ML18085A509
| ML18085A509 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/06/1981 |
| From: | Schneider F Public Service Enterprise Group |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| TASK-1.A.2.1, TASK-TM NUDOCS 8101130322 | |
| Download: ML18085A509 (31) | |
Text
..
- Frederick W. Schneider Vice President Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/430-7373 Production January 6, 1981 Mr. Robert L. Tedesco Assistant Director for Licensing Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. c.
20555
Dear Mr. Tedesco:
STATUS OF LICENSED OPERATING PERSONNEL NOS. 1 AND 2 UNITS SALEM GENERATING STATION DOCKET NO. 50-272 AND 50-311 In reply to your letter of October 31, 1980, we are providing additional information concerning our training program to qualify degreed engineers as Senior Reactor Operator (SRO) license candi-dates.
As you are aware, a waiver of the requirement to hold an operator's license for one year would be necessary to accomplish this effort.
In order to further strengthen these SRO candidates, one additional ex-Navy nuclear trained officer has been added to the program.
The information requested follows and is numbered to match the questions in your letter.
- 1.
- 2.
The resumes of the nine individuals.in the program are en-closed.
A comparison of our previous SRO training programs with the program for these individuals is provided in the following discussion.
All post-TMI SRO candidates (to date) have been either previously licensed on Unit 1, members of the training staff, or members of management.
Those licensed on Unit 1
- participated in an overall review series with emphasis on heat transfer, fluid flow, thermodynamics, plant transients and accident analysis.
Training staff and management per-sonnel attended the program outlined above and acquired additional expertise by the preparation of lecture material, attendance at vendor sponsored training sessions, guided self-study and small group discussions and seminars with qualified members of the training staff.
- s1011s o 3~~"
Mr. R. L. Tedesco9' 2 -
1/6/81*
The standard SRO program presently under development is designed for operating personnel who have held a reactor operator's license for one year and bring detailed knowledge of plant operations with them.
The program will (1) upgrade the reactor operator's knowledge of plant operations and casualties, (2) provide additional reactor theory, heat transfer, fluid flow, and thermodynamics training, (3) in-clude simulator training and.(4) include leadership training and shift supervisory experience to enable SRO candidates to understand their role as supervisors and administrators.
A special program was developed for the license candidates addressed in this letter. is a copy of the program schedule.
It has been modified as a result of a telephone conversation between our Mr. J. _K. Lloyd, Senior Nuclear Training Supervisor, and your Mr. J. Buzy, Westing-house Section Leader (OLB), concerning operating experience.
Mr. Buzy expressed concern over the lack of shift experience following simulator training.
We were able to schedule simulator training earlier to allow additional shift time following simulator training.
Based on their educational and experience backgrounds, the program moves rapidly through theory and concentrates on plant systems, procedures, administrative programs, plant inter-relationships, transient and accident analysis, and technical specifications.
It includes an intensive classroom lecture series, system check-outs, practice walk-throughs, written examinations and study time.
There is a provision for three weeks of simulator training for each candidate.
The training is for a four-loop, Westinghouse PWR with high head* safety injection equipment and of comparable thermal power capacity to Salem.
The program consists of startup certification, recent operating incidents, the TMI accident, accident and transient analysis, mitigating core damage, and the use of Salem emergency and operating instructions.
In addition, each candidate will have three months of operating experience by April 1981, and will have been administered a written and oral audit examination, by an independent contractor, prior to the actual NRC examination.
- 3.
These degreed candidates will be utilized as Shift Super-visors-Engineer.
The Shift Supervisor-Engineer reports to the Senior Shift Supervisor (SRO), who at Salem is the highest authority on shift.
We do not intend to utilize a shift Supervisor-Engineer as a Senior Shift Supervisor until they have attained one year experience on shift.
In addition, there is a fully trained Shift Technical Advisor on each shift in accordance with the January 1, 1981 commitment.
Mr. R. L. Ted~,.sco9 3 -
1/6/81 We feel this intense training program is enhanced by the back-ground of the candidates.
Additionally, seven of the nine degreed
- SRO candidates fully meet the application requirements described in NRC Action Item I.A. 2.1 as clarified in NUREG 0737.*
One candi-date, Mr. Morrison, will have three months instead of the required six months experience at Salem.
Another candidate, Mr. Catalfomo, will have eighteen months instead of the required twq years nuclear power plant experience._ Successful licensing of these candidates will provide additional personnel necessary to minimize routine overtime.
