ML20137M212

Monthly Indicator Rept, Nov 1996

ML20137M212
Person / Time
Site:	Saint Lucie, Turkey Point, Barnwell
Issue date:	12/17/1996
From:	FLORIDA POWER & LIGHT CO.
To:
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References
FOIA-96-485 NUDOCS 9704080034
Download: ML20137M212 (172)

Text

4 l

FPL NUCLEAR DIVISION TURKEY PolNT NUCLEAR STATION ST. LUCIE NUCLEAR STATION 4

i MONTHLYINDICATOR REPORT NOVEMBER 1996 l

o$$["8*

d P

issued: December 17,1996 40 4 970401 I

BINDER 96-485 PDR

o Florida Power & Light Company, P.O. Box 14000, Juno Beach, FL 33408-0420 f-f:PL JNE-NBS-96-291 December 17,1996 i

Mr. Kerry D. Landis, Region II Nuclear Regulatory Commission 101 Marietta Street, Suite 2000 Atlanta, GA 30323

Dear Mr. Landis:

Enclosed is the Nuclear Division Monthly Indicator Report for November 1996.

I

1. L. Wade Director, Business Services RLW/skb Enclosure cc: W. Kleinsorg l

an FPL Group company

l 1

-=t,

TABLE OF CONTENTS ForsunW I

D.

PERSONNELINDICATORS Talde of Contents -

ii OSHA Recordables.

D-1

":: 7 -.::.; Summary iii Lost Timeinjuries D-2 Nuclear Division Business Plan Indicator Overview v

Regular Staffing D-3 NRC Indicator Performance Overview Turkey Point vi NRC Indicator Performance Overview 8t. OW vii E.

TRAININGINDICATORS CANO Indicator Performance Overview viii Opwator Exam Performance - Turkey Point.

-.. E 1 CANOIndicatorVariance Explsch ix Operator Exam Performance - St. Lucie...

E-2 A.. WANO INDICATORS F.

NUCLEAR ASSURANCE & REGULATORY INDICATORS WANO Weighted OverallPerformana--

A-1 Overdue Conditon Reports --

.F1 Unit Capability Factor...

A-2' QA Findings......

.... F 2 '

Unplanned Capability Loss Factor...

A-3 NRC Violabons: Cite and Non-Cited....

-F-3 Unplanned Auto Trips Per 7000 Hours Critical....

A-4 List of Notice of Violations F-4

, High Pressure Safety lnjechon System Performance A-5 Ucensee Event Reports (LERs).-

F-5 Auxiliary Feedwater System Performance A-6 INPO Assessment Rahnge F-6 Emergency AC Power 5.ystem Performana.

A-7 NRC SALP Category Ratinga

=-

F-7.

ThermalPerformance-

.. ; A-8 Fuel Reliability..

A-9 G.

MATERIALSINDICATORS Chemistryinday A-10 inventory......

G-1 Radiation Exposure....

A-11 Low Level Waste..

A-12 H.

TECHNICAUENGINEERING INDICATORS Industrial Safety Performance...

A-13 Open Plant Changes /Mcdifications...

H-1 Open Temporary System Alterations H-2 B.

OPERATIONSINDICATORS Equivalent Availability Factor B-1 L

RADIATION PROTECTION INDICATORS Capacity Factor (MDC Net)..

B-2 Contaminated Floor Space. -.

.... 1 1 FuelUtilization (PTN)-

B-3 Dry Active Waste: Generated, Shipped Off. Site -

l-2.

Fuel U;ilization (PSL)..

B4 PersonnelContamination Events -

l-3 Forced Outage Rate B-5 Radiation Exposure (Y.T-D) -

l-4 Unplanned Auto Trips...

B6 J.

BUSINESSINDICATORS C.

MAINTENANCE INDICATORS O&MBudget Division J-1 Open PWO's....

C-1 CapitalBudget Division -

J-2

-m PWO Aging Curve--

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

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

C-4 APPEND (X Control Room instruments Out of Senna......

C-5 Distribution Ust...

...Z-1 ii

.t MANAGEMENT

SUMMARY

OPERATING PERFORMANCE:

Equivalent Availability Factor performance in November was as follows.

Turkey Point Unit 3. Unit 3 operated at full power in November, Y-T-D EAF was 94.9% which is slightly below the Y-T-D target of 95.0%.

j Turkey Point Unit 4. Unit 4 achieved 100.0% EAF for the month. For the year, EAF was 86.6% which is higher than the Y-T-D target of 80.9%.

St. Lucie Unit 1. EAF for Unit 1 was 98.8% in November. Power losses were the result of: repair to 1 A TCW Heat Exchanger (8.2' hours) and Heater Level Control System (0.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />). EAF performance Y-T-D was 69.0% which is below the 77.0% Y-T-D target.

St. Lucie Unit 2. Unit 2 essentially operated at full power in November; EAF for the month was 99.8%.

Power losses of 1.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> were attributed to testing of the Control Valve (0.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />) and Turbine Valve (0.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />). Y-T-D EAF was 94.4% which is s:,,ntly below the 95.0% Y-T-D target.

Nuclear Division. Equivalent Availability was 99.7% for the month and 86.2% Y-T-D which is below the 87.0% targeted Y-T-D. The year end forecast for the Division is 86.9%.

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

A summary of key plant operating statistics is summarized below-i PTN Unit 3 PTN Unit 4 PSL Unit 1 PSL Unit 2 Month Y.T,D Month Y-T-D Month Y-T-D Month Y T-D Gross Generatson (MWh) 541.566 5.471.275 542.161 4.864.859 635.420 4,872.760 638.060 6,717,580 Net Generation (MWh) 517.871 5.211.622 518.528 4,627.933 603.328 4.593,848 605,351 6.358.273 Net Heat Rate (Btu /KWh) 10886.1 10994.8 10886.1 11176.3 10849.5 11047.7 10931.9 10937.1 Equivalent Availability 100.0 %

94.9 %

100.0 %

86.6 %

98.8 %

69.0%

99.8 %

94.4 %

Capacity Factor 103.8 %

97.0%

103.9 %

86.1 %

99.9 %

68.1 %

100.2 %

94.3 %

Ado Tnps 0

1 0

0 0

0 0

0 Forced Outage Rate 00%

36%

0.0%

0.4%

0.0%

31%

0.0%

3.1%

b lii i

l

w MANAGEMENT

SUMMARY

+

REGULATORY PERFORMANCE:

Turkey Point.. No Notice of Violatons (NOVs) were reported in November; year-to4 ate, three NOVs have been reported.

St. Lucie. Two NOVs were reported in November for October.

1. 96-15 Failure to Control M&TE. Exit Meeting date: 10/18/96.

+

F15 06 - Failure of HP to Have Procedure In Hand During Realignment of Unit 1 Containment Radiation Monitor. Exit Meeting date: 10/18/96.

Year-todate, St. Lucie has reported 25 confirmed and 14 potential NOVs. (See Page F-4 for list of

. con rmed NOVs).

fi 4

i.

- COST PERFORMANCE:

- O&M Expenditures through November 1996 were $262.4 Million which represented a budget overrun ovenun of $0.4 Million or (0.2%) against the revised budget. Variance is primarily due to St. Lucie Unit 1 outage scope changes offset by transfer of the Turkey Point Thermal Uprate Project from O&M and by project and materials purchase cancellatons.

Year-to-date, C&M budget performance variances are stratfied as follows:

Turkey Point Site Spec!!ic

$15.6 Millon or 14.8% belowbudget St.Lucie Site Specific

$21.9 Million or 21.5% above budget Other Nuclear Division

$5.9 Million or 10.9% belowbudget Capital Expenditures through November 1956 were $23.5 Million which represented a budget

. underrun of $9.6 Million or (29.0%). Variance is pnmarily due to:. plant projects cancelled / deferred /or reclassified as O&M; and, an underrun in the Steam Generator Replacement Project (SGRP).

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

. Turkey Point Site Specific

$2.8 Million (or 68.6%) below budget St. Lucie Site Specific

$3.6 Million(or 14.1%) below budget Other Nuclear Division

$3.2 Million(or 89.6%) below budget

. iy

'b$

l NUCLEAR DMSION BUSINESS PLAN INDICATOR OVERVIEW y

l (Through November 30,1996) 1996 1996 1996 YE YTD YTD INDICATOR Ptar TARGET TARGET AcTUALs COMMENTS Collective Radiation Exposure PTN 5 275.0 5 270.0 185.3' Turkey Point and St. Lucie were below YTD Man-Rem targets.

PSL 5 485.0 5 476.0 383.8'

• Currentmonthincluoes DRD count PTN 1.00 y]

1.00 For the second consecutive time, PTN received superior NRC SALP Ratings

%Q ratings (1.00) in all areas for the SALP period ending 8/17S6.

PSL 1.50 TM 1.50 The next SALP penod for PSL is scheduled for March 1997.

h(h 3

PTN reported no NOVs in 11/96; 3 have been received Y-T-D.

'I PTN

$7

%{!

25 PSL reporlod two NOVs in 11S6 for the month of 10/96; Y-T-D, NRC Violabons PSL

$7 5

PSL'nas received 25 confirmed and 14 potential NOVs.

PTN3 53 WE?j 1

Unplanned Automatic PTN4 for hh 0

No unplanned automatic trips were reported in November.

Trips PSL1 Division <M/

0 PSL2 0

Budget Performance Capital 39.2 33.1 23.5 Capital Y-T-D actuals were below the Y-T-D target.

($ Millions)

O&M 292.3 262.0 262.4 O&M actuals slightly exceeded Y-T-D target primarily as a Div. Total 331.5 295.1 285.9 result of PSL's outage scope changes.

PTN3 95.0 95.0 94.9 PTN Unit 4 performance Y-T-D through November was EquivalentAvailability PTN4 82.0 80.9 86.6 higher than the Y-T D target.

Factor (%)

PSL1 78.5 77.0 69.0 For the Okision, EAF Y-T-D was 86.2% which is below PSL2 95.0 95.0 94.4 the 87.0% Y-T-D target.

Divmon 88.0 87.0 86.2 M&SInventory Levels PTN 5 38.0 34.1 PSL exceeded the Year-End target of $38.0 by $0.5M in

($ Millions)

PSL 5 38.0 #d 38.5 November.

Production Cost (O&M PTN 1.75 1J7 1.71 PSL Production Costs ((/KWh) were higher than -

l 5 and Fuel)

PSL 1.55 1.57 1.95 Y-T-D targets in November.

Total Cost (O&M, Fuel &

Division in November Division Total Cost ((/KWh) was higher CapitalCanying Costs)

Total 4.56 4.61 4.80 that the Y T-D target.

Nuclear Dmsion FPL 2045.0 A,

1820.0 Total Nuclear Division Staffing Level was below the Staffing Levels LTC 463.0 m

329.0 Year-End target.

z Total 2508.0 2149.0 Refueling Outage PIN 3 0

J 0

Refueling Outages are scheduled as follows:

Duration (Days)

PTN4 45 35 PTN3 3/3/97 PTN4-9/8/97 PSL1 63 88 PSL1 - 10/20/97 PSL2-4/14/97 PSL2 NA 0

Approved Operating Schedule, dated 11/18S7 LostTime Injunes per 200,000 PTN 0.30

• y 0.28 No Lost Time injuries were reported in November.

Hrs. Worked (12 Mo. Running)

PSL 0.30 0.26 V

i t

l

NRC INDICATOR PERFORMANCE OVERVIEW for Turkey Point (Data through Quarter Ending September 30,1995) o LEGEND rrN 3 g Plant Self-Trend Deviations From Peer FTN 4 Short Term Grovo Median Lona Term OPERATIONS t>eclined Improved Worse Better i o.o Automatic Scrams While Cribcal Iom 422 51 cD l 0.0 Safety System Actuations co 100 c.45 g 0.0 Significant Events 08 104 4.30 027 g Safety System Failures 4 30 10.0 CAUSE CODES (all LER's) 4.u 5 4.06 m Administratne ControlProblem I c.o

.o11gj om

-o ta g Ucensed Operator Problem c.o i o.o 0.0 0.72 Other PersonnelError o.o ioo

-0.14E o.42 Maintenance Problem 0.14 lF i o.o Design /Construebon/Installabon Fabrication Problem oo M o40 4

ob lob Miscellaneous eo I o.o SHUTDOWN g o.ta as4l SafetySystem Actuations c.D o.78 gwS,ifraM o.o' O.o I Significant Events 40 4.57 0.51 o33 4

Santy System Failures

_ 2.40 0.37 CAUSE CODES (all LER's)

,uv o.n Administrative ControlProblem 430 ~

west 025 i c.o o.01 Licensed Operator Problem '

030 M 406j o.o o 17 3 Other PersonnelError o.o El o.10 Maintenance Problem El o.10 I c.o 0.03l Design /Construebon/Installabon Fabncation Problem M -090 o 06 5 10.0 joa Miscellaneous ieo ieo FORCED OUTAGES l 0.06 l 0.04 Forced Outage Rate

• ll o.05 4m3J oM jo07 Eouipment Forced Outages /1000 Commercial Hours

• pagHD26 o37 l4tuur 10

-0.5 00 0.6 1.0 1.0

-0.5 0.0 0.5 1.0

• Not Calculated for Operationa! Cycle Performance Index Performance Index NOTES:

Plant SeN-Trend Short Temt Based on the slope of a knear regression kne placed over each plants data. Time intervals used in the trends are 4 Quarters for 'Operattnns' and

• Forced Outages

• indcators and 6 Quarters for ' Shutdown

• indcators.

Decatons fon Peer GrouD Median Lena Temr Compansons are made of each plant to the performance of its peers over a 12 Quarter tme intervat Pear Grour PTN 3&4 - Older Westnghouse 3-Loop.

Vi

NRC INDICATOR PERFORMANCE OVERVIEW for St. Lucie (Data through Quarter End!ng September.30,1995)

LEGENo Plant Self-Trend Deviations From Peer Short Term Group Median Lonc Term Declined imprved W rse Better OPERATIONS Ion M

l Automabc Scrams While Critical Eo18 Safety System Actuations ioo 030 MusESt$l 0.0 0.0 Signdicant Events os ch oD E 022 Safety System Failures 02 lWWagl 0.67 CAUSE CODES (all LER's) i 0.00 0.45 Administrative ControlProblem M[430 oss pam om m 022 Ucensed Operator Problem ioo agammessio.es i

o 64 ob Other PersonnelError ioo M o12 M

.14 Maintenance Probfem 4 02s o.2s o'4$

U#'

Design / Construct;n/Ir stauabon Fabricabon Problem oo 0.o als 3 MisceDaneous oo gw,,l o 45 SHUTDOWN 4 67 Safety System Actuabons om 415 g on en Signdicant Events om os 022 4 01 1 Safety System Failures ieo 13 in5MIWelM CAUSE CODES (all LER's)

Administratrve ControlProblem

!o

1. U' I pigpr} o44 0.0 0.0 Licensed Operator Problem oo 43opay fa

1. E Other PersonnelError g o.as Maintenance Problem il o.12 m o.zo Design /Construebon/Installaton Fabricaten Problem os c27 uU i 0.0 Miscellaneous o.o loo FORCED OUTAGES

.o.10 g Forced Outage Rate

• Io MP!O 49 M

-o e2 Eauipment Forced Outages /1000 Commercial Hours

• io 9 013 1.o

.o s oo os 1.o 1.o

-o.s oo os 13

• Not Calculated for Operational Cycle Performance inder Perfortnance index NOTES:

Ptent Sek. Trend Short Temt Based on the slope d a linear regresson kne plotted over each plants data. Time intervals used in the trends are 4 Quaners for ' Operations' and Torced Outages

• indicators and 6 Quaners for

• Shutdown' indicators.

Dewatons from Peer Grouc Medan Lorm Term: Compansons are rnade of each plant to the performance of rts peers over a 12 Quarter bme intervat PMrQg PSL 1&2 Combustion Engmeenng utn core protechon calculator plants.

Vil

WANO OVERALL INDICATOR PERFORMANCE OVERVIEW (November 30,1996)

Industry Median Values

• Unit or Station Values 3 Yr. Distribution 2000 PERFORMANCE INDICATORS PTN 3 PTN 4 PSL1-PSL 2

@ 93 - 6/96)

Goals Unit Capabihty Factor (Unit %,

ggy 3-Yr. Dstribubon Ending November '96).

89.2%

89.4 %

17T.0M 81.6 %

81.4 %

87.0% -

Unplanned Capabihty 1.oss Factor (Unit %,

PMG h s,.www Ar.

3 Yr. Distribubon Ending November'96) 3.1%

3.3%

c14:8% U.9%9 5.7% '

3.0%

Ur: planned Automabc Scrams Per WS. maois

,m 7000 Hours Critical (Per Unit, 0.6 0.6

%1.6p; 0.6 0.9 1.0 3-Yr. Distnbudon Ending November '96)

IMMi

{0264Q 0]!%y f

High Pressure Safetyinjeebon Q'{

.yjil}

NO.009 W.

0.003 - 0.008 not System (per Unit,3 Yr.Distribubon k0.009b 0.009h go..m n -: y

. ~i cy/

q " i. A 9

• n' available Ending September'96)

• M Mz 9

Auxiliary Feedwater System Knq i&g., 3i M2 pg ;.e wm x n (per Unit,3-Yr. Distribubon V0.0134 " 0.010 5 0.009 s 0.013 h 0.004 - 0.009 not

}

W%w -

5

,v wu 9v available Ending September'96)

F%

er*

{

.s Emergency AC Powersystem yp (per Unit,3-Yr. Distnbubon 0.006 0.003 CO.019b 0.013 0.009 - 0.014 not v;m ending September'96)

We%

available 6 %@$

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

99.9 %

,?99.0%1 99.7 %

99.9 %

99.6%

• 99.5 %

Distribution Ending November'96) it@MP e

w Collective Radiation Exposure (Man-

%l9 QMf*

t. % % AJr, Rem per unit per year,3-Yr. running 147.0 147.0 L'217.Ti C217J39 153.0 110.0 W;mf myL ^

nuun ta? n t avg. ending November'96)

Volume of Low-level Solid Radioactive

%.? j ED? @

"N"l.y $52.1e-

.46.0 45.0

?;52.1 Waste (Cubic meters per unit per year, 32.3 32.3 NM^

3-Yr. avg. ending November'96)

Chemistry index (12-mo. weighted 1.mn?

ic average through November'96) 1.01 1.04

~.1.173 1.16 1.16 "

1.10 1

industnal Safety Lost-Time Accident Rate (Station rate per 200,000 man-0.28 0.26 0.44 "

0.40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> worked ending November'96)

Fuel Reliability (Unit microcuries/g, Fuel Defect Reference not month ending November'96) 1.00E-06 4.06E-06 2.14E-04 3.32E-04 5.0E-04

• available NOTE: Shaded area denotes FPL pebance is unfavorable to actual industry median.

Source ofIndustry Data:

• 1996 MYear Report for Perlormance inecators for to U. s. Nudeer Unity industry g/93496 Dstibubon).

" 191r6 WYear Report for Portonnance indaitors for sie U. S. Nuclear Unty industy p/95496 Detnbuton).

" 1996 NYest Report for Performenos indantors for te U. S. Nudeer Utsly industy (4/96496 Detnbubon).

l' viii L

l

~

{

. WANO OVERALL INDICATOR PERFORMANCE OVERVIEW Discussion of FPL Performance Unfavorable to Industry Median J

(November 30,1996) l UNf7 CAPABILITY FACTOR f3 Years Endino 11/30/96)

St. Lucie Unit 1. The 3-Year running Capability Factor through 11/30/96 was 77.0%. Capabill;y loss is sttributed to the following: Hot Leg Valve MV-3480 leak repairs from 3/29/94 to 4/2S4 (OA%); Main Transformer trip from 6/6/94 to 6/11/94 (0.4%); Quench Tank leak repairs from 2/27/95 to 3/8/95 (0.9%): 1 A2 Reactor Coolant Pump seal repairs from 8/2/95 to 8/9/95 (0.7%); inoperable Power Operated Relief Valves from 8/9/95 to 8/17/95 (0.7%); inadvertent Containment Spray actuation and clean-up from 8/17/95 to 9/3/95 (1.3%); 182 Diesel Generator failure from 9/1/95 to 9/6/95 (0.5%); 1A Diesel Generator Radiator leakage from 9/6/95 to 9/10/95 (0.4%); Code Safety Valve repairs and modifications imm 9/11/95 to 10/13/95 (2.4%); a refueling outage from 4/29/96 to 7/25/96 (8.0%); and,18 Main Transformer repairs (0.8%). Other miscellaneous unplanned outages and derates accounted for the remaining 6.5%

Unit Capability Factorloss.

UNPLANNED CAPABILITY LOSS FACTOR f3 Years Endino 11/30/96)

St. Lucie Unit 1. The Unplanned Capability Loss Factor for the three years ending 11/30/96 was 14.8% compared to an industry median of 5.7%. Unplanned outages and power reductions contributing to this performance included:

Hot Leg Valve MV-3480 leak repairs from 3/29/94 to 4/2S4 (0.4%); Main Transformer trip from 6/6/94 to 6/11/94

.(0.4%); Quench Tank leak repairs from 2/27/95 to 3/8/95 (0.9%); 1A2 Reactor Coolant Pump seal repairs from 8/2/95 to 8/9/95 (0.7); inoperable Power Operated Relief Valves from 8/9/95 to 8/17/95 (0.7%); inadvertent Containment Spray actuation and clearFup from 8/17/95 to 9/1/95 (1.3%); 182 Diesel Generator Failure from 9/1/95 to 9/6/95 (0.5%); 1A Diesel Generator Radiator leakage from 9/6/95 to 9/10/95 (0.4%); Code Safety Valve repairs and modifications from 9/11/95 to 10/31/95 (2.4%); dropped CEA's from 2/22/96 to 2/25/96 (0.2%); a refueling outage extension from 6/22/96 to 7/25/96 (3.1%); and,1B Main Transformer repaic (0.8%). Other miscellaneous unplanned outages and derates accounted for the remaining 3.0% Capab!!!!y Loss.

St. Lucie Unit 2. The Unplanned Capability Loss Factor for the three years ending 11/30/96 for 7.9'). Major unplanned occurrences contributing to this performance included: shutdown for auto reactor trip investigation on 4/23/94 (0.3%); refueling outage extension from 12/1/95 to 1/5/96 (3.2%); and, Hydrogen System problems from 1/5/96 to 1R/96 (0.2%); and, shutdown from Hydrogen Cooling System Valve and 2C Auxiliary Feedwater Pump repairs from 6/6/96 to 6/13/96 (0.6%). Other unplanned outages and power reductions accounted for the remaini1 3.6% in Capability Loss.

UNPLANNED AUTOMATIC SCRAMS PER 7000 HOURS CRITICAL f3 Years Endino 11/30/96)

St. Lucie Unit 1, Increased rate for Unit 1 was the result of five auto trips occurring on 3/28S4,4/3/94,6/6/94, 10/26/94, and 7/8/95.

IX

~

~

.+

4 -

MIGH PRES $URE 8AFETY INJECTION SYSTEM (3 Years Endina 9/30I96) 3; Turkey Point Units 3 & 4. Average performance was affected due to the'on-line replacement of the HPSI pump motors -

4 fotowing discovery of cracked rotor bars.

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

St. Lucie Unit 2. in the 1st Quarter of 1995, everage performance was affected as a result of Component Cooling Water J

(CCW) Heat Edw@r cleaning which placed the respectNe HPSI pump OOS due to lack of dedicated seal cookng j

AUXILIARY FEEDWATER SYSTEM G Years Endina Sf30/96)

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

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

4

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

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

~

St. Lucie Unit 2. Average performance for three years was affected by failure of the AFW PP 2C Steam Admission Valve MV-p 1

06-13 to open, a mechanical trip knkage for AFW PP 20 when the Electncal Ovengmed Solenoid was energized, and a i.

discrepancy between iloid wiring and plant wiring drawing for the AFW PP 28.

EM88GENCY nigmEL GENERATOR SYSTEM (3 Years Endino Sf30196)

St. Lucie Unit 1. Unit 1's average performance for three years was the result of a high water jacket temperature trip of 1A l

EDG and failure of the govemor on 182 during monthly survei5ance run which closed off fuel to the 12 cylinder engine in the 2nd Quarter of 1995,18 diesel 12 cyhnder engine valve fadure in the 3rd Quaner of 1995, and 1B diesel due to replacement of the cooling water valves in the 4th Quarter 1995.

