ML20195J953
| ML20195J953 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 11/28/1988 |
| From: | Gallo R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Corbin McNeil PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 8812050098 | |
| Download: ML20195J953 (39) | |
Text
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NY 2 81988 Docket No. 50-352 Philadelphia Electric Company ATTN: Mr. C. A. McNeill 1
Executive Vice President i
Nuclear Correspondence Control Desk P.O. Box 7520 Philadelphia, PA 19101 Gentlemen:
Subject:
Licensee Requested Meeting Concerning Limerick Unit 1 fuel Handlers c
License l
This letter transmits the NRC report of the meeting hele on November 2, 1988 in the Region I office, King of Prussia, Pennsylvania. This meeting was i
requested to discuss the plan and schedule for Limited Senior Reactor Operator (LSRO) license examinations for the fuel handler candidates at Limerick Unit 1 to oe administrated on January 3-5, 1989.
No reply to this letter is required.
Thank you for your cooperation.
j Sincercly, em u.aue i
Robert M. Gallo, Chief i
Operations Branch Division of Reactor Safety
[
Enclosure and Attachments 1 and 2 cc w/ encl. and Attachments 1 and 2:
John S. Kemper, Sr., Senior Vice President - Nuclear 4
E. C. Kistner, Chafrman, Nuclear Review Board Graham M. Leitch, Vice President, Limerick Generating Station J. W. Gallagher, Vice President - Nuclear Troy B. Conner, Jr., Esquire Eugene J. Bradley, Esquire, Assistant General Counsel W. M. Alden. Director, Licensing Section Public Document Room (POR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector Commonwealth of Pennsylvania Y.
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OFFICIAL RECORD COPY LIM 1 FUEL HANDLERS - 0001.0.0 11/10/88 GG12050098 68112G PDR ADOCK 030003'32 V
r-o Philadelphia Electric Company 2
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bec w/ encl. and Attachments 1 and 2 i
Region I Docket Room (with concurrences)
Management Assistant, ORMA (w/o encl)
Section Chief, DRP Robert J. Sores, DRSS i
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4 U.S. NUCLEAR REGULATORY COMMISSION REGION I MEETING
SUMMARY
Docket No.
50-352 License No. NPF-39 Licensee:
Philadelphia Electric Company.
ATTN: Mr. C. A. McNeill Executive Vice President Nuclear Correspondence Control Desk P.O. Box 7520 Philadelphia, PA 19101 Facility Name:
Limerick Generating Station, Unit 1 Meeting at:
NRC Region I Office, King of Prussia, PA Meeting Date: November 2, 1988 1.
Introduction The meeting requested by the facility licensee discussed the plan and schedule for the Limited Senior Reactor Operator (LSR0) license examinations for fuel handler candidates at Limerick 1 to be given on January 3-5, 1989.
2.
Meeting Attendees 1.1 Nuclear Regulatory Commission (NRC)
T. Fish, Operations Engineer A. Howe, Sr. Operations Engineer D. Lange, Chief, BWR Section S. Pullani, Sr. Operations Engineer 1.2 Philadelphia Electric Company (PECO)
W. Barnshaw, Schedule / Qualifications Administrator i
J. Doering, Superintendent - Operations E. Firth, Superintendent - Training 3.
Purpose of Meeting The purpose of the meeting was to discuss the plan and schedule for the LSR0 license examinations to be administered to the Limerick 1 fuel handler candidates on January 3-5, 1939.
(See Attacht.ent 1 for details of Agenda).
2 4.
Licensee Presentation The licensee presented the detailed plan for the examination including the proposed trainino I,rogram, reference material requirement for the preparation of the f.'4 written and walk-through examinations, qualification and '4perience of the candidates, administrative requirements for.ne interface between the fuel handlers (5 General Electric employ' es) and the PECO Operations group and proposed examination date.
The de$ ils of the plan are presented in Attachment 2.
This was followed by a discussion session which arrived at the following conclusion' 5.
Conclusions a.
The written examination is to be given on January 3,1989 and the operating test (oral / plant walk-through to be given on January 4 and 5, 1989.
b.
The examination; and the LSR0 licenses will be for Unit 1 only.
To extend the licenses to Unit 2, they must be amended later after satisfying all the requirements, c.
The scope of the training reference material was developed after performing a Job Task Analysis (JTA) specific to the fuel handlers job requirements and identifying the associated Knowledge / Abilities (K/A). The training material will also meet the requirements for the preparation of NRC examinations.
The licensee presented a set of the reference material to the NRC at the meeting.
The licensee stated that the material presented generally satisfies the above criteria.
However, they will further review it to include any additional material (for e.g., E0P for fuel handling accident, inadve* tent criticality, loss of fuel pool level, additional Administrative Procedures for shif t rotation, interface with PECO operations, etc.).
d.
The written examination will be approximately 4-6 hours duration and the operating tests about 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
e.
Access to the refueling floor and refueling bridge will be necessary to conduct the operating examinations. Those control room systems and in plant systems, associated with refueling operations, will also be evaluated during the operating examinations, f.