Sincerely, Enclosure
Sept. 1 -
19 REACTOR THEORY Sept. 22 Sept. 23 Sept. 24 Sept. 25 Sept. 26 Sept. 29 Sept. 30 Oct. 1 Oct. 2 Oct. 3 S~M SHIFT SUPERVISOR -
ENGI~R W
COURSE SCHEDULE On Shift Atomic and Nuclear Structure Radioactive Decay and Nuclear Reactions Cross Sections, Flux and Reaction Rates Binding Energy and the Fission Process Neutron Travel and Sources Neutron Multiplication and Keff Reactivity, SDM and Kexcess Subcritical Multiplication Prompt and Delayed Neutron Fractions Reactor Period EXAMINATION Reactivity Coefficients Control Rod Worth Fission Product Poisons Time in Life Effects PWR Operating Characteristics ECP, l/M, and SDM Calculations Review EXAMINATION ENCLOSURE l
Oct. 6 Oct. 7 Oct. 8 Oct. 9 Oct. 10 Oct. 13 Oct. 14 Oct. 15 Oct. 16 Oct. 17 Oct. 20 Oct. 21 Oct. 22 Oct. 23 Oct. 24 Oct. 27 Oct. 28 Oct. 29 Oct. 30 Oct. 31 SYSTEMS October 6 - October 31 Reactor Coolant System Chemical and Volume Control System Chemical and Volume Control System Residual Heat Removal System Safety Injection System Component Cooling Service Water EXAMINATION Containment Systems Fuel Handling Systems Main Steam System Main Turbine and Support Systems Bleed Steam System Condenser and Condenser Air Removal System Heater Drain System Condensate System Condensate System Condensate Polishing Feedwater System Spent Fuel Pool Cooling System Circulating Water System Control Room Ventilation System Review EXAMINATION Main Generator and Support Systems Generator Exciter and Voltage Regulator Electrical Distribution System Diesel Generators and Support Systems Primary and Secondary Chemistry ENCLOSURE 1
Nov. 3 Nov. 4 Nov. 5 Nov. 6 Nov. 7 Nov. 10 Nov. 11 Nov. 12 Nov. 13 Nov. 14 Nov. 17 Nov. 18 Nov. 19 Nov. 20 Nov. 21 Nov. 24 Nov. 25 Nov. 26 Nov. 27 llllilSTRUMENTATION AND CONTROLtt "tlliWovember 3 -
November 26 Nuclear Instrumentation System HOLIDAY Radiation Monitoring System Incore Instrumentation System Review EXAMINATION Rod Control System Rod Position Indication System HOLIDAY Pressurizer Pressure and Level Control Steam Generator Water Level Control Steam Generator Feed Pump Speed Control Steam Dump Control Electro-Hydraulic Control Reactor Protection System Engineered Safety Features Actuation System Safeguards Equipment Control Instrument Failure Analysis Integrated System Response Transient and Accident Analysis Transient and Accident Analysis Review EXAMINATION HOLIDAY Nov. 28 - Jan 2 On Shift Practical Experience November 28 -
January 2
- a.
complete designated portions of qualification cards.
Jan 5 -
Feb. 27 On.Shift. Practical Experience/Simulator Training Simulator Training at Sequoyah Simulator.
The program is a 14 day Hot License Simulator Cert-ification Program.
The simulator schedule is to this overall program schedule.
ENCLOSURE -1"
Mar. 2 Mar. 3 Mar. 4 Mar. 5 Mar. 6 Mar. 9 Mar. 10 Mar. 11 Mar. 12 Mar. 13
~AT TRANSFER, FLUID FLOW tit AND CORE PARAMETERS January 5 - January 16 Thermodynamic Properties Measurement and Conversion Thermodynamics Heat Transfer Methods Heat Cycles Heat Exchangers Reactor Heat Generation Reactor Fuel Heat Transfer Reactor Power Limits Reactor Safety Limits Properties of Fluids Principles of Fluid Flow Fluid Flow Applications ENCLOSURE 1
Mar. 16 Mar. 17 Mar. 18 Mar. 19 Mar. 20
.91t.
HEALTH PHYSICS
~nuary 19 - January 23 Radiation Protection Principles Time, Distance and Shielding Problems Dose Rate Problems Radiation Detection Principles Administrative Procedure 24 Radiological Protection Program PROCEDURES January 26 - January 30 Mar. 23 Code of Federal Regulations Technical Specifications Mar. 24 Plant Overall Operating Instructions Mar. 25 Plant Emergency Instructions Mar. 26 Plant Administrative Procedures Emergency Plan Mar. 27 Review EXAMINATION Mar. 30 -
Ap. 10 On Shift Experience Ap. 13 -
Ap. 24 Ap. 27 -
May 8
- a.