008 I FCTIVE PADIATION EXPOSURE "" P8M (3 Years Endina 11/30/96) i-St. Lucie. Collective Radiation Exposure three-year running average level for St. Lucie was 217.3 Man-Rem per unit which 4

was greater than the industry median of 153 Man-Rem.. Site performance was influenced by unplanned and scheduled

' outages.

VOLUME OF SOLID RADIOACTIVE WASTE fAnnual Ava. for 3 Years ulina 11/30/96)

St. Lucie. Volume 6 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.

CHsu'STRY PERFORMANCE (12-Mo. Weichted Averaae Endina 11/30/96)

- St. Lucie Unit 1. Performance at.St. Lucie is affected by the elevated condensate dissolved oxygen.

L x

4

8911.

j 1

WANO WElGHTED OVERALL PERFORMANCE 100.0 0

PTN 3

• * +.. PTN 4 p

l industry Avg I

'M

. gr 20.0 O.

f

/,

g

....eee

• • • O e

70 0 l

D, 0

4

.g 1

4:

W M

+

l l

j so 0 l

mnt 7,. 3ra co w iee6 m.

=w.w m ir..

of pubhcabari and wie De added ri the Decemcor 1996 report

• g 40 0 f

SMS te$

12f95 Unit

'1991

'1992

• 1993 1994 41996

+

-3fB6 s'

PTN 3 68 0 68 9 88 6 84 8 90 6 07 8 91 8 3

_ PT98 4 -

46 3 63 8 86 6 86 7 93 7 92 7 02 7

- PSL 1 <

61 3 74 4 82 7 75 8 62 1 82 2 58 2 PSL 2 70 8 80 9 71.2 86 8 73 6 72 5 73.2 trialustry Avg rVa rVe 76 2 80 1 82 0 DEFINITION The WANO Overall Performance index is a composite indicator utilized to trend nuclear station performance. The index is a weighted combinabon of the following 11 individual performance indicators over the time period noted:

5. Lis ii.cp AC Power (10%)(2 yrs)*

9. Thermal Paimes (6%)(1 yr)

1. Unit Capabihty Factor (16%) (2 yrs)*

v

2. Unplannea Capabihty Loss Ftr (12%)(2 yrs)*

6. Unplanned Auto Scrams (8%)(2 yrs)*

10. Chemistry Indicator (7%)(1 yr)

3. High Pressure Safety injechon (10%)(2 yrs)*

7. Collechve Radiabon Exposure (8%) (2 yrs)* 11. Industnal Safety Accidents (5%)(1 yr)

4. Auxihary Feedwater Systrsm (10%)(2 yrs)*

8. PWR Fuel Reliability (8%) (most recent qtr)

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE WANO:

Through4thQuarter1995 IndustryMedian: 84.0%

PERFORMANCE

SUMMARY

St Lucie Unit 1's dechne from ist Quarter to 2nd Quarter is pnmarily the result of a decrease in Unit Capabikty Factor, increased Safety System performance rates, and increased Collecbve Radiaton Exposure.'

I i

' See above for length of period used in weighted calculabons a

i Data Prowder: Sharon Bilger 694-4255 3

A-1

UNIT CAPABILITY FACTOR (3-Year Running Average) 100.0 95.0 l

]

80.0 g-)1 4

• 6,,,

_q

_],**

' Divisen Y-E:87.5 % 8 o o Ws n... n.. n... o.

c - o - e

,0,

75.0 O*=

C

~

70.o

/

65.0

• *f

^

PTN 3 00 0

- - + - PTN 4

--O-- PSL 1 6$ 0

• O PSL 2 a

industry Avg So.0 g

4 46.0 9

40.0

i. -unit :.

"1991 1992 1803 1884 S988

.WD6e Jaf88'. i.aS$,

448' i848. Amt.

3138-iStBS

.9 98 1998 11J98 12fD6

+ PT98 3 r **

47.9 52.7 64 6 85.0 88 9 88 9 88 6 88.7 88.7 88 7 88.6 88 7 88 6 88 4 89.2 89.2 1

^ PTN 4 c 42.2 61.8 63 7 Se 7 87.2 87.3 87.3 84 6 85.7 88 3 89.2 89 0 89 4 89.5 89 4 89 4

. P98.:1,- s 77.5 78 4 82.7 84 6 77.9 78 0 77 8 77.9 80.5 80.5 79 4 77.1 77.1 77.0 77.0 77.0

. PSL'2 81.4 81.3 81.3 74 1 74 0 75 1 77.7 80 5 80 4 81 0 80.3 80.6 80 9 81.4 81.5 81.6 Industry Ave.-

72.3 74 6 76.5 78 6 80 6 i

DEFINITION Unit Capabihty Factor is the rSho of the available energy genersbon over a given bme period to the reference energy generabon over the same time period, expressed as a percentage with both energy gener8 bon terms determined relabve to reference ambient conditions. Available energy generabon is the energy that could have been produced under referenm ambent condrbons crsA,g only hmstabons within control of pl8nt management, i.e., plant equipment and personnel p.6,wa, and work control. Reference energy generation is the energy that could be produced if the unit were operated continuously at full power under reference amtsent condibons throughout the period. Reference ambent condrbons are environmental cond bons representabve of the' annual m8an (or typic 8f) ambent conditions for the unit.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE N,,gy yTD 3-vr Runnino Y.E Tar 0et WANO 7/93 6/96 Median 81.4 %

PTN 3 100.0%

94.9 %

89.2%

3 95.0%

7/95 6/96 Median 84.2 %

PTN 4 100.0 %

86.6 %

89.4 %

1 82.0%

7/95 6/96 Average 79.8 %

PSL1 98.8 %

69.0%

77.0%

3 78.5 %

Year 2000 Goal 87.0 %

PSL2 99.8 %

94.4 %

81.6 %

3 95.0%

PERFORMANCE

SUMMARY

Y See comments on Pageix.

Data Provider. Sharon Bilger 6964255 A2

\\

UNPLANNED CAPABluTY LOSS FACTOR (3-year Running Average) 1e.o 14.o

\\

Pin 3 s

p*

,y f..+..PTN4 f

f

• O..PSL 2

,e

--O-. PSL 1

)

12.0 e,

P 4

Industry Avg.

l Q

10.0

.{

O...O.. 4.**D***O***C

. q __

e \\

• l NOTE: PSL 1 correcsed the unplanned Enrgy Loss values M 9/96 and 1o46 whch caused a e.o change to the 3 Yr. Average.

_.. k c II 4---e... g $

h

/

g 2.0 0.0

'. Unit. 'u 1991 ' '1992 1983

.1994

'1995

1 TBS 2f98

' 3ft$

4 96 Sf96 ef98

~7f96 BfB6 BfB6

.10f96 11/96 12f98 PTN 3 -

15 2 48 3.8 43 3.3 30 36 3.5 35 3.5 35 34 34 3.7 34 31 PTDI4 11 5 65 30 47 4.2 4.2 4.2 4.2 40 37 34 33 31 30 34 3.3

-PSL1-51 59 44 5.7 13 0 13 0 15 3 13.2 12.7 12.1 12.5 14 5 14.2 14.8 14 8 14 8

-PSL2 31 5.5 11 8 13.2 14 8 13.1 10 7 84 63 8.1 8.7 8.5 83 81 80 79 Industry Avg.

82 7.6 64 55 49 DEFINITION Unplanned Capability Loss Factor is defined as the @o of the unsanned energy losses dunng a given period of time to the reference ene genersbon, expressed as a percentage Unpanned energy loss is energy that was not produmd during the penod because of unpl shutdowns, outage extensions, or unsanned load reducsons due to causes under pant irwwa control. Causes of energy losses are considered to be unsanned if they are not scheduled at least four weeks in advance. Reference energy generation is the energy that *muld produced if the unit were operated conbnuously at full power under reference ambent condrbons throughout the period, Reference a conditions are environmental condrhons mpi amisv6 of the annual mean (or typical) ambent conditions for the unit.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE lyr Runnina PTN 3 3.1%

WANO PTN 4 3.3%

7S3 6S6 Median 5.7%

PSL1 14.8%

7SS.6S6 Median 5.0%

PSL2 7.9%

Year 2000 Goal 3.0%

1996 Tavrt(all units): 53.2%

PERFORMANCE

SUMMARY

See comments on Pageix.

Data Source: John Ps22utelli 694-4245 A-3

I i

l UNPLANNED AUTO TRIPS PER 7000 HOURS CRITICAL (3. year Running Average) 1.8

^'

1.6

- @h.('

O O

O O

O O

O O

O O

O

,6

/.

a

/

1.0 Divisoi Y E:51 per urut,

,m.

0s E

,0.. <

O...O,,'?

'n 0,e O

O'

[

^

O O

O O

O O

/

D 04

^

PTN 3 f

.. + +.PTN4 g

g g

j

/w O.=== PSL 1 O2

-. O..PSL 2 I

A gndusty Avg

(

O.0

' Unm..

1 991 Seea 19es 1eed 18e5

-12s ams

.3e8 6

.e48 4 ems 748 1848

, ems 1e28 1148 :taes s

PTN 3 '

• 16 10 00 0.3 03 0.3 06 06 06 06 06 06 06 06 06 06

. PTN 4 -

17 14 09 1.3 09 09 09 09 09 0.9 09 09 06 06 06 06

-PSL1sr 13 10 09 1.8 16 16 16 1.6 16 16 16 16 16 16 16 16

-PeLa' 06 06 03 07 07 07 07 06 06 06 06 06 06 06 06 06 eneustry Avs..e iS 1.2 1.1 0.0 09 DEFINITION Unplanned Automatic Scrams per 7000 Hours Cntical is defined as the number d unplanned automabc scrams that ocur per 7000 hours0.081 days <br />1.944 hours <br />0.0116 weeks <br />0.00266 months <br /> of cribcal 1

operabon. Unplanned m0ans that the scram was not an anticipated part of a planned test. Scrarn means the automatic shutdown of the reactor by a rapid insertson of negative reactivity (by controi rods, liquid injechon shutdown system, etc.) caused by actuaban of the reactor protection sys The scram signal raay have resulted from exceeding a setpoint or may have beOn spunous Automabc means inst the initial signal that caused actuabon of the reactor protechan system logic was provided from one of the sensors monttonng plant parameters and mrdbons rather than from l

the manual scram switches or, in certain cases d6 scribed h INPO 94M, frorn rnanual turtune trip switches provided in the main mntrol room.

Cribcal means that dunng the steady 4 tate cordtion prior to the scram, the effechve reactor rnuthphcahon factor was essenbally equal to one STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Through November D

6S6 Median 0.9%

g ng W M Han 05 n7 0

0.9 Year 2000 Goat 1.0%

1995 Divisbn Target.130 auteinps PERFORMANCE

SUMMARY

See Page tx for comments.

4 Data Providers. (PTN) Jim Knort 24S4757 and (PSL) Ash Petl 467 7104 A.4

7 HIGH PRESSURE SAFETY INJECTION SYSTEM PERFORMANCE t -yr R'mning Average) 3 0.040 0

PTNs

4. - PTN 4

--O-- PSL 1 0 035 l. O -PSL 2 l

i.

Industry Avg O030 l

0.025 Dnnsen Y-E; s oft 5 0.020 0.01$

, / -

0.0i0 g,____

0.005 a'

4---e'

.UnR' 1991 1982

190s

~S994

-1996 34s eft $

' SfBG s2f96 PTDs 3 -

o 007 o 003 o 007 o aos 0 00s 0 008 0.009

~

o 009 i

PTes 4 -

o o'o1 o not o.cos o aos 0 000 0 F9 0 009 0 009 PSL1 o 001 0 026 0 017 o011 o p25 0 026 0 027 0026

" PSL 2 o 011 o aos o.ois o007 0 010 0 000 0.009 0p

-, Avg.

O oos o 006 o 010 o aos o oor l

DEFINITION This Safety System Performatee indicator monitors the readiness of the Safety injection (SI) System at Turkey Point and the High Pressure Salety injection (HPSI) System at St. Lucie to respond to off-normal events or accidents. The indicator is determined from the unavailabilities, due to all causes, of the components in the system dunng a time period, divided by the number of trains in be system. The definition is further explair.ed:

woucr&d unavaliability is the rabo of the hours the wnwwa was unavailable (unavailable hours) to the hours the system was required to be available for service. Data is reported on a quarterly basis.

Unavdability = (Known Unavde Hours) + (Estimated Unavailable Hours)

(Hours System Required) x (Number of Trains)

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE 3rd Ott 1996 3.vr Ava Endino 993 PTN 3 0 000 0.009 WANO Unavailability PTN 4 0:001 0.009 PSL1 0.000 0.026 7/93 6/96Medwt(PWR) 0.003 0.008 PSL 2 0.004 0.009 2000 Goal 0.020 Targets:

gTN ESL 1995 Y-E Target 1 0.016' 5 0.023 1996 Y-E Target 5 0.025 5 0.025 l

PERFORMANCE

SUMMARY

See Page x for comments.

Data Providers (PTN) Brian Dunn 246-6173/Caios Meicher 2466964 (PSL) Dave Wolf 4654235tjuri Krumins 467-7136 A5

~-

34g.g SAFt1 Y SYSTEM PERFORMANCE - AUXILIARY FEEDWATER SYSTEM (3-year Running Average) 1 0.040 PTN 3

. 4 -.PTN 4

--O-- PSL 1

... O..PsL2 0.030 Divisaan Y-E: 5 0.025 I I

j 0.020 0.

O 2

4 a

g............o %

A,

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

0-a i

l 0.000 3

,. usan e--

1991 1982

190s 1984 1998

!JdSS -

'L 2 4 8#98 4

' tits 12/96 r

}

- PTN 3 '

0 000 0 025 0 016 0 021 F;314 0 015 0 015 0.013 j

PTN 4 t 0012 0 031 0 020 0 010 0.011 0 012 0 011 0 010 PSL-11 0 012 0 030 0 C28 0 029 0 010 0 010 0 010 0 009

}

PSL 2

• 0 017 0.014 0.012 0.008 0.014 0.013 0 014 0 013 4

1 DEFINITION This Safety System Performance indicator monitors the readiness of the Auxiliary Feedwater (AFW) Sy' stem to respond to off normal events or accidents. The indicator is determmed from the unavalabilibes, due to all causes, of the components in the system durirg a time period, divided by the number of trains in the system. This definition is further explaned: comoonent unavailability is the ratio of 2

hours the component was unavailable (unavalable hours) to the hours the system was required to be available for service.

AFW Ur availability = fKncwn Unavailable Hours) + (Estimated Unava%bla Hours)

(Hours System Required) x (Number of Trains) i STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE 3rd Otr 1996 3-vr Ava Endino 9/96 PTN 3 0.004 0.013 WANO Unavailability PTN 4 0.004 0.010 PSL1 0.004 0.009 PSL2 0.003 0.013 7/93 6/96 Median (PWR) 0.004 0.009 2000 Goal 0.020 Targets:

ETy ESL 1995 Y-E Tatget 1c020 10.021

}

1996 Y-E Target 5 0.025 5 0.025 PERFORMANCE

SUMMARY

See Page x for comments.

Data Providers: (PTN) Brian Dunn 2464173M/Dody Raasd12464527 (PSL) Dave Wolf 465 4235/ Mark Wdaver 467 7083 A-6

SAFETY SYSTEM PERFORMANCE - EMERGENCY AC POWER SYSTEM (3 year Running Average) 0.030 PTN 3 1

.. +.. PTN 4

.-O--PsL 1 M-E 5 0425 0 025

• 0..PSL 2

--e--h$ustry Avg i

0.020 O

C O

O 1

i i

0.015 O.......,,,,,

,,,,,......O f ' 10

-p'.

j D'

./

O 0.005 g............q...........4 0.000 3fB6' efes 9f96:

12/96

< Unit r 1 991 1982 1 993

.1984-1906 r

PTN 3 -

0 001 0 004 0 002 0 003 0 003 0.006 0.006 0 006 4

{

PTN 4 2 0015 0 001 0 002 0.003 0 003 0 003 0 003 0 003 PSL1-0 013 0 019 0 012 0 010 0 019 0 019 0 019 0 019 PSL2' 0 019 0 006 0.011 0.007 0 012 0 013 0 012 0 013 Industry Avg.

0017 0 017 0 020 0 014 0 012 DEFINmON 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 conected at the train level. The emergency generator includes subsystems.

such as air start, tube 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.

I STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE l

3rd Otr1996 3-vr Av0 Endino 9/96 N 3A&B 0.001 OM WANO Unavailability PTN 4A&B 0.002 0.003 PSL1A&B 0.001 0.019 7/93 65J6 Median (PWR) 0.009 0.014 PSL2A&B 0.015 0 013 2000 Goal 0.025 Targets:

PIM ESL 1

1995 Y-E Target 1 0.015 1 0.016 1996 Y-E Target 5 0.025 5 0.025 PERFORMANCE

SUMMARY

i See Pageix for comments.

4

)

)

Data Providers: (PTN) Bnan Dunn 2466173/Jentsfer Murphy 246-6827 (PSL) DaveWolf 465-4235/RogerKulavich 467-7080 A.7

THERMAL PERFORMANCE (12-Month Running Average) 101.0 100.0 0

0 I

m O

O O

O O,

b

...C.. O.

Dmsson Y-E: 99.5% l l O,..O*-0O**

.90 e'

go 9

1 c

PTN 3 98.0

• + PTN4 6*

---O-- PSL 1

<> -PSL 2 4

industy Avg 97.0

" linft i,'

"f 991 -

1982

'1993

.1994

1998

' 1/98.

. 2f98

'386

+4l98

$56

$48-

7JS$

18795

_948 1958 1158

'f2fB6

.: PTN 3 *.*

99 3 99.2 100 4 100.3 99.5 99 8 99 9 99 9 100 0 100 1 100.1 100.1 100.2 100.1

'100.0 99 9

• e PTN 4 +

99.7 99.0 99 7 99 7 100 1 1001 100 1 100.1 99 9 99 7 99 4

.99.3 C9.1 99 0 99.0 99 0

-- PSU1 99 0 99 3 99 2 99 0 99 8 99.7 99 7 99.7 99 7 99.7 99.7 99.7 99.7 99.7 99.7 99 7

- pal 2 a '

99 8 99 3 97.8 99 5 99 1 99.1 99 2 99.2 99 2 99 3 99 4 99.5 99 6 99 7 99 8 99.9 ladustry Aug.+

90.2 99 3 99 4 99 4 99 5 l

DEFINITION 1

i Thermal Pesis ance is the ratio of the desgn gross heat rate (corrected) to the adjusted actual gross heat rate. Gross heat rate l

is defined as the ratio of total thermal energy produced by the reactor core to the total gross electrical energy produced by the generator during a given bme period. Design gross heat rate (mrrected)is the minimum theorebcal heat rate that can be attained at desiga operating conditions for 100 permnt power, expressed in British thermal units (BTUs) per kilowatt-hour (electric).

Adjusted actual gross heat rate is the gross heat rate attamed in the normal equipment lineup during one 24-hour period each

}

month, expressed in BTUs per kilowatt-hour (electric) power level should be greater than 80 percent.

STATFSTICAL

SUMMARY

INDUSTRY PERFORMANCE N_2r 12-Mo. Averaoe WANO PTN 3 99,5 %

99.9 %

PTN 4 99.8 %

99.0 %

7/95 6/96 Median 99.6 %

PSL1 100.0%

99..%

4 2000 W 99 3

]

PSL 2 100.0 %

99.9 %

l 1996 Target (an units): 99.5%

PERFORMANCE

SUMMARY

4 Data Providers: (PTN) Jose D0nis 2464008 and (PSL) Many Smit 467-7079 A8

- r FUEL RELIABILITY (FuelCycle/ Monthly) 1.00E+00 I

j c

PTN 3

[

• * + = = PTN 4

-O-- PSL 1 1.00E-01

- O PSL 2

}

s A

Iridustry Avg l 1.00E o2

^

h D*

h

~,

Fuel Defect Referecim 5 cE.04 g,

.p

\\

~"

.'*e*:*o.....*O**"U 100E44 O*

w 1.00E45

/

'..t

.'..' ^

^

^

1.00E-06 1,00E o7 r usigt. 4 Prowtons L Cycles '

' 1135 2fB6 "alOS 4 86' afb 6 Sf96

7/98 afg8 79fts.

1efB6 11/I6 22f88

PTN 3 ^ 4

• aata 8 4ee4 s posa tw sm im tm im im im em im tm im im

'm 4

.Pyn c im i s.E4 im ins 4

.ses4 e asE4 em4 i ssE4 seas 4 im i ns4 ime4 em usE s s ens 4 S edE4 s 415 4 81784 100E4 eM4 I SEE4 s S194 1 aEE4 48184 188E4 100E4 18454 6-PS(.1

)

PSt.,2 -

3 01E4 S F184 39354 t ecE 4 SMS t esE4 18eE4 t asE4 10e54 a seE4 34084 7 00E4 6 0AE4

? ?1t e 8 90E4 3.33E4

,eneustry Avga s essa DEFINITION i

This indicator is defined as the steady-state pnmary molant iodine-131 activity (microcunes/ gram) corrected for the tramp contnbution and power level, and normalized to a common purificahon rate and average linear heat generabon rate. The irdcator value is calculated based on the average 4

of the three monthly values for the most recent quarter of steady-state operabon above 85 percent power. Steady state is defined as contmucus operation for at least three days at a power level that does not vary more than 5 pen:ent.

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

l STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Egy Cycle No.

PTN 3 1.00E46 15 E

PTN 4 4'06E46 16 7/96 6/96 Fuel D6d Reference Threshold (PWR) 5.00 E44 14E44 14 232E44 PSL1 1994 Man mEE 3

9 PSt.2 1994 Best Quartile 3.00 E-06 Division Target for each unit: 14.50E43 PERFORMANCE

SUMMARY

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

Da:aProvider ModestoJanenez 694-3323 A9

y:

CHEMISTRYINDEX (12-Months Ending Weighted Average) 1 40 0

PTN 3

= = +

• PTN 4 1.35 1

---O--PSL 1

• * () = PSL 2 1

A Industry Av0 1.30 E

125

?

f 20 4

1 d-

^

^

l' D...

l

• • .,,, 0 = *

• O* *

• O 1.15 l

1.10 8

j

• *,.. 9 -

4.,,,

q e..4,,

1.00

. : Lint c 1991 1982

'1983

• 1994

-1885

1dBS

.2fBS' afBS'

< dies LEfBS e6tps.

7/96 af98

.SfBS, 10ft$

>$1/98 12f80 l

aPTes 3.:.

1.10 1.11 1.11 1 11 1.11 1.09 1.09 1.09 1.08 1.08 1.03 1.01

.xFTls e e 1.04 1.04 1.04 1.03 1.08 1.06 1.06 1.07 1.05 1.05 1.05 1.04 ca* PR;1 1 1.24 1.20 120 1.18 1.16 1.16 1 16 1.16 1.17 1.17 1.17 1.17

'<PSL3.

1.17 1.19 1.19 1 19 1.17 1.18 1 19 1.18 1.18 1.17 1.18 1.16 Industry Aug.'.

1.18 l

DEFINITION 1

The Chemistry index compares the concentration of selected impuribes to the lirniting values for those impurites. Ea impurity value is divided by the limiting value for the impunty, and the sum of these ratios is normalized to i

values are the ' achievable values' defined by intemational industry-accepted values.

i

)

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE l

h 124Ao. Endino Weichted Ava PTN 3 1.00 1.01 WAN,.Q PTN 4 1.00 1.04 (PWR's with Recirculating Steam Gers stars without Molar PSL1 1.08 1.17 Ratio Contro0 PSL2 1.14 1.16 7S5-6SS Median 1.16 1995 Lowest Chemistry index Value Attainable 1.00 1996Targetforeachcrut 51.20 Year 2000 Goal 1.10 PERFORMANCE

SUMMARY

See Page x for comments.

i Data Providers: (PTN) R.Steinke 2466118/ Jim Berg 2464953 (PSL) R Frechette 4653213/ Dave Faulkner 465-3393 A-10

f RADIATION EXPOSURE (3-yearRunning Average) 400

+ PTN g

-O-- PSL

-*~ Industry Avg '

300 i

260 j

rw -yravg 4

k C

Target 5 229.2 I I 5

3 gan Y

i "T r;*IO. "

iso 7-Note: 1996 nurncers are 100 adjuS19d 08Ch rnorflh to reflect TLo data so 0

Mant 1981

1982 1983

'1994 1995 l ilBS M

taf96 6

Sl06 '

. GlB5.

'7/96 Sft$

. 979 6 '

10f98 11/96 12/98 I

PTN -

350 332 257 181 162 162 161 185 164 153 152 151 150 149 147 147 PSL 214 238 193 202 230 229 227 219 187 200 210 218 218 218 218 217 tidusty Asg..

