ML20137N220

Monthly Indicator Rept, Mar 1996

ML20137N220
Person / Time
Site:	Saint Lucie, Turkey Point
Issue date:	04/17/1996
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
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References
FOIA-96-485 NUDOCS 9704080296
Download: ML20137N220 (56)

Text

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L FPL NUCLEAR DIVISION

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ST. LUCIE NUCLEAR STATION TURKEY POINT NUCLEAR STATION i

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l MONTHLY INDICATOR l

REPORT March 1996 i

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$6b Issued: April 17,1996 40 6 970402 BINDER 96-4B5 PDR

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i FPL NUCLEAR DIVISION TURKEY POINT NUCLEAR STATION l

ST. LUCIE NUCLEAR STATION i

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l MONTHLY INDICATOR REPORT i

March 1996 k

Issued: April 17,1996 40 6 970402 BINDER 96-485 PDR

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FOREWORD i

i The Nuclear Division Monthly Indicator Report presents a compilation of performance

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indicators which provide a quantitative indication of performance. Specific areas et focus include nuclear and personnel safety, plant reliability, and economic i

I parformance.

l T1e specific indicators included in this report have been selected by senior

.T.anagement as key indicators of operating performance. Summaries of NRC indicator and WANO indicator perfom1ance have been incorporated in this report.

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Data contained herein will be refined on the basis of feedback from data providers, of j

continuing quality control efforts, and of comparisons to other data sources. Each monthly report will reflect the best available data.

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TABLE OF CONTENTS Foreward D. PERSONNELINDICATORS Table of Contents i

OSHA Recordabies..

.D-Lost Time injunes..

.D-:

Management Summary lii Regu:ar Staffing.

.. D ~-

Nuclear Division Business Plan Indicator Overview v

E. TRAINING INDICATORS NRC Indicator Performance Overview Turkey Point vi Operator Exam Performance-Turkey Point..

E' NRC Indicator Performance Overview St. Lucie vii Operator Exam Performance-St. Lucie~

.E4 WANO Indicator Penormance Overviev.-

vi, F. NUCLEAR ASSURANCE & REGULATORY INDICATORS WANO indicator Variance Explanations ix Overdue Conditon Reports.-

.F; OA Findings..

. F4 A. WANOINDICATORS NRC Violatons: Cited and Non-Cited.....

F-3 Ucensee Event Reports (LERs)z F-.'

WANO Weighted Overall Performance -

.A1 INPO Assessment Ratags..

F.5 Unit Capability Factor.

.A2 NRC SALP Category Ratngs..

.F6 Unplanned Capability Loss Factor..

A.3 Unplanned Auto Trips Per 7000 Hours Critcal A4 High Pressure Safetyinjection System Performance.

.A5 G. MATERIALS INDICATORS Auxiliary Feedwater System Performance.....

.A-6 Emergency AC Power System Performance--

A-7 inventory -

. G-1 Thermal PNrmance.-

A-8 Fuel Reliuility.....,. ---

_-............,.A9 Chemistry Index..-

. A 10 H. TECHNICAIJENGINEERING INDICATORS Radiation Exposure....-

.... A.11 Low LevelWaste

. A 12 Open Plant Changes / Modifications.

.H1 Industrial Safety Performance =

. A 13 Open Temocrary System Alteratons..

.. H 2 i

B. OPERATIONS INDICATORS L RADIATION PROTECTIONINDICATORS Equivalent Availability Factor.

p.1 Contaminated Floor Space =

.M Capacity Factor (MDC Net)..

.B-2 Drv Actrve Waste: Generated, Shipped Off-Sde.....

. 1-2 Fuel Utihzation (PTN;..._

B3 PersonnelContaminaton Events

. l.3 Fuel Utihzation (PSL).

.B4 Radiaton Exposure (Y T D)...

. 1-4 Forced Outage Rate.

.B5 Unplanned Auto Tops

.B-6 J. BUSINESSINDICATORS C. MAINTENANCE INDICATORS

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tal on.. "

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Open PWO's--

C-1

... =

PWO Aging Curve.......

... C-2 PWO's Greater Than 12 Months Old--

........ C 3 Appendix Non-Outage PWO s.-

C-4 Control Room instruments Out of Senace-C-5 Distributon Ust...

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l MANAGEMENT

SUMMARY

OPERATING PERFORMANCE Turkey Point Unit 3. Unit 3 achieved an EAF of 95.4% in March The unit was shutdown March 27th for 34.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> as a result of a manual reactorinp due to tne loss of the 3B Main Feeowater Pump. For the year, tne EAF was 87.4% which is below the 95.0% Y-T D target.

Turkey Point Unit 4. Unit 4 began powering down for a seneduled refuehng outage on March 3rd and remained shutdown through month-end. The EAF for the month was 6.8% and 68.3% Y-T-D, which is higher than the Y T D target of 65.8%.

St. Lucie Unit 1. For the month, Unit 1 EAF was 95.8%. Power reduction equatirf.0 30.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> was mostly the result of waterbox cleanings. For the year, the EAF.was 94.9% which is slightly higher than the Y T-D target of 94.8%.

St. Lucie Unit 2. Unit 2 essentially, operated at full power achieving an EAF of 100.0% for the month. Year-to-date, EAF was 92.0% which is below the target of 95.0%.

Y T-D Equivalent Availability for the Nuclear Division was 85.6% which is below the 87.6% targeted through the period.

No Unplanned Automatic Trips occurred in March.. Year-to-date, one trip was experienced at Turkey Point Unit 3 in February.

A summary of key plant operating statistics is summarized below.

PTN Unit 3 PTN Unit 4 March Y-T D March Y T-D Gross Generation (WMh) 510,722 1,373,032 34,730 1,081,294 Net Generation (MWh) 487,269 1,308,954 32,680 1,032,192 Net Heat Rate (Btu /KWh) 10735.5 10852.5 11806.6 10818.9 Equivalent Availability 95.4 %

87.4 %

6.8%

68.3%

Capacity Factor 98.3%

90.0 %

6.6%

71.0 %

Auto Trips 0

1 0

0 Forced Outage Rate 4.6%

9.3%

0.0%

0.0%

PSL Unit 1 PSL U02 March Y-T D March Y-T-D Gross Generation (WMh) 632,780 1,824,369 668,680 1,783,700 Net Generation (MWh) 599,306 1,726,652 634,666 1,686,090 Net Heat Rate (Btu /KWh) 10957.8 11026.7 10738.6 10835.2 Equivalent Availability 95.8 %

94.9 %

100.0 %

92.0 %

Capacity Factor 90.0 %

94.2 %

101.7 %

92.0 %

Auto Trips 0

0 0

0 Forced Outage Rate 0.0%

2.9%

0.0%

2.2%

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MANAGEMENT

SUMMARY

REGULATORY PERFORMANCE One NRC Violation was received at Turkey Point in March:

1. 96-02 Failure to meet requirements of 10CFR50.71(e) in that the FSAR was not appropriately updated to reflect the officad of a full core during a refueling evolution. Exit Meeting Date: 3/29/96.

St. Lucie reported no NRC Violations in March: however, the following were repo:ted for February:

1. 96-01-01 -Temporary Procedure changes were made which involved changes of intent, without prior FRG review as required by Technical Specifications. Exit Meeting Date: 2/20/96.

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1. 96-03-01' - Operators falied to fo!iow procedures for boron dilution. Exit Meeting Date: 2/8/9C.

1. 96-03-02* Inadequate design control of RCS boron dilution procedure. Exit Meeting Date: 2/8/96.

2

1. 96-03-03' Inacequate 60.59 safety eva!uation of change to coron dilution procedure. Exit Meeting Date-2/8/96.

• Note: On April 1. St. Lucie was informed that these violations represent a Severity Level Ill penalty for Unit 1 only. A Civil Penalty of $50,000 was imposed.

Year to-date, Turkey Point has reported one NRC Violation, and St. Lucie has reported four.

COST PERFORMANCE O&M expeditures through March 1996 were $67.4 million which represented a budget underrun of $8.4 million (or 11.1%). This variance was primarily due to: St. Lucie Unit 1 outage schedule change; St. Lucie non-outage project underrruns: and overtime payroll underrun associated with Turkey Point Unit 4 outage.

i February O&M budget performance variances are stratified as follows:

Turkey Point Site Specific

$2.9 million (or 7.4%) below budget.

St. Lucie Site Specific

$5.8 million (or 20.8%) below budget Other Nuclear Division

$0.3 million (or 4.2%) above budget Capital expenditures for March Y-T-D were $2.9 million. This represented a budget underrun of $8.2 million (or 73.7%). The favorable variance was primarily due to: an underrun in the Steam Generator Replacement Project (SGRPJ reflecting a revision to the SGRP outage start date: St. Lucie Unit 2 Reactor Head Seal Ring Replacement Project determined to be O&M; and plant cancelled projects.

For the month, Capital budget performance variances are detailed as follows:

Turkey Point Site Specific

$1.0 million(or 94.7%) below budget St. Lucie Site Specific

$6.3 million (or 67.7%) below budget Other Nuclear Division

$0.9 million (or 124.1%) below budget iv

NUCLEAR DIVISION BUSINESS PLAN INLICATOR OVERVIEW (DATA THROUGH MARCH 31,1996) 1996 1996 1996 Indicator Plant Y-E YTD YTD Comments Target Target Actuals Collective Radiation Exposure PTN s 275.0 s 225. 153.9 Turkey Point and St. Lucie were (Man-Rem)

PSL s 485.0 5 33.

13.7 below Y-T D Man-Rem targets.

3 The SALP for St. Lucie ending l

PTN 1.00 1.00 NRC SALP Ratings 1/6/96 was 1.50; for PTN, tne period PSL 1.50 1.50 ends Aug.31.1996.

y PTN reported one NOV in March; NRC Violations PTN s7 1

.g PSL had no NOV's in March; four PSL 57 4

were reported for February.

PTN3 3

1 PTN4 0

No unplanned automatic trips were Unplanned Automatic Trips l

3 PSL1 0

reported in March.

PSL2 M4 0

For the year, O&M and Capital Capital 39.2 11.1 2.9 actuals were below Year End u

t e onnance O&M 253.0 75.8 67.4 targets; underruns were mainly due g

Div. Total 2922 86.9 70.3 to schedule revisions and project underruns.

PTN3.

95.0 95.0 87.4 PSL1 slightly exceeded the Y T-D PTN4 82.0 65.8 68.3 EAF target in March. Division EAF Equivalent Availability Factor (%)

PSL1 78.5 94.8 94.9 Y T-D was 85.6%, which is below PSL2 95.0 95.0' 92.0 the 87.6% Y T D target.

M&S Inventory Levels PTN s38 -

36.0 PSL inventory increased $1.2M in Ml March pnmanly due to the

($ Millions)

PSL

< 38 43.5 scheduled Unit 1 outage of 4/29/96.

Production Cost PTN 1.75 2.37 2.31 Production Costs (c/KWh) were 5

(0&M and Fuel)

PSL 1.55 1.49 1.36 below the Y T D tr get in March.

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In March, Division Total Cost Total Cost (0&M, Fuel, and (c/KWh) was below the Y T-D Div. Total 4.56 4.76 4.70 3

Capital Carrying Costs) target, ~ but higher than the Y-E target.

FPL 2045.0 1959.0 Total Nuclear Division Staffing Nuclear Division LT Contr 463.0 459.0 Levels year-to-date was below the Staffing Levels Total

2508, 2418.0 Y-E target.

PTN 4 began powering down for a scheduled refueling on 3/3. Future Refueling Outage 5

2 re ge s e es are:

Duration (Days)

PSL1 63 0

PTN3 0308/97 PSL1 04/29/96 PSL2 NA 5

PTN4 09/15/97 PSL2 04/15/97

'h PTN 0.30 0.11 No Lost Time Injuries or Restricted urs PSL 0.30 0.32 Duty Cases were reported in March.

Running) v

NRC INDICATOR PERFORMANCE OVERVIEW for Turkey Point (Data through Quarter Ending September 30,1995) 5 {.

Plant Self-Trend Deviations From Peer Short Ter Grou0 Median L0n0 Tem m

Declinec Imorovec Worse Bette' i

ODERATIONS f.

Automat:c Scrams While Crmca

< - a 0.0 0.0 l

-0.22 l.

0.0 0.0

{

l Safety System Actuatons 0.0 0.0 j

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0.0 Sionificant Events j

O.0 l 0,0 l

1

. o,30

- 0.27 T-Safety System Failures

-0.30

.0.0 Cause Codes (ALL LER s) 032 Admnstratue CortroI Problem 0.0 0.

I 0.0 3.18 E Lcensed Opera *or Probiem loo 02 I 0.0 0 72

.Other Personnel Error loo eo Maintenance Pre &

0.c l

DesgrConstruebonlinstattaten 0.23 049 Fabncaton Problem 0.0 OE 0.0 00 Macellaneous o.o 00 i

SPUTDOWN Oy 0.d Safety System Actuations o,o 0.78 kN\\\\\\\\\\\\M

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l0.0 l0.0 Significant Events 5.40

-0.57 i

0.51

- 0.53 Safety System Failures 2.40 0.37 Cause Codes (ALL LER's) g, 029 i

AdmnstratNe Cottrol Probem 0.30 025 Lcensed Operator Problem 030 ON

-t jo.o 0.17 Otter Personnel Error joo 0.10 g 0.cg 0.12 Manenance Probiem (gggggyg.j yo 0.10

)

Desgr.'CofWrJcicrVinstall2'Cn Faor. cation Probie...

..go 0 08 0

l Mscehus 00 FORCED OUTAGES J

M i 0.06 l0.04 Forced Outage Rate

• 0.05

-0.03 0.64

-0.07 Equipment Forced Outages.

/1000 Commercial Hours 0.26 0.37 @

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1.0 0.5 0.0 0.5 1.0 1.0 0.5 0.0 0.5 1.0

• Not CWed try OperataW Ca Performance index Performance index NOTES:

Plant Self-Trend Short Term: Based on tne slope of a linear reg ession hne plotted over ead1 plant's data. Time ritervals used in the trends are a Qua.'ters for ' Operations

• and Formd Outages

• indcators and 6 quarters for Shutdown

• indicators.

Demations from Peer Grouc Median Lena Tew: Compansons are rnade of each otant to tne performance of its peers over a 12 Quarter ame inteNa!

Peer Gmues PTN 3&4 - Older Westinonnuse 3-Looc.