Complete designated portions of qualification cards On Shift Experience/Audit Examinations
- a.
Complete designated portions of qualification cards License Course Review
- a.
Intensive review prior to NRC examination.
Concentration in weak areas, as determined by training staff.
ENCLOSURE 1
PERIOD 1-lC l-2C l-3C l-4C l-5S 2-lC 2-2C 2-3C 2-4C 2-SS 2-6S TITLE Orientation Systems Familiarization Systems Familiarization Systems Operations Systems Familiarization Systems Familiarization Theory Operations Systems Familiarization SCOPE OF INSTRUCTION Training Center Orientation Tour of Facilities Handout Material Concerning Area Reactor Coolant System Vessel and Internals Piping Reactor Coolant Pump Steam Generator Pressurizer Instrumentation and Control Systems Chemical and Volume Control Letdown and Charging Makeup and Chemical Shim Control Instrumentation Residual Heat Removal System Phase II Cooldown Mode ECCS Standby Mode Solid Plant Operations Pressurizer Bubble Formation
.Review of Previous Operations Nuclear Instrumentation Power Range Intermediate Range Source Range Auxiliary Equipment Incore Instruments Rod Control
. Mechanical Design Solid State Control Rod Position Indication Reactor Startup Theory and I/M Doubling Technique I/M Approach to Criticality Control Room Tour System Familiarization NIS Racks Incore Instruments Rod Control ATTACHMENT 1 TL"XT REFERENCE PWR Text Chapter 2.0 Observation Training Handout PWR Text Chapter 3.0 Observation Training Handout PWR Text Chapter 4.0 Observation Training Handout GOI-1 SOI-62.ID PWR Text Chapter 9.0 Observation Training Handout PWR Text Chapter 10.0 Observation Training Handout PWR Reactor Theory Handout SOI-92 SOI-94.1, TI-58 SOI-85
--1
L PERI.OD 2-7s 3-lC 3-2C 3-3C 3-4C 3-SS 4-lC 4-2C 4-3C 4-4C TITLE Operations Systems Familiarization Systems Familiarization Systems Familiarization Operations Systems Familiarization Systems Familiarization Procedure Review SCOPE OF INSTRUCTIO" Reactor Startup and Discussion of Criticality Prediction Startup Procedure Rod Withdrawal Procedure Heatup/Cooldown Reactor Trip Breaker Review of Previous Operations Feed, Auxiliary Feed and Condensate Main Feedwater System SGWLC Auxiliary Feedwater System Condensate System Steam Supply and Reheat Control Main Steam Reheat Steam MSR Controls Extraction Steam Steam Dum~ System and Control Turbine Generator Control EEC.System Mechanical Components Electronic Components Operation Reactor Startups Heatup Rate Control Moderator Temperature Effects Review of Previous Operations Electrical System A. C. Sources
- On-Site Distribution System 6.9kv 480v Reactor Protection System Reactor Trip System Permissives Interlocks Semi-Automatic Tester
. TEXT REFERrnCE GOI-2 SOI-85.lC SI-127 SI-93 PWR Text Chapter 5.0, 6.0 Observation Training Handout PWR Text Chapter 7.0 Observation Training Handout PWR Text Chapter 8.0 Observation Training Handout GOI-2
. SI-127 PWR Text Chapter 11.0 Observation Training Handout PWR Text Chapter 16.0 Review of Procedures GOI-2 Plant.Startup From Hot Standby GOI-2 to Minimum Load SOI-85 Rod Control soI-62 eves SOI-68 RCS TI-22 Shutdown Xargin Calculation ATTACHMENT 1
- soI-85 SOI-62 SOI-68 TI-22 TI-22
4-5S 5-lC 5-2C 5-3C 5-4S 6-lC 6-2C 6-3S Operations Examination Systems Familiarization Procedure Review Operations Thermodynamics Procedure