The candidates' applications, including medical certificates are to be received in Region I by December 16, 1988.
ll A*TTAC H ME tJ T 1
f SRO LIMITED LICENSE (REFUEL FLOOR) MEETING FOR LIMERICK GENERATING STATION Time:
1330 - 1500 location: NRC Region I Headquarters Date: November 2, 1988 EtENDA o
Participant introduction and Involvement in Process (NRC/PECo) o Brief discussion cf NRC Sf SRO Limited Licensing Process and recent af fort to examine PBAPS Refuel Floor SRO's (NRC) o LGS Analysis of Training Required / Proposed Training Program by LGS to prepare candidates (PEco) o Reference Material for NRC use (PECo) o Brief discussion of proposed General Electric Company SR0 Candidates dnd their qualificatiors (PECo) o Administrative Requirements for meshing General Electric's SRO's on Refuel Floor together with PECo's Operations Group (PECo) o Proposed Examination Date and HRC Examination Layout for that week (HRC) o Question and Answers for clarification (NRC/PECo) i Proposed Attendees:
PECo(LGS)
NRC J. Doering (OPS Superintendent)
R. Gallo L.Hopkins(Asst.OPSSuperintencent)
O. Lange E. Firth (Superintendent-Training)
- 5. Pu11ani W. Barnshaw (SR0/Ex-Superintendent)
A TTA CHMErJ T 2_
h PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION LIMITED SENIOR REACTOR OPEEATOR PROGRAM DESCRIPTION I.
INTROPUCTION Routine tasks performed by the Senior Reactor Operator (SRO) were identified and verified by subject matter experts, and provide the basis for the NRC Lice:
Training Program. Refueling tasks were selected from the SRO Task Analysis and were used to design and develop the training curriculum (See Attachment A).
Upon completion of this training program, the operator will be able to perform the required evaluations safely and efficiently, and the plant will be operated without danger to personnel or equipment.
Academic craining will provide the theoretical knowledge base required to enable the operator to understand and respond to tasks associated with abnormal conditions.
Since all abnormal conditions cannot be accurately predicted, the operator must rely on his/her theoretical knowledge base to recognite and diagnose the abnormal or emergency condition, and take steps necessary to mitigate the event.
II.
GOALS /0BJECTIVES The goals of this program are to prepare the operator to perform the following duties and responsibilities:
A.
Shall be responsible for ensuring that all procedures being used for core alterations are being complied with.
B.
Shall supervise the proper completion of all Core Component Trans-fer Authoritation Sheets, t
C.
Shall direct and supervise the Health Physi;s qualified personnel in the absence of the Health Physics supervision.
D.
Shall direct and supervise all operators assigned to the refuel floor.
E.
Shall determir.e the proper correceive action and direct the fuel handling crew should an abnormal event. or an abnormal instrument response occur.
P.
Shall be responsible for the completion of the Refueling platform I
and SRM core monitoring check list prior to initial fuel handling and as early as practical on subsequent shifts.
C.
Shall be responsible for review of the prerequisites to the Puel j
Movecent and Core Alteration procedure to assure that all pre.
requisites are cet during core alterations, H.
Shall be responsible for completion of the Daily SRM Operability Test.
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Shall be responsible for completion of the k'eekly Refueling Interlock Function Test.
J.
Shall direct the updating of the fuel pool and recctor tag boards.
The objectives of this program is to qualify participants to perform the tasks identified for the Limited Senior Reactor Operator (LSRO) position.
III. PREREQUISITES A.
Candidates should be badged at Limerick Generating Station.
E.
Candidates shall have successfully completed a SRO Certification Program.
C.
Candidates shall have successfully completed a Refueling Floor Technical Director / Coordinator course (See Attachment B).
IV.
LISTIt'G OF COURv2S s
A.
Theory (Attachment C) e B.
Systems (Attachment D)
C.
Proceaures (Attachment E)
C.
Techt.ical Specifications (Attachment F)
E.
Refueling Floor Technical Director / Coordinator Refresher Lab (Attachment G)
F.
Refueling Floor O.J.T.
(Attachment H)
Y.
