Joe Marchese 467 7107 1
- C2
PWO'S GREATER THAN 12 MONTHS l (GOLDEN OLDIES) TURKEY POfNT l REF PWO# PWO TITLE Orig. Date Date on List 1 94028384 CV 4 3728. ACTUATOR, WILL NOT MAINTAIN 10 PSID PER 44)P489.1(HCS HOLD REMOVED) 11n4/94 54/96 2 95001652 CV 3 3729, VALVE FAILED OPEN (HMM HOLD) 01/17/95 2/1/96 3 95005513 HSC 3-152, BRITTLE / CRACK INSUL ON WIRES (AWP HOLD) 02,2395 2/1/96 4 95006604 DPC-3-3728, ADJUST DPC (AWP/HTA HOLDS) 03t3/95 3d/96 l 5 95007510 HAGAN CONTROLLER,35V REG MEASURES 53.2 03/1395 55/96 j 6 95007509 HAGAN CONTROLLER,35V REG MEASURES 30.7 031395 5/1/96 7 95008006 VARIOUS POLISHER VALVES, DEFERRED PMT FOR POUSHER VALVES (TST HOLD) 0317/95 55/96 l 8 95008271 RCDT LEVEL LOOP L41003, VERIFY WIRING OF RCDT LIVEL LOOP L 1003 (ENG HOLD) 0321/95 M/96 9 95008285 RCDT LEVEL LOOP L 3-1003, VERIFY WIRING OF RCDT LEVEL LOOP L 1003 (ENG HOLD) 0321/95 5/1/96 10 95009033 FLUX MAPG SYS, CNTRL PANELREPL FLUX HAP NIXIE TUBES /PWR SPLY(HTNAWWP HOLDS) 032895 '5/1/96 11 95000032 FLUX MAPG SYS, CNTRL PANEL REPL FLUX MAP NIXIE TUBES /PWR SPLY(HTNAWWP HOLDS) 0328,95 5/1/96 12 95009320 FLUX MAPG SYS RECDRS R 1420,1421,1422 REPL FLUX MAP RECDRS W/1 RECDR 03"JO/95 54/96 13 95009658 R-4444. CNTMT SPR PP DISCH RECIRC TO TWST FLOW INDIC, IMPROP. TUBED BARTON IND OM3/95 5/1/96 14 95009748 F13-944. CNTMT SPR PP DISCH RECIRC TO TWST FLOW INDIC, IMPROP. TUBED BARTON IND 04/04/95 55/96 l 15 95009832 4P98, PUMP, COAT MOTOR STATND INTERNALS 04/04/95 5d196 I 16 95009829 10 PATHS FOR FLUXMAPPER, REBUILD SPARES (HMM HOLD) 04/05/95 51!96 17 95011293 TI-3-3605, RESEARCH WHY CIRCUITRY DOES NOT WORK }fTA HOLD) 04/20/95 5/1/96 l 18 95011295 Tl4 3605, RESEARCH WHY CIRCUITRY DOES NOT WORK (HTA HOLD) 04,20/95 Sn/96 19 95012008 SUPPORT 3 HDRH44 STANCHION PIECES SLIDE WITH!N EACH OTHER 04,24/95 5/1/96 20 95012096 CV4-3729, ACTUATOR, CYCUNG, CHECK CAL AND ADJUSTIF RECTD OM5/95 5/1/96 21 95012139 4P9C, PUMP, NEEDS REPACK, CR 95-240 DMS/95 5/1/96 22 95012259 LT-3-488, CHECK CHANNEL FOR SPIKING OM6/95 5/1/96 23 95012280 3-294C, VALVE BINDING, REPLACE VLV / 95008136 04.26/95 55/96 24 95012473 LS-31568, SWITCH DID NOT START PUMP 0M8/95 5/1/96 ST,LUCIE REF PWO# PWOTITLE Orig.Date Date on List 1 92052114 SCREENCORRODEDFALLING APART SAFTEY 1055/92 N/A 2 93032009 COMPLETE UPGRADE OF COMPUTER SYSTEM 12d/93 N/A 3 94025253 METER' MOVEMENT STICKY AND OUT OF CAL 10/5/94 45/96 4 95001003 INSTALL LEVEL INDICATOR FOR POOL LEVEL 1h1/95 1n/96 5 95004053 REPAIR VALVE LEAK REMOVE DRIP PAN 2/9/95 45/96 6 93034478 OVERHAUL SPARE H.'41 A MOTOR 2d0/95 2d/96 7 95004389 SUPPORT IMA IN ACTUATOR REMOVAL 2/1395 4d/96 8 95004447 REBAR IS RUSTED AND CONCRETE IS CRACKING 2A 4,95 2/1/96 9 93034478 OVERHAUL SPARE HVS 1 A MOTOR 3,27/95 3d/96 PWO Greater than 12 rnonth's, W0rk Types 1 through 5, exduding outage hold codes (SNO, SNW, HC2, HC3, HC4, HC5, HC6) status 22-48. Data Pmviders: (PTN) Greg Heisterman 246-6796 (PSL) Joe Ma@ese 467 7107 CA
NON-OUTAGE PWO'S I 1403 1200 I --+-- PTN _ l H>--PSL 1000 g 800 5 600 400 200 0 i Unit , 1991 1992 1983 1994 ~1955 ' - 1/B6 72ft6 aft 6 ,WB6 Eft 6 elB6 7/96 BfD6 9PB6 10fB6 11/96 12/96 PTN - * *
- 1024 1091 1118 1166 PSL
- 1247 1103 1016 961 DEFINITION
