ML17309A736

Forwards Summary of 940523 Meeting W/Util in Atlanta,Ga Re Plant Operating Plan & Util Engineering

ML17309A736
Person / Time
Site:	Turkey Point, Saint Lucie
Issue date:	05/25/1994
From:	Jerrica Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Goldberg J FLORIDA POWER & LIGHT CO.
References
NUDOCS 9406270176
Download: ML17309A736 (95)

Text

MAY 25

!gag Docket Nos. 50-335,

'50=38~9, 50-250, and 50-251 License Nos.

DPR-67, NPF-16, DPR-31, and DPR-41 Florida Power and Light Company ATTN:

Hr. J.

H. Goldberg President

- Nuclear Division P. 0.

Box 14000 Juno

Beach, FL 33408-0420 Gentlemen:

SUBJECT:

MEETINGS TO DISCUSS THE ST LUCIE OPERATING PLAN AND FLORIDA POMER AND LIGHT ENGINEERING This letter refers to the meetings conducted at your request at the NRC Region II offices in Atlanta on Hay 23, 1994.

The purposes of the meetings were,',to allow, Florida Power and Light to make presentations on the St. Lucie operating plan and on Florida Power and Light engineering.

It is our opinion that these meetings were beneficial and provided a better understanding of the issues and status of current programs.

In accordance with Section 2.790 of the NRC's "Rules of Practice,"

Part 1,

Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room.

Should you have any questions concerning this letter, please let us know.

Sincerely, Original signed by J.

R.

Johnson 940627017b 940525 PDR ADOCK 05000258'M5 P

PDR Enclosures.

1.

List of Attendees 2.

St.

Lucie Operating Plan Presentation Summary 3.

Florida Power and Light Engineering Presentation Summary cc w/encls:

D. A. Sager Vice President St.

Lucie Nuclear Plant P. 0.

Box 128 Ft. Pierce, FL 34954-0128 cc w/encls cont'd:

(See page 2)

Jon R. Johnson, Acting Director Division of Reactor Projects

Florida Power 5 Light Company cc w/ encls cont'd:

T.

F. Plunkett Site Vice President Turkey Point Nuclear Plant P. 0.

Box 029100

Miami, FL 33102 H.

N.

Paduano, Manager Licensing and Special Programs Florida Power and Light Company P. 0.

Box 14000 Juno

Beach, FL 33408-0420 C.

L. Burton Plant General Manager St.

Lucie Nuclear Plant P. 0.

Box 128 Ft. Pierce, FL 34954-0128 L.

W. Pearce Plant General Manager Turkey Point Nuclear Plant P. 0.

Box 029100

Miami, FL 33102 Lamar L. HcLaughlin Plant Licensing Manager St.

Lucie Nuclear Plant P. 0.

Box 128 Ft. Pierce, FL 34954-0218 E. J.

Weinkam Licensing Manager Turkey Point Nuclear Plant P. 0.

Box 4332

Miami, FL 33032-4332 T. V. Abbatiello Site equality Manager Turkey Point Nuclear Plant P. 0.

Box 029100

Hiami, FL 33102 Harold F. Reis, Esq.

Newman 8 Moltzinger 1615 L Street, NW Washington, D.

C.

20036 cc w/ encls cont'd:

(See page 3)

MAY 25 Iggg

Florida Power 5 Light Company cc w/ encls cont'd:

John T. Butler, Esq.

Steel, Hector and Davis 4000 Southeast Financial Center

Miami, FL 33131-2398 Bill Passetti Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Boulevard Tallahassee, FL 32399-0700 Jack Shreve

,Public Counsel Office of the Public Counsel c/o The Florida Legislature 111 West Madison Avenue, Room 812 Tallahassee, FL 32399-1400 Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, FL 32399-2100 Thomas R. L. Kindred County Administrator St.

Lucie County 2300 Virginia Avenue Ft. Pierce, FL 34982 Charles B. Brinkman Washington Nuclear Operations ABB Combustion Engineering, Inc.

12300 Twinbrook Parkway, Suite 3300 Rockville, MD 20852 Attorney General Department of Legal Affairs The Capitol Tallahassee, FL 32304 Joaquin Avino County Manager of Metropolitan Dade County 111 NW 1st Street, 29th Floor

Miami, FL 33128 bcc w/encls:

(See page 4)

Florida Power 8 Light Company bcc w/encls:

K. Landis, RII J. Norris, NRR R. Croteau, NRR Document Control Desk Wi cJ 49h HSOn NRC Resident Inspector U.S. Nuclear Regulatory Comm.

7585 South Highway AIA Jensen

Beach, FL 34957-2010 Thomas P. Johnson Senior Resident Inspector U.S. Nuclear Regulatory Commission P. 0.

Box 1448 Homestead, FL 33090 QY 25 Logy IPQRP RSchin 5'/94 RI 'P RII' KL is DVe elli 5/) /94 5/5 /94

ENCLOSURE 1

NRC:

LIST OF ATTENDEES AT ST.

LUCIE OPERATING PLAN PRESENTATION S. 0. Ebneter, Regional Administrator, Region II (RII)

E.

W. Herschoff, Acting Deputy Regional Administrator, RII H. A. Berkow, Director, Project Directorate II-2, DRP-I/II, Office of Nuclear Reactor Regulation (NRR)

A. F. Gibson, Director, Division of Reactor Safety (DRS), RII J.

R. Johnson, Acting Director, Division of Reactor Projects (DRP), RII 0.

H. Verrelli, Chief, Reactor Projects Branch 2, DRP, RII K. 0. Landis, Chief, Reactor Projects Section 28 (RP2B),

DRP, RII S.

A. Elrod, Senior Resident Inspector, St. Lucie R.

P. Schin, Project Engineer,

RP2B, DRP, RII Licensee:

0.

A. Sager, Vice President, St.

Lucie L. L. HcLaughlin, Licensing Manager, St. Lucie LIST OF ATTENDEES AT FLORIDA POWER AND LIGHT COMPANY ENGINEERING PRESENTATION NRC:

S. 0. Ebneter, Regional Administrator, Region II (RII)

E.

W. Herschoff, Acting Deputy Regional Administrator, RII H. N. Berkow, Director, Project Directorate II-2, DRP-I/II, Office of Nuclear Reactor Regulation (NRR)

A. F. Gibson, Director, Division of Reactor Safety (DRS), RII J.

P. Jaudon, Acting Deputy Director, Division of Reactor Projects (DRP), RII D.

H. Verrelli, Chief, Reactor Projects Branch 2, DRP, RII C. Casto, Acting Chief, Engineering

Branch, DRS, RII K. 0. Landis, Chief, Reactor Projects Section 28 (RP2B),

DRP, RII J.

A. Norris, Senior Project Manager, Project Directorate II-2, NRR S.

A. Elrod, Senior Resident Inspector, St. Lucie L. Trocine, Resident Inspector, Turkey Point R.

P. Schin, Project Engineer,

RP2B, DRP, RII Licensee:

H. N.

D.

C.

R.

S.

0. J.

D.

R.

0.

H.