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NRC INDICATOR PERFORMANCE OVERVIEW for St. Lucie (Data through Quarter Ending September 30,1995) y,[,

Plant Self Trend Deviations From Peer j

s est.2 Short Term Group Median Lono Term Dechned imoroved Worse Better OPERATIONS f

l l 0.0

- 0.56 Automate Scrams While Cntical l

k\\\\\\\\\\10.54

' O.18 0.%

-0.36 j

Safety System Actuatons Significant Events 0

0 0.0 0.22 Safety System Failures 0.0 0.67 Cause Codes (ALL LER's)

Admnstrative Control Problem 0.08 30 0E 0

trensed operator Problem gJ555555510.72 0.64 Other Personnet Error 0.48 Maintenance Prob 6em 02 028 Design /Constructiordnstallaten l M 025 0.40 Fabncaton Problem l

l00 M 0.40 0.0 0.16 E 4

yseeims 0.0 0.45 0.95

-0.67 Safety System Actuations 0.0 0.15 Significant Events oj 0

0.22

- 0.0d Safety System Failures 0.0 1.34

)

Cause Codes (ALL LER's) 0.11 02 Admnstratrve Control Prooiem txensed Openitor Probiern f0 0.30 Other Personnel Error 0

O.08

.09 020 Marttenance Proolem 0.12 Deson/Constructon/ Ins'anaton l

$0.20 00 Fauncaten Problem l

10.0 0.27

~

f0 Macehus FORCED OUTAGES

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Forced Outage Rats

• O M 0.49 2.45

- 0.82 Equipment Forced Outages.

/1000 Commercial Hours 0.0 0.13 I

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i 1.0 0.5 0.0 0.5 1.0 1.0 0.5 0.0 0.5 1.0

• Nor Calcuated for ooeratonal Cvew Performance inder Performance Index NOTES Plant Self-Trend Short Tem 1: Based on the slope of a knear regression bne pictled over each plant's data. Time ritervals used in the trends are 4 Quaders for 'Operabons' and Forced Outages' irdcators and 6 quarters for Shutdown' indicators.

Deviations from Peer Groue Median Lono Temt Compansons are rnade of each plant to the performance of its peers over a 12 Quarter time interval.

Peer Grouo PSL 1&2 Combusbon Ergneenng with core proteden calculator plants.

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9 WANO OVERALLINDICATOR PERFORMANCE OVERVIEW (March 31,1996)

Unit or Station Values lindustry MedianValues *l Performance Indicators i 3. year oistribution:

PTN 3 PTN 4 PSL1 PSL 2 2000 Goais ggg3,3993) 3-Yr.

Unit Capability Factor (Uni:

88.7%

84.6%

77.9 %

80.5 %

81.2 %

87.0 %

.e, Distribution Ending March,96)

Unplanned Capability Less Factor (Unit 3.1%

4.3%

11.0 %

6.6%

5.2%

3.0%

%, a Year Distr. Ending March '96)

Unplanned Automatic Scrams Per 7000 Hours Critical (Per Unit, 3 Year Distri-0.6 0.9 1.6 0.6 0.9 1.0 bution Ending March '96) id High Pressure Safety injection System (Per Unit. 3-Year Distribution 0.008 0.009 0.026 0.009 0.003 0.008 !

"Y 4

g Ending March '96) l l available r5 Auxiliary Feedwater System (Per not j

Unit, 3-Year Distribution Ending 0.015 0.012 0.010 0.013 0.004 - 0.009 avai'able gt March '96) eng Emergency AC Power System (Per not g

Unit, 3-Year Distribution Ending 0.006 0.003 0.019 0.013 0.007 - 0.012 available March '96)

Thermal Performance (Ratio of Design to Actual Gross Heat Rate, 1 Yr.

99.9%

100.1 %

98.9%?

• 98 2/o 99.5% "

99.5 %

Distribution Ending March '96)

Collective Radiation Exposure (Man-Rem per unit per year,3-year running 184 184 220

~220 153 120 avg. ending March '96)

Volume of Low-level Solid Radioactive T

Waste (Cubic meters per unit per year, 33.1 33.1 154.6 I rS4.6,

47.0 45.0 3-year avg. ending March '96)

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Chemistry Index (12-Mo.

average 1.11 1.03 1.18 t19 1.18 "

1.10

{

through March '96)

Industrial Safety Lost time Accident Rate (Station rate per 200,000 man-hours 0.11 0.32 0.55 "

0.40 worked ending March '96)

Fuel Reliability (Unit microcuries/g, 1.00E-6 Outage 3.81E-5 1.69E 5 Refe e month ending March '96) 5.0E-04*"

NOTE: shaded area denotes FPL performance is unfavorable to actualindustry median.

Source of industry Data:

• 1995 Year-End Report for Performance Indicators for the U.S. Nuclear Utility industry (19931995 Distribution).

• • 1995 Year-End Report for Performance indicators for the U.S. Nuclear Utility industry (1995 Distribution).

• • • 1995 Year-End Report for Performance Indicators for the U.S. Nuclear Utility industry (N95&95 Disinibution).

Rev. 4/15/96 Viti

WANO OVERALL INDICATOR PERFORMANCE OVERVIEW Discussion of FPL Performance Unfavorable to industry Median (March 31,1996)

UNIT CAPABILITY FACTOR (3 Years Ending 3/31/96)

St. Lucie Unit 1. The 3-year running Capability Factor for the unit was 77.9%. Capability loss is attributed to tne 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 tnp' 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 (t.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%); and, Code Safety Valve repairs and modifications from 9/11/95 to 10/13/95 (2.4 %). Other miscellaneous unplanned outages and derates accounted for the remaining 7.0% Unit Capability Factorloss.

St. Lucie Unit 2. Capability Factor for the three years ending 3/31/96 was 80.5%. 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.

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UNPLANNED CAPABILITY LOSS FACTOR (3 Years Ending 3/31/96)

St. Lucie Unit 1. The Unplanned Capability Loss Factor for the three years ending 3/31/96 was 11.0% compared to an industry median of 5.2%. Unplanned outages and power reductions contributing to this performance included:

Refueling Outage extension from 6/1/93 to 6/17/93 (1.6%); Waterbox cleaning due to jelly fish 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 inp 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 6/9/95 (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 cutages and derates accounted for the remaining 1.0% Capability Loss.

St. Lucie Unit 2. The Unplanned Capability Loss Factor for the three years ending 3/31/96 was 6.6%. 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 2.6% in Capability Loss.

UNPLANNED AUTOMATIC SCRAMS PER 7000 HOURS CRITICAL (3 Years Ending 3/31/96)

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

1 HIGH PRESSURE SAFETY INJECTION SYSTEM 4

(3 Years Ending 3/31/96l Turkey Point Unit 4. Average performance was affecteo due to the on-line reolacement of the HPSI pump motors following discovery of cracked rotor bars.

St. Lucie Unit 1. Average performance for the last tnree years was affected by on line Motor Operated Valve testing 1

in the 3rd Quarter of 1994 and a breaker failure on 2B HPSI pump in the 1st Quarter of 1995.

St. Lucie Unit 2. In the 1st Quarter of 1995, average performance was affected as a result of Component Cooling Water (CCW) Heat Exchanger cleaning which placed the rescective HPSI pumo OOS due to lack of cedicated sea:

2

cooling, e

AUXILIARY FEEDWATER SYSTEM (3 Years Ending 3/31/96)

Turkey Point. Average performance for both units was affected by the B ARV Turbine failure in the 4th Quarter of 1994 due to malfunction of tne mechanical overspeed tnp device: in the 3rd Quarter of 1995, cerformance was ahecteo l

by: Part 21 repairs on the Tnp and Trottle Valves, and Unit 3 outage worx.

i 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 ACW PP 2C Steam Admission Valve MV-08-13 to open, a mechanical trip linkage for AFW PP 2C when the Electrical Overspeed Solenoid i

was energized, and a discrepancy between field wiring and plant wiring drawing for the AFW PP 2B.

EMERGENCY DIESEL GENERATOR SYSTEM (3 Years Ending 3/31/96).

St. Lucie Unit 1. Unit 1's average performance for three-years was the result of a high water jacket temperature trip of 1 A EDG and failure of the govemor on 182 during monthly surveillance run which closed off fuel to the 12 cylinder engine in the 2nd Quarter of 1995,1B diesel 12 cylinder engine valve failure in the 3rd Quarter of 1995, and 1B oiesel 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 - M AN-REM (3 Years Ending 3/31/96)

- Turkey Point. The three-year running average Collective Radiation Exposure levelior Turkey Point was 184 Man-Rem per unit which was greater than the industry median of 153 Man-Rem. Site performance was influenced by scheduled refueling outages.

St. Lucie. Collective Radiation Exoosure three-year running average level for St. Lucie was 220 Man-Rem per unit which was greater tnan tne industry median of 153 Man-Rem. Sne performance was influenced by unplanned and scheduled outages.

VOLUME OF SOLID RADIOACTIVE WASTE (Annual Avg. for 3-Years Ending 3/31/96)

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

CHEMISTRY INDEX (12 Mo's Ending 3/31/96)

St. Lucie Unit 2. Unit 2 exceeded target as a result of elevated condensate dissolved oxygen.

X

.. ~.

.. ~.

- - - -. ~. - -.,.. ~ -..

i WANO WEIGHTED OVERALL PERFORMANCE n

l 100.0 3

0 PTN 3

4.. 4.

• * +

• PT N 4 '

)

+ ---C>--- PSL 1 '

90 0

.. o..Psu2 o.

U.,

80.0 l

l o...

}

.. /

'o 70.o I

l a

o i

50.0

)

I hf'/"Unk e - i

'1991 199R 1993 1994 1986

,1/96 2/L 9 '

3/96 '

4/96 5/96 6/96

~ 7/96

'8/96

'9/96 ilW96 11/96 1996

< PTN 3 57.6 74.0 91.3 92.0 90 9 92.2 91.5 90 7

)

tfit45H o w 61.3 73.0 91.1 88.5 93.8 94.0 93.4 92.4

/defM Cf.

71.6 78.3 83.8 86.1 63.3 67.3 70.9 73.5 jhW F.r 83.6 85.1 76.2 75.6 74.0 69.9 75.5 80.8 h

.DEFINiil0N The WANO Overall Performance index is a composite indicator utilized to trend nuclear station perfo mance.

The index is a weighted combination of the following 10 indh? dual performance indicators:

1. Unit Capabihty Factor (10%)

5. Emergency AC Power (9%)

9. Thermal Performance (6%)

2. Unplanned Capability Lose Factor (12%)

6. Unplanned Auto Scrams (8%)

10. Chem'stry Indicator (6%)

3. High Pressure Safety injection (9%)

7. Collective Radiation Exposure (8%) 11. Low-level Radwaste Volume (5%)

4. Auxiliary Feedwater System (9%)

8. PWR Fuel Reliability (7%)

12. Industrial Safety Accidents (5%)

STATISTICAL.

SUMMARY

INDUSTRY PERFORMANCE WANO:

Through 4th Quarter 1995 Industry Median: 82.0%

PERFORMANCE

SUMMARY

a Turkey Point Units 3 and 4 overall performance exceeds WANO's industry median of 82.0%.

Data Provider. Sharon Bilger 694-4255 A.1

1 UNIT CAPABILITY FACTOR (3 Year Running Average) j 100.0 0

PTN3

• 4 PTN 4 i

95.o

-O--- Pst $

- O PSt.,'

t IncustN Avg.

So.0 i

0

,4, 4...g Dmsson Y E 87.5*,

Ei g, 85.0

'g O

C> -

-O

.O c-80 0 C>---C ' O 75.o

' /

O.

O - * * (1 L'

e 70.o i

I 65.0 d

i

'JN2 -

1901

'1982

'1983 (1984

'1995 1/96 12/56 3/96 '

4/96 5/96 ste6 -

7/96

> S/96 9/96 10/96 11/96 12/96 i

m3 47.9 52 7 64 6 85.o 88.9 88 9 88.6 88.7 j

c tW4 <!.

42.2 61.8 63.7 86.7 87.2 87.3 87.3 84.6 J' h n-r 77.5 78.4 82.7 84.6 77.9 78 0 77.8 77.9 Md 81 4 81.3 81.3 74.1 74.o 75.1 77.7 8o.5 72 3 74 6 76 5 78 6 80 6 C

" DEFINITION Unit Capability Factor is the rabo of the available enengy generation over a given time pened to the reference energy generabon over the same time penod, expressed as a percentage with both energy generabon terms determined relahve to reference ambient conditions. Available energy generation is tne energy that could have been produced under reference ambient conditons considering only limitatinns witnin control of plant

{

sw+ sd. i.e., plant equipment and personnel performance, and work control Reference energy generation is the energy ihat could be produced if the unit were operated et,nunuously at full power under reference ambient cond:tions tnrougnout the period. Refere%ce ambient condmons are i

environmental mnditons reoresentatrve of the anrcal mean (or typical) ambient conditions for the unit.

l

~ STATISTICAL

SUMMARY

' INDUSTRY PERFORMANCE p_ar V T-D 3-vr Runnra Y-E Tarcet WANO 1993 - 1995 Med:ar.

81.2 %

2 5.0%

1995 Median 82.6%

9 PTN 3 95.4%

87.4 %

88.7 %

i PTN 4 6.8'4 68.3 %

84.6 %

2 82.0 %

1995 Average 79.4 %

PSL1 95.8%

94.9 %

77.9%

2 78.0%

1995 Goal 80.0%

PSL2 100.0 %

92.0%

80.5%

2 95.0%

' PERFORMANCE

SUMMARY

Turkey Point Units 3 and 4 Capability Factor (3-yr. running average) performance tnrough March 1996 was higher thar. WANO's 3-yr. running irdustry median.

s Data Provider. Sharon Bilger 694-4255 A-2

UNPLANNED CAPABILITY LOSS FACTOR (3-year Running Average) 16 0 c

PTN3

• + = PTN d r

14.0 4 pg.

g ~. e,.O industry Avg.

- O -PSL2 i

12.0 O

l W

D to.o l

l 0,

g f

8o y

~

. l N o

6.o 4.o

-... b+

y o

Dmsion Y E: 3.2%

l l

2.o o.o "pflank na.

!19e1 tigea 1 883 1994 1805

<1/96

'2/95 3/96 4/98

S/96 8/96 7/98 78/90' e/OS 19e8 11M6 1a#B6 l w PTtt3-15.2 4.8 3.7 3.7 2.7 2.1 2.9 3.1

&E9E964;-y.