, Non-Outage PWO's includes Work Type 1 (Planned Msc) 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 rneaningful. 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 rinfinitinn.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE PERFORMANCE
SUMMARY
Data Providers: (PTN) Greg Heisterman 246-6796 and (PSL) Joe Marchese 467-7107 C-4
l l ! CONTROL ROOM INSTRUMENTS OUT-OF-SERVICE i
.--+-- PTN j
C --O-- PSL so
- $ 0 i
i5 40 d
\
- > s
- 0 i l so
\\
1
- i \
8 fj g 20 . g April Outage Tags j PTN 20 j PSL 13 j 10 o Unit M 1981 1982 1983 1984 1986 1/B6 . 2758 3/06 ,4/06 8756 s#96 7/96 sit 6 ' 9f96 10/96 11/96 l 12/96
- ; PTN , 39 40 42 12 30 PSL: 54 46 25 20 28 DEFINmON This indicator defines the number of control room nstruments 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
Data Providers: (PTN) Greg Heisterman 246-6796 and (PS!.) Joe Marchese 467-7107 C-5
I ' OSHA RECORDABLES (Year-to-Date) 4o
! ^
35 3a
-+- PTN l
- O-PSL l l
; 25 l
^
h 20
\
h t5 . 10 5 l C o :
. Unit 1991 1992 '1993 1994 1995 1/86 .2fSS 346 4 98 5796 4796 7/96 846 946 10/96 11/96 12/98 PTN - 35 33 33 27 17 0 1 2 2 PSL 20 15 19 23 25 3 3 4 5 DEFINITION The definition by Occupational Safety Heam Administration (OSHA) is an injury occurring on the job that requires rnedical treatment beyond first aid as defined by 29 CFR 1904.
I STATISTICAL
SUMMARY
IN0l[STRY PERFORMANCE Month y-T-Q l PTN 0 2 PSL 1 5 NuclearDivisionY-ETarget 1.75
+ Corporate Y-ETarget 5.75 PERFORMANCE
SUMMARY
One OSHA Recordable injury was reported at St. Lucie:
. A utility worker strained her back while moving a 4 ft. section of a scaffold pipe.
i Data provider. W. Korte 694 4235 D-1
- LOST TIME INJURIES j (Year to-Date) i 5
f i 1
--*- PTN
^
d --O-- PSL } I
.l, s ,
1 I l
- F I
E2 - l ! o : : . . >--C
- Unit e 1981 1982 "1993 .1994 1996 '1/96
. 1226 13t36 4fB6 - <. 5796 8 416 '7/96 . af96 Sf06 10/06 11/96 1246
'PTW 0 0 0 1 0 0 0 0 0 pet. ~ 2 4 3 1 2 o o o o l
DEFINITION ' i A Lost Time injury as defined by Occupational Safety Health Administration (OSHA) is an occupational injury that requires an l employee to miss a full day (8 hour shift) beyond the day of injury. j l 1 i STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE M Y-T-D RN O O PSL 0 0 PERFORMANCE
SUMMARY
No Lost Time injuries were reported in April 1926. 1 Data provider: W, Korte 694-4235 n.9
i l REGULAR STAFFING l P FPL Employees and Long-Term Contractors by Department Turkey Point l i 1050 - ual 1000 - see oss see see -O- Planned g = = = 950 - A- - E 857 g a 900 St. Lucie 1100 1050 -
'[ 1 0,30 1.022 i,qo
. 1000 - ,,o%g i,ohn 3,,S, i,oy, 3
j 950 - 900 l Engineering & Licensing l 300-
't". D D D 3,, 3,, 3,, 3,, )
200 - 3 g 100 - , O Nucles.- Assurance l 150
- ( 106 106 106 106 303 104 104 105
- a
' 50 - l 8
0 -- Nuclear Operations
#O u s2 32 32
" ~
30 - 31 31 2 9 30 29 20 - 3 g 10 - 0 - Nuclear Business Services 15
) si ti si ti c '
a^ io si io 5-i E i 0
- Nuclear Division Total h 2.493 2.493 2.493 2.493 2500 - C 0 E U 2400 - 2.4I3 243 2,4Te ,j 2300-5 2200-E 2100 -
2000 l ims i as l ms I mes l was i ens I was I ses - l ass I swes I ives I Same i Data Provider: Alicia Simpson 694-3275 Data Source: ND Staffing Report n2
l
- OPERATOR EXAMINATION PERFORMANCE j Turkey Point Units 3 & 4 100.0 % -
^ l
( E RO/SRO Pass % ! 4 4 A f f,: Doper Reg Pass % 95.0 % < 't - 6 - d f f 1 Z i b 4 i rh i k ! y 1 3 i
; ?
f . 1 h
; 90.o % ( _ 'e .
a
!g a Z
?