TRAlt;I!;G SCHEDULE (ATTACHME!;T I)
ATTACHMENT A LCS CROSS REFERENCE HATRIX FOR LIMITED SENIOR REACTOR OPERATOR
- 2010030203 CONDUCT REFUELING INTERLOCKS FUNCTIONAL TEST / CONTROL ROD DRIVE MAINTENANCE TEST (SUPERVISE) [ DIAGNOSTIC)
FH 105 ST-6 107-630 1 RT 3-097 402 0 LSR 0760 LSR-1573
- 2010120203 REPLACE A CONTROL ROD DRIVE BLADE (SUPERVISE)
FH 301 ST 6 107 632 1 LSR 0760 LSR 0060 LSR 11]l
- 2340010203 PERFORM ROUTINE BRIDGE AND GRAPPLE CHECKS (SUPERVISE)
[ DIAGNOSTIC)
RT 3 097 402 0
- 2340020203 VERIFY CORRECT CORE CONFIGURATION [ DIAGNOSTIC)
LSR 0020 LSR 0760
- 23400?0103 OPERATE THE REFUELING MACHINE / MAIN FUEL HANDLING BRIDGE (SUPERVISE) l FH 105 597.0.A LSR 0760 597,0.L 597,0.C 597.0.D S97.0 E S97.0.F
$97,0.G
- 2340070103 OPERATE THE AUXILIARY FUEL HANDLING BRIDGE MANIPULATING CRANE (SUPERVISE)
SG7.0.B LSR 0760
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- 3410290303 SUPERVISE REF1]ELING OPERATIONS AS FUEL HANDLING DIRECTOR FH 101 FH 220
$97 SERIES ALL LSR 1570 FH 102 FH 230 RT 3 097 LO2 0 LSR 0760 FH-103 FH 240 FH 104 FH 270 FH 105 FH 301 TH 106 FH 340 FH 205 FH 605 FH 210 FH 606 FH 211
- 3410480103 CONDUCT REFUELING SHIFT SUPERVISOR SHIFT TURNOVER A7 LSR 1570 LSR 0760
.)
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ATTACHMENT "B" REFUELING FLOOR TECHNICAL DIRECTOR / COORDINATOR - 8905 GOALS:
Provide the training, skills, and knowledge necessary to personnel involved in the monitoring, directing, and coordinating of refueling floor outage preparations and outage activities.
The disciplines covered in this course include SUPERVISOR, RAD CON, SCHEDULING, QA/QC, AND i
OPERATIONS.
l DESCRIPTION:
The course consists of classroom instruction and hands-on i
training in the operation, inspection and general mainten-ance of the refueling floor equipment.
Students will also become familiar with outage planning techniques, technical specifications, refueling systems, procedures, QA/QC requirements, and radiation and safety precautions pertaining to refueling floor operations, j
f),
PRESENTATION:
The course is taught by GE instructors using conventional classrcom techniques.
The course will also consist of instruction and hands-on training on product line ecuienn:
en the refueling floor at the BWR Services Training Facility, if the courte is delivered in San Jose.
PREREQUISITES:
Tnere are no formaf prerequisites for enrollment in this course.
LOCATION:
This course is taugnt at the BWR Services Training Facility in San Jose, California, or at the custemer site.
CLASS SIZE:
It is recemended that class si:e be limited to 4-6 students, although 10 students are pemissible in the on-site course since it is primarily lecture.
COURSE LENGTH:
The course is three weeks in length for San Jose delivery and two weeks in length for on-site delivery.
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i ATTACHMEtiT "B" 1
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REFUELING FLOOR TECHNICAL DIRECTOR / COORDINATOR - 8905 (Contd)
OBJECTIVES:
Students successfully completing this course will be able l
to:
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Outline and state the importance of the cutage l
pre-planning activities, j
o Given an outage schedule, locate 2nd correct any errors in 1) tne sequence affecting critical path time and/or logic constraints. 2) the minimum manpower requirements, and 3) the interrelationship with other j
l plant outa ) activitits.
l Identify refueling tools and equipment from sketches o
or photos, briefly state their function and how they i
are used, and if there are any maintenance j
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requirements.
State radiation precautions and actions to be adhered 4
o to during various maintenance or refueling operations.
f o
Discuss refueling interlocks and identify and correct typical malfua.ctions with the refueling platform.
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State whether Tech Specs ave being violated for a o
i given set of plant con (itions.
A o
Discuss methods and/or techniques used to prevent entry of foreign cbjects into the RPV and pools.
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OUTLINE:
Orientation and Facility Tout-RPV and Internals Refuel Floor Description and Arrangement Refueling Systems Planning and Scheduling
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Servicing Aids i
Fuel Service Equipment Vessel Servicing Equipment f
Reactor Vessel Disassembly Jet Pump Servicing a
In Vessel Servicing touipment
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Refuel Platform Orientation
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RERELING FLOOR TECHNICAL 0IRECTOR/ COORDINATOR - 8905 (Contd) f l
OUTLINE:
Each subject area listed above will include the following*
(Contd) j o
Description of system, tool or component o
Procedures used for operation or handling of the equipment including the following:
l Radiation precautions 0A/QC requirements if applicable l
f Tech Spec requirements I
o Hands-on training and manipulation for familiarity with equipment rather than proficiency.
(San Jose delivery only.)
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's ATTACHMENT "C" THEORY The following THEORY subject matter will be addressed in a classroom training environment I.
LOT 0860, Fisson Process II.
LOT 0670, Characteristics of Fisson III.
LOT 0900, Neutron Cycle and Neutron Balance IV.
LOT.0930, Effective Multiplication Factor V.
LOT.0940, Reactivity VI.
LOT 0950, Excess Reactivity and Shutdown Margin VII.
LOT 0960, Neutron Source VIII.
LOT 0970, Suberitical Multiplication IX.
LOT 0980, Count Rate Comparison X.
LOT 1450, Moderator Temperature Coefficient XI.
LOT 1490, Control Rod b'arth XII.
LSR 15BO, BWR Accident /.nalysis XIII.