- operations Reactor Startup to Low Power Operation Feedwater Effects SGWLC Main Turbine Operation Malfunctions All Material Previously Covered Emergency Core Cooling Systems High Head Safety Injection Intermediate Head Safety Injection Low Head Safety Injection System ECCS Actuation System Fuel Handling System and Refueling Operations Components, Functions, Interlocks Basic Fuel Handling. Operation Procedure Review GOI-2 SOI-2.1 & 3.1 PWR Text Chapter 13.0 PWR Text Chapter 19.0 Observation Training Handout GOI-2 Plant Startup From Hot Standby GOI-2 to Minimum Load AOI-1 Reactor Trip Procedure AOI-2 Malfunction of Rod Control AOI-4 Malfunction of NIS Reactor Startup. to 50% power Main Turbine Operations Reactor Trip Control Return to Criticality Malfunctions Core Thermal Characteristics Lecture 1 Abnormal Operating Instruction AOI-1 AOI-2 AOI-4 GOI-2,5 Heat Transfer, Fluid Flow and Thermodynamics AOI-2 Malfunction of Rod Control AOI-2 AOI-2A Failure of Rods to Move AOI-2B Continuous Insertion AOI-2C Continuous Withdrawal AOI-2D Dropped Rod Recovery AOI-2E Full-Length Rod Misalignment AOI-2F RPI Malfunction AOI-3 Malfunction of Reactor Makeup Control AOI-5 Partial Loss of Forced Reactor Coolant Flow TI-2 Calorimetric AoI..:.3 AOI-5 Power Operation With Condition II Faults ATTACHMENT 1
\\ --
- "'ERIOD TITLE 7-lC 7-2C Theory 7-JC Thermodynamics 7-4C Procedure Review 7-SC Procedure Review 7-6S Operations 8-lC 8-2C Theory SCOPE OF INSTRUCTION Uncontrolled Rod Cluster Control Assembly Bank Withdrawal From a Subcritical Condition Uncontrolled Rod Cluster Control TEXT REFERENCE AOI-2 Assembly Bank Withdrawal at Power Rod Misalignment Partial Loss of Forced Reactor AOI-3 Coolant Flow Malfunction of Reactor Makeup AOI-5 Control Other Malfunctions Review of Previous Days Operations Natural Circulation and Enhancement Lecture I Core Thermal Characteristics Lecture II Abnormal Operating Instructions AOI-17 Loss of External Electrical Load and/or Turbine Trip AOI-16 Loss of Normal Feedwater Emergency Operating Instruction EOI-0,1 Heat Transfer, Fluid Flow, and The~modynamics AOI-17 AOI-16 EOI-5 Loss of Off-site power to the EOI-5 Station Auxiliaries (Station Blackout)
Power Operations With Condition II Faults Loss of External Electrical Load AOI-5 and/or Turbine Trip Loss of Normal Feedwater AOI-16 Loss of Off-site Power to the AOI-17 Station Auxiliaries Other Malfunctions Review of Previous Operations Reactor Theory Review Keff, Kexcess Delayed Neutron Fraction and Effects Subcritical Huliplication Reactivity Coefficients Fission Product Poisons ATTACHMENT 1 PWR Reactor Theory Handout
- ~-~... _
_.II'
'ERIOD
- -3C
- -4C
- -ss
-lC
-2C
-3C
-4C
-ss 0-lC J-2C TITLE Thermodynamics Procedure Review Operations System Review Procedure Review Procedure Review Operations Examination SCOPE OF INSTRUCTION Core Thermal Characteristics Lecture III Abnormal Operating Procedures/
Malfunction Discussion TEXT REFERENCE Heat Transfer, Fluid Flow and Thermodynamics Excessive Heat Removal Due to Feed-water System Malfunctions Excessive.Load Increase Accidental Depressurization of the Reactor Coolant System Power Operations With Condition II Faults Excessive Heat Removal Due to Feed-water System Malfunctions Excessive Load Increase Accidental Depressurization of the Reactor Coolant System Review of Previous Operations Emergency Core Cooling System Review PWR T~xt Chapter 13.0 Technical Specifications and Radiological Emergency Plan Abnormal/Emergnecy Operating Instructions Accidental Depressurization of the EOI-2 Main Steam System Spurious Operation of Safety AOI-19 Injection System at Power Power Operations With Condition II and Condition III, Faults Accidental Depressurizatiort of EOI-2 the Main Steam System Spurious Operation of Safety AOI-19 Injection System at Power Other Malfunctions All Material Previously Covered Accident Overview Accident Overview (Lecture I)
S.N.P. FSAR Small Loss of Coolant Accident Minor Secondary System Pipe Break Accident Fuel Handling/Refueling Accidents Complete Loss of Forced Reactor Coolant Flow Waste Gas Decay Tank Rupture Single RCCA Withdrawal at Full Power Three Mile Island Accident ATTACHMENT 1 PWR Text Chapter 13.0
