ML17266A498

Forwards Responses to Requests for Addl Info.Responses Will Be Incorporated in Future Amend to FSAR

ML17266A498
Person / Time
Site:	Saint Lucie
Issue date:	09/11/1981
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
L-81-396, NUDOCS 8109150423
Download: ML17266A498 (320)

Text

REGULATORY LNI-ORMATION DISTRIBUTION SYSTE* (RIDS)

ACCESSION NBR;8109150423i DOC ~ DATE: 81/09/11 NOTARIZED: NO DOCKET FACIL~:50 389 St ~ Lucie Plant~ Unit 2g Florida Power L Liight Co. 05000389 AUTH ~ NAME- AUTHOR AFFILIATION RIGpR ~~ ED Florida Power L Light Co, I

EC P.~ NAME~ RF C IP I EN 1 AFFILIATION EISENHUT'< D. G, ~ Division of Licensing

~ ~

SUBJECT:

- Forwards responses to requests for addi info'esponses will be, incorporated in future emend to FSAR.

DISTRIBUTION CODEi: B001S COPIES RECEiIVED! LiTR T'ITLEi PSAR/FSAR AMDTS and Related

~

Correspondence ENCl + ../o SIZE':"

NOTES: lw >C.k 9 ' +< ~~ (Ow RECIPIENT COPIES RECIPIENT COPIES I~ CODE/NAME( LTTR ENCL ID CODE/NAME LTTR ENCL ACTION A/b LICENSNG 0 L<IC BR 03 BC 1 0 l'IC BR 03 LA 1 0 NERSESgV ~ 04 1 1 27 1-INTERNAL@ ACC ID EiVAL BRPb 1 1 AUX SYS BR 1 CHEM ENG BR 11 1 1 CONT SYS BR 09 1 1 CORE PERF BR 10. 1 1 EFF TR SYS 1 1 EQUIP QUAL BR13" 3 3 BR12'EOSCIENCES 28 2 2 HUB FACT ENG 40. 1 1 HYD/GEO BR 30 2 2 I3C SYS BR 16" 1 ILE 06 3 IE'/EPDB;, 35 1 1 IE/EPLB 36 3 3 LIC GUID BR 1 1 lIC QUAL'R 32 1 1 MATL ENG BR 17 1 MECH ENG BR 18 1 1 MPA 1 0 OELD 0, OP LIC BR 34 1 1 POWER SYS BR 19 1 1 PROC/TST REV 20. 1 1 QA BR 21 1 Ra SESS BR22" 1 1 REAC SYS BR 23 1 1 4

01 1 1 SIT ANAL BR 24 1 1 NG 8R25. 1 1 EXTERNALS: ACRS 41 16 16 F EMA REP DI V 39 1 1 LPDR 03 1 1 NRC PDR 02 1 1.

NSIC 05 1 1 NTIS 1 1 8t=.p t 8 )",q)

TOTAL NUHBER'F COPIES REQUIRED: LTTR 62 ENCL 57

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, September FLORIDA POWER 8I LIGHT COMPANY 11, 1981 Letter 8L-81-396 Office of Nuclear Reactor Regulation aft',f I'tQ '~,

198~ ~

Attention: Mr. Darrell G. Eisenhut, Director S ~I' Division of Licensing U.S. Nuclear Regulatory Commission VI5y ~~0~55I5I COALMt5$ ~ yl Washington, D. C. 20555

Dear Mr. Eisenhut:

Re: St. Lucie Unit 2 Docket No. 50-389 Final Safety Analysis Report Re uests For Additional Information Attached are Florida Power & Light Company (FPL) responses to NRC staff requests for additional information which have not been formally submitted on the St. Lucie Unit 2 docket. These responses will be incorporated into the St. Lucie Unit 2 FSAR in a future amendment.

Very truly yours, Robert E. Uhrig Vice President Advanced Systems & Technology REU/TCG/nlc Attachments cc: J. P. O'Reilly, Director, Region II (w/o attachments)

Harold F. Reis, Esquire (w/o attachments)

(gk ool yis0 810911

'109150423 PDR ADOCK 05000389 '1 A PDR HELPING BUILD FLORIDA

4 E I

'l $ I t~

I 0

Attachments to L-81-396 September 11, 1981 A. -

Revised response to 282.1 B. (1) Figure 8.3.6 (125 Volt DC Bus transfer circuit from control room)

(2) Description of the showers in the battery room.

C. Revised Chapter 13.

D. Revised FSAR section 10.4.9.5 E. Revised FSAR section 5.4.2.2 F. Revised response to question 8260.5 G. Revised res'ponse to question 8460.2 8109150423

I 282'. 1 The information you have provided is insufficient

'(10 '.5) for us to evaluate the secondary water chemistry control'rogram. Provide a summary of operative procedures to be used for the steam generator second-axy water chemistxy control and monitoring program, addressing the following:

1. Sampling (requency for the critical chemical and other parameters and of contxol points or limits for these parameters for each mode of operation; normal operation, hot startup, cold startup, hot shutdown, cold wet, layup.

2. Procedures used to measure the values of the critical parameters;

3. Location of process sampling points;

4. Procedures for the, recording and management of data;

5. Procedures defining corrective actions* for off-control point chemistry conditions de-tailing time allowed at of'f-chemistry conditions; and,

6. The procedure identifying (a) the authority responsible for the interpretation of the data and (b) the sequence and timing of adminis tra-tive events required to initiate corrective action.

Answer: Although the procedures are Unit 1 procedures, simi-lar procedures will be written for Unit, 2 (taking into account any CE recommended. changes.) The numbers below correspond to the question in the request for info.

'. Sampling frequency OC-01.

- located mainly in procedure

2. Values of critical parameters - from analytical procedures derived from ASTM to ANWA standards.

P*

• Pl

<Branch Technical positron MTEB 5-3 describes the acceptable means for monitoring secondary side water chemistry in PNR steam gen-erators, including corrective actions for off-control. point chemistry conditions. However, the staff is amen'able to alter-natives, particularly to Branch Technical Position B.3.b(9) of HTEB 5-3 (96-.hour time limit to repair or plug confirmed conden-ser tube leaks.

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3. Sample pt location mainly in procedure I'

'. C-50, C-51, C-81C Recording and management procedure 5's C-pl, C-02

& C-83. (See attached Figure of data - mainly in

& C-08.

282.l-l)

5. Corrective action mainly in procedures 6-51, C-81C, C-50, C-83-and 0610030. (note l)

6. i) Data interpretation authority - procedures C-Ol, C-02 & C-08 (note 2) b) Initiation of corrective action procedures C-50, C-51, C-81C , C-83 and p6lpp3p.

Notes: l. Xn the event of condenser .in-leakage the affected waterbox will be removed fxom service and attempts made to locate and repair the leak. Saw-dust will not be used to plug the leak. Use of saw-dust to stop leakage does not apply to nuclear units.

The chemistry supervisor is the authority responsible for data interpretation and forwarding recommenda-tions for corrective action to the shift supervisor.

predetermined setpoints (as defined by the 0

When plant procedures) .are exceeded, the shift supervisor decides on the corr'ective action.

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NQZ X3 Stean Gmetator is caM.ozL conducU.Wty for detect" on of malL Xmas.

5i2~X.X Ratify Road Dc'spatular of. prublcnu ~md that you are p roceedm R to a'mtdovni I

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Page 3 of 9 OPSY'~ PROCEDURE '.iO. 063.0030, REV. 5 CO%)USER TUBE 'LEAK 5.0 Instructions- (Continued) 5.2 (Continued) 5.2,2 (Continued) 5.2,2 1 Start or increase stean generator blovdown on both generators to maximum (125 gpn/SG)-

MXE: Divert blovdown to di charge canal to prevent chloride contamination of MT'z and resin bed .

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5.2,2.2 Verify leak. by uonStoring other syr7toms listed

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5.2.2i3 Inforn load dispatcher that power vill be reduced to a load consistent with the anount oZ circulating

.puups that. wil3 .be available after securing pump of arfected quadrant. Coxuaence load reduction.

5.2,2.4 Manually override Condensate reject Ya1ve LCV<<2Z-5 from control rocnn. Honitox hotve21 level care-C fully vhile reject valve is isolated r

- 5.2 2i5 TaRe readings on the four Hoa'oil quadrant cation

• ' conductivity meters at ~ters at the ~teorological pane3. in control, Leak vill be in quadrant with-the

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5.Z.Z.6 After load. reduction has proceeded to a power level where afrected quadrants circulator can be secured, V

remove lea~g quadrant frcci service as follows

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'.. 5 2.2.6.2 Close air suction valve Tron water box air suction valve frere condensato

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"'l-";"'.".'-. '";"""'5.2 2.6.2 ~ Stop affected quadrant's circulating water pump in accordance with Operating . rocedure

~;- ', '*.- . M. 0620020.

NOTE'f the circulating water pump is secured due to condenser tube failure, the water box should be quick drained by placing the control- ~~ .tch on MGB-l02 to the Pull to Drawn" Position 5 '2 2-6 3 Insure v'acuum on water box for that quadrant

& broken. This normally occurs automatically why %Sin circulat~g pump is stopped

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.0 Page 4 of 9 OPERAZMG KMCfH)URE!D. 0610030,

'"' CD%)USER TUBE LELZ

~. 5 5.D IKIBKKIICMOIIS: (~~ti~mad 5~2 (Continued) 5,2.2 (Continued) 5.2,2. 6 (Continued) 5".2.2.6.4 Check S/G conductKvitie and condensate conductivity for a decr~~ing trend as

~ater drains bein~ leak to insure that the right quadrant has been isolated. If not decreasing try and 1ocate the leak again by checking the Howell cation con-ductivity mater readings on rmaining quadrants. If during the t& from securing of circulator to unit shutdown completion the condensate cation decreases belav l0 who/cm aud both S/G canducti-vitiea are + 200 umho/cn and decreasing.

Power reduction may.be secured and unit maintained a proper power leve1 con-sistent vith circulator floe.

5.3 Subsequent Action:

5.3.1 Notify Maintenance and Chemistry Departments.

5.3 2 Continue aaximum Mm<mm until 'S/G chemistty is restored to novel operating limits.

Il 5 ~ 3~3 Have Haintenanc'A lnrate and repair leak<

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-DATE Sl LUCIE 07/20/81, XYPIST: ek Page2 n TAPE NO.  : SD611 D611'AGE DATE PRINTED  : 07/20/81 1

SL2-FSAR 0 CHAPTER'3

'3 .02 13.0 CONDUCT OF OPERATIONS 04 05 13. 1 ORGANIZATIONAL STRUCTURE OF APPLICANT 06 07 08 13.1 ~ 1, MANAGEMENT AND TECHNICAL SUPPORT ORGANIZATION 09 FP&L utilizes a Project Management 'leam approach to integrate the varied 10 activities required to successfully complete the St Lucie Unit 2 project.

11 12 The project Management Organization is the responsibility of a Vice presi-

.13 dent who reports to an Executive Vice President. The Project General 14 Manager reports to the Director of Projects and is responsible for coordi-15 nating all groups involved with the project both inside and outside the 16 company. The Project Team is composed of staff representatives from sup-17 '. porting FP&L departments and the architect-engineer. FP&L team members 18 report to the Project General Manager on a line basis. Team members repre-19 senting the architect-engineer, for plant design and construction support, 20 are responsible to the Project General Manager through contractual ob-21 'igation. These Project Team, members are responsible for bringing to the 22 project the expertise of their resident departments. Respective department 23- heads are responsible for the quality of technical services provided by 24 Project Team Members, 2

2 After St Lucie Unit 2 becomes operational, the Project Management Organiz-ation,has the responsibility for managing the implementation of certain 28 specific modifications to the operating unit.

29 30 A brief description of FP&L Engineering, Quality Assurance, Licensing, 31 Construction and Operating (Power Resources) Departments is given below.

32 These functions are the responsibility of an Executive Vice President,

-.33 who reports directly to the President. The reporting relationships are 34 shown on Figure 13.1-1.

35 36 The organization of the Project leam is-shown on Figure 13.1-2.

37

'38 Project design and engineering support is the responsibility of the Chief 39 Engineer, Power Plant Engineering, who reports to the Vice President of 40 Engineering, Construction and Projects who reports to the Executive Vice ~Pg'i 41 President. The Power Plant Engineering Department, through the Engineer<<

42 ,ing Project Manager, and members of the Project Team, provides independent 43 analyses and evaluations of key safety related aspects of architect-44 s=,

'v engineer and vendor designs and performance commensurate with licensing re-

- 45 quirements, assures integration of nuclear design and operating experience

- 46 f rotmhe Power Resources, Department t evaluates problem and R"RC action con- P+ >

~ 47 cerning other utilities which could affect FP&L plants, and assists in (

48 evaluating bids for future nuclear plants.

49 50 Corporate quality assurance, nuclear plant licensing management, and co-

. 5 ordination of research and development are the, responsibility of the Vice President " Advanced Systems & Technology, Wo reports directly to the 5

54 s

s s e'I

13. I- I Amendment No, g, +&f824

PROJECT ST LUCIE DATE PRINTED  :, 07/24/Bl 3)ATE 07/20/81, TYPIST: ek Page7 n TAPE NO. SD611 D611 PAGE 2 SL2-FSAR 03 04

,4 Executive Vice President.

Management are represented Corporate Quality Assurance and Licensing on the Project Team. Details of the Quality Assurance Department organization are contained in FP&L Topical Quality Assurance Report (FP&L TQAR) 1-76A, Rev. 4.

05 06 The Power Plant Construction Department is the responsibility of the Direc-07 tor of Construction, who reports to the Vice President of Engineering, 08 Construction and Projects, who reports to the Executive Vice President.

This department provides construction methods, handles construction con-10 tracts, and provides quality control and labor relations personnel.

ll 12 Power plant operation and maintenance are the responsibility of the Vice 13 President - Power Resources who reports to the Executive Vice President.

14 The Manager of Power Resources - Nuclear is responsible for all matters 15 concerning the operation and maintenance of nuclear power plants. The 16 Assistant Manager Power Resources - Nuclear is responsible for those opera-17 tion and maintenance matters specifically related to the St Lucie Plant.

18 The Manager Power Resources Nuclear Services reports to the Manager of 19 Power Resources Nuclear and is in charge of the nuclear support staff.

20 The Nuclear Support Staff of the Power Resources Department is established 21 to furnish technical support in those areas of techriical expertist that 22 are unique to nuclear power plants. The Manager of Power Resources - Ser-vices reports to the Vice President - Power Resources and .is responsible 24 for staff technical support in areas common to both nuclear and fossil 25 plants. The Services staff is composed of Operations, Maintenance, Ad>>

ministration, Instrument and Control, and Test and Performance groups which provide in-house technical support to operating plants in a broad spectrum of engineering, technical and scientific disciplines. Specific technical support areas assigned to various section supervisors are indicated on 30 Figure 13.1-3 along with the authorized staffing level for each section.

31 Actual staffing levels may v'ary dependent upon tha support required.

32 Regulatory requirements for plant support specified in 9 33 Regulatory Guide 8.3, "Film Badge Performance Criteria" February 1973(RO) 34 and ANSI/8.7 are fulfilled by the Power Resources staff sections. During 35 preliminary design, engineering and construction activities that are the

. 36 responsibility of Project Management, Power Resources is represented by the 37 Power Resources Team Member.

38 39 The Pow'er Resources and Power Plant Engineering Departments have been 40 expanded to support the design and operation of Turkey Point Units 3 and 41 4 and St Lucie.Units 1 and 2.

42 43 13.1.1.1 S ecific Desi n and 0 eratin Activities

- 44 45 The following paragraphs summarize the degree to which certain design, 46 construction and preoperational activities are accomplished and describes 47 the specific responsibilities and activities for technical support to operation.

49 50 51 13 ~ 1-2 Amendment go. g, (+R'ty s

PROJEC?: ST Ll'CIE DATE PRINTED  : 07/20/81

.DATE 07/20/81, TYPIS?: ek Page7 n TAPE NO. SD6'll D611 PAGE 3 SL2-F SAR e

04 05 13.1.1.1.1 a) Meteorology A

Principa'1 Site-Related Engineering Work meteorological monitoring program was established at the site to 06 provide those meteorological factors that bear upon pl'ant design, 07 'operation and safety. The program has been conducted by Dames &

08 Moore and is discussed in Section 2.3. Direction and supervision of 09 the program is provided by FP&L.

10 ll 12 b) Geology and Hydrology 13 Law Engineering of Atlanta, Georgia performed the geologic and sexs-14 mologic studies of the site.

I 15 16 Dur ing construction, Ebasco Services, Inc. soils engineers inspect-17 ed the excavation and mapped any significant geologic features en-18 countered. Geology, hydrology and seismology is discussed in de-19 tail in Sections 2.4 and 2.5.

~ 20 21 c) Demography

.22 23 Ebasco Services Inc., performed demographic studies relative to 24 population within 50 miles of the plant as discussed in Subsection 2.1.3.

d) Environmental Effects A preoperational monitoring program for St Lucie Unit 2 was de-veloped to enable the collection of hydrothermal, biological and 31 water quality data necessary to determine possible impacts on the 32 environment due to construction activities and to establish a pre-33 operational baseline from which to evaluate future environmental 34 monitoring data. This program is described in the Environmental 35 Report and is performed by Applied Biology Inc. and FP&L.

36 37 Design of Plant and Auxiliary Systems 38 39 An evaluation of engineering progress as of December 31, 1979 40 indicated overall completion of design and engineering of 95.2 41 percent.

~ 42 43 Review and Approval of Plant Design Features

- 44 45 Design control for review is performed in accordance with the 46 quality assurance program in FP&L 'Topical Quality Assuranc'e Report

" 47 (PPLIQAR) )-766,, Rev. 4.

48 49 g) Site Layout with Respect to Environmental Effects and Security

., 50 Provisions

,51 'I 5 A preoperational monitoring program for St Lucie Unit 2 was de-veloped to enable the collection of physical, chemical, and eco-logy.cal para)neters necessary to determine possible impacts on the 13 ' 3 Amendment No. P',

t l'4Jl

.,DATE I >Z LQ.lk.

07/20/81, TYPIST: ek Pageos n TAPE NO.

'AZE. SD611 Pklh'lEL' D611 07/20/81 PAGE 4 SL2-F SAR environment due to construction activities and to establish a pre-02 operational baseline from which to evaluate future environmental 03 monitoring. Applied Biology Inc. has carried out the biological 04 and water quality monitoring programs.

05 06 Security provisions in accordance with applicable NRC regulations 07 are incorporated into overall site development by developing se-08 curity criteria and incorporating these criteria into design draw-09 ings and specifications .by FP&L and Ebasco Services, Inc. Details 10 of security provisi'ons are provided in the security program in 11 Section 13.6.

12 13 h) Development of Safety Analysis 'Reports 14 15 Overall responsibility for preparation of the FSAR rests with Power 3.6 Plant Engineering. Preparation of the individual sections was 17 assigned to the cognizant technical groups within FP&L or to Ebasco 18" Services, Inc. for balance of plant systems, and Combustion 19 Engineering for Nuclear Steam Supply System (NSSS) systems.

.20 21 i) 'eview. and Approval of Material and Component Specxficatxons 22 23 All'safety re)ated project specif'ications are reviewed in accordance 24 with the quality assurance program in FP&L Topical Quality As-2c surance Report (FPLZQAR) 1-76A, Rev. 4.

2 2 Procurement of Materials and Equipment 28 ~

29, As of December 31, 1979, approximately 84.6 percent of the over-30 all total procurement effort, is completed.

31 32 k) Management and Review of Construction Activities 33 34 Management and review of construction activities are performed by 35 the FP&L Construction Department and Project General Management.

36 37 13.1 1-1.2

~ Preoperational Activities 38

'39 a) Development of Human Engineering Design Objectives and Design Phase

=40 Review of Proposed Main Control Room Layouts

-41 42 The human engineering design objectives are developed jointly between 43 FP&L project team members and Ebasco Services, Inc. engineering design 44 personnel and conform to NUREG 0770.

45 46 The control room layouts are designed to include all the features 47 and components necessary for monitoring and controlling the 48 operations of the nuclear power plant with a high degree of re-49 liability. The control boards and panels act as a major tool in the 50 operator's interface with all the plant systems. They house con-trol, instrumentation, display and annunciation equi,pment and are arranged within the control room to facilitate the operator's task l3. 1-4 Amendment He, g QML}

-"PROJECT: ST LUCIE DATE'PRINTED  : 07/24/81 DATE 07/24/81, TYPIST: n TAPE NO. SD611 D611 PAGE 5 Pageos SL2-FSAR of control and protection. In addition the control room layouts

'nclude advanced concepts such as video displays, computer based

!e 05 data acquisition, logging. and analysis.

The basic human engineering design objectives were to improve the 06 operator's ability to maintain communication with all the systems 07 in the plant. The control boards utilize a modular design concept with compact miniaturized devices for more efficient functional 09 display. The operator, having the control board information on a 10 smaller area, will have better control of the plant operation.

11 12 b) Development and Implementation of Staff Recruiting and Training 13 Program 14 15 The staffing plan and implementation schedule is presented in Table 16 13.1-1. The training program is presented in Section 13.2.

17 18 c) Development of Plans for Initial Testing 19 20 The St Lucie Unit 2 Startup Group has the responsibility for .the 21 integrated operations of the Startup Program. The scope of the 22 testing to be accomplished during the test program is defined in 23 ~ Section 14.2.

24

'25 d) Development of Plant Maintenance Programs Plant maintenance programs for St Lucie Unit 2 are developed by the FP&L Power Resources Department by upgrading and expanding, as needed, the existing programs for St Lucie Unit l.

13.1.1.1.3 Technical Support for Operations

.32 33 Technical services and backup support for the operating organization are 34 also discussed in Section 13.1. Backup and support for the operating 35 organization in the specific capabilities of operating experience assess-36 ment, nuclear, mechanical, structural, electrical, thermo-hydraulic, 37 meteorology and materials, instrumentation and controls, plant chemistry, and fueling and refueling, operation engineering and analysis is available 39 in FP&L's Power Plant Engineering Department; in addition to the staff 40 support available within the Power Resources General Office Group.

41 42 Maintenance and backfit construction support is available through FP&L's 43 Power Plant Construction Department, providing management of contractor forces, in addition to the staff support available within the Power Re-

.45 sources General Office Group.

46 47 13.1.1.2 ~Or anizational Arran ement 48 49 The FP&L General Office Management and Support Department Organization is 50 shown on Figures 13.1-1 through 13.)-7.

51 52 33 sa 13.1- 5 Amendment Ho. P,

As shown on Figure 13.1-1, all departments, with their respective Vice Pre-sidents> with responsibility for the design, licensing, constructions quality assurance and operations, report to an Executive Vice President, who reports to the President of FP6L.

alifications'or key xn d'd ivi ua lss within the organization are provided in wi L

(J ~ a ( ~<~) Ca%(>.~

4S A~~ p. /

For specific activities, FP&L may elect to enter'nto a continual arrange-ment with a consulting organization in order to secure specific or spe-.

.lcialized expertise or to solicit .a recommendation,on a.course of action.

FP6L may .'so enter into contractural arrangement for construction ser-

~

vices provided by a contractor for specific improvement or modification-work. Ex" ended organizations will be responsible to cognizant personnel within FPSL.

After St '"sic Unit 2 Segins operation, the project Management Organization may manage the implementation. of specific major modifications of the plant or may manage a modification program for the unit if the program is ex-tensive, Tne operations of the Project Management Group is discussed in

.. Subsection 13. 1. l.

13. 1. 1. 3 Head eartera St~affin For personnel within the FP6L General Office Management and Support De-partments who have duties and responsibilities relevant to St Lucie Unit 2, as reflected in the organization charts of Subsection 13.1.1. 2, summaries of function, expertise and education are presented below.

'a

• . f t la V

'l I

4 a '

I

' a

SL2-F SAR 11.J. Dager, Jr.

Vire President

~

En ineerin , Pro'ects & Construction Educational Back round:

1975, S anford Executive Program, Stanford University 1949-1951, University of California, Berkeley, CA M. S., Bioradiology (Maj or: Nuclear Physics) 1948"1949, U.S. Navy Postgraduate School, Annapolis, HD j

(Ma o r: Nuclear Engineering No Degree) 1942-194S, United States Military Academy, West Point, New York, B. S, Military Engineering Ex erience:

. N el area'.J.

Dager has partic.ipated in nuclear wor'k since l948 with active involve-

~

ment in planning, engineering, construction and operation of over twenty nur lear rear:tors. 1!.J. Dager was licensed to operate four different nur lear reacto power plants ~

1945-195S V. S. Army, Corps of Engineers, Pl atoon Leader, Company Commander, Assistant Division Engineer, Nuc;lear Engineer Far East Command, Chief Special Studies Section Engineer Research and Development Laboratories.

1955-1956 Westinghouse Electric Corp.', Bettis Laboratory, Senior Engineer, Shippingport Project.

1956 1958 General Electric Co. Project Engineer Lorkheed.

Project (3 test reactors).

1958-1959 General Elec.tric, Project Engineer Humboldt Bay,

~

PG&E (50 Hev BWR). lr 1959-1962 General Electric, Hanager Special Projects, Test Reactors, Control System N.S. Savannah, Control

& Sa fety System Indian Point 1, !b.gh Temperature He Loop.

1962-!963 Gc.nera! E! ec tr ic:,  % i ft Superv isor', Big Rock Po int, Consumers Power Co ~

1963-!96-' ~

Genera! Elec:tric:, Manager Shift Operations, Japan Power Demonstration Reac:tora

SL2-FSAR I

1964-1967 General Electric, Principal Proj ect Engineer (Proj ect Manager) Southwest Experimental Test Oxide Reactor.

i 1967-1972 General Electric, Project MartagerF Cooper Project, Nebraska Public Power District - Iowa Power and Light .

1972-1973 Nebraska Public Power Distrirt, Assistant General Manager for power supply, generation engineering, and s

quality assurance.

1973-'Jan, '976 FP&L; Manager of Power. Resources - Nuclear; responsible for startup preparations and operation of all nuclear power plants in FP&L system.

~A 4 ssF Aosd ~7 Jane Sept. 1976 Asistant to Group Vice President.

s 1976 " Present Vice-President-Engineering, Projects and Construdtion.

f Other +4 ts,d. c s~ ~

~

Mr: Dager is presently Vice President of Engineering, Project/ and Construction. 1h is responsible for the design and construction of

, major, capital additions to the FP&L System.

Other responsible position" held include Manager, Power Resources Nuclear; Assistant General Manager, Nebraska Public Power District>

Proj ec t- Manager General El ec tric Company and Captain, U. S. Army Corps of Engineers.e J.W. Williams, Jr.

Director o Pro'ects~

Function, Rss onsibiiitiss snd Au~thori.t Primarily accountable for directing and coordinating the activities of the assigned Project General Managers, the manager of New Pro-jerts and the Manager of Project Control Services to meet the ob-.

jectives of the Project Management organization and FP&L Management.

Overal1 responsibil ity for developing, establishing, implementing and . onitoring pol icies, guidelines, procedures and technical and adm nistrative aspects of all projert related activities to insure assigned projects meet Project Management and corporate goals and ob 3 ec t l.ves ~

t'h project, for the purpose of defining the role of the Director of Projerts, typical ly enrcrnpasses the planning, design, construction, start-up and asso" a iated activities required for the completion and commerrial operation oft any new power generation facilit> but may include any task

~

assigned by management.

13. 1-8

SL2-FSAR Overall responsibility for obtaining manag ment approval of project strategies, plans"and budgets, for reporting both progress and status of assigned projects, for effecting timely management action to ensure the continued progress of project activities and for ob-taining completion of projects within approval budget, schedule and technical specification constraints and in compliarice with regula-tions and agreements made with outside organizations and agencies.

Educational Bac~k round:

BChE University of Florida, Gainesville FPhL Training instructor on Steam Generator 6 Turbine Technology 1955<<63 Nuclear Power Reactor - University 1966 of Florida Nuclear Fuel Management NUS 1966 Radiological Health - PHS 1966 Reactor Safety & Hazards Evaluation, PHS 1967 Advanced Nuclear Technology-University of Florida 1967 Stanford Executive Program Stanford University 1975 S ecific Nuclear Courses:

Nuclear Power Reactor - University of Florida, 1966 1

Nuclear Fuel Management - NUS, 1966 Radiological Health PHS, 1966 r

\

Reactor Safety 6 Hazards Evaluation <<PHS, 1967 Advanced Nuclear Technology University of Florida,'967 Ex erience:

Nuc1 ear J, W. Wi1 liams, Jr. has participated in FPf L's nuclear program since 1966, with active involvement in the preliminary planning and con-struction phases o f the nuclear plant Turkey Point Units 3 and 4, and completed the above courses in nuclear technology which relate to licensing.

a

13. 1-9 a

SL2-FSAR Ex erience:

Other Mr. Williams is presently Director of Projects, providing direction for six projects and Project Control Services Department; directs work of eight managers or assistant managers and is supported by 34 other personnel.

Other responsibilities. and positions held include: Plant Betterment Foreman, Plant Results Foreman,and Assistant Plant Superintendent-Operations and Plant Superintendent for Palatka Plant; Assistant Plant Supervisor-Operations and Plant Superi;ntendent at Cutler Plant; Plant Superintendent for Turkey Point Plant"Units 1 and 2 witn responsibilities of a safe and successful start-up, and subse-quent operation and maintenance of the plant., along with providing supervision for .plant personnel; Manager, Quality Assurance in-cluding development and implementation of, methods and systems to

. collect, record, monitor and report data for quality assurance af-fected items.

Project General Manager St. Lucie Project, providing coordination and control of activities necessary to complete the project within schedule, budge t and technical'peci fication constraints.

W. B. Derrickson Pro'ect General Mana er (PGM)

A.

Primarily accountable for directing and coordinating the timely per formance by all departments involved in the completion of a nuclear power plant within a designated time span and within the approved budget limitations and all technical specifications.

Coordinates and parti'cipates in decisions and activities relating to design, permitting, purchasing, licensing, construction and start"up of the nuclear plant project assigned to him. Establishes schedules for, and monitors, each of the activities of the depart-ments and groups so as to achieve the objectives relating to qual-ity, cost and operating date of the project. -.

Administers the project planning and scheduling system through which all areas relative to the construction of the nuclear plant and startup is planned and scheduled from authorization to commercial operation.

The PGM must be cognizant of all deviations from established ob" jectives in construction of the n uclear power plant, initiate action t'

to correct the deviation and the steps necessary to prevent the oc-currence of subsequent deviations resolve conflicts between all parties at the construction site and the various departments of the Company; secure or render timely decisions which will aid the Com-pany and the Contractor to meet t ime schedules; maintain a close e

SL2-F SAR relationship with Division Managers and other Division and District personnel regarding the interface of construction plans and Division activities,'eview actual and potential problem areas on a continu-ing basis so as to identify, isolate and arrive at the best method of problen solution; keep interested parties advised of progress and of deviations from schedules and budgets; and coordinate activities between construction forces and all other departments to insure a smooth transition of the completed project to -the commercial opera-t'on of the plant.

E=ucation:

BSEE - University of Delaware 1964 Experience:

Nuclear Mr. Derrickson joined FP&L in 1970 as an electrical start-up engineer at Turkey Point. He then progressed to Electrical Start~p Supervisor and in 1972 to Start-up Coordinator. In the latter posi-tion he assumed responsibility for all start-up activities for Turkey Point Unit 4. In 1973 he transferred to the Plant Construc-tion Department and was appointed Project Construction Supervisor for St. Lucie Unit 1. In 1974 Mr. Derrickson returned to the Gene-ral Office as Superintendent of Nuclear Plant Construction.

In 1975 he was appointed Assistant Project General Manager of the Lucie Project, Units 1 and 2. 't.

In 1976 a need for management attention to work at Turkey Point arose and Mr. Derrickson was appointed Project General Manager for major facility'modifications.

In 1976 a vacancy arose on the St. 'Lucie Project and Mr. Derrickson was appointed to his current position as Project General Manager of St. Lucie Unit 2 and Unit 1 modifications.

Ex erience:

Other A

Prior to joining FP&L, Mr. Derrickson worked for four years as an Electrical Maintenance Engineer for Delmarva Power & Light Company.

In this capacity he spent one year at the Indian River Delaware Plant and three years at the Vienna Maryl.and Plant. His chief activities were planning, scheduling and supervising 'periodic maintenance on plant equipment, supervising facility modifica-t ons and short term load forecasting and generation scheduling.

~

The two years at Hercules Inc. were spent in the design and startup of chemical plants. Activities centered mainly in the instrumenta-tion area. During the two years he worked on various proj ects at f ive plants.

SL2-FSAR At Sun Shipbuilding and Drydock Company the responsibilities were in the R6D area. The primary project was to develop a computer control system for automatic ship navigation.

G.B Brad shaw Asst Pro'ect General Mana er Assi "s the Project General Manager in directing and coordinat> ng the t'ly performance by all departments involved in the c deletion of a nu >ear power plant within a designated time span and v thin the appro ed budget limitations and all technical specific tions.

II Aids in deci ons and activities relating to design, pe itting, purch" sing, li ensing; construction and start-up of th nuclear plant project a signed to him. As assigned, establis es schedules forand monitors, each of the activities of the depa tments and groups so as to ac ieve the objectives relating to uality, cost and operating date the project.

Also participates in a inistering the project n'rming system through which all areas elatiye to the constr ction of the nuclear plant is planned and sche 'ed from authoriza ion to commercial operation.