0. A.

W. A.

L. L.

Paduano, Manager, Licensing and Special

Programs, FPL Poteralski,

Manager, Nuclear Fuels, FPL Kundalkar, Engineering

Manager, Turkey Point Denver, Acting Engineering

Manager, St. Lucie Powell, Technical

Manager, Turkey Point West, Technical

Manager, St. Lucie Culpepper, Chief, Engineering Assurance, FPL Skelly, Supervisor, Reliability and Risk Assessment, FPL HcLaughlin, Licensing Manager, St.

Lucie

~ 9406270't76

Florida Power and Light Service Area Florida Power and Light Company Fact Sheet Location Map Owner-Controlled Property Nuclear Oivision Organization St. Lucie Plant Organization St. Lucie Plant Overview 1994 St. Lucie Objectives 8-11 St. Lucie Plant Historical Performance Indicators 12-15 1993 Improvement Projects 1994 Improvement Projects 16-17 18-19 Long-term Issues 20 940114, Rev. 2 05/18l94

Florida Power L Light Company Service Area HAMILTON SUWANNEE BAKER OLUMBIA NASSAU DUVAL

~ Jacksonville AFAYETTE BRAD-FORD ST, CLAY A) N'S Georgia DIXIE I

GIL CHRISTI ALACHUA FLAGLER

'VY L

l Daytona Beach PiNELLAS CITRUS SUMTER'FRNANDO PASCO i Hl'LLSBOROUGH Tampa LAKE POLK VOLUSIA SF MINOLE ORANGE OSCEOLA Cocoa BREVARD INDIAN RIVE'R FPL Capacity Resources MANATEE HARDEE HIGHLANDS OKEECHOBEE ST. LUCIE Energy Encounter Name Capability UnitS Fuel ItttegawnIIpI A. blanatee 2

B. Ft.Myers 2

C. Turkey Point 4

Cutler 2

Lauderdale 2

F. Port Everglades G. Riviera 2

H. Martin 2

I. St.Lucie 2

J. Cape Canaveral 2

K. Sanford 3

L Putnam 2

M. St.JohnsRiver 2

N. Scherer 1

Purchased Power Peaking Units Load Management Total 32 tlt Krptuirnlnpl'LhinrnrnihtpntIIXIp>>

Oil Oil Nuc/Oil/Gas Gas OiVGas Oil/Gas OiVGas Oil/Gas Nuclear OiVGas OiVGas Oil/Gas Coal Coal 1.566 504 2.066 207 274 1.142 544 1.566 1,553'34 861 448 250"'50" 2.598 1.892 347 16.702 nrnt nt Unn IttndtLS prtrrnt tu Lnn" 840114, Rav. 2 tst Rrptturntn FPL'n Ltt prtrrnt nnnrtuhtp nl'un tIIM h'IW unnn t It Rrptruntc thr Cinn phnir nr FPL'n putthnir nf t T6 prttrnt nwnrn hip tntrrrit in thr ttttt MWHrhrtrr I'nit n SARAMTA DESOTO CHARLOTTE tl MARTIN GLADES I ihr IILrrh kri HENDRY PALM BEACH West Palm Beach Naoles

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COLLIER 0

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MONROE DADE I

Miami Beach P

O 05/18/94 BROWARD

'" FL Lauderdale

Fiorida Power & Light Company Fact Sheet 3.3-CUSTOMER GROWTH (lilt((o(+)

FIVE YEAR INCREASE ~ 17%

ENERGY WIIX FORECAST (percent) 3.2 3.21 3.26 Purchased Power eCl

~

31

.,Ae 4 di et7a e'\\ c s

28 J

I 3.1 3.0-2.9 2.79 2.91 3.02 3.12 Coal Gas fr/a Oil 28 Nuclear

18 18 27 23 26 25 13 6

12 24 2.7 86

'87

'88

'89

'90

'91

'91

'92

'93

'94

'95

'96 Actoat Forecast About FPL Established in 1925, FPL is one ofthe largest investor-owned utilities in the nation in terms ofcustomers served.

Service territory covers 27,650 square miles in all or part of 35 counties. using 58,000 miles of electric lines.

Over 14,000 employees serve more than six million Floridians from over 40 business office locations.

FPL is recognized for outstanding consumer and environmental programs by organizations including the Society of Consumer Affairs Professionals, American Society on Aging, and the Audubon Society.

Expanded conservation and load management programs can reduce summer peak demand by approximately 1,000 megawatts.

Economies achieved through a flexible energy mix and operating efficiencies contributed to an average residential customer bill that was 7 percent lower in 1991 than in 1988.

FPL's St. Lucie unit 2 was rated as the world's "most efficient" in 1991, and early in 1992 set a 502-day world record for nuclear plant (light water reactors) continuous operation before coming down for refueling.

Financial summary l1991 year-end): FPL revenues totaled $5.2 billion with net income of $376 million. To meet customers'uture needs FPL plans to spend

$6.6 billion during 1992-96 on new facilities. The utility is the largest subsidiary of FPL Group, Inc., a NYSE-listed holding company with. headquarters in Juno Beach, FL.

Customers Total Customers........

3,263,370 (Active accounts; actual population served approx.

6.1 million-about half the state total)

Growth Rate (Active accounts, above 1990) 1.7%

(Represents 55,174 new accounts)

Energy Customers Accounts Sales Residential 2,896,783 51.1%

Commercial 347,275 40.3%

Industrial 15,113 6.0%

Other(public authorities, 4,199 2.6%

wholesale, railway) 940114, Rev. 2 Energy Usage 1991 peak load (60-minute net)

Winter (Feb. 16, 1991)..........

Summer (Aug. 12, 1991)........

All-time system peak......

(Aug. 12, 1991) 11,868 mw 14,123 mw 14,123 mw 05/18/94 Total usage (all customers) 67.6 billion kwh Growth in usage (above 1990).........

3.0%

Avg.annual residential usage (and cost per kwh) 1991...................

12,083 kwh (8.2g) 1990...............

11,955 kwh (8.0g)

LOCATIONMAP ST. LUCIE NUCLEAR PLANT TO ORLANDO am 552 TO VERO BEACH STATE ROAD570 1

FT. PIERCE SEAWAYDIL CAUSEWAV6 BRIDGE. Ff. PIERCE INLET EMERGENCY OFFSITE FACIUTY ST. LUCIE WEST EXIT SSC NOWAY ROAD PORT ST. LUCIE US. ICGHWAYSI SL LUDS NUCNSI PISIS Rk 1.FS-"St EXIT 562 5W

+~

JENSEN BEACH BLVD.

(COMMERCALST.)

JENSEN BEACH~4 JSNSKN 66ACN CAUSEWAY 707 A MunOC COUNTED (5071 220.1000 M'O B

OEO MILEAGEFROM EXff.133 TO STUARTAPPROXIMATELY 6 LCLES PALMCITY US. ICGNWAYSI STUART g

STVAIIT AIA CA 5KWAT AIA axn 122 EXIT 61 C

EAST OCEAN SLYD.