189 193 193 144 153 DEFINITION Collective Radiation Exposure is the total extemal whole-body dose received by all personnel (induding contrectors and visitors) coming on site during a time period, as measured by the pnmary dosameter, thermoluminescent dosimeter (TLO) or film badge.

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

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE 3-vr Runnina per Unit Man-Rern PTN 147.0*

WANO

[perlJnit)

PSL 217.3*

(PWR's ) Median 3-yr Distnbution (7S3 6S6) 153 Division Targets:

3-vr, Ava 7S3-6S6 Median 136 PTN: Y-E thru 1996 5 170.8 2000 Goal 110 PSL Y-E thru 1996 1 229.2 PERFORMANCE

SUMMARY

]

See Page x for comments.

)

l f

• Cunent inOnth data is DRD TLD was not availabl8 at trne of pubkanon.

Data Provders:(PTN)J0hn Lindsay 2464548 and (PSL) H. M. Mercer 467-7302 A Il

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

-*-- PTN 1

l

, -O-PSL 120

' --dr-Industry Avg.

1 100 t

80 LP PSL Y-E: 67.5 1 d '"

C O

- y 40 1

0 20 0-1 i Ptsut,

"19e1 1982

'1993 19994

'1996 1JB6

~2f05 1346 14fB6 SfB6

-848

' 7f96 SfD6

.9f98 10fBS 11/96 12fDE f)

+ P7N

• 125 3 102 3 81.2 83 4 37.4 36.7 30.2 33.1 33.2 32.0 31.1 31.1 30 8 31 0 31.5 32.3 PSL-a 121.1 103 8 80 7 754 53 7 53.3 53.0 64 6 67.2 67.0 56 4 54 7 54 2 54.1 52 0

$21 hadumby 4 85 0 87.0 45 0 46 0 47.0 a

i DEFINITION 3

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

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

• in transit to or at disposal site for disposal STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE 3-vr Runnena thru Nov (Der unit)

WANO MJnthly Cu. Ft.

PTN 32.3 fper unit)

PSL 52.1 3-yr Distribution Median (7/93-6/96) 46.0 Division Targets:

7/95-6/96 Median 32.0 PTN 1996 Y-E 55 6 cu. mtr. per unit 2000 Goal 45.0 PSL 1996 Y E 67.5 cu. mtr. per und i

i PERFORMANCE

SUMMARY

i i

1 See Page x for comments.

i l

l 1

Data Providers: (PTN) Bob Schuber 246-7220 and (PSL) Bruce Somers 467-7305 1

A 12

II INDUSTRIAL SAFETY ACCIDENT RATE (12-Month Running Average) 1.00

-+- PTN 0 90

-*-industry Avg.

0.80 0.70 Q

Q 0.60

/

0 60 0 40 PTN/PSL Y-E: 5 0.30

[

\\

N^

b

^

0.10 0.00

'N.

-1901

-titt 1993 1994 1996 1786

~2fB6 afts 4f98

. Eft $

' Gl56 '

Tf96

' Sf96 '

Sf96 10f96 11136 12796

• PTDI 0.25 0 67 0 36 0 50 0.22 0 22 0.22 0.11 0.11 0 12 0 12 0.12 0 13 0 14 0 28 0.28

.+ PSL -

0.75 0 61 0 50 0 51 0 40 040 0 41 0 32 0.32 0 33 0 34 0 33 0.36 0.25 0.26 0.26 tedustry4 0 97 0 77 0.77 0 64 0 55 DEFINITION Industrial Safety Accident Rate is defined as the number of accidents per 200,000 man-hours worked for all utility personnel permanendy assigned to the stabon that result in any of the following: (1) one or more days of restricted work (excluding the day of the accident); (2) one or more days away from work (excluding the day of the accident); and, (3) fatalities. Contractor personnel are notincluded for thisindicator.

Industrial Safety Accxlent Rate = (number of restricted-time + lost-bme accidents + fatalibes) x 200.000 (number of stabon man-hours worked)

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE 12-Mo.Endino (Nov)

MNO PTN 0.28 PSL 0.26 7/95 6/96 Median 0.44 0.40 DmsionTargets:

+

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

SUMMARY

No Lost Time injuries were reported in November.

Data Providers: J. Sambito (PTN) 246-7372 and T. Moser (PSL) 467-7171 A-13 r

r

. EQUIVALENT AVAILABILITY FACTOR (Year-to-Date) 100.0 i AA

/

...&.,_c.. L.A.. 8. + + -o kM..W V\\

Y

~

my7

.;g. 4 e

o 10.0 if

\\

/

,,0 g 50.0

^y v

l 1

40 0

/

30 0

/,'

..... P1.N 3 PT a

,, 0

- O - PSL1 e

O-.PSL2 10.0 e

ind Avg 00 Unit 1991

'1992 1 993 1994-

1936

' 1fBS :

J/tt

3f98 AfBS rafBS

+ 4fDS 7758' 8795

. afb 6 10f98 11JB6 12f96

_PTN 3 -

22 3 66 3 94 6 83 6 88 7 99 9 83 3 87 4 90 5 92 5 93 3 94 3 94 6 93 8 94 4 94 9 PTN 4 13 9 85 5 81 1 83 1 97 4 100 0 100 0 88 3 68 4 74 8 78 9 00 9 83.3 84 9 85.2 86 6 P8L'1 78 5 95 4 74 0 84.5 75 3 99 6 94 5 94 9 94 6 75 3 62 9 56 6 61.8 62 4 06.1 89 0

-PSL2 98.5 73 2 71 8 77 4 72 9 76 8 87.9 92.0 92.1 93 5 89 8 91.3 92 4 93 1 93 8 94 4 ind Avg 72 2 72 8 75 3 77 4 DEFINITION Equivalent Availability Factor (EAF) is the rabo of the actual energy produchon capability to the energy that would be produced operating at full power for the same period expressed as a percent. Equivalent Availability provides an indication of the effectiveness of plant programs and pracbces in maxirnizing electncal generation.

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

Period Hours

~

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Nov Y-T-D Y T-D Taroet 3-vr Run. Ava NERC/ GADS PTN 3 1054 94.9 %

95.0%

89.2 %

PTN 4 100.0 %

86.6 %

80.9%

89.4 %

1995( @ )

75.7%

PSL1 98.8%

69.0%

77.0 %

77.0 %

19911995 W types) 72.7%

PSL 2 99.8%

94.4 %

95.0%

81.6 %

WANO Division 99.7%

86.2%

87.0 %

84.3 %

7/95-6/96 Median 82.3%

1996 Division Y-E Target 88.0%

7SS.6S6 Average 77.3 %

1996 Year-End Forecast:

86.9%

PERFORMANCE

SUMMARY

Equivalent Availability Factor 4;ormance in November was as follows:

Unit 3 operated at full power in November, Y T-D EAF was 94.9% which is slightly below the Y-T D target of 95.0%.

Unit 4 achieved 100.0% EAF for the month. For the year, EAF was 86.6% which is higher than the Y-T-D target of 80.9%.

EAF for Unit 1 was 98.8% in November. Power losses were the resutt of: repair to 1A TCW Heat Ex2 anger (8.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) and Heater Level Control System (0.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />). EAF performance Y T-D was 69.0% which is below the 77.0% Y-T-D target.

Unit 2 essenbally operated at full power in November, EAF for the month was 99.8%. Power losses of 1.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> were attributed to testing of the e

~

Control Valve (0.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />) and Turbine Valve (0.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />). Y-T-D EAF was 94.4% which is slightly below the 95.0% Y-T-D target.

Equivalent Availabiirty for the Division was 99 7% for the month and 86.2% Y-T-D which is below the 87.0% targeted Y-T-D. The year end forecast for the Division is 86.9%.

Data Provider. Sharon Bilger 6944255 B-1

+

CAPACITY FACTOR (MDC NET)

(Year-to-Date) 110.0 100.0 o..

.. = = * * * * * *

• A M..X W

\\

- y

_y...--

!/ v N

/

v 1,,,

• f Y

i 60.0

'/,

40.0 c

m3 l 30 0

- + PTN 4

--O-- PSL 1 20.0 O PSL 2 A

Ind Avg 10.0 0.0

-' Unit.;

(1991 1992 1993 1994 1 988 1J88 ' M af98.

4f90 i r GlBS

- Sf96 -

7/98

. Af96

9f98 1948 11/96 12f98

• PTN 3 -

22 5 58 4 97 0 84 8 89 5 103 9 85.7 00 0 93 1 94 9 95 6 95 9 96 4 95.3 96.2 97.0 PTN 4 e 13 7 79 3 81 4 83 0 99 5 104 5 104.2 71 0 67.5 74 1 78.1 79 3 82.2 83 8 84 2 86 1

~ PSL 1 --

78 8 96 9 73 0 84 1 75 0 98 8 93.3 94.2 94 1 74 9 62.5 55.2 60.5 61.1 65.0 68 1

'PSL2 101.1 73 7 64 1 76 3 71.9 74 1 87.0 02.0 92.0 93.5 89 5 91.2 92.3 93 0 93 7 94 3 Ind Avg 71.2 72.3 75 4 77.9 DEFINmON Capacity Factor (CF) is the index of the actual electncal energy produced by the unit with respect to its potential Capacity Factor Net ElectncalGeneration X 100 Maximum Dependable Capacity (839 or 666) X Period Hours STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Nov Y T-D 12-mo endina NERC/ GADS PTN 3 103.8 %

97.0 %

97.2 %

1995 M Types 75.2%

PTN 4 103.9 %

86.1%

87.4 %

19911995M Types 71.3 %

PSL1 99.9%

68.1 %

71.0%

PSL 2 100.2 %

94.3 %

86.4 %

WANO Division 102.0 %

86.4 %

85.5 %

7/95 6/96 Median 81.1 %

7/95 6/96 Average 77.9%

PERFORMANCE

SUMMARY

Capacity Factor performance in November was essentially 100.0% for all four units.

Data Provider. Sharon Bager 694-4255 B-2

i PTN FUEL UTILIZATION FACTOR Turkey Point Unit #3, Cycle 15 Turkey Point Unit #4, Cycle 16

$50 300 Onginal Planned Refueltry March 8.1997 500 -

Onginal Planned Refuehng September 15.1997 450 Current &cheduled Refuehng-March 3.1997 Current Scheduled Refueling September 8,1997 4*

f

$400 -

g

ft 3

g350-8" 300-1 i

g zu h 250 -

j y

o 200 Isl 150 -

iM 100 60 60 -

]

o PTid e3 -

cet New mes

.Jun sus atur

.Apr esy

. Asa

<Ad

-Aug

-ene Odd 0909 Dee Jam fue atur

.Ast deny Jun M

. Aeg esp I

remaned, -

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

18 47 78 100 128 157 187 218 248 278 300 333 365 395 i

Vestense f+84 13 12 12 11 1

-1 1

1 1

-3

-4 9

-8 8

j

<, Pfas ed

< elanned -

6 37 67 98 129 159 190 220 251 282 310 341 371 402 432 463 494 509

. asemos is 49 79 1U6 137 166 1 94 224

• W---

- (+84 -

12 12 12 8

8 7

4 4

DEFINmON i

Fuel utilization plots the amount of nuclear energy used during the current fuel cycle. The amount of nuclear energy loaded into the core is expressed in effective full power days (EFPD). One EFPD is the equivalent of operating the reactor at maximum thermal rabng (2300 at PTN or 2700 at PSL) for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. Planned energy is compared to actual energy used during the cycle. Fuel i

utilizabon is directly related to plant performance. The significance of variance EFPD(+/-) is the difference between planned and actual energy consumpton. Fuel utilization can be used to project longer or shorter operabng fuel cycles.

i Actual Energy i Calendar Days = Fuel Utilization Factor 1

Fuel Cycle Operating Assumptions i

PTN 3: In accordance with the April 26,1995 Approved Operabng Schedule (AOS), Unit 3, Cycle 15 was scheduled to run 498 l

calendar days (October 27,1995 to March 8,1997) with design energy to run 501 (EFPD) days. ((GLTE: Due to the 34-day outage, startup began on October 7,1995,20 days earlier than planned.

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

NOTE: The Approved Operatng Schedule dated 11/18/96 indicates Unit 3's refueling outage has been rescheduled for 3/3/97 and i

Unit 4's is scheduled for 9/8/97.

PERFORMANCE

SUMMARY

Unit 3 achieved a Fuel Utihzabon Factor of 99.8% and operated for 718 effective full power hours in the month of November.

l e

For the period October 27,1995 to November 30,1996, the Fuel Utikzabon Factor was 98.5%.

Unit 4 achieved a Fuel Utilizabon Factor of 99.9% and operated for 719 effectve full power hours in the month of November. For the penod April 8,1996 to November 30,1996, the Fuel Utdizabon Factor was 101.7%.

a Dataprovider JimrruePerryman 694-3330 i

B-3

PSL FUEL UTILIZATION FACTOR St.Lucie Unit #1, Cycle 14 St. Lucie Unit #2, Cycle 9 a

m Orlgoal Planned Refuehng: Feeruary 3.1994 Onginal Planned Refuehng AprW 15,1997 550 - Current scheduled Refue6ng: October 20,1997 450 - Current Scheduled Refuehng-Aprtl 14,1997 400

<w i

u. no

@ 350 -

w 350 -

' s00 -

I i

= 250-u 250 -

o gon.

fa f.._

s,,,.

r 100 -

100 -

50 -

50 -

Oq P1 p31.pt<

u

.as we e,

om es.

eee Jim ese anne der mar Am Jd Ass esp

.os

.m ens

..nma ese aner

.asr Ptraned n 9

39 69 96 129 158 186 218 246 276 305 335 365 395 425 454 485 514 544 573 575

.a Actest - ~

0 5

35 56 87 117

< Vesiance t+f-)

9 34

-34 42

-42

-41

<9at02' Plannea 5

36 67 SS 126 155 186 215 247 276 306 336 366 397 427 455 485 500 t Actissi

• 0 0

23 52 83 111 141 162 193 224 254 285 315 Verbance (+8-)

-5

-36

-44

-43 43

-44

-45 53 4.,4 52 52

-51

-51 DEFINITION Fuel utilization plots the amount of nuclear energy used during the current fuel cycle, Th6 amount of nuclear ene core is expressed in effective full power days (EFPD). One EFPD is the equivalent of operating the reactor at maximum ratng (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 du utilization is direedy related to plant performance The significance of variance EFPD(+/-) is the difference betwee actual energy consumption. Fuel utilization can be used to project longer or shorter operating fuel cycles.

Actual Energy 1 Calendar Days = Fuel Utilization Factor FuelCycle Operating Assumptions PSL 1: in accordance with the February 8,1996 Approved Operating Schedule (AOS), Unit 1, Cycle 14 was sc operaton June 22,1996. This provided for a cycle of 591 calendar days with design energy to run 575 effective full pow (EFPD). Unit 1, Cycle 14 actually began operation July 25,1996 and is currently scheduled to refuel February 3,1 P,$L2: In accordance with the April 26,1995 AOS, Unit 2, Cycle 9 was scheduled to begin operation November 24,1995 provided for a cycle of 508 calendar days with design energy to run 500 EFPD. Unit 2, Cycle 9 actually beg 1996 and is currently scheduled to refuel April 15,1997.

NOTE: The Approved Operabng Schedule dated 11/18/96 indicates Unit 1's refueling outage has been rescheduled for 1 and Unit 2's is scheduled for 4/14f37.

PERFORMANCE

SUMMARY

Unit 1 achieved a Fuel Utilization Factor of 98.7% and operated at 710 effective full power hours in the month For the period of June 22,1996 through November 30,1996, the Fuel Utilization Factor was 74.1%.

Unit 2 achieved a Fuel Utilization Factor of 99.7% and operated at 718 effective full power hours in the month For the penod of November 24,1995 through November 30,1996, the Fuel Utilizaton Factor was 86.1%.

Data provider Ruben R0dnguez 694 3345 B-4

p FORCED OUTAGE RATE (Year-to-Date) 25.0 -

~

Q l

0 PTN 3

• 4 - PTN 4 s,l.

--O-PSL 1

• O - PSL2 lnd Avg

' 20 0

'e.

I 10 15

\\.

N 1

m 40 0

~

ib 6,-

l O'

l l

o,"

v.,,

j 4

s.0 l

.,., (

o..*

5, e

• • • • • • • e*=.+..4....q......,

t Unit m 1 991-1992 1 983

.1984 1 988 Mit$ r

300 =

?3f88 6.

1 Sf95 :

' GADS

• 7/96 1:OfD6 :

9f96 10f98

.11358

?t2fBS 4

17383 -

1.2 15 6 18 19 05 00 11 8 9.3 7.0 56 4.7 4' O 35 45 40 38

' PT98 4 +

18 13 2 20 39 1.5 00 00 00 1.3 1.0 08 06 05 05 04 04 pal 1' 1.2 35 21 39 21 8 00 44 29 22 22 2.2 21 18 41 36 31

' Pat.'2.

0.0 8.1 23 5 2.3 24 r.0 34 2.2 2.2 1.7 5.7 4.8 4.2 37 34 3.1

. lad Avg 12.1 10 9 10.3 10 8 0.0 DEFINITION Forced Outage Rate is the perantage of time that the unit was unavailable due to forced events compared to the trne planned for fuD power operation. A forced outage exists when the unit requires immediate removal from service, i.e. the unit is not synchronized to the grid. This type of outage usually results from immediate mechanical /electncalthydraulic controls systems and operator-initated trips in response to unit alarms.

Forced Outage Rate Forced Outaoe Hoors x100%

Forced Outage Hours + Service Hours i

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE 1

((g,v Y T-D 12 Mo. Endino NERC/ GADS PTN 3

. 0.0%

3.6%

3.3%

1995(Alltypes) 9.0%

PTN 4 0.0%

0.4%

0.3%

1991 1995(Alltypes) 10.6%

PSL1 0.0%

3.1%

2.8%

l PSL 2 0.0%

3.1%

3.1%

PERFORMANCE

SUMMARY

No forced outages occurred in November, f

Data Provder: Sharon Bilger 694255 B5

~

l UNPLANNED AUTOMATIC TRIPS WHILE CRITICAL l

(Year to-Date) 5 PTN3 i

..+..PTN4

--O-- PSL 1

.. o..PSL2 4

^

t.

lnd Avg.

I 3

Division Target 5 3 I

2

^

^

1 g

^

0 0

0 0

0 0

0 0

0 0

M d.tJalt W 11991' :1982 11993 11954 t1998 c1798 7 1395' 19961 a498; iaSS' iSS$:.7/96

? Sit $

f946-t10SS

. tim

'12/98 wPTDIS.

0 0

0 1

0 0

1 1

1 1

1 1

1 1

1 1

• • Pflid

• O 1

1 2

0 0

0 0

0 0

0 0

0 0

0 0

.7 PSt.1.

2 1

0 4

1 0

0 0

0 0

0 0

0 0

0 0

? PSL2.';

O 1

0 1

1 0

0 0

0 0

0 0

0 0

0 0

'ted Avg i 1.3 1.1 0.9 0.8 0.9 DEFINITION An Unplanned Automatic Scram is a non-manual actuation of the reactor protecton system that results in a scram signal any time the unit is critical. Scrams that are planned as part of special evaluations or lests are not included in this de6nition. This indicator provides an indication of success in improving plant safety by reducing the number of undesirable and unplanned thermal-hydraulic and reactivity transients requiring reactor scrams STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE f[qy Y T-D 12-Month Endino WANO Trios per unit PTN 3 0

1 1

Trips per 7000 CriticalHours PTN 4 0

0 0

3 yr Distribution Median (1993 95) 0.9 PSL1 0

0 0

1995 Median 0.9 PSL 2 0

0 0

1995 Goal 1.0 Division Totat 0

1 1

NRC (19953rd Qtr Performance indicator Rpt) l Quarterly Trips Annualized 1.0 1996 Division Target 53 Quarterly Trips per 7000 Critical Hours 1.2 PERFORMANCE

SUMMARY

No automatic inps occurred in November 1996. Year-to-date, one automatic trip has been expenenced:

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

Data Provders: (PTN) J. Knorr 2464757 (PSt.) Keny K0rth 467-7054 B-6

I ~'

OPEN PWO'S 2,600

- +-- PTN

- o-- PSL 2.000

]

A f

.m 1

1,000 3

j L

8#

o

> Unit +.

1991 1992 1 983' 1994 4 006 51798 rafts.

3f98 - 6 rafts

' Sf98 -

'7796 28f98 -

9fts -

10f96

-11/96 12706 1.406 1.589 1 441 1.422 1,310 1.330 1.544 1,636 1.808 1.553 1.462 PTN x. -

i

.PM - -

1.008 1.920 2,030 2.006 2.166 2.066 1.697 1,7 82 1.644

.762 1.722 DEFINm0N i

This indicator includes Work Type 1 (Planned Mocellaneous), Work Type 3 (Projects), WorkType 5 (Trouble & Breakdown), Status 17 through 48, and allhold codes.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE i

PERFORMANCE

SUMMARY

i I

Data Provde s: (PTN) Greg Heisterman 2464796 and (PSL) Joe Marchese 467-7107 C-1

J.

PWO AGING CURVE i

i i

l PTN Actual-

- + PTN Goal soo i - - O--- PSL Actual l

o - PSL Goal

,00 600 i

e

$00 I-

'9 4oo 300

'.,*.,4 l

200 V*.'.","..,*

i 100 M

l m-]

TOTE 8 ' *

" :'3 8*8 8"'"'"

2 ' ' "*#" 8'" " *

~'"'$'""

r.

pgg aggung.

873 s362 169 79 3

pygg gogg.

873 437 219 1t0 0

778 31 138 g Agggg.

773 389 195 37 0-DEFINmON PWO Aging curves includes Work Type 1 (Planned Miscellaneous), Work Type 3 (Projects). WorkType Breakdown), status 17 through 48, and txcludes HC2 through HC6 and SNO. INPO definition is to be used f Goal; To halve the backlog every three months.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE PERFORMANCE

SUMMARY

Data Penders:(P'h) Greg Hesterman 2464796 and (PSL) Joe Ma-Jee 467-7107 C2

PWO'S GREATER THAN 12 MONTHS (GOLDEN OLDIES)

TURKEY P0miT REF PWOf PWO TTTLE Org. Date Date on LJst j

1 950E806 CONTROL BWG ROOF TROLLEY BEAAL INSTAL.L TROLLEY BEAM 10/3065 11n/96 i

2 95031490 1848,lMPLEMENTATl0N OF PCM95 072 11695 12/1EJ6 3

95033166 150 J52. LEAKS B f. NOISOLATION 11/22/95 12/1/96 ST. LUCE REF PWO$

PWO TULE Ong. Date Date on Lst 1

94017403 SUPPORT PCW.042-299(H21 SOL WVS)

1. 13/94

1. 13/WD 2

95003809 S2 DSG2A ANN 6.2 ALARM 2/b/Wb Zib/Wb 3

96013260 REPMR REPLACE CONDUIT SUPPORTS M/93 b/J2 4

95013570 MLL NOT CAUBRATE. REPCR bib /95 b///Wb 5

95018290 ENG MOUNTED ELAPSED HOUR METER INCORREC tru./UD tir21!90 6

95020079 ALARMS WLL NOT ASlUST.REPMR/ REPLACE U13/95

1. 12/90 7

95022001 REPLACE FR1 A AND FW1 D00RS 5/S!Wb 5/5/Wb 8

96024538 WATER LEAK 5/31/95 Bi302 9

95030665 U/2 OVERHAUL SPARE HVE.219 WOTOR WTIS/95 Bi25%

10 95029229 NEED TO BE CALBRATED FOR LOCAL READING lWlblWb 1WIDIUb 11 95029299 OSCILATING AND NOT CONTROUNG 10/1645 10/1D/90 12 95029430 PLEASE REPMR WV. LEAKS BY SEAT 10/17S5 1Wite 13 95030597 REPAIR CRACKS ON AC BASE NE CORNER 10/23/95 10/R221'C 14 95031853 PUMP CASING DEGRADEDREPMR OF REPLACE 10/23/95 Igralvb 15 95030795 REPAlR AS REoVIRED 10/3085 lut2W/vb 16 95031220 READING IS APPROX 45 DEGREES BELOW 11/03/95 11/2/95 17 95031208 STAR s9411C304 11/04/95 11/3/30 18 95031848 T.V40001 U/S LEAK 11/04 S 5 11f3/95 19 95031806 TR 59.002A LOW /ERRATICINDICATION 11/09S5 1115/90 20 95032671 REMOVE SIZE 1 OVERLOAD FOR 864846 PWO.