He m st be cognizant of all d yiations fro. established objectives in construction of the nuclear gower pla f, initiate action to

'correct the ',deviation and the st s'ec ssary to prevent the occur-rence 'of subsequent deviations; r solv conf1.icts between all par-ties at the construction site and e various departments of the Company; review actual and potential problan areas on a continuing

, basis so as to identity, isolate a rive at the best method of proble solution; keep the PGM ad xsed f progress and of deviations from schedules and budgets; and oordina activities between con-struction forces and all other epartment's to insure a smooth'ran-of the completed proje to the comm cial operation of the 'ition plant.

B ~ Education:

Bachelor of Science, Mechanical Engineering 1964 Master of Science, Nuc16ar Engineering, University Cali fornia, 1965 Manage..ent Certifica e, Univer ity of California Exten ion, 19I5 C. Ex erience:

t<uc 1ea.r Registe"ed Pro,essional Nuclear Engineer in the State of Calx ornia, Mr ~ Bradsha- gas licensed to operate a research reactor nd wa employed hal ~ time by the University of California at Los Angel s

. SL2-FSAR a a licensed nuclear research reactor operator assis ing in numer-ous scientific experiments. Since 1973 has been nvolved in 'the Proj qt Management and Project Engineering of nucl r power genera-tion uX ts.

Presently, Assistant Project General Manager fo the St. Lucie Unit 2 nuclear p wer plant. Responsible for manag ent 'nd project di-rection of u 'lity activities on 850 MWe nucl ar plant. Activities include applic tion of cost and schedule .con rol techniques for the entire project e fort, coordination of the u ility functional depart-ment activities and interfaces with the ar hitect-engineer and con-jectss.

struction organiza 'on. He assisted in the evolution, planning, organizing and imple entation of new ility management concepts "or improving control f 'roject costs and schedule on large pro-

\

0 her 4 General Atomic Com an, San ieg, California Manager, Applied Fuel'ngineering. Responsible for design control, licensing support, fuel cycle environment effects, presentation of testi-mony at licensing hearings, pro ec control systems and coordina-tion of all project support ac iviti s within the Fuel Engineering Division for the large High T mperatu e Gas-Cooled Reactor (BTGR).

Fuel Project Engineer-Assig ed to th 'hiladelphia Electric

'- Ful ton-.Generating Station T.

roject fox t:n 1160 M'shte. flTGRs and the Delmarva power and ght Summit St tion project for twin 770 tele llTGRs, both with foal contract valses in excess of $ 100 million. Responsibili es included coordx'tion of all fuel -.

activities related to design, development, icensing, contract provisions and project ontrol of the projects.

Staff and Senior engineer, Special Nuclear S stems Division.

Responsible as a Ask Leader and Principal Engineer for the design; development and test of direct energy conversion space nuclear power sy tems. Performed thermal design electrical performance predi tions, reliability assessment an evaluation of flight data.

s Member of the 'chnical Staf f. Responsible for the Gesign and developme o high temperature radioisotope heat sources; carrying out RGD programs; performing radiation leffects st dies on satellite power systems; and, evaluating mobile nuc ear reactors. Obtained Air Force patent on eat

-"source.

I "Additio ally, published 20 Technical Papers on Energy Conversion Techno) ogy 1 " T~chnical Paper on Cost oE Nuclear Plant Delays

,1 " echnical'Paper on Licensing and Construction

,o! St. Lucie Nuclear Plant

13. 1-13

SL2-FSAR Gran Pro'erc General 'Aana er

. nccion, Responsibilities. and Authority:

Assx cs the Project General Hanager in direct'ing and coordi~ acing the c'mely performance by all departments involved in the completion of a n lear power plant within a'designated time span a d within the app ved budget limitations and all technical speci ications.

Aids in dec'sions and activities relating to design, ermitting, purchasing, icensing, construction and start-up of @he n'uclear plant project ssigned to him. As assigned, establishes schedules for and monitor each .of the"activities oE'the departments and groups so as to hieve the objectives relating t quality, cost and operating date of the project.

gals'o participates in dministering the project planning system through which all area relative to the const uction of .the nuclear plant is planned and sc eduled from authoriz tion to commercial.

operation.

He must be cognizant o all deviations Er m established objectives in construction of the nucle r power pla t, initiate action to correct the deviation and the 'steps nec ssary to prevent the occur-rence of subsequent deviations, resolv conflicts between all parties at the construction sit and he various departments of the Company; review actual and potent al problem areas on a continuing basis so as to identify, isolate a arrive at the best method of problem solucion; keep the PGi~l adv ed of progress and of devia-tions from schedules <<.nd budgets'n coordinate activities between construction Eorces and all oth r depa tments to insure a smooth transition of "the completed pr ject to he commercial operation of the plant.

B ~ Education:

BS in Aerospace Technol gy, 1969, Kent State nivexsity Worked as co-op Eor Ford Rotor Company as a Quality Cont I. Engineer.

C ~

'Nuclear 4 February, 1979 to present, Assistant Project General Na ager on St Lucia Uni 1 Backfic and Betterment. Joined FPSL in. 'g7'3 as Back.'it Con truce ion Supervisor for Turkey Point Backfic. +Before his prese . appoincmenc held Area Construction Supervisor and Project onscrucc ion Supervisor position at PTP. From 1971 tb 1973, s an Installation Service Engineer Eor General Electric in T bine Generator Erection area for both fossil and nuclear uni s.

13. 1-14

SL2-FSAR W. B. Lee Director of Construction Education: B.S. General Engineering and Physics, Univ. of Richmond, 1948.

Work Experience Mr. Lee hhs more than 30 years experience in engineering and construction for fossil and nuclear plants. He has spent the last 25 years in the nuciear electric generation area from engineering and design to project and construction'anagement; involved in over 30 nuclear fueled elec-tric generation plants world wide. He served in the United States Navy in "orld War II and the Korean conflict.

In 1953 he joined Bettis Atomic Power Laboratory where he worked on the prototype of the USS NAUTILUS and the first commercial atomic plant, at Shipp ngport.

In 1966 he was assigned to the Commercial Atomic Power Divisions and becane Project Hanager for the Carolina Power and Light 800 Megawatt nuclear station turnkey project. From 1966 to 1969 he was assigned as Executive Vice-President and General Manager of WEDCO Corporation, a wholly-owned subsidiary of Westinghouse, established to perform all engineering and construction of the Indian Point nuclear project. In 19 72 he was named Vice President, Facilities Construction for Offshore Power Systems (a joint venture of Westinghouse and Tenneco>. Since March, 1975, he has been with FP&L as Director of Construction.

B. J. Escue Site Mana er, St Lucie Unit 2 Construction EDUCATION Junior College " One semester of Petroleum Engineering (1950> N.E. Junior of L.S.U., Monroe, Louisiana.

College Graduated 1954 from U.S. Herchant Marine Academy, Kings Point, N.Y. (B.S.).

r1ISCELLANEOUS U.S. Coast Guard License as Third Asst. Engineer (Diesel & Steam>, Active.

Class I Contractor License for Monroe County, Florida. 1966 - 1968.

n ~

Allowed to expire.

SU+MARY OR UALIFICATIONS Mar. 1976 - Present Site Manager, St. Lucie Plant Unit 2 Responsible for construction.

13. 1-15

SL2-FSAR Oct. 1972 - Mar. 1976 Project Manager of Construction in Facilities Construction Dept, responsible for all Platens and Waterfront Construction. This includes engineering, budgets and construction and ascertaining that the Construction Manager was following his contractual responsibilities.

Feb. 1971 - Oct. 1972 Site Manager for W NES of two 4"loop reactor sites (2 plants on each site>. This work consisted of maintaining a staffed office of experienced engineers to provide technical assistance to the customer in all phases from the receipt and warehousing of equipment through.

installation and test.

June 1968 - Feb. 1971 Manager of Construction of the Carolina Power &

Light Co. Three-Loop Nuclear Plant (Robinson Plant), responsible for a staff of engineering specialists, Q.A. engineers, civil; cost and scheduling personnel.

A r. 1967 - June 1968 Construction Superintendent for W NTD to field erect water distillation plant for U.S. Steel at Clairton, Pa. Supervised all of the work pertaining to assembling the Flash Evaporator and setting all major equipment with mill-wrights ~

Ma 1966-A ril 1967 Construction Superintendent for W 11TD to field erect world's largest Desalt Plant (Single Unit 2.62 MGD) at Key West, Florida for Florida Keys Aqueduct Commission.

Jul 1965-Ma 1966 Bettis Atomic Power Laboratory, Pittsburgh, Pa.

Cognizant Engineer for PWR-2 omega seal welding machine which is used to perform all omega seals on reactor vessel head automatically.

Jul 1961-June 1965 Bettis Resident Engineer's Office Shippingport Atomic Power Station PWR Project (Pressurized Water Reactor>

Shippingport (Beaver County>, Pa.

Mechanical Engineer.

Dec. 1958-June 1961 Bettis Resident Engineer's Office for construc-tion of U.S.S. Enterprise, Newport News Ship-yard and Drydock Co., Newport News, Virginia.

Mechanical Engineer.

13. 1-16

SL2-FSAR March 1957-Nov. 1958 A-1-W Project, Naval Reactors Facility, Idaho Falls, Idaho (Prototype of U.S.S. Enterprise).

Hired as Chief Operator Trainee for A-1-W and underwent operational training at S-1-W (Operational Prototype of U.S.S. Nautilus'1 for a short time prior to entering plant construc-tion group for A-1-W. Job consisted of follow-ing construction, intallation of equipment, and tes'ting as per specifications and 'drawings.

Dec. 1954-Dec. 1956 U.S. Navy J. E. Vessely

, g.l...

B.B.A. " Industrial Engineering & Management, University of Miami - 1952 U S. Army - Marine Engineering 1952-53

~

Manufacturing Management Training Program General Electric Co. - 1953-56 Statistical Quality Control General Electric Co. - 1960 Plastics Engineering General Electric Co. - 1960 Management Courses at University of Florida - 1966"67 Nuclear Power Reactors Georgia Tech 1975 Nuclear Power Reactor Safety - 1fassachusetts Institute of Technology - 1975 Stanford Executive Program-Grad. School of Business, Stanford University 1978

.Professional Engineer in Quality Engineering - State of California 1979 1952 -...1953 ., ~

U.S. Army Marine Engineering - responsible for main power and all general maintenance work 1953 - 1956 General Electric Co. .Manufacturing Management Training Program 1956 " 1962 General Electric Co. Manager, Advanced Manu fac tur ing Engineering new electronic product design fox Atomic'nergy Commission

- 1967 General Electric Co. - Manager, Quality Programs development, implementation, and evaluation of reliability and quality program activities for Apollo/NASA 1967 - 1973 General Electric Co. Manager, Washington, D.C. Program Of fice Program Manager for the following. types of

'programs: Quality and Reliability, Configuration Control, Data Management, Information Systems 1973 - 1974 FP&L - Senior Quality Assurance Engineer - System Develop-

'ent " Assistant l~')'962 System

'1974 1975 FP&L Manager of Quality Assurance Development 1975 - 1978 FP&L Manager of Quality Assurance 1978-Present > "l'~ FP&L - Director of Quali'ty Assurance

/ ~ f> /'r iy r~ + I); rrc<i.r O> i ~u<C<< rf l-8 H Member of: P Il C

0 American Society of Mechanical Engineers Committee on Quality Assurance !Governing Body for ANSI Standards>

~ i

'Chai alsaBA 1978 C 1981 K

SL2-FSAR haft Subcommittee on Personnel Qualifications H45. 2. 23 Quali ty Assurance 7 ~ <o>

Acr f4arf 2< y'o>>4 yr Per~i<<

r Work Group o ac my r mrna f'rior 6/ iu'q, f' f'&hr q cy f.

American Huc lear Society Amarican Sociaty for Quality Contra~i tt 5 $ rr ~7lrC tyta $

r> f-r Huclear Division Advisory Council /rrra J or r (PV nr= 4ytr CC>6 $>f J Huclear Division - Area 15 Regional Councilor Huclear Division - 1979 Conference Chairman Edison . lectric Institute - Prime Movers Southeastern Electric Exchange Quality Assurance Committee International Atomic Energy Agency (XAEA)

U.S. Represe'ntative fo" Standard on "Quality Assurance for Fuel Cladding Des'gn and Manufacture" Electric Power Research Institute (EPRI)

Rotating Electrical Machinery Task Force Of ri t or ro$ C 'D)3h l. ~Woo) ay W 4=la h,t. < ir$ y ( <f'par V.$ -4 <Pr <i' y" + yt er. 74>I' r r + ~+i P<+Cor /fry /'jf P g~Pggi/r J. William Brown Hang er, Qualit Assurance, A lications B.S., Industrial Management - Auburn University - 1954 Manufacturing Training Program - General Electric Co. - 1959 Professional Business Hanagement 1966

,1950"1952 U.S. Steel Co. - Co-op Student 1955-1957 United States Air Force Research & Development Command, 1st Lt.

1957-1974 General Electric Co.

Manager, Inventory Control Manager, Purchasing Reliability Engineer Senior Quality Assurance Analyst

) 9 74-19 75 FP&L Senior Quality Assurance Engineer, Procurement Group 19 75-1979 Assistant Manager of Quality Assurance, .Systems 1979"Present Manager, Quality Assurance, Applications Nelnber Aiaerican Society for Quality Control (ASQC)

Qua1iiications:

Certified Principa1 Auditor - June, 1975 Professional Engineer, QA " 1978

SL2-FSAR It Theodore Essinger Assistant Mana er of. Qualit Assurance,. Desi n E. Stcv qs Institute of Technology 1953 H.B.A. Hanaghpent, Xavier University 1962 Hanufacturing ~ raining Program, General Electric Co,. - 19' Reliability Eng'neering, Genexal Electric Co. - 1962

!1953-1956 ited States Air Force-Pilot and/Ground Safety Officer 1957-1963 Ge eral Electric Co. Hanagergfarge Jet Engine Test 1963-1966 We's inghouse Electric Corp. -~Manager, Quality Assuxance, Atomic Equipment Division ( 6mmercial and Navy Nuclear 1966-1968 1968-1972

'oledo 'Progra )

Control 6gta cale Co. = Manas, r, Quality Control Corp. )yf nager Quality Assurance, Military Systems Division (Poyeidon Submarine and F14 Phoenix Programs) 19 72-19 73 Hazeltine Corp,. -director, Quality Assurance 1973"1975 FP6L Assistant~Hanager of Quality Assurance - Procurement 1975-Present FPhL Assistant .anager of Quality Assurance Design Hember of:

I Anerican Society for Qual'y Control (Senior Member, Chairman of Local 'Chap er)

Anerican Society of I mechanical Engineers Edison Electric I titute Chairman of De ign Sub-Committee of Quality As urance Tas)'orce Qualification Professio 1 Engineer, 8QU2627 Certifie Principal Auditor, June, 1975 Certified Quality Engineer, 81873-1969 t

Alan E. Siebe Assistant Mana er of Qualit Assurance S stems BS, U.S. Naval Academy, Annapolis, HD, 1965 HBA, Universi ty of Miami, 1978 U.S. Naval Nuclear Power School and Nuclear Prototype, 1966 U.S. Naval Submarine School, 1967

!'ommissionedAssigned 1965 "1973

\ SSBN658:

Officer, U.S.

as Reactox Navy', USS Hariano G. Vallejo Control Officer, Electrical Officer, Hain Propulsion Assistant> Radiological Contxols Officer and Cotmnunicator. Commander Submax'ine Floti)la Assigned Assistant Operations Officer I

Seven:

USS Lafayette SSB."I616: Assigned as Engineer Officer.

Responsible for nuclear pow"r plant operations, maintcn-

. ancc and overhaul.

SL2-FSAR 1973-1974, FNL: Quality Assurance Department, Quality Assurance Engineer. Responsible for management audits of nuclear power plants and supporting departments.'PSL:

1974-1975 Licensing Department, Sr'. Licensing Engineer.

Responsible for preparation and review of nuclear plant licensing documents and for licensing hearing prepara-tions.

1975-1979 FP6L: Quality Assurance Department, Assistant Manager Quality Assurance for Operating Plants.

'f

'qgo 19 79-B.r-eeent FP&L: Quality Assurance Department, Assistant Manager of,Quality Assurance - Systems.'

/reer (

rgb P/'<I-: Q~ II'/y ~jgur - ~ Oi~, rl'~-i J'~o Member of: h>uri ~ ~ c 1

4 American'uclear Society Southeastern Electric Exchange QA Committee (Committee Chairman>

N45.2.6 Pork Group for ANSI Standard on Qualifications of Inspection, Examination and Testing Personnel for Nuclear Facilities Anerican Society for Quality Control, Energy Division Registration: .

Registered Professional Engineer (State of Cali,fornia)

H. T. adeem s Ass'istÃnt Mana er of Qualit Assurance for Construction B. S. Electrical Engineering Vanderbilt University 1949 Graduate study. in Engineering Management University of South. Florida 1951-1957 Western Electric/Bell Telephone Labs Test Planning Engineer 19 57-1968 General Electric Co. Neutron Devices Department Manager Test Equipment Engineering 19 68-19 71 General Electric Co., Nuclear Instrumentation Department Manager of Quality Assurance 19 72-19 73 J. A. Jones Construction Co. Corporate Manager of Quality Assurance 19 73-19 75 Motorola, Commdnications Division Manager of Quality

.Assurance .

'19 75-19 75 Project Management Corp. Manager Quality Engineering 6 Improvement

. 1975-Present FPGL Assistant Manager of Quality Assurance for Construc-tion E

Hmnber of: I N

. National Society of Professional Fngineers Florida Engineering Soci'ety Anerican Society for Qua)ity Control Institute of Electrical and Electronics Engineers

13. 1-20

SL2-FSAR Amer'ican Nuclear Society Qualification:

Registered Engineer - Florida 8875) h Rober t F. Eng lmeier Ass stant Mana er of Qualit Assurance Procurement 0 %'>>>~i~g BS:IE Virginia Polytechnic Institute .-'955 Manufacturing Training Program, General Electric Company - 1962

.".anufacturing Problems Analysis Course, Gener'al Electric Company 1966 Business Administration, International Correspondence School 1972 Nuclear Power Reactor Safety, Georgia Tech - 1977

'~~~~~~6p ~k ~i>~.-

1955-1958 United States Air Force Pilot and Communications Officer 1958-1960 General Elec tric Company Manufacturing Engineer 1950"1962 General Electric Company Manufacturing Training Program 1952-1966 General Electric Company Producibility Engineer 19 66-19 71 General Electric Company Unit Manager, Shop Operations 19 71-1974 General Electric Company Manager Shop Operations 1974-1975 FP&L Senior Quality Assurance Engineer 1975"Present FPGL Assistant Manager of Quality'Assurance Procurement 4~6'< ~

Heinber of:

" American'Society of Quali ty Control American Society of Qua lity Control (Energy Division Secretary 1976-77)

American Society of Quality Control (Energy Division Secretary 1978-79)

American Society of Quality Control (Energy Division Vice-Chairman 1978"79)

Coordinating Agency for Supplier Evaluation (Chairman Nuclear Section)

Atomic Industrial Forum Qual i ficat ions:

Lead Auditor June 12, 1975 Certified Professional Engineer of California QU 3653 l3. 1-21

VI+>> VU>> ) VV

4) K )laxett B.S. hlcchanical Engineering; University of hfissouri at Rolla, 1970.

Hastcrs in Business Administration, 'Florida Xntcxnational Univaxsity, 1975 Nuclc,ar Pot~ex Engineering Progxam, 650 hour0.00752 days <br />0.181 hours <br />0.00107 weeks <br />2.47325e-4 months <br /> FPL Program, 1976 Amexi.can hlanagement Association, Seminar for New or Prospective Hanagexs, 1974 Officer Commission Course, United States Army Reserve, 1972, commissioned 1st Lieut(

Hanagerial Grid Xnstructor, 1974 Present Kepner-Trego. Effective Leadership Behavior Xnstructor, 1977 Present Apprentice Training Xnstructox. for Plant Electricians and Hachanics, 1971 1973 First Aid and Cazdio Pulmonary Resuscitation Xnstructor, 1976 Present Nucleax Power, Reactor Safety Course, Hassachusatts Xnstitute of Technology, 80 hrs, Registered Professional Engineer, 1969 hlis ouri Pacific Railzoad, Co-op Engineer 1978'965 1966 - 1970 Part Time, University of Hissouri, llachinist; Q 1970 Hilltop FPL Plant Cab, hlechanic; Herman Lumber Company, Yardman Test Engineer testing of fossil power planning and supervision, gas turbine plant'quipment,'aintenance construction inspection 1971 1972 FPL Plant Supexvisoz responsible fox" maintenance, planning and supervision for 2 fossil and 12 gas turbine uni'ts 1972 1973 FPL hfanagament Services Analyst, participated in the development and implementation of tha powex plant Work Order & Planning Hanagemant Analyst, participated in the davelopm..nt and imp-,

Systc)'PL 1973 mentation of the system fuel economy and outage scheduling 1974 FPL Construction 'Analyst responsible foz developing and imple" progxa'973 r>>tenting the FPL construction aquipmant, manpower and construction planning systems 1974 - 1976 FPL Construction Coordinator - responsible for supervising contractor activities on various nuclear con truction projects, and maintenance work 'during refuelings. Represented FPL in the development of the planning, cost and schedule systems fox the St. Lucia Nuclear Plant 1976 1978 FPL Senior Ouality Assurance .Engineer, System Davelopment-responsible for development and revision of the QA hlanual, Topica.'.

Organization Hanual, PSL SAR, Fossil QA Program, and serving as t i

'PQAE for the Hartin, hlanatee and Turkey Point projects 1978 1980 Project Supaxvisox) responsible for the supervision of 'the Projee QA Engineers fox the.-Turkey Point and Tx'ansmission & Distxibutiou axeas; saxved as the PQAE for the lfaxtin Plant, the JEA Coal Proj>>

and the St. Lucia Nuclear Plants 1980-Present Assi.'stant Hanager for QA Engineering & Naw Projects,'esponsible for supervision of PQAE's assigned to new projects, T&D; and QA services pxovided to other. departments. Represents the QA Depart-..'.

with other depaztmants requesting QA support services, and respon; for obtaining and coordinating QA Department project input for de>>

opmant of the Project Quality Plans and presentation of status re;,

to department management.

Hcmber of:

Am rican Society of Hachanical Engineers Florida Engincezing Society National Society of Professional I:ngineef:s National Society for. Quality Control American Nuclear Society

James B. Harper OCTOBER 1980 h* '.~-" ..'<<:-

B.S. Indust:ria3: Engineering, University of. Sout:h Floxida, Tampa, FL - 1971 t

Haste>> of Business Administratio, Floxida International University, Miami, 1'L - 1977

\

Management Development Sales Analysis Institute 1972 Management by Objectives FPL Grid Bla'ke & Houton 1974 1974'anagerial Financial Seminar FPL 1974

'!anaging Management Time Oncker Associate 1975 Effective Reading FPL 1975 Cost Benefit Analysis Seminar - K & G Associates .1975 Nucleax'oMex Engineering Program FPL 1976 Nuclear Fuel Qua3.ity Assurance Seminar 1976

, Quality Assurance Auditox Course Bechtel 1976 Virtual Memory Operating System Part 1 FPL 1977 Genco Kepner Tregoe 1976 Telos Kepner Tregoe . 1978 Quality Assurance in Procuxement General Atomic - 1978 Virtual Hemory Operating System Part 2 FPL 1979 Non-Destructive Examination Lic!uid Penetrant, Hagnetic Paxtic63;,

Radiography - FPL - 19/9

.daxcductiOn

.../ /" <<< /"/~

'to / Coal Power. Generation

/'iJ C '"<.'bg,/'/g <e ic'i'/'~J ~

/ /ti'/

C.E. 1979 hoxk Experience 1967 1971 IBM Corporation, Space Systems Center, Co-op Student 1971 1973 FPL Consumer Service Department {various) 3.973 1975 FPL Consumer Service Supexvisor, Miami Beach District 1976 1977 FPL Senior Quality Assurance Engineex, Design 1977 1979 FPL Senior Quality Assurance Engineer., Procurement 1979 1980 FPL Supervising Engineer, Quality Assurance Procurement 1980 Present FPL '- Assistant Manager - Quality Assurance Systems

• Audits Member e of:

"-.." American Society for Quality Control (ASQC)

Association of HBA Executives (AHBA}

f'<:!,JIc/;.fi i'~//-6//<t>> (iii- E'i~<~pg /);L<,/, <,"n - AS4C'/'/Sl

)".><<J <~'i'".~ S<'< '/i /$ '/t: g <<<> (

Yualitifications: <'<>

I /O'x<

Cer t i fied Principal Auditor Haxch, 1977 fh ~)

w/ /

SL2-PSAR M. }l. Rogers, Jr.

Chief En ineer - Power Planta A. Function, Responsibilities and Authority 1

Responsible for recting Power Plant Engineering Depaztment to ensure design o&efficient, economical and reliable power plants meet 'Company's requirements for power generation. 'Ihis includes changes to existing units as well as instaLlation of new units.

Responsibilities include establishing and implementin'g design criteria, meeting codes and regulations, formulating and implement-ing engineering policics, practices and problems, resolving engineering problems, establishing equi.pment, technical specifica-tions and equipment acceptance, and all similar engineering func tions. A.~expansible ~ha-Nuebw. h~r" in A~~~xxn~tfe The MITER-Pux. ~

fN eutr~iw~Nuakear PUF~nagement Sa Chief Engineex-Power Plants has authority for administration

a. tmen and technical guidance of the Power Plant Engineering and Nuclear Analysis Departments. He is a Registered Professional Engineer.

Ed ucational Background BSHE Rensselaer Polytechnic Institute Graduate courses,eat Transfer, Brooklyn Po'lytechnic Institute Masti.nghouse, Nuclear,Power Fuel Management, NUS Seminax'uclear

         }tuc leer Power               Reactor, University of Fl.orida Radiological Health, PHS P~actor Safety 6 }}asards Evaluation, PHS Advanced Nuclear Technology, University of Florida Nucle r Power Reactor Safety, Massachusetts 'Institute of Technology.

Experience (1) Nuc Lear D sign and construction of Turkey Point Nuclear Units 3 arid 4 and St. Lucie Nuclear Units 1 and 2.

                                    ~

Cr ept

                                  -                                                    /I (2)    Other                 For five yeazs irked for Foster Mheelez Research and Development in steam generation equipment.                     For 27 years worked for FP6L on design and construction of nuclear and oil fired power            plants   and gas   tuzbine units.

of PK years in engineering areas, 9y'otal rrlated to the electric

        ,ut i Li ty o

13. 1-22

0 SL2-F SAR E H Oiheal Assistant Chief En ineer - Power Plants A. Function, Responsibilities and Authority Responsible for directing and coordinating Power Plant Engineering Department efforts in project related areas.. Handles the depart-mental functions and affairs in the absenc'e of the Chief Engineer. Directs engineering Project Managers to ensure the design of ef-ficient, economical and reliable power plants to mret the Company's requirements- for power generation. Other functions parallel those of .the Chief Engineer. He is a Registered Professional Engineer. B. Educational Background BSHE University of, Florida Graduate courses conducted by University of Florida "in Elements of,Vibration, Nuclear Engineering, Advanced Nuclear 'Zechnology and Nuclear Power Reactors ..

 . ~

C. Experience a (l) Nuclear - Engineering Project Management for St. Lucie Units 1 and 2 for seven years prior to'eing promoted to Assistant Chief Engineer. (2) Other Worked for General Electric Co. for l 1/2 years on jet

                        'ngines       and. steam    turbines. For 29 years worked for FP6L on design and         construction of nuclear and oil fired power plants.
                                        '3~

Total of utzlLtye

                                       ~ years      in engineering areas related to the electric L. F. Pabst
     ~Mana   er Plant       -  Hechanicai       C, Nua)ear En~inearin A.         Function,Responsibilities                and  Authority Responsible to direct and coordinate Mechani'cal/Nuclear power Plant Engineering design to optimize cost, availability, maintainability,
               ,ef ficiency and operability. The principle accountabilities are as   fo l l ows  '-
              '1)        Organize and manage Plant Mechanical/Nuclear Engineering and l
                      ~

select, develop and evaluate the'echanical/nuclrar personnel r to ensure that technical and project competence meet the mechanical/nuc1 ear engineering design objectives. (2) Coordinate "nd direct Plant Mechanical/Nuclear Engineering

                      'n      establishing design criteria and in providing the
     .*,   .   ",  . expertise for decision making in the areas of plant: systemi, for nrw power plants to ensure thr design optimizds cost, availability, maintainability, efficiency            and operability.

a

13. 1-23

SL2-FSAR (3) Train, coordinate and .direct Plant Mechanical/Nuclear Engineering personnel in the efficient technical performance of procurement activities such as vendor technical qualifica-tion, specifications, bid reviews, change control, acceptance activities, etc. (4). Direct mechanical/nuclear engineering personnel in ensuring mechanical/nuclear designs comply with local, state and federal codes, rules and regulations. (5) Coordinate and direct personnel in the evaluation and authorization of architect-engineer activities; provide FP6L direction of courses of action and eValuation of the technical and cost aspects of scope changes; and evaluate and implement as required inputs from Power Resources, Nucl ear and General Engineering, Construction and others within FP6L. (6) Direct the preparation of FPGL Power Plant Standards for the purpose of standardizing documentation, design, construction practices, storage of equipment and testing. (7) Direct mechanical/nuclear personnel in providing technical assistance to operatj.ng power plants for design modifications, tests, or problem solving . B. Ed uc a C iona 1 Background a BSME University of F1orida Graduate courses conducted by the University of Florida in 1'ndoctrination to Nuclear Engineering, Nuclear Engineering Laboratory, and Advanced Nuclear Technology. Completed West inghouse Reactor Training Program and qualified on the Saxton Reactor. Trained at Turkey Point as student and instructor and qualified for Senior Reactor Operator License on Turkey Point Nuclear Units. C. Exper ienc e-Nuc 1 ear Worked in nuclear related work at FP&L for 13 years in the operating and engineering departments. Worked for eight years for FPGL in start-up, testing and special projects on modern fossil fuel generating units. Total of 21 years in engineering areas related to the electric utility. D. M. Van Tasse11, Jr. ~Mana er " Plant Elertriral En ineerin A. Function, Responsibilities, and Authority lhe basic function of the Manager Electrical Engineering is to direct and coordinate electrical power plant engineering

13. 1-24

SL2-FSAR design to optimize cost, availability, maintainability, efficiency, and operability. Tne principle responsibilities of this position are: (1) Organize and manage Pl'ant Electrical Engineering and select, develop and evaluate the electrical personnel .to ensure that technical and project competence meet the electrical engineering design obj ectives. (2) Coordinate and direct Plant Electr'ical Engineering in

   .. establishing    design criteria and in providing the expertise for electrical decision making in the areas of auxiliary power systems, controls and instrumentation for new power plants to ensure the design optimizes cost, availability,'aintain-ability, efficiency,       and  operability.

(3) Train, coordinate and direct Plant Electrical Engineering personnel in the ef f icient technical performance of procurement activities such as vendor technical qualification,. specifica-tions, bid reviews, change control, acceptance activities, etc; Direct electrical engineering personnel in ensuring electrical designs comply with local, state and federal codes, rules and regulations. (5) Coordinates and direct personnel in the evaluation and author-ization of architect-engineer activities. Provide FPhL direction and courses of action and evaluation of the technical and cost aspects of scope changes, and evaluate and implement as required inputs from Power Resources, Nuclear and General Engineering, Construction and others within FPGL. (b) Direct the preparation of FPEL Power Plant Standards for the purpose of standardizing documentation design, construction practices, storage of equipment 'and testing. (7) Direct electrical personnel in providing technical assistance to operating power plants for design modifications, tests or pr oh 1 ~ solv ing . 0 Educational Background J Received a Bachelor of Sc ience. in the Power Option of Electrical Engineering from Drexel University in 1962. Continued education by completing successfully a Rectifier Circuit Theory'ourse, an Electronic Course, a Review 1/athematics Course for Engineers, a Material Applications Course for Engineers and a High Volt ge D'electric Behavior Course while with the General Electric Company. A'.so completed successfully the power System Analysis Course at FPoL. p, jp~ $ $ g< o I

13. 1-25

SL2-F SAR Experience (1) Nuclear (a) Directly related Upon joining FP&L in April, 1971, until November, 1973 was directly responsible for the electrical design review of FP&L Nuclear Generating facilities under construction. From November, 1973 to the present:has been responsible for the supervision of all electrical worl." and design review performed on all FP&L power plants both nucl.ear and fossil. (b) Other During the time he was with General Electric's relay department worked on several jobs associated with nuclear power. (2) Other From 1950 through a portion of 1967 was employed by the General Electric Company; during this period a series of positions of increasing responsibility were held. Served as a tester of AK circuit breakers; requisition engineer for control switches, indicating lamps and wiring devices; requisition enginner for protective relays; requisition engineer for power rectifier equipment; design engineer for type AKD load center equipment; and magnetic design engineer for the relay department. From 1967 through a portion of 1969, was employed by the Electromagnetic Compatibility Branch of ITT Federal Electric Company at NASA - Kennedy Space Center. Was employed as an engineer and served for one year as Branch Chief . 1969 to early 1971 was employed by the Electric O'rom Util ities Branch of Trans World Airlines at NASA-Kennedy Space Center. Has first employed as a System

   . Engineer on the NASA Power System and served the, last year as supervisor of engineering responsible for auxiliary systems consisting of standby diesel generators, protective relays, the supervisory control system and fault and t rans ient recorders.

Total of 25 years in engineering.