PI 5

ST. LVCC SLVD.

iNDIAN51, MILEAGEFROM STUART TO ST. LUCIE PLANT'PPROXSSATELY 16 MILES EZTF INDNNTOWNROAD 558 gg JUPITEII MAEAGEFROM EXIT40 TO EXIT133 APPROXSSATELY 33 MILES P.D A. SLYD.

109 DONALDADSS ND p III NS Da NO Ng D

UN<YSIISS SLVD, NORTH PALMBEACH YS I APPROIL 6 IALES EXn 99 OKEECNOBEE BLVD.

WEST PAI.M BEACH PALM BEACH INTERNATIONAL~

AIR POILT EXff 61 C

Ng SZ 840114, Rev. 2 05/18I94

OWNER CONTROLLED PROPERTY ST. LUCIE NUCLEAR PLANT Gate A - Contractors who do not require ptant access.

Gale 8 - FPL Employees, Supplers and Vlsllors Gate C - FPL Employees, Suppliers and Visitors Gate D - Contractor bargaining unit personnel.

Gale E - FPL Material Deivery GateF

- RestrlctedFromUse Gale G - Recreational Facilities g

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OUTLINE OF ST. LUCIE PLANT St. Lucie Plant Res onsibilit - Continue to emphasize safe, reliable and efficient operation of St. Lucie Plant and to supply generation to our customer, Power Supply.

1.2

~sco e - St. Lucie Power Plant consists of two nuclear generating units iocated on Hutchinson Island in St. Lucie County Florida.

~

Base load operation - units are run at 100% power prior to all other fuel types.

~

St. Lucie Unit 2 has one of the highest lifetime capacity factors in the United States; number 1 in the world for 1988 and 1991.

UNIT

SUMMARY

Unit Reactor Power Generating Capacity Date of Operation 2700 MNt 839 MNe 2700 MNt 839 MNe'ec 1976 Aug 1983

'125 MNe of Unit 2 capacity ls owned by Orlando UtllltyCommlsslon and Florida Munlclpal Power Authority.

St. Lucie's importance to FPL's generation:

~

In 1993, net nuclear generation was 20.5 million MWH or 35% of the energy generated by. FPL plants.

The Nuclear Division represents 21%

of FPL's internal generating capacity.

St. Lucie's position in the regulatory environment:

St. Lucie has consistently received favorable SALP ratings from the NRC.

St. Lucie has consistently received favorable INPO evaluation ratings.

St. Lucie construction and operation has proceeded without serious intervenor action, or negative public perception.

ST. LUCIE NUCLEAR PLANT GOAL "To become and be recognized as the best performing nuclear power plant through teamwork and a recognized commitment to excellence."

940314, Rev. 2 05/18/94

19 OBJECTIVES Objective 1: Nuclear Safety Achieve and maintain high nuclear safety performance.

Strategy:

Attain the highest level of regulatory performance consistent with NRC and INPO Standards.

1994 St. Lucie Actions:

1.

Maintain the number of NRC Violations at less than or equal to 7.

2.

Maintain Systematic Appraisal of Licensee Performance (SALP) overall rating of less than or equal to 1.25.

3.

Maintain an INPO Category 1 Rating.

4.

Operate with less than or equal to 1 Automatic Reactor Trip/Unit.

5.

Incur 600 ManRem or less of Personnel Radiation Exposure.

. 6.

Maintain a high level of emergency response preparedness through:

a.

b.

C.

Adequate emergency response planning No program weaknesses identified during Annual E-Drill 2 or less Inspector Follow-up Items (IFls) identified during Annual E-Drill 940114, Rev. 2 05/18/94

1994 OBJECTIVES (continued)

Objective 2: Cost Positioning Nuclear Power as a preferred economic choice for electrical generation.

Strategy:

Identify methods to reduce the cost of power generation and contain future cost growth.

1994 St. Lucie Actions:

Reduce O&M costs to less than or equal to $118.75M.

2.

Reduce capital expenditures to less than or equal to $29.5M.

3.

Maintain plant staffing level of less than 1098 (FPL employees and Long Term Contractors).

4.

Reduce Nl&S inventory value to less than $59 Million.

5.

Identify and implement projects to further reduce costs by 1995.

940114, Rev. 2 05/18/94

1994 OBJECTIVES (continued)

Objective 3: Availability Maximizing the equivalent availability of our Nuclear Units.

Strategy:

Maximize the overall equivalent availability of St. Lucie Units 1 and 2.

1994 St. Lucie Actions:

1.

Achieve or exceed an equivalent availability of 76.7/o on Unit 1 and Unit 2 by:

Unit 1 Unit 2 1a.

Completing the planned Refueling Outage in less than 1b.

Having Unplanned Days Off less than 1c.

Incurring Derate Days less than 1d.

Having Total Maintenance Outage Days of less than 55 I6 55 days.

days.

days.

days.

Note:

Unit 1 Equivalent Avallablllty= 365 - 16 (Unplan. days) - 8 (Malnt. Out. days) - 55 (Plan. Outage) - 8.0 (Derated days) + 365 x 100.

Unit 2 Equivalent Avallablllty= 365 -16 (Unplan. days) - 8 (Malnt. Out. days) - 55 (Plan. Outage) - 6.0 (Derated days) + 365 x 100.

2.

Improve planned outage management methods in order to consistently reduce refueling outage durations to less than or equal to 50 days by 1996.

940114, Rev. 2 10 05/16/94

OBJECTIVES (continued)

Objective 4: Employee Relations and Development Maximize the effectiveness of our workforce.

Strategy:

Build and maintain a safe working environment for site employees which encourages innovation, professionalism, and teamwork in pursuit of site objectives and provide opportunities for knowledge enhancement, increased responsibility, and career advancement.

1994 St. Lucie Actions:

Provide facilities to centralize and permanently house site personnel.

2.

Complete a management development plan.

3.

Continue to develop the professional and technical skills of plant employees through training, and educational opportunities.

4.

Incur less than or equal to 1 Lost Time Injuries.

5.

Incur less than or equal to 22 Doctor Cases.

940114, Rev. 2 05/18/94

HISTORICAL PERFORMANCE INDICATORS NRC VIOLATIONS St. Lude Plant LICENSEE EVENT REPORTS St. Lude Plant 14 13 12 10 lt Qaooo Pg 20 gX 10 17 15 14 17 10M 1990 1N1 1992 1N3 May 1, 1N4 1099 1090 1991 1092 1993 May 1, 1094

- RADIATIONEXPOSURE - TLD St. Lude Plant ACluAL 3 YEAAAVEAAGE AUTOMATICREACTOR TRIPS St. Lude Plant 642 588 548 4>6

+GOOD 383 4

I 170 0

1090 1090 1991 1002 1093 May 1, 1094 0

1099 1000 1001 1092 1093 May 1 ~ 1004 940114, Rev. 2 12 05/18/94

HISTORICAL PERFORMANCE INDICATORS (continued)

INDUSTRIALSAFETY Lost Time lnIurles St. Lude Rant

+GOOD 32 INDUSTRIALSAFETY Recordable Doctor Cases St. Lucfe Plant 21 24 19 21 10 10 0