11/18S5 11anse 21 95033YO REPLACE THERMAL OVERLOAD BLOCK 11/24 S 5 11/23 2 PWO Greater than 12 month's, indudes Work Type 1 (Planned Miscellaneous), Work Type 3 (Projects), WorkType 5 (Trouble &

Breakdown), status 17 through 48, and exdudes HC2 through HC6 and SNO.

I Data Providers: (PTN) Greg Hesterman 2464796 (PSL) Joe Martese 467 7107 C-3

• P e

NON 0UTAGE PWO'S i

1400 Nb 1200 l--O-PSL l

\\

\\-

1000 W/

\\

0 600 1

400 200 0

<128

'.256 TA

'446 596 446 786 IS6' '956' 1856 1196 1286 h

'1994]:gB5

_Unt --

1991 1982 1 903 1024 1091 1118 1166 949 936 1081 1035 1049 993 876

' r PTN.

"PSL 1247 1103 1016 961 890 889 1102 1101 902 993 778 DEFINITION l

Non-Outage PWO's indudes Work Type 1 (Planned Miscellaneous), Work Type 3 (Projects), WorkType 5 (Trouble & Breakdown),

l status 17 through 48, and exdudes HC2 through HC6 and SNO.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE PERFORMANCE

SUMMARY

Oata Pmviders: (PTN) Greg Heisterman 2466796 and (PSL) Joe Marchese 467-7107 C-4

~

CONTROL ROOM INSTRUMENTS OUT-OF-SERVICE 60 l

--+-- PTN C

-O-PSL 60 e

\\

O M

y 4

Outage tags

]

$ 4o PTN: 23 i

]

O PSL 10 30

^

l

\\

/

\\

l 2o o

t a

u 10 NOTE: PTN numbers for 6/96 to 10/96 have been adjusted to align with PSL's method of reporting as described in the current definition.

0 Unit -

1991 1992 1983 1994 1996 1796 aft $lJ/98.

'4f98 Sitt efts 7/96 879 5

' 9f96 '

10f96 11/96 12f96 l

PTN 39 40 42 i 12 30 16 15 16 17-24 26 26 PSL-64 46 25 l 20 28 27 27 33 22 12 11 11 DEFINITION i

This indicator defines the number of control room instruments for each unit that cannot perfom) their design function, regardless of the reason. Instruments on the control room back panels are readily available for use by the control room crews l

and are included; however, instruments in adjoining areas where operators are not normaHy stationed (such as computer rooms) are not included. Count de6ciency tags that are in status 05 to 48.

i STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE l

i PERFORMANCE

SUMMARY

4 t

Data Prov&T (PTN) Greg Heisterman 2464796 and (PSL) Joe Marchese 467-7107 C-5

m m

.m..

.. _ ~. _

- OSHA RECORDABLES (Year-to-Date) 60

-+-- PTNl' - PSL 40 e

30 o

x 20 O

10

..M

.f" c

Unit 7 1991 1982 1933 M984

• 1905 c146 L3fBS. M

.426.

525-

.SSE

' 748. l.'.8fB6

'SSE*

1858 114C 12f98 FTW 35 39 29 27 20 0

1 2

2 2

4

• 4 5

6 6

7 PSL 20 22 23 41 26 3

3 4

5 10 14 17 18 19 20 21 DEFINITION The definition by Occupational Safety Health Administration (OSHA) is an injury occurririg on the job that requires medical treatment beyond first aid as defined by 29 CFR 1904. This graph shows OSHA Recordables reported at the sites.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Month Y-T-D PTN 1

7 PSL 1

21 Nuclear Division Y-E Target 1.75 per 200,000 Hours Worked Corporate Y-E Target 3.75 per 200,000 Hours Worked PERFORMANCE

SUMMARY

Two OSHA Recordables were reported in November:

PTN an employee dropped a scaffold pipe on his toe and fractured it.

PSL while processing blueprints, an employee's eyes were affected by ammonia vapor.

A total of 28 OSHA Recordables have been received year-to date.

Data provders: J. Sambita (PTN) 24SJ372 and T. Moser (PSL) 467-7171 D-1

. -. ~

E LOST TIME INJURIES (Year-to-Date) 6 l

j -+- PTN l d

d-O--PSL j

^

1 1

3 i

O O

O O

~

~

2 a

l 1

C C

C C

i I

o 1

Unk ~~

1991' 1992 J1993

.1994-1995

'1/99 ' N "Sitt t 4796 -

Sf98 8706 -

'7M

-8756 SISS -

10P96 11J98 12f96 1

'PTN 0

0 0

1 0

0 0

0 0

0 1

1 1

1 1

1

'PSL.

2 4

3 1

2 1

1 1

1 1

1 2

2 2

2 2

DEFINITION i

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

i STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE

}.

Month Y-T-D NN 0

1 l

PSL 0

2 PERFORMANCE

SUMMARY

No Lost Time injuries were reported in November.

a Data providers: J. Sambito (PTN) 246-7372 and T. Moser (PSL) 467-7171 D-2

P" REGULAR STAFFING FPL Employees and Long Term Contractors by Department j O-Planned;l 9-Actual Turkey Point t_ -

y

{ 1100-I *900 - E3

~N

• B

~

~

~

~

o 27 e4 es 1

,7,

,g j.,

g%

I 800-sis era sTe of 700 St. Lucio 1100 -

to24 toso top

,,e&o 5,o3, toi,3

toi,

,,o I#'

leo toto to7s toli teos C

C U

900-ed e2e og

^

,p, g

800 -

700 Engineering y

400 34s 347 347 343 343 3

300 t.

sos aos aos aos 2

0 3

mis aR 314 si2 sit soo 2s2 2Te zee soo 29-200 -

g 100~

0 Nuclear Assurance gjo.

ios tos tos sog tos tos 1os

)

g 100-ior 104 to.

Im sa tot

,,3 90 -

94

'I E

~

I 80 Licensing & Specla! Programs s

4-y g

2-0 50 45 -

n M

43 43 M

M c

42 42 n

40 -

.m a

a 4

44 ai g

35 -

38 E

30 Nuclear Division Total J

-^'

2600 -

2,481 2.493 2.492 2.483 2.4ee 2 ase 2 co C

C O

C C

C 2.372 2,3?2 2.372 2,372 2400-2.4L 2.43 1 2 die 2d gb

=

C Q

2200-2M 2.2e %s -

I 2.tia 2.1Te 2.1T6 2.tTo 2000 l 1ss l 2/ss j stes l ens. l ses l ses l 7sse l ass l sies l toss l 11tes l 12res l Data Provider. Laune Hertzlin 6%4631 D-3

OPERATOR EXAMINATION PERFORMANCE Turkey Point Units 3 & 4 100.0*4 i

e RO/SRO Pass %

)

BOper Req Pass %

950%

d j

90.0%

i i

l 85 0%

I I

80 0%

{

. Enems:

l :1991

-1992

1993'

'.1994

-1996

• 1/96 '

.2f96.

3/96-6 5/98.

6/96 7/96 4796:

9/96 19796 11/96 12/96 floresto 7ahan - l 39 5

8 13 peut a 1

39 6

8 13

. heriim, pass % l 100 0%

100 0%

100 0%

100 0%

- e,., a,

n a n

se s3 u

u

--- 1 i u n

.o u

u 4

a Oper nog Paes % l 94 0 %

96 0 %

M 0%

95 0 %

96 6%

100 0%

95 0 %

DEFINITION

}

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

NRC.

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

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

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE initial RO/SRO License Exams 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:

i YTD 1995 13 13 100.0 %

IntalNRC Exauls NRc Reaual Exam RO's Pass Raie 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 Pasted Pass Rate %

Upgrade SRO's Pass Rate 94.7%

Average Overal 88.0 %

2 YTD 1996 83 82 98.8%

Amage oman 94.6 %

YTD 1995 58 56 96.5%

a PERFORMANCE SilMMARY No exams were given at Turkey Point in November.

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

OPERATOR EXAMINATION PERFORMANCE St. Lucie Units 1 & 2 100.0 %

} m RO/SRO Pass %

10Oper Reg Pass %

9s.0%

90.0 %

8s 0%

t:

so o*4

' Esas :-

l-1991

.1992

1993

.1994

1996 21/96

'2/96

.3/96 ret 96 8156 8/96 7/96 8/96 St96 10/96 1 1/96

12/96

.====o1

-i is e

so 4

i 35 e

so si 4

-,s.o e s. i im es im os im os im os

$m os

.e,nv i es es 6s 7s 73

^p d

-l 61 6o 66 68 71 opwa p s.I e4os a7 os too os ei os 97 es DEFINITION Inibal Ucense Examination (RO/SRO) results are reported for all candidates taking an initial Ucense Exam as conducted by the NRC.

Operator Requalificabon Examinabon results are reported for both RO's and SRO's. This examination is administered annually by the utility and may be jointly administered by the NRC. Retests of operators who failed examinations are notincluded.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE initialRO/SROU nseExams The NRC at their last Regional Training Managers Meeting (f r fiscal year 1994) provided the fo!!owing data:

YTD 1996 4

100.0, YTD 1995 0

0 0.0%

ing,, yqe g,,,,

yne q,cy,, g,,,,

RO's Pass Rate 94.6 %

RO's Pass Rate 91.0 %

Operator Requal Exams Instant SRO's Pass Rate 94.4 %

SRO's Pass Rate 85 M No Taken No Passed Pass Rate %

Upgrade SRO's Pass Rate 94 7%

Average Overall 88 M Amage Oman R6%

YTD 1996 0

0 0.0%

YTD 1995 73 71 97.5%

PERFORMANCE

SUMMARY

St Lucie began Operator Requalification Exams in November; results will be provided in December's report.

Data Provider Mike Allen (PSL)4674161 E.2

. ~

OVERDllE CONDmON REPORTS 100 4

^

-+- PTN

-O-- PSL 90

! --&-Jur.o -

l i

70 1

\\

1 5

80 o

l

\\ /\\

1

I

+

0 30

\\

/

\\

/

l

\\/x"m u

~

O

1. ~

Usut ' !!

1 991 1992'

1903- '1904.

Mead

ites,

2f88 -

'3fes' M m

swas-

7ses

. sig8 -

SfB6 10f98 11796 12796

'- PTN 6

0 0

12 0

1 3

0 2

7 0

0 PSL 2 95 25 51 0

8 19 29 29 13 15 24 h '

11 19 9

12 S

3 1

6 J

DEFINITION 4

T'his graph shows Condition Reports that exceed assgned priority timeframe. This indicator takes a snapshot the last day of each month. Record the number of overdue condition reports the last day of each month.

Severity Levels are as follows: A = 3 worldng days B = 10 calendar days C = 30 calendar days i

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE i

PERFORMANCE

SUMMARY

i Dets Ph (PTN) Ed Lyons 2464967.(PSL) J. Voorhees 467-7567, and Bob Symes (Juno) 6944287 F-1

QA FINDINGS 4

12

PTN '

+ PSL i

• Juno _

go l

8 o

1 15 6 4

2 p

y 0,

"'.Une : -

,, Eb.30 doye '.

2140 days.

~. 0140 days '-

a 91120 days -

' 121.tM days.

- 1511Mdays :

4100 days -

. Pm 1

0 0

0 0

0 1

- P8L -

5 to 4

0 0

2 2

- June ~

5 3

0 3

1 0

4 DEFINITION The,ndicator represents the age of audit findings open as of the last day of the monin. The clock starts on the day of the audit report transmittal and continues until Cuality Assurance (QA) verifies that implementation has occurred.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE PERFORMANCE

SUMMARY

Daw Pnmders: T, Abbebeto (PTN) 2464581, W Bladow (PSL) 467 7111, and R. A. Symes (Juno) 6944287 F-2

NRC VIOLATIONS Cited and Non-Cited (Year-to-Date) 30 0

PTN NOVs 28

. -.e.

PTN NCVs

--O-PSL NOVs 26 O PSLNCVs

/

O 4

4 y

O--

22

/

?

5 go

/

/

i.

/

Sr.o

~~

l

_. + ~~

/.o 1cr '

3,,

s s i,

• .. I' ~.

p'/

},,,

y.

'l

.. ~ /.**

. \\ :~

):

J 4.' ~

1996 Y-E Target: 5 7 E y

/

[,,'

~

N J o~..i 0 - O - O Oh

[, 5 /- *' '

0 0

3 c6, o'- - O' f

0

~; taNr

1901

-1982 : 'ist3 1964

?1995

1 ABS

.2f95 - M s4f98 ' 'Ef98 Sets.

.~7796 L Sftsi

Sf98 10f98 11198 12f96

- PTNNOVs4 13 8

4 4

1 0

0 0

0 1

2 2

2 3

3 3

e PTNNCVs s 21 7

13 12 15 0

1 3

3 5

8 11 14 14 15 16

- PSL NOVs -

8 8

7 9

21 1

4 4

8 9

9 17 20 23 25 25 PSLNCVs a 3

3 3

3 12 1

1 1

5 10 13 15 17 18 22 22 l

DEFINITION Notice of Vdations (NOVs) are categonzed in terms of five levels of severity 'o show their relative importance. Severity Levels I and 11 are violations that involve actual or high potenbal impact on the public. Severity Level 111 Vdations are causefor significant concern. Severity Level IV violations are less serious, but are of more than minor concem; i.e., if left uncorrected, could lead to a more serious concem. Vdabons are counted on the date of the inspechon exit meeting. Vdations are now counted with respect to the date of occurrence (using the date of the inspechon exit meeting)instead of the date of the inspecton report, as was done in the past.

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

l STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE NRC Violations Ngv HQ Year End Tarnet PTN Cited 0

3 7

1995IBG Group Mean 9.4 1995 Region 11Mean '

10.5 PTN Non-Cited 1

16 PSL Cited -

0 25 7

1995IBGTop Quartile Mean 3.8 '

1995 IBG Top Quartile Entry 6.0 PSL Non-Cited 0

22 1995 Region 11 Top Ouar'Ve Entry 7.0

.w,. m PERFORMANCE

SUMMARY

~.

Turkey Point reported no Nobce of Violations (NOVs) in November. Year-to date, three NOVs haw been reporttu St. Lucie reported twc NOVs in November for October, fourteen potential NOVt; are pending investigation. Year-to date, the total conArme,d is 25.

See next page for details.

Data Prowders- (PTN) Gary Hohnger 24%078 and (PSL) Ed Wertam 467 7162 F3

i.

4 NOTICE OF VIOLATIONS -1996 TURKEY PONfT 1 #964402 Premndleoneg of EWuel system pnere surmsence test Ed Mig date. 6/14/96.

2 #964442 Fadure 2 totow Chemmal Volume Contal System Opermang Procedure dunng a Unit 4 blender flushing evolutert En Mig date: 5/15/96.

3 #E1143 Fire Zones 64 and 143 not coveed by exempton b Appenda R. Ed Mig aste: 927/96.

$T, LUCE 1 8960141 Tempomry Changes e Procedures improperly Changed intent of Procedures. Ed Mig Date: 1/26/96.

2 #964341 Operaers Islied to fotow procedures weih bur examples. Ed Mg Date: 2/8/96.

3 #E0342 inadequate dengn coned of RCS boren diiulian procedure. Ed Mig Date: 2/8/96.

4 #964143 A10CFR50.59safetyevaluetonwasinadequate. EdMig Date: 2/846.

5 #964441 A contunment gaseous /pereculate4cdme monitor wee rendered inoperable due to a foHure e toiow procedures, combosc with a lack of proper loenw evough on sie part of norWxansed operators teidng logs. Ed Mig Date. 4/3/96.

6#964442 Fadures b make mquired log ereies for rescavity snanipuletons and a mem generator hydrogen addeon. Ed Mig Dele: 4/3/96.

7 #964443 An EDG was rendered irrporable due to a leaure e fotow prordures while pleang the fuelou tonk on recrculaton. Ed Mig Date: 4!3/96.

8 #964444 Renews of haloncal dets for CEA rnantenance revealed that poetanoddicaton teetng acceptance creerta for Unit 1 CEA power cabies were not apphedtopost-modiAcetontestdate. EdMigDeer 4/346.

-9 #964645 An sudd of tre bngade member qualdiatons resumed in a vioiston for iniure to mentan c;rrrnt physcais. Exit Mc date: 5/17/36.

10#964941 Faaure e corsol overnme. Ed Mig dese: 7/8/96.

11#96-0942 inadequate procedure for managing overnme. Exit Mig date: 7/8/96.

i 12#96 0943 Falure to test sie Reactor Cavity Pressure Relief Dempers in # ctordance with the Vendor's Tedincal Manual Exit Mig date:7/8/96.

13#964944 Faiiure to perbrm adequate testing on sie Reactor Cawty Pressure Relef Dampers. Ext Mig date 7/8/96.

14 # 5 09 06 Fadure b contal conismmeted tools in accordance wnh toensee proceaurus. Ed Mig date: 7/8S6.

15# 5 1144 Procondeoneg of valves pner to surveibence. Ed Mig der 8/5/96.

i 16 #E1242 Falute to perform selety evolueton as required by 10CFR 50.59 for feMure to recognize an unrewswed safety queston in the development of a esiety evalueton for an EDG fuel oil traneler line volve lineup charye (Level!!!). Ed Mig date: 7/12/96.

17# 5 1243 Failure to morenate dengn changes with the namesary dienges to operseng procedures as endenced by three eramples. Ed Mig date:

4 7/12/96, 18#961244 Failure b soeure that the deegn of the Circulatng and intehe Coohng Water System was correchy fansisted hto plant drawings. Exit Mig date 7/12/96 19# 5 1641 Failure e make a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> somnty event not6 canon b sie NRC in xxx) dance with to CFR 73.71 and plant prtxadure 0006125 for the July 26.

1996, temperug event Ed Mig date: 8G3/96.

20#96 1644 Falure b foaow procedunes for Irey cereal for sie Unit 1 PORV hay lock switches. Ext Mig dele: 8/21'J6.

218 % 1341 Faaurs to hdude some SSC's wnhin the scope of the Rule in tie Plant's Montenance Rule Progrom (PASS, Communcatons, Service Air, Rumann Monsors). Exit Mig detr 9/2046 22 # 5 1142 Fadure to losow procedures in actnns rogured by ADM 17.08 (muitpie examples). Ed Mig date: 9G0/96.

23 #E13 03 Improper use of IFFFs as inhor of reiebihty for safety sgnincant systems. Exit Mig date: 9G0/96.

4 24 #96 15 04 Failure 2 Coreal M8TE. Ed Moseng date: 10/18/96.

25 #E15-06 Failure of HP b Have Promdure in Hand During Realignment of Unit 1 Contenment Radston Monitor. Ed Meetng date: 10/18/96.

Polantal Nocce of Volatons at St. Luae for November were reported as blows:

1 #961741 For cambratons performed on Unit 1 ouside ar intake montors on 4/11/95, the Nuclear Plant Work Order did r6 indude attadimente as requved by l&C Procedure 1-1220053 2 #%1742 The procedure for perbrmng Rad Monitor coibraton was not adequate in that Die procedure was not dear in desenbog proper documernabon b pnmary and seendary calibratons, edudmg addreemng salsey mncems for personnet 3 #E17 03 Personnel performing the calibraten of the Unit 1 Rad EfRuent Montors were not property trened h that there was no phnin place b tram and quality l&C personnel aher assumeg this responsibuity of caibraton from the Chomsty Department 4 #96 17-04 Twe cases where the TECB had not been updated within 39 deys as required by QI 3 6.

5 #96-17-95 Reacevey devotor value n the plant physcs cunes had not been updated as rogured.

6 #51801 ERO augmentaton scheme not montened 7 #51842 Deleted TS not relocated to Security Plan and REP.

8 #E1843 Inadequeans in certen Emergency Plan impiamentng Procedures.

9 #961844 Training program not adt.cuately implemented.

10#951941 Fadure to imit unescorted a: cess e protoded and vnai areas dunng norHemergency conditons e individuals who require access in order e perform theirdubes.

11 #96-19-02 Falute b report an event under tie cr:terte of 10CFR 73.71.

12 #E2241 Failure to Consolthe Desgn Proms: Aczordmg to the Regurements of !0CFR 50, Appendor B, Crttenon 111.

13#50242 Failure to Fotow Proandure for Pinang the BEACON System in tarvice.

14# 5 2243 Failure to initate a Condson Report for Labe6ng on Safety Related Detectors Data Providers: (PTN) Gary Hoihnger 2466078 and (PSL) Ed Weekam 467 7162 F-4

i,

LICENSEE EVENT REPORTS (Year-to-Date) i 2$

l --+ - PTN '

{ --O-PSL f M

i

?

!e 15

)

a:

l10 q\\

^

^

^

~

b j

6

^

^

l I

i 0

l

. Undt

'1991 1982 21983

1994 ' -1998 rif96

2fB6 2fB6 44fB6

' afD$

EdO6 17/96

.8#96 9/38 10f96 11/96 12/96 I

-P7N-20-24 9

12 7

1 6

5 7

8 9

0 10 10 10 12 PSL 9

10 8

15 18 1

1 6

5 7

11 11 13 to 19 23 DEFINITION i

J Ucense Event Reports (LER) are submitted to the NRC by the licensee to report unusual occurrences presenbed by 10CFR50.73.

i 4

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Her H2 PTN 2

12 PSL 4

23 1

PERFORMANCE

SUMMARY

i i

1 i

Data Provders (PTN) Gaiy Hoarger 2464078 and (PSL) Ed Weinkam 467-7162 F-5

INPO ASSESSMENT RATINGS a no ISPWl d oo lOPsl.

3 50 soo

)

2.6o i

l 100

,,o 0 00 Unit 1989

'1997

.1984 "1949 1990 -

1991 1 992 11s93 1994 1995 1995 PTN-4 00 4 00 3 00 4 00 3.00 2.00 2 00 t oo est zoo S oo

$ co 1 00 INPO ASSESSMENT PROGRAM DESCRIPTION The institute of Nudear Power Operations (INPO) conducts periodic evaluations of site act:vities to make an o Information is assembled frorn safety, to evaluate rnanagernent systems and controls, and to identrfy areas needing improvement.

discussions, interviews, observabons, and reviews of dtm1 tion.

INPO's goal is to visit each pant on an average of every 18 months. However, this frequercy may Evaluation Frequency:

upon the previous assessment rabngs. For instance, if a plant is rated a '1' or *2', the interval between if a pant is rated a *4' or a *S*, the assessment interval is < 18 rnanths.

Performance Cateoory Rahnes:

Category 1: Overall performance is excellent. Industry standards of exceUence are met in most areas. N Category 2: Overall performance is exemplary. Industry standards of excellence are met in most area Category 3: Overall perictmance is generally in keeping with the high standards required in nudcar power. How needed in a number of areas. A few significant weaknesses may exist.

Category 4: Overall performance is acceptable, but irnprovements are needed in a wide range of areas several areas.

Category 5: Overall performance does not meet the industry standard of acceptable performance. The margm rneasurably reduced Strong and immediate management action to correct deficiences is required. Spedal attencon assistance, and fonow-up are required.

p_QTE If a plant is found to be operatmg without an adequate margin of nudear safety, INPO will request th started up.

PERFORMANCE

SUMMARY

Turkey Point and St. Lucie received an INPO category rating of '1' in 1995.

The next evaluations for Turkey Point and St Lucie are expected in the last quarter of 1996 and first quarter of respectively.

De's %vdes (PTN) Gary Hosinger 24%078 and (PSL) EdWer*am 467-7162 F-6

)

I NRC SALP CATEGORY RATINGS 2.50 IE PTN Ratmg ;

l 2.00 O PSL Rat ng !

i i

g 1.50 3

i 1.00 0.50 0.00 -

~

i 1986 1987-J1988 x1989'

'1990-1991-1992-J1993-1924 1995 "1996 netAsune 2.27 2.18 2.25 2 14 1.86 1.38 1.29 1.00 1.00 Pedoe snrans 4/30/86 5/31/87 6/30/88 7/31/89 7/31/90 9/28/91 1/30/93 8/27/94 8/17/96 1.29 1.14 1.00 1.00 1.50 PSL memno :

1 55 1.20 4/30/89 10/31/90 5/2/92 Peded esunne 4/30/86 10/31/87 1/1/94 1/6/96 SALP PROGRAM DESCRIPTION it a tu pahey of tie NRC b use te Systemsbc Assessment of Uoensee Pabmence (SAIP) process e alculaw N agscy's otservatons sesghts on konsee saWy portrmance.

5 The SALP report w....

these otservatons and insights.