11.5 6.5 3.6 5.o 4.4 4.4 4.3 4.3 l

ffMMal %. ;

5.1 5.9 2.6 4.2 t o.8 1o.8 11.o i t.o j

N 3.1 5.5 11.9 12.5 13.o 11.9 C4 66 7 " ~ 7_*

8.2 7.6 64 5.5 4.9 I

l M

DEFINITION Unp!anned Capabihty Loss Factor is defined as the ratio of the unplanned energy losses dunng a given penod of time 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 management control Causes of energy losses are consdered to be unplanned if tney are not scheduled at least four weeks in advance. Re'erence energy generation is the energy that could be produced if the urit were operated continuously at full power under referenca ambient conditiorgthroughout the period. Reference amtnent conditions are environmental conditions representative of the annual mean (or typical) ambient cordtions for the unit.

STATISTICAL

SUMMARY

INDUSTRY PERFOP.MANCE 3-vr Runnino Ava WANO PTN 3 3.1%

PTN 4 4.3%

1993 1995 Median 5.2%

PSL1 11 # 4 1995 Median 5.0%

PSL2 6.6%

1995 Goal 4.5%

1996 Target (all units): 53.2%

-PERFORMANCE

SUMMARY

m.

St. Lucie Units 1 and 2's Unplanned Capability Loss Factor performance for 3-yr running through March 1996 was higher than the WAN0's 3-year running industry median.

Data Source: John Ptzzutelli 694-4245 A.1

= - -

i

=

UNPLANNED AUTO TRIPS PER 7000 HOURS CRITICAL (3-year Running Average) 1.e 0

PTN 3 t

1.6 0,

O O

O

+ = PTN 4

\\ *.

---C>--- PSL 1 i

C

}g

. - O PS ;

. - Mcustry Avg.

E

\\% // ,

] g

'. /'

's Omsson Y E s 1 per und g

g,

%4-

+4$

j o.e l

h QC O

O, j

A 5 o.6 O

O

^

'O

.\\

r y

' \\

/

2 g"

j I

o.2 j

i j

o.o

.- Unk FE -

'1991 19ta

> 190a-1 984

.1986 1/08 2708 i 3f96:

Af06.

8798 malt 6 7/96 tefts' ref96 110ft$

11/96

• 12/96 W PT9tS La 1.6 1.o o.o o.3 0.3 o.3 o6 0.6

- Pill 4 D 1,7 1.4 o.9 1.3 o.9 o.9 09 o.9

. a; eR,vl **

1.3 1.o 0.9 1.5 1.6 1.6 1.6 1.6

@@EMOT o6 o.6 o.3 o.7 o_7 o.7 0.7 o.6 f_3 1.5 1.2 1.1 0.9 o.9

' ^ ^

~ DEFINITION Unplanned Automatic Scrams per 7000 riours Critical is defined as the number of unplanned automabc scrams that occur per 7000 hours0.081 days <br />1.944 hours <br />0.0116 weeks <br />0.00266 months <br /> of critical operation. Unplanned means that the scram was not an anticipated part of a planned test. Scram means the automatic shutdown of the reactor by a rapid insertion of negative reactrvity (by control rods, Equid injectjon shutdown system, etc.) caused by actuabon of the reactor protection system.

The scram signal may have resulted from exceeding a setpoint or may have been spurious. Automatic means that the inital signal that caused actuation of the reactor protecton system logic was provided from one of the sensors monitonng plant parameters and conditions rather than from the manual scram switenes or, in certain cases described in INPO 94409, from manual turbine inp switenes prtmoed in the main control room.

Cntical rneans that dunng tne steady state condmon pnor to tne scram, the e'fectnre reactor multplicabon factor was essentally equal to one.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Tnrough Maren WANO 12 me, 36 mo DMsion Totab:

1993 1995 Median 0.9 1996 0.5 0.9 190 Median 0.9 1995 1.8 1.0 1995 Goal 1.0 Division Target: s 3.0 auto tnps

' PERFORMANCE

SUMMARY

No unplanned automatic trips were reported in March.

e Turkey Point Unit 3 expenenced an automatic trip on February 9th. The 'B' Steam Generator Feed Pump was stopped to monitor e

its discharge check valve closing stroke which dci not strike closed as expected. The resulting feed flow transient caused the "C" Steam Generator level to increase resulting in a turbine tnp which tnpped the reactor. Unit 3's 3-year running average of 0.6 was below the industry median.

St. Lucie Unit 1's 3-year running average of 1.6 exceeded WANO's 3-year running average of 1.0 as a resuk of four tries occumng in 1994 ano one in 1995.

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

HIGH PRESSURE SAFETY INJECTION SYSTEM PERFORMANCE (3-yr Running Average) o.odo e

PTN3 o.035 l - + - PTN 4 i + PSL1 O PSL 2 g

-Inoustry Avg. ~

De M s o.o25

@ o.025 i

'i

} o.o2o o.015 l

l o'. -l

---

.,..g 0 O'O o.005

o. coo MRAlma.! Y 19e1 1802

-1983

'1984 1986 af96

' G/96 afb 6'

• r infB6 4t?Msla 1 0 007 0 Or4 0 007 0 000 0 006 0.008 l

f.W JJ 0.001 0.001 0.006 0.006 0.009 0.009 NE 0.091 0.026 0.017 0.011.

0 025 0.o26

• iP.1 0.011 0.006 0.0 t 8 0.007 0.010 o.009 0 006 0.006 0.010 0.006 0.006 h,

. DEFINITION -

m This Safety System Performance indcator monitors the readiness of the Safety injection (S!) System at Turkey Point and the High Pressure Safety Irjecton (HPSI) System at St. Lucie to respond to off-rcrmal events or accidents. The indicator is determined from the unavailabilities, due to a!!

j causes, of the components in the system during a time period, divided by the number of trains in the system. The definition is further explained:

I m,,&,,st unavaitsuty is the ratio of the hours the cornponent was unavailable (unavailable hours) to the hours the system was required to be available for service. Data is reported on a quarterty basis.

Unavailability = (Known Unavailable Hoursh (Estimated Unavailable Hours)

(Hours System Required) x (Number of Trains)

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE ~

ist O*r 19M 3-vr Ava Endino 396 PTN3 0.006 OM y(yJQ Unavailabilti MN4 0.005 0.009 PSL1 0.015 0.026 1993-1995 Median (PWR) 0.003 0.008 PSL2 0.000 0.009 1995 Goal 0.020 Targets:

E!11 P.E 1995 Y E Target s 0.016 s 0.023 1996 Y E Target 5 0.025 5 0.025

' PERFORMANCE

SUMMARY

• M-*

amm Turkey Point Unit 3's 3-year running average for Safety injection System performance through the 1st Quarter 1996 was below 3

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, SL Lucie Units 1 and 2's High Pressure injection System average performance for 3-years running was higher than the industry i

e median through the 1st Quarter 19M; 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 i

O.5

SAFETY SYSTEM PERFORMANCE - AUXILIARY FEEDWATER SYSTEM (3-year Running Average)

I 0.00 j

0 PTh 3

+

PTN.

- -O-- PSL 1

' - - O - PSL 2

_- nnoustry Avg.

0.030

)

i e

Divmenn Y.F < 0 OX l.

Y 1

1 s 0.020 0.f+.

a l

0 4

m, s

T, V

,,,,....*v 0.010 O

O h

0.000 MWi**e-

1991' -1982 rites' '1994

'1996 iW96 W96

~ SPts 12/96 MMFMS%

0.008 0.025 0.016 0.021 0.014 0.015

• +6 W 0.012 0.031 0.020 0.019 0.011 0.012 h64 0.012 0.030 0.028 0.029 0.010 0.010

.J__

"r*

0 ' '7 0.014 0.012 0.008 0.014 0.013 f.

hi4i

. 14 0.014 0.012 0.012 0.009 as;pi.f 1

This Safety System Performance indicator monitors the readiness of the Auxiliary Feedwater (AFW) System to respond to off-normal l

events or accidents. The indicator is determined from the unavailabilities, due to all causes, of the. components in the system during a time period, divided by the number of trains in the system. This definition is further explained: comoonent unavailability is the ratio of hours the component was unavailable (unavailable hours) to the hours the system was required to be available for semce.

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

(Hours System Required) x (Number cf Trains)

• lNDUSTRY PERFORMANCE STATISTICAL;

SUMMARY

l 1st O! 19M 3-vr Ave Endino 3/96 PTN 3 0.006 0.015 PTN 4 0.007 0.012 WMQ Unavaaabilti PSL1 0.005 0.010 i

PSL2 0.008 0.013 1993 1995 Median (PWR) 0.004 0.009 1995 Goal 0.025 Targets:

EIN ESI.

1995 Y-E Target 5 0.020 5 0.021 1996 Y E Target s 0.025 5 0.025

{

q;e

,_. m ge

.e

.-r Turkey Point Units 3 & 4 Auxiliary Feedwater System performance for 3-years running through the 1st Quarter 1996 was lower e

than the year-end target and higher than tne industry med.an i

St. Lucie Units 1 & 2 Auxiliary Feedwater System performance for 3-years running through the 1st Quarter 1996 was below the e

year end target and higher than the industry medan.

Data Providers: (PTN) Jose Donis 246-6008/ Woody Raasch 246-6527 (PSL) Chuck Wood 467 7034/ Mark Wolaver 467 7083 1

A-6 4

SAFETY SYSTEM PERFORMANCE - EMERGENCY AC POWER SYSTEM (3-year Running Average) 0.030 0.025

=l 0

PTN 3 0.020

+ - PTN 4 k

l--C>--- PSL 1 f

E E.

" 'T

' - O

• PSL 2 0.015 0

~

msW %

g f.

x/3.......... o m

o 0.010 i

o 0

0 005 y..........

Q.**

0.000

'348 3 '<

~SMS P"

isms 4

thes f,' '; Unit ! "'

' Stet 1190e 1983 1994 tites W

7'PTN3-0.001 0.004 0.002 0.003 0.003 0.006

.r& PTN41 0.015 0.001 0.002 0.003 0.003 0.003

• • • TPSL-1 0.013 0.019 0.012 0.010 0.019 0.019 l

0.019 0.006 0.011 0.007 0.012 0.013 j

QMS7 genrymmer 0.017 0.017 0.c20 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 co!Iected at the train level The emergency generator includes subsystems such as air start, lube oil, fuel oil, cooling water, etc. However, for this safety system performance indicator, unavailable hours are counted only when the emergency generator is unavailable to start or load-run. For example, if a component fails in one train of a redundant support system the emergency generator is still operable, and no unavailable hours are counted.

STATISTICAL

SUMMARY

. INDUSTRY PERFORMANCE 1st Otr 1996 3 vr Ave Endina 3/96 PTN 3A&B 0.029 0.006 PTN 4A&B 0.000 0.003 g

UnavailabiMy PSL1A&B 0.006 0.019 PSL2A&B 0.005 0.013 1993 1995 Median (PWR) 0.007 0.012 1995 Goal 0.025 Targets:

EIN ESL 1995 Y E Target s 0.015 s 0.016 1996 Y E Target. s 0.025 s 0.025

-aPERFGulANCE

SUMMARY

/ ' ~4n UEi ~.

4 4

Turkey Point Units 3 & 4 Emergency AC Power performance for 3-years running ending 1st Quarter 1996 was below the year.

end target and industry median.

St. Lucie Units 1 & 2 Emergency AC Power performa ce for 3-years running through the 1st Quarter 1996 was below the year-end target and higher than the industry median for 3-years running.

Data Providers: (PTN) Jose Donis 246-6008/ Jim Freyre 246-6539 (PSL) Chuck Wood 467 7034/ Roger Kulavich 467-7080

THERMAL PERFORMANCE (12-Month Running Average) l 101.0 PTN3 1

- + *PTNA

+ PSL*

\\j

+4-+

... o..pst;

,\\

industry Av;:

1. =

• +,

Dnnsion Y E: 99 5*.

1I p

l C

j h

99.0

, O.

O O

C 3

a

+'

.A.

O

• C5

-O 6

1 97.o

.,.Jalt 4 d

':1991

1982

1983

-1994 1 985 1/96 L2e6 6

4/96

' Sft6

< 4/96

~ 7/96

.8/58.:

t/96

• 10/06 1 1/96 12fB6 5 MS a ;

99.3 99 2 100 4 100.3 99 8 99.8 99.9 99.9

• M4 98.7 99.0 99 7 99.7 100.1 100.1 100.1 100.1 W44.1 L' 99.0 99.3 99.2 99 0 99 0 98.9 98.9 98.9 st&"%d 99.6 99 3 97.8 98.5 98.1 9F.2 98.2 98.2 F'^

~~8 99 2 99.3 99 4 99 4 ' 99.5 DEFINmON Thermal Performance is the ratio of the design gross heat rate, corrected) to the adjusted actual gross heat rate. Gross heat rate is defined as the ratio of total thermal energy produced by the reactor core to the total gross electncal energy produced by the generator during a grven 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).

AdjusMd actual gross heat rate is the gross heat rate attained in the normal equipment lineup dunng one 24-hour period each month, expressed in BTUs per kilowatt-hour (electric) power level should be greater than 80 percent.

- STATISTICAL

SUMMARY

clNDUSTRY? PERFORMANCE M,1 12-Mo Averace WANO PTN 3 100.0'.

99.9%

PTN 4 Outage 100.1 %

1995 Median 99.5 %

PSL1 99.0%

98.9 %

1995 G0a!

99.5 %

PSL 2 99.3%

98.2%

1996 Target (all units): 99.5%

PERFORMANCE

SUMMARY

Turkey Point Unit 3 Tnermal Performance for March 1996 was higher than the year-end target For 12-mo. running average, Units 3 and 4 performance was higher than WANO's 12-mo. running industry average.

St. Lucie Units 1& 2 Thermal Performance for the montn was below the year-end target Performance for 12 mo. running was below WANO's 12-mo. running average.

Data Provioers: (PTN) Jennifer Nicnolson 2464827 and (PSL)Marty Smit 467 7257 A4

FUEL RELIABILITY (Fuel Cycle / Monthly) 1.coE+oo 0

PTN 3

+

PTN4 1.coE.o1

--O-PSL 1 O ' PSL 2 0

%stnr M t$ coEo2 l' n'.

1.

?