PERIOD 10-3S 11-lC 11-ZC 11-JS 12-lC L2-2C L2-3S Operations SCOPE OF INSTRUCTI~
Power Operations With Condition III and Condition IV, Faults Loss of Reactor Coolant, From Small Ruptured Pipes or From Cracks in Large Pipes Which Actuates ECCS TEXT REFERENCE Minor Secondary System Pipe Break Inadvertant Loading of a Fuel Assembly Into an Improper Position Complete Loss of Forced Reactor Coolant Flow Waste Gas Decay Tank Rupture Single RCCA.Withdrawal at Full Power Three Mile Island Accident Other Malfunctions Review of Previous Operations Accident Overview Accident Overview (Lecture II)
Major Loss of Coolant Accident Major Secondary Steam Pipe Ruptures Operations Power Operations With Condition IV Faults Major Loss of Coolant Accident Major Secondary Pipe Ruptures
- Inside Containment Outside Containment Review of Previous Operations Accident Overview Accident Overview (Lecture III)
Steam Generator Tube Rupture Anticipated Transient Without Scram (ATWS)
Operations Fuel Handling Accident RCCA Ejection Power Operations With Condition IV Faults Steam Generator Tube Rupture Anticipated Transient Without Scram (ATWS)
Fuel Handling Accident RCCA Ejection Other Malfunctions ATTACHMENT 1 SNP FSAR EOI-0,1 EOI-0,2 SNP FSAR
. EOI-0,3 AOI-1, EOI-14 EOI-0,3 AOI-1, EOI-14 EOI-0,1
--:*,--*t
*Alt----*
-** e PERIOD TITLE 13-lC 13-2C Theory 13-3C
- Theory 13-4C Procedure Review 13-SS Operations 14-lC Theory 14-2C Current Topics 14-3S Operations 15-1 SCOPE OF INSTRUCTION TEXT REFERENCE Review of Previous Operations Reactor Theory Review Student Weak Areas Heat Transfer, Fluid Flow and Thermodynamics Review Student Weak Areas Emergency Procedure Review Reactor Startups with Malfunctions Power Operations with Malfunctions Natural Circulation and Enhancement Review and Study of Recent NRC Licensing Examinations Natural Circulation Demo. and Enhancement Cooldown on Natural Circulation Diesel Generator Operations Incore Instrument Operations Testing of Source, Intermediate and Power Range Nuclear Instruments NRG Hot License Certification Examination ATTACHMENT 1 GOI-2
PS~G Public Service Electric and Gas Company P 0. Box # 168 Hancocks Bridge. New Jersey 08038 F'...i-r..L NN-!E:
Gerald T. Slaby
.ADDRESS:
12 Oriental Avenue Pennsville, New Jersey 08070 CITIZENSHIP:
United States P..GE:
25 P~E:-7!' E:-!P!...OYER:
Public Service Electric & Gas Company PClSITICN TITLE:
Engineer EI:CC.-;.,,'i'J:CN:
Bachelor of Science -
Nuclear Science States University of New York, Maritime College -
1977 State of New Jersey Stationary Engineer, Fireman-in-charge (Black Seal)
Salem Generating Station Sep. 1980 - Present Forwarded directly to the Director of Nuclear Reactor Regulations.
Student, SRO license training program Mar. 1980 -
Sep. 1980 Served as Interim Shift Technical Advisor Apr. 1978 -
Mar. 1980 Engineer, Rx Engineering Department.
Duties included acquisition and reduction of data from movable incore flux mapping system, performance of surveillance requirements and computer progranuning.
95*2189 15MJ 10*79
'l.,1' NAME:
Gerald T. Slaby WORK EXPERIENCE (cont.):
DATE Apr. 1979 Dec. 1979 Dec. 1977 Apr. 1978 Jan. 1977 Dec. 1977 DESCRIPTION Test Engineer, Sale~ I initial tefueling.
Supervised the refueling crew performing the fuel shuffle, and participated in Phase 3 physics testing.
Maintenance Supervisor Mercer Generating Station (Fossil-fueled).
Planned and supervised corrective and preventive maintenance performed on two 300MW coal-f ired plants.
Associate Engineer, Mercer Generating Station.
Assisted Operations and Chief Engineers in special projects; familiar-ized myself with plant operation.