E<Wuseen Fascuency-The NRC we rcumally revew ed evalusie each power reacer kansee tial fa== an operatng ksnse at least every 18 rnares When te NRC determmes fiat the pertarmsice warsia a more Iroquent evauason, te normal SALP toquency mer to mcremed. The assessment pened may te edended b a mammum of 24 months uten a plant j

recsves a Category t ranno en d bur funcbonal sea.

f tictonal Seas Perbrmance is generap evalualed m hur (4) tunctonal seas.

j y

1. PiaM Owaoons The bictonal sea conssts cheRy of to convoi and exacutcn of actnntes drec9y retaand a geratng a pist it meludes activibes such as plart striup power operanons. piant shutdown, and system imeups. t also ecludes inom sid reguakecanon teneg of ksneed operaiors 1 Metarce TNs functons ses includes so scavees =w e eeer diagnoste, prodcove prevenove.or correctve mantenance of plant sanctures, systems, sid componens_

w orinantenance of the physcal.An& ton of te piant 3 Evvsenna. The functand ses addresses to singuacy of techncal and engneenng support br al ptsit acevites. t ecludes af konsee s* vees assoraaned we design control; the desen, estanacon, sid testing of past modrhcanons. oneneenng and achncW support b operseons, outages, manensica, tseng, survoasics, sid procurement s2vnes, conagurabon mrworrent desgr4msa mbmaton and its nrtnevai sid support b kanseg acevites.

4 Pirt Leocrt The lunctons sea covers at! acinntes related e otant soort betons. mcsuong raddogcal controls, emergency preonedness, secunty, chemistry, and tre promenon.

Housekeepmg controts se also wcluded m to sea Pe+ nance Cseomr Ramos Ucensee pedurmata m each functonal sea a massaaf try assgnmg a category rabng as h=t beloor

'l' Caiegory 1. LEensee anennon and evcivement have been property bcused on saMy aid resuhsd m a supenor level of safety performance 1

Cawgary 2. Lxensee sceneen ad sndvement se normany we teused sid resumed m a good hvel of sawy perdmance Camgory 3 Lcensee etwnton and involverrent have resuhed m an exsptatte level of portrmsu However, pedarmsus may exNbd one or more of the bkanng charactensbcs meffective programs sid sgnrhesit usues, tack of conective acton fioroughness, and defssences m soot cause andysis. Became lhe magm e unacceptatne pertrmance m rnportant aspects a smatt. meremed NRC and kansee sesnton a requred.

PERFORMANCE

SUMMARY

The Nucicar Regulatory Commemon asued its Systemate Assessment of Lamee Perkvmance (SALP) report for the Turkey Point plant for Augu t 28.1994 through August 17,1996. For the second consecutive time, the plant received Category 1 (supenor) ratings in 88 four lunctrmal Snpas rated by the NRC.

Turkey Point St Lucie Pnor Most Recent Pnr>r Wst Recent Funchona! Area.

P: ant Operations 1

1 1

2 Maintenana 1

1 1

2 Ergneenng 1

1 1

1 Plant Support 1

1 1

j, Overal.

1.00 1.00 1.00 1.50 pgta Providear (PTN) Gary Holknger 2466078 and (PSL) Ed Weinkam 467-7162 F.7

INVENTORYVALUE ACCOUNT 154.300 80 f

70

--+-- PTN

. --O-PSL l

80 80 3

1996 Y-E C

$ 36(SM) 1 40 1

m m

o e

'N:

30 1

20 10 l

0

. Unst.

1981 1992 1993

1994 1996 1JB6

. 2f96.

IsfB6 4f86 -

EfBS -

,4fts 17/B6

. Sits

sf96 10fD6 11/96 12fB6

-PTN 79 1 74 7 54 6 42 4 3'/.4 37.4 37.2-36 0 35.1 34.0 35.1 35.3 35.1 34 9 34 6 34 1 PSL 58 6 65.2 60.2 43 7 36 4 42.0 42.3 43.5 42.9 43 6 41.3 42.7 41.3 40 5 38 4 38 5 i

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

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Start End % Chanoe YE Taroet IBG O' ear 19951

'Totat Average

$39.2 Million PTN Monthly 34.5 34.1 1.2%

Top Quartile Entry

$35.0 Milhon Y T-D 37,4 34.1

-8.8%

$38M Top Quarble Average

$29.0 Million PSL Monthly 38.4 38.5 0.3%

Y T-D 39 4 38.5

-2.3%

538M

'Value does not include Capital as de6ned by PRUC PERFORMANCE

SUMMARY

Turkey Point's Regular inventory decreased by $0.4M in November.

St Lucie's Regular inventory increased by $0.1M for the month.

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

OPEN PLANT CHANGES / MODIFICATIONS (PCIMs) 350 l

--+- PTN

-O-PSL l 300

\\

250 e

N g,,,

=

3 100 E

EIL Desagn:

20 33 Review 14 28 Wortung $1 68 50 Update:

57 54 lTotat 144 173 O

Unit 1991 1992 1993 1994

'1995 ilts.

'2f98 '

'.3f98 6

SBS 4196 7f96

, afts 9796 10/96 11196 12C4

- PTM 240 242 230 219 170 170 155 153 157 152 144 PSL 316 326 269 274 285 202 303 295 227 223 173 DEFINITION This indcator tracks the total number of PCMs in the modification cycle. The purpose is to provide management a sna of the number of PCMs. Include al1 PCMs in design (not issued to the plants) review (issued to the plants for revie implementation or drawing update phases. The PC/M is considered open until drawing update is complete.

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE PERFORMANCE

SUMMARY

Data Providers: (PTN) Isidro Rosec02464184 and (PSL) Paul Basile 467-7397 H1

1

+

[

OPEN TEMPOR RY SYSTEM ALTERATIONS 4

4 80 l --*-- PTN ;

I --0-- PSL }

25 J

^

20 (l

15 v

10 g

6 I

O

' " Unit '

1991 r1992 ' 1 993

.1994

• 1996

128 '

2f98i d af96 6

>848

> efts

-7f96

, Set

. Sf96 10f96 11f98 12f98 PTN.

A 6

6 2

3 6

3 3

2 0

0 0

1 PSL 17 15 16 21 24 27 19 20 1W 16 18 16 DEFINITION I

j A temporary system alteration is a modi 6cabon made to plant equipment, mrnponents, or systems that does not conform with approved drawings or other design documents; a modi 6cabon that is necessary for continued safe plant operation; a modification that will remove a nuisance or distracbon to the Plant Operators; a irMfuuvii necessary to enable the plant to start upin a safe manner.

l STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE g

Year End Goal PTN 1

5 PSL 15 10 PERFORMANCE

SUMMARY

Data Provders: (PTN) Juho Balaguero 2464971 and (PSL) Kris McNndroo 467 7482

.H 2 1

. _ = -. _.

..~.

CONTAMINATED FLOOR SPACE e

6000

--+- PTN

- PSL 1

i 6000 i

4000 3000 k

^

2000

\\

.1 1000 a

0

+ : Une 1991 1992 t1993 1994 t1995 1JOS '

2 98.

13798 6-

. 5f98 6/96 47496 Sit $ '

- 9f98 "

10f94 11/9A

'12f96

- PTN 1750 50 330 700 3748 32 559 77 1048 250 489 312 229 i

PSL-5610 4351 4600 2048 1480 250 280 12 12 4354 2725 800 505 242 540 0

4 DEFINITION j

This indicator, designed to measure contaminated floor space with removable siivity 11000 dpm/100cm sq. beta / gamma or 120 dpm/100cm sq. alpha, is counted against the base. Areas that can be specrfically exempted from the base indude: 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 induded as part of ' recoverable' floor space (i.e. not considered floor area you can walk or step on).

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

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

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE

!LqY IAsti i

PTN 229 50 PSL 0

50 PERFORMANCE

SUMMARY

1 Turkey Point's Contaminated Floor Space was higher than the year-end target Data Providers: (PTN) John 1jndsay 2464548 and (PSL) Hank Buchanan 467-7300 l

l-1

DRY ACTIVE WASTE: GENERATED, SHIPPED OFFSITE (Year.t>Date) 20000 PTN Generated o

10000

.. +..PTN Shipped

--o-PSL Generated isooo.

- - o- - PSL Shipped O

14000

-a f

10000 p'

Cu

/'

a

,ooo

/,

M 6000 s'

p... q....e JJ

~

y

_... ~

0

^ u theR';.

1991

'1992 1993

• 1994 1998

+1f98 2fts J346 4 98

.5fts afts 17f96 '

.Sf98 Sf96 -

10f98 11f98 12f96 8100 425 515 3925 4115 4355 4675 5285 5415 5655 5775 6275 Pres ennessess r

PTRISNpped u 3 2560 0

0 0

0 0

2560 2560 2560 4368 4368 4368 11740 0

820 1845 2595 7595 13040 14950 16060 16310 17470 17745 PSLeonensed +

POLONpped a 13003 0

2000 3120 5314 7508 9702 11896 11896 11896 16284 18478 DEFINITION Generated. is an es'dmate based on the number of 'yeRow bags' initially generated prior to surveying for free release or shipment as radwaste.

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

1 Shiooed offsite. The amount of dry active radioactnfe waste that FPL ships to either Scientific Ecology Group Inc. (SEG) or American Ecology Recycle Center (AERC) for promssing.

i STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE PSL made 6 shipments to SEGin 1995.

PTN made 3 shipments to SEGin 1995.

t PERFORMANCE

SUMMARY

1 St Lucie shipped 2,194 Cubic Feet of Dry Active Waste in November.

Data Providers: (PTN) John Undsay 246-6548 and (PSL) Hank Buchanan 467-7300 12

~.. _ _.

- _ - ~.

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

4 e

PERSONNEL CONTAMINATION EVENTS (Year-to-Date) i I

180

+ PTNI 160

,q) pgt 1

140 120 100

^

80 3

7 1

0 60

^

40 20 W

O

. tine 1991 1982 1993 1994 1995 %.

M 3rts

-4788 Sits

< 8its 7/96 SISS

-SfBS 10fDS 11/96 12/96

-PTN 163 85 95 100 73 4

9 23 32 _ 36 38 43 47 52

'54 55 PSL 87 76 84 82 0

2 2

6,, 53 92 93 95 95 95 95 DEFINITION This indicator is designed to monitor personnel contaminatkn. A personnel contamination exists when 5000 dpm per 100cm2 on skin or personal clothing as detected by Personal Contamination Monitor and >100 counts per minute (net) using the Friskeris observed.

5 l

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Noy Y T-D o

PTN 1

55 PSL 0

95 PERFORMANCE

SUMMARY

Data Provders:(PTN) John Undsay 2464548 and (PSL) Hank Buchanan 467-7300 13

V

~

s RADIATION EXPOSURE (Year-to-Date) 1000 T

--*- PTN Y-T-D l

-O-PSL Y-T-D

\\'

2 700

\\

s. -

I PSL Y-E Target 485 I I W

O O

O O

N PTN Y-E Target: 275 I I L

m 0

/J

_s PTN Y-Te -

938 0 3249 281 8 478.2 214 6 5.3 9.5 150.2 185.5 188.7 171.0 172.8 1754 178 0 181.0 185.3

' PSLY T4 -

451.3 244.5 4599 504.7 412.8 3.0 9.0 13 0 21.9 209.2 321.9 371.3 374 6 377 4 381.2 383.8 DEFINmON Collective Radiation Exposure is the total effechve dose equivalent received by all on-site personnel (sicluding contractors and visitors), it includes extemal deep dose as measured by the thermoluminescent dosimeters (TLD's) plus intemal dose. It is reported in man-rem for the station. Current month readings may be taken from the direct reading dosimeters (DRD's).

STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Nov M

YTD Taroet Man-Rem PTN 47 185.3 270.0 WANO (PWR's)

(two units)

PSL 2.6*

383.8 476.0 1995 Median 306 Year-End Targets:

1995 Goal 370 PTN: 275.0 PSL: 485.0 PERFORMANCE

SUMMARY

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

Data Providers-(PTN) John Lindsay 24M548 and (PSL) Hank Buchanan 467-7300 I-4

l 6

O&M BUDGET-DMSION (Year-to-Date) j 2

j 350.0 j ---4--- Actual

.,,a****

J...... Budget j

I 250.0 f 200.0 1s0.0 -

i 100.0 s0.0 00 1991 1992 190s 1994 1595 1/99 ASS 3/96 4#94

. Ef96 4#98 7/98'

.8194

> 9f96 10f98

11/96 12/96 Ac8 uni -

342 4 295.2 290 6 285.2 269 5 13 4 31.2 67.4 96 7 128.5 162.2 181.9 195 8 232.5 246 9 262 4 Seedget 333 3 314 6 326 4 302.0 279.2 17.8 36 7 75 8 104 8 129 6 147.4 164 0 179 6 220.1 237.0 262 0 292.3

. verennes og -

27 6.2 11.0

-56 3.5

-24 8

-14 9 11.1 7.8 09 10 1 11.1 90 57 4.2 0.2 l

DEFINITION Operating and Maintenance Expenditures include Nuclear Division operation and maintenance expenses associated with direct employees, contractors and consultants, equipment, tools, design, engineering and other items / activities required to sustain the electncal generation of the plants and to provide required support. Fuel costs, mrporate administrative and

]

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

Y.T-D Actual Expenses Y T-D Budaeted Excenses x 100% = O&M Variance %

Y T-D Budgeted Expenses STATISTICAL

SUMMARY

INDUSTRY PERFORMANCE Novy.T-D Actual ($M)

Y.T-D Variance ($M)

O&M Budoet 1996 262.4 ($M) 0.4 ($M) 0.2%

IBG Actual 1995 Average

$334.1M 19L4 242.9 ($M) 11.9 ($M) 4.7%

IBG Top Quartile Entry

$277.6M IBG Top Quartile Average

$234.2M 1996 Y-E Budget 292.3 ($M)

PERFORMANCE

SUMMARY

O&M Expenditures through November 1996 were $262.4 miUion which represented a budget overrun of $0.4 minion (or 0.2%). Significant contributors to the variance include: St. Lucie Unit 1 outage scope changes offset by transfer of the Turkey Point Termal Uprae Project frorn O&M and by project and material purchase cancenations.

Data provider: Laurie Hertzhn 694 4631

)

J-1

f sus CAPITAL BUDGET-DMSION (Year-to-Date) 100.0 160.0 Budget [

1 j

140.0

\\\\

120 0 100.0

...K..

80.0 V"-

60.0 I

.0.0 20.0

,...... f -

~

0.0 1991 1992

'1993 1994 1996 2

r2f98 M

M

' Sf96 Sf98 7dDS OfB6 Sf85 10ft$

11J96 1 arts Actual-150 7 68 4 90 3 76 5 47.2 15 2.5 29 6.3 93 12.1 12 9 15.7 16 4 21.5 Sudget 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 39.2 Vertence r%)

-16 1

-90 11 0 12.7

-27.0 87.6

-65 0

-73 7

-59 7

-47.7

-38 6 428

-40 4

-40 9

-28.3 DEFINITION Capital Expenditures are those directly incurredbudgeted by the Nuclear Division for the construction of new utility plant additions and improvements made to increase efficiency, reliability or safety. Capital fuel costs are excluded.

Y T D Actual Exoenses -Y-T-D Budoeted Exoenses x 100% = CapitalVariance %

Y T-D Budgelad Expenses STATISTICAL

SUMMARY

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

Caprtal Budaet 1996 23.5 ($M)

-9.6 ($M) 29.0 %

IBG Actual 1995 Average

$75.8M 1995 37.5 ($M)

-19.4 ($M) 34.0 %

IBG Top Quartile Entry

$42.6M IBG Top Quartile Average

$27.2M 1996 Y-E Budget 39.2($M)

PERFORMANCE

SUMMARY

Capital Expenditures through November 1996 were $23.5 million which represented a budget underrun of $9.6 million (or 29.0%). Significant contributors to the variance include: Plant protects cancelled / deferred /or reclassrfied as O&M; and, underrun in the Steam Generator Replacement Projec'(SGRP).

Data provider. Laurie Hertzhn 694463t J-2 9

4 INTERNAL DISTRIBUTION:

R.J. Acosta JNA/JB D. E. Jemigan PTN/ PLT T.V. Abbatiello PTN/ PLT H.H. Johnson PSUPLT M.

Allen PSUPLT V. A. Kaminskas

- PTN/ PLT L.W. Bladow PSUPLT R.

Kundalkar JPN/JB G.J. Boissy PSUPLT J. T.

Luke PTN/ PLT J.B. Brady CC/JB J.

Marchese PSUPLT J. L.

Broadhead JEX/JB R.D. Mothena JNE/JB R. L. Castro JDC/JB H.N. Paduano JPN/JB J.

Clay PSUPLT J. G. Pizzutelli JNE/JB K. R. Craig JPN/JB R.

Rey ETS/JB R. E. Dawson PSUPLT D.

Ssmil FNG/JB D. J. Denver -

PSUPLT J.

Scarola PSUPLT M. S. Dryden JNUJB C.H. Shotweli JHR/JB D.

Fadden PSUPLT J. A.

Stall PSUPLT 4

]

J.R. Hartzog PTN/ PLT R. A. Symes JNA/JB R.G. Heisterman PTN/ PLT J.

Voorhees PSUPLT i

G.

Hollinger PTN/ PLT C.

Villard JPN/JB R.J. Hovey PTN/ PLT E.

Weinkam PSUPLT M.

Huba PTN/ PLT R.

West PTN/ PLT EXTERNAL DISTRIBUTION:

W. R. Corcoran W. Bearden 21 Broadleaf Circle Nuclear Regulatory Commission Windsor,CT 06095 101 Marietta Street N. W., Suite 2900 Atlanta, GA 30323-0199 T. P. Johnson NRC Senior Residentinspector Kerry D. Landis, Region 11 PTN/ PLT Nuclear Regulatory Commission 101 Marietta Street N. W., Suite 2900 Atlanta, GA 30323-0199 f

I Z-1 i

I

I@

l FPL l

l NRC STATUS UPDATE l

11/1/95 L

l l

ST. LUCIE NUCLEAR PLANT PLAN TO IMPROVE OPERATIONAL PERFORMANCE

1 i

I AGENDA I.

OPENING REMARKS D. SAGER II.

RESOLUTION OF LONG-STANDING J. SCAROLA PROBLEMS III.

PERSONNEL PERFORMANCE J. SCAROLA IV.

EQUIPMENT PERFORMANCE L. ROGERS D. DENVER V.

PROCEDURE IMPROVEMENT J. WEST VI.

ASSESS / TREND PLANT EVENTS B. DAWSON W. BLADOW i

VII.

SUMMARY

D. SAGER e

.i.

7--

OPENING REMARKS OPERATIONAL PERFORMANCE PLAN DEVEL.OPED FROM '

FPL/NRC/ INDEPENDENT TEAM KEY AREAS OF PLAN RESOLUTION OF LONG-STANDING PROBLEMS EQUIPMENT PERFORMANCE PERSONNEL PERFORMANCE PROCEDURE IMPROVEMENT ASSESS / TREND PLANT EVENTS i

i 5

1 i

i r

OPENING REMARKS (cont'd)

HAVE MET ALL ACTION PLAN COMMITMENT DATES FOCUSING ON PLJiANENT PROGRAM AND PROCESS CHA.NGES CORRECTIVE ACTION PROGRAM (STAR) IS KEY TO

!9iCCESS J

)

l 2-

F I

RESOLUTION OF LONG-STANDING PROBLEMS UNIT 1 EQUIPMENT PROBLEMS

~

PZR CODE SAFETIES PORVs IB DIESEL GENERATOR RCP PUMP SEALS SAFETY RELIEF VALVES CONTAINMENT SPRAY VALVE OPERATIONS PERSONNEL DETERMINED WORK SCOPE ADDITIONS EQUIP OUT OF SERVICE STARS PLANT WORK ORDERS CAUTION TAGS PLANT MODIFICATIONS JUMPERS / LIFTED LEADS OPERATOR WORKAROUhTS RECOGNITION AND RESOLUTION OF DEFICIENCIES 3-j

p RESOLUTION OF LONG-STANDING. PROBLEMS (cont'd)

RESOLUTION OF UNIT 2 EQUIPMENT PROBLEMS EXCORE NI REPLACEMENT INCONEL 600 NOZZLE REPLACEMENT CONDENSER CLEANING SYSTEM STANDARDIZE SCOPE REVIEW PROCESS:

" ASSESSMENT OF ABNORMAL PLANT CONFIGURATIONS OR SIGNIFICANT MATERIAL DEFICIENT CONDITIONS ON PLANT OPERATION" OPERATIONS SETS THE PRIORITY l

SENIOR MANAGEMENT APPROVAL l

l 4

r

(

l l

5 RESOLUTION OF LONG-STANDING PROBLEMS (cont'd)

PERSONNEL PERFORMANCE HAS NOT BEEN ADEQUATE i

i REVISED CONDUCT OF OPERATIONS 9

'l PROMPT ATTENTION TO ERRORS THOROUGH ANALYSIS FOR LESSONS LEARNED J

i f

6 5

t EQUIPMENT PERFORMANCE STRENGTHENED TECHNICAL LEADERSHIP STRENGTHENED ROOT CAUSE ANALYSIS IMPROVED MANAGEMENT VISIBILITY OF EQUIPMENT PERFORMANCE EXPEDITE REDUCTION OF OPERATOR WORKAROUND5 IMPROVE POST MAINTENANCE TEST PROGRAM IMPROVE QUALITY OF WORK PERFORMED BY CONTRACTORS

^

i i

6

y' t-

. PROCEDURE IMPROVEMENT PROCEDURE REVIEW PROCESS STRENGTHENED:

TECHNICAL REVIEWS FOR FIRST-TIME USE OF i

i PROCEDURES OR UNUSUAL CONDITIONS I

l FACILITY REVIEW GROUP (FRG)

RESPONSIBILITY OF SERVICES MANAGER VOLUME OF MATERIAL REVIEWED IS REDUCED TECHNICAL MANUAL REVIEW i

SCREENING SUBCOMMITTEE ESTABLISHED 4

DEPARTMENT PROCEDURES 4

7 i

t t

PROCEDURE IMPROVEMENT (cont'd)

PROCEDURE UPGRADE PROCESS i

OPERATIONS PROCEDURE UPGRADE DEDICATED SIX (6) PSL SENIOR REACTOR OPERATORS PHASE I - PLANT MANEUVERING PROCEDURES (16)

PHASE II - NORMAL /OFF-NORMAL PROCEDURES (80) t MAINTENANCE PROCEDURE UPGRADE l

I DEDICATED THREE (3) EXPERIENCED MAINTENANCE SUPERVISORS PROCEDURES BEING PRIORITIZED J

8 A.

r ASSESS / TREND PLANT EVENTS MISSION - INFORM MANAGEMENT OF UNDESIRABLE TREND OR CONDITIONS CORRECTIVE ACTION PROCESS IMPROVEMENTS ST. LUCIE ACTION REPORT (STAR)

IMPROVE PROCESS BY BENCHMARKING 1

(TURKEY POINT /VEPCO/ENTERGY) 1 PROGRAM CHANGES FOR REPORTING / TRENDING ADD REMAINING SOURCES TO DATABASE 4

i

.g.

A

A l

ASSESS / TREND PLANT EVENTS (cont'd)

SELF-ASSESSMENTS USE OF OUTSIDE PERSONNEL CONTROL ROOM LOG IMPROVEMENTS t

REMOTE ACCESS BETTER USE.OF SHIFT TECHNICAL ADVISOR (STA) i ASSIGN TO OPERATIONS MANAGER REMOVE ADMINISTRATIVE DUTIES i

-10

/

1 7

I ASSESS / TREND PLANT EVENTS (cont'd)

MANAGEMENT WILL REVIEW QA AUDIT INSPECTION PLANS QUARTERLY THE INITIA.L MEETING REVIEWED THE FOURTH QUARTER INSPECTION PLAN DELEGATE QA MANAGEMENT OVERSIGHT OF STEAM GENERATOR REPLACEMENT PROJECT FROM QA MANAGER TO QA SUPERVISOR 1

ESTABLISH A. ROTATION PLAN FOR LINE/QA EMPLOYEES FOR 1996

?