13. 1- 26

SL2-FSAR . i H. H. Jabali ad (p S. ervis~ - Plant Civil En ineerin Function, Responsibilities and Authority Supervise and manage the Civil engineering section within Power Plant Engineering D pt. Direct civil engineering personnel in preparing design modifications and additions at operating power plants and in providing technical assistance in the civil areas to,.other FP&L departments. Establish scope and design criteria of power plants in the civil, structural and architectural areas and directs the engineering activities of the architects engineers and consultants to ensure implementatio'n thereof. Ed uc at iona 1 Background BSCE, 1968, University of Miami HSCE, 1970, University of Miami Major: 'Structures Minor: Applied Mathematics MS Theoretical & App1ied Mechanics, 1971, northwestern University Major: Solid Hechanics C. Experi ence (1) Nuc lear Worked for Sargent & Lundy Engineers in structural design

                      - - wo'rk for nuclear plants for five years. Worked for FP&L in civil design areas and Supervisor, Civil Engineering for three years.

(2) a Worked in structural research and development areas for three years in Academic Teaching & Research area a Total of eight years in engineering areas related to the 1 electric utility. F. G. F 1 ug ger A. Function, Responsibil ity and Authority: s Raspo'nsible for ensuring that nuclear plant designs are in compliance with NRC regu)at ions. R~~M ~or nq;u+atory da!J.gn tantara~~sar pi~st-dnsidn.mnd 'or-nodidioatlons-to-rdtintdnt-nnn tndr~panta dd ~d~oyddP gW- 'v4 ~ I"../ f: A '.i r f ~PC f'tra' rr n I Clor~~..6' Responsible for development and implementation of the Power Plant Engineering Depar tment's QA Progr ~. Approualmk-design-in arenas involv.ing-t<RC-~urrisd-i~Hvrt. C r r sr

SL2-F SAR Eddcational

Background:

Bachelor of Marine Engineering MS in Engineering Science- (AEC Fellow) Graduate work beyond MS, 42 credits MIT Reactor Safety Course NUS Advance Nuclear Fuel Management Course C. Experience-Nuclear 1 (a) Directly related

                    ~

Worked for six years with Consolid.ated Edison Company )n nuclear engineering and management areas.,Worked 'for two

                       . years       on nuclear projects for Long Xsland Lighting. Worked for NUS Corporation for l-l/2 years in nuclear areas. Worked on nuclear plants in engineering and design for FP6L for cia           gr/

years. This'is a total of P6" years in nuclear related work.

                           ><>~) 'i C~~~~ +>'~f~ J       k>~~~ (mm 7i~W eai gi,g/t'y v ~W I/)p 8'>>><4.~ye. (I)'e~>

(b) Other Worked for two years 'in other work related to utilities. Pf years utility experieuce.

                             ~g'otal J. R. Tomonto Mana,er       - Nuclear          Anal sis   ~

A.~ ~ - - Function, Responsibility and Authority: Responsible in providing direction of the Nuclear Analysxs Department in the following areas: Technical assessments of nuclear, fuel designs, nuclear plant safety systems and

               'preparation of reload licensing reports. Functional reviews of vendor supplied nuclear physics, thermal, hydraulic and safety designs of nuclear cores. to ensure that they meet operational, regulatory and quality assurance recuirements.

Perform safety analyses to support plant operation and recommend procedures to meet established criteria. Perform analyses of reload nuclear fuel designs to ensure, that all parameters are within es tao l ished 'imits. Develop procedures and methods used to verify that nuclear plant power dis-tributions are within technical specification limit's. Assist and augment nuclear plant Reactor Engineering staff" during refueling, start-ups and spec$ .al test evaluations. Authority i,s in the administration and technical guidance of the Nuclear AnaIysis Department. e r B. Educationa) Background e BS,in physics, Villanova University, 1954 HS in Reactor Physics, Rensselaer Polytechnic institute, 1959. ee

13. 1- 28

SL2-F SAR Advanced Reactor Engineering Progrmn conducted by the Knolls Atomic Power Laboratory, 1960 "62. Engineer ing Management Ski 1 1 s Course, 1969. Doctoral Student in Nuclear Engineering, H.Y. University, 1967 to 1970. Gulf Corporation Management Training Program, 1973, Experience (1) Nuclear Manager, Nuc lear Analysis Department, FPSL, Miami, Florida, March, 1974 to present. Manager, Nuclear Engineering Department Gulf United Nuclear Fuels Corporation, Research and Engineering Division, Elms ford, N.Y., January, 1970 to March, 1974. Manager, Nuc lear Development Section, United Nuclear Corporation, Elmsford, N.Y, March, 1964 to January, 1970. Nuclear Physicist, Knolla Atomic Power Laboratory, Schenectady, N.Y., November 1959 to March, 1964.

     . Nuclear Engineer, Alco Products, Inc., Nuclear Power Engineering Division, Schenectady, N.Y., June, 1958 to Nov emb er, 1959.

(2) Other Electrical Engineer, Airborne Instrument Laboratory, Modoe Division, Thornwood, N.Y., June, 1957 to September, 1957. Chief Engineer, DD775, U. S. Navy, Norfolk, Va., June, 1954 to June, 1957.

13. 1-29

                 ,  Pro jeer Mana er8-Function, Responsibilities, 1'rvs SL2-FSAR St-Lucan-Huclea~nits-1-and~

and Authority

                                                                              /~s    r Responsibilities for coordinating Power Plant Engineer dr sign/

review activities. Responsible. for engineering budgets and schedules. Responsible for directing the architrct-engineer and NSSS vendors. b)'- 'uc at ional Background BS Chemistry -'lorida Southern College Nuclear Engineering, University of Florida c) Experience

1) Nuclear ~ t<<

Worked in design and project engineering relaLed areas for ppaL in nuclear plane related assignments fcrpifyaars.

                                                                            /2.

2) 'ther Two years lg Total of Pg years utility experirncee ~

s Dr. Robert "". Uhrig

        ~

Vice President Advanced S 'stems and Technolo B.S, (with honors) Mechanical Engineering, University of Illinois 1941 M.S. Theo. and Applied Mechanics, Iowa State University 1950 Ph.D. Theo. and Applied Mechanics, Iowa State University 1954

     ]94S - 1951     Iowa State r

University Teaching Staff 1951 1952 Institute for Atomic Research, Iowa State University, Resr arch Asst. 1952 - 1954 Institute for Atomic Rrsearch, Iowa StaLe University, Graduate Asst. 1954 1955 Department of Mechanics, U. S. Military Academy, West Point (on active duty with U. S. Air Force) 1956 1960 Institute for Atomic Research, Iowa State University Associate Professor of Theoretical and Applied Mechanics and h'uclear Engineering,. Nuclr ar Reactor Supervisor, Group of Nuclear Engineering, Group III 'eader 1960 - 1967 University of Florida, Professor and Chairman, Department of Nuclear Enginr ering Sciences 1967'- 1968 Department of Defensr " Deputy Assistant, Director for Research (on leave of absence from University of Florida~ 1968 - 1973 University of Florida, Dean, Collr gc of Engineering and Directo., Engineering and Industrial Exprrirn@nts Station

13. 1- 30

'I V Function, Responsibilities, and Authority Responsibilities for coordinating Power Plant Engineer d(sign/ review activities. Responsible for engineering budgets and schedules. Responsible for directing the architect engineer and HSSS vendors.

                                                               ~ * ~

I

0 SL2-FSAR I 1973 Present FPc L - Vice President - Advanced Systems and Technology Registered Professional Engineer - Florida and Iowa States i')ember of: A .erican Socinty for Engineering Education American Huc) ea r Society P~erican Society of Mechanical Engineers Hational Society of Professional Engineers P~erican Association for Advancement of Sciences American Institute for Aeronautics and Astronautics Florida Engineering Society

0. . Pearson, III Direc r, Licensin and Environmental Plannin De a tmp ~ t Educ a t i on: C qrgc town University Law Center Juris Dp tor Corh 11 University - Master of Engineeriyg (Huclear)

Come University - Bachelor of Engineering Physics Harvard niversity - Completed a program for Management

                                              ~ Development Fxperience          1966-1972:        R   actor Engineer    g Branch Head    in the Division of       Hav     Reactors 1972-1973:        Executi e Assistant to .Vice President
                --Power Plant Engineerihg and Construction.

1973-1975: Exing tive Assx tant to Vice President Strategic Plea <king, FP6L. 1976 - Pre ent: Director of Li n ing and Fnviron-mental Ianning, FPAL. Member of: Amer can Bar A'ssociation D~dtrict of Columbia Bar he Florida Bar AIF Steering Committee on Licensing and Safe AZF Environmental Committee American Huc lear Energy Council J. A. DeMastry Mana.er, Huclr::r Licensin, Educ at'.on' Ohio State University " Graduate School Metallurgical Engineering One Year Ohio State Univ'sity - B.Sc. 1953 Experience: 197'~ - Present: hesi-stant Manager, Huclear Licensing To plan, coordinate and direct overall company lies nsing program in order to obtain and maintain the various nuclear

SL2-FSAR regulatory licen es and approvals necessary for nuclear power plant siting, construction and opr ration. General . Experience: Twenty-three years experience in riuclear licensing, engender-ing management, reactor plant design, nuclear fuel develop-ment., nuc.lear marketing, nuclear safety, genrral nuclear technology and quality assurance. Experience in preparing

                  'lant      licensing documents. Last 10 years experience has been at various levels of engineering management such as nuclear applications. 'pecific experience in design of reactor con-tainment. Experienced. in developing 'materials and components for use in nuclear reactors. Active in studying liquid metals and their interactions with materials and components.               Exper-
                 " ience in fracture mechanics studies of metals and ceramics, welding and effect of welds on materials properties. Adminis-tered mechanical properties laboratories concerned wi th study-ing the effects of environmental such as temperature, radia-tion, vacu'um, etc. on materials and components.. Author and/or coauthor of more than'0 technical papers and in access of 50 t echnical r e p ort s . Active in P rofessional societies.

Aug t L. Heil Assist t <1ana er for Neutronics and ruel mana ement BS, Mrtallur and Materials Science, Carnegie Hr lion University 1950 1968 Supervisor, Core Manufacturing, Vlestinghouse Bettis Laboratory; fabrication of reactor fuel a d core cornponr nts for the Navalgldclr ar Program inc ding Shippingport. Development of new fabri tion processes and pr p~aration of in-pilr fuel tes samples. 1968 - 1970 Supervisory inee , Nuclear Materials and Equipment Corporation', pr c ss engineering responsibility for the, fabricatio o the portable military type reactor cores and qyEificat n fuel assemblies for commer-cial rrac .6rs.

  '1970   -  1974               Projp t Manager, westinghouse 'uclear Fuel Division; pr gect management and administr "ion of the comm@r-
                      't ial nuclear fuel contracts in the utheast.
  '1974   -  Present            FPGL, Nuclear Analysis Department Assistant Manager for Neutronics        and Fuel Management a'l       o                  AHS and ASME                                      I C

13. 1-32

SL2-FSAR J. E. Carson H r~~~L-Su 1 DSEE, Duke University, 1949 University of Florida Extension Nuclear Engineering, 1966 HUS Nuclear Fuel Management, '969

  '949 "   1955       City of. Danvil le, Virginia,      Power electrical     power transmission Engineer,'ngineering and distribution 1955  - 1957       FP&L; Senior 'Field 'Engineer; distribution engineering and commercial. service 1957  - 1964       FP&L;  Assistant   Supe  rvisor 'transmission
                                                       ,                             and distribution cohstruction supervision, metering, overhead,  underground,      trouble 1964  - l968       FP&L;  Industrial Relations Supervisor;" labor contract administration and negotiations n; 6      oS-  I= ~l~

1968 Present FP&L; Manages~:Fm 1-Supp~ oil, gas an'd nuclear fuel procurement and contract administration Member of: ANS, IEEE; Federal Power Commission Technical Advisory Committee on Fuels

13. 1-33

OJECT  : ST. LUCXE FSAR DATE PRINTED  : 07/24/81 ATE 07/24/81, TYPIST: Page? n DISKETTE NO. : SD-572 PAGE 1 SL2-FSAR 13.1.2 I OPERATING ORGANIZATION I p ~ s d)vs%~ ~.6 P dto 13.1.2.1 Plant Or anization 04 05 Figure ig.l-g provides a chart showing the title of each position, tha 06 number of operating shift crews, and the positions for .which reactor 07 operator and senior reactor operator licenses are required. Table 08 13.1-1 displays plant staffing changes to the existing St Lucie Unit 1 09 organization to accommodate operation, administration and maintenance 10 of St Lucie Unit 2. These changes follow manpower requirements to support 11 St Lucie Unit 2 and may vary ~joky dependent upon proJec progress and l2 schedule. ' is( ssp.j ash<ps>> kr Isr( sfsdrvfjd I a,Q 5 6r t'swjd pil Q ) r) lr s'p sbds

                            ~    e                ~                       s a                   s         d 13                /d:d. pb<<        /dp. Le 1~

14 13.1.2.2 Plant Personnel Res onsibilities and Authorities 15 l6 The function, responsibilities, and authorities of plant positions are D described below. These positions are indicated on the organizational chart 18 of Figure 13.1-8. 19 20 a) Plant Manager 21

 '22                           -   The Plant Manager reports to the Assistant Manager Power Resources 23                               Nuclear (refer to Figure'3.1-3) and has direct responsibility for and maintaining the plant in a safe, reliable and efficient       'perating manner.        Be is responsible for protection of the plant staff and the 26                                general public from avoidable radiation exposure and/or any other conse'quences of an accident at'he plant. He bears the responsibility 30 for compliance with the facility operating license. He has the authority to take any action necessary, without consultation, to pre" vent or mitigate the consequences of an accident.

31 32 b) Operations Superintendent 33 34 The Operations Superintendent reports to the Plant Manager and acts 35 in his behalf during his absence. He is responsible to the Plant ,'36 Manager for operating and maintaining the plant in a safe, reliable, 37 and efficient manner. Be will asssume the duties and responsibilities 38 of the Plant Manager as the primary alternate to that position. 39 40 c) Operations Supervisor 41 42 The Operations Supervisor has the responsibility for directing the 43 actual day-to-day operation of the unit and holds a Senior 44 Operator License. He reports directly to the Operations Superinten' 45 dent and directs the plant operating staff. He coordinates opera-46 tions related activities with all departmental supervisors. He 47 assumes all of the Operations Superintendent's responsibilities and 48 authority in this absence. He is responsible for overall supervision 49 ~ of fuel handling operations. He has the authority to shut down the 50 unit, initiate the Emergency Plans, and issue standing orders on a 51 'ay"to-day basis. 52 13.1-34 Amendment No. P; (8/81)

OBJECT .: STs LUCIE FSAR DATE PRINTED: 07/22/81 TE 07/20/81, TYPIST: ek Page? n DI SKETTE NOr SD 5 72 PAGE 2 SL2 FSAR d) Plant Sdpervisox'he Plant Supervisor is responsible for the actual opexation of the plant on his assigne'd shiftd He reports to the Operations Supervisor and directs the activities of the operators on his shifts He must be cognizant of all maintenance activities being performed while he is on dutyp The Plant Supervisor on duty has the authority to shut down the unit if, in his opinion, conditions warrant this action. He has the authority to initiate the Emergency Plans and to issue standing oxdexs for operation in conjunction with the Operations Supervisorp During fuel handling opexations he may direct the operation or operate fuel bandlind equipment. Responsibilities are specified by an admin-istrative procedurep s Hatch Engineer The Watch Engineer is the working operating foreman and is responsi-ble for plant operations on this shifts He xeports to the Plant Supervisors Upon assignment he may assume the responsibilities of Plant Supervisor. During fuel handling operations he shall direct or operate fuel handling equipment. He is also the fire 'team leader and maintains proper qualifications for this position. The Watch Engineer on duty has the authority to shut down the unit if in his opinion conditions waxrant this actions He has the authority to initiate the Emex'gency Plans'esponsibilities ara e specified by an administrative procedured Control Center Operator The Control Center Op rator operates controls and monitors instru-- ments located in the contxol room containing reactor, turbine-genera-tor and txansmission line control boards, and under direct or genexal 3 supervision directs the operation of all plant equipment as required 4 to maintain proper opexating conditions'e executes or directs the execution of orders xeceived from the Plant Supervisor, Watch Engi-7 neer, and Dispatcher. He had the authority to shut down the unit in his opinion conditions waxrant this action. During fue handling if operations, he may operate fuel handling equipment under general supervisionp He may'perate radiation survey'nstruments. Respon-0 sibilities are specified by an administrative procedure. l 2 = g Shift Technical Advisox 4 ,>

                            ,The        Shift Technical Advisor provides                                             an independent,          dedicated concern for the safety of the St. Lucie Plant. This is accomplished by pro-
                          ,  viding diagnostic support in an advisory capacity only to Operations 7                             personnel during off-normal events and by advising the Plant Bupervi sor on actions to terminate or mitigate the consequences of such events                                The Shift Technical Advisor is responsible to the Technica 0  I.   = *>
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PROJECT: ST. LDCIE FSAR DATE 'PRINTED: 07/20/81 DATE 07/20/81, TYPIST: ek Page? n DISYZTTE NO.: SD-572 PAGE 3 SL2-FSAR h) Nuclear Operator 0 03 The Nuclear Operator operates nuclear reactor auxiliary equipment 04 and turbine-generator auxiliary equipment under the direction of a 05 licensed operator or senior Operator. He performs inspections of 06 operating equipment and systems including but not limited to the 07 Reactor Coolant System, Chemical and Volume Control System, Com-08 ponent Cooling Water, Shutdown Cooling and Spent Fuel Pool Cooling 09 Systems, Waste Management System, engineering safety features systems 10 and components, radiation detection equipment, containment and radio-ll 12 active area ventilation and purge systems, Primary Water Makeup Sys-tem, refueling water tank, gas supply systems, liquid and gas sampling and analysis equipment, and chemical feed addition equipment. He per-13 14 forms operating adjustments and service's, records operating data, and 15 operates radiation survey instruments. During fuel handling opera-16 tions he may operate fuel handling equipment under the supervision of 17 a licensed operator. He may operate other plant auxiliary equipment 18 ~ under the direction of a Plant Supervisor, Watch Engineer, or Control 19 Center Operator. Responsibilities are specified by an administrative 20 procedure. 21 22 Nuclear Turbine Operator 23 24 The Nuclear Turbine Operator operates turbine controls and serves 25 as turbine-generator attendant. He acts under the direction of a licensed operator or senior operator and may be assigned additional

                         ,duties and assist the Nuclear Operator and performs operating adjust-2                        ments and services and records operating data. He is a member of the 29                        interim fire team and is properly qualified for this position. Re-30                        sponsibilities are specified by an administrative procedure.

31 32 Auxiliary Equipment Operator 33 34 The Auxiliary Equipment Operat'or operates plant auxiliary equipment, 35 such as the water treatment plant and the Intake Cooling Water Sys-36 tem equipment. He may operate other plant auxiliary equipment under 37 the direction of a Plant Supervisor, Nuclear Watch Engineer, or a 38 Control Center Operator. He is a member of the fire team and is pro-39 . perly qualified for this position. Responsibilities are specified 40 by an administrative procedure. 41 42 k) Technical Supervisor 43 . 44 The Technical Supervisor reports to the Plant Manager and is respon-45 sible for supervision of the staff engineers and directs activities 46 concerning technical analysis and advisory services. The Technical 47  : Supervisor is responsible for the operating experience feedback 48 function. 49 50 Reactor Supervisor 51 The keactor Supervisor conducts or supervises tests, accumulates and evaluates data and maintains records of the performance of the plant

                       ~   'including core performance and fuel records. He reports to the dY 13 '-36               Amendment No. $ ,,  (8/81)

I 0

PROJECT: ST. LUCIE FSAR

                     -                                                          DATE PRINTED: 07/24/Bl DATE 07/24/81,   TYPIST:             Page7            c DISKETTE      NO.:       SD-572                  PAGE 4 SL2-FSAR Operations Superintendent.                      He has the responsibility to recommend that the unit be shut down                    if    in his opinion conditions warrant this action and he has the authority to initiate the Emergency Plans.

Health Physics Supervisor The Health Physics Supervisor conducts or supervises surveys and monitoring programs to detect, measure and assess radiation levels within the facility and maintains records and reports to all radia<< tion surveys and monitoring programs. He instructs or assists in the instruction of all personnel in the basic principles of radiation protection. He assists or supervises decontamination operations.

                                                                                                                 'e has the       responsibility to recommend that the'nit be shut down                   if in his opinion conditions warrant this action, and he has the author-ity to initiate the Emergency Plans. The Health Physics Supervisor reports to the Operations Superintendent.                         He also has an authorized direct line of communication to the Power Resources Staff Health Physics Section Supervisor and to the Plant Manager. These lines of communication give him access to upper management to assure that exposures are as low as reasonably achievable.

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                       /  /4 ~ f     y~(~Fg  mv I    /  r      /~<    gg%gc   f/y o  ~.            r'n.e  m        aW o)        Chemistry Supervisor The Chemistry Supervisor conducts or supervises the chemical and radiochemical analyses of water and gas samples. He evaluates test results and directs corrective measures incident to the analyses.

He has the authority to initiate the Emergency Plans. p) Maintenance Superintendent The Maintenance Superintendent reports to the Plant Manager and is responsible for supervision of the maintenance of all equipment and facilities and for maintaining all required maintenance records. Pe~~ ~

                                              +~           ~ /~~               /3./-3   ~   a.

Assistant Superintendent - Mechanical Maintenance Xhe Assistant Superintendent - Mechanical Maintenance reports to the Maintenance Superintendent and is responsible fo" supervision of the mechanical maintenance of all equipment and facilities and for maintaining all mechanical maintenance records. l5+I - g7

PROJECI': 'ST. LUCIE FSAR DATE PRINTED  : 07/24/81 DATE 07/24/81, TXPIST: Page? DISKETTE HO. : SD-572 PAGE 5 SL2-FSAR 01 r) Assistant Superintendent Electrical Maintenance 02 03 The Assistant Superintendent - Electrical Maintenance reports to 04 Maintenance Superintendent and is responsible for supervision 'he 05 of the electrical maintenance of all equipment and facilities and 06 for maintaining all electrical maintenance records. Instrument and Control Supervisor The Instrument and Control Supervisor reports to the Maintenance Superintendent and is responsible for supervision of maintenance, calibration and installation of all instrument and contr'ol equip-ment and for maintenance of instrument and control records. He has the authority to shut down the unit if in his opinion conditions warrant this action, and he has the authority to initiate t e Emergency Plans.

                 ?  )  Quality Control Supervisor The  Quality Control Supervisor reports to the Plant Manager. and is responsible for the coordination of the overall quality control (QC) effort within the St Lucie Plant organisation.      Refer to FP6L Topical Quality Assurance Report (FPLTQAR) 1-76A Rev. 4 for a more detailed description of the Quality Control Supervisor's responsibilities.

The following describes the line of succession of authority and responsi-bility for the overall station operation in the event of unexpected contin" gencies of a temporary nature: a) Plant Manager

1) . Operations Superintendent

2) Operations Supervisor b) Operations Superintendent

1) Operations Supervisor

2) Plant Supervisor 0 3) Match Engineer Operations Supervisor

1) Plant Supervisor

2) Match Engineer

0

                                           ~
                                             ~

13.1.2.3 0 eratin Shift Crews I During fuel handling operations op either unit, one senior reactor operator is assigned the responsibility of fuel handling with no other concurrent duties. A licensed operator operates the refueling machine and another licensed operator monitors fuel handling operations from the control room of the affected unit. The other refueling stations are manned by licensed and non-licensed operators as required to perform the evaluation. The minimum shift crew has five members dedicated to fight fires during a control room inaccessibility situation. The s6a4~~hift crew composition is given in Subsection 6.2.2, Facility Staff, of the T chnical Specifi" cation. Licensed personnel are shown on Figure 13.1-8'r

JECT  : St. Lucie ~ 'DATE PRINTED  : 07/24/81 DP.= 07/24/81, TYPIST:,Rox Page?

n TAPE NO. SD419 ~ PAGE 1 SL2-FSAR I 13.1,3 QUALIFICATIONS OF NUCLEAR PLANT PERSONNEL RP&L complies with Regulatory Guide 1.8, "Personnel Selection and Training" 0/ iiii 05 Guide is addressed by FP&L TQAR }-76A, Rev. 4. 05 dt~J WO'S 7,/ / j7g 07 13.1.3.1 alifications Re uirements OB 09 AN&M'ANS3.}-}978 describes the minimum qualifications for several of the

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management, operating, technical and maintenance position categories ll ~ specified in Subsection 13.1.2. In addition to these qualifications, operator license candidates will have one year of experience as a senior'eactor 12 13 reactor operator or equivalent experience. Table 13.1-2 .provides the cor-14 and thy 15 actual St. Lucie Plant'Staff positions. p4s .>-t

  }6 17 18            ,

i' are specified below,: gars ) -/ 19 1 20 ~)The Shift Technical Advisor shall have a bachelor's degree or equivalent in 21 a scientific or engineering discipline. Specific training is provided in 22 response and analysis of the plant for transients and accidents; details of the design, function, arrangement and operation of plant systems; and 24 response of instrumentation and controls in the Control Room. 25 30 T~ c~~ 31 g/.,// 32 33 34 35 p e,lii~r pg ep~~ (>(gc~ b~ .reerr 35

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49 e 41 42 43 -44 45 45 '3.1.3.2 alifications of Plant Personnel 47 The qualifications of incumbents in key plant supervisory positions and all 49 licensed personnel are summarized in resume format below. The qualifies 5C tions of the Startup Superintendent whose responsibilities are discussed i n

.51                   Section 14.2 are also included.

13.1>>39 Amendment Ne. P, (888+ e

SL2-FSAR Al fr ed D. Schmid t Vice President Power Resources BHE, Vniversi ty of Fl orida, 1942 Nuclear Fngineering course, Vniversity of Florida Management of Radiation Accidents course, EPA, 1972 FP&L Management Development courses, 1972 - Present Carnegie - Hellon Program for Executives, 1973

              ~

1937 1942 FP&L; Co-op student 1942 - 1945 FP&L; Junior .Engineer, Operation Department 1946 - 1948 FP&L; Betterment Engineer; Sarasota, Lauderdale and Miami Plants 1949 - 1951 FP&L; Assistant Plant Superintendent; Miami Plant 1951 .1954 FP&L; Plant Superintendent; responsible for operating and maintaining the fossil fuel units, Pal at ka Plant 1954 - 1957 FP&L; Superintendent of Operations, Power Plants; responsible for safe, efficient operation of all power generating plants in FP&L system 1957 1970 FP&L; Regional Superintendent of Power Plants; re'sponsib'le for operation and maintenance of all units in his region 1970 - 1972 FP&L; Superintendent of Generating Stations 1972 Present FP&L; Vice President - Power Resources; responsible for the safe and efficient operation and mainten'ance of all'ower plants, including staff support. Since 1978 also responsible for the System Operations, System Protection and Power Supply Technical Services groups. lb gisterad professional engineer. Member of: ASHE, NSPE, EEI, EPRI J. Russell Bensen Assistant to the Vice President - Power Resources BHE, Tulane University, 1946 Nuc.lear Engineering and Nuclear Engineering Laboratory courses, University of Flor:da, )966 Nun Iear Fuel Hanagement course, NUS, 1966 Advanced'Nuc1ear Techno)ogy courses, University of Florida, 1967 West 'rghouse Reactor Operation Training Program and Design. Lecture Series, Wa1t1} and Saxton, Pa. 1968" 1969 Manage.-.,ant of Rad iation Accidents Course and Environmental Rad iation Laboratory, EPA 1972 I FP&L .".ana-ament Development courses, 1973 <<Present

                                        '13. 1-40

PROJECT ~: 07/21/81, St. Lucie TYPIST: ek Page? n TAPE NO.  : DATE PRINTED SD419

07/24/81 PAGE 3 DATE SL2-FSAR 1947 - 1948 FP&L; Water Tester; Miami Beach Plant 1948 1949 FP&L; Instrument Mechanic, Miami Plant 1949 - 1951 FP&L; Betterment Engineer, Results Department; 04 Miami Plant 05 ) 951 1954 FP&L Assistant Plant Superintendent-06 Operation and Maintena'nce', Miami 'Plant 07 1954 r

                                        -  1955        FP&L;   Assistant Plant Superintendent 08                                                     Maintenance; Cutler Plant 09                              1955   -  1957        FP&L; Superintendent of Maintenance; Power .

10 Plants; responsible for. maintenance of all 11 steam generating power equipment in FP&L system 12 1957 - 1967 FP&L; Regional Superintendent of Power Plants; 13 responsible for operation and maintenance of 14 five power plants in his region 15 1967 - 1972 FP&L; Regional Superintendent of Power Plants-16 Nuclear 17 1972 - 1973 FP&L; Manager of Power Resources - Nuclear; 18 responsible for startup preparation and 19 operation of all nuclear power plants in 20 FP&L system 21 1974 - 1976 FP&L; Assistant to the Vice President of Power 22 Resources 1976 1978 Ff%L; Manager Power Resource,s Nuclear 24 1978 " present FP&L; Assistant to the Vice President - Power Resources Registered'Professional Engineer Member of: ASME, ANS, NSPE 31 Joseph W. Dickey 32 Mana er Power Resources - Service 33 34 BSCHE - Massachusetts Institute of Technology - 1966 35 HSCE - Massachusetts Institute of Technology 1967 36 University of Virginia - Colgate Darden Graduate School of Business 37 Administration - The Executive Program 1978 38 39 1967 1968 FP&L; Assistant Plant Engineer, Port Everglades Plant 41 1968 - 1971 FP&L; Plant Engineer, Port Everglades Plant 42 1971 1972 FP&L, Assistant Superintendent - Operations, 43 Port Everglades Plant 1972 - 1973 FP&L; Assistant Superintendent, Temporary 45 assignment to Industrial Relations Department 46 1973 - 1976 FP&L; Plant Manager, Lauderdale Plant, respon-47 sible for all plant operations, maintenance and administration 1976 1980 FP&L; Assistant Manager - Power Resources Fossil, 50 responsible for all plant operations, maintenance ..51 and administration for Port Everglades. Lauderdale, Ft. Myers, Manatee and Cutler plants 1980 - present FP&L; Manager " Power Resources - Services 54

13. 1-41 Amendment Nn. g, (8/81)

P ROJECT ': St. Lucie

              'lYPIST:              n ll4TE SD419 PRINTED: 07/24/8)

PAGE 4 ATE 07/24/81, Page2 TAPE NO. SL2-FSAR

           ~

Registered Professional Engineer - Florida Member of: ASCE, NSPE, FES 5 EEI Prime Movers Committee 6 EEI Steam & Combustion .Turbine Subcommittee 7 EEI Gas Turbine Operations Task Force 8 EPRI Advance Power Systems Task Force, 9 0 H. Grosswald 1 Power Resources Section Supervisor - Maintenance Hanagement Section 2 3 Management Development Courses 1973 - 1978 4' 1957 1958 FP&L; Helper, Miami Plant 1958 - 1966 FP&L; Mechanic, Hiami Beach Plant 7 1966 1973 FP&L; Maintenance Foreman, Cutler Plant 1973 - Present FP&L Power Resources Section Supervisor; Maintenance Management 0 1 C. E. Branning 2 Power Resources Supervisor - 0 eratin, Section 3 University of Florida, Gainesvil'le, Florida, BSME, USAF, Primary and Basic Multi Engine Flying School -1954Reese AFB, Texas, 1955 Academic Instructor's Course - Lackland AFB, Texas, 1956 Management and Development Program, FP&L TOP Courses, ]955 - Present 1951 FP&L; Helper at the Miami Plant (Summer Employment) 1 1953 General Motors Plant Layout, Chevrolet Gear 2 and Axle Co., Detroit, Michigan 3 1954 FP&L; Student Engineer, Field Service Representative, Coral Gables Office 1954 1955 FP&L; Field Engineer, Riviera Plant 6 1955 1957 U.S.A.F., Rated Pilot, Candidate. School 7 Instructor, Advanced to rank of 1st Lieutenant 1957 1960 FP&L; Plant Test Engineer, Riviera Plant; Conducted plant equipment performance tests, 0 supervised installation and operation of 1 systems added to existing plant 2 *', 1960 1966 FP&L; Plant Engineer, Riviera Plant. 3 c Supervised Results Department for ~ster testing and treatment, plant instrumentation and control, performance testing and 6 evaluation. 7 1966 - 1970 FP&L; Assistant Plant Superintendent, Riviera Plant. Responsible for Plant Operations and Results Departments. 0 1970 - 1972 FP&L; Start'-Up Coordinator at Turkey Point Plant. Responsible for coordination of Mechanical, Electrical and Instrument Control Start-Up Groups in the flushing, cleaning, 13 ~ 1-42 Amendment No, 5, (8/81)

e PROJECT  : St. Lucie J)ATE 07/24/81, TYPIST: DATE PRINTED  : 07/24/81 Page? n TAPE HO. SD419 PAGE 5 SL2-PSAR pre"operational testing, and other activities 03 necessary to make the plant ready to receive 04 - fuel. 1972 1974 FPEL; Plant Managehr, Turkey Point Plant 05 1974 - Present PPGL; Power Resources, Section Supervisor-06 07 Operations 08 g. D. Peacocp 09 Power Resources Section Supervisor - Administration 10 ll Approximately Miami-Dade 70 business Commu nity College related credits and Nova University 13 14 FPGL Job Related and t1anagement Development courses, 1960 - Present 15 16 195o - 1960 U.S. Air Force; Aero l1edic Specialist-17 Airman 1st Class 18 1960 - 1965 FPSL - Coral Gables District Office; various 19 Customer Services and Customer Accounting 20 jobs 5 classifications. 21 1966 - '1970 FP8L - Systems and Programming Department-Programming and Analyst c'lassifications; 23 System and Programming training. Experience 24 in developing various FPRL computer systems 25 and programming RCA computers in assembly

'0 1971 - 1973 and COBOL languages.