O 1.ooE43 Fuel DeM Re'erence 5 OE.04 I I

.51 A.ooE.04 w

v 0

1.coE-o5 1 ooE46

-- ~4 :

O O

c 1.ooEP Cycles r"

,1/98 12fg8 - 73/96

1. 98 5/96 e/96 7t3G

' alB8 SMS 10e6 1126 1a28 bb)ilRnKW Prevlones s.

4 n/glergs a t.

4 4ssa i 44:4 e rosa i.rssa miss4 s cos4 tw4 s ocs4 uwssw.,

a-4 i o.s4

,4 s-4 im.s J,0gnas.4.u aseso 64is4 sirs 4 im.

4 :21 s im4 sais4 fMs.,

t ois.:

stis4 asas4 e sos 4 asas4 i cos4 im4 im4 h3 soosa 1

41 TDEFNTION.

1 This bdcator is defined as the steady-state primary coolant iodine 131 activity (mcrocunestgrarn) corrected for the tramp contributon and power level, and normahzed to a common punicabon rate and average knear heat generaton rate. The indcator value is calculated based on the average of the three monthly values for the most recent quarter of steady-state operabon above 85 percent power. Steady state is defined as contanuous operaton for at least thre? cays at a power level that does not vary rnore than 15 percent.

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

STATISTICAL'

SUMMARY

?

-INDUSTRYi8ERFORMANCE ME Cvde No.

M iQ PTN 3 1.00E-06 15 PTN 4 Outage 1995 Fuel Defect Reference Threshold (PWR) 5.00 E44 PSL1 3.81E-05 13 1994 Median 7.36 E-05 PSL2 1.69E 05 9

1994 Best Quarble 3.00 E46 5.50E 03 4

Dmsonlarget for each unit:

CESUM M Y

,q,r

.7 %.

Unit 3's Fuel Reliability continues to indicate zero fuel defects in Cycle 15. A scheduled refueling outage began on March 4th.

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 hdicate zero fuel defects in Cycle 9.

Data Predder. Modesto Jimenez 694-3323 4

75

1 CHEMISTRY INDEX (12 Months Ending Weighted Average) 1.40 l'06 PTN 3

+ * = PTN 4 1.30

---O-- PsL 1

.O PsL2 Incustry Avg o

g Dmsio9 Y.E. s 1.20,

6..

6 1.15 i

1.0$

$**4.,,

4' 1.co j

Jd -ulaak'a.9 1991 1992 1@83 1994

'1996

146

~246 346

' 4 96' 3 96

-4/06 7/96 846 HG 10f96 1146 12/96 3 ' PINS du 1.10 1.11 1.11' 1 11 J PNit$th 1.04 1.04 1.04 1.o3

%4 M42 1.24 1.20 1.2o 1.18 I

A h;s 1.17 1.19 1.19 1.19 k

M 1.18 Wfa ~

-DEFINmON #

The Chemistry index compares the concentration of seiccted impurities to the limiting values for those impurities. Each impurity value is drvided by the limiting value for the impurity, and the sum of these ratios is normalized to 1.0. The laniting values are the ' achievable values

• defined by intemational industry-accepted values.

• :STATISTICA1.

SUMMARY

sINDUSTRY. PERFORMANCE

, M;g 12.Mo. Endrna Weichted Ava WMO PTN 3 1.00 1.11 (PWR's wth Reorculahng Steam Genera: Ors weout Molar PTN 4 1.11 1.03 Ratio Control)

PSL1 1.10 1.16 1995 Median 1.18 PSL2 1.11 1.19 1995 Lowest Chemistry index Vs!ue Attainable 1.00 1996Targetforeachunit s1.20

,PEREORMANCE

SUMMARY

h u..

_m Turkey Point Units 3 & 4 and St. Lucie Unit 1's Chemistry Index performance for 12eo. running was below the year-end target e

of51.20 and the industry rnedian.

St. Lucie Unit 2's performance was below tne year end target and slightty higher than the industry median.

Data Providers: (PTN) R. Sterike 246-611&' Randy Woodard 246-6810 (PSL) R. Frechette 465-3213/ Dave Faulkne 465-3393 A-10

RADIATION EXPOSURE (3 year Running Average) 4x

-+- PTN l

i --O-PSL L_

'^

350

. Industry Avg.

300 250 Targ t. s

.2 c

y_

m PTN: 3-yr Avg g ;

Target: 5,170.8 j

l'

'M I

50 o

grdgguay,y aget sage 1988

1994 1906 S

W-ta25 445 6

. EMS 745 iWSE : Lems 1046 11/30 1948

.M%

350 332 257 181

.162 182 181 184 M

274 238 193 202 230 229 227g 220

~~l 189 193 193 144 153 l

^ ^ ' ' -

7y~

,mgy,,

Collective Radiation Exposure is the total extemal whole-body dose received by all personnel (including contractors and visitors) coming on site dunng a time penod, as measured by the pnmary dosimeter, thermoluminescent doseneter (TLD) or film badge.

Exposure measured by direct reading dosimeters should be included only for those periods or situations when more accurate data is not available to the utility f om TLD's or film badges. In order to correlate this indicator with the new 10 CFR 20 reporting guidelines, U.S. utilities report deep dose equivalent (DDE) and the total effective dose equivalent (TEDE).

INDUSTRY RERFORMANCE 4

• ?W STATISTICAL'

SUMMARY

-1 3-vr Runnino oer Unit j

I PTN 184~0*

WANO (oer Unin PSL 219.E*

(PWR's ) Median 3.yr Distribubon (1993 1995) 163 Dm..ston Targets:

3-vr. Avg 1995 Median 153 PTN: Y Ethru 1996 s 170.8 1995 W 185 PSL Y-E thru 1996

.s 229.2

• March data ' DRD TLD was not mMe at Wne of pdcaten.

n

'SPERFORMANENMARYr ^ 1 "" ' ' ' '"

H Turkey Point Collective Radiation Exposure for 3-years running through March 1996 was 184.0; performance was higher than WANO's 3-yr. running median of 163.

St. Lucie's Collectrve Rad.ation Exposure for 3-years running through March 1996 of 219.6 was higher than WAN0's 3-yr.

runrung median.

Data Providers:(PTN)Joan Undsay 246-6548 and (PSL) H. M. Mercer 467 7302 4

19

LOW-LEVEL SOLID RADIOACTIVE WASTE (Cubic Meters per unit per year,3-year Running Average) 140

-+- PTN

-C>- PSL 12o

--Industry Av;;. -

100

'E p.

80 c.

U

{

Zi Psl Y-E: 67.5 I

PTN Y E. 55.C 1 40 l'

2o o

Ment..dj 18801-

1982

.1983- '1984 1995 1/06 2/96 " > 3/96 64/96 5/96 8/98 7746 "8/96

'9f86 1996 11/96 1246 4

' 1Pf35 s4 125.3 102.3 81.2 63 4 37.4 36.7 36.2 33.1

'*1 #1pW.WW 1.11.1 103.8 80.7 75 4 53 7 53.3 53.0 54.6 hetaggans %J 86.0 87.0 45.0 46.0 47.0 VMW

' DEFINITION '

This indicator is defined as the volume of low-level solid radioactive waste that has been processed and is in final form (for examp compacted or solidified) ready

• for disposal during a given period. It is calculated using the amount of waste in final form, includin the container, actually shipped for disposal from both on-site and off-site facilities, plus tne change in inventory of final-form waste in storage at both on-srte and off-site facilities.

' in transit to or at disposal site for disposal STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE 3-vr Runnina tnru Mar (oer unit) i WANO Monthly Cu. P l

PTN E1 (2 Unit Soel

{

I PSL 54.6 l

l 3-yr Distribution Median (1993 - 1995) 47.0 l

h Targets.

19N Median 30.0 PTN 1996 Y-E 55.6 cu. mtr. per unit 1 M oal 110.0 PSL 1996 Y-E 67.5 cu. mir.per unit j

l we.-

PERFORMANCE

SUMMARY

~

Turkey Point's Solid Waste Disposal performance for 3-yrs, running was below the year-end target and WANO's 3 yr.

industry median.

St. Lucie's performance was below the year-end target but higher than WAN0's 3-yr. industry median.

e Data Providers: (PTN) Bob Schuber 246-7227 and(PSL) Bruce Somers 467-7305 l

1

4 INDUSTRIAL SAFETY ACCJDENT RATE (12-Month Running Average) 4 f

1.00

-+- PTN 0 90

~

-O-PsL t

' "-Iridustry Av;.

0.80 3

7 1

0.70 5

4 0.60 l

i

/

s 4

2 l

h, 0.50

~

I 8

N 0.40 b

h:

j N o.go

\\

PTNPSL Y-E s 0?

g 020 0.10 l

I C.00

'I OFs Plant s

.1991 1982

.1333

.1004

_1936

.146 r296

.Ses

>47p8 546

tes, 7ms

> ASS

.328 10f86 1146 13f96 MJW5tll'* ?

0.25 0 67 0.36 0.50 022 022 022 0.11 Nh " O 0.75 0.61 0.50 0.51 0 40 0.30 0.30 0.32 N'f 4 0.97 0.77 0.77 0.64 0.55

'H

'DEFINmON Industrial Safety Accident Rate is defined as the number of accidents per 200,000 man-hours worked for all utilny p3rsonnel permanently assigned to the station that rr.sult in any of the following: (1) one or more days of restricted work (excluding the day of the accident); (2) one or more days away from work (excluding the day of the accident); and, (3) fatalities. Contractor personnel are notincluded for thisindicator.

industrial Safety Accident Rate = (number of restncted-time + lost-trne accidents + fatalities) x 200.000 (number of statKm man-hours worked)

STATISTICAL

SUMMARY

INDUSTRYPERFORMANCE jjiLWo -Endina Nar)

PTN 0.11 PSL 0.32 1995 Median 0.55 1995 Goal 0.50 Division Targets:

PTN 1996 Year-End 0.30 PSL 1996 Year-End 0.30

'PERFORMANCE

SUMMARY

Turkey Point's industria! Safety Accident Rate for 12-mc. running through March 1996 was below the year-end target an industry median.

St. Lucie's rate of 0.32 for 12-mo. running through March 1996 was higher tnan tne year-end target but bajow the industry median.

Data Provider W.Korte 694-4235 A.13

_ - ~.

EQUIVALENT AVAILABILITY FACTOR 3

i (Year-to-Date) 100.0 h

j j( +.

..W o-=>oa ' '9e S7 e -

c PTN 3 4

70.0 4

+ PTN 4

---O- - PSL 1

, 60.0

?

• O * ' PSL 2 '

i!

1

• 50.0 g

c.

40.0 i

/

30.0 1

20.0 4

j 10.0 1

0.o f N % 1991 (1902 1983 1994

• 1985

?1/96 2f96 3/06 4/96 8/962

, 8/06.

.7196 18P96

• SfBS ' (1958

.11J88

,1a46 Ar del 22.3 88.3 94 6 83.5 88.7 99.9 83.3 87.4 4

i M 13.9 85.$

81.1 83.1 97.4 100.0 100.0 68.3 6 78.5 95 4 74.0 84.5 75.3 99 6 94.5 94.9 4

M 98.5 73.2 71 8 77.4 72.9 76.8 87.9 92.0

%L DEFINITION Equivalent Availability Factor (EAF) b the ratio of the actual energy production capability to the energ operating at full power for the same period expressed as a percent. Equivalent Availabilrty provides an indcaten o of plant programs and practices in maxirnizing electncal generaten.

EAF% = Available Hours -(Eau' valent Unit Derated Hours) x 100%

r Period Hours

• STATISTICAL

SUMMARY

lNDUSTRYPERFORMANCE Mg Y T-D Y T-D Tarcet 3-vr Run. Av PTN 3 95.4 %

87.4%

95.0%

88.7%

NERC/ GADS PTN 4 6.8%

68.3 %

65.8%

84.6 %

1994 (PWR's) 77.8 %

PSL1 95.8 %

94.9 %

94.8 %

77.9 %

1W (AH types) 74.1'n PSL 2 100.0 %

92.0 %

95.0%

80.5 %

1990-1994 (PWR,s) 74.4 %

Division 74.5 %

85.6 %

87.6%

82.9 %

1

( types) 71.2'a

?L@.Q 1996 Dmson Y-E Target 87.6 %

2 an 80 3 1996 Year-End Forecast:

87.1 %

1. 1. '*9' 70 r-e.SEREORMANCESUMMAREGH&.Meif&h4#G**8 o Major contributors to March 1996 Equivalent Availability loss for the Division was es foHows:

PTN Unit 3: Manual reactor trip due to the loss of the 3B Main Feedwater Pump (34.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />).

e PTN Unit 4: Scheduled miueling outage beginning March 3rd and continuing tnrough the month.

^ PSL Unit 1: Waterbox cleanings (30.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />).

e For the Dmson, Y T-D Equivalent Availabikty was 85.6% which is below the 87.6% targeted through the period.

Data Provider. Sharon Bilger 694-4255 p.t

a CAPACITY FACTOR (MDC NET)

(Year-to Date) 110 0

% -+

0 PTN 3 O

100.0

.. +.. PTN 4 -

j

--O --PSL1

+

90.0

• O - PSL 2_._

' ^

80.0

,0 O'

{

70.0 g

O' 3 60.0 1

l i

25-

/.'

40.0 30.0 20.0 d

10.0 0.0 rtant l'

'1991 1982

-1998

'1984

-1995 s1/96'

. 2t96

3/06

-4/96 St96 8/96 7/96 8/98 aft $

10/96 11/96 1246 MP3ESM 22.5 58 4 97.0 84 8 89.5 103.9 85.7 90.0

'M4T 13.7 79.3 81.4 83.0 99.5 104.5 104.2 71.0 AMM 78.8 96.9 73.9 84.1 75.0 98.8 93.3 94.2 46 101.1 73.7 64.1 76.3 71.9 74.1 87.0 92.0

^

DEFINITION Capacity Factor (CF) is the index of the actual electrical energy produced by the unit with respect to its potential.

Capacity Factor =

Net Electrical Generation X 100 Maximum Dependable Capacity (839 or 666) X Period Hours i

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE j

NERC/ GADS Mal Y T-D 12-rno end.ina 1994 Avg PWR s 76.7%

PTN 3 93.3%

90.0 %

86.4%

1994 Avg AllTypes 72.8 %

PTN 4 6.6%

71.0 %

93.3%

1990-1994 PWR's 72.8 %

PSL1 96.0 %

94.2 %

76.1 %

1990-1994 AllTypes 69.5%

PSL2 101.7 %

92.0 %

70.9 %

g Dmsson 75.7 %

86.8 %

81.7 %

1995 Median 81.1 %

1995 Average 77.9 %

i

~ PERFORMANCE

SUMMARY

j l

Major contnbutors to March 1996 Capacity Factor loss for the Division was as follows.