i 1 $_ a 0 m Q s ? i u A - j Q ';- j
- ! 4
--g'v 85.0% - --
j { l j d, b M i 3 e 3e t [3 80.0 % f h j Emanas: 1991 '1992 '1993 1994 1996 ,1/96 ' 2f96 3/96 4 96 5/96 '8/96 7/96 8/96 ~ 9/96 10/96 11/96 12/96 1 norsno tehen . 39 5 - 8 13 - - - - l Poseed . 39 5 - 8 13 - - - - i
. SCWsao pues % 100os 100 os 100 o % 100 0% l
- OperNegfekan 47 78 69 63 58 64 - -
]
. Passed - 44 75 66 60 56 - 64 -
opor Aeq Pese % 94 o % 96 o % 96 o% 96 o % 965 % 100o% l f DEFINITION Initial License Examination (RO/SRO) results are reported for all candidates taking an initial License Exam as conducted by the NRC. l' Operator Requalifivation 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 STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE initial RO/SRO License Exams No. Passed Pass Rate % The NRC at their last Regional Training Managers Meeting No. Taken 0 0.0% (for fiscal year 1994) provided the following data: YTD 1996 0 I YTD 1995 13 13 100.0 % Inta! NRC Erams NRC Recual Erams i RO's Pass Rate 94.6 % RO's Pass Rate 91.0 % i Operator Requal Exams W SRO's Pass Rate 94*4 SRO's Pass Rae 85.0'4 No.Taken Ng Passed Pass Rate % Upgrade SRO's Pass Rate 94.7% Average Overall 88.0 % YTD 1996 64 64 100.0 % Average Overall 94.6 % YTD 1995 58 56 96.5 % PERFORMANCE
SUMMARY
No initial RO/SRO License or Operator Requalification Exams were given in April 1996 at Turkey Point. Data provider: K. E. Beatty 694-4217
,l T' 1
l l OPERATOR EXAMINATION PERFORMANCE , St. LuCle Units 1 & 2 , 100.o % E RO/SRO Pass % 0 Oper Reg Pass % 4 9 95.0% 4 D 4 1 I f 90.o% . I -
; e a
- e f A 1 y d
8s.o% - ( l , R j 00.0*. i ! Exems: 1 991 1992 '1993 1994 '1995 '1/96 '2/96 3/96 4/96 519 6 6/96 7/96 '8/96 9f96 10/96 11/96 12/96
- RO9540Tehen . 15 8 10 11 - - - 4 j - Passed 15 8 10 11 - - - 4 -
i ' ROIS M) Pese % - 100 0% 100 0% 100 0% 100.0% 100 0% Oper Reg Teenn 65 69 68 75 73 - - - l 1 - Passed ' 61 60 68 68 71 - - - - I Oper Asq Poes % 94 0 % 870% 100 0% 910% 97.5 % l ! DEFINITION 5 Initial Lcense Examination (RO/SRO) results are reported for all canaidates taking an initial License Exam as conducted by the
, NRC.
] Operator Requalification Examination results are reported for both RO's and SRO's. This examination is administered annua!!y by
~
j the utility and may be icintly administered by the NRC. Retests of operators who failed examinations are not included. 1 STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE Initial RO/SRO License Exams l The NRC at their last Regional Training Managers Meeting No.Taken No Passed Pass Rate % l g , j YTD 1995 0 0 0.0% initia! NAC Exams NAC Recual Erams RO's Pass Rate 94.6 % RO's Pass Rate 91.0% Operator Requal Exams Instant SRO's Pass Rate 94.4 % SRO's Pass Rate 85.0% i No.Taken No. Passed Pass Rate % Upgrade SRO's Pass Rate 94.7% Average Overall 88.0% 0.0% Average Overan 94.6 % YTD 1996 0 0 YTD 1995 73 71 97.5 % PERFORMANCE
SUMMARY
[ No Operator Requalification Exams were given in April 1996 at St. Lucie. Initial RO/SRO License Exams were given at St. Lucie in March; all four participants passed, resulting in a 100.0% pass rate. Data provider K. E. Beatty 694-4217 i F-?
.. . . . . ~ ~~ . - - . . , . - - ~ . ~ ~ . . ~ _ _ _ . . - . ~ . - - . .
i' i OVERDUE CONDITION REPORTS j 100
# } l -+- PTN
~~j -O- PSL 1 So
\
f 1 a: 60
\
9 O f 50 !4 a f 40
-\ /\
i n o 30 i a
- \
) 0 . . .
. : Unit '1991. M 1983 1994 ~1996 *146 2138- :3/96 4 06 ' 6P06 W96 '726 > 8/96 t/96 1W96 1146 12A6 2 PTM 6 0 0 12 0
'PSL 95 25 51 0 DEFINm0N Currently, the Nuclear Division is transitioning to a consistent Condition 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 fol lows: A = 3 working days B = 10 calendar days C = 30 calendar days STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE PERFORMANCE
SUMMARY
Da'.a ProvideT (PTN)Juho Balaguere 2464971 and (PSL) Bob Dawson 467 7154 C.1
l QA FINDINGS i l 20
--+-- PTN
-O-- PSL
-dr-Juno I 15 The Juno Beach Auct Fmengs
, open 151-180 days are pnmarWy F assoaateo =tn ina Nuu nuet- 1 g it is samed that most wm tw j c mono aunas the % aum j ,
y 10 at PTN m May. j 5 l o . - - . . 4 u,gt _ s- o.30 , , t 31.e0.- +
. , ; c140 ,.e1120;
+ 121-150 4151-1e0 :JLi
- PTN a + 0 o 1 0 0 0 ePSL- 5 1 0 0 0 2 Juno 6 0 0 0 1 11 DEFINmON 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 audit report transmittal and continues until Quality Assurance (QA) verifies that implementation has occurred.