LOT 1705. Health Physics Principles J
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ATTACRMENT "D" SYSTEMS 1.
The Systems Course vill be administered in the following three (3) separate training environments where applicable:
1.
Classroom 2.
Plant Tours of Limerick Generating Station 3.
On The Job Training (0.J.T.) at G.E. BVR Services Training Facility in San Jose, California, and Limerick Generating Station II.
The following list of systems will be addressed in this course A.
LSR 0010, Reactor Vessel and Internals B.
LSR 0020, Nuclear Fuel and Control Rods C.
LSR 0060, Control Rod Drive Mechanism
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D.
LSR 0070, Control Rod Drive Hydraulics E.
LSR 0110, Reactor Vater Cleanup F.
LSR 0130 Primary Containment G.
LSR 0190, Secondary contaiteent a
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H.
LSR 0200 Reactor Enclosure Ventilation I.
LSR 024r tource Range Monitor J.
LSR 030
.seactor Protection System K.
LSR 037:
Residual Heau Removal L.
LSR 0400, Residual Heat Removal Service Water M.
LSR 0480, Condensate and Refueling Water Storage N.
LSR 0520, Condensate System of Demineralization 0.
LSR 0640, Main and Aexiliary Power Distribution P.
LSR 0650, 4Sv and 120 VAC Powcr Distribution Q.
LSR 0710. Area Radiacien Mor.itoring R.
LSk-0720, Process Radir, tion Monitoring i
S.
ISR 0733. Fire Protection Systems T.
LSR.0750, Tuel Pool Cooling and Cleanup U.
LSR 0760, Refueling and Refueling Equipment i
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ATTACHMENT "E" t
l PROCEDURES l
J The procedures listed below will be addressed in the following training l
environment as applicable:
1.
"Classroom j
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Refueling Floor Technical Director / Coordinator Refresher Lab i
3.
Refueling Floor 0.J.T. at Limerick Generating Station I
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ADMINISTRATION l
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4 A.
A 7 Shift Operationc l
B.
A 8, Locked Valdes l
C.
A 12, Ignition Source Control
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A 13, Reporting Defects and Non Coapliance l'
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A 30, Plant Housekeeping
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A 31, Notification of the NRC i
G.
A 41, Control of Safety Related Equipment j
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A 42, Control of Temporary Circuit Alteration i
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A 44, Special Nuclear Material Accounting l
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A 90, Control of Heavy Loads t
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A 95, Operator Aids I
II.
FUEL HANDLING A.
TH 101, Receipt of New Soiling Vater Reactor Fuel B.
TH 102 h ansfer of New Fuel from New Fuel Storage Area to R9 fuel
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C.
TH 103 Uncrating and Unpacking of f.ev Fuel on the Refueling Floor i
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TH 104, Preparation and Shipeen of Empty Fuel Boxes l
E.
FH 105, Core Component Movement Core Transfers F.
TH 106. Core Coeponent and I; radiated Item Movement Ne Core i
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TH 201, New Fuel Inspection. Channeling and Pincer.e.'t: in the Fuel l
I Pool i
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TH 210, New Channel Cleaning and Inspection I.
TH 211, New Channel Fastner Inspettien j
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TH 220, Preparation and Inspection of New Control Reds l
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TH 230. Preparation and Inspection of New Control Rod Guide Tubes I
L.
TH 240. Inspection of New Fuel Support Tiece I
M.
TH 270, Blade Guide Preparation N.
TH 301. Transfer of New control Rods to the Fuel Pool O.
TH 340 Removal / Installation of Local Power Range Monitors t
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TH 605, Core Component Transfer Authori:at!on Sheet Ir.s t ruc tions f
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TH 606, Instructions for Refuel Floor Air *.ock Access I
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!II. FDUTINE TEST J'
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A.
RT 3 097 402 0 Checkout of Refueling Platfore Bridge, Trolley, l
i Monorail in Fuel pool B.
RT 6 097 410 0, Daily Refueling Platform Checkout i
1 4
2 IV.
SURVEILLANCE TEST A.
ST 6107 591 1, Daily Surveillance Log OPCONS 4 & 5, B.
ST 6 107 630 1, Core Alteration Testing for Offloading, Shuffling and Reloading the Core
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C.
ST 6 107 632 1, One Rod Out Interlock Verification Testing V.
SYSTEMS A.
S53.4.A. Draining Reactor Well and Dryer / Separator Storage Pool i
B.
S97.1.A. Electrical and Pneumatic Ali nment of Refueling Platform 5
j Bridge, Trolley and Main Hoist for Operations j
C.
S97.0.A. Operation of the Refuelin6 Platforn Bridge Trolley and Main Hoist l
D.
S97.0.B. Operation of the Refueling Platform Auxilliary Hoists I
E.
S97.0.C, Transfer of Fuel from the Fuel Pool to the Reactor J
F.
S97.0 D, Transfer of Fuel from the Reactor to the Fuel Fool C.
SC7.0.E, Transfer of Fuel within the Reactor H.