FP&L - Internal Auditing-Internal Auditor; training and experience in financial audits 29 of District Offices, Power Plant Offices, Service Center Offices and various General 31 Office Department.

/32                             - 1973  -  1974         FP8L - Power Resources Department-Power 33'5                                                   Resources Specialist; Office Administration for General Office personnel (approximately 75 people).

1974 - 1980 FP8L - Power Resources Department-Power 37 Resources Review Section Supervisor; development, monitoring and reporting of 39 Departm nt By8gets Eel Cost Control Systems. 40 1980 - Present FPSL - Power Resources Department-Power 41 Resources Section Supervisor-Administration; 42 Supervision of'epartment Budgets, Personnel 43 and Cost Control Processing and .44 Review'ystems. 45 46. ,47 r

                                                                                                           /               h 48                                                                                                          'h

( 49 50 d~ 54: l3. 1-43 Amendment Nn. f, (8/d])

l SL2-FSAR R. A. Watson Power Resources Section Su ervisor - Tests and Performance Wa sh ington Comp tome ter School, 1936 B, S. Chfmistry, University of Maryland, )942 . Navy Communications and Radio, 1943 Radiological Monitoring, U.S. Department of Interior, 1961 Meteorological Aspects of Air Pollution, U. S. Public Health Service, 1965 Nuclear Engineering and Nuclear Engineering Laboratory courses, University of Florida, 1966 Bas'c Radiological Health, U. S. Public Health Service, 1966 Radionuclide Analysis by Gamma Spectroscopy, USPHS,'1966 Advanced Nuclear techno}.ogy, University, of Florida, 1967 FP5L Management Development Courses, 1972 - 1973 1942 1946 U~ $ Navy (Lt ) Commasnir nate nn aa fRaaanae t nant 1945 - 1948 National Bureau of Standards, Analytical Chemist 1948 - 1949 U. S. Navy; (Lt. ) Communications Department 1949 - 1952 Armed Forces Security Agency, Research and Analytical Chemist in Organic and inorganic . Chemistry 1952 - 1972 FP&L; Production Test Group, Power Supply Department, Assistant Engineer, Engineer, Senior Engineer, Production Test Supervisor. Established analytical chemistry laboratory for fuel analysis. Consult with Plant Raaourcea Department on water for treatment and control procedures. Set up programs for evaluating fuel additives.'esign sampling and analytical programs for environmental analysis of air and water. Work with Environmental Engineering Department in setting up long range sampling and test programs for surface and ground water. Design, construct, purchase, calibrate and operate varied instrumentation used for equipment acceptance'and performance tests.

                                 'et     up computer    programs for calculation and reporting    of  results. Coordinate activities of power plant personnel and consultants in obtaining climatological and meteorological data.

1972 - Present FPhL; Power Resources Section Supervisor-Tests and Performance "P Membe. of.'ealth Physics Society E

13. 1-44

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0 SL2-FSAR M. S. Gonzales Power Resources Section Supervisor Instrument & Control and Electrical Maintenance BEE, University of Havana, 1953 Advanced Nuclear Technology course, University of Florida, )967 FP&L Management Development courses, 1973 - Present 1956 - 1961 Cuban Electric Company; Junior Engineer to Results Engineer 1961 - 1966 Bailey Meter Company; Foreign Service Engineer; control systems design and electric power plants staqtup 1966 1967 FP&L; Plant Engineer, Results Department; Turkey Point Plant; Calibration checks and startup of instruments and controls, Turkey Point Units 1 and 2 1967 - 1973 FP&L; Assistant Plant Superintendent; Turkey Point Plant; checkout and documentation of all instrumentation and controls, Turkey Point Units 3 and 4 1973 Present Power Resources Section Supervisor; Supervises Power Resources I & C and Electrical Staff Registered Professional Engineer Member of: ASME, ISA Clarence 0. Woody Mana er Power Resources Nuclear U. S. Army, Corp of Engineers Electrician, )956 ICS Electrical Engineering/Plant Electrician, 1957 - 1960 Electronic Technology, MCC, 1964 FP&L Electrical Apprenticeship, 1961 h University of Miami, MBA, 1977 Massachusetts Institute of Technology - Reactor Safety, 1978 FP&L Management Development course, 1972 present 1956 1962 U. S. Army: Staff Sergeant (E5) Active and Reserve status; U. S. Corps of Engineers Electrician Instructor, Ft. Leonardwood, MO; U. S. Sig. Corps Active Reserve responsible for signal equipment on company level as Supply Sgt. 1956 " 1957 FP&L; entrance level position through Auxi-liary Equipment Operator in two fossil fuel plants Miami Beach and Miami 1957 - 1960 FP&L; Plant Apprentice Electrician under the standard apprentice training program - April, 1961. Instructor in program

                                                                                 'ompleted 1965 " 1969

13. 1-45

J ROJECI': ST LUCIE DATE PRINTED: 07/24/81 ATE 02/12/80, TYPIST: nr Page7 n TAPE NO. SD 613 PAGE 3 SL2-FSAR 3. 4 1960 - 1964 FP&L; Journeyman Electrician, Cutler Plant performing all types electrical maintenance. Approximately 30 percent of this time spent at other plants on major overhaul work. 5 1965 1969 FP&L; Chief Electrician, Cape Canaveral Plant: 6 primary responsibility for check ou't, startup 7 and maintenance of all electrical devices and 8 controls on two 400 MW fossil fuel units; 9 maintained all equipment and administered 0 department personnel. 2,969 ] 972 FP&L; Assistant Superintendent, Cape Canaveral 2 Plant: Responsible for all mechanical and electrical equipment and personnel adminis-tration of said department. 1972 - 1973 FP&L; Superintendent of Maintenance, Port Everglades Plant: Duties involved all mechanical-electrical and instrument responsibilities. 1974 - 1976 FP&L; Assistant Manager of Power Resources Fossil: Responsible for the operation and administration of four fossil fuel plants. 19 76 19 78 FP&L; Assistant Manager Of Power Resources Nuclear: Responsible for operation, mainte-nance and administration of one nuclear plant. 1978 - present FP&I; Manager of Power Resources Nuclear: . K. N. Harris Responsible for operations, maintenance and administration of all nuclear generation. Assistant Manager Power Resources Nuclear

      ~

Graduate - Academy of Aeronautics, Long Island, N.Y. 1959 Industrial Electronics course, Central Technical Institute j963 Awarded SR0-912, 1967, SR0-1612, 1972 Management Development courses, 1972 - Present Stanford Executive program August ]977 Master of Business Administration .- University of Miami, 1981 I'961 )966 Combustion Engineering, Naval Reactor Division; Assistant Shift Supervisor; qualified as Engineering Officer of the Match, trained naval personnel on SIC, nuclear prototype plant; supervisor of off<<hull operations. Responsible for operation & maintenance of all SIC prototype support systems. 7 1966 - 1970 Connecticut Yankee Atomic Power Company; Shift Supervisor and Refueling Supervisor; participated in plant construction, initial startup and full commercial power operation; held AEC Senior Operator license. Ew

13. 1-46 Amendment: No., (8/81)

ROJECT: ST LUCIE DATE PRINTED: 07/24/8), 'TE 07/24/81, TYPIST: sc Page? n TAPE HO.: SD 6)3 PAGE 4 , 1970 - 1972 SL2-FSAR FP&L; Power Resources Plant Superintendent Department: Assistant Operations, Turkey Point Plant; attended Nuclear Operators Training Program and received AEC SRO Turkey Point 3 and 4. Responsible for Plant Operations. ~ ~ 1972 1978 FP&L; Power Resources Department; Plant 8 Manager. Responsible for operations, maintenance and administration of the St. Lucie Plant. 1978 - Present FP&L; Assistant Manager Power Resources Nuclear. 4 13.1-47

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SL2-FSAR H. N. 'aduano, Jr. Mana er of Power Resources- Nuclear Services BCHE, University of Virginia, 1964 U. S. Navy Nuclear Power. School, 1965 Environmental Management'f Nuclear Power Plant, )972 FP6L Management Development, 1973 " Present 1964, - 1969 U. S. Navy, Nuclear Power School, Nuclear . Plant Match Officer, Electrical Division Officer, Nuclear Ship Superintendent, construction and;testing of reactor plant 1969 - 1972 Me st inghou se Electric Cor pora't ion, Fluid Systems Engineer,'WR Systems Division. Systems design, multi-project systems field during plant construction, startup 'ollow-up and hot functional testing member of team that established modifications 'to ECCS to meet AEC interim criteria 1972 1973 Potomac Electric Power Company, Senior Fluid Systems Engineer, Nuclear Engineering Manage-ment Group responsible for directing activi-, ties incident to Nuclear Steam Supply System 1 icensability, radwas te systems, Emergency Core Cooling System, steam generators" and miscellaneous reactor auxiliary systems 1973 ", 1977 FP6L; Power Resources Specialist, Nuclear Projects 1977 - 1979 FPGL; Power Resources Section Supervisor Plant Support; Provides technical assist-, ance to operating nuclear power plants in the areas of trouble shooting maintenance, safety evaluations, responses to NRC questions, and special project coordination. 1979 " present FP6L; Manager of Power Resources - Nuclear Services; responsible for, the overall direc-tion of the Power Resources General Office Nuclear Staf f . Ha ey r. Story Power . ources Su ervisor- Health Ph sics 0 BCHE Georgia In. itute of Technology, 1967 Summer Course, Radar emistry, Universi of Missouri at Rolla, 1968 Summer Course, Radioiso ne Method gy, Texas A 6 M Unive'rsity, 1969 MNE, Texas A 6 M University, 1 Advanceo Health Physics C se, tomics International, 1975 FphL Management Devel ment courses, 1973, 1975 1969 Columbus Col e; Chemistry Instructor 1970 1971 FP6L; Plant Test ineer, Procedures, preparation and revi of preoperational and operating procedures

13. 1-48

0 George Gotch Sr ~~ Power Resour" es ~~~.I BSME, Tri"Scate College, Angola lrdinnn 195 1952 -'96l Mesc nghouse Ato~ic Po~er 'boratory, ~est Miff f flin lini Pa, En> in, cn <n Engin;cr, <cad Valve Project'eehan'"al Engineer. Reponsible for ini-n procurement, fabrication an ereccion of General Purwee Test ."-acidity, and a Thermal Shock Va3ve Test Facf;i i req~nslble for preliminary design an

                                   ~  ~

development o;::,ih <<.--,~rnture Crit'cality Reactor Facil,icy, lear powe components, 1961 <<1962 Aero>et Cene al Co. p. Sacra-ento, California, Area; Quality Analyst. ~ sponsible for auditing seller's rocket missi3e equip ent quality programs. 1962 " 1967 E. I. Dupont de Nemours 6 Co,, In"., Pittsburgh, Pa. area> Qual i v Contro' pre nta tive. Source surveil>>n<<<<Sell 1 inspect'on program to assure adequate control of chemical and 3 let s HDT inspec 1967 1970 General Electric Company, Nuclear Energy Division; Quality Contro3. Representat've " Pittsburgh, Pa. area. Audited quality control program of Seller to provid'e effective control of nuclear process equipent; source surveillance of Seller's quality con tro1 NOT ins pec "on efforts. 1970 " 1974 MSA Resear"h Corporation, Evans City, Pa.; Quality Assurance Manager. Responsible for passing che ASME Section III Huclear Survey. Designed a Concrolled Manufacturing System authorizing the Company the use of the "N" and "HPT" symbols for Classes 3., 2, 3 and MC nuclear vessels, pumps, parts, piping subasse=blies, and appurtenances. Responsible for upgrading of plant facility and preparing Quality Assurance Manual. Responsible or passing RDT E2-2 Audit by upgrading the Huclear ASME Manual and plant facility. Provided the technical dire" tion for training and certi )ication of nondestruccive personnel, development and implementation of quality assurance program plans, inspection and tests plans, HKt pro" edure and specificacions, quality assurance ASME nuclear and RDT programs, and the quality control policies on ASME Sections I, XII & VIII. 1974 - present S~r77p" ~pl r.v,(( FPL; Powe" Resources Department; Power Resources S~ka~e " Codes and Inspections.

R.~ J.~ ACOSTA Power Resour" es Section Su<.,v AS"Ei University of Sol h Ior da l968 Xntroduction to .'nuclear En incor in Florida Power Corp. Course 1968 Convair NDT S hoo (Level, { { ~ ( f ~ Jog) {97 Ractor Physcis Courses, Florida Power C,rp, 1971 and 1975 Course, Horth Carolina University 1973. Nuclear Plant Design Tra..'nin,, 8 6 '~ Course 3972 H ~ uclear 1 P3ant Systems Trainine, Florid~ Pow"r C rp 1975 1968 - 1970 Florida Power Corp.; Fngineer in plant performance section; P<<ror-ed performance and efficiency tests on fossil units. 1970 - 1971 F3.<<ida .ower Corp.; Environmental Test Engineer; testing, of fossil units for SO and particulate emissions and evalua tions or f uel adII< tive s. 1971 - 1973 Florida Po~er Corp.; Planr. Engineer, Crystal River Huclear Plant; developed proced'ur es, Q.A. audit tr ips, training, review of plant systems. 1973 1975 Florida Power Corp.; Results Engineer, Crystal River Huclear Plant; responsible for supervising the plant engineers in providing technical support to the plant staff. Included procedure review and development, report writing and responsibility for pr{. service inspection. 1975 " 1976 Florida Po~er 6 Light Company; Power Resources Specialist-Huclear Operations. 1976 - 1979 Florida Power 6 Light Company; Power Resources Specialist-Plant Support. 1979 - Present Florida Power 6 Light Company; Power Resources section Supervisor - P3.ant Support. Registered Professional Engineer Hember ASHE, Al<S, FES

l II H.D. JOHNSON 5 vP~/~'ri v Power Re sou"..">>s  !'.-c. (;;ntv pl annini 8 A. Chtc))istr y and .ath Ccr tral !!ct'ed;st College, 1"64 Ph.D. Chemistry The Gh'o State "')'"crsity 1969 1969 - 1972 Post-Doctorll Pcl lou Thc Ohio State University, Depart ent of Chemistry 1972 - 1973 ccturcr and Rcsc~rch A sociate, The Ohio State University, Department of Chc~istry 1973 " 1978 Assist nt Prof ssor of Chumistry, Northern Illinois Univ ur s i ty 1978 - 1980 ealth physics Tc hnician, Institute for Resource management, Bc th>> sda, !D. S vP~) ~>dv 1980 - Present

                          "-mergency Planning.

Member of ACS and Sigma Xi.

t J. L~ D inEti Power Resources BEEE, l1NES, Supervisor - Health Physics University of Florida, University of Florida, 1975 (Honor Graduate) 1976 1972 - 1973 Florida Power and Light Company, Engineer Technologist at the Materials Test Lab with the primary responsibility of conductin9 laboratory tests to determine performance criteria and standards for field equipment and for the selection of that equipment of optimum value to the company.- 1976 - 1978 Oak Ridge National Laboratory, Oak Rdige, Tennessee, Practical experience in radiological surveyi ng on an applied basis. Co-author of several papers including a protocol procedure manual involving On-Site Environmental Monitoring Procedures. at ORHL. Responsible for the environmental assessment of the radiological impact in recovering uranium from phosphate in Florida. Also, involved in the radiological assessing of various sites throughout the country, to determine the degree of severity of contamination. 1978 - 1981 Florida Power and Light Company, Supervisor in the Health Physics Department at Turkey Point Nuclear Power Plant. Responsibilities have included supervising initial health physics training for craft workers and training Health Physics Personnel (Radiation Protection Men). Also, acted as Shift Supervisor in the Radiation Controlled Area, supervising daily activiti es involving radiation control of plant workers. Designated to supervise all Health Physics activities for the upcoming Steam Generator Replacement Project (including budget, facility design, procurement of material, radiological protection preplanning, etc.) prior to promotion to Power Resources Health Physics Supervisor. 1981 - present Power Resources Supervisor, Health Physics. Health Physics Society

0 E. HOABA Power Resource. S ~ lg Bach. of Eng. - Stevens Institute of Technoloogyy i 1971 1971 - 1972 Newpor'ews Shi pbuilding Eng ~ Dry Dock Co., Facility Design

                               'esigned machines andandequipment shipyard,                                      utilized in the 1972   "  1976         United Engineers S, Constru" performed cost/benefit             tors; Project Nuclear Eng.;

and optimizatin studies, developed systems to meet NSSS interfaces, wrote eaupment specifica tions and performed rupture analyses. Worked on high/moderate energy pipe numerous nuclear projects. 1976 1977 Ebasco Services, In".; Waterford 3 dire"ted Project Licensing Fngineering for design against design bases preparatin oi FSAR, reviewed plant all licensing responses for and safety criteria, prepared project. 1978 - 1980 Florida Power 6 Light Cmpany; Lead Licensing Engineer for St Lucie Unit 2 directed preparation of FSAR and ER, evaluated plant design changes safety criteria prepared all against design bases and project. licensing responses for the 1980 - present Florida Power

                                                         ~

Pp wr~ 6) o ar(rs gpr (,>/n T-I a Light Company." EIT " Pennsylvania

0 SL2-FSAR C. M. Wethy BEE, University of, Miami, 1952 Nuclear Engineering Course, University of Florida, 1966 Westinghouse Reactor Operator Training Program, 1968 Turkey Point Operator Training Program, 1970 MBA, University of Miami, 1975 Business Law, Miami-Dade Community College, 1975 1943 - 1945 United States Navy; Aircraft Carrier 1950 - 1954 FP&L.; Cutler Plant, Helper, Water Tender and Instrument Mechanic 1954 - 1968 FP&L; Productio'n Test Group 1968 - 1975 FP&L; Turkey Point Plant, Reactor Engineer, Assistant Plant Superintendent - Technical, and Operating Superintendent 1975 - 1976 FP&L; Power Resource Operatio'ns and Mainte-nance consultant for South Dade Nuclear Pro<< ject and member of evaluation team for nuclear plant to be built in De Soto County 1976 - 1978 FP&L; St Lucie Unit 2 Power Resources Team Member 1978 - Present Plant Manager - St Lucie Plant. Registered Professional Mechanical Engineer, State of Florida, 1967 NRC Senior Operator License - Turkey Point Units 3 and 4, 1972 Registered Professional Nuclear Engineer, State of California, 1977 Member of: ASME, American Nuclear Society, Florida Engineering Society, National Society of Professional Engineers, and Air Pollution and Control Association. J.E. Bowers Maintenance Su erintendent Advanced Engineering course, U. S. Maritime School, 1946 Management Training and Mathematics courses, Appalachia Power Co., 1958 19 1959, 1957 Applied Electronics course, Indiana & Michigan Electric Corp., 1963 Business Management Motels, Inc., 1966 Electronics Course, RCA, 1969 Manage"ent Seminar course, FP&L, 1972 I 1955 1958 Indiana & Kentucky Electric Corp., Asst. Control Room Operator; Auxiliary Equipment Operator 1958 1959 Appalachia Power Co.; Control Room Operator/ Unit Foreman 1959 1967 Indiana & Michigan Electric Co.; Unit Foreman; Assistant Shift Engineer

13. 1- 50

SL2-FSAR (e 1967 - 1967 1970 1969 Pan American World Airways; Load Dispatcher, Supervisor, Coordinator and Scheduling United Engineers and Constructors; Nuclear Start-up Engineer, Construction'nd design standards verification,.Dresden Units 2 and 3; preoperational testing & start-up, nuclear and steam systems 1970 - 1972 FP&L; Hechanical Start-up Group; Plant Super>> visor; Turkey Point Unit 3. 1972 - 1973 FP&L', Asst..plant Superintendent - Haintenance, Turkey Point; Haintenance Supervisor of Units No. 3 and 4 1973 Present FP&L; Power Resources Department; Maintenance Superintendent, St. Lucie Plant C. K

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AM. B. Vincent Assistant Su erintendent " Electrical Maintenance B. S Electrical Engineering, University of Florida, 1971 Various vendor technical schools FP&L Nuclear Power Engineering Program, 1976 FR& L - Management Development Cources, 1974 - present 1971 - 1976 FP& L; Overhead and underground di s tribut ion engineer. Responsible for designing elec-trical service facilities for new and exist-ing residential and commercial customers. 1976 - 1978 FP&L; Electrical Startup and Maintenance St. Lucie Plant 1978 - Present FP&L;. Assistant Superintendent - Electrical Maintenance T. A. Dilla d Assistant S oerintendent " Mechanical Maintenance BSiiE, Letou"..eau College, 1969 1969 19 73 Mestinghouse Power generation Service, Field Engineer, Service Specialist, Start-up Engineer Turkey Point Units 3 and 4 19 73 19 74 FP&L; Plant Supervisor, Maintenance Department; Sanford Plant 1974 Present FPL; Assistant Superintendent - Mechanical Maintenance, St. Lucie Plant R. R. Jennings Technical Supervisor BSME, Vanderbilt University, 1969 General Electric Co., Operations Management Course, 197'? 1969 " 1973 Knolls Atomic Power Laboratory; Shift Super-visor; qualified as Engineering Officer of the Match and Plant Engineer. Trained naval and civilian personnel in operation, maintenance and testing of S3G, nuclear submarine proto-type plant. Senior Training Assistant; pre-pared various training materials and proce-dures for safely conducting emergency drills for .student and staff training; responsible for man loading and work priorities. 1973 - 1976 FP&L; Start"up Engineer, St Lucie Plant Mechanical Start"up. Responsible for startup

                                                                              ~

testing of various emergency core cooling safety related systems and containment/Shield Building Ventilation Systems. 1976 - 1977 FP&L; Staff Engineer, St Lucie Plant Technical Staff Department 19 77 Present FP&L; Supervisor, St Lucie Plant Technical Staff Department Hembe r ASM

St. Lucie h'ROJECT DATE PRINTED: 07/27/81 DATE 02/07/80, .TYPIST: nr Page? n TAPE NO. SD420 PAGE 4

                                                                                                                   'L2-FSAR 0                John Cordon West 02              Securit           Su    ervisor 03 04               B. A. Political Science, St. Mary's College, 1973 05               Various military courses including: Area Intelligence Specialist, Defense 06               Against Hethods Entry, Investigative Photography, Counterintelligence Agent.

07 08 '1955 - 1975 U. S. Army; CW3 retired, Personnel Specialist, 09 Axea Intelligence Agent - Japan and Vietnam, 10 Instructor - U. S. Army Intelligence School, ll Defense Against Methods Entry and Photo Tech-nician, Senior Counterintelligence Agent 12 13 1975 - 1979 FP&L; Senior Security Supervisor - Construction 14 for the Hartin County and St. Lucie Unit 2 15 16 1979 - Present FP&L; Security Supervisor St. Lucie Plant. 17 'i 18 19 H. Barrow 20 0 erations Superintendent 21 22 Bachelor of Hechanical Engineering, Alabama Polytechnic Institute, Auburn, 23 Alabama, 1957 24 Introduction to Nuclear Engineering and Nuclear Engineering Laboratoxy, 2c University of Florida, Gainesyille, Fl., 1966 Management Development Course; Basics of Supervision, 1967 Westinghouse Reactor Operator Training Program, Waltz Mill and Saxton, Pa., 28 1968 I 29 Westinghouse Design Lecture Series, Monroeville, Pa., 1969 30 Completed the on-site training program, Turkey Point Unit 2, Westinghouse 31 Senior Review Series,, and passed the Westinghouse examination for Senior 32 Operator. Combustion Engineering Co.> Nuclear Steam Supply 'System Lectures, 33'4 86 hours, 1974 35 1957 - 1958 FP&L; Engineer on Rotation, Results Department, 36 Miami Plant 37 . 1958 - 1959 FP&L; Plant Test Engineer, Results Department, 38 Cutler Plant

   ,39                                       1962      - 1966       FP&L; Plant Test Engineer - Maintenance, 40                                                              Lauderdale Plant 41                                       1966      - 1967       FP&L; Assistant Plant Engineer - Haintenance, 42                                                              Lauderdale Plant 43                                       1967      - 1968       FP&L; Assistant Plant Superintendent - Main 44                                                              tenance and Operation, Lauderdale Plant
   -45                                       1968                   Operator training 'for the Saxton Nuclear
~

46 Experimental Corporation, Saxton, Pa. 47 1972 FP&1 Received Senior Reactor Operator's i 46 License for Turkey Point Unit 3 49 FP&L; Received Senior Reactor Operator's h' 1973 h 50 License for Turkey Point Unit 4 5

                                                  '973
                                                       - Present    FP&L; Operations Superintendent, St Lucie h

Plant; Holds SRO License, St. Lucie Unit 1 5 54 13 '<<53 Amendment No. , (8/81)

PROJECT  : St. Lucie DATE PRINTED  : 07/24/81 n TAPE NO. SD420 PAGE 5 3)ATE 07/24/81, TYPIST: Rox Page7 SL2-FSAR 01 R. J. Frechette 02 Chemistr Su ervisor 03 04 Machinist Mate, Submarine, Nuclear Power and Engineering Laboratory Technician courses, U.S Navy (1965 - 1974) IRCC 60 Credits in various

     '5
                                              ~

06 math and science courses 07 ,08 1965 - 1974 U. S. Navy; Nuclear Plant Mechanical Operator, 09 Engineering Laboratory Technician on SIC 10 prototype SSW (SSN 625) nuclear plants. 11 Staff 'instructor (1971 1974) at SIC Pro-12 totype. 13 14 1974 - 1979 FP&L; Plant Coor'dinator chemistry department 15 during Start"up of St Lucie Unit 1 and operat-16 ing since 1976. Assistant plant technician,

17. Plant technician, Results technician, and 18 Senior technician.

19 20 1979 - Present FP&L; Chemistry Department Supervisor, St

.21                                                  Lucie Plant

.22 23 H. F. Buchanan 24 Health Ph sics Su ervisor BS, Adelphi University, 1968 1962 - 1968 Brookhaven National Laboratory, Brookhaven, New York Health Physics Training, Technician and Senior Staff Health Physicist Technician .31 1968 - 1971 United Nuclear Corp., Health Physicist-

'32                                                  Nuclear Materials Management 33                             1971   -  1977        Yankee Atomic Electric Company, 'Huclear Ser-34                                                  vices Division, Senior Engineer - Radiation 35                                                  Protection Group. Supported seven plants in
.36                                                   areas of licensing, FSAR preparation, auditing, 37                                                  computerired record keeping, OSHA, Title 10         "
.38                                                   Code of Federal Regulations and overseeing all 39                                                 Health Physics Training. Responsible for es-40                                                   tablishing and implementing policy for the "ALARA" program, all Emergency Planning and 41 42                                                  ': he 'entire TLD personnel exposure monitoring
.43                                                   program.

-44 "~

                              '977     Present      FP&L;     St. Lucie Plant, Health Physics Supervi-45                                                   sor.
.46

-47 Member of Health Physics Society, Power Reactor Health Physics Group,

-48             Working Group N343, American National St'andard Internal Dosi'metry Standards

. 49 for Mixed Fission and Activation Products, Atomic Industrial Forum Working .50. Group on Occupational Exposure.

..51 I
                                                        , 13 '   54                 Amendment: No. g, (8/81)

PROJECT  : St. Lucie DATE PRINTED: 07/24/81 Pagef n TAPE NO. SD420 PAGE 6 DATE 07/24/81, TYPIST: Rox SL2-FSAR 01 P. L. Fincher 02 Trainin Su ervisor 03

04. Combustion Engineering Co., Nuclear Steam Supply System lectures, 86 hours, 05 1974 06 07 1961 - 1962 Aerode, Inc., Miami; Inspector 1962 Fansteel Metallurgical Corp., No. Chicago; 09 Hydraulic Press Operator 10 1962 - 1969 U. S. Navy; Machinist Mate First Class ll 1969 - 1973 FP&L; Plant Results Technician, Nuclear Control Center Operator; Turkey Point Plant 13 Units 3 and 4 - SRO License 14 1973 - 1975 FP&L; Nuclear Plant Supervisor, St. Lucie Plant 15 1975 - Present FP&L; Training Supervisor, St. Lucie Plant, 16 Holds SRO License, St. Lucie Unit l.

17 J. Boissy

    '8 G.

19 Startu Su erintendent 20 21 University of Orlando, one year, 1964 U. S. Navy, IC "A" School, NucIear Power School, Nuclear Power Training 23 Unit, Noise and Vibration Analysis School, 1964 - 1969. U. S. Navy Sub-marine School Grantham School of Engineering, Electronics Engineering course, 1973 Diploma Electrical Engineering (Power Option), ICS School of Engineering, 1976 Leader Development Institute - Kepner Tre'goe, 1977 Bachelor of Industrial Technology, Florida International University, 1980 1960 - 1965 U. S. Navy; IC Technician 1st Class 1965 - 1967 U. S. Navy; Motor Room Engineering Supervior; 31 USS Moctobi .32 1967 - 1970 U. S. Navy; Electrical Operator and Electrical 33 Instructor, S5G facility; Electrical Operator and Control Panel Operator, U. S. S. George M.

.35                                               Carver   SSBN 656; Reactor Plant Shutdown Man-36                                               uevering Area Match, SSG and SSM, Plants Cer-37                                                tified   Operator on  SSG and  SSM n

38 1970 1973 FP&L; Plant Test Engineer, Turkey Point Plant 39 Electrical Startup 1973 Present FP&L; Electrical Department, Assistant 41 Superintendent, Electrical Maintenance; St. Lucie Unit 2, Startup Supervisor, 43 Startup Superintendent 45 Member of IEEE, Power Engineering Society, and ASME Subcommittee on Equip-46 ment Performance Testing. 47 ~ 48 49 50

13. 1-55 Amnndmnnn Nn. ), (8/81)

0854M-1 0~/A r 5 << ED UCAT ION: r Bachelor of Science Naval Eagiaeeriag US Naval Academy 1968 Haster of Science Mechanical Eagineeriag USN Post Graduate School 1969 Haster of Business Administration Florida Institute of Technology 1979 EXPBRIE NCE: 1970-1975 US Navy Eagineeriag Officer of the Hatch, Damage Control Assistant, Reactor Control Officer, Operations Officer, Sonar Officer, Submarine School Officer Instructor. 197 5-1977 FP&L Quality Assurance, St. Lucia Plant 1977-1981 FP&L Senior Engineer, St. Lucie Plant Technical Staff, liceased senior reactor operator. 1981>>Present FPSL Operations Supervisor r!~l < rr( Sy E DUCATION: US Navy Submarine, Nuclear Power and Prototype Schools EXP'IE NCE

              '954-1957 US  Navy Diesel Submarines Eng. Dept.

1957-1965 US Navy (Enlisted) Nuclear Submariaes-Qualified.Engineering Officer of the Hatch. 1966-1974 US Navy (Officer)-Naval Reactors Representatives Office! Technical Assistant; Prospect Eagiaeer 1975-1981 FP&L Quality Control Engineer, St. Lucie Plaat, Senior Reactor Operator Licease, St Lucie Unit l. 1981-Present Quality Control Supervisor, St. Lucia Plant Jo

13. 1-56 Amendment No. $ , (8/81)

0852W 8 3 We MIKELL-CO>v-A.r ~4 &e EDUCATION: High School Graduate Electrical School-U-S- .Navy 1949 International Correspondence SchoolWech. Engineer Course 1956 Westinghouse Reactor Operator Training Program Westinghouse Senior Reactor Operator Training Program C.E. Co. Nuclear Steam Supply Lectures 86 hours 1974 One week training in Reactor Theory at University of Florida Three weeks training at C.E. Simulator in Windsor, CT. EXPERIENCE: 1947-1948 FP6L Co.~ Auxiliary Operator>>Lauderdale Plant 1948-1950 U.~ S.N-

      ~ ~  ELectrician's Hate 1950-19 51 EQ.kell Plumbing Co-Hollywood,    Fl: Plumbers Helper 1951-1972 FP&L Co-    - Auxiliary Operator,  Fireman AA, Turbine Operator, Control Center Operator, Watch Engineer 1972-1973 Turkey Point Plant Nuclear Watch Engineer during much     of the low  power physics testing   and initial operation 1974-1977 Participated in writing operating procedures for St. Lucie Plant Unit No. 1.

Operated Unit No. 1 through initial startup and operation. Senior Reactor Operator License. e 1978-Present St ~ Lucie Plant Outage Coordinator, Responsible for scheduling and coordination of all outage activities for St. Lucie Plant ~ e (g (-s a+ Amendment Nn. g, (8/81)

0854M-2 C, A. Pell R.S ~, Ptysfcs, Unfvarsfty of Central plorida, 1975 Advanced PORTRAS Coarse, Control Data Corporation, 1976 Computer Applications and Reactor Design Codes course, Rennsselaer Polytechnic Institute, 1978 1975 - 1976 FP&L; Engineer Trainee, Core Modeling, PRN, General Office. 1976 1978 FPGL; Associate Analyst, Reactor Support and Core Modeling, PRN, General Office. 1978 - 1980 FPGL; Plant Engineer II, Reactor Engineering Department, St. Lucie Plant. 1980 1981 FPGL; Plant Engineer I, Reactor Engineering Department, St. Lucie Plant; coordinated refueling, reload physics testing, core analysis code applications, and participated in plant efficiency and stretch power efforts. 1981 Present ~ FPGL; Reactor Supervisor, St. Lucie Plant. MICHAEL GARRY ALTERMATT Nuclear Vetch Engineer EDUCATION: 1965-1967

 . Liberal Arts    Degree Program  Completed equivalent 40 semester    credits
   .1967-1973 US  Navy Nuclear   Machinist Mate and Power training 1'573-1975 FPhL St    Lucie Unit No. 1 Cold  License Program EXPERIENCE:

1967-1973 US Navy Nuclear Program 1973-1981 St- Lucia Reactor Control Operator, Nuclear Match Engineer f 13.1-57 Amendment No. 49 (8/81)

085 4W-3 WILLIAM J. BLOESER - Reactor Control Operator EDUCATION: 3 years college Electronics technology, Aerospace technology Factory schools from Bendix Corp, and King Radio Dealing with Electronics Equipment. EXPERIENCE: Vorlced in Navy and civilian avionics field, ia navigation, communication, radar, autopilot repair and calibration and installation-6/76 to Present FPSL-Electrician, Instrument and Coatrol Specialist, Senior Plant Technician, Reactor Control Operator Xn trainiag for reactor operator license. J. R. BORDEN Reactor Coatrol Operator EDUCATION: High School Graduate

. Bachelor of Science     in  Marine Engineering 4

Massachusetts Maritime Academy - 1978 Third Asst Engineer License (USCG) EXPERIENCE: 1978-1979 One year sea experience oa steam powered ships as a watch engineer. 600 PSI Boilers driving steam propulsion turbines aad auxiliaries-1979-1980 Auxiliary Equipment Operator at FPBL St. Lucie Plant. In training for Reactor Operator License.