1 STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE ! 4 PERFORMANCE
SUMMARY
Data Provider: R. A.Symes 6944287 F-2
1 1 1 l NRC VIOLATIONS Cited and Non Cited (Year-to-Date) 22 = 1 T PTN NOVs l
. +
- PTN NCVs l I
1s -O-- PSL NOVs I 16 i f O- PSL NCVs 1 I) i
- o 14 \
1 - 12 . ' T' C e 8to \. ; <
/ '
2
$gE -
\', >l/ ) el a
-5 4 ,
I 1996 Y E Target: s7 I
\ ..: J.o l
- o . . . . . . .;. . . ox g.. I C * ; O ' = O' o
i i 118nt ' ' 1991 M992 190s 1994 -1995 -1/Of, *2/96 ,3/96 4/96 9/96 ' 6f96 '.7/96 1 8796 ' tf96 10f96 11/96 12/96
)
k :PTM NOW's ' 13 8 4 4 1 o o o o l
- -PTN NCV'e 21 7 13 12 15 o 1 3 3 h
' PSLe00V'e r 8 8 7 9 21 o o 4 8
. > PSL'91CV's - 3 3 3 3 12 1 1 1 5 ! DEFINITION Vdations are categonzed in tenns of five levels of severity ta show their relativer' nportance. Seventy Levels I and 11 are vdatons that involve actual or high potental impact on the public. Seventy Level 111 Violabons are cause for sgnificant concem. Severity Level IV violations are less senous, but are of more than minor concem; i.e.,illeft uncorrected, could lead to a more sonous contem. Severtty Level V violations are minor sc.fcty or ermrenmental concem. Vdations are counted on the i date of the espechon exit meetng. Violations are now' counted with respect to the date of nccurrence (usrig the date of the inspecton exit meetng) hstead of the date of the inspechon report, as was done in the past. STATISTICAL
SUMMARY
- INDUSTRY PERFORMANCE AQI IIQ Year End Target NRC Violations 1994 IBG Group Mea., 16.2 PTN Cited 0 0 7 1994 Region 11Mean 13.1 PTN Non-Cited 3 3 1994IBG Top Quartile Mean 9.0 PSL Cited 4 8 7 1994 Region IlTop Quartile Entry 8.0 PSL Non-Cited 4 5 PERFORMANCE
SUMMARY
Turkey Point reported no NRC Vdabons in April. An NRC violation reported in March 1996 was reclassified to an Urresolved issue (URI) by the NRC. St. Lucie reported four' NRC Vdations for the month; eight violations have been reported year-tcKfate as follows:
#960141: Temporary Procedure changes were made which involved changes of intent, without prior FRG review as required by Technica!
Specifications. Exit Meetng Date: 2/20/96.
#9643-01: Operators failed to follow piocedures for boron dilution. Exit Meeting Date: 2/8/96.
#96-03-02; inadequate design control of RCS boron dilution procedure. Exit Meeting Date: 2/8/96.
#96 03 03. Inadequate 50.59 safety evaluation of change to baron dilution procedure. Exit Meeting Date: 2/8/96.
'#96040t: A containment gaseous monitor was rendered inoperable due to a failure to follow procedures, combined with a lack of taking proper logs. Meetng Date: 4/3/96.
' #96-0442: Failures to make required log entries for reactivity manipulations and a main generator hydrogen addition. Exit Meeting Date: 4/3/95.
* #9644 03: An EDG cendered inperable due to a failure to follow procedures while placing the fuel oil tank on recirculaton. Exit Meetng Date: 4/3/96.
* #96-04-04: Reviews of histoncal data for CEA maintenance revealed that post modificaton testing acceptance crit 6na for Unit 1 CEA power cables were not applied to post-moditcation test data. Exit Meeting Date: 4/3/96.
Data Providers: (PTN) Gary Hollirger 24&6078 ard (PSL) Ed Weinkam 467 7162 rn
. - ._ . ._.- - - - _ . - - . . . . -_ - . ~ ~ - - - ~ - - - - ~ . - ~---- - - - --- ~- . - - ~
i j LICENSEE EVENT REPORTS i (Year-to-Date) 1 25 l j i i l ! -+- PTN 20 . -O- PSL } ' Y IK ( { 15
! 5
- s
^
8 lto
=
N
^
5 O ,l ! ' Unit - 1991 ~1992 *1993 1994 1995 *1/96' .2f96 Sf96 4 96 Sf96 4/96 7/96 SIDS 946 10/96 11/96 12/06 ! -PTN- 20 24 9 12 7 1 5 5 6 J~ tPSL' 9 10 8 15 18 1 5 5 5 i.
' DEFINm0N '
l License Event Reports (LER) are submitted to the NRC by the licensee to report unusual occurrences prescribed by 10CFR50.73. l l
- . STATISTICAL
SUMMARY
' INDUSTRY PERFORMANCE J ARI .YIQ 4 i!
; t NN 1 6 ll PSL 0 5
- i i !
i! ' PERFORMANCE
SUMMARY
No LER's were reported in April 1995 by St. Lucie. 1 1 Turkey Point reported one LER for the month:
#96 01 manual reactor trip occurred due to a turbine govemor control oil perturbation.