4 PARTICIPATE IN QA AUDIT TECHNICAL SPECIALIST EXCHANGE PROGRAM WITH OTHER UTILITIES

)

.)- - --

y

SUMMARY

ST. LUCIE PLANT HAS BEEN AN INDUSTRY LEADER IN THE PAST 4

OUR PERFORMANCE DECLINED-BUT WAS NOT IMMEDIATELY RECOGNIZED BY PLANT MANAGEMENT t

COMMITTED TO NOT REPEATING THIS EXPERIENCE:

UPGRADING "LANT OPERATING AND MAINTENANCE PROCEDURES MORE OPEN TO OUTSIDE INFLUENCE AND INPUT l

ESTABLISHED BETTER INDICATORS AND CONTINUOUS SELF r.lESSMENT TRENDING MORE CRITICAL OF PLANT OPERATION IN THE FUTURE AS PLAN IS COMPLETED, MONTHLY MANAGEMENT MEETINGS WILL ENSURE ACTIONS CONTINUE TO BE EFFECTIVE IN THE FUTURE 1

I i'

12

.3

... _.. ~. _..

...._.-__-..__...-__.___-...._-...._-_m....._.-.,_--=-.._..___.m.-..

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

~

i i

l s

i ST. LUCIE PLANT l

PLAN TO IMPROVE OPERATIONAL PERFORMANCE l

I i

A i

i Flev. 2.11/l/95 i

.w -

~

- PROBLEM #1:

- Acceptance Of'Long Standing, Repetitive Problems By.

4 Plant Management ITEM ACTION DESCRIPTION DATE 1-Immediate work stoppage on Unit 1 Employee meetings were held with President-Nuclear-to impress on'all personnel the need Division, Site Vice President, and' Plant General Complete for change.

Manager. Meetings focused on the need to reduce equipment deficiencies which impact operations.

2 Kept Unit I shut down to correct Existing deficiencies (including work orders, jumpers, deficiencies which could impact St. Lucie Action Reports and caution tags) were operations.

reviewed by senior plant management. 83 deficiencies which could adversely impact operations were added Complete to the work scope of the Unit I shutdown: These deficiencies were corrected prior to returnii.g the Unit j

to service.

[

3 Unit 2 was maintained at reduced A plant modification was implemented to eliminate a power to resolve a long-standing history of low flow trips on the Heater Drain pumps.

C.omplete IIcater D' rain pump problem.

The same modification was made on Unit 1.

]

4 Improve the process for ensuring Administrative Procedure, " Assessment of Abnormal timely resolution of existing Plant Configurations or Significant Material Deficient deficiencies.

Conditions on Plant Operation," was developed to Complete enhance outage scope review and ensure that equipment deficiencies are restored in a timely manner.

Rev. 2.11/1/95 -.

.<w2

~

-.r y

PROBIEM #1:

Acceptance Of Long Standing, Repetitive Problems By Plant Management (continued)

ITEM ACTION DESCRIPTION DATE 5'

Identify and correct deficiencies on A review of the scope for the upcoming Unit 2 Unit 2 refueling outage was completed, which utilizes the new outage scope review process. Appropriate activities were added to the scope of the outage.

Complete To accommodate the increased scope of the Unit 2 refueling outage, and to provide an added measure of conservatism, the planned-fuel shuffle has been replaced by a complete core offload / reload sequence.

t s

l

(

l l

Rev. 2,11/1/05 l

l PROBLEM #2:

Equipment Performance Is Not Satisfactory i

ITEM ACTION DESCRIPTION DATE i

i Strengthened technical leadership.

Vacant Technical Manager position was filled on

(

September I,1995.

Consolidated plant engineers from the Maintenance Department into the Techni~ cal Department.

Complete i

Suspended SRO certification course. The Engineering Manager and Maintenance Manager returned to normal duty on August 19,1995. They will complete this course at a later date.

l 2

Strengthen root cause analysis.

Reinforced and carried out the Division policy that l

defines the threshold of when a formal root cause should be executed and standardizes root cause format.

Complete R2 l

Refresh key personnel in the new technical group and l

engineering in root cause analysis methods.

l 3

Improve management visibility of Established weekly management review of approp,riate equipment performance problems.

performance indicators and work backlog status, including magnitude of work, age of open items, and operator workarounds*.

Complete

• Operator workarounds at St. Lucie include operator inconveniences which are categorized separately by other utilities.

iI

. Rev. 2.11/1/95 e,

---x

. - ~ ~ - _.

s.

,4_..

PROBLEM #2:

Equipment Performance Is. Not Satisfactory (continued).

I ITEM ACTION DESCRIPTION DATE 4

Expedite reduction of operator 83 operator workarounds exist. These will be reduced 6/1/96 workarounds.

by half.

5 Improve the post maintenance test Test groups were consolidated under a single program to ensure equipment will manager reporting to the Operations Manager on Complete operate as designed in the plant.

September 1,1995.

Review Unit 2 outage scope test procedures to ensure 11/9/95 critical component functions are addressed.

Revise process for post maintenance testing to improve coordination between Outage Management, Operations 1/1/96 and Maintenance.

6 Improve quality of work performed Re-emphasized that each FPL centract administrator by contractor personnel.

is accountable for the quality of work performed by contractors.

Provided training /re-training for FPL personnel assigned duties as contract administrators.

Technical and engineering personnel will review Complete R2 procedures used by contractors during the upcoming Unit 2 refueling outage to identify quality control attributes / processes and desired confidence levels

' deemed critical for equipment performance.

Inspection plans to meet these specifications will be developed.

Flev. 2,11/1/95 ---

,w.w em.

PROBLEM #3:

Personnel Performance Has Not Been. Adequate ITEM ACTION DESCRIPTION DATE I

Reinforcement of management Plant meetings have been held to reinforce high expectations at Manager / Supervisor standards of personal accountability and will continue level.

periodically. Nuclear Plant Supervisors met with their Complete crews to set clear expectations for error-free performance.

2.

Increase managemen: oversight.

Managers and supervisors have been directed to spend significantly more time monitoring work areas under Complete their oversight.

3 Push high standards of accountability Reinforced expectations of recognition for superior throughout the organization.

performance and discipline for subs'tandani Complete performance.

4 Assess ability of first line The independent assessment team identified this as an supervision to address personnel area for further evaluation. Conduct an assessment of 12/10/95 perfonnance issues.

this issue and develop an action plan to resolve.

Rev. 2,11/1/95.

a r n

. PROBLEM #4:

Procedures Have Been Approved With Technical Deficiencies-9 ITEM ACTION DESCRIPTION DATE 1

~ Improve the technical review for Plant Policy 105 has been revised to include a first-time use of procedures under technical review for first-time use of procedures under conditions different than originally conditions different than originally intended.

Complete intended.

This policy has been integrated into the Infrequently Performed Test and Evolutions procedure.

2 Improve the Facility Review Group FRG administrative accountabilities have been-(FRG) process so that senior plant transferred from the Plant General Manager to the Complete R2 managenent can apply greater focus Services Manager.

to safety-significant procedures.

(

Reduce the volume of material reviewed by the FRG.

Maintenance has redefined the review criteria for work Complete orders that reference Technical Manual instructions.

q Es%'olish a screening subcommittec [similar to the Company Nuclear Review Board (CNRB) i subcommittee] to allow the FRG to perform a Complete R2 more detailed critical review of safety-significant

~

procedures.

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.i Convert those procedures which are not required by Technical Specification 6.8.1 to departmental 2/29/96 guidelines.

i Rev. 2.11/fl95 '

,7 PROBLEM #4:

Procedures Have Been Approved With Technical Deficiencies-

[

(continued)

=

ITEM ACTION DESCRIPTION DATE 3

Expedite correction of errors in plant Place emphasis on accountability of a procedure user procedures to ensure that the procedure is correct and adequate.

Adopt the definition of' procedure compliance Ccmplete R2 consistent with Turkey Point Plant.

Establish a schedule for upgrade of Operations Normal and Off-Normal procedures.

i Rev. 2.11/1/95 t

a h

PROBLEM #5:

Management Is Not Provided With Sufficient Information To Assess / Trend Plant Events ITEM ACTION DESCRIPTION DATE 1.

Improve assessment of deficient Combined the personnel from St. Lucie Action conditions.

Request (STARS), In-House Event (IHEs), and Complete Human Performance Enhancement System (HPES) into a single group.

Include all data bases in trending effort, including 12/31/95 Operations, Security, Health Physics and Safety.

Policy established to integrate personnel from outside St. Lucie Plant into benchmarking efforts and plant Complete assessments.

2 Better utilize Quality Assurance Management will rev4w QA audit inspection plans (QA) capabilities.

quarterly. The initial meeting reviewed the fourth Complete quarter inspection plan.

Delegate QA management oversight of Steam Generator Replacement Project from QA Manager Complete to QA Supervisor.

Establish a rotation plan to line/QA employees for 12/31/95 1996.

Participate in QA Audit Technical Specialist Exchang 12/31/95 Program with other utilities.

Rev. 2,11/1/95 - -

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I PROBLEM #5:

Management Is Not Provided With SuiTicient Information l

To Assess /frend Plant Events (continued)

. ITEM ACTION DESCRIPTION DATE i

-3 Upgrade log-keeping activities to Management is conducting a daily review of Control supply better communications to Room logs to reinforce the expectations for detail and Complete management.

completeness.

Computerize Control Room logs and make logs Complete R2 available to management electromcally.

4 Improve focus of the Shift Technical Reassign the STA's to the Operations Department.

Complete l

. Advisor (STA) during normal plant operation.

Reduce STA administrative duties.

12/31/95 Rev. 2.11/1/95.

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FLORICA P0t(R AND LICHT MANACDENT OvCRVIEW PRE 5!OENT NUCLEAR OtVtSION T. T. Plunkett 3/96 (407) 694-4222 I

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VICE PR[510ENT 14ANAGER OIRCETOR NUCLEAR MANACER VIEC PRESIDENT VICE PRES! DENT

[MCINEERING ANO LICEN51NG ANALY315 AND [0 Nit 0L5; SERVICES NUCLEAR ASSURANCE ST. LUCIE PLANT ftRKEY POINT plant R. Kundalkar Robert Wade 3/91 Robert Accosta 4/96 J. A. Statt 5/96 R. J. Hovey 11/95 (407) 694-3241 (407) 694-3786 (407) 694-3592-(407) 694-4630 (407) 468-4100

-(305) 246-6190 ST. LUCIE STEAna CENERATOR NUCLEAR TRAINING 3

PLANT CENERAL MANACER PLANT CENERAL MANAGER PROJECT MANAGER MANACER ST. LUCIE Richard Sipos 10/93 TURKEY POINT Kenneth Beatty 4/92 (407) 694-3217 Jim Scarola 6/95 Don E. Jern19an 11/94 (407) 694-4217 (407) 458-4103 (305) 246-6180

[NCINEERIkG MANAGER WU[t[AR $((URITY St. LUCIE MANACER Dan Denver 9/94 Cary Mayer 11/93 (407) 466-4109 (407) 694-3992

[NGINEERING MANACER TURKEY POINT Tom Luke 2/96 (305) 246-6431

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. Thomas F. Nnkett seues as peakient d the nucisar dMobn and member of the board of droctors at Flockie Power & Ught Company, in thne espedty. Mr.

Munkett oversees the operation of FPL's four nudear units, two at Turkey Point in south Dede County and two at St. Lucie on Hutchinson Islatud h St Lucie County as well as the associated technical support actryllies at corporate headquarters in Juno Beach, Florida.

Mr. Nnkett, a 33-year veteren d the nuclear power industry, began working for FPL in 1990 as vios prooident of the Turkey Pdm nodar power plert,.

During his tenure at Turkey Point. the taoility progressed from one of the ratbn's most troubled nuclear power stations to one of the best.

i Prior 6)obing FPL W. Pfunkett serwd as gwwn! manager d the hf Dend nuclear power station for Gutf States thTrties Company b Louisana. Mr.

Plunkett began his career with McDonnel Douglas

's nudear department. He later aefvod as a technical supervisor for and Michigen Power Com's D.C. Cook nudosi piant. In 1977, hk. Plunkett moved to llEnols Power Company as plant me.gr d the C6nton nucisar power station.

Mr. Plunkett la a Graduals d the Urdversity d Wisconsin with a 58 degree i

in mechanical engineering and an MS degree in nucioar enginsedng.

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I: P L John A. Stall Vice President, St. Lucie Plant' Art Stallis Plant Vice President of Florida Power & Light Company's St. Lucie Nuclear Power Plant. He reports to the Nuclear Division President and oversees the operation of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach. Mr Stalljoined FPL ir. May 1996.

Mr. Stall previously served as Station Manager for Virginia Power Company at the North Anna nuclear plant. He joined Virginia Power in 1977 and held various positions of increasing responsibility, including superintendent of operations, assistant station manager for safety and licensing, and superintendent of technical services. A career nuclear professional, Mr. Stall brings his extensive experience to St. Lucie and will play an important role in the continued performance and efficiency improvements.

Mr. Stall earned his Bachelor of Science degree in nuclear engineering from the University of Florida in 1977, and achieved his Master of Business Administration from Virginia Commonwealth University in 1983. Mr. Stallis a registered professional engineer and held a senior reactor operator license while at Virginia Power Company.

i Biographical lnformation I: P L 9

James Scarola Plant General Manager, St. Lucie Plant Jim Scarola is Plant General Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function Mr. Scarola reports to the Site Vice President. He is responsible for Operations, Maintenance, and technical Support activities at.the St. Lucie site located on Hutchinson Island.

Mr. Scarola began working for FPL in 1980. He has held a variety of positions of increasing authority, including !&C startup engineer, I&C maintenance engineer, assistant superintendent electrical maintenance, manager special projects, maintenance manager, manager equipment, support, and inspections, engineering project manager, and operations manager at St. Lucie.

Mr. Scarola holds a Bachelor of Science degree in Electrical Engineering from the University of Notre ' Dame and a Master of Business Administration degree from Florida Institute of Technology. Mr. Scarola has completed the senior reactor operator certification training program at St. Lucie.

1/96

Biographical Infor3 nation F:PL Edward J. Weinkam 111 Licensing Manager, St. Lucie Plant Ed Weinkam is Licensing Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this' function, Mr. Weinkam reports to the Site Vice President and is responsible for coordination of the St. Lucie Plant regulatory interface among the NRC Resident inspectors. NRC Region il Staff, and NRC Headquarters staff.

Mr. Weinkam began working for FPL in 1986. He has held a variety of positions of increasing authority, includir.g NRR licensing engineer and corporate licensing sur.svisor for the St. Lucie Plant, licensing manager for the Turkey Point Plant. He has worked in the nuclear industry since 1979 in various engineering, educational, and regulatory areas. He was a U. S. Navy nuclear submarine officer, an engineering instructor at the University of Maryland, and USNRC, NRR project manager. Mr. Weinkam completed certification as a senior reactor operator at the Turkey Point nuclear units.

Mr. Weinkam is a graduate of the University of Notre Dame and holds a Bachelor of Science degree in Mechanical Engineering-He received a Master of Science in Mechanical Engineering from the University of Maryland in 1979.

4 i

1/96 i

T 1

Biographical Information F:PL Robert E. Dawson Business Manager, St. Lucie Plant Bob Dawson is Business Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant, in this function, Bob Dawson reports to the Site Vice President and is responsible for the strategic plan, the plant op3 rating plan, the corrective action program, and the in-house-event tracking and trend analysis programs at the St. Lucie Nuclear Plant.

Mr. Dawson began working for FPL in 1973. He has held a variety of positions of increasing authority, including reactor engineering department head at Turkey Point Plant, staff reactor support, mechanical startup group supervisor'for St. Lucie Unit 2, core barrel repair project, electrical maintenance department head, plant maintenance manager, and plant licensing manager. Mr. Dawson has held an senior reactor operator license at St. Lucie.

Mr. Dawson is a graduate of the University of Virginia and holds a Bachelor of Science degree in Nuclear Engineering.

He is a member of the American Society of Mechanical Engineers (ASME) and the Arnerican Nuclear Society (ANS).

1/96 l

Biographical Information G

FPL Daniel J. Denver Site Engineering Manager, St. Lucie Plant e

Dan Denver is the Site Engineering Manager for Florida Power & Light Company's St.

Lucie Nuclear Power Plant. In this function, Mr. Denver reports to the Vice President - Nuclear Engineering and Licensing and is responsible for engineering services including design packages, as-building, procurement engineering, fuel design, and outage NDE inspections for the two nuclear units at the St. Lucie site located on Hutchinson Island.

Dan joined Florida Power & Light Company in May,1993 as Director, Nuclear Technical Support in the Juno Beach offices. In this capacity, he was responsible for nuclear fuel supply, information services and the administrative staffs for Nuclear Engineering and Licensing. He has worked in the nuclear power industry since 1967 in various engineering and technology development areas. He worked for a number of electric utilities including Public Service Electric & Gas, Yankee Atomic, and Houston Lighting and Power as well as Westinghouse Electric and a nuclear industry services company, El Internctional.

Dan graduated from the University of Notre Dame in 1966 with a Bachelor of Science degree in Mechanical Engineering and received a Master of Science in Nuclear Engineering from Massachusetts Institute of Technology in 1967.

In outside activities, Dan has served in local town government and on the boards of several amateur theater organizations and professional societies. He is a registered professione1 engineer in the Commonwealth of Virginia.

Biographical lnformation I: P L L. Wesley Bladow Site Quality Manager, St. Lucie Plant Wes*Bladow is the Site Quality Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant, in this function, Mr. Bladow reports to the Vice President Nuclear Assurance and is responsible for independently assessing the Quality Control and Quality Assurance Program implementation by the St. Lucie Nuchsr Plant.

Mr. Bladow began working for FPL in 1967 in the Distribution Engineering Department.

He has held a variety of positions of increasing authority, including quality assurance supervisor, quality assurance superintendent, and site quality manager at the Turkey Point Nuclear Plant and quality assurance manager of the St. Lucie Unit 1 steam generator replacement project, and manager of nuclear safety speak out.

Mr. Bladow is a graduate of Florida International University and holds a Bachelor of Science degree in Industrial Technology with a minor in industrial safety.

Mr. Bladow is a member of the American Nuclear Society.

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' 19 6

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FPL Dennis L. Fadden Services Manager, St. Lucie Plant Dennis Fadden is Swices Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In thi. ' unction, Mr. Fadden reports to the Site Vice President. He is responsible for Training, Fire Protection, Emergency Planning, Land Utilization, Security', and Information Services at the St. Lucic site.

Mr. Fadden began working for FPL in 1996. Before joining FPL he held a variety of positions at the Institute of Nuclear Power Operations, conducting plant and corporate evaluations, along with accreditation evaluations. Mr. Fadden has a senior reactor operator certification at River Bend.

Mr. Fadden is a graduate of the United States Military Academy and holds a Bachelor of Science degree in Applied Science. Mr. Fadden also holds a Master of Business Adr.,inistration degree from Xavier University.

)

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Lynn Morgan Human Resources Manager, St. Lucie Plant Lynn Morgan is Human Resources Manager of ':lorida Power & Light Company's St:

Lucie Nuclear Power Plant. In this function, Ms. Morgan reports to the Nuclear Division Manager of Generation Human Resources. In this position Ms. Morgan is accountable for proper implementation of personnel policies and procedures at the St. Lucie Nuclear Plant.

Ms. Morgan began working for FPL in 1971 She has held a various positions, including compensation analyst for the Nuclear Division, project manager for the Child Development Center and Satellite Schop! at the Turkey Point Nuclear Plant, supervisor of Benefit Planning and Design, Retirement Coordinator and Human Resource generalist.

Ms. Morgan is a graduate of Florida Atlantic University and hcids an Bachelors degree in Human Resources. Mr. Morgan also holds a master's degree in human resources from Nova Southeastern University.

l F:PL Hugh H. Johnson Operations Manager, St. Lucie Plant Hugh Johnson is Operations Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. Johnson reports to the Plant General Manager and is responsible for Plant Operations, Operations Support, Health Physics, Chemistry Departments for the two nuclear units.

Mr. Johnson began working for FPL in 1981. He held a variety of positions of increasing responsibility at St Lucie from 1981 to 1985, including Reactor Control Operator, Senior Reactor i

Operator, and Assistant Nuclear Plant Supervisor. From 1985 to 1989, Mr. Johnson worked at Houston Lighting & Power-South Texas and held the positions of Shift Supervisor and Unit 1 Operations Manager. Mr. Johnson returned to FPL in 1989 at Turkey Point Plant and held the positions of Assistant Operations Superintendent, Operations Supervisor, and Operations

{

Manager. Prior to his tenure at FPL, he served in the U.S. Navy Nuclear Submarine Service.

Mr. Johnson has held a senior reactor operator's license at St. Lucie, Turkey Point and South Texas and is working toward a Nuclear Science Degree from Thomas Edison State College.

I Biographical lnformation O

I: P L Joseph Marchese Jr.

Maintenance Manager, St. Lucie Plant Joe Marchese is Plant Maintenance Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. Marchese reports to the Plant General Manager and is responsible for supervision and coordination of the maintenance activities including electrical, mechanical, instrumentation & control, records and planning at the St. Lucie Plant located on Hutchinson Island.

Wr. Marchese began working for FPL in 1984. He has held a variety of positions of increasing authority, including lead construction electrical supervisor -Turkey Point Plant, lead construction mechanical supervisor - Turkey Point Plant, site construction manager - Turkey Point Plant, and plant maintenance manager. Prior to his tenure at FPL, Mr. Marchese had 12 years nuclear experience in various positions of increasing authority with Bechtel Power Corporation, including Milestone, Davis Besse, and St. Lucie Nuclear Plants construction and stanup testing. Mr. Marchese completed the senior reactor operator certification training program at Turkey Point.

Mr. Marchese is a graduate of the University of Akron and holds a Bachelor of Science degree in Electrical Engineering. Mr. Marchese is a registered Professional Engineer in Florida and Virginia.

He is a member of the American Nuclear Society (ANS). '

I 1/96

9 I:PL Jeffrey A. West System & Component Engineering Manager, St. Lucie Plant Jeff West is System & Component Engineering Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function Mr. West reports to the St. Lucie Engineering Manager. He is responsible for the direction and coordination of the technical support to the Operations and Maintenance Departments and the coordination of issues technical and documents at the St. Lucie Plant located on Hutchinson Island.

Mr. West began working for FPL in 1980. He has held a variety of positions of increasing authority, including shift technical adviser, reactor control operator, nuclear watch engineer, assistant nuclear plant supervisor, technical training supervisor, nuclear plant supervisor, a sistant operations supervisor, assistant superintendent - mechanical s

maintenance, operations supervisor, services manager and operations manager. Mr. West has held a senior operator license at St. Lucie. Prior to his tenure at FPL, he held the rank of Lt.

Commander in the U. S. Navy Nuclear Submarine Service Mr. West served from 1974 to 1979.

Mr. West is a graduate of the University of Tennessee and holds a Bachelor of Science

1 degree in Electrical Engineering. Mr. West also holds a Master of Business Admiristration degree from Florida institute of Technology.

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Biographical Information I:PL JOSEPH MARCHESE JR.

Maintenance Manager, St. Lucie Plant Joe Marchese is' Plant Maintenance Mannper c,f Florida Power & Light Company's St.

Lucie Nuclear Power Plant. In this function, Mr. Marchese reports to the Plant General Manager and oversees the maintenance of the twc, nuclear units at the St. Lucie site located I

on Hutchinson island, approximately 50 miles r.crth of West Palm Beach.

Mr. Marchese began working for FPL in 1984. He has held a variety of positions of increasing authority, including lead constructico electrical supervisor -Turkey Point Plant, lead construction mechanical supervisor Turkey Pcint Plant, site construction manager Turkey Point Plant, and plant maintenance manager. Pr:or to his tenure at FPL, Mr. Marchese has 12 years nuclear experience in various positier.s ;,f increasing authority with Bechtel Power Corporation, including Milestone, Davis Besse, and St. Lucie Nuclear Plants construction and startup testing. Mr. Marchese completed the senior reactor operator certification training j

program at Turkey Point in 1992.

Mr. Marchese is a graduate of the Univers:ty of Akron and holdh a Bachelor of Science j

degree in Electrical Engineering. Mr. Marchese s a registered Professional Engineer in Florida.

I and Virginia.

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He is a member of the American Nuclu Society (ANS),

1 9/30/94 4

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Biographical Information 9

PPL J.H.GOLDBERG President, Nuclear Division J. H. Goldberg serves as President of the Nuclear Division and a member of the Board of Directors at Florida Power & Light Company. In this capaaity, Goldberg oversees the operation of FPL's four nuclear units, two at Turkey Point in south Dade County and two at St. Lucie on Hutchinson Island in St. Lucie County as well as the technical support activities at corporate headquarters in Juno Beach, Mr. Goldberg, a 38-year veteran of the nuclear power industry, began working for FPL in September 1989. Prior to that he worked for Houston Lighting & Power Company (HL&P) as group vice president, nuclear. During his nine years with HL&P, Goldberg was responsible for a number of milestones, including construction and licensing of the Soutn Texas Nuclear Project, the most advanced state of the art nuclear power stations in the U.S.