1989 1990 1N1 1992 1N3 Msy 1,1994 1999 1990 1991 1N2 1993 Msy 1, 1994 83,839 111,360 90,210 O&MBUDGET St. Ludo Plant 94,455 98,324 ActuAL 3.YEARAYERACE 108,789 96,8II:I CAPITALBUDGET St. Ludo Plant 31,622 28,008 ACrVAL 3 YEARAVERAGE 80,962 41,888 0

m,oS 20 21,263 21,610 23,602 23,254 10 14,268 13,277 8,127 0

19N 1990 1991 1992 1993 May1,1994 0

1989 1990 1991 1N2 1993 May 1,1994 940114, Rev. 2 13 05/18/94

HISTORICAL PERFORMANCE INDICATORS (conttnued) 02.7%

05.4%

EQUIVALENTAVAILABILITYFACTOR St. Lude Unit 1 93.2%

0 EQUIVALENTAVAILABILITYFACTOR St. Ludo Unit2 08.5%

76 81.2%

7e.ss 74%

73.5%

72.2%

732%

rl 3%

+OOOO 39%

0 1980 1090 1N1 1N2 1093 May t, 1994 19N 1NO 1N1 1N2 1093 May 1, 1994 UNPLANNEDDAYS OFF-LINE St. Lucfe Unit 1 UNPLANNEDDAYS OFF-LINE St. Lucfe Unit 2

+GOGO 10 5.3 12.8 eo 80 0

s.e 24.2 0

'IN3 13N INI IN2 INI MIII,INI 1089 1090 1N1 1N2 1993 May 1.1094 940114, Rev. 2 14 05/18/94

HISTORICAL PERFORMANCE INDICATORS (continued)

M&S INVENTORYVAIUE SL Lude Plant 88.2 0

1089 1090 1091 1002 1093 May 1, 1094 940114, Rev. 2 15 05/18/94

1993 IMPROVEMENT PROJECTS NUCLEAR SAFETY Increase Emergency Diesel Generator Reliability Severe Weather Preparedness

- Andrew: Lessons Learned Lower Mode Emergency Operating Procedures Development Enhance Control Room Work Center Activities Emergency Plan Projects Setpoint Program Probabilistic Risk Assessment Redesigned Steam Generator Nozzle Dams Plant Simulator Upgrade COST Reduction of Regulatory Burden Steam Generator Blowdown Valves - Unit 1 Implement Computerized Processes in Control Rooms Control Element Drive Mechanism Control System Improvements - Unit 1 Obsolescent Equipment Issues Plant Material Condition Valve Change-out Program (2" and Under)

Inventory Cost Reduction Abandoned Equipment Program

1993 IMPROVEMENT PROJECTS (conttnued)

AVAILABILITY Steam Generator Replacement - Unit 1 Replace Turbine Lube Oil Filtration System Replace Excore Detectors - Unit 2 Improve Pressurizer Safety Relief Valve Performance - Units 1 & 2 Develop Long-Range Maintenance Requirements for Reactor Coolant Pumps Replace Low Pressure Turbine Blading Condenser Performance Improvements EMPLOYEE RELATIONS INPO Reaccreditation - Operations Develop Long-Term Site Development Plan Safety Incentive Program Management Development Plan Enhancements to Training Programs 940114, Rev. 2 05/18/94

1994 IMPROYEMENT PROJECTS NUCLEAR SAFETY Modify Pressurizer Safety Relief Valve Tailpipes Develop IPEEE for St. Lucie External Events Thermo-Lag Issue Evaluation of Surveillance Testing of Motor Operated Valves Shutdown Risk Reduction Develop Lower Mode Off-Normal Procedures Implement Maintenance Rule Continue Simulator Upgrade Implement Emergency Preparedness Enhancements COST M&S Cost Reduction Inventory Reduction Reduce High Cost Contractors Establish Critical Spare Parts Identification Implement On-Site Printed Circuit (PC) Board Repair Facility Maintain Plant Material Condition Implement Outage Overtime Tracking Controls Reduction of Regulatory Burden 940114, Rev. 2

1994 IMPROVEMENT PROJECTS (continued)

AVAILABILITY Outage Scope Reduction/5-Year Plant Review/Single Train Method Reactor Tooling Upgrades Supporting Refueling Improvements Install Permanent Reactor Cavity Seal Ring Reduce Dropped Control Rods Replace Pressurizer Spray Throttle Valves - Unit 1 Evaluate Inconel 600 Penetrations Outage Scope Reduction/Plant Change/Modification Reduction Assess 24 Month Operating Fuel Cycle Implement Condenser Performance Improvements Evaluate Enhancements for Acoustic Feedwater Flow Devices Monitor Manufacture of Unit 1 Steam Generator Replacements EMPLOYEE RELATIONS Construct St. Lucie Plant Operations Building Phaseout Ozone Depleting Chemicals Development of 5-Year Planning Horizon Reduce Lost Time Injury Rate Formalize Management Plan Renew INPO Accreditation - Maintenance/Technical Staff OS/18/94

LONG-TERM ISSUES

~

Emerging Regulatory Issues Refueling Outage Duration/Risk

~

Steam Generator Replacement (Unit 1)

~

Spent Fuel Storage

~

O&M Cost Reduction

~

Capital Cost Reduction

~

Environmental Issues

~

Implementation of Maintenance Rule

~

Integrated Management Information Systems

~

License Renewal Option

~

Thermo-Lag

~

Inventory Reduction 940114, Rev. 2 20 05/18194

FPL NRC FPL Engineering and Technical Staff Information Meeting May 23, 1994 Atlanta, GA

AGENDA I.

Introduction II.

St. Lucie Initiatives III.

PSA Results/PSA Applications IV.

Turkey Point Initiatives V.

Reactor Physics Analysis-Vendor Independence Vl.

Self Assessment Process Vll.

Closing Comments

ST. LUCIE NUCLEAR PLANT UNITS) 8 2 ST. LUCIE RCP 2AI FAILURE FINALREPORT D.H. West Technical Manager

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2A'I CRACK LOCATIONS THERMAL BARRIER ZONE RUNOUTGROOVE WELD CRACKS I

SHAFT Q UPPER SIDE PLATE

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ST. LUCIE NUCLEAR PLANT UNITS 1 8 2 PRIMARYACTIVITIES

~ Review Design/Fabrication/Testing Documents of Original Assembly

~ Thermai/Stress Analysis

~ Metallurgical Examination

ANSYS 5.0 JUN 15 1993 12:04:50 PLOT NO.