i 4 Data PremdeT (PTN) Gary Holknger 2464078 and (PSL) Ed Wenkarn 467 7162 l 1 ob
n i INPO ASSESSMENT RATINGS i 4.So l 1.00 . RPTN l
- O PSL j 3.50 -
z= - l
- a - -
j 2.So - . E
= - -
2.00 = 1 1.50 - i 1.co = l i _ o.5o . I c.co . Unit - "1986 1987 1988 - '1980 ' 1990 - 1991 1992 1993 1994 1995 1996- ] 2.00 2.00 1.00 . J 'PTN 4.00 4 00 1 00 4.00 1 00 2.00 1.00 1 00 1.00
/- PSL INPO ASSESSMENTPROGRAM DESCRIPTION d
The institute of Nuclear Power Operations (INPO) conducts periodic evaluations of site activities to make an overall determination of plant safety, to evaluate management systems and controls, and to identify areas needing improvement. Information is assembled from discussions, interviews, observations, and reviews of documentation. i j Evaluation Frequency INPO's goalis to visit each plant on an average of every 18 months. However, this frequency may vary depending
! upon the previous assessment ratngs. 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 "S*, the assessment interval is s 18 months. I j Pedaimave Catecorv Ratinos: Category 1: Over !! performance is excellent. Industry standards of excellence are met in most areas. No significant weaknesses noted. ) I Category 2: Overall performance is exemplary. Industry standards of excellence are met in most areas. No significant weaknesses noted. ! Category 3: 0.erall performance is generally in keeping with the high standards required in nuclear power. However, improvements are i needed in a number of areas. A few significant weaknesses may exist. Category 4: Overall performance is acceptable, but irnprovements are needed in a wide range of amas. Significant weaknesses are noted in several areas. 1 Category 5: Overall performance does not meet the industry standard of acceptable performance. The margin of nuclear safety is j measurably reduced. Strong and immediate management action to correct deficiencies is required. Special attention, l assistance, and follow-up are required. 3
! HQIE:If a plant is found to be operating without an adequate margin of nudear safety,INPO will request that the plant be shutdown, or not started up.
l 4 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. Dea omders (PTN) Gary Hollinger 246-6078 and (PSL) EdWeinkam 467 7162 cA
_ . . . . _ ~ .. ____ _ _ _ _ ._ _ .. _ ._. _ . _ . _ _ __ _ _ _-. _-.._ . _ _ l' i NRC SALP CATEGORY RATINGS l 2.50 1 1 l 2.00 - { E PTN Rating l l O PSL Rating !
$ 1,50 - -
i s ' a S 1.00 - 1 1 ( i 1 0.50 - mg 1 , -:1986 '1987- 1988' ~1989 1990 ~ 1991~ 1992 1993 '1994' '1995 ':1996 " PTN Reeng ! 2.27 2.18 2.25 2.14 1.86 1.38 1.38 1.29 1.00 - - merled Erunng 4/30/86 & 31/87 6/30/89 7/31/89 7/31/90 9,"28/91 - 1/30/93 8/27/94 - - j PSLneung - ' 1.55 1.20 - 1.29 1.14 - 1.00 - 1.00 - 1.50 f 7.2 Endeng 4/30/86 1 0/31/87 - 4/30/89 10rJ1/90 5"2/92 - 1/1/94 - 1/6/96 1 SALP PROGRAM DESCRIPTION j lt a me poncy of Ihe NRC to use the Systernanc Assessment of Licensee Performance (SALP) process to aracuate the agency's ceservanons and esghts on kcensee safety performance The SALP report commurecates those ot)servanons and ms ghts. d Evndm Fnmuencv The NRC as normally review and evaluate each power reactor bcenset that possesses an coeranng hcense at least every 18 months. When the NRO determmes that )! lhe performance warrants a more frequent evaluanon, the nonnal SALP frequency may be mcrnased. The assessment penod rnay be extenced m a mammum of 24 months when a plant receeves a Category 1 raang e an leur luncticmal areas. Funetm2! Amar Perforrnance a generasy evaluated miour(4) funceanalareas: j 1. Punt comews This funcDonal area consists chelly of the contrd and execution of actMbes strectly related c cperstrg a plant it meludes acDvibes such as plant startup, power
- cperations, plant shut
- fown, and system hneups. R also mduces esbal and requahAcatir.m traevng of bconsed cperators.
! 2. Martenance Ths funcnonal area includes all actmbes assocated witn eriher diagnosac, presenve, prevenove, or cor ecove mantenance d plant structures, systems, and components. i l crrnamrenance of the physcalcondnan of the plant l l 1 F~xneeniv This funceanal ersa addresses the adequacy of tectncal and engneenng support for an plant a::liveet R bduces all hcensee actmoes assooated with desgn contrd; thej l desgn, estasanon, and iesing of piant rnodificanons; engneenng and metacal support for operanons, culages, rreseenance, tesong, survisance, and procurement scovmes; i } coniguranon management; cesgn basis mformanon and its retneval; and support for kanung actMbes. l 4. Pbm? Srmet_ Ths funcnonal area covers all actmnes related to plant support funcbons, mdudng raddogeal connais, emergency preparedness, searrtty chemisay, and fire protecno
- Housekeepmg contress are also rdJoed m this area.
Peermare Cavemrv Ra'w Licensee performance m each funceanal area is assessed by asegung a category rabng as dscussed below- $+ )
' Category 1. bcensee atterinon and mvoNement have beer: property locused on safety and reedted m a s@enor level el safety performance j
Category 2. bcensee attengan and mvolvement are normally wel focused and resulted in a good level ci safety performance. '!' Catepry 3. bcensee at'ennon and rivoNement have resulted m an acceptable level of periormarum. However, performance may exhibal one or more el the losowing chea .ter:snes l ineffecove programs and sgnificant usues, lack of conoceve actan thoroughness, and deficences m root cause analyst Because the rnargn lo unacceptanie performance a rnportant aspects a small, mcreased NRC and bcensee attenson a required. PERFORMANCE
SUMMARY
Turkey Posit St. Lucie Pnor Mos+ Recent Prior Most Recent Functonal Area: Plant Operations 1 1 1 2 Marttenance 2 Improving 1 1 2 Engineenng 2 improving 1 1 1 Plant Support n/a 1 1 1 Emergency Preparedness 1 n/a n/a n/a Flasological Controls 1 n/a n/a n/a Security 1 rVa n/a n/a Sd Assessment / Quakty Venficaton 1 Dli D& Dal Overall: 1.29 1.00 1.00 1.50 Data Premde's- (PTN) Gary Holhnger 246-6078 and (PSL) Ed Weinkam 467 7162 i FJ
_ - . . . _ _ _ _ __...__ _ __ __ . . _ _ _ - _ . _ . _ _ . ._ m ___.____ . .. J l lNVENTORY VALUE ACCOUNT 154.300 80 4 70
+PTNl'
-C>-- PSL
- a i
?