S97.0.F. Transfer of Blade Guides from Reactor to the Fuel Pool j
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S97.0.C, Transfer of Blade Guides from the Fuel Pool to the Reactor 4
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S97.0.H. General Handling of Core Component and Irradiated Items in
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the Fuel Fool / Cask Pool i
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S97.0.J. Transfer of Blade Guides within the Reactor
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1]f4Il}i ?HY$IfGji 9
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HP 102, Adrinistrativ: Dose Limits, Dose Extensions and Notification P.equirements 7
j B.
HP 109, High Radiation Area Key Control C.
HP 215. Establishing and Posting Controlled Areas D.
HP 310, Radiatic-n Vork Permits F.
HP 817, Personnel Contamination Monitoring VII. GENEFAL A.
CP 6.1, Shutdown Operations Refueling, Core Alterations and Core Off Loadin:
B.
CP 6.2, Shutdown Operations Shutdown condition Tech. Spec.
Action-C.
CP 9(III), Refuel Area Secondary Containnent Integrity (Zone I.I)
On 111, Loss of Secondary Containnent IX.
IMERGENCY A.
IP 101, Classification of Energencies
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X.
The less'en plans listed below will be addressed in a classroom environment A.
LSR 1520. Emergency Plan and Procedures B.,
.LSR 1530, General Prc-:edures.
C.
LSR 1550, Off Normal Procedures 3
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LSR 1570, Administrative Procedures E.
LSR 1573, Surveillance Test Procedures F.
LOT 1760 Health Physics Procedures G.
LSR 1860, Permits and Blocking 9
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ATTACHMENT "F"
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TECHNICAL SPECIFICATIONS The lesson plans and associated TECHNICAL SPECIFICATIONS listed below will be addressed in the following training environments as applicable:
1.
Classroom 2.
Refueling Floor Technical Director / Coordinator Refresher Lab 3.
Refueling Fluor 0.J.T. of Limerick Generating Station I.
LSR 1800. Introduction to Technical Specifications l
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LSR 1810, Technical Specifications Definitions III. LSR 1820. Tech. Spec. Safety Limits and Bases IV.
LSR 1830. Tech. Spec. LSSS and Bases i
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V.
LSR 1840, Tech. Spec. LCOs and Bases 4
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LSR 1850, Tech. Spec. Administrative Control
, i VII. LSR 1855. Tech. Spec. Subtleties a
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l ATTACHMENT "G" REltELING FIDOR TECHNICAL DIRECTOR / COORDINATOR RETRESHER LAB 5
This four (4) day course will be administered at the G.E. B'*R Services Tr.. 'ning ' Facility in San Jose, Calif ornia.
. This course provides the license candidate with the opportunity to reinforce i
his/her knowledge on the operation of refueling equipment and introduces him/her to the Limerick Generating Station fuel handling procedures l
identified in Attachment "E".
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ATTACHMENT "H" 4
I ON THE JOB TRAINING AT LIMERICK GENERATING STATION 4
The license candidate will supervise a qualified refueling platform operator performing his/her duties in accordance with Limerick Genera *.ing Station
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a procedures as identified in the Lirnerick Generating Station SM Task Analysis j
(See Attachment "A"),
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l MICHAEL D. MARLOV Office ligu 1000 First Avenue 209 King of Prussia Rd.
Vayne, Pennsylvania 19087 King of Prissia. PA 19406 (215) 964 8443 (215) 962 6152 CER! ?.FICATIONS
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NRC Snnior Reactor Operator, Browns F6rry GE Senior Reactor Operator, Dresden
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US Navy Engineering Office of the Watch US Navy Engineering Vatch Supervisor
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l EDUCATION ATD TRAINING I
t University of Tennessee, Chattanooga, completed 3 years in Mathematzes/
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Computer Science Regents College, University of New York, enrolled in N'tclear
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j Technolo5y degree program r
i GE BV1 SRO Certification Course t
LE Fundamental of Nuclear Engineering GE Refuel Floor Technical Director Course i
US Navy Nuclear Power School & Prototype rg US Navy Electronics Technicien "A" School l
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WORK EXPE*AIENCE i
r 1979 Present CENERAL ELECTRIC COMPANY 1
t 1985 Present Training Sales Manseer Nuclear Traiteing Services, King of Prussia, PA t
Identifier
. 2tomer training service / product needs J
. Coor/inat<< rits.related deliveries and ensures 5'
eustomer s.
.sf act.in at 11 ites 1
l Directed Refuel Ficor SLO program for Peach Bottom t
Directed 1C instrue ors se customer cites h
1983 1985 Prerram Manarer Simulator Training, Chattanooga, l
4 i
Directed delivery of initial and reqvslification J
training for licensed operators l
I Served on Plant Hatch Steering Committee for l
j i
Training l
Evaluated licensed operators, training programs, and adninistrative procedures at Plant Hatch f
Analyzed NRC exa results and reported to Plant
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l Hatch Management.