PTN Unit 3: Manual reactor trip due to the loss of the 3B Main feedwater Pump.

PTN Unit 4: Schedpled refueling outage beginning March 3rd and continuing through the month.

PSL Unit 1: Waterbox cleanings l

=

Data Provider: Sharon Biloer 694-4255 n~

I PTN FUEL UTILIZATION FACTOR Turkey Point Unit #3, Cycle 15 Turkey Point Unit #4, Cycle 15

)

500 45o Planned Refuenng Date Ma en 8,199' 450 Planned Refuenng Date March t 1996 I

et,% -

400 M ***-

400 -

Revised Date: Matn 4,1996 epg[l

/,

i d$

g 35o.

1 { 350 -

n i

W.

}b f

n, 300-d*

] f 300 -

M1 M4

~

g g250-

, y$ og,,,.

o

$ 20o.

200 -

t y

e b 1$0 vg4 150 -

3 too.

100-1

+

50 -

50 -

j D

0 0-

~

- PTN 83r s Oct

. 06ov i. Dec-Jan

- Fet tier.

- Apr.

Assy !Jun

. -Jul

'Aug

Sep Oct

.- Stor sDec

.h

Feb. ' 4Aer Plannes M+

5 35 66 98 127 158 188 219 249 281 312 342 373 403 435 466 494 501

<ActusM:

18 47 78 109 128 157 J

Varlenee(4/4 '-

13 12 12 11 1

1 trusses 7m t@tenand %

4 34 64 91 121 150 180 209 239 269 298 328 357 387 417 445 446

< PfJAsheat44ft 13 42 73 101 125 155 186 215 246 276 306 337 366 397 428 457 459

{

~ WWhnee(4%4 9

8 l 9 10 4

5 6

6 7

7 8

9 9

10 11 12 13 DEFINITION Fuel utilizaton plots the amount of nuclear energy used during the current fuel cycle. The amount of nuc6 ear energ core is expressed in effective full power days (EFPD). One EFPD is the equivalent of operating the reactor at maximum thermal rating (2200 at PTN or 2700 at PSL) for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. Planned energy is compared to actual energy used during th utihzation is directly related to plant performance. The signifcance of variance EFPD(+/-) is the difference between planned actual energy consumption. Fuel utiltzation can be used to project longer or shorter operating fuel cycles.

Actual Energy / Calendar Days = Fuel Utilization Factor Fuel Cycle Operating Assumptions EltL2 in accordance with the April 26,1995 Approved Operating Schedule (AOS) Unit 3, Cycle 15 is scheduled to run 496 ca:endar days (October 27,191,5 to March 8,1997) with design eneray to run 501 (EFFD) days.11QIE: Due to the 34-cay ou2ge, startJp began on Occer 7,1995,20 days earher the planned.

PTN 4: Unit 4, Cycle 15 ended on March 3,1996.

' /7ERFORMANCE

SUMMARY

F ""~~" ' "

Unit 3 achieved a Fuel Utilization Factor of 93.69. and operated for 697 effectrve fun power hours in tne month of March. For e

the period October 27,1995 to March 31,1996, the Fuel Utilizaton Factor was 100.0%

Unit 4 operated for 51 effective full power hours in the month of March. For the penod of November 27,1994 to March 31, e

1996, the Fuel Utihzaten Factor was 103.0%

Data provider: Jrnmie Perryman 694 3330

~,

J l

i PSL FUEL UTILIZATION FACTOR l

St. Lucie Unit #1, Cycle 13 St. Lucie Unit #2, Cycle o 500 450 -

Ongina! P:anned Refueleg. Apri' 8.19E 4$o.

Planned Refueang oate: Apni 15.1997 Revised Date: Aoni29.1996 y

400,

{

400 -

35o-m w

E 300 -

E j.

g.

250 -

250 -

k

'5 o 200-0 200-i R

E 150 -

t$o 100-100-1 go.

So..

o o

gg,ggi */

Ider "Dec i,Jan

-feb M ar

• Apr-Afar

'Jun

., Jul - "Aus

-Sep

' Oet.

480sv, 4mo h

>Feb'

.8Aar Apr Nh

• o 11 41 68 98 127 158 187 217 247 276 306 335 366 396 423 453 est Ah%

29 60 86 109 139 170 199 227 227 227 244 271 302 331 357 387

^ _ ^

18 19 18 11 12 12 12 10

-20 49

-62

-64 64 65

-66 66

' ^ ^

& M.n.

,,1, 6,,,,,2Ls,,,,,,2,47,,,,,g6,,,,gg6,,,,,,,gglL,,,,3ll6,,,,,3,g,,,,,,gg,,,,4,,5,,s,,,,,,3a,5,,,,5g0,,

-l

,,,j,,,5,L, e

E' 5

5 g6,L,,,,,,j!L,,,,,gs,L,,,,12,6,L, 0

0 23 52 83

5

2!L. d' fL dl DEFINmON Fuel utilization plots the amount of nuclear energy used dunng 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 I

rating (2200 at PTN or 2700 at PSL) for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> penod. Planned energy is compared to actual energy used during the cycle. Fuel utilization is drectly related to plant performance. The significance of vanance 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 / Calender Deys = Fuel Utillastion Fector FuelCycle Operating Assumptions E.SL,1: In accordance with the October 28,1994 Approved Ooerating Schedule (AOS), Unit 1, Cycle 13 was scheduled to begin i

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 is currently scheduled to refuel April 29,1996.

NQE Per the revised AOS dated February 8,1996, the unit will shutdown 21 days later tnan previously scheduled.

ESL.2 in accordance with the April 26,1995 AOS, Unit 2, Cycle 9 was scheduled to begin operation November 24,1995. This provided for a cycle of 508 calendar days with design energy to run 500 EFPD. Unit 2, Cycle 9 actually began operation January 5, 1996 and is currently scheduled to refuel April 15,1997.

}

<pd%:Qn

-udR,w-M ggggggyhpw % w M%

Unit 1 achieved a Fuel Utilization Factor of 95.8% and operated at 713 effective full power hours in the month of March. For the period of December 20,1994 through March 31,1996, the Fuel 061ization Factor was 83.2%.

Unit 2 achieved a Fuel Utilization Factor of 99.4% and operated at 740 effective full power hours in the month of March. For

~

the period of November 24,1995 through March 31,1996, the Fuel Utilization Factor was 64.5%.

Data previoer. Ruben Rodriouez 694 3345

--.,.----n--. - -.

a

.-,-n u

. __ =_.

.~...

l FORCED OUTAGE RATE (Year-to-Date) 30.0 PTN 3

- - + PTN 4 25.0 I

O-PSL2 _

9 d

li f

20.0 q

4 1

e l

F Y'

15.0 l

)

8 l ',

. '..\\

10.0 s

~

' o '.\\

/

O, s.0

,/

,'., g

?

4 0.0 0

, - Unit ix

!$991

<1992 1993 1994

-1995 1/96

2/96 396 4/96 5/96 6/96

-7/96 456 9/96 s10f96 11/96 12/96

..PT183 4 1.2 15.6 1,8 1.9 0.5 0.0 11.8 9.3

'.tPIBI4 6

' I.S 13.2 2.0 3.9 1.5 0.0 0.0 0.0 j

• W E.*f45 1.2 3.5 2.1 3.9 21.8

• O 44 2.9 (N.

0.0 8.1 23.5 2.3 2.4 3

34 2.2 1

a DERNITION j

]

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

to tha grid. Thrs type of outage usually results from immediate mechanicaVelectricaVhydraulic controls systems and operator-i initiated trbs in response to unit alarms.

Forced Outage Rate Forced Ousaae Hours x 100%

l.

Forced Outage Hours + Service Hours 7 STATISTICAL

SUMMARY

' INDUSTRY PERFORMANCE -

Mgr Y T-D 12 Mo Endin NERC' GADS PTN 3 4.6%

9.3%

3.1%

1994 (PWR's) 8.1%

PTN 4 0.0%

0.0%

1.5%

1994(Alltypes) 10.6%

PSL1 0.0%

2.9%

22.0 %

1990-1994 (PWR's) 7.6%

PSL 2 0.0%

2.2%

2.0%

1990 1994 (M types) 10.8%

SM@m eg.o;PERFORMANCE

SUMMARY

""~C"'

'"'~FF 7

Turkey Point Unit 3 Forced Outage Rate of 4.6% was the result of a manual reactor trip on March 27th due to the loss of the 3B e

Main Feedwater Pump.

Data Provider Sharon Bilger 694-4255 p.<

a

4 3

4 L

UNPLANNED AUTOMATIC TRIPS WHILE CRITICAL

}

(Year to-Date) i 5

0 PTN3

- + PTN4

--O-- PSL1 a

4

.. o..pst2 i

Dmsron Target: s3 3

4 mk I'

O 2-

[

^

{

/ ',

/

1 0

^

0

?

?

1

/

l l

0

. unit "

1991 1982

'1993

'19M 1985 1J55 att 2 96 4det gi/98 Alt $

7/t6 i Sles r

arts 1efes 11/ps la46 A1PEISJ 0

0 0

1 0

0 1

1 bMe 0

1 1

2 0

0 0

0 I

%M 2

1 0

4 1

0 0

0 M

0 1

0 1

1 0

0 0

DEFINmON An Unplanned Automatic Scram is a non-manual actuation of the reactor protection system that results in a scram signal any time the unit is critical. Scrams that are planned as part of special evaluations or tests are not included in this definition. This indicator t

provides an it'dication of success in improving plant safety by reducing the number of undesirable and unplanned thermal-h1"jraulic l

and reactivity transients requinng reactor scrams.

4 1

i STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE jfal Y-T-D 12-Month Endina WANO Trios per unit PTN 3 0

1 1

Tnps per 7000 Cntical Hours PTN 4 0

0 0

3-yr Distribution Median (7/92-6/95) 1.0 PSL1 0

0 1

1994 Medisn 0.8 PSL2 0

0 0

1995 Goal 1.0 Division Totat 0

1 2

fiBQ (1995 3rd Ott Performance indcator Rpt)

QuarterlyTrips Annuahzed 1.0 1996 Division Target s 3 Quarterly Trips per 7000 Critical Hours 1.2 e.

n.e ?.w.44 peppy,

No automate trips occurred in March 1996. Year-to4 ate. one automatic tnp has been expenen,. n Turkey Point Unrt 3 expenervxd an automatic tnp on February 9th; tne "B" Steam Generator Feed Pump was stopped to rnonitor its discharge check vahre closing stroke which did not strike closed as expected. The resulting feed flow transent caused the *C" Steam Generator level to increase resulting in a turbine tnp wh'ch tnpped the reactor.

Data Providers: (PTN) J. Knorr 2464757 (PSL) K. Korth 467 7054 n/

OPEN PWO'S 2.500

-e-PTN

-O-- PSL 2.000

\\

g 'sw r

x c

1.000 s00 o

- Una : w 1991

1992 1983 1994 1995 1/96 2/96 T96

1. 96 5/96 6/96 7/96

-4/96 9/96 1046 11/96 1846

' PT90 a ^

1.466 1.589 1.441 mpse m

1. sos i.s20 2,030

, j,,,

DERNITION This indicator includes Work Type 1 (Planned Miscellaneous), Work Type 3 (Projects), WorkType 5 (Trouble & Breakdown) and includes all hold codes, status 22 through 48.

' Histede data not meaningful Prior to 1996, each site was counting Open PWO's differently. St. Lucie was counting only Work Type S nonautage conectue and Turkey Pornt was counting Work Types 1 and 5. Each site now agrees to report per the aoove definition.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE -

1 i

l l

PERFORMANCE

SUMMARY

Data Pmviders: (PTN) Greg Heisterman 246-6796 and (PSL) Joe Marchese 467 7107 C-1

PWO AGING CURVE 1200 PTN Actua'

- + PTN Goa!

1000

--o-- PSL Actual O

PSL Goa!

800 "e

O o 600 h

y 400 6

.g, 0

o1-6 9'

12-Over12

• v'thalt. *

• TOTALS-e PTBt Accuel.~

1050 524 244 117 17 0

N emi 525 263 132 0

0 1016 641 200 82 65 29 M,7 500 254 127 64 32 DEFINITION PWO Aging curves includes Work Type 1 (Planned Misc) Work Type 3 (Projects) and Work Type 5 (Trouble & Breakdown),

and excludes short notice outages (SNO), HC2 Startup, HC3-Hot Standby, HC4-Hot Shutdown, HC5-Cold Shutdown, and HC6-Refueling This only includes status 22 through 48.

Goal: To halve the 'udeklog every three months.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE i

PERFORMANCE

SUMMARY

Data Provde s: (DTN) Gres testerman 246-6796 and (PSL) Joe Marchese 467-7107 r.?