- ~ *..
t
~*
-~
PS~G Public Service Electric and Gas Company P 0. Box #168 Hancocks Bridge. New Jersey 08038 FULL 1'W£:
Carl Timm ADDRESS:
47 Mahoney Road Pennsville, New Jersey 08070 CITIZENSHIP:
United States AGE:
25 PRESENI' EMPIDYER: Public Service Electric & Gas Company PCSITICN TITIE:
Engineer EDUCATICN:
Bachelor of Science - Nuclear Science State University of New York - Maritime College PRESENT OR PREVIOUS LICENSE (INCI1JDm'.; SERIAL NO.):
None SPECIFIC FACILITY:
Salem Generating Station.
MEDICAL ~CN: Forwarded directly to the Director of Nuclear Reactor Regulation.
IDRK EXPERIENCE:
Aug. 1980 - Present Feb. 1980 -
Aug. 1980 Student, SRO license-training program Enrolled in Westinghouse training program for Shift Technical Advisor.
Apr. 1978 -
Feb. 1980 Engineer, Rx Engineering Department.
Duties involved fuel accountability records; perform-ing various operating surveillance procedures; performing zero power physics testing, running and reducing incore flux maps.
Tne Energy People 95*2189 l5M) 10*79
-1
~.t... : **- N1M."-m :
Car 1 Timm WORK EXPERIENCE (cont.)_:
DATE Apr. 1979 Aug. 1977 DESCRIPTION Dec. 1979 Served as a refueling supervisor auring Salem I refueling, duties involved with developing fuel shuffling procedure and supervising the refuel-ing crews.
Apr. 1978 Worked as a Associate Engineer in a fossil Gener-ating Station, duties involved in the supervision of the operating personnel.
PS~G Public Service Electric and Gas Company P.O. Box #168 Hancocks Bridge, New Jersey 08038 FtJ!.LNAME:
James Martin Ellis ADDRESS:
23 Bowfin Drive Newark, Delaware 19702 CITIZENSHIP:
United States AGE: 27 PRESENI' ~= Public Service Electric & Gas Company PCSITICN TITLE:
Engineer EI:CO...ri'1:CN:
Bachelor of Science - Marine Engineering United States Naval Academy -
1975 United States 'Navy Nuclear Program - Officer None SF::CI:'IC ~~~: Salem Generating Station MED!CU. E:Q~""ICN:
Forwarded directly to the Director of Nuclear Reactor Regulation Sep. 1980 - Present Student, SRO license training program.
Jun. 1980 - Sep. 1980 Startup Engineer assigned to Salem Unit 2 for perfor:nance of Phase 3 startup testing.
95*2189 i5MI 10*79
NAME:
James Martin Ellis WORK EXPERIENCE (cont.):
DATE Apr. 1977 - Jun. 1980 DESCRIPTION U.S. Nuclear Submarine Program, u:s.s. George E.
Marshall, SSBN 654.
Served in various assign-ments involving propulsion plant operation, including:
Interior Communications Officer, Main Propulsion Assistant, Quality Assurance Officer, and Damage Control Assistant.
Qualified Engineer.
PS~G Public Service Electric and Gas Company P.O. Box #168 Hancocks Bridge. New Jersey 08038
~
~= Richa=d J. Newman ADCRES=:
R. D.
~ 1, Box 2 3 9 Centerton - Porchtown Road Elmer, N.J.
08318 C!TIZENSEIP:
United States
-~: 28 P~i'!' D1P!..t..,-~:
Public Service Electric & Gas Company
?:S...L:o::l.CN ~: Engineer
!:CC"..,!!'!CN:
Bachelor of Science - Marine Engineering State University of New York Maritime College -
1974 State of New Jersey Stationary Engineer's License, Third Class (Blue Seal) s.:-~~-: :?-..c::I..J..~:
Salem Genera~ing Station
.!'S!O.:..;:G.i..~..TICN:
Forwarded directly to t.."'le Director of N~clear Reactor Regulation 1980 - P=esent Student, SRO license t=ai~ing prog=am.
1979 -
Sep. 1980 Senior Operations St~!f Supe=visor, Salem G
.,..-=
~ '""I 1,, ~
~
ene_ -ting Sta... ion.
P.espons... bili._ies..... c_.. ce...
writing LER's, reviewi~g plant design c~anges for their effect on Operating procedures,
- .vriting special test procedures, and assisting Operating Engineer ~ith Shi=t t=ai~ing require."tlen ts.
95-2189 15MI 10*79
NAME:
Richard J. Newman WORK EXPERIENCE (cont. ) :
DATE Feb. 1979 - Aug. 1979 Mar. 1978 - Feb. 1979 Aug. 1977 - Mar. 1978
-Jun. 1975 - Aug. 1977 Aug. 1974 - Feb. 1975 DESCRIPTION Assistant (Unlicensed) Shift Supervisor, Salem Generating Station. Assistea the licensed (SRO} shift supervisor in the day-to-day operations of plant, including the refueling mode.