l j2 m e ao e 2 do j 3
- 1996 Y E Target: s 38 ($M) l l t '
.1 i 2 80 1 s , 20 1o o Unit i 1991 '1982 1983' 1994 1995 1/96 2/56 2PD6 4fB6 5/86 St96 7/96 8/96 9/96 -10/96 11/96 12f96 PTN' 79.1 74.7 54 9 42 4 37.4 37.4 37.2 36.0 35.1 PSL 58.6 65.2 60.2 43 7 39 4 42.0 42.3 43.5 42.9 DEFINITION i 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. j I STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE IBG (Year 1994) ' gT
$1an End % Chance YETaraet Average $43.6 Million PTN Monthly 36.0 35.1 -2.3% Top Quartile Entry $34.7 Million 6.1% Top Quartile Average $28.9 Million Y-T D 37.4 35.1 $38M PSL Monthly 43.5 42.9 3.5%
'Value does not include Capital as define < l by PRUC Y-T D 39.4 42.9 8.9% $38M PERFORMANCE
SUMMARY
e Turkey Point Regular Inventory decreased by $0.9M in April.
. St. Lucie's. Regular Inventory decreased by 50.6M for the month.
Data Providers: (PTN) Dick Rose 246-6692 and (PSL) Tom Kreinberg 465-4183 n.1
m___._____ _ . . . - . . . . _ _ _ - - _ . . . . . . . - . . _ _ . . .. ._..m._ _ .._ _ .. -__ _ _ . _ _ _ . _ _ . . _ . . _ _ _ _ _ _ 1 i
- OPEN PLANT CHANGES / MODIFICATIONS (PC/Ms)
- 350 l 300 1 --+- PTN
-O- PSL
? 250 EIN ESL Design: 67 42
.a 200 Remew: 10 36
@ Wortung: 57 114
- a. Update: 85 112 C
Total: 219 274 150 100 50 i 0 Unk* - :1991 1992 ,1993 1994 1995 41/9 6 .2S6 346 .W96 5/96 646 '7/96 396' Sf96 10/06 11/96 12/96 PTN ' 240 242 230 219
-PSL<
316 326 269 274 DEFINITION This indicator tracks the total number of PCMs in the engineering department. The purpose is to provide management a snapshot of the number of PC/M's. 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 Tumover Sheet (SATS) and drawing updateis complete. STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE PERFORMANCE
SUMMARY
Data Providers: (PTN) Jim Reed 246 6903 and (PSL) Kns Mohindroo 467-7482 u.1
l i } OPEN TEMPORARY SYSTEM ALTERATIONS l 4 25
-+- PTN
-O- PSL j to 4
} f ( ' $ E J
.p 15 .
E 4 i ! E to i b i
^
j 5 ? 1 3 l o
,286 346 4496 ?W96 9/96 ' 7/96 8/96 W96 1W96 11/96 12/96 Unit 5 1991 1992 1993 1994 1995 '1196 PTM ' 5 5 2 3 6 17 15 16 21 24 PSt. 2 DEFINITION A temporary system alterabon is a modifcation made to plant equipment, components, or systems that does not conform wit approved drawings or other design documents; a modifcation that is necessary for continued safe plant operation; a modification that will remove a nuisance or distraction tc the Plant Operators; a modifcation necessary to enable the plant to start up in a safe manner.
STATISTICAL
SUMMARY
- INDUSTRY PERFORMANCE eg Year End Goal l WN 6 5 PSL 24 10 1
PERFORMANCE
SUMMARY
l 4 Data Providers: (PTN) Julio Balaguero 246-6971 and (PSL) Kns Mohindroo 467 7482
. _ _ . . _ _ _ _ _ - _ _ _ _ . . _ _ - . -.. . . - - . ~ . - . __m. -. . - . - - - - - - - - - -
4 l CONTAMINATED FLOOR SPACE +
-+-- PTN l l -O- PSL l I
400o E i o* 5 . 2000 l i 1000 o _
' Unit ' '1991 1992 1993 1994 1 995 11/86 ;296 73fD6 <4its Eft 6 4796 ~ 786 :8/96 ' Sf96 '10f96 11/96 12f96
'PVN ' 1750 50 330 700 3748 32
'PSL' 4 5610 4351 4600 2848 1480 250 280 12 12 DEFINITION '
This indicator, designed to measure contaminated floor space with removable activity 21000 dpm/100cm sq. beta / gamma or 2 20 dpm/100cm sq. alpha, is counted against the base. Areas that can be specifically exempted from the base include: reactor containment building, chemical volume control system demineralizer room and long term process areas such as the decontamination facility. Contaminated components such as charging pumps, evaporators, etc. are not included as part of ' recoverable" floor space (i.e. not considered floor area you can walk or step on). PTN:Ig13!.Hgg(117,746 sq. ft.) Exemoted Area (6,110 sq. ft.) PSL Total Base (112,422 sq. ft.) ExgmJted Area (7,722 sq. ft.) STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE
& IEgit PTN 32 50 PSL 12 50 PERFORMANCE
SUMMARY
Turkey Point and St. Lucie's Contaminated Floor Space was below year-end targets in April. Data Providers: (PTN) John Lindsay 246-6548 and (PSL) Hank Buchant on 467 7300
DRY ACTIVE WASTE: GENERATED, SHIPPED OFFSITE l i (Year-to-Date) 14000 c PTN Generated 12000
< , - + - PTN Shipped
--0-PSL Generated
- - o PSL Shipped 10000 8000 l o
.0.