1 NODAL SOLlJTION STEP=1 SUB

=1 TIME-0 100F.Ori TEMP TEPC=50.09 SMN =90.253 SMX =550 90.253 141.336 192.419 243 502 294.585 345.668 396.751 447.834 498.917 550 TEMPERATURE DISTRIBUTIONWITH NO SEAL INJECTION

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ST. LUCIE NUCLEAR PLANT UNITS 1 8 2 RESULTS/RECOMMENDATIONS MOST PROBABLE CAUSE

~ Low Frequency Thermal Mixing on Idle Pump with Seal Injection e High Cycle Fatigue CORRECTIVE ACTIONS

~ Limituse of Seal Injection

~ Replace 2A1 RCP Element

~ Relocate Vibration Probes just above Pump Seal

~ Install Upgraded Vibration Instrumentation on all R s

~qucLg ST. LUCIE NUCLEAR PLANT UNITS 1 8c 2 ST. LUCIE INITIATIVES D.J. Denver St. Lucie Engineering Manager

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ST. LUCIE NUCLEAR PLANT UNITS 1 8c 2 ST. LUCIE INITIATIVES

~

Engineering Support for the Unit 2 1994 Refueling Outage

~

Unit 2 Key Outage Modifications

~

Outage Self Assessment

ST. LUCIE NUCLEAR PLANT UNiTS1 5,2 ENGINEERING OUTAGE SUPPORT - UNIT 2 1994

~ Assigned Responsible Engineer to Follow Construction I Testing of all Modification Packages

~

Shared Experience by Providing Engineers to Work in Maintenance and Planning Areas

yucky C

ST. LUCIE NUCLEAR PLANT UNITS 1 8 2 UNIT 2 KEY OUTAGE MODIFICATIONS

~

Pressurizer Safety Valve Discharge Piping Support Modifications

~

On-Line Turbine Trip Testing Capability

~

RCP Vibration Monitoring Upgrades

~

New AFW Pump Steam Inlet Valves

~

Pzr. Instrument Nozzle Replacement

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ST. LUCIE NUCLEAR PLANT UNITS 1 & 2 UNIT 2 RCP VIBRATION MONITORING 270

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ROTATION

ST. LUCIE NUCLEAR PLANT UNITS I 8 2 UNIT 2 MV-08-12, -13 REPLACEMENT STEAM GENERATOR 2A

~

MAIN STEAM STEAM GENERATOR 2B (OC)

A hMV4tH2 s

(DC) l4lV48-13 (DC) l4N4S4 STEAMTURSNE AUX. FEED PP.

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ST. LUGIE NUCLEAR PLANT UNITS I 8 2 UNIT 2 PRESSURIZER NOZZLE REPAIRS 4.12 }

PRESSURE UPPER HEAD NOZZLE SHIM &

WELD RETAININGCLAMP NOZZLEATTACHMENTVlELD BUTTER WELD HEAD MATERIAL SA-533 GR B CI 1 CLADDING EXISTINGNOZZLE SB-166, INGO 690 8/SA-I82 -F316L SAFE END ORIGINALCONFIGURATION

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I ST. LUCIE NUCLEAR PLANT UNITS' 2

UNIT 2 PRESSURIZER NOZZLE REPAIRS 4.12 }

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PRESSURE UPPER HEAD EXISTING NOZZLE SB-166, IMCO 690 W/SA-182 -F316L SAFE END NEW CONFIGURATION

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ST. LUCIE NUCLEAR PLANT UNITS I 8 2 OUTAGE SELE ASSESSMENT

~

Continued Attention Toward Post-Modification Testing

~ Continue to Identify and Address Operator Work-Around Items

~

Re-Engineer Existing Processes to Improve Engineering Interface With Operations & Maintenance

ST LUCIE PSA RESULTS AND PSA APPLICATIONS BILLSKELLEY SUPERVISOR RELIABILITYAND RISK ASSESSMENT ENGINEERING TECHNICALSTAFF

CURR NT PSA ACTIVITIES PTN MR SSC ISK DETERMINATION PTN GL89 MOV PRIORITQTION PSL PRA COMPLETION l

PSL MR SSC RISK DETERMINATION PSL GL89-10 MOV PRIORITIZATION PTN IPEEE THERMO-LAG PSL IPEEE 1Q/93 12/93 3/94 6/94 IO/94 12/94

ST LUCIE PSA RESULTS 5E-04 3E-04 2E-04 cc 1E-04 5E-05 3E-05 2E-05 t

0 M ST LUCIE2 (26E 05/YR) 0 ~- ST. LUCIE 1 (2.3E-05/YR}

NRC SAFETY GOAL ESSENTIALLYSAME RESULTS 1E-05 CE PLANTS

I I

ST LUGIE PSA RESUI TS

SUMMARY

~ PSL OVERALLINTERNALEVENTS CDF MUCH LESS THAN 1E-4/YR NRC SAFETY GOAL

~ PSL OVERALLCDF WITHINRANGE OF OTHER CE PSAs

~ NO INTERNALEVENTS VULNERABILITIESIDENTIFlED

~ NO HARDWARE RECOMMENDATIONS

~ NO UNUSUALCONTAINMENTPERFORMANCE ISSUES

~ ONE PROCEDURE ENHANCEMENTIDENTIFIED

-INCREASE THE LEVELOF DETAILOF THE WATER PLANT OPERATIONS PROCEDURE - COMPLETED 40 SEVERE ACCIDENT VULNERABILITIES l

MAINTENANCERULE RISK DETERMINATIONOF SYSTEMS AND COMPONENTS SSC SCOPE DETER MINATIO 60/100 SYSTEMS SSC RISK DETERMINATION 25 SYSTEMS SELECT PERFORMANCE CRITERIA ST. LUCIE MONITOR PERFORMANCE TURKEY POINT BASE LINE GDF X2 FAILUREA X FAILURE B X FAILUREC = CDF ( CUTSET 1)

FAILUREA X FAILURED X FAILUREE = CDF ( CUTSET2)

FAILUREC X FAILUREF X FAILUREC " CDF ( CUTSET 3)

FAILURE E X FAILUREH X FAILUREJ = CDF ( CUTSET 4)

~ 0 ~ 0 ~

FAILURETX FAILUREQ X FAILUREE = CDF ( CUTSET298)

FAILUREA X FAILUREM X FAILUREP = CDF ( CUTSET 299) gnoz FAILURES X FAILURE B X FAILUREW = CDF ( CUTSET 300)

FAILUREH X FAILUREN X FAILURER = CDF ( CUTSET 301)

~01la Rl KACHIEVE ENTW RTH 90 o OF TOTALCORE DAMAGEFRE UENCY

MAINTENANCERULE RISK DETERMINATIONOF SYSTEMS AND COMPONENTS PRA SSC RISK DETERMINATION EDG CCN ICW RPS AFW PLANT EXPERT PANEL OPERATIONS MAINTENANCE TECHNICAL STAFF PSA ENGINEERING Cl VALVES CR HVAC {POST ACCIDENT}

FINALSSC RISK DETERMINATION CCW ICVI RPS

'FW Cl VALVES CR HVAC ACCOUNTS FOR LEVEL 1 PSA LIMITATIONS

~ SHUTDOWN MODES LEVELOF DETAIL

~ SAFETY FUNCTIONS NOT MODELED

TURKEY POINT MOY PRIORITIZATION-GL 89-10 REDUCTION OF DYNAMICTESTING SCOPE (GL 89-10)

GROUPING SERVICE CONDITION DESIGN MARGIN PRA RISK INDEPENDENT OVER-CHECK PSA RISK PRIORITIZATION HIGH MEDIUM LOMf

TURKEY POINT MOV PRIORITIZATION-GL 89-10 TREATMENTOF COMMON MODE FAILURES BASELINE CDF X 2

~ ~ ~

MOV26 MOV27 1.44 1.44 CUMULATIVECHANGE IN CDF RAW*

1.00 1.01 1.02 1.00 1.01 1.04 1.97 2.07 LOW RISK MEDIUM/

HIGH RISK RISK ACHIEVEMENTWORTH (RAW)

~ ~ ~

MOV52 MOV53

~ ~ ~

16.2 19.7 RESULT: REDUCED DYNAMICTESTING FOR VALVES IN THE SCOPE OF GL 89-10 ATTURKEY POINT.