PWO'S GREATER THAN 12 MONTHS (GOLDEN OLDIES)

TURKEY PONT REF ' PWO#

PWO TITLE Orig. Date l Wks en List 1

95000527 P-4498 REPLACE WITH ROSEMOUNTl/P 01695 2

95001652 CV 33729. VALVE FAILED OPEN (AWP ENG HOLDS) 01/1395 3

95005744 CV 343478. VALVE LEAK $

01/20S5 4

95005514 HSC-3-151. BRITTLE / CRACK INSUL ON WIRES (AWP HOLD) 01!27/95 5

95005513 HSC 3152. BRITTLE / CRACK INSUL ON WIRES (AWP HOLD) 01!27S5 6

95006234 40210. MOTOR SIGHTGLASS LEAXING OIL 02n0S5 7

95006427 VARIOUS DOORS THROUGHOUT PLANT, INSTALL DRP FLASHINGS ON DOORS 0101S5 B-95006428 D096-1 DOOR. WATER INTRUSION 03/01/95 9

95007509 HAGAN CONTROLLER. 35V REG MEASURES 30.7 03/10/95 10 95007510

%GAN CONTROLLER. 35V REG MEASURES 53.2 1

031095 ST.LUCIE REF PWOs PWO TITLE Orig. Date Wks on List 1

92052114 SCREEN CORRODED FALLING APART, SAFTEY 1G%92 2

93032089 COMPLETE UPGRADEOF COMPUTER SYSTEM 12/1/93 3

94025159 REPLACE VALVES REMOVE DRIP PAN.

10/454 4

94025159 REPLACE VALVES REMOVE DRIP PAN.

1(y17S4 5

95000079 ASSIST MECHANICAL MAINTENANCE 113/95 6

95001003 INSTALL LEVEL INDICATOR FOR POOL LEVEL 1/1185 7

93034478 OVERHAUL SPARE HVS 1 A MOTOR-2/10/95 8

95004447 REBAR IS RUSTED AND CONCRETE IS CRACIC N 2A4/95 9

93034478 OVERHAUL SPARE HVS-1 A MOTOR.

32745 PWO Greater than 12 month's, Work Types 1 tnrough 5, exduding ottage hold codes (SNO, SNW, HC2, H Data Provost (PTN) Greg Hetsarman 2466796 (PSL) Joe Marcuse467 7107

l NON-0UTAGE PWO'S 1

14o0 1200

-+-- PTN _

-O-- PSL 1000 O

g soo 8,

I 800 430 200 l

o j'cMQ 11081'

'1982

1983

,1004

.1988

' t/96 aft $

.3/96

4/96 5/96 eft $

7/96

! aft $'h tfB6 itW96 11/96 12f98 M d1 1024 1001 1118 Em ir47 isos tois

' DERNITION :

Non-Outage PWO's includes Work Type 1 (Planned Misc) Work Type 3 (Projects) and Work Type 5 (Trouble & Breakdown), ar.d

, excludes all outage hold codes. Short notice outages (SNO), HC2 Startup, HC3-Hot Standby, HC4-Hot Shutdown, HCS-Cold

~ Shutdown, HC6-Refueling and includes status 22-48.

Historic data not meaningful. Prior to 1996, each site was countrng Open PWO's differently. St. Lucie was counting only Work Type 5 noneutage corrective and Turkey Point was counting Work Types 1 and 5. Each sne now agrees to report per the above tiefinihnn.

- STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE PERFORMANCE

SUMMARY

Data Provice s:(PTN) Greg Hersterman 246-6796 and (PSL) Joe M 1 hese 467-7107 r2

CONTROL ROOM INSTRUMENTS OUT OF-SERVICE a

60 1

-+ - PTN C

' PSL J

50 1

e j

g O

j March Outage Tags PTN 12 (Unit 3 only. Unit 4 in g

40 g

4 refuehng outage)

PSL 10 o

E m

30 N

O E

8 N

l 3

20 0

8 i

]

I 10 4

O VMbW 119M 1982 ettes: Mete

199t> l t1JWs ists

345 d445' ;sts' tems' J7 Jus'-.;4ms? ; ems-.1WB6 11/96

.1346 1

4PM!ae.

r 39 40 42 12 I

OMM 54 46 25 20 l

J q

DEFINITION t

This indcator defines the number of control room instruments for each unit that cannot perform their design function, j

regardless of the reason. Instruments on the control room back panels are readily available for use by the control room crews i

and are included; however, instruments in adjoining areas where operators are not normally staboned (such as computer j

rooms) are not included. Count deficiency tags that are in status 05 to 48.

i STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE 1

i JPERFORMANCE

SUMMARY

~~

A correction has been made to PTN data for Year End 1995 and January. The data reflects the corrected numbers.

Data Provide s: (PTN) Greg Heisterman 2466796 and (PSL) Joe Marchese 467 7107 r.$

1 OSHA RECORDABLES (Year-to Date) 40

^

35

' --+-- PTN

--o-PS L y 25 n

h 20

^

m 15 10 5

C.Y 0

', IUset -

1991 1992

'1993 1994-1995 1/96 2/96 3/96

1. 98 5/96 M

728 8/96 948-10f96 11/96 12/96 wesp4tl 4.4*

35 33 33 27 17

• )

1 2

L4rMWKc 20 15 19 23 25 3

3 4

- DEFINITION

~

The definition by Occupational Safety Health Administration (OSHA) is an injury occurring on the job that requires medica!

treatment beyond first aid as defined by 29 CFR 1904.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Month yT-Q PTN 1

2 PSL 1

4 Nuclear Division Y-ETarget 1.75 Corporate Y-E Target 3.75

'.s_._..

a.

. ~ : PERFORMANCE

SUMMARY

One OSHA Recordable injury was reported at Turkey Point a mechanic was swinging a sledge hammer and caught his finger between tne handle and a shacide causing a hairline e

fracture to the finger.

St. Lucie reported two OSHA Recordables in March; a mecharse w holding an elephant trunk to remove smoke from an area where another mechanic was bumrig off bol's on e

a damper. He was in a cramped area and his coveralis ignited causing 2nd degree bums to his cam.

A SNPO injured his knee in sanuary and was placed on resmeted duty. An MRI in Maren revealed a tom ligament in the knee.

Data provider. W. Korte 694-4235 e

D' a

4 i

LOST TIME INJURIES i

(Year-to-Date) s

=

i' i

l

-+- PTN l

l -O-PSL i

i 2

C,

l' i 'l

/

/

i

.E i.

e.,.

j j2 l

l l

o W

_ Unit "

i1991' test 1983 1984 19e5 1/96 af98 2#36 4ft6 25#85 8#98 7#36 846 l 946

'1&B5

'11/B6 12f96 PT98 0

0 0

1 0

0 0

0

{

UNW 2

4 3

1 2

0 0

0

]

DEFINm0N A Lost Time injury as defined by Occupational Safety Health Administration (OSHA) is an occupational injury tnat requires an employee to miss a full day (8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shift) beyond the day of injury.

< STATISTICAL S'JMMARY INDUSTRY PERFORMANCE Montn Y-T-D PTN 0

0 PSL 0

0 PERFORMANCE

SUMMARY

No Lost Trne injuries were reported in Mar:h 1996.

Data provider: W. Korte 694-4235 D-2

REGULAR STAFFING FPL Employees and Long-Term Contractors by Department Turkey Point

+ Azal 1050

-O-- Pianned 98o.

966 SSE z

C 3

E 950 -

9d 95 900 St. Lucie 1100 f 1050 t.cy 1.oso 1

1.c22 b

1000 -

2 t.ct;

, 1.010

. 1.cii E

950 -

1 900 Engineering & Licensing 400

{

3* -

>n

.s.

)

200 -

E 100 -

l o

Nuclear Assurance 150 ice toe toe 1C3 104 104 50 -

0 Nuclear Operations 32 32 32 i

30 C

C-2 r

3-at x

20 -

z E

10 -

0 Nuc6eer Businees Servlees 11 11 11

'l C

C 3

$g.

10 10 10 i

5 5-5 0

l Sies - l aos { <.ses l 4ns l - ses :l ses. ) "7ms l ens.l tesc l ~ 1 ems l - 11ms -l Sans l Data Provider: Ahcia Simpson 694-3275 Data Source: ND Stathng Report n3

OPERATOR EXAMINATION PERFORMANCE Turkey Point Units 3 & 4 saa m.

1,

f I E RO/SRO Pass 'e

!D Oper Reg Pass 'e e

t.

r g - 7 y

95.0 %

g.

y 4

n 7

k h

5 90.0*/.

E y

1 i

4 85.0 %

4 l

l s

l

' Emiserl.;i i dS$1 riget 1993 1994 1995 1/96 42/96

1. 3/96

@ 96

< 8/96 4/96

.7/06 '

• W96 e 9/96' 1996 11/96 12/96 t ritof9Apfeben e 39 5

8 13

. c wpagagg;c*r-39 5

8 13

". - _ Za*'

100 0 %

100.0%

100 0%

100.0 %

!.aeswM' 47 78 69 63 58 64 NW7M 44 75 66 60 56 64 roper 6 94 0 %

960%

96 0%

95 0 %

96 5 %

100.0 %

DEFINm0N i

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

Operator Requalification Examination results are reported for both RO's and SRO's. This examination is administered annually by l

the utility and may be jointly administered by the NRC. Retests of operators who failed examinatens are not included.

1 STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Intual RO/SRO Ucense Exams l

No Taken No Passed Pass Rate %

The NRC at their last Regional Training Managers Meeting l

YTD 1996 0

0 0.0%

(for fiscal year 1994) provided the following data:

l YTD 1995 13 13 100.0 %

MM NRC Exams NRC Raoual Exams RO's Pass Rate 94.6%

RO's Pass Rate 91.0%

rade@alh instant SRO's Pass Rate 94 4 %

SRO's Pass Rate 85.0%

No. Taken No. Passed Pass Rate %

Upgrade SRO's Pass Rate 94.7%

Average Overall 88.0%

YTD 1996 64 64 100.0%

Average OveraH 94.6 %

VTD 1995 58 56 96.5 %

~ PERFORMANCE

SUMMARY

No Initial RO!SRO License or Operator Requalification Exams were given in March 1996 at Turkey Point.

Data pro # r. K. E. Beatty 694-4217 i

l E-1

• .i l

OPERATOR EXAMINATION PERFORMANCE St. Lucie Units 1 & 2 a

100.0 %

i E RO/SRO Pass %

1 D Oper Reg Pass %

95.0 %

l I

y 90.0%

8 l

E I

e5.0%

l I

i 80.O*l.

j R493ssumm3 M3

.3991: #199a i.1983. :1994 f1996 PJt6 J2fB6

' 3/96 ' '4/96 6/96 6/96

'7/96'

?4f96 i Sf96 '. 10/96

,11/96 12/96 l

e 15 8

10 11 l

C_--'-^~2 15 8

10 11

- ~ _ 100 0%

100 0%

100 0%

100 0%

1 65 69 68 75 73 I

a v_ ! 7 - ~~ "4m 61 60 68 68 71 e4 0%

s70%

100.0 %

910%

e7 5%

4 1

i DEFINITION t

{

inrDal License Examination (RO/SRO) resu'ts are reported for all candidates taking an initial License Exam as conducted by the i

NRC.

j Operator Requalification Examinaton results are reported for both RO's and SRO's. This examinaten is administered annually by i

the utility and may be jointly administered by the NRC. Retests of operators who failed examinabons are not included.

2 STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE inital RO/SRO License Exams N

amen RegionaNining Managers Meetng No Taken No. Passed Pass Rate %

0 r Escalyear 19% pmme foDoeg dat YTD 1996 0

0 0.0%

YTD 1995 0

0 0.0%

weame Exams NRC A*a Exm RO's Pass Pam 94.6 %

RO's Pass Ram 91.0%

Operator Requal Exams tratant SRO's Pass Rate 94.4 %

SRO's Pass Ram 85.0 %

No. Taken No Passed Pass Rate %

Upgrade SRO's Pass Rate 94.7%

Avarsge Overall 88.0 %

YTD 1996 0

0 0.0%

Average Owall 94.6%

YTD 1995 73 71 97.5 %

7 m,y,y. '

~^

• ~

'PERFORMANCE

SUMMARY

'~ ~

Nc Operatur Requalification Exams were grven in March 1996 at St. Lucie.

Initial RO/SRO License Exams were given to be given in March; results from the NRC are expected in April.

Data provider. K.E.Beatty 694 4217 t- -

OPERATOR EXAMINATION PERFORMANCE j

Turkey Point Units 3 & 4 io w.

h I E RO/SRO Pass '.

10 Oper Reg Pass %

95.0%

N - h (C

k 1,

[

g i

4:

4

{ Ooo%

Q 1

8 A

E k

Q.

-lh j

j l

t 8s.0%

h-l

\\

h

}

f to o*'.

^

f a dtminas:Tj 81991

,1981

'19%

.1994 1996 1/96

2/96

1. 3/96 4/96

,6/90 r 6/96 7/96- '846 9/96' 1496 11/D6 1246 u nofBROfstanc-39 5

8 13 u wmuenessee.

39 5

8 13 l

, 6. _i T ^^^2 100 o %

100 0%

100.0%

100 0%

j camperm 47 78 69 63 58 64

• 4WM 44 75 66 60 56 64 cour nadamuse, e4 o%

se os 96.0%

es o%

se 5%

100 os DEFINITION 4

l Initial Ucense Examinaten (RO/SRO) results are reported for all candidates taking an Initial Ucense Exam as conducted by the NRC.

j Operator Requalification Examinaten resutts are reported for both RO's and SRO's. This examinaten is administered annually by 4

the utility and may be jointly administered by tN NRO. Retests of operators who failed examinations are not included.

STATISTICAL.

SUMMARY

INDUSTRY PERFORMANCE 1

initial RO/SRO Ucense Exams No Taken No. Passed Pass Rate %

The NRC at their last Regional Training Managers Meeting

[

YTD 1996 0

0 0.0%

(for fiscal year 1994) provided the folicwing data:

YTD 1995 13 13 100.0 %

3 Inthat NRC Erams NRC Raoual Exams

]

RO's Pass Rate 94.6 %

RO's Pass Rate 91.0%

Operator RequalExams Instant SRO's Pass Rate 94.4 %

SRO's Pass Rate 85.0 %

No.Taken No. Passed Pass Rate %

Upgrade SRO's Pass Rate 94T4 Average Overall B8.0%

YTD 1996 64 64 100.0 %

Average Overall 94 6 %

1 YTD 1995 58 56 96.5 %

t i

' PERFORMANCE

SUMMARY

I No Initial ROSRO Ucense or Operator Requalificaton Exams were given in March 1996 at Turkey Point.

