|
---|
Category:APPLICATION
MONTHYEARML19350D1611981-03-19019 March 1981 Reapplication by Wa Fraser for Operator License ML19350D1601981-03-19019 March 1981 Reapplication by Re Boyer for Senior Operator License ML19350D1591981-03-19019 March 1981 Reapplication by Nj Monson for Operator License ML20129H1651979-01-31031 January 1979 Partially Withheld Application for M Kending for Reactor Operators License Examination ML20128F5071979-01-31031 January 1979 Partiallt Withheld Application by C Mell for Reactor Operators License Examination ML20128F5331979-01-31031 January 1979 Partially Withheld Application for J Brummer for Senior Operator License Examination ML20128F5561979-01-31031 January 1979 Partially Withheld Application by J Garrison for Senior Operator License Examination ML20129H1461979-01-31031 January 1979 Partially Withheld Application by J Herman for Operator License ML20129H1881979-01-31031 January 1979 Partially Withheld Application for D Smith for Reactor Operator License Examination ML20129H2011979-01-31031 January 1979 Partially Withheld Application by D Mayhue for Reactor Operator License Examination ML20129H1281979-01-24024 January 1979 Partially Withheld Application for Amendment to Senior Operator License for R Hutchinson ML20129G6381978-11-0909 November 1978 Partially Withheld Application for Renewal of Senior Operator Licesne Number SOP-2866-1 by J Seelinger ML20129G4601978-09-14014 September 1978 Partially Withheld Application for Reactor Operator License for E Hemmilia ML20129G4311978-09-14014 September 1978 Partially Withheld Application for Senior Operator License for Hb Shipman ML20129F5161978-09-14014 September 1978 Partially Withheld Application for Senior Operator for R Zechman ML20129F4871978-09-14014 September 1978 Partially Withheld Application for Senior Operator License for C Hartman ML20129F4741978-09-14014 September 1978 Partially Withheld Application for Senior Operator License for J Logan ML20024B7591977-07-0505 July 1977 Application by Wh Zewe for Senior Reactor Operator License ML20024B7581975-07-10010 July 1975 Application by Wh Zewe for Senior Reactor Operator License ML20024B7571974-05-20020 May 1974 Application by Wh Zewe for Hot Reactor Operator License.Prof Qualifications Encl ML19270H5331973-12-19019 December 1973 Amend 2 to Application for SNM License Re Higher Strength Source to 1,300 Ci of Americium ML19270H5311973-10-15015 October 1973 Amend 1 to Application for SNM License ML19270H5291972-06-0808 June 1972 Application for SNM License for Storage Only of Fuel Elements & Byproduct Matl 1981-03-19
[Table view] Category:SENIOR OPERATOR LICENSE
MONTHYEARML19350D1601981-03-19019 March 1981 Reapplication by Re Boyer for Senior Operator License ML20128F5561979-01-31031 January 1979 Partially Withheld Application by J Garrison for Senior Operator License Examination ML20128F5331979-01-31031 January 1979 Partially Withheld Application for J Brummer for Senior Operator License Examination ML20129H1281979-01-24024 January 1979 Partially Withheld Application for Amendment to Senior Operator License for R Hutchinson ML20129G6381978-11-0909 November 1978 Partially Withheld Application for Renewal of Senior Operator Licesne Number SOP-2866-1 by J Seelinger ML20129G4311978-09-14014 September 1978 Partially Withheld Application for Senior Operator License for Hb Shipman ML20129F5161978-09-14014 September 1978 Partially Withheld Application for Senior Operator for R Zechman ML20129F4871978-09-14014 September 1978 Partially Withheld Application for Senior Operator License for C Hartman ML20129F4741978-09-14014 September 1978 Partially Withheld Application for Senior Operator License for J Logan ML20024B7591977-07-0505 July 1977 Application by Wh Zewe for Senior Reactor Operator License ML20024B7581975-07-10010 July 1975 Application by Wh Zewe for Senior Reactor Operator License 1981-03-19