                                                                                       ,lj 'p

13. 1-570 Amendment No. g, (8/81)

08548M ANN V. BRAMHALL Reactor Control Operator EDUCATION High School Graduate AA Degree Edison Community College 1971 ~ e BA lfathematics Florida Atlantic University - 1973 Poet Grad Courses Florida Atlantic University 1974 H EXPERIENCE: 1975-1980 FP&L Power Plant Laboratory Technician 1980-Present Reactor Control Operator at FP&L St ~ Lucie Plant ~ In training for Reactor Operator License C L. BURTON - Nuclear Plant Supervisor EDUCATION: High School Graduate College: University of Kentucky 40 semester hours US Navy - Electronics Technical and Nuclear Power Training FP&L St ~ Lucie Plant "Cold Licensed Operator Training Program" Combustion Engineering - One week "PETR Simulator Training Course" covering accident analysis EXPERIENCE: 1969-3.975 US Navy Reactor Operator 1975-Present FP&L St Lucie Nuclear Control Center Operator, Patch Engineer,

            ~                                                               Shift Supervisor e

13. 1-57b Amendment Ne. $ , (N/8>)

e 0854M-5 CHARLES F. CALLAS Reactor Control Operator EDUCATION: High School Graduate Southeastern Community College 39 Credit Hours 1978 to 1980 US Navy Nuclear Power Training EXPERIENCE: 1973-1977 US Navy Reactor Operator 1977-1980 Carolina Power & Light, Brunswick Units No. 1 & 2 Auxiliary Operator. 1980-Present FP&L St. Lucie Plant Reactor Control Operator t In training for Reactor Operator license. CHARLES RUSSELL GRIFFITH Reactor Control Operator EDUCATION: Attended Western Kentucky University for 2 semesters (August 1971 May 1972) Attended two IRCC night classes (August 1980 December 1980) USN Nuclear Power Program EXPERIENCE: 1976 to 1980 US Navy Reactor Operator 1980 to Present FP&L St. Lucia Plant Reactor Control Operator In training for Reactor Operator License e 13.1-57c Amendment No. g, (8/81)

0854 i+6 ROBERT HAMILTON CZZHENTS - Reactor Control Operator EDUCATION: 1971-1 9 72 27 hours Central Florida Community College, Radiological Health 1981 6 hours Indian River Coaznunity College, Communications, Algebra 1973-1974 Navy Hachinist Mate Nuclear Power Training EXPE RK N(Z: 1972-1 979 US Navy Machinist mate, engineering watch supervisor

  '1979 Ingalls Shipbuilding; submarine test engineer (Nuclear      & Non-nuclear) 1979-1980 FP&L Power    Plant Mechanic 1900-Present FP&L   St. Lucie Plant Reactor Control Operator In training for Reactor Operator License.

CARL G. CRIDER - Reactor Control Operator EDUCATION: 3 years College (Ohio State, IRCC, Florida Institute of Technology) 1974-1979 Pursuing Industrial Engineering - B SKI.E ~

                                           \

", 16 months Hot License Training - FP&L EXPERIENCS: h. 1971-1974 Four Years - Hydraulics Specialist apprentice (Ford Motor Co.) 1975-1980 Power Plant Mechanic (FP&L St Lucie Nuclear Plant) 1980-Present FP&L Reactor Operator

0854M-7 J CHARLES COUTURE Reactor Control Operator EDUCATION'igh School Graduate General Engineering at Florida Community Colleges PBJC & BCC completed 1-1/2 years. Extra curricular training during high school in television production electronics EXPERIENCE: Television production technical support, (electronic) for 1 CATV and 2 Cable TV stations) FP&L 2 years Mechanical, Maintenance Dept. 3 years Operating experience in Operating positions: Auxiliary Operator Boiler Attendant Turbine Operator Fossil Control C nter Operator (1 year) 1980-Present FP&L St. Lucie Plant Reactor Control Operator In training for Reactor Operator License. PAUL MICHAEL CURRY - Reactor Control Operator EDUCATION: 1973-1977 University of California at Irvine - B.S. Physics 1975-1976 Fullerton College Statistics, Business Math Courses 1978-1979 Southern California Edison Reactor Operator Training Program 1978 Atomics International-1 veek reactor training program (L-85 Reactor) Certificate received'ncluded 4 start~ps. EXPERIENCE: 1978-1 979 Southern California Edison Co. San Onofre Nuclear Generating Station. Reactor Operator trainee. Approx 4 startups performed. 1981 to Present FP&L Co. Reactor Control Operator. In training for Reactor Operator License.

0854M-8 EPH BURNUM DELRUE Reactor Control Operator EDUCA N-'igh School raduate Michigan Technol ical University - BSEE 19 EXPERIENCE: 1978 Consumer's Pover Plant Compan . R. RMting Plant Maintenance 1979 Detroit Edison Company- roe Polar P t Student. Engineer 1980-1 981 FP&L-Pt Myers Pl t Assistant Plant Engineer 1981-Presen PP&L St. ucie Plant Reactor Control Operator. In aining for Reactor Operator License. RICHARD S. GOLDSTEIN - Reactor Control Operator EDUCATION: 28 credits State University of Nev York - Stony Brook January 1975 - September 1975. EXPERIENCE: 1979-1980 PP&L Itinerant Electrician 1980-Present St. Lucie Reactor Control Operator In training for Reactor Operator License

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cr r ~~~9<~ J.3 l.: ~

0854M-9 DENNIS D. DRYDEN Reactor Control Operator EDUCATION: High chool Graduate Ohlone J College, Fremont California, September 197 February 1974, English, Ps chology, Philosophy Basic Electric Electronics School, San Diego California USN Hay 1974 July 1974 Interior Communicatio "A" School, San'go, California USN July 1974 >> October 1974 Naval Academy Prep School>> wpor , RI, USN October 1974-June 1975 USNA Annapolis, HD., July 197 tober 1975 Nuclear Pover School, Ha Island, ifornia, October 1975-May 1976 S5G Prototype, NRF aho June 1976 l&y 977 EXPERIENCE: 1974-1977 US Navy- clear Pover Program 198 S ~ Lucie Unit No. 1 Licensed Reactor Operator GREGORY A. EVANS - Reactor Control Operator EDUCATION: High School Graduate Completed th'e folloving Navy Schools: Navy Nuclear Pover and Interior Communication Training S8G Trident design course. Completed the folloving Utility Schools: FP&L Licensed Operator Training Program 1980 Combustion Engineering PMR Simulator Training Program: 5 weeks of operations practice including, normal and emergency/off~ozmal operations and startmp certification. PP&L Senior Reactor Operator Training 1981. g'p 13.1-57g Anendment No. g, (8/81)

0854W-10 EXPERI ENCE: 1975-1980 United States Navy Nuclear Power Program Electrician 1980-Present FP&L Co. Reactor Control Operator'enior Reactor Operator License MICHAEL BRUCE GILMORE Reactor Control Operator EDUCATION: High School Graduate Related Technical Training: Hot License Operator Training at FP&L St ~ Lucie Plant - 1978 Combustion Engineering "PWR Simulator Training Course," including Reactor Startup Certification-1979. EXPERIENCE: - 1971-1972 Apprentice Electrician Gilmore Electric Co. 1972-1975 Mechanic's Helper, Auxiliary Equipment Operator, Boiler Attendant, Turbine Operator 1975-1978 PP&L St ~ Lucie Plant Nuclear Turbine Operator, Nuclear Control Center Operator 13.1-57h Amandmsnt NoJ(, (8/81)

OS52M 1 ROBERT S ~ GLAZE Plant Coordinator EDUCATXOH: High School Graduate College-Seminole Junior College 1969-1971 'AA Liberal Arts FP&L Co. St. Lucie Plant "Cold License Operator Training Program" 1975 Combustion Engineering "Nuclear Steam Supply System" lecture series'1974 Combustion Engineering S~eek "PMR Simulator Training Course" covering general plant technology and operation Combustion Engineering 1-week "PMR Simulator Training Course" covering accident analysis H~iaz~ Yas ~~icipa1art-~quired-iu-thMMMq-piucMicausad i tion-Program~

   @para tor-Requall'f ca EXPERX ENCE:

19 71 Us S NAVY 19 71>>1972 Halt Disney Morld-Host 1972 Central Exterminating Co., Maitland, FL-Termite Pretreatment 1972-1973 Helper Sanford Plant-FP&L a

   .1973-1976 FP&L Co. St ~ Lucie Plant, Nuclear Control Center. Operator at St ~ Lucie Plant 1976-1980 Licensed Nuclear Control Center Oper'ator involved in the power operation of
   .St. Lucie Unit Ho. 1. Senior Reactor Operator Licen e 1980-1981 FP&L  St. Lucie Plant Training Instructor. Conducting  training for licensed operator requaI.ification training program    and  initial hot  license operation training.

0 I gF 13s1-57i Amendment Ho. g, (SiS>>

0852M 2 THOMAS A GONZALEZ Reactor Control Operator EDUCATION: High School Graduate<feequahic H5.gh School, Nevark, NJ 1957 College-Santa Maria Jr College AA Degree 1963 FP&L Co. Turkey Point Plant "Cold License Operator Training Program" FP&L Co. St. Lucie Plant "Cold License Operator Training Program" Combustion Engineering 8~eek "PWR Simulator Training Course" covering Plant Technology and Operation 'Combustion Engineering one~eek "PHR Simulator Training Course'overing Accident Analysis EX PERI ENCE: 1958-1966 USAF, teletype operator, supply specialist and ground controlled approach radar technican'9 68>>19 70 Instrument Technician at Pratt & Whitney Aircraft 19 71-1972 FP&L Plant Results Technician, Auxiliary Equipment Operator, Boiler Attendant 1972-1974 FP&L Co. Turkey Point Plant Nuclear Operator 1974-Present Nuclear Control Center Operator at St ~ Lucie Plant WILLIAM L. HAGAR - Reactor Control Operator EDUCATION: High School Graduate Correspondence Course (&vy): Hath Part I 1976 Hath Part IIA 1977 Hath Part IIB 1977 Diesel Engines 1976 Ship's Store Afloat 1977

'U  S   Navy         Machinists Matc and Nuclear Pover Training

0852W 3 EXPERIENCE: 19 73-1981 U.S. Navy Nuclear Power Program Machinist Mate 1981>>Present FP&L St. Lucie Plant Reactor Control Operator. In Training for Reactor Operator License. WILLIAM BRADFORD HALL Reactor Control Operator ., EDUCATION: BSME-University of Florida 1960 Airframe & Power Plant Mechanic 1975 EXPERI ENCE: FP&L 5 year s Fo ssi 1 Plant Ex peri enc e 2 years performance testing 2 years plant retrofit 1 year maintenance planner In training for Reactor Operators License. O'BRIEN D. HAYES Nuclear Plant Supervisor EDUCATION: Kigh School Graduate Lincoln College (Northeastern University) 1 year-no degree obtained U.S. Havy Nuclear Power School-1967 FP&L Co. St' Lucie Plant "Cold License Operator Tra'ining Program" 1975 Combustion Engineering l~eek "PWR Simulator Training Course" covering Accident Analysis ppgg~ gT 1~ac c ~ adt Ltcocaad Oparato-r gagoa11pgcatioc program" 8+(8/81) 13.1-57k Amendment No. W,

0852W 4 1 C EXPERIENCE: 1964-1966 Chatam Mfg. Co' Lab Technician Textile Chemistry 1966-1974 U. S. Navy Nuclear Power Program Machinist Hate. Qualified Engineering Officer of the Watch. Engr'orps, 1974-1975 Stone & Webster Engineering Associate 1975-Present FP6L Co. St ~ Lucie Plant Control Center Operator, Shift Supervisor R'. HAYES - Plant Engineer I Ines EDUCATION: Florida Atlantic University, Boca Raton, FL., B.S.M.E- 1974 EXPERIENCE: 19 74 Rogers 6 Associates, , Engineers and Surveyors, Palm City, FL Business and Operations Manager 1973-1974 VariousIneslandscape architects in Palm Beach and Broward Counties. Free Lance

     . Design Engineer 1973 American     Irrigation, Inc.,      Boynton Beach, FL Design Engineer 1975-l977 FPGL  St ~  Lucie     1  Technical Staff Mechanical Engineer    SRO License No. SOP-2957 1977-1980 KoHa,         ,   President, Ft Pierce, FL.      Owner of Sporting  Goods and Marine business 1980-Present r

r FP6L Co, St. Lucie Plant (CE-PWR) Shift Technical Advisor/Staff Engineer/License Training Instructor SOP 3771 PROFES SIONAL ACITIVITES: American Society For Mechanical Engineers Registered E.I.T., Florida Certificate No. 199ET76

'l

't 0

0852M 5 GERALD J IHBRIALE Reactor Control Operator EDUCATION: U S Navy Electrician and Hate School Nuclear Power Training PAL Co. St. Lucie Plant Reactor Operator Hot License Training Program Combustion Engineering PMR Simulator Training course: 5-weeks of operations practice including normal/emergency operations. EXPERIENCE: 1976-1980 U. S- Navy: Nuclear Power Electrical Operator 1980-Present FP&L Co. St ~ Lucie Plant Reactor Control Operator In training for Reactor Operator License. HUGH H.~ JOHNSON JR Reactor Control Operator

 . 'EDUCATION:~

High School Graduate U. S. Navy Electronics and Nucear Power Training EXPERIENCE: 1977-1980 U.S. Navy Reactor Operator 1980-Present PAL Co. St. Lucie Plant Reactor Control Operator In training for React'or Operator License. GEORGE R. B. KAASA - Reactor Control Operator EDUCATION: High School Graduate Clinical Laboratory Course - U. S. Army 1970 P'F 13.1"57m Amendmene Nn. Ps, (8/81)

0852W 6 EXPERIENCE: 1978-1980 Duke Power Co. Power Plant Technician Nuclear & Fossil 1980-1981 Turkey Point Plant Nuclear & Fossil Maintenance Mechanic. 1981-Present St. Lucia Plant Reactor Control Operator. In training for Reactor Operator License. DENNIS J. KRING Plant Coordinator EDUCATION: High School Graduate United Electronic Institute Louisville, Kentucky U.S- Axmy Basic Electronics Training Course-1967 Advanced Intercept Equipment Course-1967 Instructor Training Course-1969 Auxiliary Equipment Operator Training at FP&L Turkey Point Plant 1971 Nuclear Operator Training at FP&L Turkey Point Plant 1972 Watch Engineer Training at FP&L St ~ Lucie Plant 1974 Hot License Operator Training at FP&L St. Lucie Plant 1978-1979 C.E. "PWR Simulator Training Course," including Start~p Certification-1979 EXPERIENCE: 1966-1970 U.S. Army Intercept Equipment Repairman

    '970-1978 FP&L Mechanics  Helper, Auxiliary Equipment Operator, Nuclear Operator, Watch Engineer 1978-Present Senior Plant technican responsible for developing and conducting training programs for all non-licensed and licensed operator positions.          NRC Operator

~ II Licensed on Unit No. l. 13.1-57n Amendment No. (8/81) 1

0852M 7 CHARLES D. MARPLE - Nuclear Watch Engineer EDUCATION: High School Graduate College-Brevard County College-61 credit hours in Elect. En'ech. FP&L Co. Introduction to Steam Power FP&L Co. St Lucie Plant "Hot License Operator Training Program" C.E one week "PWR Simulator Training Course", including Start-up Certification EXPERIENCE: 1973 FP&L Apprentice mechanic, boiler at.tendant 1974-Present FP&L St Lucie Nuclear Operator, Nuclear Control Center Operator, Nuclear Watch

          ~

Engineer RIQIARD L. HcELROY - Reactor Control Operator EDUCATION: High School Graduate U S. Navy and Nuclear Power Training Indian River Comm. College 1980 Present Associate of Science (Hohegan Comm. College) 1980 EXPERI ENCE: 1976-1981 U.S- Navy Reactor Operator 1980-Present FP&L Co. Inst. & Cont ~ Spec. Reactor control operator, in training for Reactor Operator License on Unit No. l. 0 13.1-57 o Amendment No. L, (8/81)

0852M 9 HILTON H. MOSLEY << Reactor Control Operator EDUCATION: High School Graduate Sacramento State University Miami Dade Jr. College Indian River Comm. College Miscellaneous U. S. Afr Force Tech. Schools FP&L Reactor Theory Course Observation Training at Turkey Point Plant University of Florida Reactor Theory Review C-E. Nuclear Steam Supply Lecture Series C E. Simulator Training Program FP&L 21~eek series-Systems Training 12~eek supervised self-study .program covering the following: Principles of Reactor Operation, General Operating Characteristics, Control Station Instrumentation, Safety and Emergency Systems, Standard and Emergency Operating Procedures, Plant Operation and Transient Response, Reading and Interpreting 'Control Instrumentation. EXPERIENCE: 2 months helper at Turkey Point Plant. Involved in Rx preparation and initial cold load. 8 months Aux. Equip. Operator at Turkey Point. Operating turbine generator and secondary equipment. 6 years St. Lucie Nuclear Plant ~ Cold license, NCC Class and NCCO for cold hydro and hot Ops Senior Reactor Operator Licensed on Unit No. 1. Pl P

13. 1-57( ~ Amendment Ne. g, {8/81)

A' 0855W-1 I JAMES EDWARD O'EIL Reactor Control Operator EDUCATION: University of Hartford-1967-1968 Math Major Hartford State Technical College 1969-1971-AS-Nuclear Engineering Technology FP&L Co Reactor Operator Hot License Training Program 1980-1981 EXPERIENCE: 1972-1975 Knolls Atomic Power Lab, Windsor, CT. Radiation Controls Tech (HP) 1975-1980 FP&L Health Physics Tech. 1980-Present Reactor Control Operator St Lucie Unit t 0'1. L W PEARCE - Nuclear Plant Supervisor EDUCATION: High School Graduate I St John's River Junior College 1967 'estinghouse Operators Training Program 1970 Westinghouse Senior Operators Training Program 1972 CE Nuclear Steam Supply System Lectures, 86 hours, 1974 CE Simulator Training, 60 hours, 1974 FP&L Co onsite training program 1975 EXPERIENCE: 1968-1970 FP&L Helper, Aux. Equip. Operator, Boiler Attendant 1970-1973 FP&L Turkey Point Plant Nuclear Control Center Operator, Watch Engineer 1973-Present FP&L St Lucie Plant Nuclear Watch Engineer, Plant Supervisor 13.1-57' Amendment No. P, (8/81)

0855N-2 MICHAEL ALLEN PERRY EDUCATION: 2 Years of College {EE Ma5or) 1970-1972 US Navy Electronics and Nuclear Power training EXPERIENCE: 1972-1978 US Navy Reactor Operator 1978-1980 Operator {non-license) at CP&L Brunswick Plant 1980 2/3 of Hot License Class at CP&L 4

 '981-Present FP&L St  Lucie Plant Reactor Control'perator In training for Reactor Operator License ALDO LOUIS RAMIREZ  Reactor   Control Operator EDUCATION:

US Navy Machinist Mate and Nuclear Power training EXPERIENCE: 1977-1979 US Navy Nuclear Power Program 1980-Present FP&L Co Maintenance Mechanic Reactor Control Operator. In Training for Reactor Operator License. LAURENCE M RICH Nuclear Match Engineer EDUCATION: / High School Graduate FP&L Co St Lucio Plant "Hot Licensed Operator Training Program" 1976-1977 CE one week "PMR Simulator Training Course", including Startup Certification. g/ p.

13. 1-57// Amandmant Na. P, (8/Bl)

0855W-3 EXPERIENCE: 19 68-19 72 USN Machinist Mate Second Classy'perated and maintained steam power components and auxiliaries. 1972-1977 FPGL Apprentice Mechanic, Nuclear Operator, Nuclear Control Center Operator (unlicensed) 1977-Present St Lucie Pl Licensed Reactor Operator, Nuclear Watch Engineer JAMES J SHANNON, JR EDUCATION: US Navy Machinist Mate and Nuclear Power Training Broward Community College (Assoc. in Business Administration) 1977 Johnson Pneumatic Controls School 1979 EXPERIENCE: e 19 65 USS Eestroyer Forrest Shermau DD931 Steam Plant Operator ~ =1967-1971 USS Submarine Nathan Hale SSBN 623(g), Steam Plant & Primary Systems Operator. 1981 FP6L Boiler Attendant 1981-Present St Lucie Nuclear plant Reactor Contxol Operator In training for Reactor Operator License k MARK D SHEPHERD - Plant Coordinator l EDUCATION: High School Graduate 1981-Bachelor of Professional Studies in Training Management in Nuclear Technology, Memphis State University xF 13.1-578'S Amendment Nn. P, (8/81)

O855W-4 Seminole Community College, Sanford PL, Earned Associate of Arts degree 1978 Northeastern University, Boston, MA, earned 65 hours College of Engineering ~ US Navy Electronics and Nuclear Power Training PP&L Co Senior .Reactor Operator Training Program. CE PWR Simulator training program: Pour weeks of operations practice including normal, off~ormal and emergency operations and Reactor Startup Certification EXPERIENCE: 1974-1978 US Navy Reactor Operator. Qualified as Engineering Watch Supervisor 1979-1980 Instructor, Center for Nuclear Studies, Memphis State University, Memphis; Tennessee. Responsible for the development, delivery and administration of various programs of study related to the Nuclear Industry'980-Present Instructor FP&L Co St Lucie Plant. Senior Reactor Operator License EDUCATION: High School Graduate College-University of Florida 1963-1966, 72 credit hours George T Baker Aviation School, Miami, FL, Airframe and Power Plant License 41551561 and Private Pilot's License 81548856, 1962 PP&L Co St Lucie Plant "Cold License Operator Training Program", 1975 CE Nuclear Steam Supply System, lecture series 1974. CE 8 week "PWR Simulator Training Course" covering general plant technology and operation. CE 1 week "PWR Simulator Training Course" covering accident analysis. Mr. Spalding has participated as required in the St Lucie Plant "Licensed Operator Requalification Program". 13.1-57fg Amendmene Ho. P, (8/81)

0855M"5 EXPERI ENCE: 1966-1972

     .US  Coast Guard Reserves 1967-,1973 Pan American Morld Airways  Airframe and Power Plant Mechanic 1973 FP&1   Co  Turkey Point Plant Aux. Equip- Operator.   ~
                              /

1973-Present FPL Co St Lucie Plant huclear Control Operator, Nuclear Match Engineer JEFFREY A SPODICK Plant Supervisor II EDUCATION: High School Graduat'e AA in Liberal Arts 1968 Palm, Beach Jr College

     .FP&L Co St    Lucie Plant "Cold License Operator'Training Program" a/1
 ~qual'.f4caagoa-Program "a~rLucia-Pica't.

US Navy Electronics and Nuclear Pover Training EXPERIENCE: 19 7l-1974

   ~

US Navy Reactor Operator 1975-1977 FP&L - Nuclear Control Center Operator. Senior Reactor Operator License I 1977-Present FP&L Co St Lucie Plant training staff instructor. Responsible for preparation and conduct of licensed operator training programs.

                                                            /

RGIN Reactor ntrol Operator EDUCATION: Mgh ol Graduate

0855W-6

   .,Dayton    Beach Community College  No Degree 1

Embry Ridd Aeronautical Inst. Aircraft Airframe/Power Plant Certif ion

 ~   1969 Seminole Communi       College  completed requirements    for    in Education Related Technical Tra ning:

Licensed Reacto Operator training a t Lucie Plant 1978-1979 CE "PWR Simulator raining Cours , including Reactor Startup Certification-1979 EXPERIENCE: 1972-1978 FP&L Mechanic's per, Aux. Equip. Oper or, Apprentice Electrician 197 8-Pre nt Nucl r Control Center Operator at FP&L St Lucie nt. ROBERT A STORKE Nuclear Watch Engineer EDUCATION: High School Graduate FP&L Co St Lucie Plant "Hot Licensed Operator Training Program" 1976-1977 CE one week "I%/R Simulator Training Course" including Reactor Startup Certification, 1976.

   , EXPERIENCE:

1960-1968 US Air Force

   'et
   =

Engine Mechanic and Jet Engine Technician. Test run various types of aircraft, operated engine test cells and ground equipment, included trouble shooting, repair and overhaul of various types of get engines. 1972-1977 FP&L Aux. Equip. Operator,'oiler Attendant, Nuclear Turbine Operator, Nuclear Control Center Operator (unlicensed) 1977-Present St Lucie Unit No. 1 Licensed Reactor Operator, Nuclear Watch Engineer

13. 1-57' Amendmant No. g (8/81)

0855V-7 E KEVIN HALL THOMAS Reactor Control Operator EDUCATION: Palm Beach Jr College 1969-1971 Business Courses approx. 50 semester hours. US Navy Electrician and Nuclear Power Training Palm Beach County Journeyman Electrician Licensed 1978 Air Conditioning/Refrigeration/Heating Correspondence Course Certificate 1980 EXPERIENCE: 1972 US Navy Served aboard USS Alamogordo AREN2 as a power plant electrician. 1974-1977 US Navy Nuclear Power Program Electrician e 1978'm1980 PAL Electrician e 1981-Present FPSL St Lucie Plant Reactor Control Operator. In training for Reactor Operator License. KATHLEEN DOLORES NARD Reactor Control Operator EDUCATION:

                                    'I Certificate Lowell     Tech  Institute Health Physics Training,           1971 Ihgree Lowell Tech     Institute BS in Health Physics 1975.

License (Pending) Reactor Operator St Lucie Unit 1 1981- ~ Ihgree presently in progress, Florida Institute of Technology, MBA. EXPERIENCE: 1975-1978 'I Dosimetry Engineer Yankee Atomic Electric Co., Nuclear Services Division, Radiat'ion Protection Group. E I E E ~ E

18. 1-57+ ~ Amendment Ne. P, (8/81)

0855M-8 1978-1979 Radiation Physicist Yankee Atomic -Electric Co , Nuclear Services Division> Environmental Laboratory Group. 1979-1980 Health Physics Senior Tech St Lucie Unit 1-1980-Present Reactor Control Operator. ROGER D ALLER Reactor Control Operator EDUCATION: McCluer High School, Florissant, MO. 1973. Related Technical Training: US Navy Machinists Mate and Nuclear Power Training I Utility: FP&L Licensed Operator Training Program-1980 CE PQR Simulator Training Program: 5 weeks operations practice including normal and emexgency/off~oxmal operations, and Startup Certification. EXPERIENCE: 1973-1980 US Navy Nuclear Power Program Machinist Mate qualified as Engine Room Supervisor 1980-Present Reactor Control Operator at FPGL St Lucie Plant JEFF A WEST Reactor Control Operator EDUCATION: 1967-1972 BSEE University of Tenn. (Control Systems 6 Computers) 1972-1974 - 30 hours graduate work on MSEE 8 Univ of Tenn Space Institute.

 . Topic: Network    Theory'oined Navy prior to completing degree 1980-Present - 15 hours completed on      MBA   at Florida Institute of degree date December 1982.

Technology'stimated 1972 Engineer in Training Certificate r 0 g rp

13. 1-57+ Amendment No. g (8/81)'

0855M-9 I FP&L St Lucie Unit fl Shift Technical Advisor Training Program-EXPERIENCE: 19 75-19 79 Navy Nuclear Power Program, qualified F~ineering Officer of the flatch 1980 FP&L St Lucie Unit fl Shift Technical. Advisor 1980-Present FP&L St Lucie Plant Reactor Control Operator. Xn training for Reactor Operator License on Unit tl. NORRIS D MEST Nuclear Plant Supervisor EDUCATION: Andrew Junior College 1 year 1960 US Navy Electrician and Nuclear Power Training, 1960-1962 Eettis Atomic Power Laboratory, 1962

CE Nuclear Steam Supply System Lectures, 86 hours, 1974 ~

Simulator Training, 60 hours, 1974 CE kg g. Participated in the St Lucie Plant Onsite Training Program FP&L Reactor Operator Training Program PTP-1970-1971 FP&L Senior Reactor Operator Training Program PSL-1973-74 EXPERIENCE: 1960-1967 US Navy Nuclear Power Program Electrician, 1 1968-1974 FP&L Helper, Aux. Equip. Operator, Reactor Operator, Nuclear Match Engineer 1974-Present 1 FP&L Nuclear Match Engineer, Nuclear Plant Supervisor, St Luci.e Plant.

13. 1-57gf'p No. f, (8/81)

                                                                                        'mendmant

s ~ ~ I I

              ~       ~

0855W-10 KENNETH J WIECBK - Nuclear Watch Engineer t El) UCATION: High School Graduate Pittsburgh Institute of Aeronautics AA Degree 1970

 'PP&L Co St         Lucie Plant "Cold License Operator Training Program" CE   "Nuclear Steam Supply System" Lecture series CE   8 week "PWR Simulator Training Course" covering plant technology and operation
  ~ .one week "PWR Simulator Training Course" covering accident analysis.

University of Plorida 3 week course in Reactor. Operation and Reactor Theory Hr. pieceet lias part'icipated'-as-required-iu the St Lucia pisa't "Licaesed- ~Opma~Requa1i'f ication Program~ EXPERIENCE: 1962-1967 US Navy Aircraft Hydraulics Mechanic Second Class Air Crew member on HU-4,6D Helicopter 1967-1968 US Naval Printing Office, Printers Apprentice 1970-1973 Pratt & llhitney Aircraft, Jet Engine Test Cell Mechanic 1973 PP&L Co. Riviera Plant, Mechanics Helper 1973-Present St Lucie Plant Nuclear Control Center Operator, Nuclear Watch Engineer 8 S WIllDEQZR - Supervisor Planning & Scheduling E DUCATION: High School Graduate FP&L Co- Training Opportunities Program courses in mathematics, physics, chemistry, steam generators and auxiliaries, steam turbine and auxiliaries, simplified electricity.

13. 1-57ae- V Amendn~nt No., (8/81)

'C 4

                                                  ~ ~

0855W-)1 Westinghouse Reactor Training Program, Turkey Point Plant CE Nuclear Steam Supply Systems Lectures, 86 hours, 1974. Reactor Theory Review, University of Florida, 40 hours Participated in the St Lucie Plant onsite training program FP&L Co. Reactor Theory Course, 3 weeks. EXPERIENCE: 19 57-19 70 FP&L Co. Helper, Aux. Equip. Operator, Fireman, Turbine Operator, Control Center Operator,. Watch Engineer 19 70-19 73 FP&L Co. Control Center Operator and Watch Engineer, Turkey Point Plant 1973-1979 FP&L Co. Watch e Engineer and Nuclear Plant Supervisor, St Lucie Plant 1979-Present PSL Unit P2 Planning & Scheduling Supervisor e Amendment No. P, (8/81)

SL2-L'SAR TABLE 13.l-l ST. LUCIE OPERATIV(G ORCAt! IZATIOtt STAFFIt!G PLA4 Months to Fuel Load Comme rc a i l

                                                                                      ~0~ or a t' on Ma i ntenance          Dept. (Inc Lude itinerant..

and speciaL cree personneL) I& C Maintenance /o

  . r..      Sar jurat     ~   &   Tech                         2g       z~     30 I & C Spec.

Electrical Maintenance 5~pp : & Techs. /0 Chief Elec. EteatrM nrtpneA 'echanical Maintenance S~pe':. & Techs Maintenance Fore.nan Machi ni;st f&r(l ',/ Pf i~."~'.:, Hach':xr Helpers Technical De artment 5crgtPP' & Techs. ~

                                                                    /3   /3o     /3 artment

Securit De Asst, Security Supervisor Administrative Department Asst, Admin. Supervisor-~ t z. Clerks gual it Cont rol Dept.

                                & . Techs.