Before joining HL&P, he spent nine years with Stone and Webster Engineering Corp., overseeing the design, construction, operation and modification of numerous nuclear power stations in the U.S.

Earlier in his career, he worked for Bethlehem Steel Co. and General Dynamics Corp. in a variety of er:gineering and management functions associated with the design and construction of nuclear powered surface vessels and submarines for the U.S.

Navy.

Goldberg is a graduate of the U.S. Merchant Marine Academy and holds a master's degree in nuclear engineering from Massachusetts Institute of Technology.

He is a registered professional engineer in Texas, California, Virginia, Massachusetts, Rhode Island, Pennsylvania and New York. Goldberg has been affiliated with many nuclear industry organizations, including the Institute of Nuclear Power Operations (INPO), Electric Power Research Institute (EPRI), and the newly created Nuclear Energy Institute (NEI). Goldberg was elected a Fellow of the American Nuclear Society in 1994 S

9/94

+

Biographical Information O

I:PL

)

DAVID A. SAGER Vice President, St. Lucie Plant Dave Sager is Plant Vice President of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. Sager oversees the operation of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach, Mr. Sager, a 22-year veteran of the nuclear power industry, began working for FPL in 1975. He has held a variety o.f positions of increasing authority, including quality assurance engineer, technical staff engineer, operations supervisor, plant manager, staff vice president and plant vice president. Mr. Sager has held a ser:ior reactor operator license at St. Lucie.

Prior to his tenure at FPL, he held the rank of Lieutenant in the U. S. Navy Nuclear Submarine Service. Mr. Sager served from 1968 to 1975.

Mr. Sager is a graduate of the U. S. Naval Academy and holds a Bachelor of Science degree in Naval Engineering and a Master of Science degree in Mechanical Engineering. Mr.

Sager also holds a Master of Business Administration degree from Florida Institute of Technology.

He is a member of the American Society of Mechanical Engineers (ASME) and the American Nuclear Society (ANS). Mr. Sager is Vice chairman of the Combustion Engineering Owners Group (CEOG) Executive Committee and has served on the Institute for Nuclear Power Operations' National Academy of Nuclear Training.

9/30/93

Biographical Information 9

I:PL CHRISTOPHER L. BURTON Plant General Manager, St. Lucie Plant Chris Burton is Plant General Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. Burton reports to the Site vice President and oversees the operation of the two nuclear units at the St. Luciealte located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Burton began working for FPL in 1975. He has held a variety of positions of increasing authority, including reactor operator, nuclear plant supervisor, assistant operations supervisor, reliability maintenance supervisor, operations supervisor and operations manager.

Mr. Burton has held reactor operator and senior reactor operator licenses at St. Lucie.

Mr. Burton is a graduate of State University of New York and holds a Bachelor of Science degree in Electronics Technology. Mr. Burton also holds a Masters of Business Administration from Florida Institute of Technology.

He is a member of the American Nuclear Society (ANS) and the Professional Reactor Operator Society.

i 9/30/93 1

1

4 Biographical Information PPL C. ASHTON PELL Outage Manager, St. Lucie Plant Ash Pell is Outage Manager of Florida Power & Light Company's St. Lucie Nuclear I

Power Plant. In this function, Mr. Pell reports to the Site Vice President and oversees unit refueling outage performance at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Pell began working for FPL in 1975. He has held a variety of positions of increasing authority, including Reactor Engineer, Reactor Supervisor, Technical Staff Supervisor, Assistant to Senior Vice President Nuclear, Director Nuclear Administrative Services, Plant Services Manager and Outage Manager. Mr. Pell completed certification as a senior reactor operator for both the St. Lucie and Turkey Point nuclear units.

Mr. Pell is a graduate of the University of Central Florida and holds a Bachelor of i

Science degree in Physics.

He is a member of the Southeast section of the American Nuclear Society (ANS).

9/30/93

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J Biographical Information O

PPL 1

ANDREW DeSOlZA Human Resources Manager, St. Lucie Plant Ar: drew DeSoiza is Plant Human Resources Manager of Florida Power & Light j

Company's St. Lucie Nuclear Power Plant. In this function, Mr. DeSoiza oversees all human 1

resource activities for the St. Lucie Nuclear Plant.

Mr. DeSoiza began working for FPL in 1972. He has held a various positions, including payroll clerk and human resource manager.

Mr. DeSoiza is a graduate of Miami Dade Community College and holds an Associates of Arts degree in Business.

4 4

i 9/30/93,

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Biographical Information 9

I:PL DANIEL H. WEST Plant Technical Manager, St. Lucie Plant Dan West is Plant Technical Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. West reports to the Plant General Manager and oversees the operation of the technical department including the technical engineers, testing group and shift technical advisors for the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. West began working for FPL in 1980. He has held a variety of positions of increasing authority, including staff engineer, lead engineer, and technical department i

supervisor. He obtained a senior reactor operator license at St. Lucie. Prior to hic tenure at FPL, he was employed by General Electric Company at the Knolls Atomic Power Laboratory from 1973 to 1979.

Mr. West is a graduate of the U. S. Merchant Marine Academy at Kings Point and holds a Bachelor of Science degree in Marine Engineering.

He is a member of the American Society of Mechanical Engineers (ASME) and the American Nuclear Society (ANS).

9/30/93 i

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Biographical Information 9

I:PL Daniel J. Denver Project Engineering Manager, St. Lucie Plant Dan Denver is the Project Engineering Manager for Florida Power & Light company's 1

St. Lucie Nuclear Power Plant. In this function, Mr. Denver reports to the Vice President -

Nuclear Engineering and Licensing and oversees the Production Engineering, Site Engineering and Procurement Engineering groups for the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Dan joined Florida Power & Light Company in May,1993 as Director, Nuclear Technical Support in the Juno Beach offices. In this capacity, he was responsible for nuclear fuel supply, information services and the ad ainistrative staffs for Nuclear Engineering and Licensing. He has worked in the nuclear power industry since 1967 in various engineering and technology development areas. He wo'rked for a number of electric utilities including Public Service Electric

& Gas, Yankee Atomic, and Houston Lighting and Power as well as Westinghouse Electric and a nuclear industry services company, EI International. He graduated from the University of Notre Dame in 1966 with a Bachelor of Science degree in Mechanical Engineering and received a Master of Science in Nuclear Engineering from Massachusetts Institute of Technology in 1967..

In outside activities, Dan has served in local town government and on the boards of several amateur theater organizations and professional societies. He is a registered professional engineer in the Commonwealth of Virginia.

9/1/94

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Biographical Information 9

l PPL HERMAN L. FAGLEY Site Construction Manager, St. Lucie Plant Herman Fagley is Site Construction Manager of Florida Power & Light Company's St.

Lucie Nuclear Power Plant. In this function, Mr. Fagley reports to the Plant General Manager and oversees the construction services of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Fagley began working for FPL in 1978. He has held a variety of positions of increasing authority, including construction supervisor, start-up engineer, project site manager, staff specialist.

Mr. Fagley is a graduate from Brevard Junior College and holds an Associates degree and a Bachelor of Science degree in Building Construction from the University of Florida.

He is a member of the American Nuclear Society (ANS).

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Biographical Information i

9 FPL JEFFREY A. WEST Plant Services Manager, St. Lucie Plant Jeff West is Plant Services Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. West reports to the Site Vice President and oversees various departments, including Security, Fire Prctection, Safety, Environmental, Emergency Planning, Training, Information Management, Budget, and Administration at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. West, began working for FPL in 1980. He has held a variety of positions of increasing authority, including shift technical adviser, reactor control operator, nuclear watch engineer, assistant nuclear plant supervisor, technical training supervisor, nuclear plant supervisor, assistant operations supervisor, assistant superintendent - mechanical maintenance and operations supervisor. Mr. West maintains an active senior operator license at St. Lucie.

Prior to his tenure at FPL, he held the rank of Lt. Commander in the U. S. Navy Nuclear Submarine Service. Mr. West served from 1974 to 1979.

Mr. West is a graduate of the University of Tennessee and holds a Bachelor of Science degree in Electrical Engineering. Mr. West also holds a Master of Business Administration degree from Florida Institute of Technology.

9/1/94

J Biographical Information I

PPL f

JAMES SCAROLA Operations Manager, St. Lucie Plant J

Jim Scarola is Operations Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. Scarola reports to the Plant General Manager and oversees the operations, health physics, chemistry, and reactor engineering departments of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Scarola began working for FPL in 1980. He has held a variety of positions of increasing authority, including l&C startup engineer, l&C maintenance engineer, assistant superintendent electrical maintenance, manager special projects, maintenance manager, manager equipment, support, and inspections, and engineering project manager at St. Lucie.

Mr. Scarola holds a Bachelor of Science degree in Electrical Engineering from the University of Notre Dame and a Master of Business Administration degree from Florida institute of Technology. Mr. Scarola has completed the senior reactor operator certification training program at St. Lucie.

9/30/93

Biographical Information I:PL L. WESLEY BLADOW Site Quality Manager, St. Lucie Plant Wes Bladow is the Site Quality Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. Bladow reports to the Vice President Nuclear Assurance and rnanages the quality assurance and quality control departments of St. Lucie Nuclear Plant, Mr. Bladow began working for FPL in 1967 in the Distribution Engineering Department.

He has held a variety of positions of increasing authority, including quality assurance supervisor, quality assurance superintendent, and site quality manager at the Turkey Point Nuclear Plant and quality assurance manager of the St. Lucie Unit 1 steam generator replacement project, and manager of nuclear safety speakout.

Mr. Bladow is a graduate of Florida International University and holds a Bachelor of Science degree in industrial Technology with a minor in industrial safety.

Mr. Bladow is a member of the American Nuclear Society.

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Biographical Information 9

PPL ROBERT E. DAWSON Plant Licensing Manager, St. Lucie Plant l

Bob Dawson is Plant Licensing Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Bob Dawson reports to the Site Vice President and oversees all licensing activities associated with the operation of the St. Lucie Nuclear Plant. The St.

Lucie Plant islocated on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Dawson began working for FPL in 1973. He has held a variety of positions of increasing authority, including reactor engineering supervisor, staff reactor support, startup supervisor-mechanical, core.ba.rrel project, quality improvement, assistant superintendent-electrical maintenance and plant maintenance manager. Mr. Dawson has held an senior reactor operators license at St. Lucie, Mr. Dawson is a graduate of the University of Virginia and holds a Bachelor of Science degree in Nuclear Engineering.

I He is a member of the American Society of Mechanical Engineers (ASME) and the American Nuclear Society (ANS).

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• l Biographical Information PPL THOMAS G. KREINBERG Manager, Materials Management, St. Lucia Plant Thomas Kreinberg is Manager of Materials Management of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. Kreinberg reports to the sSite Vice President and oversees purchasing and procurement at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Kreinberg began working for FPL in 1980. He has held a variety of positions of increasing authority, including purchasing & contract services, contracts administrator, menager of contracts and manager materials management.

i Mr. Kreinberg is attended Syracuse University and holds a Bachelor of Arts degree in Russian and a Bachelors of Business Administration Ecuiomics from the University of Florida.

He is a member of Contracts Management Owners Group (Nuclear Power Utilities).

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M-I Biographical Information O

PPL ANDREW DeSOlZA H.uman Resources Manager, St. Lucie Plant a

Andrew DeSoize is Plant Human Resources Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. DeSoiza oversees all human resource activities for the St. Lucie Nuclear Plant.

Mr. DeSoiza began working for FPL in 1972. He has held a various positions,includina payroll clerk and human resource manager.

Mr. DeSoiza is a graduate of Miami Dade Community College and holds an Associates of Arts degree in Business.

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Biographical Information I:PL JAMES SCAROLA Operations Manager, St. Lucie Plant j

c Jim Scarola is Operations Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. Scarola oversees the operations, health physics, chemistry, and reactor engineering departments of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Scarola began working for FPL in 1980. He has held a variety of positions of increasing authority, including l&C startup engineer, l&C maintenance engineer, assistant superintendent electrical maintenance, manager special projects, maintenance manager, manager equipment, support, and inspections, and engineering project manager at St. Lucie, i

Mr. Scarola holds a Bachelor of Science degree in Electrical Engineering from the University of Notre Dame and a Master of Business Administration degree from Florida Institute of Technology. Mr. Scarola has completed the senior reactor operator certification i

training program at St. Lucia.

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Biographical Information 1:PL DANIEL H. WEST Plant Technical Manager, St. Lucie Plant Dan West is Plant Technical Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. West Mersees the operation of the technical department including the technical engineers, testing group and shift technical advisors for the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. West began whrking for FPL in 1980. He has held a variety of positions of increasing authority, inclujing staff engineer, lead engineer, and technical department supervisor. He obtained a senior reactor operator license at St. Lucie. Prior to his tenure at FPL, he was employed by General Electric Company at the Knolls Atomic Power Laboratory from 1973 to 1979.

Mr. West is a graduate of the U. S. Merchant Marine Academy at Kings Point and holds a Bachefor of Science degree in Marine Engineering.

He is a member of the American Society of Mechanical Engineers (ASME) and the American Nuclear Society (ANS).

9/30/93

Biographical Information I: P L JEFFREY A. WEST Operations Supervisor, St. Lucio Plant Jeff West is Operations Supervisor of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. West oversees the direction of all licensed operators within St. Lucie's operations department.

Mr. West, began working for FPL in 1980. He has held.a variety of positions of increasing authority, including shift technical adviser, reactor control operator, nuclear watch engineer, assistant nuclear plant supervisor, technical training supervisor, nuclear plant supervisor, a ssistant operations supervisor, assistant superinterulent - mechanical maintenance and operations supervisor. Mr. West maintains an active senici operator license at St. Lucie.

Prior to his tenure at FPL, he held the rank of Lt. Commander in the U. S. Navy N.uclear Submarine Service. Mr. West served from 1974 to 1979.

Mr. West is a graduate of the University of Tennessee and holds a Bachelor of Science degree in Electrical Engineering. Mr. West also holds a Master of Business Administration i

degree from Florida institute of Technology.

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Biographical Information i

9 PPL JAMES L. BROADHEAD Chairman and Chief Executive Officer James L. Broadhead is chairman and chief executive officer of FPL l

Group, Inc., a diversified holding company with utility and non-utility operations. He also is chairman and chief executive officer of FPL Group's principal subsidiary, Florida Power & Light Company, one of the largest electric utilities in the nation. FPL Group's diversified activities include non-utility energy production, agriculture, real estate development, and cable TV.

Prior to becoming associated with FPL Group in January 1989, Mr.

Broadhead was president of GTE Telephone Operations and a member of GTE's

+ board of directors. Before his association with GTE, Mr. Broadhead was president of St. Joe Minerals Corporation. He had previously served in a variety of positions there beginning in 1968, including general counsel, vice president of corporate development, vice president of finance for St. Joe Petroleum Corporation, and president of St. Joe Zinc Company.

Mr. Broadhead received a bachelors degree in mechanical engineering from Corne!! University in 1958 and a juris doctor degree from Columbia University Law Schoolin 1963. He is a director of Barnett Banks,Inc., Delta Air Lines,Inc., and the Pittston Company, and a Board Fellow of Comell University.

Mr. Broadhead, his wife and four children reside in Palm Beach County.

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i Biographical Information 9

PPL JEROME H. GOLDBERG President, Nuclear Division J. H. Goldberg is President, Nuclear Division at Florida Power & Light ' ompany. In this C

function, Goldoerg oversees the operation of FPL's four nuclear units, two at Turkey Point in south Dade County and two at St. Lucie on Hutchinson Island in St. Lucie County as well as the technical support activities at corporate headquarters in Juno Beach.

Mr. Goldberg, a 37-year veteran of the nuclear power industry, began working for FPL in September 1989. Prior to that he worked for Houston Lighting & Power Company (HL&P) as group vice president, nuclear. During his nine years with HL&P, Goldberg was responsible for a number of milestones, including construction and licensing of the South Texas Nuclear Project, the most advanced state of the art nuclear power station in the U.S.

i Before joining HL&P, he spent nine years with Stone and Webster Engineering Corp.,

overseeing the design, construction, operation and maintenance of six nuclear power plants.

Earlier in his career, he worked for Bethleht o Steel Co. and General Dynamics Corp. in a variety of engineering and management functions, all nuclear-related.

Goldberg is a graduate of the U.S. Merchant Marine Academy and holds a master's' degree in nuclear engineering from Massachusetts institute of Technology.

He is a registered professional engineer in Texas, California, Virginia, Massachusetts, Rhode Island, Pennsylvania and New York.

Goldberg has been affiliated witn many utility / nuclear organizations, including American Nuclear Society (ANS), institute of Nuclear Power Operations (INPO), Nuclear Utility Management and Resources Council (NUMARC) and the Edison Electric Institute (EEI).

1 2/25/93

Biographical Information 9

PPL DAVID A. SAGER Vice President, St. Lucie Plant Dave Sager is Plant Vice President of Florida. Power & Light Company's St. Lucie Nucle'ar Power Plant. In this function, Mr. Sager oversees the operation of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Sager, a 21-year veteran of the nuclear power industry, began working for FPL in 1975. He has held a variety of positions of increasing authority, including quality assurance engineer, technical staff engineer, operations supervisor, plant manager, staff vice president and plant vice president. Mr. Sager has held a senior reactor operator license at St. Lucie.

Prior to his tenure at FPL, he held the rank of Lieutenant in the U. S. Navy Nuclear Submarine Service. Mr. Sager served from 1968 to 1975.

Mr. Sager is a graduate of the U. S. Naval Academy and holds a Bachelor of Science degree in Naval Engineering and a Mester of Science degree in Mechanical Engineering. Mr.

Sager also holds a Master of Business Administration degree from Florida institute of '

Technology.

He is a member of the American Society of Mechanical Engineers (ASME) and the American Nuclear Society (ANS). Mr. Sager is Vice chairman of the Combustion Engineering Owners Group (CEOG) Executive Committee and has served on the institute for Nuclear Power Operations' National Academy of Nuclear Training.

9/30/93

Biographical Information 9

I:PL CHRISTOPHER L. BURTON Plant General Manager, St. Lucie Plant Chris Burton is Plant General Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. Burton oversees the operation of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Burton began working for FPL in 1975. He has held a variety of positions of increasing authority, including reactor operator, nuclear plant supervisor, assistant operations supervisor, reliability maintenance supervisor, operations supervisor and operations manager.

Mr. Burton has held reactor operator and senior reactor operator licenses at St. Lucie.

Mr. Burton is a graduate of State University of New York and holds a Bachelor of ~

Science degree in Electronics Technology.

He is a member of the American Nuclear Society (ANS) and the Professional Reactor Operator Society.

9/30/93

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Biographical Information l

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I:PL C. ASHTON P5LL Plant Services Manager, St. Lucie Plant Ash Pell is Plant. Services Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. Peli oversees various departments, including l

Security, Fire Protection, Safety, Environmental, Emergency Planning, Training, Information i

Management, Budget, and Administration at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Pell began working for FPL in 1975. He has held a variety of positiorn of increasing authority, including Reactor Engineer, Reactor Supervisor, Technical Staff Supervisor, Assistant to Senior Vice President Nuclear, and Director Nuclear Administrative Services. Mr. Pell completed certification as a senior reactor operator for both the S.t. Lucie and Turkey Point nuclear units.

l/.r. Pell is a graduate of the University of Central Florida and holds a Bachelor of Science degree in Physics.

He is a member of the Southeast section of the American Nuclear Society (ANS).

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L Biographical Information 9

I:PL JOHN B. HOSMER Project Engineering Manager, St. Lucie Plant John. Hosmer is Plant' Project Engineering Manager of Florida Power and Light Company's St. Lucio Nuclear Power Plant. In this function Mr. Hosmer oversees the production engineering and site engineering groups of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Hosmer began working for FPL in 1988 as the director of nuclear engineering.

Prior to his tenure at FPL, Mr. Hosmer held several positions of increasing authority, including plant engineer with Standard Oil of California, project engineer, chief engineer and project manager with Bechtel Power Corporation, and project engineer for the Sequoyah Nuclear Plant for Tennessee Valley Authority. Mr. Hosmer was a Lieutenant in the U. S. Navy Nuclear Submarine Service and served from 1969 to 1973.

Mr. Hosmer is a graduate of Purdue University and holds a Bachelor of Science and a Master of Science degrees in Chemical Engineering. Mr. Hosmer also holds a Master of Business Administration degree from California State University, Long Beach.

He is a member of the american Nuclear Society (ANS) and a registered professional Mechanical and Nuclear Engineer in Florida and California. Mr. Hosmer is Chairman of the Region 11 engineering directors interface meetings.

9/30/93

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Biographical Information PPL LAMAR L. MCLAtJGHLIN

. Plant Licensing Manager, St. Lucie Plant Lamar McLaughlin is Plant Licensing Manager of Florida Power & Light Company's St.

Lucie Nuclear Power Plant. In this function, Mr. McLaughlin oversees alllicensing activities associated with the operation of the St. Lucie Nuclear Plant.

Mr. McLaughlin began working for FPL in 1980. He has held a variety of positions including staff engineer and lead engineer in the technical department, and plant licensing manager. McLaughlin obtained a senior reactor operator license at St. Lucie.

Mr. McLaughlin is a graduate of the University of Florida and holds a Bachelor of Science degree in Electrical Engineering. Mr. McLaughlin also holds a Master of Business Administration degree from Florida Institute of Technology.

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Biographical Information O

I:PL ANDREW DeSOlZA Human Resources Manager, St. Lucie Plant i

Andrew DeSolza is Plant Humt-Resources Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. DeSoiza oversees alt human

]

resource activities for the St. Lucie Nuclear Plant.

Mr. DeSoiza began working for FPL in 1972. He has held a various positions, including payroll clerk and human resource manager.

Mr. DeSoiza is a graduate of Miami Dade Community College and holds an Associates of Arts degree in Business.

1 9/30/93

Biographical Information PPL JAMES SCAROLA Operations Manager, St. Lucie Plant Jim Scarola is Operations Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. Scarola oversees the operations, health physics, chemistry, and reactor engineering departments of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Scarola began working for FPL in 1980. He has held a variety of positions of increasing authority, including l&C startup engineer, l&C maintenance engineer, assisterit superintendent electrical maintenance, manager special projects, maintenance manager, manager equipment, support, and inspections, and engineering project manager at.St. Lucie.

Mr. Scarola holds a Bachelor of' Science degree in Electrical Engineering from the University of Notre Dame and a Master of Business Administration degree from Florida Institute of Technology. Mr. Scarola has completed the senior reactor operator certification training program at St. Lucie.

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l Biographical Information O

FPL DANIEL H. WEST Plant Technical Manager, St. Lucie Plant Dan West is Plant Technical Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant, in this function, Mr. West oversees the operation of the technical department including the technical engineers, testing group and shift technical advisors for the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. West began working for FPL in 1980. He has held a variety of positions of increasing authority, including staff engineer, lead engineer, and technical department supervisor. He obtained a senior reactor operator license at St. Lucie. Prior to his tenure at FPL, he was employed by General Electric Company at the Knolls Atomic Power Laboratory from 1973 to 1979.

Mr. West is a graduate of the U. S. Merchant Marine Academy at Kings Point and holds a Bachelor of Science degree in Marine Engineering.

He is a member of the American Society of Mechanical Err cers (ASME) and the American Nuclear Society (ANS).

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l Biographical Information O

I: P L JAMES L. BROADHEAD Chairman and Chief Executive Officer James L Broadhead is chairman and chief' executive officer of FPL Group, Inc., a diversified holding company with utility and non-utility operations. He' also is chairman and chief executive officer of FPL Group's principal subsidiary, Florida Power & Light Company, one of the largest electric utilities in the nation. FPL Group's diversified activities include non-utility energy production, agriculture, real estate development, and cable TV.

Prior to becoming associated with FPL Group in January 1989, Mr.

Broadhead was president of GTE Telephone Operations and a member of GTE's board of directors. Before his anociation with GTE, Mr. Broadhead was president of St. Joe Minerals Corporation. He had previously served in a variety of positions there beginning in 1968, including general counsel, vice president of corporate development, vice president of finance for St. Joe Petroleum j

Corporation, and presiderit of St. Joe Zinc Company.

Mr. Broadhead received a bachelors degree in mechanical engineering from Comell University in 1958 and a juris doctor degree from Columbia University Law Schoolin 1963. He is a director of Barnett Banks,Inc., Delta Air Lines,Inc., and the Pittston Company, and a Board Fellow of Cornell University.

Mr. Broadhead, his wife and four children reside in Palm Beach County.