Test Engineer, Salem 2 initial startup.
Participated in Phase 1 & 2 testing, including systems turnover from the vendor and the writing of necessary startup procedures.
Maintenance Supervisor, Linden Generating Station (fossil-fueled).
Responsible for the maintenance and repair of various plant equipment.
Operations Supervisor, Linden Generating Station.
- Responsible for all aspects of operation of two 275 MW oil-fired units.
Operations & Test Engineer, Seatrain Shipbuild~
ing Corp., Brooklyn Naval Shipyard.
Responsible for ensuring proper installation and start-up of propulsion plant equipment.
Partic-ipated in sea trials as a shift engineer.
c PS~G Public Service Electric and Gas Company P. 0. Box #168 Hancocks Bridge, New Jersey 08038 FOLL 'tWm: William 0' Brien
- ADDRESS:
26 Lake View Avenue Pennsville, N.J.
08070 CITIZENSHIP: United States AGE:
25 PRESnn' EMPIDYER:
Public Service ELectric & Gas PCSITICN TITLE:
Engineer EIXJCATICN:
Bachelor Science -
Nuclear Science State University New York Maritime College -
1977 PRE.SENT OR PREVIOOS LICENSE (INCUJDTIX; SERIAL NO.):
None SPECIFIC FACILITY: Salem Generating Station MEDICAL EXAMINATICN: Forwarded directly to the Director of Nuclear Reactor Regulation IDRK.EXP.ERIENCE:
DATE Sept. 1980 - Present March -
Sept. 1980 Oct. 1978 -
March 1980 The Energy Peop!r.=*
DESCP.IPTICN Student, SRO license training program Served as Interim Shift Technical Advisor Engineer, Rx Engineering Department.
Duties involved fuel accountability records; perform-ing various operating surveillance procedures; performing zero power physics testing, running and reducing incdre flux maps.
95-2189 15Mi 10*79
NAME:
William O' ~rien WORK EXPERIENCEcont.):
DATE April - *oec. 1979 Dec. 1977 -
Oct. 1978 DESCRIPTION Test Engineer, Salem 1 initial refueling.
Duties mainly involved developing fuel shuffle procedures, and supervising the refueling crew performing the fuel shuffle.
Served as Test Engineer for the Post Refueling zero power physics testing program.
Nuclear Engineer at Charle~ton Naval Shipyar~
Responsible for many facets of the Radiological Controls discipline.
- .1.*
PS~G Public Service Electric and Gas Company P.O. Box #168 Hancocks Bridge. New Jersey 08038 FOLL NAME:
Lee. A. Catalfomo ADDRESS:
42 Klessel Avenue Pennsville, New Jersey 08070 CITIZENSHIP:
United States AGE: 29 PRESENT EMPLOYER:
Public Service Electric & Gas Company PCSITICN TITLE:
Engineer EI:XJCATICN:
Bachelor of Science -
Marine Engineering State University of New York Maritime College -
1973 P~"'T OR PREVIOOS LICENSE (INCLUD~ SERIAL NO.):
State of New Jersey Stationary Engineer's License, Second Class (Red Seal)
SPECIFIC FACILITY:
Salem Generating Station MEDICAL EX1>.MINATICN:
Forwarded directly to the Director of Nuclear Reactor Regulation IDRK. EXPERIENCE:
Sep. 1980 - Present Mar. 1980 -
Sep. 1980 Student, SRO license-training program.
Interim Shift Technical Advisor, Salem Generating Station.
95-2189 (5MI 10*7~
I!
-.,J NAME: Lee A. Catalfomo WORK EXPERIENCE (cont. ) :*
DATE Jun. 1979 -
Mar. 1980 Jun. 1977 -
Jun. 1979 Nov. 1975 -
Jun. 1977 Jul. 1975 -
Nov. 1975 Jun. 1973 - Jul. 1975 DESCRIPTION Lead Engineer, Operations Department, Salem Generating Station.
Responsible for writing various Operating and Surveillance procedures, reviewing plant design changes to determine their effects on these procedures, and the development of a system to computerize valve lineup information.
Technical Supervisor, Mercer Generating Station (Fossil-fuel).
Responsible for operation and maintenance of Instrumentation & Control systems, and the supervision of bargaining unit employees.
Shift Supervisor, Mercer Generating Station.