NOTE PTN: 4715 cu. 4000
^
fL actually onsite which indudes 600 cu. ft.
, carryover from 1995.
4
'O l
c : : : :
- Unit '1991 1902 1993l 1994 1985 :146 :246 ~346 -446 -546 446 7/96 849 6 W96 1G46 11/96 12f96 PTH eenssuted
- t- 8100 425 515 3925 4115 l PFwSNaped 2560 0 0 0 0 )
PGL eononauer 11740 n/a 820 1845 750 l PSLSMpped 13003 0 2080 3322 2396 I DERNITION . Generated - Is an estimate based on the number of ' yellow bags" initially generated prior to surveying for free release or shipment as radwaste. Calculation: Number of yellow bags x 5 cubic feet = Estimated Monthly Generated Waste figure. Shiooed 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 l
PSL made 6 shipments to SEG in 1995. PTN made 3 shipments to SEG in 1995. l i PERFORMANCE
SUMMARY
. PTN projects to ship 5,120 cubic feet in 1996. . St. Lucie shipped 2396.1 cubit feet of Dry Active Waste in April (2194 ft. to the processor and 202.1 ft. to Bamwell Waste j A
Management Facility). Data Provtars: (PTN) John Lindsay 246 6548 and (PSL) Hank Buchannon 467 7300 Y"
i i ' PERSONNEL CONTAMINATION EVENTS (Year-to-Date) ; 18o l 3 , --+- PTN l --O- PSL , 14o l l l 12o 1 I i ! ! $ 100 ^ l _5 l 4 s
- 8 l So l
'o o
l Unit ? ' 1991 1982 1983 1984 1995 '1/96 :2/96 :2 36 446. ;546' 646 726 846' 996 1tWB6 11/96 1226 ( -PTN>' 163 85 95 100 73 4 9 23 32
+ ' PSL " 87 76 84 82 0 2 2 3 DEFINITION This indicator is designed to monitor personnel contamination. A personnel contamination exists when 5000 dpm per 100cm2 on skin or personal clothing as detected by Personal Contamination Monitor and2100 counts per minute (net) using the Friskeris observed.
STATISTICAL
SUMMARY
INDUSTRY PERFORMANCE
&!! H-D PTN 12 32 PSL 1 3 PERFORMANCE
SUMMARY
Data Providers:(PTN) John Lindsay 246-6548 and (PSL) Hank Buchannon 46N300 1.1
-. _ ~ .
i 3 ! RADIATION EXPOSURE (Year-to-Date) 1000 i -+- PTN Y-T D _ 1 1 l l-O- PSL Y-T-D 5 800 1 ^ \ 700 a-t *W \ PSL Y-E Target: 485 g I J
~
_a I
" N PTN Y E Target: 275 I I 200 4
Note: March 1996 numbers 100 j adjusted to reflect TLD data O T -- Unit - 1981 1982 1983 1904 1906' :1/96 305 afts 436 Wes Gfes ~7/06 ' 9796 Sig6 l 10/96 :11/B6 12/96
- PTN Y T@ 938.0 324.9 281.8 476.2 214.6 5.3 9.5 159.2 178.2
- PSt.Y-T4 ? 451.3 244.5 459 9 504.7 412.8 3.0 9.0 13.0 212 1
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 AprH E YTD Taroet 12-Mo. Endino Man-Rem PTN 19.0* 178.2 235.0 349.1 WANO (PWR's) (two units) PSL 8.2* 21.2 86.0 385.4 1995 Median 306 Year-End Targets: 1995 Goal 370 PTN: 275.0 PSL: 485.0 PERFORMANCE
SUMMARY
. Turkey Point's performance Y T-D was below the Y T-D target; performance for 12-mo.'s ending of 349.1 was higher than the industry medianin April.
. St. Lucie's performance Y-T-D was below the Y-T-D target; performance for 12-mo.'s ending totaled 385.4 which is higher than the irdustry median.