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20211D1321999-08-20020 August 1999 Application for Amend to License DPR-50 to Revise TS Bases Re Degraded Undervoltage Relay Setpoint Calibration Frequency & Degraded Voltage Relay Tolerance Rev ML20210J0941999-07-29029 July 1999 Suppl TS Change Request 274 to License DPR-50,revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance Tss,As Result of NRC Generic Concerns Re CR Habitability Issues ML20209D6651999-07-0808 July 1999 Corrected TS Pages 3-21,4-5a,4-9,4-38 & 6-3 to Amends 211 & 212 to License DPR-50.Pages Failed to Reflect Previously Approved Changes Granted in Amends 203 & 204 in Case of Amend 211 & 207 in Case of Amend 212 ML20196K5901999-06-29029 June 1999 LAR 285 for License DPR-50,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matls Can Continue to Be Moved ML20209C0551999-06-29029 June 1999 LAR 77 for License DPR-73,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matl May Continue to Be Moved ML20195E3341999-06-0404 June 1999 TS Change Request 265 to License DPR-50,modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20209B5891999-05-26026 May 1999 LAR 281 to License DPR-50,revising TMI-1 UFSAR Chapters 5 & 14 to Permit Use of Conservative Deterministic Failure Margin Methodology for Seismic Analysis of Portions of Auxiliary Steam Line.Rept 240046-R-001 Encl.Rept Withheld ML20206R1111999-05-13013 May 1999 Application for Amend to License DPR-50,requesting That License Sections 2.a.(3) & 2.c.(7) & TS Section 3.1.1 Be Revised to Incorporate Administrative Updating & Changes to Bases Statement ML20205H0691999-04-0101 April 1999 TS Change Request 262 to License DPR-50,revising TS by Adding LCO Action Statements & Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20203B0421999-02-0202 February 1999 TS Change Request 274 to License DPR-50,expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems ML20196H9751998-12-0303 December 1998 LAR 279 to License DPR-50,reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G4401998-12-0303 December 1998 LAR 278 to License DPR-50,requesting Consent to Transfer & Authorize Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License.Supporting Documentation,Encl ML20196G7671998-11-25025 November 1998 TS Change Request 277 to License DPR-50,changing Surveillance Specs for OTSG ISIs for TMI-1 Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only ML20195C6811998-11-12012 November 1998 Amend 52 to License DPR-73,relocating Audit Frequency Requirements from TMI-2 to TMI-2 Post Defueling Monitored Storage QA Plan & Extends Max Allowed Interval Between Certain Audits from 12 Months to 24 Months ML20154P8441998-10-19019 October 1998 Application for Amend to License DPR-50,providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage.Proprietary & non- Proprietary Calculation,Encl.Proprietary Info Withheld ML20154Q6201998-10-19019 October 1998 TS Change Request 248 to License DPR-50,adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18, Remote Shutdown Sys ML20154M3691998-10-15015 October 1998 Application for Amend to License Amend Request 276 to License DPR-50 Revising UFSAR Chapter 14 Accident Analysis Atmospheric Dispersion Factors.Ufsar Revised Pages Encl ML20249B2391998-06-11011 June 1998 TS Change Request 273 to License DPR-50,incorporating Alternate High Radiation Area Control Consistent W/Reg Guide 8.38 ML20217E5131998-03-23023 March 1998 Application for Amend to License DPR-50,revising TS Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 Efpy.Request Also Submitted in Response to NRC ML20217G0161997-10-0303 October 1997 Suppl to License Amend Request 268 to License DPR-50, Replacing Pages 4-80 & 4-81 Previously Submitted w/TMI-1 License Amend Request 268 on 970812 ML20211C2221997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re TS Change Request 266.Supplement Provides for Phased Review & Issuance of License Amends & Involves Administrative Correction to TS Decay Heat Removal Sys Leakage Rate ML20211C3211997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re License Amend Request 269 Submitted on 970814.Suppl Includes Addl Change to TS Section 3.1.4 & Proposed Page Rev Clarifying That UFSAR Analysis Is More Conservative ML20210J9951997-08-14014 August 1997 Revised