Responsible for the proper operation of two 300MW coal-fired steam units.
Associate Engineer, Mercer Generating Station.
Assisted Operating Supervisor in the perform-ance of his daily projects; familiarized my-self with the plant.
Nuclear Licensing Engineer, Ebasco Services Inc., N.Y.~ Prepared Safety Analysis Reports, provided accident analysis reviews, and inter-related with the NRC and the Advisory Committee on Reactor Safegaurds (ACRS).
- .I PS~G Public Service Electric and Gas Company P.O. Box #168 Hancocks Bridge, New Jersey 08038 12 Mansfield Av~nue FULL ~"!E
.John.Wayne Morrison ADDRESS:
East Brunswick, New Jersey 08816 United States AGE:
2 7 P~
~I.OYER: Public Service Electric and Gas Company PC6ITICN TITLE:
Engineer EI:CO.TIC'N:
Bachelor of Science -
Mechanic al Engine er in g Cornell University -
1975 United States Navy Nuclear Program -
Officer None
~.:..c:='!C ~"""TY: Salem Generating Station MEJICAL =:x;.~..TICN:
Forwarded directly to the Director of Nuclear Reactor Regulation Oct. 1980 Jan. 1977 Present Student, SRO license training program Oct. 1980 U.S. Navy Nuclear Submarine Program, U.S.S. Jack, SSN 605.
Served in various assignments involving propulsion plant operation, including'.
Interior Communi-cation Officer, Electrical Division Offi-cer, Reactor Controls niv~£ion Officer, and Chel!listry & Radiological Assistant.
95-2189 (5M) 10-79
J...
PS~G Public Service Electric and Gas Company P. 0. Box #168 Hancocks Bridge. New Jersey 08038 FtJU. w..ME: Vincent J. Polizzi ADDRESS:
202 Franklin Court Mullica Hill, New Jersey 08062 CITIZENSHIP:
United States AGE:
27 PFESENI' EMPI.DYER:
Public Service Electric and Gas Company PCSITIOO TITLE:
Enq ineer
- e:IXJCATICN:
Bachelor Science - Mechanical Engineering Villanova University -
1975 United States Navy Nuclear Program - Officer PRE.S:Em' OR PREVICOS LICENSE (INCT11Dm3 SERIAL NO. ) :
None SPECIFIC FACILITY: Salem Generating Station MEDICAL EXA~CN: Forwarded directly to the Director of Nuclear Reactor Regulation IDF!< EXPERIENCE:
DATE Sen. 1980 Present Jun. 1980 Sep. 1980 Aug. 1976
,Juin. 1980 The Energy Peopii:-
Student, SRO license training program.
Startup Engineer assigned to Salem Unit 2 for performance of Phase 3 startup testing.
U.S. Navy Nucle2r Submarine Program: u.s.s.
Ulysses S. Grant, SSBN 631.
Served in vari-ous assignments involving nropulsion plant ooeration, including:
Interior communications Officer, Damage Control Assistant, Radiological Controls & Chemistry Officer, and Main Pro-pulsion Assistant.
95-2189 (5MI 10*79
( ** PS~G Public Service Electric and Gas Company P. 0. Box #168 Hancocks Bridge, New Jersey 08038 FOLL NAME:
Louis F. Lake ADDRESS:
R. D. # 3, Box 269A Birch Lane Woodstown, New Jersey 08098 CITIZENSHIP:
United States AGE:
35 PRESnn' EMPI.DYER:
Public Service Electric & Gas Company POSITICN ~: Engineer EJ:CCATICN:
Bachelor of Science - Mechanical Engineering Technology Fairleigh Dickinson University PRESENT OR PREVICUS LICENSE (INCUJDJN; SERIAL NO.):
None SPECIFIC FACILITY:
Salem Generating Station MED!OU. ~CN: Forwarded directly to the Director of Nuclear Reactor Regulation Sep. 1980 - Present Aug~ 1978 -
Sep. 1980 Student, SRO license training program.
In-Service Inspection (ISI) Engineer, Salem Generating Station.
Responsible for plan-ning, co-ordinating, and supervising the ISI program on safety related pumps and valves.
The Energy People 95-2189 i5MI 10-79
,..:J-I
)**,'
NAME:
Louis F. Lake WORK EXPERIENCE (cont.):
DATE Sep. 1974 -
Aug. 1978
- DESCRIPTION Engineer, Engineering' & Construction Department, Salem Generating Station.
Responsible for the Preservi~e Inspection program ori initial instal-lation equipment.