Data Providers: (PTN) John Undsay 246-6548 and (PSL) Hank Buchannon 467 7300
- DRD count I-4
1 4 O&M BUDGET- DIVISION (Year-to-Date) 350.0
., ---G--- Actual
., Budget 250.0
{ 200.0 ,- 5 *'
$ 150.0
- 100.0 ,
,o' 50.0 w 0.0 1991 '1992 +1993 1994 1995 ' 1/B6 . JfB6 m 6 5756 8796 7/96 8756 Sf96 10/96 11/96 12f96
. Actsal- 342.4 295.2 290.6 285.2 269.5 13.4 312 67.4 96.7 Budget " ^ 333.3 314.6 326.4 302.0 279.2 17.8 36.7 75.8 . 104.8 129.6 147 4 164.0 180.0 201.2 218.0 233.9 252.8 variance (%) 2.7 -6.2 -11.0 -5.6 3.5 -24.9 -14.9 11.1 l -7.8 DE'4!! TION Operating and Mahtenanw Ou,eaditures include Nuclear Division operation and maintenance expenses associated with direct employees, contractors arj consultants, equipment, tools, design, egineering and other items / activities iguired 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 Exoenses Y-T-D Budoeted Exoenses x 100% = O&M Variance % Y T-D Budgeted Expenses STATISTICAL
SUMMARY
= INDUSTRY PERFORMANCE O&M Budaet AorY-T-D Actual ($M) Y-T-D Variance 1M) %
IBG Actual 1994 Avg. $297.0M IBG Top Ouartile Entry $270.0M 1996 96.7 ($M) 8.2 ($M) 7.8% IBG Top Quartile Avg. $2132M 1995 65.4 ($M) -10.9 ($M) 142 % IBG Projected 1995 Avg. $284.0M 1996 Y-E Budget 252.8 ($M) Projection (per dual unit site) derived by trending 1986-94 Actual data and 1995 Budgeted data for IBG Group. PERFORMANCE
SUMMARY
O&M Expenditures through April 1996 were $96.7 million which represented a budget underrun of $8.2 million (or 7.8%). The variance was the result of: a St. Lucie Unit #1 outage schedule change and the deferral of St. Lucie Spare Low Pressure Turbine Rotor refurbishment. . Data provider. T. O. Nasby 694-4188
- 1. I
1
- CAPITAL BUDGET- DIVISION (Year to-Date) i 180.0 l
1604
---4--- Actual i . . . . . . . Budget j 140.0 .
I
- 4 120.0 ;
s ,wo . . .
. , k' .
I A 80.0
's 60.0 40.0 -
! 20.0 ,,,,...- 0.0
. . . . .: . -Q
+ 71581 1983 1983 1994 1806 '188 12SE JOS 7488 'E DE' GS$ ;T/96 WB6 '956 1856 11/86 1a46 1 ' Actual u 4 150.7 68.4 90.3 76.5 47.2 1.5 2.5 2.9 6.3 Sudget 2 s 179.6 75.1 101 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 Variance (%) 16.1 -9.0 11.0 -12.7 27.0 -67.6 -65.0 -73.7 -59.7 DEFINm0N Capital Expenditures are those directly incurred / budgeted by the Nuclear Division for the construction of new utility plant additions and improvements made to increase efficiency, reliability or safety. Capital fuel costs are excluded.
1 Y-T-D Actual Expenses - Y-T D Budoeted Exoenses x 100% = CapitalVariance % Y-T-D Budgeted Expenses
- STATISTICAL
SUMMARY
- INDUSTRY PERFORMANCE CaoitalBudaet
- AorY-T-D Actual ($M) Y T-D Variance ($M) % IBG Actual 1994 Avg. $63.1M IBG Top Ouartile Entry $28.3M 1996 6.3 ($M) 9.3 ($M) -59.7% IBG Top Quartile Avg. $21.1M 1995 7.3 ($M) -7.5 ($M) -50.7% IBG Projected 1995 Avg. $58.5M i
1996 Y-E Budget 39.2 ($M) Projection (per dual unit site) derived by trending 1986 94 Actual data and 1995 Budgeted data for IBG Group. PERFORMANCE
SUMMARY
Capital Expenddures through April 1996 were $6.3 million which represented a budget underrun of $9.3 million (or 59.7%). j The variance was primarily due to: the underrun in Steam Generator Replacement Project (SGRP) reflecting a revision to the SGRP outage start date; the St. Lucie Unit #2 Reactor Head Seal Ring Replacement project de' ermined to be O&M; and, during year cash flow revisions for various St. Lucie Plant projects. Data provider: T. O. Nasby 694-4188 T. 7
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INTERNAL DISTRIBUTION: , R. J. Acosta JNA/JB D. E. Jemigan PTN/ PLT T. V. Abbatiello PTN/ PLT H. H. Johnson PTN/ PLT K. E. Beatty JNO/JB V. A. Kaminskas PTN/ PLT L W. Bladow PSUPLT T. Kreinberg PSUPLT W. H. Bohlke PSUPLT T. Luke JPN/JB G. J. Boissy JNO/JB H. N. Paduano JPN/JB J. B. Brady CC/JB J. G. Pizzutelli JNE/JB J. L Broadhead JEX/JB T. E. Roberts JPN/JB C. L Burton PSUPLT R. E. Rose - PTN/ PLT R. L Castro' JDC/JB D. Samil FNG/JB J. Clay PSUPLT J. Scarola PSUPLT K. R. Craig JPN/JB C. H. Shotwell JHR/JB J. L Danek JNS/JB R. Sipos PSUPLT R. E. Dawson- ' PSUPLT D. L Smith JPN/JB D. J. Denver PSUPLT J. A. Stall PSUPLT M. S. Dryden JNUJB R. A. Symes JNA/JB P. L Fincher PSUPLT C. Villard JPN/JB J. C. Hampp ETS/JB W. E. Walker PSUPLT J. R. Hartzog PTN/ PLT E. Weinkam PSUPLT R. G. Heisterman PTN/ PLT D. H. West PSUPLT G. ~ Hollinger PTN/ PLT J. A. West PSUPLT R. J. Hovey PTN/ PLT 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 29(0 Atlanta, GA 30323-0199 D. B. Miller, Jr. . Supervisor Nuclear Safety & O/ 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 Residentinspector PTN/ PLT Z-1}}