Report used in presentation 1
to NRC
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t 2-i 1979 - 1983 Instructor / Senior Instructor Operator Training Services. Morris. IL Developed EOP validation scenarios and Emergency Plan drill guides, assisted Fit: patrick validation E0Ps and conducted E0P training Trained operations and management staff at Shoreham during initial plant license preparation Provided initial /requalification simulator training for 4 plants Conducted NRC audit examinations and SRO certification examinations for 10 plants Provided one on one trainirg for the Susquehanna Operations Manager 1971 1979 US Navy 1976 1979 E6 Electronics Technician aboard Submarine NR 1
- Qualified Engineering Officer of the Vatch Ieplemented preventive maintenance program for all departments and served as Maintenance Coordinator fhl 1973 1979 Electronies Technician aboard USS Spadefish
- Qualified Engineering Vatch Supervisor Reactor Operator for Hot / Cold plant testing Directed major modification of reactor safety equipeent i
0 RESUME VILLI AM J. DAGAN, JR.
NAME:
=
CURRENT TITLE:
Senior Engineer, Plant Operations NUCLEAR EXPERIENCE:
10 1/2 Years EDUCATION:
BS Nuclear Engineering, Penn State ADVANCED TRAINING:
Senior Reactor Opetator's Certificate Engineer in Training Certificate Station Nuclear Engineer Refuel Floor Technical Director Instrumentation for Engineering Moasurements Course (emphasis on vibration instrumentation)
Kepner Tregoe Problem Solving Course Licensing Program Management Course Management Practice Course EXFLL ENCE:
GENERAL ELECTRIC COMPANY - 10 1/2 Years
()I Senior Encineer. Plant Overations (July 1QF7 Present)
Supervise the writing of Limerick Unit 2 Startup Test e
Trocedures and Hot Tunctional Test Procedures Assist in the review, approval and scheduling of the Startup Test Procedures Supervise the scheduling and setup of the power ascension pipe test program for Linerick Unit 2 Ti' led in as C.E. Refuel Floor Technical Director for 3 seeks during Limerick i first refueling outage Vrote special procedures and perfoteed restart testing on the pressure control systen for Limerick Unit 1 Senior Engineer, Plant 6 System Startup Testing (1987)
Ccordinated the Perry Startup Test Sieplication program with General Electric engineering and the Ferry Plant Resolved problems, test exceptions, and changes for startup tests conducted at Ferry. Clinten. Terei, and Nine Mile Foint 2 Defined and scheduled testing for the Alto Lazio units.
This included system flushes, prelieinary checkouts, pre-operational and startep tests a
6
~T 2
lesd Startun Test Desien & Analysis Encineer (1083 1986)
Managed the power ascension test program at River Bend.
This ine).uded organizing the program, writing and reviewing test procedures and reports, conducting tests, analyzing results and resolving exceptions.
Supervised test persennel Defined and successfully implemented the first startup test simplication program Responsible for calibrating and testing the Emergency Response Information System (ERIS). This included updating interfacing system documentation.
Initiated both hardware and software design changes Responsible for pipe vitration and expansion resting for both l
BOP and NSSS system piping during the preoperational and startup test phases.
Defined types, locations and installa.
L tion of instrumentation.
Performed testing, analy:ed results and resolved problems
)
Was Chairman of a power ascension task force compesed of members l
of most utility disciplines.
The task force was implemented to effectively coordinate initial fuel receipt, neutron source i
installation and fuel load Startun Tart Enrineer (1080 1082)
On shitt as a Startup Test Design 6 Analysis Engineer for all startup testing at Kuosheng Unit 1 and Unit 2.
This 1
included extensive process computer, control systems and pipe j
testin6 j
Reactor Enrineer (1980) 4 Acted as a reactor engineer at Hatch, Oyster Creek and Kuosheng i
Lis.ensinc Encinaer (197c) j Addressed licensing issues (fuel and ECCS concerns) for J
operating plants J
i
[ ore Manarerent Enrineer (197fl Authored va ious data books Perform Core Management of reloads.
J including Cycle Sum:uary Reports, Reference Leading Pattern, Rod
)
Vithdrawal Error, and Fuel Loadin5 Error I
I l
10/31/S5 i
I
- .o
)
RESUME N/,ME :
SIETZE JEFF ROTTON CURRENT TITLE:
Engineer Startup, Test 6 Operations NUCLEAR EXPERIENCE:
8 Years EDUCATION:
B.S.
U. S. Naval Academy ADVANCED TRAINING:
16 Veek BVR Simulator Training Class -
SRO Certificate 8 Veek Prospective Nuclear Engineer Officer Course Navy Nuclear Engineer Qualified 2 Veek Advanced Water Chemistry and Radiological Controls 6 Month Naval Nuclear Prototype E00V Qualified 6 Month Naval Nuclear Power School 3 Veek Refuel Floor Technical Directors Course 1 Veek MSIV Maintenance and Recire Purp Seal rsplacement Course EXPERIENCE:
General Electric Company 2 Years Startup ens neer - Limerick Generating Station i
Responsible for the Main Steam, MSIV Leakage Control, Steam Leak Detection and AD5 preoperational test procedures. This included writing, reviewing and performing the preoperational tests.