Data provider K. E. Beatty 6944217 E-1

OPERATOR EXAMINATION PERFORMANCE St. Lucie Units 1 & 2 i

100.0 %

)

4 E RO/SRO Pass *e i13Oper Reg Pass *.

j 95.o%

4 l

90.0%

E 85.0%

80 0 %

M 4AsemencMiG

$991

'19Ba. '1903. 11994

'1995 1/96

.2/96

'3/96 4/96

' 5/96 : : 6/96

• 7/96

• 4f96 ' !$$$1 10/96

_11/96 12/96 15 8

10 11 i

6.__

anb 15 8

10 11

~ ^ ' ^ ^

100 0%

100 0%

100 0%

100 0%

'^ --

65 69 68 75 73 e i. - 7 " "N3:

61 60 68 68 71 V;,-^^ T 940%

87 0%

100 0%

91.r'%

97.5 %

e DERNITION Inroal Ucense Examinaten (RO/SRO) results are reported for all canoidates taking an initial Ucense Exam as conducted by the NRC Operator RequalifK,aton Examination results are reported for both RO's and SRO's. This examinaten is administered annually by the utility and rnay be jointly administered by the NRC. Retests of operators who failed examinatens are not included.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Initial RO/SRO license Exams The NRC at their last Regional Training Managers Meeting No. Taken No. Passed Pass (for fiscal year 1994) provided the following data:

YTD 1995 0

0 0.0%

g,,, yqe g,,n,,

gqe p _,gx,m, RO's Pass Ram 94.6 %

RO's Pass Rate 91.0%

Operator Requal Exams instant SRO's Pass Rate 94.4 %

SRO's Pass Rate 85.0%

No.Taken No. Passed Pass Rate %

Upgrade SRO's Pass Rate 94.7%

Average Overall 88.0%

YTD 1996 0

0 0.0%

Average Overall 94.6 %

YTD 1995 73 71 97.5 %

PERFORMANCE 3UMMARY ^

~

y.., _

No Operator Requalification Exams were grven in March 19% at St. Lucie.

Initial RO/SRO Ucense Exams were given to be given in March; resuts from the NRC are expected in April.

Data provider: K. E. Beatty 694 4217 t-

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

.m......

m... _ -.

1 j

OVERDUE CONDITION REPORTS f'

100 l

--+- PTN 90 c>., pg. -

80

\\

}

70 E

ch I.

$ 60

!The CR process was wripternentec on e

64!1/96 at PSL Ah existing STARS as of f

j that cate wW be processe as CRs.

t 50 -

O

therefore, the 51 STAR s over 30 days old ias of 4'1 are now conseereo overoue.

I 40 g

I e

30 h

i ao 10

/

0 4 ;(JudtQ >

1991

1982 1985

'1994 19M 1/96 2ft$

' aft $ D a4fB6

! 996 ' -' SfB6

7/06 MG'

'GS$

10f96

'11/06

,12/96 i

- -L1MJ'A 6

0 0

12 wp3,. ' a 95 25 51 l

DEFINITION -

~~"

f Currently, the Nuclear Division is transitioning to a consistcat Condition Report. The project is scheduled to be completed by May 1, 1996 at all locations. This graph shows Condition Reports that exceed assigned prionty timeframe.

Seventy Levels are as follows:

A = 3 working days B = 10 calendar days C = 30 calendar days STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE PERFORMANCE

SUMMARY

~~'

Data f5mdatr (PTN) Juho Balaguero 2466971 and (PSL) Bob Dawson C/ 7154 F-1

l 1

QA FINDINGS 20

-+- m -

j

-O-PS.,

a Juno Tre scue m Ja amt nrongs coen :21-15c -

\\

15 asys is oue to re cmventy et reams ine large meume of Arnngs resulong from fne Matenats Maw aut r

i

g e

\\

3 io,

5 l

z 5

c o

2 648nt -

0 30 :

- 31 80 61-90 91 120 121-150

151-100

'N-0 1

0 0

0 0

vvPR;,

1 o

4 o

3 o

I o

0 o

5 17 0

J ch

• a.,.

DEFINITION -

This indicator represents the time it takes for verification of implementation of correctrve action for audit findings. The clock for the OA group starts when the audrted organization notifies OA that implementation of audit finding correctrve actons are complete and ready for verifcaton. The process is complete when OA closes the audit finding and notifies the auded organization that tne audit finding corrective acton is complete.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE l

i j

PERFORMANCE

SUMMARY

Data Pmvides (PTN) Tom AbbatMiho 246-6581 and (PSL) Wes Bisoow 467 7111 v.:

i NRC VIOLATIONS Cited and Non-Cited 1

l.

(Year-to-Date) l

)

22 T

f 0

PTN NOVs

[

+ PTN NCV s l

18

+ PSL NOVs j

- O PSL NOVs 16

/,<

i j

j 14 I

\\\\

- C 12 t

\\ '.

I:

1 o,n t

s

^

8 4

I 1996 Y E Target: 5 7I

\\

^.:

i 4

^

b f

O C>

O

\\

o ::of;>o o

i j

itankthi

1991 1992 1983 1994 1996 1/96 2f96

'3f96

1. 96 6/96 af96 7/96 GP96. *W96 10P96 11/96

.12/96

• PF18 8 ems ?

13 8

4 4

1 o

o 1

"PTId SIEMe t 21 7

13 12 15 o

1 3

'iPSL 9dOW's :

E 8

7 9

21 o

o 4

I I

TFSt.8N Wa.1 3

3 3

3 12 1

1 1

\\

C DEFINITION t

Violations are categorized in terms of five levels of severity to show their relatrve importance. Severity Levels I rd 11 are violations j

that involve actual or high potent:al imoact on the public. Severity Level lli Violations are cause for significant concem. Severity Level 1

IV violations are less serious, but are of more than minor concem; i.e., if left uncorrected, could lead to a more serious concem.

Severity Level V violations are minor safety or environmental concem. Violations are counted on the date of the inspection exit meeting. Violations are now counted with respect to the date of occurrence (using the date of the inspecbon exit meeting) instead of the date of the inspection report, as was done in the past.

STATISTICAL

SUMMARY

'lNDUSTRY PERFORMANCE l

M;Lr Im Year End Tat,et NRC Violations 1994 IBG Group Mean 16.2 PTN Cited 1

1 7

1994 Region 11Mean 13.1 i

PTN Non-Cited 2

3 1994 IBG Top Quartile Mean 9.0 PSL Cited 0

4 7

1994 Region ilTop Quartile Entry 8.0 PSL Non-Cited 0

1 4;g y WS:. u e.

N ePERFORMANCE

SUMMARY

" ' # "'~

Turkey Point reported one NRC Vdabons for March:

1. 9642-04:Failurs to meet requrrements of 10CFR50.71(e) in that the FSAR was not appropnateY updated to reflect the officed of a full core dunng a refueling evolubon. Exit Meetng date: 379/96.

St. Lucie reported no NRC Violacons for the month: nowever, tour violations were reported for February:

1

1. 964141: Temporary Procedure enanges were made which involved changes of intent, witnout pnor FRG rewew as reouired by Technica!

Specifcanons. Ent Meeting Date 2/20/96.

1. 960101: ' Operators failed to follow procecses for boron dducon. Exit Meetng Date: 2/8/96-c%CS02: ' Inadequate design control of RCS boron diluton procedure. Exit Meetng Date: 2/5/96.

1. 960303: 'InadegJane 50.59 safety evaluaton of chang 1 to toon dilution procedure. Exit Meeung Date: 2/8/96.

'On April 1 St. Luoe was informed tnat tnese wotabons represent a Seventy Leallit problem for Unit 1 only. A Civil Penalty of $50.000 was emposed I

Data Proeders: (PTN) Garv Hollinoer 2466078 and(PSL) Ed wer*am 467 7162 F-3

t LICENSEE EVENT REPORTS l

(Year to-Date) 25 i

--+- PTN

' + PSL 2o

?

5 i

e y 15

\\c L

r i

2 i

w,o i

N 3

5 0

^

l 0

%d M G J1981 1992

.1983 1984 s1995 ftJ95 225.

2 56 4 85

SdB5

.645-7J98 Ja95' WBE.

.1 afb 6 11/98 1246I

sMr to 24 9

12 7

1 5

5 F- ^

9 10 8

15 18 1

5 5

l 3

DEFINm0N-4 -

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

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE ME XID PTN O

5 PSL 0

5 PERFORMANCE

SUMMARY

n

-e">

No LER's were reported in March 1996 Dan PnMdas (PTN) Gay Hokger 24640'T8 and (PSL) Ed Wer*m 467 7162 F.!-

INPO ASSESSMENT RATINGS 5

4 50 4 00

.WPTN g

3 50 C DS-3 00 '