CURRENT PSA ACTIVITIES

SUMMARY

~ FPL CONTINUES TO USE THE PSA TECHNOLOGY FOR A WIDE RANGE OF APPLICATIONS

~ PSA PROVIDES AN IMPORTANT DIVERSE AND INDEPENDENT ANALYTICALTOOL TO EXAMINEPLANT SAFETY ISSUES

~ KNOWLEDGE OF PSA STRENGTHS AND LIMITATIONSIS IMPORTANTIN APPLICATIONOF THE TECHNOLOGY

~ PSA CAN BE AN INPUT TO THE DECISION PROCESS TO DETERMINEWHERE TO FOCUS RESOURCES MAJOR STUDIES

- MAINTENANCERULE

-GL89-10 MOV'S

- THERMO-LAG

- IPEEE DAILYWORK

- DESIGN CHANGES

- EQUIPMENT OOS

- SAFETY EVALUATIONS

- MAINTENANCEREVIEW

TURKEY POINT NUCLEAR PLANT Og~

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UNIT 3 CYCLE 14 OUTAGE STATUS PRESENTED BY:

RAJ S. KUNDALKAR ENGINEERING MANAGER

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0 g py4 TURKEY POINT NUCLEAR PLANT UNITS 3 8c. 4 U3C14 OUTAGE STATUS

~

SCHEDULED DURATION

~

ACTUALDURATION 46 DAYS 45 DAYS 11 HOURS

~

PREVIOUS U4C13 OUTAGE 46 DAYS, 17 HOURS

~

PLANNED WORK SCOPE ACCOlVIPLISHED 17 Major PClVIs 29 Minor PCMs NO LOST TIME INJURIES

~

NO NUCLEAR SAFETY ISSUES

~

MAJOR PROGRAMS'G Eddy Current Inspections ISI Inspections GL 89-10 MOVs Erosion/Corrosion 1400 PWOs WP)PRESENTlNRC ATLMTG

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TURKEY POINT NUCLEAR PLANT UNITS 3 8c 4 ENGINEERING OUTAGE SUPPORT

~

ENGINEERING PLANNING 1 - CYCLE AHEAD

~

ENGINEERING ROLE IN RISK ASSESSMENT TEAM Contingency Plans ln-Place EFFECTIVE PROBLEM SOLVING Containment Fuel Assembly Upender Crane Turbine Generator Inspection and Refurbishment GL 89-10 MOV Testing Safeguards Testing

~

ENHANCED POST MODIFICATIONTESTING

~

IN-HOUSE ENGINEERING

~

24 HOUR ENGINEERING OUTAGE SUPPORT WPlPRESENHNRC ATL.MTG

>ay TURKEY POINT NUCLEAR PLANT UNITS 3 S. 4 MAJOR OUTAGE MODIFICATIONS Unit 3 Cycle 14 PLANT RELIABILITYMODIFICATIONS

~

D.C. Contactor and Relay Replacement

~

Condenser Cathodic Protection

~

H2 Purity Panel Replacement

~

New Gold Chem Lab Modifications New condenser sample piping New control room conductivity monitor

~

Turbine Trip Pilot Valve Leakoff Line

~

Generator Protective Features

~

Turbine Runback Elimination

~

I Flux Mapper Improvements

~

Repair/Inspect Intake Structure WPLPRESENTLNRC ATL.MTG

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a>ear W TURKEY POINT NUCLEAR PLANT UNITS 3 5.4 MAJOR OUTAGE MODIFICATIONS Unit 3 Cycle 14

~

Enhancements Associated With Unisolable Small Bore High Energy Lines PLANT SIMPLIFICATION MODIFICATIONS

~

Annunciator "Darkboards"

~

S.l. Hot Leg Injection Cross-Tie Valves PLANT MAINTENANCEMODIFICATIONS o

RCP Motor Refurbishment Condenser Waterbox Outlet Expansion Joint PLANT REGULATORY MODIFICATIONS GL 89-10 MOVs

~

A46 Structural Modifications WPlPRESENTLNRC ATL.MTG

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TURKEY POINT NUCLEAR PLANT UNITS 3 &. 4 EROSION CORROSION PROGRAM AGGRESSIVE E/C INSPECTION PROGRAM

~

Expanded Scope Due to lVlid-Cycle Leaks of Moisture Separator Drain Line Independent review of EPRI CHECMATE model completed - no chscrepancies Base scope expansion based on results of thermography, past experience, industry experience Changed pipe 5 tee configuration to elbow 8c expander

~

Systems lnspected-Heater Drain Blowdown Extraction Steam Cross-Under Piping Main Steam

~

Condensate Feed water Moisture Separator WRPRESENWNRC ATl.MTG

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D 0)tS p(pE 0

AFTER p)pf S

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)0)lS 3D MSR DRAIN LINE (ASTM A53 GR.B OR ASTM A1D6 GR.B; SCHEDULE 40)

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TURKEY POlNT NUCLEAR PLANT UNlTS 3 8c,4 EROS1ON CORROSION PROGRAM INSPECTION RESULTS SCOPE PLANNED COMPONENT INSPECTIONS EXPANSIONS DUE TO INSPECTION RESULTS INSPECTIONS PERFORMED...........

TOTAL COMPONENTS O OR BELOW MIN WALL REPAIRS REPLACEMENTS (PLANNED AND UNPLANNED) 1992 U3 OUTAGE 124 22 18 1994 U3 OUTAGE 203 45 248 46 63

~

Replacement of Portions of Moisture Separator B, C, and D Drain Lines with 8" Carbon Steel

~

Replacement of Portions of Extraction Steam 5A and 5B Lines with 16" Chrome-Moly Alloy

~

MSR B, D, Drain Line Tee's Replaced with Transition Elbows WPLPRESENTLNRC ATL.MTG

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0yg p>4 TURKEY POINT NUCLEAR PLANT UNITS 3 5. 4 EROSION CORROSION PROGRAM

SUMMARY

OF COMPONENT REPLACEMENTS REPLACEMENT MATERIAL REPLACEMENT CAUSE PRE-PLANNED DEGRADED ORIFICE AT OR BELOW IVIIN WALL BELOW SCREENING OR MARGINAL REPLACED AS CONSERVATIVE MEASURE TOTAL QUANTITY 24 10 63 CARBON STEEL 13 23 CHROME-STAINLESS MOLY STEEL ALLOY 12 ISI ACTIVITIES