Have also participated in other flush and preoperational tests U.S. Navy 6 Years
- Main Propulsion Assistant /Chenistry and Radiological Controls Officer Supervised 15 eachinist cates and four engineering lab technicians. Responsible for all mechanical and
{
radiological training Responsible for operation, repair and raintenance of i
nuclear reactor and nechanical reactor support l
)
systems, steam generatiag systtes and associated auxiliary systees Responsible for caintainin5 proper prirary/ secondary water chemistry and radiological controls
.s 2-Responsible for operation and maintenance of ship's turbine generators, main propulsion equipment and associated auxiliaries and emergency diesel generator Damage Control Assistant / Quality Assurance Supervisor Supervised 12 non nuclear machinist mates and four intarior communications technicians.
Responsible for operation, repair and maintenance of submarine's auxiliary mechanical and safety systems Responsible for operation of ship's quality assurance program and all applicable training
()
10/31/SS
6 I
i RI:SUME NAME:
VILLIAM R. VICTOR CURRENT TITLE:
Nuclear Servicer Trainee BVR NUCLEAR EXPERIENCE:
? oars t
EDUCATION:
f M.
U.S. Naval Academy ADVANCED TRAI!
s Vet Refuel Floor Technical Director Class Refuel Floor TD Certification 5
ik BVR Simulator Training Class -
so artification Month Nuclear Power Training Unit i
o EOOV Qualified 6 Month Naval Nuclear Power School i
EXPERIENCE:
General Ele:tric Company 2 Years
)
Startun Enrineer Limerick Ceneratine Station
)
Responsible for the investigation and closure of discrepancy documentation, performance i
of NSSS preoperational testing and flushing l
l procedures i
Startur Enrineer Pilrrim Station Lead Engineer responrible for implementing changes
[
a to station procedures based on Tech Spec j
j Amendments and plant design changes.
Vork included reviev and revision of station pro-l 4
l cedures and the cevelopment and operation of a
}
l computer document tracking system t
Investigated applicability and developed courses of action for namerous INFO SER's and SOER's and l
GE SIL's as part of an administrative breklog com-miteen; to the NRC
.J I
i
0 1
2 U. S. Navy 5 Yests Division Officer USS Henry L. Stimson (SSBN055)
Main Propulsion Assistant (1983 1986)
Supervised 20 technicians and oversaw extensive testing and inspectiens of the propulsion plant durin6 refueling overhaul Electrical Officer Responsible for 10 personnel in performance of major maintenance projects during post-overhaul upkeep period and regular refit cycles Enrineerine Officer of the Vatch and Encineerine Duty Officer J
Directed operations, maintenance and testing of reactor plant for three years Held many other primary and collateral duties including Chemistry and Radiological Controls Officer. Interior Communications Officer, Ship's Customs Inspector and Structure Borne Noise Officer all performed to Cormand's conplete satisfaction.
Nuclear Fever School. FL (lCF1 1083)
Navy Nuclear Power Training Unit (SBC) NY Submarine Officers' Basic Schoc1, CT Graduated from all Schools Nuclear Power Recruiter A Months Represented the Navy on college cacpuses at speaking engagenents and employnent fairs.
Performed s:reening and interviews
-)
with prospective officer candidates.
Responsible for planning and initiating the highly successful fiscal 19E2 advertising campaign
4 RESUME N/.ME :
STEPHEN CONROY CURRENT TITLE:
Engineer - Startup, Test & Operations NUCLEAR EXPERIENCE:
7 Years EDUCATION:
B.S.
Physics and Math ADVANCED TRAINING:
1 Week in Vessel Visual Inspection Class 3 Veeks Refueling Floor Technical Director Class 1 Veek Instructor Training Workshop J
16 Veek EVR Simulator Training Class SRO Certification 6 Month Nuclear Power Training Unit - Qualified l
E00W 6 Month Nuclear Power School J
EXPERIENCE: CENERAL ELECTRIC COMPANY 2 1/2 Years
~
Peachbottom Atomic Power Station Review of Vender Manuals for Procedure Updating Pilgrim Station Assistant to Operations Manager for writing procedures j
for special restart program tests B7R Training Course Instructor Instruction of SRO Certification students in classroom l
and simulator t
U, S, Navy 4 1/2 Years Main Propulsion Assistant Responsible for supervision of 20 personnel assigned to eaintain the main propulsion equipment This equipment includes all primary coolant systems, steam generators, all steam systems and components, j
cain turbines and turbine generators, feed and condensate systems, air conditioning systems, all cooling water systees, all lube oil systems, and the e ergency diesel generator i
4 2-Major Evolutions Two year refueling overhaul of a nuclear powered submarine; initial criticality, power range testing, and sea trials Three month post overhaul shakedown
- Qualified EOO*'
]
10/30/67
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L APPENDIX I PROGRAM SCEDLA E FW8846 MONDAY TUESDAY WEDNESDAY THURSDAY FRIDAY SATURDAY:
POV 7-12 0800 REFUELING FLOOR TECHNICAL DIRECTOR REFRESHER LABORATORY AT THE BWR SERVICES TRAINING FACILITY IN SAN JOSE, CA j
0300
\\
l 1000 110C8 1
1 1200 i
1300 i
1400 1500 1600 1700 1
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APPENDIX I PROGRAM SCHEDULE FW8847 MONDAY TUESDAY WEDNESDAY THURSDAY FRIDAY NOV 14-18 0800 COURSE OVERVIEW DUIZ #1 OUIZ #2 OUIZ #3 HEALTH PHYSICS THEORY 0900 CONDENSATE &
REACTOR REACTOR PRIMARY /
HEALTH PHYSICS REFUEL WATER THEORY THEORY SECONDARY THEORY STORAGE CONTAINMENT 1000 FUEL POOL RWCU/
FIRE REACTOR TECH SPECS COOLING & CU CRD PROTECTION ENCLOSURE VENTILATION 1100 RHR/RHRSW SRM/
ELECTRICAL ARM /
TECH SPECS RPS DISTRIBUTION PRM 1200 LUNCH LUNCH LUNCH LUNCH LUNCH 1300 PLANT TOUR PLANT TOUR PLANT TOUR PLANT TOUR SELF STUDY
!400 EXAM #1 1500 SELF STUDY SELF STUDY SELF STUDY SELF STUDY 1600 1700 v-m e
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l APPENDIX I PROGRAM SCHEDULE 1
a FW8848 MONDAY TCESDAY WEDNESDAY THURSDAY FRIDAY NOV 21-25 0800 EXAM REVIEW QUIZ #4 GENERf.L HOLIDAY HOLIDAY PROCEDURES c.