2.50 e

I k 2.00 iE i

,30 t oc

-===--

==

~~~

i Ild 4

0 00

<thdt 1986 1987 1680 1989 1990

- 1991' 1992

'1993

-1994 199s l 1996

yyyN, 42 4.00 3 00 4.00 3.00 2.0c 2.0c 0 00 i

..sper.t <

2 00 im t0c im 4

INPO ASSESSMENT PROGRAM DESCRIPTION d

i The Insttute of Nuclear Power Operat: ens (INPO) conducts penodic evaluations of s.'te activitres to make an overall determination of plant j

safety, to evaluate management systems and contrais, and to idently areas needing improvement. Informabon is assembled from discussions, interviews, observations, and reviews of documentation.

t 1

Evaluation Frequency: INPO's goal is to visit each plant on an average of every 18 rnonths. However, this frequency may vary depending i

upon the previous assessment ratings. For instance, if a plant is rated a *1* or 7, the interval between assessments is usually 20 24 l

months; if a plant is rated a '4' or a '5", the assessment interval is s 18 months Performance Catecorv Ratnes:

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

Category 2: Overall pertermance is exemplary. Industry standards of exe:.ience are met in most areas. No significant weaknesses noted.

Category 3: Overall pertormance is generally in keeping with the high standards required in nuclear power. However, irnprovements are

'needed in a number of areas. A few significant weaknesses may exist.

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

Category 5: Overall performance does net meet the industry standard of acceatable performance. The margin of nuclear safety is measuraDiy reduce 1 Strong and immed: ate management accon to correct defcencies is required. Special attention, ass: stance, and followe are reouired.

RQ.IE:If a plant is found to be operating without an adequate margin of nucear safety, INPO wSI request that the plant be shutdown, or not started up.

PERFORMANCE

SUMMARY

Turkey Point and St. Lucie recerved an INPO category rating of *1' in 1995. The next evaluations for Turkey Point and St.

Lucie are expected in tne last quarter of 1996 and first cuarter of 1997, respectively.

Dati Pmdeer (PTM Ga'y Hennger 246-6078 and (PSL) Ed Weinkam 467 71f.,2 F5

l NRC SALP CATEGORY RATINGS 1

I 2.50 1

4 iE PTN Rating 5

2.00 -

6 O PSL Rating f

E 1.50 -

E i

e i

S N 1.00 0.s0 0.00 -

t

-tdma>n

1 998 ?

.19874

-1988 ;

• 1989 +

' d 990,

11991 "

,1992 J.1993,

r1994*

-1995-s1996 i 4

1 PTNItueqe*, W %

2.27 2.18 2.25 2.14 1.86 1.38 1.38 129 1.00 4/30/86 5/31/87 6/30/88 7/31/89 7/31/90 9/28/91 1/3093

& 27/94 PuremeEsiinimal

+

1.50 1.00 1.00 pet.fteeng M W-1.55 1 20 1.29 1.14 5'2/92 1/1/94 1/6/96 perteemmeng MS; 4/30/86 1 &31/87 4/30/89 10/31/90

%T-SALP PROGRAM DESCRIPTION a a ein patcy of gie NRC to use me Systemetr* Assessment d Lcensee Panormance (SALP) process to attoJate tre egencys 6 -. and risghts on kersee sarry Jettormanc The SALP report commtrecates thcme observanons and sagts EYalLebGD FfaGJefrr The NRC wil ncrmarf renew and evaluate each power reactor konsee Irat possettes an oceranng hcanse at naast every 18 nute When the NRC de the portramance wanants a more treguent evaluanon, the normal SALP frequency mey be ratased. The assessmet penod tray ta enended to a rnammum d 24 months eoeives a Category 1 ranng n aR four luncnonal areas.

Ftrema! Areas Performance a generah evaluated miour(4) tunencmal areas:

1. Rars Ooeranons This funcoanal area consists crue ty el the ccntrd and execunon d actmbes drecoy related e operatmg a piart R rduces actmbes such as piant startup. power r

operators, plant shutdown, and system kneups. It also scudes runal and requaldcanon trammg of kansed operators.

2. Maintanarum. Ths funcbonal area ecludes all actmbes assocated with other degnosec, pngktmi, prevensve. or correctrve martenance d start snuctures. systems. and componen or mamtenance et the styscai ecndnan of the plant

3. Enceiserane. Ths tuncnonal area accresses the adea.acy of techrscal and engneenng seport for el p' ant actmees it reuries as hcensee acambes =anr==* with dese cored.

l oesgi, ristalianon, and tesang al peart modificanons: engneenng and iscrrical succort lor openitions. outages macionance, tesang. survetance, and pro:uremera acavees.

1 conhguraeon managemenc cesgNass reormanas and as removat and scoort for bcenang actmoes.

4. Plant.'anxnt. Thrs tuncnonal area covem all actmoes related e peart support luncDons. indudng radolopeal controls, emergency prepartmess. seoJrtty, chemessy, and tre Housekeepmg ccrters ani arso rouced m this a ea.

Pe%nce Er=wv Pe: Licensee performance m eacti luncnonal area a assessed by assgung a category ranng as dscussed tiect Category 1. Lcensee attenbon and myolveme it have been DT0efty facMsed on safety and resulted m a supenor level of safety peftermance Cavgory 2. Lrensee a!!ennen and riververnent are normady neilocsaed and resumed m a good evel of salmy pertarmance Category 3. Lcenset attennon and entcsvement have resulted e an accettable leve of periormance However, per oma ice muy euhtet one or trofe of the following chara r

rs!!acave programs and agrdcant r aues. lack of comicove acnos thercugnness. and cetoenoes e root cause analyss. Because ine margn e unacceptasie perfo rreertart asoects a smeA. increased NRC and bcensee atterson a recuired.

PERFORMANCE

SUMMARY

Tunury Port St Lucie Pnor Most Recent Pner Most Recent Funcbonal Area:

Plant Operations 1

1 1

2 Marttenance 2 tmproving 1

1 2

Engineenng 2 Improving 1

1 1

Plant Support na 1

1 1

Emergency Preparedness 1

rva rva rva Radiological Centrots 1

rva rva rVa 1

rva rva rVa Secuntf Self Assessment / Qualty Vertficaton 1

GA NA 6A Overa'!

1.29 1.00 1.00 1.50 Da a Provide r (PTN) Gary Hourger 2464078 and (PSL) Ed Wer*am 467 7162 F.6

INVENTORY VALUE ACCOUNT 154.300 12o

-+-- PTN 100

_o pgt p 80 3e U

b C

~

N 0

1996 Y E Target s 38 (SM) l I 2o 0

JF ^^ - "" t(Wla ASR 48803'

.1304 JOSE, %_h;

]im 'emalm/t ^ dm., g iges R W :,1140'W M 8 g

T:^

_ __, 79.1 74.7 54.6 42.4 37.4 37.4 37.2 36.0 wrahi.] $8.6 65.2 60.2 43.7 39.5 42.0 42.3 43.5 1

DEFINITION This indicator reflects the valve of Account 154.300. This account reflects materials needed to keep operational the physical equipment and facilities of the plant (e.g., spare parts, consumables, commodrues, tools). The information is pulled from SAR Report #G0009R72-501. The Passport system utilizes SAR for system data reporting.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Staa End

% Chanae YE Taraet IBG (Year 1994)

'T.gta!

Average

$43.6 Million PTN Monthly 37.2 36.0

-3.2%

Top Quartile Entry

$34.7 Million Y-T-D 37.4 36.0 3.7% $38M Top Quartile Average

$28.9 Million PSL Monthly 42.3 43.5 2.8%

Y-T-D 39.4 43.5 10.4% $ 8M

'Value does not include Capital as defined by PRUC 3

A.] ; :. -

4 PERFORMANCE

SUMMARY

u n

4 Turkey Point Regular Inventory decreased 1.2M in March.

St. Lucie's Regular inventory increased by 1.2M for the month.

Data Providers: (PTN) Dick Rose 246-6692 and (PSU Tom Kreinberg 465-4183 G-1

OPEN PLANT CHANGES / MODIFICATIONS (PC/MS) 350 i

1

' -+-- PTN 300

-O-PSL l

l i

250 1

i

.* 200 h

c 8,

O 150 i

100 1

l i

1 0

l 1198L 41002 J8m8 2004.;1998. +1788.<;;W5S

1ftS

<#56.

05f96, 24#38 87 TBS _ m4

,346 1988 19148

.'1998 240 242 230 4

4 N

316 326 269 i

DEFINmON -

i This indicator tracks the total number of PCMs in the engineering department. The purpose is to provide management a snapshot of the number of PCMs. Includes all jobs that have been approved by plant management, and are in design, j

operabiltty review, or implementabon phases. The PCM is consioered open until System Acceptance Tumover Sheet (SATS) l and drawing update is complete.

i; STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE f

Desian Review y&rigr!2 Vodate 191a1 PTN 74 14 70 72 230 PSL 42 52 81 94 269

~-

~ -

wfEPERFORMANCESUAW St. Lucie has excluded tne Steam Generator Replacement Project PCMs which accoents for 20-30 PCMs. The increase of PC'M's in Review is due to the upcomng PSL1 outage preparation.

Data Preders: (PTN) Am Reed 24&6903 and (PSL) Kris Utndr00 467 7482 S1

- -....... -. ~.... -. ~.. - -.... -,-

l' CONTAMINATED FLOOR SPACE

+-+-Pn

. --O-- PSL 4

5 a

4000 L

3 2000

/

1000 0

~~M steet; +Z: i a000s-,.teet,, Jess 9tigt:.

rafts., sage: ;Af964.W. Mt UFSSy h 78f563 4858, 11JOS' 43ft$'

6 6+

1750 50 330 700 3748

__-W 5610 4351 4600 2848 1480 250 280 12 DEFINmON This hdicator, designed to rrtsre cor$alminated floor space with removable activity 21000 dpm/100cm sq. beta / gamma or 2 20 dpm/100cm sq. alpha, is c>unted against the base. Areas that can be specifcally exemp;ed 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 wak or step on).

PTN: Total Base (117,746 sq. ft.) Exemoted Arg (6,110 sq. ft.)

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

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE ME liLf9fd PTN 3748 50 -

PSL 12 50

.. ~

PERFORMANCE

SUMMARY

Turkey Point increase of Contaminated Floor Space is the result of Unit 4 outage in process dunng March.

(

Data Pr:mdem: (PTN) John unosay 2466548 and (PSL) Hank Buchannon 467 7300 1-1

.___m.__

M i

OPEN TEMPORARY SYSTEM ALTERATIONS i

i 25 i

-+-- PTN

)

14 out of 21 TSA s are

-O-PSL t iretated to Unit 1 and will oe f iremoved pnor to tne unit i

}

20 retuming from tne retueirng~

ou' ace i

j 5 15 b

i V) l 10 g

1 5

5-

^

o JE spees- :tese

tees tesee- :,sses ' :vas

ssa, 1sas w mes. e m

' ass-fees: sees 1m assa 6

5 2

3 N rm 17 15 16 21 DEFINITION A temporary system a:ieration is a modification made to plant equipment, components, or systems that does not conform with i

approved drawings or other design documents; a modification that is necessary for continued safe plant operation; a modifcation that will remove a nuisance or distraction to the Plant Operators; a modifcation necessary to enable the plant to start upin a safe manner.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE ME Year End Goal PTN 3

5 PSL 21 10 PERFORMANCE

SUMMARY

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

.r

DRY ACTIVE WASTE: GENERATED, SHIPPED OFFSITE (Year-to-Date) 14000 l

0 PTN Generated

<2000 g

.. +..PTN Snoped

-O-- PSL Generated

-o PSL Sn:cce:

10000 l

,8 8000

~

l I

4000 7

1 '

i 2000

" 4 1

0 0

Ir the& '- l 1981 1 992 1983 1994 1995 ilt6 2/96 3/96 4/96 S/96 6/96 7/96 8/96 9/96 10/96 11/96 12/96 FWeesemmend a l 8100 425 515 3925

~*2"I 2560 0

0 0

i

"'~ -

11740 1040 1860 2065 13003 0

2080 3322 V '~

DEFINITION Generated is an estimate based on the number of ' yellow bags" initially generated prior to surveying for free release or shoment as radwaste.

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

Shiooed offsite The amount of dry actrve radioactive waste tnat FPL mes to either Scientihe Ecology Group Inc. (SEG) or Amencan Ecology Recycle Center (AERC) for processing.

l 1

^

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE PSL made 6 shipments to SEG in 1995.

PTN made 3 shipments to SEG in 1995.

l l

l l

l

-- +:ww

. PERFORMANCE

SUMMARY

1 I

PTN projects to ship 5,120 cubic feet in 1996.

Year-to-date, PSL has shipped 3,322 cubic feet of 1995 outage waste.

e J

l oatarm _ oe m e ome5.n e m a eS o., m eo.

l l

i

e PERSONNEL CONTAMINATION EVENTS (Year-to-Date) 18o

+ -+- PTN 160

_cp_ pg,,

140 120 k

^

100

!c i

Y E

60 40 2o O

o

[ifi$

-.M '

ifWt. fM 4W1 M' 11 TBSP Wr taf5S: tW, SSW1 Mf985 Wi*WWh"#WW 8'!19W !

11/DS M E--

_r' 163 85 95 100 73 4

9 23 M'*?"

87 76 84 82 0

2 2

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 and 2100 counts per minute (net) using the Friskeris observed.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Mit H-Q PTN 14 23 PSL 0

2

• j "'

PERFORMANCE

SUMMARY

1 Data Providers: (PTN) John Lindsay 246-6548 and (PSL) Hank BuchannOn 467 7300 j

13 l

RADIATION EXPOSURE (Year to-Date) 1000

-+- PTN Y T D _

j

> -o-PSL Y-T-D i

\\

y 700 600 I

s PSL Y E TaIget: 485 i l

^

E 5N s\\

A 400 0

3 N

PTN Y E Target: 275 I I 200

/

1x

+

- B M.thiRe,j': 4001 198R. 4 908 1994 (1995,.M

2 08

!Sf88 6448

'846

045, ~728 1888..448 10fB6 1146 12f96 M,1@

938.0 324.9 281.8 476.2 214.6 5.3 9.5 153.9 M '.&

451.3 244.5 4599 504.7 412.8 3.0 9.0 13.7 i,. '-

4DEFINm0N '

Collectrve Radiation Exposure is the total effective dose equivalent received by all on-site personnd (including contractors and visrtors), it includes extemal deep dose as measured by the thermoluminescent dosimeters (TLD's) plus intemal dose.

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

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE -

m

~

Mt B

iTD Taraet 12-M1 Endina it PTN 144.4' 153.9 225.0 353.5 WANO (PWR's)

(two units)

PSL 4.7*

13.7 33.0 382.6 1995 Median 306 1995 Goal 370 Year-EndTargets:

PTN: 275.0 PSL: 485.0

.iPERFORMANCE

SUMMARY

T

.a..

Turkey Point's performance Y-T-D was below the Y T-D target; performance for 12-mo.'s ending of 353.5 was higher than the industry median in March.

St. Lucie's Man-Rem Y T-D was below the Y-T-D target; performance for 12-mo.'s ending totaled 382.6 which is higher than theindustry median.

Data Providers: (PTN) J0nn Undsay 24H548 and (PSL) Hank Buchann0n 467-7300

' DRD count I-4 L

4 Q

O&M BUDGET - DIVISION (Year-to-Date) 350.o

--*-- Actual

• * *

• Bu0get 250.0 4

~

.i.r 200.0 j

)

81s0.0

.l 100.0 b

f s0.0 0.0 li.c + ^ m

=mv me i es seu ms im ms mes es was

.ams am s es nos sou sim swes i

I h aA2 342.4 2952 290.6 2852 269.5 13 4 31.2 67.4

^^ -SA 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 1

l mt 2.7

-s2 11.0

-s.s 3.5

-24.9 14.9 11.1

)

&We-

.' DEFINmON' Operating and Maintenance Expenditures include Nuclear Drvision operation and maintenance expenses associated with j

direct employees, contractors and consuhants, equipment, tools, design, engineering and other items / activities required to sustain the electrical generabon of the plants and to provide required support. Fuel costs, corporate administrative and general expenses, and charges from other departments outside the Nuclear Dtvision are excluded.

Y-T-D Actual Exoenses Y-T-D Budoeted Excenses x 100% = O&M Variance %

Y-T D Budgeted Expenses STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE '

O&M Bud 0et j

Y-T-D Actual ($M)

Y-T-D Variance ($M)

IBG Actual 1994 Avg.

$297.0M i

IBG Top Ouartile Entry

$270.0M Jan '96 67.4 ($M) 8.4 ($M) 11.1 %

IBG Top Ouartile Avg.

$213.2M i

Jan'95 45.8 ($M)

-8.4 ($M) 15.6 %

IBG Projected 1995 Avg.

$284.0M 1

l 1996 Y-E Budget 252.8 ($M)

Protechon (per dual unit site) denved by trending 1986-94 1

Actual data and 1995 Budgeted data for IBG Group.

i sh.s

- ?PERFORMANCE

SUMMARY

.e O&M Expenditures through March 1996 were $67.4 million which represented a budget underrun of $8.4 million (or 11.1%).

The variance was the result of: St. Lucie Unit 1 outage schedule change; St. Lucie non-outage project underruns; and overtime payroll underrun associated with Turkey Point Unit 4 outage.

?

Data provider: T. O. Nasby 694 4188 1-1

i l

CAPITAL BUDGET - DIVISION (Year to-Date) g 180.0 -

!---9--- Actual i......googet 140.0 l

\\,',,

120.0 3g f 100.0 80.0 i

60.0

.~

~

20.0 0.0

%"*l$%,Tpff,2' 41est 1902 1983

.1984 1906 1/96 2f58 3f96 4/98 SdSS 4 4fBS -

WBG GSE eSS 1848 11/06 12ft6 150.7 68 4 90.3 76.5 47.2 1.5 2.5 2.9

~ ~ ~ " "'

f__

179.6 75.1 101 4 87.7 64.7 48 7.1 11.1 15 7 17.9 19 8 22.6 26.3 27.8 30.1 33 1 392

_[

16.1

-9.0 11.0 12.7 27.0

-67.6 65.0

-73.7 DEFINITION I

Capital Expendr..res are those direct / incurred / budgeted by the Nuclear Division for the construction of new u additions and improvements made to increase efficiency, reliability or safety. Capital fuel costs are excluded.

Y T-D Actual Excenses - Y-T-D Budaeted Excenses x 100% = CapitalVanance %

Y T D Budgeted Expenses STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE CaoitalBudoet YT-D Actual ($M) Y-T-D Variance ($M)

IBG Actual 1994 Avg.

$63.1M IBG Top Quartile Entry

$28.3M Jan '96 2.9 ($M)

-B.2 ($M)

-73.7%

IBG Top Quartile Avg.

$21.1M Jan'95 6.0 ($M)

-4.B ($M)

-44.2%

IBG Projected 1995 Avg.

$58.5M 1996Y EBudget 39.2($M)

Projection (per dual unit site) denved by trending 1986-94 Actual data and 1995 Budgeted data for IBG Group.

{

. PERFORMANCE

SUMMARY

ti;.*

Capital Expenditures through March 1996 were $2.9 million which represented a budget underrun of $8.2 millio

)

The vanance was pnmarily due to: underrun in Steam Generator Replacement Project (SGRP) reflecting a revision to the SGRP outage start date, St. Lucie Unit 2 Reactor Head Seal Ring Replacement Project determined to be O&M; and concebed projects.

Data provider. T. O. Nasby 694-4188 J.2 l

C \\

• i INTERNAL DISTRIBUTION:

R. J.

Acosta JNA/JB R. J.

Hovey PTN/ PLT j

T. V.

Abbatiello PTN/ PLT D. E.

Jemigan PTN/ PLT j

K. E.

Beatty JNO/JB H. H.

Johnson PTN/ PLT L. W.

Bladow PSUPLT V. A.

Kaminskas PTN/ PLT W. H.

Bohlke PSUPLT T.

Kreinberg PSUPLT G. J.

Boissy JN0/JB H. N.

Paduano JPN/JB J. B.

Brady CC/JB J. G.

Pizzutel!!

JNE/JB J. L.

Broadnead JEX/JB T. E.

Robens JPN/JE 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.

Smitn JPN/JB D. J.

Denver PSL/ PLT R. A.

Symes JNA/JB M. S.

Dryden JNUJB C.

Villard JPN/JB P. L.

Fincher PSUPLT W. E.

Walker PSUPLT J. C.

Hampp ETS/JB E.

Weinkam PSUPLT J. R.

Hartzog PTN/ PLT D. H.

West PSUPLT R. G.

Heisterman PTN/ PLT J. A.

West PSUPLT G.

Hollinger PTN/ PLT R.

West PTN/ PLT EXTERNAL DISTRIBUTION:

W. R. Corcoran W. Kleinsorg 21 Broadleaf Circle Nuclear Regulatory Commission i

Windsor,CT 06095 101 Marietta Street N.W., Suite 2900 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