~

Augmented Inspections of Safety Related Feedwater System Inside Containment

~

Augmented Inspections of Feedwater Flow Control Valve Expanders/Reducers WPLPRESENRNRC ATL.MTG

++ogior TURKEY POINT NUCLEAR PLANT UNITS 3 8c 4 POST MODIFICATIONTESTING PMT REQUIREMENTS ENHANCED Changes Resulted From Self-Assessments of Previous Outages

~

Engineering Qls Revised to Increase Design Engineering Involvement with Complex Mod PMT

~

Engineering and Plant Tech Dept Interface for PMT Proceduralized (TDI-SE-007)

COMPLEX IVIODIFICATIONPMT CONSIDERATIONS (Flowchart)

WP>PAESENTWRC ATL.MTG

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TURKEY POINT NUCLEAR PLANT UNITS 3 5.4 ENHANCED PROCESS FOR POST MOD TESTING DESIGN CHANGE IMPLEMENTATIONREVIEW

~ 6IQNIFICANTEFFECTS TO CONTROL ROOM OPERATION

~ LCO ENTRY OR EXTENSIVE CLEARANCE REQURED

~ POTENTIAL FOR PLANTTRIP6

~ EXTENSIVE STER-DEPARTMENT NTERFACES REauaED

~ EVOLVES NEW, COMPLEX HARDWARE

~ EVOLVES LOGIC CHANGES NO YES

~ DEDICATEDPMT MEEmIQ w CONSIDER FAILURE MODES AS KEY INPUT TO TESTINQ CON6IDER PRE4lOD TESTINQ IMOCKZJP OR SIMUlATOR)PRIOR TO INSTALLATION ENQ REVIEW TEST PROCEDURE AS A MhlIMUM.SPECIFY/DOCUMENT ANY POST MOD TESTING REQUIRED TO DEMOSTRATE THE ACCEPTABLE FUNCTIONINQ OF THE DESIQN, SIMULATETHE ACTUALDESIQN CONFIQURATIONAS CLO6E AS POSSIBLE.

8PECIFY ACCEPTANCE CRITERIA.

ENQ REVIEW/APPROVE TEST RESULTS COMMUNICATEWITH PLANT DURWQ TEST PIAN DEVELOPMENT.TESTIQ. AND CLOSEOUT.

WP)PRESENTINRC ATLMTG

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~~a TURKEY POINT NUCLEAR PLANT UNITS 3 5. 4 POST MODIFICATIONTESTING FOLLOWlNG PCMs DETERMINED TO BE OF COMPLEX NATURE

~

Annunciator Darkboard

~

Flux Mapper

~

Turbine Runback

~

162/TDDO Relay

~

Generator Protection

~

H2 Purity Panel

~

DC Relays

~

Reactor Protection Relays RESULTS

~

All PNfTs Successful as Demonstrated by Smooth Startup WRPRESENTLNRC ATLMTG

04 TURKEY POINT NUCLEAR PLANT UNITS 3 R4 OPERATOR WORKAROUNDS OBJECTIVES

~

Identify long standing equipment issues which result in increased operator action

~

Perform a detailed investigation and identify a course of action

~

Implement the corrective actions in accordance with existing plant processes

~

Operator Survey

~

Prioritized I ist

~

Safety Review

~

7 of 21 Complete Others in progress WPLPRESENTLNRC ATL.MTG

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TURKEY POlNT NUCLEAR PLANT UNlTS 3 5.4 OPERATOR WORKAROUNDS TURBINE GLAND STEAM SUPPLY CV-"-3724-DOES NOT CONTROL PRESSURE

~

Revised calibration to correct static head in sense line

~

Vendor research verified design performance/options

~

Research PWO history and industry experience

~

Valve replaced during the Unit 3 outage WPLPRESENTLNRC ATL.MTG

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+ogpu +%4 TURKEY POINT NUCLEAR PLANT UNITS 3 % 4 OPERATOR WORKAROUNDS TURBINE GLAND STEAM SPILLOVER CV-+-3726 UNABLETO MAINTAINPRESSURE

~

Evaluate sources of excess steam in gland steam system 0

~

Vendor verify flow curves for existing valve

~

Revised calibration to correct static head in sense line

~

Review Cylinder Heating/Turbine Glands as major steam source WRPRESENTLNRC ATL.MTG

120 Gland Steam Supply GY-'-3724 Gland Steam Spillover CV-'-3725 Turbine Shaft

'land Seal Steam S stem Gland Steam Condenser Cylinder Heating Steam CV-'-3728 CY- -3729

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TURKEY POINT. NUCLEAR PLANT UNITS 3 Sc 4 SUlVIMARY

~

Effective Realtime Problem Solving

~

Consistent High-Level Performance in Planning for and Implementation of Outages

~

Initiatives to Find/Resolve Old Problems That Affect Operations and Maintenance

~

Sensitive to Issues Associated with Higher Capacity Factors, Age

~

Improved Performance Based on Lessons Learned

~

Results indicated by High Capacity Factors for Both Units Unit 3 - 95%

Unit 4-83%

~

Safe and Reliable Operation of the Plant WRPAESENDNRC ATL.MTG

TURKEY POINT NUCLEAR PLANT UNITS 3 & 4 TURKEY POINT TECHNICALSTAFF ORGANIZATION

~

CURRENT DEPARTMENT EFFORTS Task teams (2 examples}

ISI/IST Program updates and improvements Maintenance rule implementation Continued Improvement in thermal performance (PEPSE code)

Continuation of system engineer training Integrated valve maintenance program development Condition report administration / quarterly trend reports Event review teams (continued effort)

Temporary system alteration backlog reduction (currently at 3 for the site)

+~ogegq fL TURKEY POINT NUCLEAR PLANT UNITS 3 8c 4 TASK TEAMS EMERGENCY DIESEL GENERATOR AIR COMPRESSOR TASK TEAM Problem:

Repetitive failures {one per 3 month period} of the EDG AirStart Compressors Solution:

2.

3.

4.

5.

6.

Replaced pressure control switch Revised circuit breaker settings to reduce in-rush current Replaced air compressor unloader that provides consistent operation at the proper pressure rating Use of PST 580 sealant and repacking program to reduce air leaks Use of higher heat resistant head gasket material Used corrosion resistant material to replace original iron head assembly and parts.

Result:

Improved reliability {expect no failures per operating cycle}; Lower compressor temperatures with improved cycle times; lower air leakage {as low as 13 pounds In 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />s}

+'o~e<<W4 TURKEY POINT NUCLEAR PLANT UNITS 3 &4 CHARGING PUMP TASK TEAM Problem:

Low reliability due to: packing failures, valve guide failures, suction stabilizer failures, oil leaks, and speed control.

Status:

PACKING: Changed type of packing material and corrected a problem with sizing; developed leakage performance criteria, improved parts inspection, improved training, increased clearances in the packing and plunger area-RESULT: Improved packing performance to over 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> of operation before repack VALVEAND VALVEGUIDE: changed material to improve resistance RESULT: reduced valve and valve guide use by 45%

SUCTION STABILlZER: Reduced bladder

pressure, increased PM check and now have an indicator to track.