Z Z-0 eratio'ns D partment Chemistry

                                                ~

Techs. l /< re Sag

                ~
                    ~

Healt'h Physics

                ~up~        '       Techs."                    /~     l
                                                                           /'     i~

Rali arran Prorare Hen I rp Reactor Enpineer l

         ~

g~p+ & Techs  ! Trainin., Dnparrnanr Instructors 7 7 Draf t:sman l3. l- 58

SL2-FSAR TABLE 1 3. l-i (Con t' d ) Comme'rci al Operat'i on ~oerar iona P l ant Su pe r vi .'or ~ ~ ~7 /7 l7 fl Mat'ch Engineer-~ Yt 3~ ~Z Control Center Operator~ SP hue l ea r Ope r - t'r l IX Turbine Opera."or. Auxi liary Equip. Operator rr~p ~ g e jpl p ) A+

                            ~
                                                                  /~

Outa e Coord i nat' on t /g Techni<<ianna f

$ V~r r ir~1~

p I I Start -Up

               & Tea&a   ~

3 C7 ~oI e p I

fager

                                                                                         /Y ~

SLZ-FSAR TABLE,13.1-CORRELATION OF ST LUCIE PLANT STAFF POSITIONS

                                'WITH ANSI/ANS 3.1-1978 TITLES ANSI/ANS 3.1-ANSI/ANS 3, 1-1978                      1978                ST. LUCIE'LANT STAFF Position   Title                        Section No.         Position Title Plant Manager                         - 4.2.1               Plant Manager Operations Super-intendent Opera t ions Manager                    4.2.2               Operations Super%'i></

h Maintenance Manager 4.2.3 Haintenance Super-intendent Assistant Super-intendent " Hechanical Mainte-nance Assistant Superintendnent-Electrical Mainte-

                                                                . nance 1

Technical Hanager 4.2.4 Technical Supervisor I Reactor Engineering Group Leader 4.2.4 O Reactor Supervisor

      'Instrumentation   and                                       Instrument and Control >~i"-~"

Control Group Leader 4.4.2 I

   'hemistry       & Radiochem-
     'stry    Group Leader                     4.4.3               Chemistry Supervisor Radiation Protection Group Leader                            4.4.4               Health Physics C

Supervisor Quality Assurance Quality Control. Croup Leader 4.4. 5 Supervisor Supervisor Requiring

   ~   NRC License                             4.3.1               Plant Supervisor n

Match. Engineer Supervisor not Requiring- Training Supervisor NRC License 4.3.2 y~r vol er g'(~ ~r~'7 (e,)r>~ $ ~

4 SL2-FSAR TABLE 13.1 P (Cont'd) N)SI/AHS 3.1 AHSI/AHS 3.1"1978 1978 ST LUCZE PLAHT STAFF Position Title Section Ho. Position Title Operators Control 6enear

                                              ~

Operator Technicians 4.5.2 Technician J~>h~ww/ Maintenance Personnel, 4.5.3 Mechanic S~a'1'rst " Electrician

3

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0 VICE PRESIDENT. ENGINEERING, PROJECT ViANAGEMENT . 5 CONSTRUCTION CHIEF ENGINEER POV/ER PLANT ENGINEER li JG ASSISTANT /p gyes( f ~/iPlP'+P ( CHIEF ENGINEER ~ypr,) ri <<c guc c.fA)< PROJECTS, zc)f~~S. SUPER-VKOR MANAGER ~ PROJECT MAi JAGER PROJECT MANAGE/ ST. LUCIE ~ ~" ~is'56k" " PLANT PLANT NUCLEARI ENGINEERING MECHANICAL PROJECT 'ROJECT ENGINEERING

                                                                               . LICENSING UPBRKKQR         MANAGER PROJECT MiANAGER-            PROJECT MANAGER PLANT           PLANT TURKEY POINT SX         cv n.~PUT-NATO S/&)                                     CIVIL        ELECTR ICAL

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ViCE PRESIDENT ENGINEERING, PROJECT ViANAGEi".1ENT& CONSTRUCTION DIRECTOR OF PROJECTS PROJPCT PROJECT PROJECi PROJECT iMANAGER MANAGER PROJECT GEi'icRAL M 'i'iAGER GEMiERAL I'.!AMAGER GENERAL tr~AMAGER GENERAL tifAMAGER NEIY PROJECTS PROJECT GENERAL t.lANAGER LANO us'-r'LANNING trlARTIM 6 ST. LUCIE COAL . SO~ CONTROL TURKEY t.lANATEE PLANTS PLANT PROJECT SERVICES POINT g s ps 7/r' I

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                                                                                                                                                                                                                        .ST..LUCIE PLANT UNIT 2 OPGANIZATIO:I CHART PLAIIT ORGANIZATION F IGURE 13.1-9

PROJECT: ST LUCIE-2 FSAR DATE PRINTED  : 07/22/81 DISKETTE NO. : 225 PAGE 1 %AXE 07/22/81, TYPIST: ek Pageos n SD SL2-F SAR 0 02 13 ~ 2 TRAINING 03 Plant personnel have a combination of education, experience, health and 04 skills so that their decisions and actions that affect the plant are such 05 that the plant is operated in a safe and efficient manner. The training program supplements the individual's background to give him the required 06 07 08 knowledge and ability. ~ ~~ Pim c~~ 09 13.2 1 PLAN1 STAFF TRAINING PROGRAM 10 11 The overall objective of the training program is to provide technical J,2 development, specialized training and operating experience to FP&L operating 13 and maintenance personnel. The Plant Manager is responsible for the conduct 14 and administration of the initial onsite training program and for the train-15 ing of replacement plant personnel. Plant training programs are conducted 16 under the direction of the plant training staff. Those programs conducted 17 for licensed operator candidates vill be supervised by personnel with Senior 18 Operator Licenses on Unit $ 1. Mhere special knowledge or expertise is avail-19 able, non-licensed instructor personnel may be used for teaching portions 20 of license training programs. The Plant'raining Supervisor provides 21 direction and assistance to departmental personnel where needed to insure 22 implementation of training plans. FP&L has over 10 years of nuclear unit startup and operating experience vith Turkey Point Units 3 and 4 and St Lucie Unit 1, Functional and ongoing training programs, primarily conducted onsite, are developed for the St Lucie Plant and are based on the guidance of Regulatory Guide 1.8 "Personnel Training" Selection and May 1977 r' f(Rl-R) N 29 re'<5 0 I > 30 31 13, 2 ~ 1. 1 ~ Pro ram De seri t ion 32 33 13.2.1.1.1 Licensed Personnel Training Objective 34 35 It is planned that cola license personnel for St Lucie Unit 2 will be drawn 36 from personnel licensed on St Lucie Unit 1 and that all licensed personnel at 37 the St Lucie Plant vill be licensed on both units. To this end all of the 38 initial group of cold license candidates vill have obtained an NRC reactor 39 operator or senior reactor operator license on St Lucie Unit 1. Cold license 40 candidates will be drawn frcm the following list of personnel who currently 41 hold NRC operator licenses on Unit 1 or are in training for licensing on 42 Unit 41. See Subsection 13.1.3 for experience summaries of these personnel. 43 -44 J. H. Barrow Operations Superintendent (SRO)

.45                             ,  D. A. Sager                           Operations Supervisor          (SRO) 46 47                                C, L. Burton                          Nuclear  Plant    Supervisor    (SRO) 48                               F. G. Davis                            Nuclear  Plant    Supervisor    (SRO) 49                                0. D. Hayes                           Nuclear  Plant    Supervisor    (SRO) 50                                L. Q. Pearce                          Nuclear  Plant    Supervisor    (SRO)

N. D. Nest Nuc lear Plant Supervisor (SRO)

13. 2-1 Amendment No. p, (8/81)

PROJECT: "ST LUCXE-2 FSAR DATE PRINTED  : 07/21/81 DATE 07/21/81, TYPIST: ek. Page2 n DISKETTE NO. SD 225 PAGE 2 SL2-FSAR H. G. Alter att Nuclear Match Engineer ( SRO) 02 C. D. Harple Nuc lear Match Engineer (SRO) 03 L. H. Rich Nuclear Match Engineer (SRO) 04 L. A. Spalding Nuclear Match Engineer (SRO) 05 R. A. Storke Nuclear Match Engineer (SRO) 06 K. J. Miecek Nuclear Watch Engineer (SRO) 07 08 M. J. Bloeser Reactor Control Operator 09 J ~ R. Bowen Reactor Control Operator 10, A. V. Bramhall Reactor Control Operator ll 12 C. E. R. H. Callahan Clements Reactor Reactor Control Control Operator Operator 13 C. J. Couture Reactor Control Operator 14 C. G. Crider Reactor Control Operator 15 P. H. Curry Reactor Control Operator 16 17 14-I~ryan Geezer 18 G. A. Evans Reactor Control Operator 19 H. B. Gilmore Reactor Control Operator 20 S. Gol'dstein Reactor Control Operator 21 A. Gonzalez Reactor Control Operator 22 Griffith Reactor Control Operator 23 L. Hager Reactor Control Operator 2i M. B. Hall Reactor Control Operator J. Imbriale Reactor Control Operator P. B. Isaacs Reactor Control Operator 27 H. H. Johnson Reactor Control Operator 28 G. R. B. Kassa Reactor Contzol Operator 29 R. L. McElroy Reactor Control Operator 30 H. H. Hosley Reactor Control Operator 31 J. E. O'eil Reactor Control Operator 32 Ho A. Perry Reactor Control Operator 33 A. L. Ramirez Reactor. Control Operator 34 J. J. Shannon Reactor Control Operator 35 36 K. H. Thomas Reactor Control Operator 37 K. D. Ward Reactor Control Operator 38 R. D. Meller Reactor Control Operator 39 J. A. Mast Reactor Control Operator 40 41 P. L. Fincher Training Supervisor 42 B. M.. Hikell Outage Coordinator 43 N. G. Roos Quality Control Supervisor 44 R. L. Hayes Plant Engineer 45 J. A. Spodick Plant Supervisor 46 R. S. Glare Plant Coordinator 47 D. J. Kring Plant Coordinator 48 M. D. Shepherd Plant Coordinator 49 M. S. Mindecker Planning & Scheduling Supervisor Following licensing on St. Lucie Unit 1, a minimum of three months operat'ing time will be provided, if possible, for these personnel to gain operating 53 experience prior to cold licensing on St. Lucie Unit 2. Subsequent hot 54 license candidates will be trained for St. Lucie Units 1 and 2 concurrently 1342-2 Amendment No. , (8/81)

PROJECT: ST LVCIE-2 FSAR DATE PRINTED  : 07/22/8) DATE 07/21/81, 'IYPIST: ek Page? n DISYZTTE NO: SD 225 PAGE 3 SL2-FSAR 02 Initial Trainin 03 " The training program for license candidates follows the format for 04 hot license training used for St Lucie Unit'1 but also includes in-05 formation pe'rtinent to Unit 2. licensing. Sp'ecial classes emphasizing 06 differences between the tvo units are held for those personnel already 07 licensed on St Lucie Unit 1. Refer to Subsection 13.1,2 for a des-08 cription of position titles and license status. 09 10 The licensed operator training program encompasses the following ll outline for Cold License Candidates: 12 13 Phase I: Hot license training on Unit 01 in accordance with 14 St ~ Lucie Plant Administative Procedure "Hot License 15 Operator Training Program". 16 17 Phase Ii: Three months of Unit 41 opexation, vhere possible, to 18 gain operation experience prior to cold licensing on 19 Unit 02.

.20 21                      Phase    III:       Unit 41/42 differences training program. A training 22                                          program describing design diffexences between Units 1 and 2   vill  be prepared and presented, to each candidate covering the following areas (a) Core Mechanical Design (b) Core Thermal and Hydraulic Design (c) Reactox Physics 29                                          (d) Instrument and Control Systems Design 30                                          (e) Mechanical Systems Design 31                                          (f) Electrical      Systems Design
.32                                          (g)   NSSS  Response 33                                          (h)   Safety Analysis and Technical Specifications 34'5                                        (i)   Operating and Emergency Procedures (j)   Startup Test Program 36 37                                          Time  vill be available during this phase for candidates 38                                          to accomplish appropriate field study and equipment 39                                          familiarization.

-40 41 Phase XV: Simulator training: Since all cold license candidates 42 will have been licensed on Unit 41, no special simula-43 tor training vill be given for Unit 42 cold license 44 training. Normal annual simulator requalification 45 sessions vill serve this purpose.. Simulator examina-46 tions may be conducted by the NRC at the end of these 47 sessions. Sequencing of simulator sessions vill be 48' dependent upon availability of the simulator and may 49 occur out of sequence vith the program phase. e 54 Phase V: Screening and vill be NRC tion similar in type licensing examinations: and

                                                                                                'An examina-content to an NRC examination given at the completion of the program to de" I3.2-3                    Amendment No. g,    (8/81)

  .OJECZ:           ST LUCIE-2       FSAR                         DATE   PRINTED: 07/24/81
  .TE 07/21/81, TYPIST: ek         Pagef n    DISKETTE   NO.:     SD  225                               PAGE 4 SL2 FSAR termine each candidates      readiness   to take the            NRC examination.

The schedule for the above training is indicated by Fig. )3.2.1. The scheduled start dates and activity durations may change if the core load date changes. b) Prior Experience Credit Some license candidates may have received training in military service, other reactor locations, college, or other specialized train-ing. For these individuals some of the training program may be elimi-. nated based upon review of credentials, transcripts, or testing at the plant site. This will be done on a case by case basis and must 'be approved by the Training Supervisor and Plant Manager. The following list represents those areas of training which may be eliminated:

1) Reactor Theory

2) Principles of Reactor Operation

3) Thermodynamics

4) Heat Transfer

5) Fluid Mechanics 7

8 c) Training Program Evaluation Periodic examinations are given throughout the program to gauge the candidate's progress and overall performance. The Training Supervi<< sor determines the frequency of these examinations. A final compre-hensive exam is given to each candidate to determine his readiness 0 for the NRC examination. This examination .is comparable to an NRC 1 examination, both in scope and content. Grade criteria for the final 2 canprehensive examination shall be an overall score of )80X and )70X 3 on each examination category. License candidates are certified as ready by NRC examination by the Vice-President - Power Resources') 5 0 TMI action plan (NUREG 0737) items have been integrated into Unit 81 7 training activities. The specific items include I.A.2.1, I.A.2.3, I.A.3.1. I.G.l, and II.B.4. Since cold license candidates vill have 9 . been licensed on Unit 4'] these requirements will have been met. As 0 additional requirements are established, they will be factored into l Unit 41/2 training activities concurrently. 2 83 13.2.].1.2 Non-Licensed Personnel Training 4 Non-lac d operators are trained for their positions thr a ccmbination 6 of classroom le res, on-the job training and par 'pation in the system 7 checkout and plant st effort . These t xng programs vill be defined 8 in Administrative Procedures. 9 t (> / $ g /)et. A Q WV/Zdtg 0 Shift Technical Adviso awning is descry in Administrative Procedures

                                                                               'echnical Advisor

~l p2 t3 Requali 'on "Shift Technic visor Training Program" and Program". The Shift Technical Advisors t c assroom portion of the licensed operator differences tram 'rogram.

                                                                                       'rticipate                  in (8/81) 13.2-4                   Amendment Ne.

g

"PROJECT ST LUCIE-2 FSAR DATE PRINTED  : 07/24/81 .~ATE 07/24/81, TYPIST: Rox Pageos n DISKETTE NO. : SD 225. PAGE 5 4 SL2-FSAR 03

  ,              The Mechanical and        Electrical Maintenance Supervisors receive training in appropriate maintenance procedures Sh Lucie Plant.

and supporting when assigned They participate in maintenance functions during the tartup sta to the 04 a checkout of St Lucie Unit 2 systems and equipment. They partici ate in a 05 lec re series conducted by FP&L pertaining to appropriate mechani al and 06 elect cal maintenance functions. 07 08'9 Instrumen ation and control, radiochemistry and health physic technicians are assign several months prior to initial fuel loading a are trained as 10 required in eir respective responsibilities. For radioc emistry and health 11 physics person el the training includes mitigation of ac dents involving a 12 degraded core. 14 Selected superviso and maintenance personnel atte applicable portions of 15 the Licensed Operato Differences Training Program Maintenance personnel 16 meet the requirements f the FP&L/IBEX'oint App ntice Training Program. 17 Handouts from this prog are used by St. Luc'lant departments as deemed 18 ( applicable to job functio in on-going depar ental training programs for 19 the St. Lucie staff. 20 21 Personnel who are not required o hold a NRC operator's license, including, supervisors, engineers, technics ns, op rators, maintenance personnel and 23 others, whose duties require them o rk within the radiation controlled 24 area or on systems associated with e nuclear plant, receive training in 25 Radiation Protection. Upon comple o of this training the individuals con-26 cerned are required to pass an e mina 'on signifying that they have basic understanding of the principles nvolved. Personnel with previous training are required to pass this exam'nation but ay not participate in the formal 29 training program. All plant rsonnel are quired to either have read the plant Radiation Protection anual or attend t Radiation Protection Course. 31 The Radiation Protection urse covers the foll wing subject material:

32. le~.~ ~/~-( -~~i&

33 a) Radiation and R ioactive Materials

     '5 b)        Biological    E   ects of Radiation and Exposure L         its 37               c)        Radiation     etection   and Personnel   Monitoring 39               d)        Princi   es   of Protection 41                e)        Sit   Emergency Plan and Radiation        Protection 42 43               f)          diation Control Area Nork Guidelines 45               Perso nel assigned to the St Lucie Plant,            in an administrative capacx y and 46                whos     duties would preclude their presence         within the Radiation Contro Area, 47                re ive training in Radiation Protection. The Radiation Protection Tram ing 48                P ogram provided for these individuals covers the same material as the no-49                  icensed personnel training program although not as detailed and generally on a more basic level.          Emphasis is placed on the site emergency plan and            e e               St Lucie Plant Radiation Protection manual.

51 13.2-5 Amendment No. 5, (8/81)

Page 1 of .17 13 2

    ~  ~  1  ~  1  ~ 2     NOH-LICENSED PERSONNEI     TRAINING Non-licensed personnel are trained for their positions thxough          a    combination of classroom lectures, on-the-gob training, self-study- participation in plant startup,,and experience or training obtained prior to assignment to the St Lucie plant ~,.
                         )
                                                                      ~

The staff required for operation and maintenance of St- Lucie 2 will be obtained by augmenting the existing staff for St Lucie l, ~ 'n operating uni t The exis ting functional non-licensed

                                  ~

personnel training and qualification programs used for St. Lucie Unit will be used for the staff increase 1 ~ The ovex'all plant training program is defined by a plant quality instruction. Each specific training program is furthex defined by an Administrative Procedure, course manual, PP & L/ISED Joint Apprentice Training Program, or other descriptive documents. These training programs will be modified as necessary based on departmental assessment of the skills and knowledge levels required to operate and maintain plant equipment and systems. A general description of each of the major programs follows: 13 2 ~ 1 ~ 1 ~ 2 ~ I Et1PLOYHE INDOCTRINATION TRAINING All new employees receive'indoctrination in the emergency plan, health physics, security, quality control, fire protection, general admini. tra tive matters, overview of the department to which they arc assigned, and are issued an PP & L Safety Hanual ~ This orientation is usually accomplished during the

first week of employment. Contractors and visitors receive a similar indoctrination in suf ficient depth determined by their

page 2 of 17 scope of work. The training is accomplished through lecture and k l personal instruction. Specific requalification'is not required since further training and experience on the gob increases the level of knowledge in the area addressed by the indoctrination program. However, monthly safety meetings for all employees provide continual emphasis in this area ~ Upon completion of this training, personnel are qualif ied f or unescorted access to the plant excluding the radiation controlled and locked areas ~ i4 kiri-iif'yur~ r 13-2 1 1 ~ 2 SHIFT TECHNICAL ADVISOR TRAININC The Shi f t Technical Advisor Training Program encompasses reactor theory, plant system descriptions, transient and accident analysis, plant procedures, technical specif ications, and simulator training.'he Shift Technical Advisors (HTA) will also participate in the "mitigating damage with a degraded core" and the Unit 1/2 differences training programs for licensed personnel, section 12 2 ~ ~ 1 ~ 1 above. Methods of instruction will include lecture, seminar, videotape and self-study- Periodic examinations will be used to monitor progress The training program requires about 150 contact hours. The requalification program 'emphasizes system descriptions, emergency/off normal procedures, technical specifications, the emergency plan, and administrative procedures. Lectures are planned on a biweekly F

 'requency with an entixe,requalif ication cycle completed as spccif ied in the administrative procedure. Examinations are used to evaluate program ef fcctivcness                      ~ Annual simulator training and participation in the operational assessment 'eedback system for licensed personnel are also components of: thc STA rcqualif Ication pr ogram  ~

1'ge 3 o E 17 13 13.2.1.1.2-P

     ~  ~   ~    ~     ~          FXRE TEAN TRAXNXNG
                                              ~

The Fire Team Training Program implements the training requirements of 10CFRSO, Appendix RE Classroom training includes fire hazard identification and location, fire fighting equipment use and location, individual responsibilities, use of systems and equipment in support of fire fighting, toxic products'f combustion, fire fighting strategies and techniques, procedures, applicable plant changes and modifications, respiratory protection, precautions in radiation area fires, and direction'nd coordination of the fire fighting activities (Pire Team Leader only) ~ Xnitial training which includes practice sessions requires approximately 24-32 contact hours dependent upon class size. Requalification will repeat this training over a time period specified by the administrative procedure. Practice sessions in actual fire extinguishment will be conducted av< for e<<4 ran'fL >> BaC~ P~C C f'CCC~ C>>ig>>, LPCP gCCrC<~~ Prr/rc jP>> f.C. ) ~ /-iv> dr i.lls ~~f&r~t~aa~~M~ per year, 8ne drill per year on a

                                                                                                                   '>>d bactc:   shi f t f:-o-r          aa.~~4-f-t         f'-Ur~~~ one unannounced drill per f Crt year     ~ rCCrrJccCl   t'>>      Pr  CrrqC'4              acr
              ~a Training is provided to all Fire Team Henbers C

r which presently includes the Hatch Engineer, Nuclear Operator, Nuclear Turbine Operator, Auxiliary Equipment Operator, and . Radiation Protection Man. Naintenance personnel who perform maintenance and inspection of f ire protection equipment also receive training and may attend the fire team classroom training sessions to satisfy this requirement ~ Training program effectiveness is confirmed by a triannual audit oE the overall fire protection program g by an outside agency.

Page 4 of 17 13+ 2 ~ 1 ~ 1 ~ 2~4 HFC!!ANICA! HAINTI'.NANCE DEPARTMENT TRAINING PROGRAHS

                                                               ~

a. A rent4ce Plant Hechanic Trainin Pro ram' ~

Prior to qualification to maintain plant equipment, Journeyman mechanics complete this program or acquire

               'Journeyman level skills prior to employment with FP
                     'I L- The apprentice program .is composed of skills d evelopmen t and rela ted s tudy courses.

Skill development includes safety, fires; mobile equipment, rigging, gaskets, gxinders, valves, piping, insulation, sheet metal, regulators, basic welding, . precision instruments, shop equipment, bearings, pumps, seals, couplings, compressors, painting, structural maintenance, construction fundamentals, condenser and heat exchangers, and other skillsI required of a plant g oux'neyman mechanic ~ Skills development generally consists of "hands-on" type of training ~ Job related study courses in mult'i-media f irst aid, power plant fundamentals, piping systems, blueprint reading, bearings, pumps, drive components and turbine and generator maintenance arc part of the apprentice ~ ~ 5, mechanic program. These courses are more closely related to classroom study.

                         .'Hethods of instruction include 'on-the-gob training, class sessions and self-study. Training effectiveness is monitored        thx'ough examination and       skill demonstration-          The   apprenticeship     duration is     two   to t           I f our years       depending    upon  individual experience        and capability      ~

0 Page 5 of 17 b.,Hacbicfat Toaiace ~Pao mam The Machinist: Trainee Program is similar to the apprentice mechanic program described above ~ Machinist journeymen either complete this program or obtain similar skills prior to employment with FP 6 L There

        ).
                                                               ~

are no related study courses for this program ~ Skills development includes machine shop safety, materials, measuring tools and gages, and blueprint reading; drills, reamers, expansion and contraction, and tool e bits; operation of lathes, shapers, drill presses, milling machines, and surface grinders; heat treatment; shaft traightening'nd boring bars; pouring and machining babbit bearings; and metalizing'- This program requires approximately two years for completion

   ; depending upon individual experience and capability              ~

c ~ Mechanic.cal Maintenance Trainin Pro ram The Mechanical Maintenance Training Program functions to supplement the experience and knowledge of mechanics ~pith additional maintenance repair training to assure- work is performed in an efficient and safe manner. Topics include advanced training in many of the areas addressed by the Apprentice Plant Mechanic Training Program. Other topics include crane operation, tool control procedures, radiation safety, protective clothing, containments, safety related equipmont, quality control, and nuclear steam supply systems. Four

   .hours pcr week is planned for this training and can vary

Pape 6 oE 17 dependent upon'plant conditions. These training topics are repeated in cycles as specified in the administrative procedure Examinations or demonstrations are used for assessment of training effectiveness for most topics-

d. De artmental Em lo ee Indoctrination Pro rams Departmental Employee Indoctrination Programs are used for newly reporting personnel after completion oE the general Employee Indoctrination Training Programs I

These require approximately one week to complete. Hechanical Naintenance De artment Su ervisor's Trainin Pp~o pram A 11echanical 1faintenance Department Supervisor s Training Program provides retraining on pertinent procedures, standards,'ork practices, opera. ting experience and plant changes ~ Classroom training topics are repeated in a cycle as specified by the administrative procedure. 13-2-1-1 ~ 2.g OUALITY CONTROL DEPARTHPNT TRAXNXNG PROGRAH The quality cont:rol training program provides formal I training including scheduled participation in lectures, qualif ication in non-des true tive examinations, selE-study, indoctrination of new e'mployees, 'and independent certification training of NDH level IXX department:al personnel includes personnel'ndoct:rinat:ion oE accomplishment: of required readinp of applicable plant: I procedures, repulatory guides, PSAR and other documents; a I general plant tour; and introduction to the plant: document control system.

I I'age 7 of 17 Znspectors receive training to be qualified to ANSZ N 45 ~ 2 ~ 6-1978 requirements as modified by Regulatory Guide l ~ 58 ~ Those who perform non-destructive examinations shall be qualified per ASNT-TC-1A-1975- The duration of traininq will be individualized based upon experience and backgrounds I L. 13 ~ 2 ~ I ~ l ~ 2 P NON-LXOENEEO OPERA'fOR ERAENINO a.. NonLicensed 0 erator Trainin Pro ram The Non>>Licensed Operator Training Program qualifies personnel for the Nuclear Operator, Nuclear Turbine Operator and Auxiliary Equipment Operator I positions prior to assignment to a shif t in other than a training capacity. The training addresses the systems assigned to each of these positions ~ Training for each 1 system includes a general description, major components, I system operation, limits and precautions, instruments and controls', system interrelations, and drawings and references. Training is also provided in duties and responsibilities of each position, safe work practices, emergency condition responsibilities, the emergency plan, in-plant clearance orders, plant work orders, and security responsibilitie. ~ These operators gain a general familiarization with certain specified letters of instruction, Quality Instructions, Administrative Procedures, Operational Procedures and Hmergency Plan Procedures. Training methods include classroom sessions, system walkdown, on-shif t tralnlng tQne, self-

• ~

Pago 8 of . 17 study, and video tapes. Training ef fectiveness is monitored by )ob knowledge checkouts. Ob')ective criteria are used for each specific gob knowledge item Final writ ten and oral/walkthrough examinations determine overall knowledge for each position. The durations of these programs are about nine wee'ks for Nuclear Operators, seven weeks fox Nuclear Turbine Operator and four weeks for Auxiliary Equipment Operators ~ These durations can vary dependent upon individual experience and background Requalif ication

  'raining is provided to familiar%.ze non-licensed operatoxs with procedure,             equipment and syst:   em changes     ~   Syst: em requalif ication will also        be completed in  a    time period specif ied by the administrative procedure.

be Power Plane 0 eratin Fundamentals Entry level plant operating personnel who lack knowledge of basic powex plant fundamentals corLplete this program. This program includes principles of steam power plants, power plant physics, chemistry, measuring instrument:s, piping systems, valves, heat exchangers, pumps, turbine, condensate and fcedwatex'ystems, circulating water systems, bearings and lubricating systems, basic electricity, generators and excit:oxs, instrument and control systems and auxiliary systems ~ This program requires about one to four weeks for completion ~ No speci f ic requal'i f ication is required since subsequent: training and experience advances o pc r a to rs'n owl.ed gc b cyo nd th is 1ev el .

Page 9 of 17 3 13 ~ 2 ~ 1 ~ 1 ~ 2.Q

                     ~     HI,HCTRICAT. MAINTENANCE DEPARTMENT TRAINING a  ~       A     rent4ce Plant Electrician Trainin Pro       ram Prior to qualification to maintain plant equipment, Journeyman electricians complete this training program or"'.acquire Journeyman level skill prior to employment with PP & LE The Apprentice Electrician Program is similar to the Apprentice Plant Mechanic Program described above. Skills development includes safety, rigging and mobile equipment; National Electric Code:

calculations and construction; switchgear; transformers;

                 ~ protective devices; D AC motors, relays and controllers; generator and excitation systems;. A.C. motors and controllers; and systems and troubleshooting'he related study courses include multi-media first aid, power plant fundamentals, electrical. maintenance, D C       ~ ~

circuits, A-C. circuits, elementary and schematic diagrams, and po~er electronics. This program requires two to four years for completion dependent upon individual experience and capability.

b. Electrician Trainin Electrician training may consist of on-the-gob or classroom training in the general areas of plant sys tems, electrical sys tems, measur emen t and test equipment, electrical safety, and p'lant ins truc tions and procedures. Specific areas are dependent upon assigned 1 Job task requirements which include instrument inverters," battery chargers, heat trace equipment,

Page 10 of 17 reactor trip switchgear, limitorque valves, diesel generator control, polar crane, and grounding techniques. Changes may be made dependent upon overall department expertise ~ Training will be provided or proficiency demonstrated in these areas on approximately a biannual frequency ~ C ~ Electrical De artment Su ervisors Trainin Electrical Department Supervisors and Technicians obtain traininq in'dministrative policy, technical specif ications, emergency and security plans, procedures, ~ and personnel management ~ They also attend selected sessions o'f the electrician training ~ d ~ De artment Em lo ce Indoctrination

                       .'Department Employee Indoctrination is provided for newly reporting personnel after completion of the general Employee Indoctrination Training Programs
                    /0 1 3 2 ~ 1 ~ 1   ~ 2 oP'EALTH        PHYS ICS BEPARTHENT    TRAINING PROGRMCS a.'ealth            Ph  sics uglification The Health Physics Qualification checkoff is designed for departmental use. The Health Physics
             . Supervisor indicates applicabXe areas for each individual- Specific qualification areas include, where applicable, required reading,      I radiation work permits, contamination control, radiation and exposure control, radioactive material control and waste, respiratory protection, erne'rgency training, measuring and test

Page 11 of 17 I equipment, b ioassay program, and adminis tra tive activities. Duration of the qualification program is dependent upon individual capability and experience. Selected personnel attend the "mitigating damage with a degraded core" training programs

      )
         , The requalif ication program includes topics that are relevant to needs         of departmental personnel.       A minimum average        of about two hours per month is devoted to   requalification.       This program is designed to review all   aspects    of Health Physics in      a  time period specified by the adminis     tra tive procedure.

b ~ Emer enc Radia tion Team Trainin The Emergency Radiation Team consists of the Nuclear Operators, Nuclear Hatch Engineer, Radiation Protection Hen and other Health Physics Department personnel- Specific training topics include radiation surveys and sampling for radio analysis, personnel protective clothing and equipment personnel dosimetry equipment, estimating the magnitude and extent of radiological hazards, establishing and posting radiation or contamination area boundaries, monitoring personnel for exposure and contamination evaluation, location and use of emergency equipment, records and logs, and emergency facilities and locations. This program requires approximately eight hours to complete dependent upon in d iv id ual cap ab ili ty and experience ~ Annual rcquali f ica t ion is required ~

Page 1 2 of 17 c., Radiation Controlled Area Trainin S ~ pic/iA rx II,A'u J.u 6

            ]gas r an~l~s access t o the r a d ia t io n p r o g am controlled area      ~     Specific training areas include an
                                                                'I introduction to the plant radiation protection program, radiation f undamentals, units of radioactivity, biological effects of radiation, protection against radiation and contamination, methods of detection of radiation, exposure limits and personnel monitoring, protective clothing and equipment, emergen'cies, and applicable standards, regulatory guides and regulations    ~    Instructional methods include lectures, videotape and hand-on practice. Training ef f ectiveness is measur ed by writ ten examinations and skil ls demonstration     ~    This program requires sixteen hours for delivery and biannual requalif ication.

Respiratory protection training is conducted for personnel whose assigned Job tasks and responsib ilities might require access to the radiation controlled area when such protection may be necessary - Xn addition to a . physical examination and a respirator f itting, classroom and hand-on sessions are conducted. Knowledge of respiratory protection is tested with a written examine t ion. This pr ogram req uires .about f our hours f o r gg vacuum / delivery ~)tuM requalif ication is required-

             ~

Page 13 of 17 Hra-t e-e ~res ad.~ ar-ge t-lwi-ree.e-u<-5.-t+-a.n1-Mmn pr~t~~~~-pe-n~~~ per-eel.ek ~eee4 h kn owl ed 13 ~ -2 ~ 1 ~ 1-2 ~ 9 CHEMISTRY DEPARTMENT TRAINING PROGRAM

                     . The Chemistry Depar tment         Training Program is           gob task oriented        ~   Job   tasks are assembled      into six areas o f responsibility:          . secondaries,    primaries, coun ting room, ef fluents, was te systems,            and   environmental       ~

Technicians are assigned to specific responsibility areas and rotate areas at approximately two month intervals ~ The'ncumbent technician trains each incoming technician for each rotation through on-thc-job 'C training using ori gob sheets for each area as a " guideline. This training includes, where applicable, chemistry control, adminstrative functions, reports, equipment operation, technical specifications, procedure changes for the previous twelve months, reagent chemical certif ication, computer program changes, sampling techniques, and other skills and knowledge required for the assigned responsibility area Selected personnel

                                                           ~

attend the "mitigating damage with a degraded core" training program.. Training effectiveness is monitored by an annual oral e>:amination of each technician by the Chemistry Supervisor.