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Biographical Information I:PL JEFFREY A. WEST Operations Supervisor, St. Lucie Plant Jeff West is Operations Supervisor of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. West oversees the direction of all licensed operators within St. Lucie's operations department.

Mr. West, began working for FPL in 1980. He has held a variety of positions of increasing authority, including shift technical adviser, reactor control operator, nuclear watch engineer, assistant nuclear plant supervisor, technical training supervisor, nuclear plant supervisor,assistantoperationssupervisor,assistantauperintendent mechanicalmaintenance and operations supervisor. Mr. West maintains an active senior operator license at St. Lucie.

Prior to his tenure at FPL, he held the rank of Lt. Commander in the U. S. Navy Nuclear

- Submarine Service. Mr West served from 1974 to 1979.

Mr. West is a graduate of the University of Tennt ssee and holds a Bachelor of Science degree in Electrical Engineering. Mr. West also holds e Master of Business Administration degree from Florida institute of Technology.

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Biograr'aical Information O

I: P L JEROME H. GOLDBERG President, Nuclear Division J. H. Goldberg is President, Nuclear Division at Florida Power & Light Company. In this j

function, Goldberg oversees the operation of FPL's four nuclear units, two at Turkey Point in south Dade County and two at St. Lucie on Hutchinson Island in St. Lucie County as well as the technical support activities at corporate headquarters in Juno Beach.

Mr. Goldberg, a 37-year veteran of the nuclear power industry, began working for FPL in September 1989. Prior to that he worked for Houston Lighting & Power Company (HL&P) as group vice president, nuclear. During his nine years with HL&P, Goldberg was responsible for a number of milestones, including construction and licensing of tho South Texas Nuclear i

Project, the most advanced state of the art nuclear power station in the U.S.

Before joining HL&P, he spent nine years with Stone and Webster Engineering Corp.,

overseeing the design, construction, operation and maintenance of six nuclear power plants.

Earlier in his career, he worked for Bethlehem Steel Co. and General Dynamics Corp. in a variety of engineering and management functions, all nuclear-related.

Goldberg is a graduate of the U.S. Merchant Marine Academy and holds a master's degree in nuclear engineering from Massachusetts institute of Technology.

He is a registered professional engineer in Texas, California, Virginia, Massachusetts, Rhode Island, Pennsylvania and New York.

Goldberg has been affiliated with many utility / nuclear organizations, including American Nuclear Society (ANS), Institute of Nuclear Power Operations (INPO), Nuclear Utility Management and Resources Council (NUMARC) and the Edison Electric Institute (EEI).

2/25/93

e Biographical Information I:PL DAVID A. SAGER Vice President, St. Lucie Plant Dave Seger is Plant Vice President bf Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. Sager oversees the operation of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Sager, a 21-year veteran of the nuclear power industry, began working for FPL in 1975. He has held a variety of positions of increasing authority, including quality assurance engineer, technical staff engineer, operations supervisor, plant manager, staff vice president and plant,vice president. Mr. Sager has held a senior reactor operator license at St. Lucie.

Prior to his tenure at FPL, he held the rank of Lieutenant in the U. S. Navy Nuclear Submarine Service. Mr. Sager served from 1968 to 1975.

]

Mr. Sager is a graduate of the U. S. Naval Academy and holds a Bachelor of Science degree in Naval Engineering and a Master of Science degree in Mechanical Engineering. Mr.

Seger also holds a Master of Business Administration degree from Florida institute of f

Technology.

He is a member of the American Society of Mechanical Engineers (ASME) and the American Nuclear Society (ANS). Mr. Sager is Vice chairman of the Combustion Engineering Owners Group (CEOG) Executive Committee and has served on the institute f or Nuclear Power Operations' National Academy of Nuclear Training.

9/30/93

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Biographical Information PPL CHRISTOPHER L. BURTON Plant General Manager, St. Lucie Plant Chris Burton is Plant General Manager of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. Burton oversees the operation of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Burton began working for FPL in 1975. He has held a variety of positions of increasing authority, including reactor operator, nuclear plant supervisor, assistant operations supervisor, reliability maintenance supervisor, operations supervisor and operations manager.

Mr. Burton has held reactor operator and senior reactor operator licenses at St. Lucie.

Mr. Burton is a graduate of State University of New York and holds a Bachelor of ~

Science degree in Electronics Technology.

He is a member of the American Nuclear Society (ANS) and the Professional Reactor Operator Society.

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Biographical lnformation i

PPL

'C. ASHTON PELL Plant Services Manager, St. Lucie Plant 4

Ash Pell is Plant Services Manager of Florida Power & Light Company's St. Lucie Nucle'ar Power Plant. In this function, Mr. Pell oversees various departments, including Security, Fire Protection, Safety, Environmental, Emergency Planning, Training, information Management, Budget, and Administration at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Pell began workirig for FPL in 1975. He has held a variety of positions of increasing authority, including Reactor Engineer, Reactor Supervisor, Technical Staff Supervisor, Assistant to Senior Vice President Nuclear, and Director Nuclear Administrative Services. Mr. Pell completed certification as a senior reactor operator for both the St. Lucie and Turkey Point nuclear units.

i Mr. Pell is a graduate of the University of Central Florida and holds a Bachelor of Science degree in Physics.

He is a member of the Southeast section of the American Nuclear Society (ANS).

9]30/93

Biographical lnformation FPL 1

4 JOHN B. HOSMER i

Project Engineering Manager, St. Lucie Plant John Hosmer is Plant Project Engineering Manager of Florida Power and Light j

Company's St. Lucie Nuclear Power Plant. In this function Mr. Hosmer oversees the 1

production engineering and site engineering groups of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Hosmer began working for FPL in 1988 as the director of nuclear engineering.

Prior to his tenure at FPL, Mr. Hosmer held several positions of increasing authority, including j

plant engineer with Standard Oil of California, project engineer, chief engineer and project manager with Bechtel Power Corporation, and project engineer for the Sequoyah Nuclear Plant for Tennessee Valley Authority. Mr. Hosmer was a Lieutenant in the U. S. Navy Nuclear l

Submarine Service and served from 1969 to 1973.

Mr. Hosmer is a graduate of Purdue University and holds a Bachelor of Science and a Master of Science degrees in Chemical Engineering. Mr. Hosmer also holds.a Master of Business Administration degree from California State University, Long Beach.

He is a member of the american Nuclear Society (ANS) and a registered professional Mechanical and Nuclear Engineer in Florida and California. Mr. Hosmer is Chairman of the Region 11 engineering directors interface meetings.

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J Biographical Information

. 9 PPL LAMAR L. MCLAUGHLIN Plant Licensing Manager, St. Lucie Plant 4

)

Lamar McLaughlin is Plant Licensing Manager of Florida Power & Light Company's St.

Lucie Nuclear Power Plant. In this function, Mr. McLaughlin oversees alllicensing activities associated with the operation of the St. Lucie Nuclear Plant.

J Mr. McLaughlin began working for FPL in 1980. He has held a variety of positions including staff engineer and lead engineer in the technical department, and plant licensing manager. McLaughlin obtained a senior reactor oparator license at St. Lucie.

Mr. McLaughlin is a graduate of the University of Florida and holds a Bachelor of Science degree in Electrical Engineering. Mr. McLaughlin also holds a Master of Business Administration degree from Florida Institute of Technology.

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Biographical lnformation 9

I:PL HERMAN L. FAGLEY Site Construction Manager, St. Lucie Plant Herman Fagley is Site Cons'truction Manager of Florida Power & Light Company's St.

Lucie Nuclear Power Plant. In this function, Mr. Fagley oversees the construction services of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Fagley began working for FPL in 1978. He has held a variety of. positions of increasing authority, including construction supervisor, start-up engineer, project site manager, staff specialist.

Mr. Fagiay le a graduate from Brevard Junior College and holds an Associates degree and a Bachelor of Science degree in Building Construction from the University of Florida.

He is a member of the American Nuclear Society (ANS).

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Biographical Information 9

PPL ROBERT E. DAWSON Maintenance Manager, St. Lucie Plant i

s Bob Dawson is Plant Maintenance Manager of Florida Power & Light Company's St.

Lucie Nuclear Power Plant. In this function, Mr. Dawson oversees the maintenance of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Dawson began working for FPL in 1973. He has held a variety of positions of increasing authority, including reactor engineering supervisor, staff reactor support, startup supervisor-mechanical, core barrel project, quality improvement, assistant superintendent-electrical maintenance and plant maintenance manager. Mr. Dawson has held an senior reactor operators license at St. Lucie.

Mr. Dawson is a graduate of the University of Virginia and holds a Bachelor of Science degree in Nuclear Engineering.

He is a member of the American Society of Mechanical Engineers (ASME) and the American Nuclear Society (ANS).

9/31/93

Biographical Information l

O PPL THOMAS G. KREINBERG Manager, Materials Management, St. Lucie Plant 1

Thomas Kreinberg is Manager of Materials Management of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. Kreinberg oversees purchasing and procurement at the St. Lucie site located on Hutchinson Island, app'oximately 50 miles j

north of West Palm Beach.

j Mr. Kreinberg began working for FPL in 1980. He has held a variety of positions of increasing authority, including purchasing & contract services, contracts administrator, manager of contracts and manager materials management.

Mr. Kreinberg is attended Syracuse University and holds a Bachelor of Arts degree in Russian and a Bachelors of Business Administration Economics from the University of Florida.

He is a member of Contracts Management Owners Group (Nuclear Power Utilities).

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Biographical Information O

PPL HERMAN L. FAGLEY Site Construction Manager, St. Lucia Plant Herman Fagley is Site Construction Manager of Florida Power & Light Company's St.

Lucie Nuclear Power Plant. In this function, Mr. Fagley oversees the construction services of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Fagley began working for FPL in 1978. He has held a variety of positions of increasing authority, including construction supervisor, start-up engineer, project site manager, staff specialist.

4 Mr. Fagley is a graduate from Brevard Junior College and holds an Associates degree and a Bachelor of Science degree in Building Construction from the University of Florida.

He is a member of the American Nuclear Society (ANS).

9/30/93

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Biographical Information O

PPL ROBERT E. DAWSON Maintenance Manager, St. Lucie Plant i

Bob Dawson is Plant Maintenance Manager of Florida Power & Light Company's St.

Lucie Nuclear Power Plant. In this function, Mr. Dawson oversees the maintenance of the two nuclear units at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Dawson began working for FPL in 1973. He has held a variety of positions of increasing authority, including reactor engineering supervisor, staff reactor support, startup supervisor mechanical, core barrel project, quality improvement, assistant superintendent-electrical rnaintenance and plant maintenance manager. Mr. Dawson has held an senior reactor operators license at St. Lucie.

Mr. Dawson is a graduate of the University of Virginia and holds a Bachelor of Science degree in Nuclear Engineering.

He is a member of the American Society of Mechanical Engineers (ASME) and the American Nuclear Society (ANS).

9/31/93

'l Biographical Information I:PL THOMAS G. KREINBERG Manager, Materials Management, St. Lucie Plant Thomas Kreinberg is Manager of Materials Managemerit of Florida Power & Light Company's St. Lucie Nuclear Power Plant. In this function, Mr. Kreinberg oversees purchasing and procurement at the St. Lucie site located on Hutchinson Island, approximately 50 miles north of West Palm Beach.

Mr. Kreinberg began working for FPL in 1980. He has held a variety of positions of increasing authority, including purchasing & contract services, contracts administrator, manager of contracts and manager materials management.

Mr. Kreinberg is attended Syracuse University and holds a Bachelor of Arts degree in Russian and a Bachelors of Business Administration Economics from the University of Florida.

He is a member of Contracts Management Owners Group (Nuclear Power Utilities).

e 9/30/93

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. m og agn ,p,g R IM 6[ ' May,1995 Page 89 of 96 4 RGURE 4 TEMPORARY CHANas REQUEST e (Page 2 of 2) Yes No D 10 CPR 80.85 Sereening ,,,M,,, . Does tie change represent a change to the feedity as desenbod in ttie SAR7 1 ,,j!(,_, . Does the change represent a change to procedures as asscribed in the SAR7 2 _f

3. la tie change maanntater4 wtlh a test or expertment not desertbed in the SAR7

4. Could the change aftset nuotsar safety in a way not provously evaluated in y

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5. Does the change require a change to the Techncal specificatons?

t !EIR f if the answer to & the ateve 10 CFR 80.50 somening gtwetions are no, (Quescons l 1 - 5), then a safety evaluation is not reouimd. R 1 MeY Dale % 3,_,11J M j STA review (signature) i E Does this chanos: (NPs to complete) Yes No D 7 Cornpromme the separaton of redundant treins of equipment? O B"' Potentially isolate pressure roliels? 7 D N automate signals? D FDetest mechancal or eiestnoal siterlooie? 7 O Pelor FRG review regulfed? M2Hi If any at the atmo criteria are marked yes, doouss possible alternatives with the originator. l NPS Signature. dM _ Date db PT F FRG Revtew: 8W W _ oane f // 7/ 2f Plant GeneralManager Approval PRG Number _ E __. I 7 I This change shall be rev6ewed Of prior FRG renew is not required) by the Faciltty Rewow Group wthin 14 days of the Wie DPost authortranon date. (Tech. Spec. 6.8.3.C) I G asemal: (This change sheit have prior appmvel by a NPS and one rnamber of the plant, manneement senfr.)(Tech. spec e >. O 13 /.,$k, / Date Plant Management statt navre __ Authortzstion Date M[6 'M M NPE Signature /. l -(NPS/ANPs) Date / / H Canoelianon Authonzaten ~ Meason: ~ I

03-22-1995 11:55AM St Lucie Resident Office 1 407 461 4622 P.03 .4 t'ag) 129 of zse ST. LUCIE UNIT 1 ADMINISTRATIVE PROCEDURE NO.1-00t0125A, REVISION 39 SURVEILLANCE DATA SHEETS DATA SHEET #24 VALVE TESTING PROCEDUREE (Page 2 of 9) 1.0 (continued) 2. (continued) E. Closed stroke time seconds. F. Record stroke times on Data Sheet BB.

• Satisfactory perbimance of the above asterisked steps assures conformance with applicable Technical Specifications.

NPS/ANPS l 2.0 PORV Stroke Time Test: ( vj l 5b**+#) .-C W ~lIb -2.1 ? ^. g g f-t y Q cru.. vr :: . LTcr t

• A. Ve at both PORV Block Valves, V-1 d V-1405, have be en sufficient time to pr nze the spaos between the and the B alves. Close the PORV Block Valves.

B. Place t>Wi PO errida/ Norm e/ Low Range switches in OVERRI C. te a high PZR pressure reactor trip signal by oving two high PZR pressure modules from the RPS. i 9 O

08-3 '995 11:55AM St Luc 1e Res:drnt Offiee ' 407 461 4622 P.04 Pcge 130 cf 236 ST. LUCIE UNIT 1 . ADMINISTRATIVE PROCEDURE NO. 1-0010125A, REVISION 39 SURVEILLANCE DATA SHEETS DATA SHEET #24 VALVE TESTING PROCEDURES (Page 3 of 9) an-tw nion 2.1 (continued) j D. at a time, stroke open and time each PORV by placin rride/ Norm Range / Low Range switch in the Norm R e position. Time e valve stroke from the switch actuation to pen indica ' (the acousitic monitor). Retum the swit to OVERRID d verify that the PORV closes. TC If the stroke time less than one second en record less than 1. Also recor e stroke times ata Sheet 10 of AP 1@10125A. Time (see) OS Pressure V 1402 %1404 E. Insert the two PZR Pressure RPS modules. F. Retum the RV hanil control switches to Norm Range. G. Vertfy t both of the PORVs remain closed. H. O PORV block valves as required. I 9

00-22-1995 11:56 # 1 St Lucie Res2 dint OMice

• 407 461 4622 P.05 Pcge 131 of 236 ST. LUCIE UNIT 1 ADMINISTRATIVE PROCEDURE NO. 1-0010125A, REVISION 39 SURVEILLANCE DATA SHEETS DATA SHEET #24 VALVE TESTING PROCEDURES (Page 4 of 9) i 2.

(oontinued) iN PZR Pressure Less than LTOP Setpoint f,, g._ f g g T\\h CAUTION test will initiate a reactor trip. Do not perform this test with CEAs I A. Verify e RCS cold leg temperature is less than F. B. Verify the S is on Shutdown Cooling with a bble in he PZR. C. Cycle both PO V Block Valves (V 1403 V 1405) full closed and then open to erify operability. D. Place both PORV Oy 'de/ Norm go/ Low Range switches in OVERRIDE. E. Initiate a high PZR pressu ctor trip signal by removing two High PZR Pressure m s from the RPS. j CA0 TION If the PORVs do not recio, immediate close both of the PORV block valves. F. One at a time, roke open and time each RV by placing its Override /No Range / Low Range switch in NORM RANGE. Time the va stroke from the switch actuatlo to the open I ication, (the acoustic monitor). Ret the switch to VERRIDE and verify that the PORV of s. If the oke time is less than one second, then reco 1. Also rd the stroke times on Data Sheet 10 cf AP 1 10125A. Time (see) RCS Pressusc -1402 V-1404

' 08-22-1995 11856Ct1 St Luc 1e Residint OHice

• 407 461 44622 P,06 Pcge 132 of 236

') ST. LUCIE UNIT 1 ADMINISTRATIVE PROCEDURE NO. 1-0010125A, REVISION 39 SURVEILLANCE DATA SHEE_TE DATA SHEET #24 VALVE TESTING PROCEDURES (Page 5 of 9) Date / 2.0 (continued) ~ 2.2 (continued) / C /- 9 f-/ff insert the two High PZR Pressure RPS modul H. Retum RV Hand Con dches to Low Range. I. Verify that e. s remain closed. Reviewed HPS/ANPS N, 3.0 Flow Exercising of NaOH Tank Vacuum Relief Check Valves: 3.1 initial Conditions: A. Health Physics har been notified of the test to be performed on the 0.5 levelIri the Unit #1 RAB. B. The nitrogen bottle, ladder, test cart and test rig have been moved to the test location. C. Instrumentation: 1. Test Cart Helse Gage (0 to 60 psig, t2%) TG#: Cal Date: 1 / 2. Test Rig Pressure Gage (0 to 15 psig, 2%) TG#: Cal Date: / / 3. Test Cart Roto Meter (274 SLPM, 2%) TG#: Cal Date: / / 4. NaOH Tank Pressure indication (PI-07 8) .___.i

~ 90-22-1995 11856AM St Lucie Rea:osnt OHice 1 407 461 4622 P.07 IC l~1f /y 2.0 ' PORV Streke Titne Test: Date j j _ ] 1 atTTICE 'Ihis test will initiate a reactor trip. De rot rform this test with the-eliiAs hache4. H8 cl.eud Jt G L 5 A. Veri RCS cold leg temperature is less than 304 .F. B. Verify the RCS is on shutdown cooling with a bubble in the pressurizer. 4 i C. Verify the RCE pressure is between 240 psia and i j 265 psia. m1 are to recorti V1402 and Verify IEC Fic flow si D. .mam V1404 acoust voltages on tertporary s p.1; % s.a wa J0pw:q 8 t(n m,ug) - i fg. Cycle PORV Block. Valve V1403 full closed and than l cpan to verify operability. C f. Cycle PORV Block valve V1405 full closed atd then i open to verify operability. A g. Place Pressurizer Relief Valve V1402 Override / Norm Range /Iow Range switch in the Overide position.

3. M.

Place Pressurizer Relief Valve V1404 Override /NJrm Range /Iow Range switch in the Overide position. 'I 1. Initiate a high PZR:ressure reactor trip signal by j_ zwoving two High PZR Pressure trodules from the RPS. Y a e . (continued on next page) -ww r

" 00-22-1995. 11 G W ' St Lucie Res.dsnt DHice 1 407 461 4622-P.08 A / L - f. j a~./ 9 g TNTTT2LT. k k. Record the Initial conditions for testing Pressurizer Relief Valve V1402 in the table below. PORV v1402 INITIAL CDNDITICNS FINAL CENDITIONS ACCEFIANCE CRIT 5RIA RCS Pressure: RCS Pressure: Greater than (PI-1103A or PI-1104A) (PI-1103A or PI-110 w 5 psi Reduction l Quench Tank 0 - h Tank N/A g ture: _ g g ure: Quench Tank Quench Tank Ievel: Imvel: N/A (LIA-1116) (LTA-1116) Quench Tank Ow eh Tank Pressure: Pressure: N/A (PIA-1116) [(FIA-1116) Relief Valves Relief Valves Disch. TWtperature Disch. Tenperature N/A 1 (rIA-1106) (TIA-1106) CRUTIC2r If the Pressurizer Relief Valves do not reclose, imnsdiately close both PCRV Block valves. EZIE If the change in RCS pressure does not treet acceptance criteria after 30 secords, close the Pressurizer Relief Valve and notify the NPS. 7 INITIAL L. d. Stroke open Pressurizer Relief Valve V1402 by placing its Override / Norm Ran!pe/ Low Range switch 2.n the Nerm Range position. Time the valve stroke frem the switch actuation to the open indication, (Acoustic Monitor V1402 LED Lights). (continued an next page)

__. ~... ' 89-22-19CE 118 5*7AM. St Lucie Residsnt OHies 1 407 461 4622 P.09 y

f. qg,,9 (

/c l .s. s i TNTTIAL - d Record the strake time arxi the number of Accustic Monitor V1402 I20 lights illuminated below. Press 2rizer Relief Valve Stroke Time: sec '(If less than one second, then reevsd < 1.) i Number IED Lights' Illuminated: IEDs i 1 el % Verify Pressurizer Relief Valve V1402 main valve 'l disc actuation by cbserving the requizwd change t .in RCS pressure. l 0 h. ' Return the Pressurizer Relief Valve V1402 override / Norm Range /Iow Range switch to the override position and verify Pressurizar Relief i V1402 closes. fh Record final conditions data in the table following Step J. Q 4. Record the Initial conditions for test i Pressurizer Relief' Valve V1404 in the le below. 1 PCRV V1404 l 2NITIAL CX2CITICNS FINAL CINDITICES ACCEPIANCE CRITERIA RCE Pressure: RCE Pressure: Groeter than 1 (PI-1103A or PI-noth) (PI-1103A cc PI-now 5 psi Reduccion Quench Tank Quench Tank 'Dutparature: Tenparature: N/A 1 (TIA-ins) (TIA-uts) Quench Tank G M Tank Isvel: Imvel: N/A (LIA-1116) (LTA-liis) Quench Tank Om eh Tank i Pressure: Pressure: N/A (PIA-n16) { PIA.nig) l Relief Valves Relief Valves j Disch. Tenparature Disch. 'Dmperature N/A (TIA-nos) (TIA-nos) (continued on next page) v v ..--v

^' 00-22-1995 1185841-St Luc 1e Resad2nt ONice 1 407 461 4622 P.10 /C t-q g r9 ( CAUTIN If the Pressurizer Relief Valves do not recloa, innediately close both PORV Block Valves. C MZIE i If the change in RCS pressure 'does.not meet a tance criteria after 30 secegis, close the Pressurizer ief Valve and notify the NPS. IhfITIAT.2 l 'E % Stroke open Pressurizer Relief Valve V1404 by placing its Override / Norm /Iow switch in the Norm Range position. T the ve stroke from the switch actuation to the open indication, (Acoustic bbnitor V1404 IED Lights). S. % Record the stroke tirre and the number of Acoustic Monitor V1404 LED lights illuminated below. Pressurizer Relief Valve Stroke Time: sec (If less than one second, than rewid < 1.) - Number LED Lights Illuminated: LEDs T Yn. Verify Pressurizer Relief Valve V1404 rnain valve disc actuation by observing the required change in RCS pressure. i O% Return the Pressurizer Relief Valve V1404 Override / Norm Range /Iow Range switch to the override position and verify Pressurizer Relief V1404 closes. Y% Record final conditions data in the table following Step P. W N. Insert the two High PZR Pressure trodules. Return the Pressurizer Relief Valve V1402 Override / Norm Range /Iow Range switch to the Low Range position. yA Vg Pressurizer Relief Valve V1402, remains (continued on next page) t b r

p ., f. .00-22-1995 11858AM St Lucie Reoit:nt Offaca 1 407 461 4622 P.11 I c i,,._ m /xv 1 f. Return the Pressurizer Relief Valve V1404 override / Norm Range /Iow Range s#.tch to the f Iow Range position. /_ A V Pressurizer Relief Valve V1404 remains $$ % Record the Pressurizer Relief Valve stroke titres on Data Sheet 10 of AP 1-0010125A. Reviewed KPS/AnPS t TOTAL F.11 .}}