PUMP AND FLUID DRIVE OIL LEAKS: Identified source of leaks, developed conceptual design to preclude oil from entering the radwaste system, repaired accessible oil leaks CHARGING PUMP SPEED CONTROL: Awaiting overhaul of the 3B pump to test theories concerning the problem.

TURKEY POINT NUCLEAR PLANT UNITS 3 &4 IN-SERVICE INSPECTION AND TESTING

~

Ten year ISI/EST program revision complete.

It has been submitted to NRC and implemented at the site The revised IST program reduced the total number of requests for relief from ASME section XI Code from 35 to 7.

~

Currently perform a hand stroke of all snubbers during each refueling to identify any frozen snubber (this is not code required)

~

Procured and are using staff-the-art check valve diagnostic testing equipment (reduces the number of

. check valve disassembiies)

Procured and are using stat~f-thwart computerized equipment for testing the main steam safety valves

+epee'4 TURKEY POINT NUCLEAR PLANT UNITS 3 Sc 4 MAINTENANCERULE IMPLEMENTATION

~

System Engineers are tasked with implementing the rule on site

~

Risk significant systems have been determined and engineer assignments made for tracking key indicators

~

Data has been collected for a majority of the systems-goal is to have approximately one and one-half years worth of data as a minimum by the end of the year

~

Close coordination with our PSA department in reviewing and implementing changes to plant systems willbe maintained The integrated valve maintenance program willfit nicely into this overall effort

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REACTOR PHYSICS VENDOR INDEPENDENCE D.C. Poteralski Manager, Nuclear Fuel

REACTOR PHYSICS VENDOR INDEPENDENCE OBJ ECTIVES:

~ Perform Independent FPL Fuel Management

~ Develop Physics Input To Safety Analyses

~ Generate Start-up and Operations Data

REACTOR PHYSICS VENDOR INDEPENDENCE GOALS:

~ Replace Turkey Point (PTN) Vendor 100/o for Fuel Management - Now

~ Replace St. Lucie (PSL) Vendor 60-70'/o Now,

't00 lo in Future

~ High Quality Reload Design and Analysis

~ Provide Timely ln-house Support For Plant Operations

~ Maintain Effective Oversight of Remaining Vendor Activities

REACTOR PHYSICS VENDOR INDEPENDENCE Purchased Install Codes and Norkstatlons Completed Methods and Codes Tralnlng Developed Fstabllsh Reload and Internal Interface Controls Plans Letter to NRC (GL 83-1$ )

3/93 6/93 10/93 2/94 3/94 8/94 10/94 PTN 3/14 Reload Completed PTN 4/15 Reload Planned

REACTOR PHYSICS VENDOR INDEPENDENCE TRAINING:

~

Provided Hands-On Training Through Their Core Design Training Center

~ More than 5000 Manhours of Training Among FPL Nuclear Fuel Personnel

~ Training Received on Workstations, Codes and Procedures

REACTOR PHYSICS VENDOR INDEPENDENCE

\\

1 PROCEDURES AND CONTROLS:

~ QMETCOM Adopted as FPL Standards

~ FPL's QA Department Performed An )nterface Assessment for the PTN 3/14 Reload Effort

- Completed 12/93

~ Nuclear Fuel Internal Self-Assessment Also Performed For PTN 3/14 - Completed 1/94 "Lessons Learned" Disseminated to All Nuclear Fuel Personnel

~ FPL - Vendor Design Interface Document Deveioped For Physics Input to Safety Analyses

~ Detailed Reload Task Schedule Developed For PTN 4/15

REACTOR PHYSICS VENDOR INDEPENDENCE

SUMMARY

~ Reactor Physics Vendor Independence Meets Nuclear Division Goals

~ FPL Responsible For PTN Fuel Management Now, PSL in Future

~ Improved Knowledge Among FPL Personnel

~ Improved Plant Support

~ Lower Analysis Costs

Licensing j

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Iai prog LICENSING AND SPECIAL PROGRAMS SELF ASSESSMENT D.A. CULPEPPER Chief Engineer Engineering Assurance

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PeelIaI pp09 LICENSING AND SPECIAL PROGRAMS SELF ASSESSMENT POLICY:

~ Establish, maintain 8

continuously improve problem-solving culture

~ involvement at all levels of the organization

~ Use of senior personnel oversight for "high risk" activities

~ Nlulti-element process

Icensing S

Pe a

lai prog LICENSING AND SPECIAL PROGRAMS SELF ASSESSMENT MULTI-ELEMENTPROCESS

~ Self Assessment Guides

~ Technical Alerts

~ Report Cards

~ Calculation Quality Indicator

~ Design Reviews

~ Process Deviation Review

~ Functional Reviews

~ VP Quarterly Quality Review

IcensIn p(p'5 e!;"pa S

Pe f8 aI pfog LICENSING AND SPECIAL PROGRAMS SELF ASSESSMENT RECENT ASSESSMENTS:

~ TURKEY POINT DRAWING UPDATE Scope:

Modification-Related Docurrient Revisions Method:

Used Cross-Project Team Approach

==

Conclusions:==

Process Weakness in IEE/DCR Interface

~ ST. LUCIE PRESSURIZER SNUBBER DAMAGE Scope:

Assessed 1992 Post-Water Hammer Inspection Decisions Method: Probed Decision Influences

==

Conclusions:==

Process forthe Analysis of Dynamic Events Needs Strengthening

Icensing S

P e ra ial prog LICENSING AND SPECIAL PROGRAMS POST-MODIFICATION TESTING:

~ Assessments Performed in Indicated Weaknesses in PINT 1992

~ Technical Alerts Issued to Heighten Awareness within Engineering

~ Procedure Ghanges to Strengthen Engineering Involvement in PMT

~ Specific PMT Focus During 1993

~ Monitoring PINT Performance in 1994 No inwervice problems from mods PMT identified installation problems

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S S

P m

e ra iaj rog LICENSING AND SPECIAL PROGRAIIS SELF ASSESSMENT Current Focus:

Analysis of Near Misses

~ Root causes for near misses are the same as those for more serious events

~ Near misses "untampered" quality capture process

~ The most cost effective identification of weaknesses

~ The most objective opportunity for problem solving

THE FOUR LEV'f LS Of.

DEFE>USE Of UllALI1Y FULL SCOPE ON-LINE REAL-TIME SA )4PI.I.

OFF-I INL At TF'R-kkRE-f A(.f FPL IN A P PROPRIA T E ACTION THE IHDlVIDUAL/

WORK CROUP IST LEVEL OF'EFEHSE.

SUPERVISIOH MAHAGEMEHT 2HO I t Vf.

OF DEf'f.HSt I

I THTFRHAT OVERSIGHT SRI) I fVt A)F DEFFHSE I

j'TF RHAT OVERSIGH)

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T-'ERSPFCTIVE.

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AGENDA I.

Introduction II.

St. Lucie Initiatives III.

PSA Results/PSA Applications IV.

Turkey Point Initiatives V.

Reactor Physics Analysis-Vendorlndependence Vl.

Self Assessment Process Vll.

Closing Comments