Page 14 of 17 h The First Aid and Personnel Deco'ntamination Team is composed of the Auxiliary" Equipment Operator,,the Nuclear Operator and all Chemistry. Depar tment personnel ~ Specif ic training topics include multi-media first aid, communication, supplies and equipment, assessment and treatment of injurieb and personnel h

                  'contamination, radiation environments                    and exposure, decontamination procedures,                   evacuation to of f-site medical               facilities,   emergency    plan, and procedures.

This program requires approximately ten manhours. Triannual requalification is required for mult'i-media first aid and annual requalification for the remainder of the training'('2 h 2. 1. 1. 2.P5 RFAGTOP. ENGXNEERING BEPARTHFNT TRAINXNG This program provides for training of dep'artment personnel in reactor theory, plant systems, technical specifications, plant procedures, and departmental documents'he level of knowledge required for each of these areas is dependent upon gob tasks assigned to specific individuals. Requalification is required on a frequency specified by the administrative procedure. This program also provides for departmental indoctrination" of new employees 13 ~ 2 ~ 1 ~ 1 ~ 2.~ TRAINING DEPART."1ENT TRAINING PROGRAH

                                                       ~

Tliis program primax ily provides for

        ~

certif ication of training department in'tructors J ~ All instructors shall be

Page 15 of 17 certified in general instructional capability This will be ~ based on demonstration prior to conducting any actual training sessions'evelopment nf this cability may be obtained through specific individualized training or from past experience. Hach staff instructor shall hold a specific certification for the .topic being presented by him'he required technical expertise is certified by demonstration and is obtained from self-study in preparation for a lecture. Attendance of classes conducted by previously certified instructors can also be used'nstructors who conduct or supervise a complete Operations Match Station Training Program shall have completed all requirements of that Match Stition Qualification Program ~ Requalification is composed b-i~~ ~of eel completion of required reading, annual attendance instructional topics which are not assigned

               ~'ar tie i to the of
                                                                                      /~Sf~"<~~~

t ion in wa t ch s t a t ion r eq uali f i ca t ion, and pa any assigned remedial action based on ~~m~X evaluation of instructional ability. ~ ~~T" '+ 6

                                                             '     "       P'       ~        /'~>~ '

gg ~/Q cf, P4 gd IQ w < gf 4)'cA~ 13 2 ~ 1 1 ~ 2+2 SECURITY FORCE TRAINING PROGRAM This program meets the requirements of 10CFR 73 ~ 55 with an approved training plan for guardforce personnel. The specific details of this program are FP & L proprietary information 10 CFR 2 70 (d)

 ~          ~    Specific course material is dependent upon gob assignment and based on the gob tasks.'nitial training requires approximately 200 hours.

About 1~0 hours of annual refresher training is provided. Hethod. of instru'ction include lecture, 'demonstration,

                        ~

and practical exercises. Mritten examinations

                            ~                                      and   demonstrations       are used to evaluate training ef fectiveness                    ~

Page 16 of 17 2-13 ~ 2 ~ 1 ~ 1 ~ 2 ~ INSTRUMENTATION AND CONTROI DEPARTMENT TRAINING PROGRAM Instrumentation and Control Department journeymen typically qualify in'heir job skills prior to assignment to the St Lucie ~ plant These specific prerequisite skills are those required to

            ~

function as an electronics technician- Typically; personnel acq'uire these skills through completion of an Associate of Science Program stressing electronics, military training in an electronics specialty area, or equivalent industrial experience. Specific departmental training is provided for skill areas that require supplemental training ~ This training is conducted by plant or vendor personnel. This program provides for required reading and new employee indoctrination ~ 1 3 2 1 1 2 )A OIJTAGH MANAGEMENT TRAINING PROGRAM This program provides department personnel with the requirwd expertise 9n thc planning and scheduling system, use of the comput: er and othex hardware, outage management, and relevant plant procedures. Training methods include vendor schools, self-study and on-the-job experience.. The program provides for I required reading and new employee indoctrination ~ 7 13 2 ~ 1 ~ 1 ~ 2 ~

                                ~      ADMINISTRATIVE DEPARTMENT TRAINING      PROGRAM This program provides departmental                      personnel with the required expertise for speciiic job assignments                            ~   The. e

'ass ignmcn ts include swi tchb oard, payroll, pet ty cash, pur chasin g~ personnel admini tration, and management ol supplies

Page 17 of 17 inventory ~ The method of'raining is primarily on-the-gob experience. Job task assignment rotation is used to assure an adequate depth of knowledge within the depar tment ~ 1 3 ~ 2 ~ 1 ~ 1 ~ 2 ~ 1 6 STARTUP DEPARTMENT TRAINING PROGRAM This program provides general training and qualification in conduct of and administrative requirements for the preoperational and startup test program. Technical training is individualized depending on experience and background of personnel and the assigned job tasks.

a e PROJECT  : ST LUCIE-2 FSAR DATE PRINTED  : 07/24/81 DATE 07/24/81, TYPIST: Rox Page7 n DISKETTE HO. : SD 225 PAGE 6 SL2-FSAK

.,e 02 Indu. trial   safety  and employe training program.

first aid training is provided as part o~ft e general Each employee is issued a cop~y f the FP.'L Safety 03 Rule Book, w)erich covers first aid practices and safe w rk p"actices related 04 to the utilit ndustry. Included in this book a the latest first aid techniques and in rial emergency procedur . Employees may also attend 06 first aid classes. Th standards and~ cedures are developed and admin-. 07 istered by the Joint Advis Safety mmit tee. This program is augmented 08 by the Plant Safety Program wh all include regular monthly meetings with emphasis placed on t'e nuclear aspects as well as the latest industrial 10 ll safety practices.

                                                                              ]q,~        g->    '-b 12               All new plant      perso     1  assigned  to the St L e Plant are given an orienta-tion to general          nt  facilities,   Health Physics        licies, quality assurance, 14               and the emerg cy and security plans.               This orientate          is usually conducted 15               during the erst week of employment at the St Lucie Plant                      ~  provides them 16               with the inimum practical training they need until they can .at . the Radi-17               atio~frotection class or complete the Radiation Protection Program e ina-18'9"            tion.
      '0 13 2~1    1~.F+raeror-camion-Training-21 22              Wire-p~~w~azn~~ ~meri bed-i~ubsect-ion-9                                5  1~

13.2.1.2 Coordination Pith Prep erational Tests and Fuel Loadin~ Table 13.2-1 shows the schedule of each part of the Training Program in rela-tion to the schedule for preoperational testing and expected fuel loading. This schedule also shows expected time frames for examinations and any vendor supplied training. Should fuel'loading be delayed from the date'ndicated, 30 the licensees will supplement the St Lucie Unit 1 operatihg staff as well as 31 support St Lucie Unit 2 startup and preoperational testing activities. 32 Section 14.2 describes the preoperational and startup test program. Subsec-33 ~ tion 14.2.12.4.1 specifically addresses natural circulation training., 34 35 . 13.2.2 REPLACEMENT AHD RETRAINING 36 37 13.2.2.1 Licensed Operators Re ualification Trainin 38 . 39 The requalificat'son training program for licensed operators complies with GacJ~n ~~M.<<'.i&~~~&7+, "American National Standards for Selection 41 and Training of Nuclear Power Plant Personnel," to implement the requirements 42 of Appendix A of 10CFR55. This program is described in Administrative Pro-43 cedure, "Licensed Operator Requalification Program". 45 13.2.2.2 Non-Licensed Personnel Retrainin Refresher Trainin, 47 Plant persopnel not incguded in th~icensed P~esonnel Training Program re-ceive refresher training in radia'tion protection and occupational safety as rgrams are established 49 a par~tof the FPGL ongoing safety progr-".m. Training 50 for>each department to ensure that its personnel maip gpss ain familigr~ity with "0 51 54 tlfeir job spec'xfics and Leep abreast of+changes ing6he plant equipment, policies gad procedures~which couldgdfect their Job functio< This tra'ng is conducted r periodic ly at a frequency specified by the espective depart-i V.

                                                                   ~c<'v> rZrnr lr
                                                '.2-6
                                                            . i cS                                        ~<a(

r"" " amenimene No.

                                                                                                          $      (8/8>)
                     /~. o    t /.~-

P ROJECT  : 'T LUCIE-2 FSAR

                                                               .'DDATE II PRINTED: 07/22/81 PAGE 7

.r~aTE 07/ 21/Sl, TYPIST: ek, Page? n DISYZTTE NOe 225 SL2-FSAR 13)2e2)3 02 03 13e2 ~ 2 ~ 3 ~ 1 Replacement Training - Licensed Personnel 04 05 A continuing training program during the life of the plant assures that each 06 replacement employee who requires an NRC operator license receives the same 07 general material, follows the same fundamental program used for the initially. 08 licensed personnel and knows his specific duties and responsibilities for 09 normal and emergency operations. Personnel from other FP6 L plants are con-10 sidered for these replacement positions on a selective basis'he supervi-ll 12 sory and technical staff are the primary source of instructors'or the con-tinuing training program, but outside assistance may be obtained as necessary 13 to assure competent replacement personnel. 14 15 13e2e2)3)2 Replacement Training Non-Licensed Personnel 16 17 Training programs are established by each department to insure that new per-18 sonnel are trained sufficiently to meet the minimum requirements for their 19 job) These programs provide new personnel with the required familiarity with 20 the job specifics, such as plant equipment, procedures, and policies affect-21 ing their job function> 22 13)2)2)4 Plant Drills Drills are conducted periodically to provide training in plant evolutions 26 such as site evacuation, response to fires, breaches of security, and emer-27 gency medical response , 28 29 13+2 ~ 3 APPLICABLE NRC DOCUPZNTS 30 31 , The following NRC regulations, regulatory guides and reports are discussed 32 in the referenced sections: 33 34 Section 35 36 10 CFR Part 50 3) 1 37, 10 CFR Part 55 13 ' 36 10 CFR Part 19 12i5 39 Regulatory Guide 1)8 13) 1) 13) 2 40 Regulatory Guide 1)101 13)3 41 Regulatory Guide 8e2 '12)5 42 Regulatory Guide Seg 12) 1 43 Regulatory Guide 8)10 12)5 44 Regulatory Guide 8e13 12)5 45 47 48 52

 .53 54 13.2-6a                      Anendeent No'. g, (8/81)

FSAR - . ST. LUCIE PLt, TRAINING SCHEDULE 1981 1982 1983 6/1 7/1 8/1 9/1 10/1 11/1 12/1 1/1 2/1 3/1 4/1 5/1 6/1 7/1 8/1. 9/1 10/1 11/1 12/1 1/1 2/1 COLD HOT CORE HYDRO 'PS LOAD REVXEN. 1/2 DrFF. 0 0 DESIGN 1/2 DIFF. PROGRAM UNIT !ll 'HOT LXCENSE TRAINING OPERATING EXPERXENCE PREP 1/2 DIFF. TRAINING MATERIALS SIMULATOR TRAIN t / t C UNIT 1/2 DIFFERENCES/UNIT 1 REQUAL. TRAINING GROUP 1 GROUP 2 GROUP 3 NRC OEXA~M ONGOING DEPARTMENT 1/2 DIFF; TRAIN. 1/2 DIFF. TRAIN. 1/2 DIFF. TRAIN. TRAINING & RETRAINING p UNIT 81/2 HOT LICENSE TRAINING PROGRAM tI FIG 13.2-1 ir<<r~w <<ar av van ~ ~ ' - ~ r

( 0853 W-1

13. 3 EHERGENCY PLANNING The St Lucie Radiological Emergency Plan is a separate document which has been previously submitted for St Lucie Unit 1, Docket No. 50-335. This extant Plant Emergency Plan will be applicable to both St Lucie Units 1 and 2 since it ><<111 be revised prior to Unit 2 fuel load to incorporate St Lucie Unit 2 design -information as appropriate, .utilizing the guidelines of NUREG-0654, Rev. 1 {November, 1980) "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" 'he revised St Lucie Radiological Emergency Plan will be

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provided in a separate volume entitled "St Lucie Plant Radiological Emergency Plan" ~ 13.3-1 Amendment No. 5, {8/81)

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ST LUCIE PRINTED: 07/21/8] PROJECT DATE 10/04/79> TYPIST; gw Page2 n I TAPE NOi: KATE SD612 PAGE 2 SL2-FSAR 13e5 PLANT PROCEDURES )2

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)3 This section describes administrative, operating and maintenance procedures )4 that are used by the operating organization to ensure that routine )5 operating, offmormal and emergency activities are conducted in a safe )6 ( .

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A: g ~ '~W / 9 The following is a list of categories of procedures to be utilized for LO St Lucie Unit 2: ll l2 a) Administrative Procedures I l3 t4 b) Chemistry Procedures l5 l6 < c) Emergency Plan Implementation Procedures l7 [8 d) Environmental Test Procedures l9

 ?0                       General Maintenance Procedures
 ?1
 ?2                       Health Physics Procedures
 ?3
 ?4                       Instrument and Controls Department .Procedures
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 ?6             h)        Letters of Instruction
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 ?9 30                       Offmormal     and Emergency Procedures 31 32                       Operating Procedures Premperational Procedures 5

36 m) Security Procedures 37 38 n) Quality Instructions 39

lt In order to simplify procedures writing and to incxease operators 'famil' iarity, basic formats are chosen for Che procedure writing effort, as described below. General Administrative and Security Procedures: lrO Title 2 ' Review and Approvals 3s0 Scope 4e0 Precautions 5r0 Responsibilities 6.0 References 7r0 Records and Notifications 800 Instructions Operational Procedures: li0 Title 2 ' Revie~ and Approvals 3a0 Purpose 4e0 Precautions and Limits 5eO Related Systems Status 6 ' References 7~ 0 Records Required Si0 Instructions f Of mormal and Fmexgency Procedures; 1~0 Title 2eO Review and Approvals 3i0 Purpose and Discussion 4.0 Symptoms 5i0 Ins true t ions 6 ~0 References 7e0 ~ Records Required Letters of Instruction: leO Title 2~0 Approvals 3eO Purpose and Discussion 4rO Instructions ~ Quality InsCxuctions'; lrO Approvals 2r0 Purpose 3r0 Scope 4,0 Res pons ibi'ties 5~0 Instructions

Because of the nature of plant operations, any specific task may involve selected procedures from the categories (a) through (n), as listed above. This overlap is necessary to successfully integrate the required work ac-

 'tivity with necessary controls and provide adequate documentation'here

~ required these procedures will cross-reference administrative, operation, maintenance or'ther proceduresi 13 5 1 ADMXNXSTRATXVE PROCEDURES 13' ~ 1 rl Conformance with Re ulator Guide 1 ~ 33 The St+ Lucie Plant procedure program described in this section complies with Regulatory Guide 1.33, "Quality Assurance Program Requirements

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PRXHTED: 07/22/81 ST LUCXE TYPIST: sc. Page? n TAPE HO. DATE SD612

                                                           '               'AGE 4 SL2-FSAR 13.5.1.2          Pre  aration of Procedures The  plant staff"prepares, within approximately six months prior                to core emergencies.

load, the procedures necessary for plant startup, operation and Section 14.2 describes the 'startup and preoperational test procedure program. The cognizant plant supervisor'nsures that these procedures

 .properly    reviewed   by  the Facility     Review  Group   (FRG)  and  approved  'by the are I(( >

Plant Manager. Procedures shall be adhered to and any changes necessary are handled as follows: q Routine changes must be submitted on Change Form for FRG review and Plant Manager approval. b) Temporary changes approved by two members of the Plant Staff, one of which holds a.senior operating license. Temporary chang'es may not be made which change the intent of the procedu" e. Temporary changes must be reviewed, within 14 days (or as specified in the license) by the FRG and approved by the Plant Manager. Changes 'to'procedures which conflict with the operating license are not made without HRC 'approval. 13.5.1.3. Procedures "Duties and Responsibilities of Operators on Shift" prescribes the minimum number of licensed operators per shift, control, room. access and access limitation criteria, shift and relief turnover procedures and'operator's authority and responsibilities, e.g., SRO directing return to power, shutting down the plant when safety of the reactor is in jeopardy, adherence to license requirements, review of routine data, etc. This procedure will contain the requirements of 10CFR.50.54 (i), (j), (k), (, and (m). Guidance concerning shift supervisor administrative duties,con-tained in a corporate directive issued by the Vice President Power Resources has been incorporated into this procedure. Figure 13.5"1 shows those areas specified as "at the control,s". Overtime limitations for "Licensed Operators" defines the overtime policy.

providing for special

                                                                                                                  )'in-there shall be no Administrative Procedures orders of a transient or self-cancelling character.                                                1"'c         JV                    ~r'v)rp     ~

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                                                                                                                                 /')  ~   ...r     ~   rj Administrative procedures, as a minimum, shall be provided which address the administrative control of valves, locks and switches and for the control and use of jumpers and disconnected ldads in safety related systems.

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Administrative procedures are provided covering the ASIDE code testing of pumps and valves; the schedule of periodic tests, checks and calibration; the reactor engineering schedule of periodic tests and reports; and the schedule of maintenance surveillance requirements. Pg r

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Operatic~-4 procedures cover~ the normal operation of a unit from a cold sliutdown condition to power and return to cold shutdown. Additional

     ........,... procedures cover sLzrtup, operation and shutdown of individual and components.'hese systems
       " "" condition                                                           include check lists for establishing the necessary of system components to perform the specific procedure, and precautions to be followed during the procedure.
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OEE-normal/emergency operating procedures cover the range of equipment and system troubles. These are procedures that describe actions to be taken when equipment malfunctions or to prevent a perturbation Erom

                " . resulting in a situation of more serious consequence.                                                                                        Typical conditions included are excessive system leakage, pump Eailure, loss of of f-site power, instrument air failure, and a stuck or faulty control element
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and Inverse Count Rate Ratio Estimated Check Instrumentation,n Periodic Channel Remote Shutdown Monitoring Yerification and Selector Switch Position CEDH HC Set Operation Extension Shafts Coupling and Uncoupling of CEA Full Length CEA - Periodic Exerciseckr Zoo(n.. f- ~ps f-r~ f; If;~,~ g VC h~r) f/~ g,C~ System Draining the Reactor Coolant / Opening Leak Test Following RCS Pump Hormal Operation Reactor Coolant c C

SL2-FSAR Pressurizer Steam Space Venting ca'},v' es Quench Tank Operation ~a )ties 'y tn:. < f Steam Generator Met Lay-up 'l ~ 0!'l.l'='.".:Neutron Shield Installation 6 Removal Charging and Letdown Normal Operation Volume Control Tank Hydrogen and Nitrogen Concentration Control H 2 System Normal Operation N2 System Normal Operation Liquid Nitrogen Dewar Operation Boron Concentration Control Normal Operatxon -. Boric Acid Batching and Transferring Component Cooling Mater - Normal Operation Turbine Cooling Ma ter System (TCM) Normal Opera tion Fuel Pool Cooling and Purification System - Normal Operation HPSX/LPSX Normal Operation Safety Injection Tank Normal Operation Containment Spray - Initial Valve Alignment'Oxygenated Maste System Maste Concentrator Operation Radioactive Resin Replacement Solid Maste Baler Operation Drumming of Con"entrator Bottoms Maste Gas System Operation Controlled Gaseous Batch Release to Atmosphere Boron Recovery System Lineup Boric Acid Concentrator Operation Operation of the Cathodic Protection System 13 5~ Q c~w

S SL2" F'3AR Condenser Air Removal System OperatLons Circulating Water

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System -, Normal OperatLon ~ 42Mk~Ct'll o~lato r'Ope rat Lon' i/>> c4 "~~f/ < >+pt z ~ p~c ra ~/ o Intake Cooling lfater System Operation Condensate and Feedwater Systetn Operation Auxi 1 iary Feedwa ter Normal Operations Fe<<dwater lleaters Placing in or Removing. from ServLce Cond<<nsate Recovery System OperatLon Fe<<dwater l<ecirculation l.inn Filter Operation huxi liary Steam System - Placing in Service lllowdown System Operation A~l-iw-vy-)3o-i-lmr-Opera L i-on'- Removal 5 Restoration of a Startup Transformer 13ack Feed Through Hai'n Trans formers lloric Acid lleat: Tracing System Operat ion 12> V DC Systein Normal Operation I Inst,ruct ious for Switchyard I)C System Operat.ion 13alance of Plant. 12") V DC System Normal Operation Operation of the 120 Y InsLrument AC System <Class 1; 120 V Vital. AC System Operation" (tton-Class IF) InsL runteor Ai Y Sys Lem Opc rat ion SLatiun Air System Operation Operation and Calibration of HSA-701 CO Alarm Operation and Calibratioii of HSA-70~i CO Honitor Proce~Mlon i-t.-or-i <>t, &ye"LemiOIri<Mtt on Radiation Honitoring System, Operation of I'rimary Sample System ) Vn+vL A-li ~ttrr~il'v

SL2-FSAR Gas Analyzer Operation Secondary Sample System Valve Alignment Fire Protection C System Operation Fire Detection Procedure System Operating Proce

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System Operatron Containment Cooling System Operate.on C'. mr~ ~~'-I <3 i~ <6~'7y C-.v ( $~ y 7 C~~ Continuous Containment Hydrogen Purge System Operatron Shield Building Ventilation Operation Hydrogen Recombiner Turbine Seal Oil System Operation Generator Gas System Operation Turbine Oil System Operation Containnent Building Access llatches - Operatrons Sequence of Events Recorder Operatron Domestic Mater System Operatron Vacuum Degasifier Operation Primary Mater System Filling and Draining t the Refuelrng Canaa and Cavity Source Handling and Xnstallation New Fuel Elevator Operation Spent Fuel Handling Hachine Operatron Fuel Transfer System Operation Refueling Machine Operation .CEA Change Fixture Operation Hew Fue1 lland ling Crane Opera t ron

SL2- FSAR Emergency Diesel Generator Standby Lineup In-Plant Equipment Clearance Orders Equipment Out of. Service Class 1 Prestart Checkoff List Reactor Plant Heatup - Cold to Hot Standby Reactor Startup Reactor Operating Guidelines During, Steady State and'cheduled Load Changes Turbine Startup Zero to Full Load Turbine Shutdown Full Load to Zero Load Reactor Plant Cooldown Hot Standby to Cold Shutdown Reactor Shutdown Reactor Trip Records Secondary Plant Operating Checks and Tests Initial Criticali ty Fol lowing Refueling P~ > f Pp-g7> 8C.r Cn ur rP WM-l.kg anon t-i-ng-tht~CS Reac tivity Deviat ion From Design RCS Flow Determination by Calorimetric Procedure Controlled Liquid Re'lease to the Circulating Mater Discharge Alignment for Pumping From Reactor Cavity Sump to Spent Resin Tank at the Steam Generator Blowdown Treatment Facility 1leater Drain and Vent Sys tern Alignment 11ain Steam System Initial Valve Alignment Instrument Air System Initial Valve Alignment Re fueling Operation Re fueling Sequencing Guidel ines Receipt and Hand ling of lb.w Fuel

SL2- I'SAR i Ax a 1 Shape .Ind ex Control P) Of f-Normal/Emer enc erational Procedures Shutdown Resulting From Reactor Trip or Turbine Trip P/. t- PN~ c,-~. f ~ Sv~w-J ry Blackout Operation Control Room Inaccessibi lity RCS Cooldown During Blackout CEA Off-Normal Operation and Re-Alignment Excessive Reactor Coolant System Leakage Excessive Re~actor Coolant System Activity Reactor Coolant Pump,- Of f"Normal Operation Pressurizer Pressure and Level - Of f-Normal Operation Pressurizer Relic f/Safety Valve Of f-Normal Operation Loss of Reactor Coolant Flow Steam Generator Tube Leak Failur'e Loss of Reactor Coolant Giarging and Letdown - Of f-Normal Operation Emergency Boration Boron Concentration Control Off-Normal Component Cooling Water Off-Hormal Operation Component Cooling Mater Excessive Activity Turbine Cooling Water System Off-Normal Operation

  'uel    Pool Cooling System  Off-Normal Operation Operational Requirements           for the Ultimate    Neat Sink Nigh Pressure      Safety Injection        Of f-Hormal   Operation Shutdown Cooling/Low Pressure           Safety Injection - Off-Normal Operation Uncontrol led release         of Radioactive Liquids

                                                                                                                             ~ ~

PcCT ST LUCIE-2 DATE PRINTED: 07/22/81

07/22/81, TYPIST

Rox Page? n DISKETTE NO.: SD-226 PAGE 1 SL2 FSAR Alarm Response Procedu:es are -in-the form of an annunciator verification

          .Lint" indicating- the actions to be performed should off-normal conditions occur in the operation of systems or equipment. This list provides the guidelines for a preplanned course of'esponse to alarms under certain conditions; hoMever, the particular situation govex'ns the extent to which each action is carried out.( ds + >g p                                                                                         !
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au~(Irr u4 (@~~('0> < ~Q fQ rg~rr furr g(cc 6/ 4( o/Rigg>> 4 s Temporary control room operating procedures are used only to a limited . extent. These are in the form of letters of instruction. Letters of instruction are issued depending upon specific plant operating conditions. Example of such procedures may include personnel authorized to hold clear-t4',~ 44- os( ~ ~~ ances, jurisdiction of systems during startup, or pu=p base line data col-lecti.on. I%-) 13.5. 2. 2 ~Other" Procedures'ther'- procedures are included with the categories listed in Subsection 13;5.1.3. The responsibility for the initiation, development and implementation of these procedures are as indicated belo~. The Operations Department is responsible for". Health Physics Procedures The general objective and character of these procedures is described in Section 12.5. These procedures describe radiation protection and t'e Health Physics Department Supervisor is responsible for ensuring these procedures are folio@ed. b) Emergency Plan Implementation Procedures The general objective and character of these procedures support the St Lucie Site Emergency Plan and are described therein. The Emergency Plan is contained in a separate voLume. These procedures describe emergency preparedness and are the responsibility of the Operation Superintendent. c) Chemistry Procedures Chemistry procedure., are provided for chemical and radiochemical control activities. They include, 'for example, the nature and frequency of sampling and analyses; instructions for maintaining coolant quality vithin prescribed limits; and limitations on con-centrations of agents that could cause corrosive attack, foul heat transfer surfaces, or become sources of radiation hazards due to activation.

ST LUCIE-2 DATE PRIM.'ED  : 07/22/81 DISKETTE HO. : SD-226 PAGE 2 /81, TYPIST: Rox Pageos n SL2 PSAR Procedures shall also be provided for the control, treatment, cali- and management of radioactive wastes and control of radioactive bration 'sources. The Chemistry Supervisor is responsible for ensuring these procedures are followed. The Maintenance Department is responsible for:

1) Maintenance Procedures Maintenance 'procedures are written for maintenance of equipment expected to require frequent attention Examples of such equipment are control rod drives, pump seals, important filters and strainers, diesel generator sets, major valves and steam generators. As experience is gained in operation of the plant, routine maintenance is altered to improve equipment perform-,

ance, and procedures written for repair of equipment az'e improved, if required. Since the probability of failure is usually unknown and the time and mode of failure are usually unpredictable for most equipment, specific piocedures cannot be written for repair of most equipment before failures. Radiation protection measures are prescribed before the task begins as necessary.

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After permission is granted, equipment is made safe for work. Measures provide for protection of equ'ipment and workers. Equipment and systems in a controlled status are clearly identified. Strict contzol measures foz'uch equip-ment is enforced. r The procedures contain enough. detail to permit the maintenance woz'k to be pez formed safely and expeditiously. Cr r rrr g W~P I Instructions are included for returning the equipmenttheto equip-4 its normal operating status. Operating personnel place mant in operation and verify its functional acceptability. S P ecial attention is given to restozation of normal conditions, such as removal of signals used in maintenance or testing, an d

to systems that can be defeated by leaving valves or breakers miopositioned or by leaving switches in "Test" or "Manual" pooitions. All jumpers are controlled. When placed into service, the equipment receive special surveillance until a run-in period has ended. The Instrument and Control Department Supervisor, the Assistant Superintendent Electrical Maintenance, and the Assistant Superintendent Mechanical Maintenance are responsible for ensuring their respective procedures are followed. Ca ~ p" ~l~/ 4 Lrp v,/,0 s 0 i rq pppr~g+V~/ o r/

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> General Maintenance Procedures General Maintenance Procedures are provided to cover welding, inspection, personnel training and other concerns generic to the implementation of a comprehensive maintenance program. The Maintenance Superintendent'is responsible for ensuring these procedures are followed.

3) Instrument and Control Department Procedures Instrument and Control Department Procedures are provided for d odic calibration of plant. instrumentation such as interlocks, alarm devices, sensors, signal conditioners, s and an protective circuits. The procedures have provisions or meeting surveillance schedules and for assuring measurement accuracies adequate to keep safety parameters within oper" ational and safety limits. The Instrument and Control Depart-ment Supervisor is responsible for ensuring these procedures are followed. The general objective and character of these procedures are described in Section 17.2.

Other Plant Staff Departments are responsible for: Quality Instructions Quality Instructions are provided to cover plant quality related matters including material control. The Quality Control Supervisor io responsible for ensuring these procedureo as followed. The general objectives and char-acter of these procedureo are described in Section 17.2.

2) Security Procedures Plant Security Procedures describe specific plant related security matters. The Security Supervisor is responsible for ensuring these procedures are followed. The general objectives and character of these procedures are described in Section Y -r i n 'plant

~ A Qcnerotore, Steam generator pressure and voter 1&el indicatioa ir pro- ~ ~ vided ta inform the operator >area the N'43 can he shutdoma t'Aaao Qxo ~ ~ provided to start/r.top each pump or to open/close the AV~.S~jsolation @ad tMrbine steam stop valves Aeon the contxol room+ 'Ae Auxin',ie~g Feeamter Gynic, is provided with cmaplote sensor ex@ "I control instruct atetipn to enable the oyaten to automatically re."."oad to a loss of. stem generator iaveatozyi Upon low stem y'Ineretor level oa Auxiliary Peed~ate" intention Signal (AFAS} io generated. %hie g'gael starts the euxxlxcry.feed'Rater plumps end fully*opens Chc Ycdundi at Lsole Eioa valves" automatically providiap e minimus feed~ate" Qos ox 3 0 g~. %he ALAS logic employs four channels of initiatinp ignoble Co pxovide a tMo cut oz three ectgetioa sequence of eystrm components. A sepaa'ate ALAS kc generated for each stean, generator, AFAS l for generator M ead hM 2. 'or pcnerat:or 25, Aa AFAS 3 >ilk indicate that 5 G 2A requires feedvater 6nd thus, sad,ll sterh am".fXiaxg fee8veter pumps RA and PC en" miH. open %so let%on valves X HV-09-9 & Xl @ad X-SE-09-2 <<4~ steam inlet vn'jve X-~3'-08-13 and NFXV X HCV<<Q9-lA~l9 Si+Qarly~ on ALAS R v,Dl indicate Chat 8C 28 r@~ quizzes Red@ster and thus Qi3.X Stark, p~~g RB And N Qad Vill Opon ioo4r.fOXk valises X-Lg'-09-N 8 X2 end X<<M-09 3 ~ 5~ steam Inlet valve X-K'-M<<12 end . HFXU X-HGV QQ-2A~-S, Both "latched" end "oaletche'd" oigaaKs are generated by ea AFASo The pmps,.~hose operation is initiated gad never interrupted, receive ~ ~ latched signals. Tae isolation valves~ which op n on >ox steer generator level and close oa hip+ level~ <<eceiww unlatched signals Additionallj> ~ using, four'hannel prcasure instruct acatioa oa the main stem cad food ~ water lines, the, system has the ability to identify sad isolate n faulted ~ ate~ generator ox ruptured feed~uter $ iaei Should a differential prec-Gure of apprp",.irately 1QO paid be detected, feedeater fKw to the loop Mith th lour pressure is isolated. Yaks is done by closi~ the appli.- cable auxiliary Leedvetex'aoketioa valves+ Redundant isolation valves are provided to @asure thee fccdvster does not enter e faulted loop even ofter 8 sin@i. acti>~8 failnreo A cc-piete de;"criptioa of the APhs logic circuitrg io provided in TSAR Subsection 7+3.1 l~Q, Ihie ccmplieo m.tb SRP 10.4,9 (Rev X) aad BTP ASS lo section 10.h.9h. l l (Rem j/galzs beatified in TSAR.Sub<< VerHLcat9oa of system operatton io provided M tho coatro3. room by a redundant safety related floe Indicatioa end recordinp for each Aux&- Xery Feedvater pinup. Por Pm~ P., the indicator ie powered free. safety bus SA end the recording ie powered from safety bus SB. For Pump 5, the indicator ts @overed fry safety bus SB and the, recording ie powered from safety bus SA. For Pump C, the indicator is po~wrcd from bus SAR RG5 recorder fs pcY28lo'd rrcm Gafctp bg8 SA>> 'n addi.tioa redundant &edvater hider prcssure Xa4$ ~agggg are provided $a the control xop-. for each ot nsa generators. Th4ginda"@toro ia con>unction M,th the atom 3eneratox.. level~indicators provide the operator viaL> a re3.ieb3.~~ system operation status. 4 VX< t.hg,y pE.~~~~@ pg~ p P 0II GGHAp.,', p GHA~i;. gGAd m 0zT~~~VE, Roid 1 ~ i . SL2-FSAR J c) , Potential Effects of Tube, Rupture The steam generator'tube rupture incident is a penetration of the barrier between the RCS and the, Hain Steam System. The integrity of this barrier is'ignificant from the standpoint of radiological safety in that a leakirig steam generator tube allows the transfer of reactor coolant into the Main Steam System. Radioactivity contained 4 in the reactor coolant would mix with water in the shell side of the

---

'--'---'* - ~ ~ "" affected steam generator. This radioactivity would be transported by steam tn the 'turbine and then to the condenser or directly to the condenser via the Steam Dump and Bypass System. Noncondensible ra'dioacti ve gases in the condenser are removed by the Main Condenser Evacuation System and discharged to the plant vent. Analysis of a steam generator tube rupture incident, assuming compLete severance of a tube, is presented in Section 15.6. 1 P

Experience with nuclear steam generators indicates that the proba-bility of complete severance of a tube is remote. The material used to fabricate the vertical U-tube is a Ni-Cr-Fe alloy. A double-ended

                                       . rupture has never occurred in a steam generator of this design.                               The' more probable modes of failure, which .result in smaller penetrations, are those involving the occurrence of pinholes or small cracks in the tubes, and of cracks in the scil we'lds between the tubes and tube sheet. Detection and control of steam generator tube leakage is described in Subsection'.2.5.