? *-
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0900 ADMIN HP PROCEDURES PROCEDURES
& PRACTICES l
J 1000 t
1100 l
1200 LUNCH LUNCH LUNCH 1300 ADMIN TECH SPECS SELF STUDY PROCEDURES i
1400 EXAM #2 1500 SELF STUDY SELF STUDY 1600 1700
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APPENDIX I PROGRRM 6CHEDULE
~
FW8849 MONDAY TUESDAY WEDNESDAY THURSDAY FRIDAY NOV 20-DEC 2 0800 EXAM REVIEW DUIZ #5 DUIZ M6 DUIZ #7 SYSTEM PROCEDURES 0900 RPV &
REFUELING FUEL HANDLING FUEL HANDLING INTERNALS EDUIPMENT PROCEDURES PROCEDURES 1000 1100 FUEL &
REFUELING CONTROL RODS INTERLOCKS 1200 LUNCH LUNCH LUNCH LUNCH LUNCH 1300 REFUEL FLOOR SURVEILLANCE FUEL HANDLING ROUTINE TEST SELF STUDY ORIENTATION TEST PRDCEDURES PROCEDURES PROCEDURES 1400 TOUR EXAM #3 1500 SELF STUDY SELF STUDY SELF STUDY SELF STUDY 1600 1700
l 4
h j
APPENDIX I PROGRAM SCHEDULE FW8830 MONDAY TUESDAY WEDNESDAY THURSDAY FRIDAY DEC 3-9 0000 EXAM REVIEW DUIZ #8 FINAL EXAM EXAM UPGRADE REVIEW 0900 ON JOB DN JOD PROCTICE ORAL TRAINING TRAINING EXAMS / UPGRADE 1000 1100 1200 LUNCH LUNCH LUNCH LUNCH LUNCH 1300 ACCIDENT SELF STUDY PRACTICE SELF STUDY ANALYSIS WALKTHROUGHS 1400 OFF NORMAL &
EMER
G. PROCEDURE
S 1500 SELF STUDY 1600 1700
y
./
A APPENDIX I PROGRAM SCHEDULE 1
FW8851 MONDAY TUESDAY WEDNESDAY THURSDAY FRIDAY DEC 12-16 0800 AUDIT EXAM WALKTHROUGHS WALKTHROUGHS ORAL BOARDS ORAL BOARDS WRITTEN 0300 1000 1100 l
l 1200 LUNCH LUNCH LUNCH LUNCH LUNCH 1300 ORAL BOARDS ORAL BOARDS ORAL BOARDS 1
l 1400 1500 1600 1700 l
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APPENDIX I PROGRAM SCHEDULE 1
FW8852 MONDAY TUESDAY WEDNESDAY THURSDAY FRIDAY DEC 19-23 0800 SELF STUDY SELF STUDY SELF STUDY SELF STUDY HOLIDAY O'300 1000 1100 1200 1300 1400 1500 1600 1700 t
L L
APPENDIX I PROGRAM SCh~IDULE FW8833 MONDAY TUESDAY WEDNESDAY THURSDAY FRIDAY DEC 26-30 0800 HOL I D+W SELF STUDY SELF STUDY SELF STUDY SELF STUDY 0"300 10tX*
11 <:H) 1200 1300 1400 1500 1600 1700 l
l i
3 APPENDIX 3 PROGRAM SCHEDULE FWG301 MOfJDAY TUESDAY WEDriESDAY THURSDAY FRIDAY SATU JAN 1-5 0000 HDLIDAY NRC EXAMS F4RC EXAMS NRC EXAMS 0300 1000 1100 1200 1300 1400 1500 16(@
1700
-. _ _-.