( "i \ d) Composition of Secondary FLuid and Radiological Considerations

                                                              ~ .

k

               ~
                 ~,               .  ~

Radioactivity connection in the secondary side of the steam aenerator is dependent upon the activity Level of the Reactor CooLant System, the primary to secondary Leak rate, and the operation of the Steam Generator Slowdown System. An eveluatinn of shell side radioactivity is given in Section 11.1... 'oncentration 1

                                         ,. The   recirculation water          wi thin the steam. generators contains     volatile'..

additives necessary

                                     .chemistry considerations proper   for            chemistry control. These and other
                             .'                                                  of the Hain Steam System are discussed in Subsection 10.3.5.

8,/eggkgAtlt,gent Ap,w I,1P,K'=- ~

                                            .Materials used in fabrication of the steam generator are not affected by t'e radiation levels and doses resulting from operation.                  Although
                                     ". radiation levels are significant for any internal maintenance opera-
  ."'."..'.-'".".,"'*'"'.'tions, procedures and equipment have been developed to minimize individual personnel exposure during these operations                 by allowing rapid completion of individual maintenance operations
                                                                              ~  "

5.4.2.2 Steam Generator In-service Ins ection a) Preservice and periodic inservice inspections of the steam generators will be prepared. These programs, are developed to comply with the ASHE Code, Section XI requirements as appropriate to permit examina-tions of the steam generator Code Class 1 and 2 component parts, in-cluding the steam generator tubes (refer to Subsection 5.2.4 and Section 6.6).

           ;3~

5. 4-14' v ~ ~

1 SL2.-P SAR b) The paxameters-of the preservice and inservice inspection programs comply with the guidelines recommended in Regulatory Guide 1.83, "In-service Inspection of Pressurized Hater Reactor Steam. Generator Tubes", July i@75 (Rl). c) The preservice and inservice inspection program examination method, . equipment'nd reporting requirements comply to Appendix'V of the ASME Code, Section XI. The program parameters governing the criteria used for tube inspection, tube sample sizes, inspection intervals, and acceptance criteria. (including plugging limits) are included in Techni-cal Specifications. 5.4.3 REACTOR COOLANT PIPING 5.4.3.1 ~ The reactor coolant piping is designed and analyzed for normal operation and all transients discussed in Subsection 3.9.1. Loading combinations and stress criteria associated with faulted conditions are presented in Sub-section 3.9.1. In addition, certain nozzles are subjected to local trans-ients that are included in the design and analysis of the areas affected. Thermal sleeves are installed in the surge nozzle, safety. injection noz-. zles, and charging nozzles to accommodate these additional transients. Principal parameters are listed in Table 5.4-3. The ASME Code and Addenda the piping is designed to is 'speci fied in Subsection 5'.2.1. In addition to being specified as seismic Category I, the following ad-di tional vibratory requirement is specified in the engineering speci fica-tion. The various piping assemblies are designed so that no damage to the equipment is caused by the frequency ranges of 14 to 15 Hz and 70 to 75 Hz. The frequency ranges account for mechanical vibratory excitation of coolant pump and impeller vane passing pressure variations.. the'eactor 5.4.3.2 Each of the two heat transfer loops contains five sections of pipe; one 42 inch internal diameter pipe between the reactor vessel outlet nozzle and steam generator inlet nozzle, two 30 inch'nternal diameter pipes fran the steam generator's two outlet nozzles to the two reactor coolant. -"----- pump suction nozzles, and two 30 inch internal diameter pipes from

                                                                                                      'the reactor coolant pump di scharge           nozzles       to     the   reactor    vessel      inlet      nozzles.

These pipes are referred to as the hot leg, the suction legs, and the co1d legs, respectively. The other major section of reactor coolant piping is the surge line, a 12 inch schedule 160 pipe between the p'ressurizer and the hot leg in Loop 28, and the spray line, a 4 inch Schedule 160 pipe at .the. pressurizer reduced to two 3 inch schedule 160 pipes between the 4 inch pipe and each c.'old leg in Loops 281 and 282. Arrangement of this .piping is further described in Subsection'5.1.1. 'I l, r r

                                                                                     ,r 1

I 1 1 ' ~ r

               *> r 'r                                                                              1 r                     5. 4-15 rr

St. Lucie 2 - Revised Response (9/10/81) Item 260s5a

       ~Res onsa The  analysis and reanalysis (design calculations) required by IE Bulletin 80-11 on the safety related concrete block walls   will comply with the per-tinent requirements of the FSAR operational quality assurance program. The inspection program and the reevluation programs imposed'y IE Bulletin 80-11 will ensure the safety related concrete block walls are installed properly.

The concrete block walls are considered as part of the RAB which is already indicated in Table 3.2-1.

2. ~Res onse See revised PSAR Table 3.2-1, structure (attached).

3~ ~Res onse s See revised PSAR Table 3.2-1, structure (attached). 4~ ~Res onse . See

       ~Res See revised onse revised FSAR FSAR Table 3.2-1, structure (attached).

Table 3.2-1, structure (attached).

6. ~Ras onse

     ~ See  revised  PSAR  Table 3.2-1, structure (attached).

7. ~Res onse See revised FSAR Table 3-2-l(T) (attached).

8. ~RQ5 ossa See revised FSAR Table 3.2-1(T) (attached).

9. ~Res onse See revised PSAR Table 3.2-1(T) (attached).

10. ~Res onse Item (al0) PHB Cask Handling Crane and item (a27) RAB Steel Stop Logs, sheet-pile groins, and concrete bulkheads are not to be added to Table 3.2-1. These

     . items include safety related design features to assure that no failure occurs

I ~ 1

   ~Res ones (oone1nned) that could significantly reduce the functional capability of associated safety related structures or equipment, these. items axe subject to the pertinent requirements of the PPL quality assurance program.

11. ~Res onse See revised FSAR Table 3.2-1(T) (attached) .

12. ~Res onse The. spent fuel handling system is described in items a(5) thxough a(11),

above. ~<

13. ~Res onse See revised PSAR Table 3.2-1, structure (attached).

16. ~Res ones See revised FSAR Table 3.2-1(U).

15. ~Res ones Item numbers 15 through 22 and 24 are important to .the public health and safety and therefoxe are controlled by procedures which implementation will be audited under the PPL quality assurance program., These items have testing, inspection, surveillance and audit requirements specified in the Tech. Specs.

which provides assurance that these items and activities will perform their intended functions.

16. ~Res onse See response to 260.5a.15

17. ~Res onse See response to 260.5a.l5

18. ~Res onse See response to 260.5a.15

19. ~Res ones See response to 260.5a.15 (Note: All instruments are to be stored in accordance with ANSI N45.2.2 Class B.

20.~Res anse See response to 260.5a.l5

22. '~Res onse See response to 260.5a,15 I

22. '~Res'onset See response to 260,5a.l5 23.~Res'onse See revised PSAR Table 3,201, stxuc'ture (attached) for shieldinp,

24. ~ReR ones See response to 260.5a.l5

25. onse

                                       '~Res Xtem number .25 has been    identified,      as  important to safety and,is covered by the FPL gA program.

26.Rks onse See revised PSAR Table 3.2-1(V) (attached).

27. '~Res ones See response to item 260.5a.l0.

28. '~Res'6hse See revised PSAR Table 3.2-1, structure (attached).

29.'Res 'n so These items are not added to Table 3.2-1, Xn the event of a flood,,these items will help alleviate, the excess water conditions found on si'te, however they serve no safety purpose. FPL procedures provide that proposed changes to plant systems are reviewed for their potential impact on plant safety. 30.~Res ones Xntake canal, slope is not seismically designed. Xn the case of a seismic event the intake canal slope will sluff off. Howevex, even with this reduced area, the canal will be able to provide sufficient water to the plant to preclude an event from occurring. This will not be added to Table 3.2-1, although it is subject to the pertinent surveillance requirements of the Tech. Specs. The Tech. Spec. requirements will be audited under the PPL quality assurance pxogram.

The Emergency Cooling Mater Canal Slope is seismic. The sides of this canal is reinforced with piles to preclude excess sand from slumping into the canal and disrupting the flow of water. See revised Table 3.2-1.

32. ~Res onse Intake pipes are non seismic. These pipes are not essential to the shut-down of the plant and will not be added to Table 3.2-1. This response is consistent with response a(30) above.

33. ~Res onse See revised FSAR Table 3.2-1(m) (attached) for manholes). Class 1E conduits are considered as a raceway and are covered under the Emergency Power Sys-tems (H) Ho. 12. The raceway syst: em is seismically analyzed. Cooling

   - water lines are not used on St. Lucie Unit 2 and are not    included on this table.

34. ~Res ense See revised FSAR Table 3.2-1 (attached).

Safety related instrumentation and control systems covered in FSAR sections 7.2 through 7.6 are included in the quality assurance program in accordance with note 12, Table 3.2-1. (a) The combustible gas control system is completely described in PSAR Table 3.2-1(0). All instrumentation and control systems for the components of the systems de-lineated in this table meet the criteria for siad system. (b) Refer to revised FSAR Table 3.2-1(y) (attached). (c), See revised Table 3.2-1(v) 260-5.b.2 A 5% solution of Hydrazine is stored in a horizontal tank in .5 elevation of the Reactor Auxiliary Building. A nitrogen cover gas at a nominal pressure of, 10 psig is provided by the bulk gas storage system. The storage tank is isolated from the non-safety N2 supply line by two seismically qualified Safety Class 2 check valves. The cover gas is not required for pump operability- but is provided only to prevent the breakdown of the Hydrazine solution. A safety grade pressure alarm is provided in the control room to alert operators to a drop in tank pressure. 260.5.b.3a (a) ~Res onse

   'an    Motors    They  are described completely under the heading   in Item  P (Pans) contained     in Table 3.2-1.

(b, c, d, e) ~Res onsa Demistexs, Charcoal Ahsorbers, Piltex Housings, and Heaters are all de-scribed in Table 3.2-1 item P by the description of filters. 260.5.b.4 (a) ~Res onse Raceways and their supports This is covered under Item M No. 12. The race-ways with Class lE and non-Class 1H cables axe seismically supported except in areas where it can be demonstrated that their failure would not damage any safety related systems. a (b) ~Res onse This is covered under Diesel Generator Control Boards (6) and Diesel Generator Sets (1).

{c) '~Res onsa Cable splices and connectors that are used as interface material vere pur-chased as Class lE material, non-Seismic. .The terminal blocks were pur-chased as Class 1E Seismic Catetory X. (d)~Res'onse s Valve Operators are handled under Diesel Air Start System (15), Diesel Oil day tanks, Diesel Generator Sets. (a) '~Res onse s Protective relays are covered under Diesel Generator Control Boards (6). 4 (R)~R44 onse

       ,This  is handled under safety related  480V  Switchgear, 125V  DC, 120 VAC  panels, transformers, motor control centers.

(g) ~Res ones This is covered under plant: emergency batteries and invertors (8) and safety xelated 480V svitchgear, 125V DC, 120V AC panels, transformers, motor contxol e centers.

       ~Res  on.,e See Table 3.2.1 Xtem M.12. Cables by themselves are not seismic Category" X.

The underground racevay system is designed as Seismic Category X. For <ornado wind note b is correct. For fluid group one must add a new note: all cables are qualified to operate in a wet/dry environment. 260.5.c 1~ ~Res onsa Xtem X.D.2, Plant Safety-Parameter Display Control The plant safety parameter display system is xequixed by NUREG-0695 "Functional Criteria for Energency Response Facilities", February 1981 is a non-seismic and non Class lE system (Ref. Appendix 7.5A). Hence it is not added to Table 3.2-1, although it is subject to the pertinent requirements of the FPL quality. assurance program. 2~ ~Res onse See xevi.sed FSAR Table 3.2-1(M) (attached) . 3~ ~Ras onso Xtem XX.B.2, Plant Shielding, Appendix 12.3A describes the shielding study performed using TMX source terms. No safety related structures or systems vere added that needs to be incorporated into Table 3.2-1.

e

      ~Res onse See revised  FSAR  Table 3.2-1(X) (attached).
      ~Res onse Item XL.D.3, valve position indication  As described in Subsection 7.6.3.8, acoustic valve flow monitors axe provided for pressurizer safety and power operated relief valve position indication. This valve position indication is designed per NUREG 0737 item II.D.3 requirements and is not safety grade.

Hence is is not included in Table 3,2-1, although it is subject to the per-tinent requirements of the FPL quality assurance. progxam.

6. ~Res onse This is contained in FSAR Table 3.2-1(L) (attached).

7. ~Res onse This is contained in FSAR Table 3.2.1(L) No. '4 (attached).,

8. ~Ros onse Xtem XI.E.3.1 Emergency Power for Pressurizer Heaters - As described in Appendix 1.9A item IX.E.3.1, no safety grade systems components, or struc-tures were added because of this NUREG 0737 item hence no revisions for Table 3.2-1 is necessary, although it is subject to the pertinent require-ments of the FPL quality assurance program.

9. ~Res onse Xtem II.E.4.1, Dedicated Hydrogen Penetration As described in Appendix 1.9A item II.E.4.1, no change to the existing design is required hence no revision

   '. is required to be made for Table 3. 2-1.

10. ~Res ones Xtem IX.E.4.2, Containment Isolation Dependability no safety grade system, components or structure is required to be added because of this NUREG 0737 requirements (Appendix 1.9A), hence no change to Table 3.2-1 is to be made.

      ~Res onse r

Item XX.F.1, Accident Honitoxing Instrumentation The list of instruments for this item have been added to Table 3.2-1 item Y. 12- ~Res onse A description of the instrumentation for inadequate core cooling (XCC) is pxovided in Appendix 1.98. XCC instrumentation will meet the requirements of NUREG 0737 and will be added to Table 3.2-1 when the deisgn is finalized. e

       ~Res  onse s

Item II.G.1, Power Supplies for Pressurizer Level Indicators same as above item 10.

14. ~Res onse The St. Lucie Unit 2 reactor penetration system does not include automatic trip of the RCP. Rather the pumps are tripped manually in accordance with emergency procedures established as part of the CE owners group post TMI

     'ctivities.

15. ~Res onse A safety grade supply of Component Cooling Water to Reactor Coolant Pumps Seals is not required since tests (see the response to question 410.19) have shown that the pump seals can withstand a Loss of Cooling Water for more than 50 hours without losing integrity.

16. ~Res onse This is not identified as safety related and is subject to the same require-ments as outlined for items 15 et al of 260.5a above.

17. ~Res onse Item III.A.1.2 Emergency Support Facilities NUREG 0696 does not require safety. grade instrumentation data display systems and communication systems be provided for the Emergency Support Facilities. Structures and ventilation systems are not required to be Category 1 (NUREG 0696); hence not included in Table 3.2-1, although they are subject to the pertinent requirements of the FPL quality assurance program.

168s. ~Re onse The response to item 16 is applicable to item 18, including the'equirements noted in FSAR Table 3.2-1 (21.4) 199o. '~ReS Ones Item XIX.D.3.4 Control Room Habitability - See item 10 above.

SL2-.FSAR TASLE 3.2-1 OESICII CIRSSIFIChTIOIIS OF STRUCTURES SYSTFIIS RIIO CO!IFO! IITS Tlat;RDO SEISNIC Mlttflst.'lISSjLJ FLOOD QVAI.ITY STRUCTURE CATEGORY CRITERIOttt CRITERION( CIIOIIF NOTES Shfdld Sufldfng Conte I nncnt Vessel Reactor Building interior structutcs I c Reactor Auxf)fary Building I e Dienel generator Bufldfng a Intake Structute I Fuel ltandlfng Building I a Co=ponen Cooling Area Sttucture I b Diesel Ot.l Storage Tank, Building I a Condensate Storage Tank Building I SYSTENS Attfl CONPOttgeNTS h.'eet:ot Conte~at S ~ tea X%p RV

l. Reactor i~seel Eol 2~ Reactor vessel lel S

                     . internals

3. Coritrol rod drive nechanfaua

4. Control elenent assenblies

5. Pressuriaer Stean generator a) Ptfeary sfde b c A b) Secondary side b c B

7. Reactor coolant pucp b c A

8. Piping and valves vhich arc part of RCPS A,B (1)

9. Reacfor protection instruhentatfon (2) 8 S. S~afet In eetion~S ~ tea Fl 0, 1 ~ Safety in)ectfon tanks I b .B s

SS 2. Refueling vater tank I B SU 3. Punps I b 3

4. Piping and valves (3) 0 (1) a) gart of RCPS A,B O b) Required only for initial fn]ectfon c) Required for lory tern os poet-accident cooling I a b Cl d) tthose failure vould prevent operation of portions of systen covered in (a), (b) or (c)

INSERT "A"

                                     .~

STRUCTUR SEISMIC CATEGORY IND/ MISSILE CRITERION g FLOOD ~ CRITERION. QUALITy GROUP NOTES Steel Missile Barriers (RAB, FHB, Intake Str, DGB CCt)B, Condensate Storage Tank Building) Spent Fuel Pool and Liner Spent and Hew Fuel Storage Racks Main Steam Trestle, Biological Shielding w thin the RAB and FHB Padiation Shielding Roofs of Safety-Related Structures . Class l backfill around safety related structures Spent Fuel Cask Emergency Cooling Water Canal Slope'

SL2-FSA TABLE 3.2 ni'd) TORNADO SEISMIC t'IND/MISS// FLOOD SYSTEMS AND COMPONENTS CA RCORY CRIT RIOR CRITERION

                                                                                          ** QUALITY GROUP  NOTES B. Safet        In ection    S   steeR    (Cont'd) c)     Normally isolated or autonsticclly isolated free parts of        systeTa covered by      (a), (b) or (c)                                                 (4)

5. Instrunentation (2)

C. Shutdown Coolin S stea I

l. Heat exchsngers a) Reactor coolant side b) Component cooling uater side

2. Piping and valves (3) a) Part of RCPB (1) b) Required for residual heat removal b c) Normally isolated or automatically isolated

                   , froa parts of system covered by (a) or (b)                                                           (4)

RAN I 3'natruncntation b (2) RJR D. ChccRical Volune and Control

       ~Reeeee

l. Charging pu-ps b c B 2~ Boric acid nake-up tanks . b c B 3: Boric acid pumps b c B

4. Letdown heat exchanger b c B

5. Regenerative heat exchanger b c B

6. Volme control tank b c B

l. Bo r ic ac id be t ching tank b c D 8'

8. Ion exchangers b c 90 Pulsation daapners ' c

10. Suction stabili-ers b c B

11. i P p ing and valves a) Pert of RCPB b c b) Required for letdoT> b c c) Required for post" accident injection of boric acid d} Normally or autona-tically isolated froTe parts of system covered by (a), (b) or (c) (4)

12. Instr T "en tat ion (2)

SL2"FSAR TABLE 3.2-1 'd) TORNADO SEISMIC MIND/MISS/g FLOOD

• qUALITY SYSTEMS AND COMPONENTS CATEGORY CRITERION t J GRTTERELT GROUP NOTES E. Contcianent S rc S stea

l. PucEpo b c 2~ Spray nocxlro b 3~ Piping ead valves (3) a) Required for spray and r ec irc ul at ion b) Noratelly or automati-cally ieolatrd fry parts of systea covered by (a) (4)

4. Instrmeatctioa b (2)

P. Vaete Mane eaeat S eteu

l. Rrcctor drain tank b c C 2~ Flesh teak .b c C 3~ Rr.actor drain pumps c C

4. Holdup tanks b c D

5. Spent resin tank c D

6. Flesh tank puaps I b c C

7. Cas surge tank I b c C s

8. Meetc ges cmprcosors I b c C

9. Ccs decay tanks I c C

10. Piping aad valves not (3)(4) normally or autoaatically isolated from guelity Croup C conponcnto c ll, Redictioa csonitoring tinst runra tet c

        ~

ion b

12. Flash tank gee vent trap c

13. All other lMS coloponcnto b c C, Containment Coolin S etea (6)

l. Fcn coolers I b c B 2~ Ductvork I b c B 3~ Inotrunrntctioa I b c (2)

H. Co" oncnt Coolin Voter S sten I. Pumps I b b C 2o Surge tank ,I c C 3~ Hret cxchcngers I b C

4. Piping ead valvrs a) Required for pcrforaence of safety functions

                                                                    $ 1.2"FSAR TABLE 3 '-1    (Cont'd)

TORMDO SEISMIC MIND/tlISSjl.g FUND QVAI.ITY SYSTEMS AKD COBPOSEYITS CATECORY Ciljk.R10ii CRITERION(* ) CROVP ROTES II~ Cc" onrnt Cooline later S stra (Cont'd) 4~ Piping ano valvrs (Cont'd) b) Roraally or autoaatically isolated froa parts of systea covrree by (a) (4) S Inctrvacntation b b (2) I'oolin I I ster S strac Intake cooling vater puaps b C 2~ Circulating vater puaps D 3~ Piping ana valves (3) a) Required for prrfor-aance of safety functions a,b b) Noraally or autoaat-ically isolateo froa parts of systcrL covered by (a) D - (4) 4~ Instru"entation b (2) a

   'i J~    Containaent Isolation        S  stea 1     Piping and valves (of all systras prnetzating contain-aent)                                                                                              .  (3)
    ~   .      a) Part of RCPb                                                                              A,g     (1) b)    Frca first isolation vaLve inside containarnt or froa containaent penetra tion veld to ovteraost isolation valve (if not part ot RCPB)                                                     b           c 2,    lnctrvaentation                                                   b           c                     (2)

E~ lysin Straa and Frrcvatrr S ctra 1 Piping and Valvrs froa steca generator to outeraost iso-0 lation valve b b (3) 2~ Instruarntation b b,c (2) CO

TORHADO I SE SH IC , /HISS)g FLOOD QVALITY SYSTEHS AHD COHPOHEHTS CATECORY SR!ON CP.IT R!OIIE**! CRONY R'OTCS L tv~tell r PERE~ter S ~ tto 1 ~ Puops b b 'C

2. Condensate storage tank b a C

3. Piping and valves a) not noroally or autoaati-cally isol ~ ted froa Quality Croup B coaponents (4)

I b) ReNluired for perforoancc of safety functions a

4. Instruaentation b (2)

      !'..   ~ERer     .Re    pe~er    S  ~ teo

1. Dias'rl generator sets I" b c

2. Diesel oil storage tanks I b c C

3. Diesel oil day.tanks I b c C Diesel oil transfer puops I b c C 5 Diesel 5'ta'r'ting systeos I b c C sa

6. Diesel generator control I boards b c os

7. Safety related 4.16 kv svitchgear b c 8, Plant eaergency batteries and inverters b t~ b 9~ InstruoentatlEsn 10, Safety related 480v sEEitchgears 125vdc 120vac panels, transforrwrs, rotor control centers

11. Conte lnacnt electrical pcnetrations

12. Safety systeo pover, control and instruaent cables and racevays I b c (fi)

13. Diesel Cooling Mater Systea I b c n 14. Diesel Lube Oil Systea I b C c <7)

15. Diesel Ai r St ar t Sys t es I b c c <7) 16, Diesel Air lntakc & Exhaust ~S I b c (1)

PT ll. S!Cc jriC. t'ai Huis> f'NPr C(oLtl I C~POnaHrT N. ~Salle S te 0 O 1~ Piping and valves (3) a) Part of RCPB oe b) Horaally or autoaati" oo cally isolated froa alley Croup A or B (4) coaponents 0 spl os) l 'f Ppg~iWdr- 8(cd~1 (is) 20 UHPERQHDOAO Q SLY

SL2-ts . TABLE 3.2-l (Cont'd) TORNADO SEISHIC MIND/HISS/+ P LOCO

• QUALITY SYSTEHS AND COHPONENTS CEYECORY CRKYEREOR CRITCR IOH CROUP NOTES O. Co=1 t bit C t C~ootrot E tr

l. Hydrogen reco bincrc c B 2o Conteknaent Purge Syetcn D (s) 30 Continuous Conteinacnt/Hydrogen Purge System

4. Hydrogen Sapling System c

5. pn~acfQ~~

I CO IO 0 CRY

SL2-PSAR TABlE 3.2-1 (Cont'd) SEISMIC MIND/HISS le PLOOD QUALITY SYSTE..S AND COHPOHEHTS CATEGORY CRITERIOMt*) CRITERION(* ) CROUP HOTES P<<Shield Buildin Ventilation S sten- (6)

1. Pans I B 2<< Filters I c 8 3~ Ducting and danpcrs I b c B

4. Instrunentation I b Ventilatfon S steno (6)

1. Control Roon AC and Ecergency Cleanup Syste s b 2~ ECCS brea Vencflarton Systen b 3~ Reactor Auxf liary Buildtng Mafn Supply Syoten

4. RAB Electrical Equfpcent'nd Battery Roon Ventilation Systen 5<< Diesel Cenerator Bufldfng Ventilation Syocen 6 Intake Cooling Hater Vent!1st ton Syoceu I a C

7. ~ Reaccor Cavity Coolfng System I b D 8<< Reactor Support Cooling Systcn I b D

9. CEDN Cooling System I b D

        ~  10. PHB Vent tlation Systen (portion connected to SBVS)                                              b                      C Fuel Pool Coolin     and  Purificatton  S sten

l. Coolt.ng &op i) Punps I b c C b) Heat exchanger I b c C c) Pfptng and Valves I b c C d) Inetrunencacton I b 2<< Purfftcacfon Loop a) Pun p c C b C b) Ion exchanger c) Piping and.Valves b c C d) Inotruncntatfon b (>)Q'Q) o S<< Iodine Renoval SZseca O

1<< Hydracihe punps b c B V

~

l4 2~ Hydrarinc scoragc tank b c B

                                                                                    '       c            B    (3) 3~   Piping and valves                                               b O                                                                                          c                 (2)

4. Inscrurencac ion

0 SL2 FSAR TABLE 3. 2- I (Cont ' )

TORNADO SEISMIC MIND/MISS[L$ FLOOD QUALITY SYSTEMS AND COMPONENTS CATECORY CR ITER ION

                                                                           ~* / CRITERIONS i  CROUP   NOTES
 -T. Fuel Handlin     S  stea I~  Fuel t rana f er tube'nd penetration aaa~eab]y                     I                b

2. Fuel transfer valve I b

3. Reactor vessel head lifting rig I b Containment polar crane I b RRDI AT'roe ouirovel 86 S

       ). /Pica'tT   Ag~       fÃodCV4'.S                                                    C.      (s)

2. SaFnr 6'FA.~< H>N~~< C. (s) 5 P~gRQ QD+l silPg C.

(s) (iop /5)

                                          ~

P~gQ Pe~ Josef MPAI(k+S Couk~wM tJp~~ RCccP

p. JQQ7'pcc~~ crtVM2 lppf (IS)

Qn)

0 TABLE 3.2-1 SEISMIC TORNADO WIND/ g FLOOD  %+~ QUALITY SYSTEN CATEGORY NISSILE CRITERION CRITERION CRITERION NOTES W. Reactor Coolant Gas Vent

1. Piping & Valves a) Part of RCPB b AiB b) Required for RCS Pos't Accident Venting c) Required for RCS, venting during normal operation -.

only.

2. Instrumentation .(Note 2)

                                                                                ~

6 X. Post Accident Sampling

1. Sample Storage Vessel b c (i@

2. Pumps ~ 'b c Os)

3. Piping & Valves a) Lines forming a part of H2 sampling c

                                                                                             'is) b.

All other equipment system') b c 4 -. Instrumentation b c . Os)

SYSTEN SEISMIC CATEGORY TORNADO NINDf g MISSILE CRITERION FLOOD '1

                                                                       'RITERION I QUALITY CRITERION NC'ZES Y. Post Accident Monitoring Instrumentatxon NUREG 0737 l)  Containment Pressure Monitors (wide range)

2) Containment Water (wide range) 1 Level'onitors

3) Incontainment High Range I b Radiation Monitor

4) Plant Vent Accident Range Radiation Monitor

5) ECCE'rea Ventilation 03)

System Exhaust Monitor

6) Atmospheric Steam Dump Fxhaust Monitor

TABLE 3.2-1 (Cont'd) Footnotcst a structure or cooponent is designed to withstand design vind/tornado losdings and nissile inpccts. b couponcnts housed within a structure designed to vithstand vind/tornado loadings and nissile inpacts. a " structures and coaponents designed to vithstand flooding effects. b " positioning structures and conponents at sufficient elevation to-preclude Elooding., c ~ cocponents housed vithin vaterproof structure. g: c+tc (s dcSig~~h Notes: 4o c pcroEC (u Loth mW or ofy 1, Refer to 10CPR50 Section 50.2(V) for definition oE reactor coolant pressure boundary (RCPB).' Conponents <<xcludcd by footnote 2 to Section 50.55a are Quality Croup B.

2. Instruncntation required to actuate, naintain operation of, or detect Eailure of equipment needed to safely shutdown, isolate and naintcin the reactor in a safe condition and prevent uncontrolled release of radioactivity co the environcent is ac(saic Category I. Instrunentation designated as seisaic Category I includea sensing lines, except those whose breakage vould cause thc instru=entat ion to assuage a "fail safe" posit ion. Nonscisnic sensing lines fron

      ~ eisnic Category I piping or conponent       arc seisnic Category I froa the piping connection up to cnd including the root valve. Iapulsc tubing and associated valve's are thc saae quality group as   the piping and root valve from which thc tubing commences.                 Vhen a root valve or orifice is used for a quality group brcak, thc root valve or orifice is, classified to the higher quality group class-ificat ion ~

3, Valves arc of the sane quality group as connected piping. Valves which conprisc an interface betvccn piping of different quality groups are oE the higher quality group.

4. Conponents of differing quality group other than Quality Croup A arc considered to be nornally isolated Eras each other if separated by at least one valve which's always closed during reactor operation or open during testing, sanpling or other routine operation of ahorr. duration vhich is under sdoinistrative control.

Such components are considered to be autonatically isolated iE separated by at least onc valve which closes autonatically upon cn appropriate Zngineered Safety peaturcs actuation signal or by a check valve which prevents flow frca the higher to the lover quality group.

5. 'The only portion of the Containnent Purge Systea and Continuous Containnent/Hydrogen Purge Systcn which is 0 Quality Croup B is that portion perforaing a containnent isolation function. Thc portion of ductwork located outside of the contain"ent is seisnically qualified.

6, Although this is not a stean or water containing systen, it functionally corresponds to the Quality Croup classifi-cation noted as per Regulatory Guide 1.26(R3). 4

7. Those portions of the lube oil, jacket vatcr air start, and co"bustion air intakes and exhaust systems required 430.45 for the operation of the diesel generator sets are classified seisnic Category I and Quality Croup C. See CESAR Subsections 9.5.5; 9.5.6; 9.5.7; and 9.5.8.

re~6od S~e vh>~ ~ t2.3 ~. for 4'wr~for fuge g)S~fiOW /t.S, For At'~~Pt I M fo~iv~6+~ 2CC fc Zeg~fuP~~ ~>~ Rr OC4<(S >H ~f gccidt~f HoairOPig P tea% ~ fcr ~ (0. ~7"'/'~* ' W tt?(7.4 Kcf aV /i dent<< (kscripho/) << / 'utdic 7 fg p~~;gpy$ 'egypt IL 3<<< /

                                                 <CO // 0A/d./y'ZC           ~ ~

I SL2-FSAR Table 3.2-1 (cont'd.)

12. All systems designated as quality group A, B, or C or seismic Category I are designed, constructed and operated under the pertinent requirements of the quality assurance program in Chapter 17 of this FSAR consistent with their effects upon safety.

13. Although certain systems or components are not designated quality group A, B, or C nor seismic Category 1, these items are subject to the pertinent requirements of the FPL quality assurance program.

460;2'11.2) Lisz o'utdoor'torage tanks that may contain potentially radioactive. liquid and describe provisions designed to prevent; col'lect, spills from outdoor storage tanks. It is our position and'rocess that outdoor tanks should be designed in accordance with Regulatory Position 1.2 in Regulatory Guide 1.143, Rev. l. ~Res ense: The Refueling Water Tank (RWT), Condensate Storage Tank (CST), Primary Water Storage Tank (PWST) and the Steam Generator Blowdown Monitor Tank (SGBMT) are outdoor storage tanks which could contain potentially radioactive liquid. The RWT, CST and PWST are provided with control room level indica-tion and high level alarm. The CST and PWST are also provided with local high level alarm and the SGBMT is provided local level indica-tion and high level alarm. The SGBMT overflow and drains are routed to the equipment drain tank in the Liquid Waste Management System. The CST is surrounded by the CST building so that overflow and leakage are collected in the building. 'Level, control systems will be provided for the RWT and PWST, to prevent tank overflow. FSAR Subsection 6.3.2.2.4 and 9.2.3.1.5 will be revised to incor-porate the RWT level control system and the PWST level control system. respectively. The RST and PWST level control systems will be implemented as backfit items subsequent to the plant startup but not later than the completion of the first refueling.}}