License Amend Request 269 for License DPR-50, Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J3981997-08-12012 August 1997 Tech Spec Change Request 268 for License DPR-50,revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operations ML20198E7871997-07-30030 July 1997 TS Change Request 266 to License DPR-50,incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 ML20141E1311997-05-0808 May 1997 Application for Amend to License DPR-50,consisting of Change Request 264,incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2351997-04-21021 April 1997 Application for Amend to License DPR-50,requesting Rev to TS 3.3 Re Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Systems ML20134M1111997-02-0707 February 1997 Application for Amend to License DPR-50,incorporating Certain Improvements from Revised STS for B&W Plants, NUREG-1430 & Addl Changes as Described in Encl TS ML20133D2651996-12-24024 December 1996 Application for Amend to License DPR-50,requesting Reinstatement of Auxiliary & Fuel Handling Bldg Ventilation Sys TS ML20132F3221996-12-16016 December 1996 Application for Amend to License DPR-50,consisting of Change Request 260,reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135C5201996-12-0202 December 1996 TS Change Request (Tscr) 75 to License DPR-73,relocating Audit Frequency Requirements to Pdms QA Plan ML20134D7761996-10-24024 October 1996 Amend 51 to License DPR-73,revising TS to Extend Surveillance Interval for Demonstrating Operability of Containment Airlock ML20128K1831996-10-0808 October 1996 Amend 50 to License DPR-73,revising TS to Incorporate Improvement from Administrative Controls Section of Revised STS for B&W Plants ML20117H0181996-08-29029 August 1996 Application for Amend to License DPR-50,consisting of TS Change Request 257,incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1901996-06-28028 June 1996 Application for Amend to License DPR-50,consisting of Change Request 259,allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8751996-05-24024 May 1996 Errata to Application for Amend to License DPR-50,consisting of TS Change Request 243,replacing Pages for App a ML20101R1361996-04-10010 April 1996 Application for Amend to License DPR-50,consisting of Change Request 243,revising Addl Group of Surveillances in Which Justification Has Been Completed Following Receipt of 930623 Application ML20100J6831996-02-22022 February 1996 Application for Amend to License DPR-50,consisting of Change Request 254,revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Station Battery Cell Parameters Not Met ML20095J2261995-12-21021 December 1995 Revised TS Change Request 254,raising Low Voltage Action Level to 105 Volts DC ML20091L2831995-08-23023 August 1995 Rev to TS Change Request 223 to License DPR-50,incorporating Ref to 10CFR20.1302 ML20087F4881995-08-11011 August 1995 Rev to TS Change Request 252 to License DPR-50,removing TS Section 3.2 Re Makeup,Purification & Chemical Addition Sys Requirements.Certificate of Svc Encl ML20086R3001995-07-24024 July 1995 Rev to LAR 250 to License DPR-50,clarifying Section III, SE Justifying Change for source-range Nuclear Instrumentation SRs ML20085N1551995-06-22022 June 1995 TS Change Request 227 to License DPR-50,replacing Pages for App A.Certificate of Svc Encl ML20084N3461995-06-0101 June 1995 TS Change Request 223 to License DPR-50,deleting Remaining Portions of RETS & Relocating TSs Per Guidance in GL 89-01 & NUREG-1430 ML20084L4201995-06-0101 June 1995 TS Change Request 251 to DPR-50,revising TS 5.3.1.1 to Describe Use of Advanced Clad Assemblies ML20084B3261995-05-24024 May 1995 Application for Amend to License DPR-50.Amend Would Change Surveillance Test Requirements for source-range Nuclear Instrumentation ML20083N7771995-05-17017 May 1995 Application for Amend to License DPR-50,consisting of Change Request 252,removing Chemical Addition Sys Requirements from TS to COLR ML20079A7771994-12-23023 December 1994 Rev to TS Change Request 221 to License DPR-50,revising TS Page 3-32a ML20073F9241994-09-26026 September 1994 LAR 246 to License DPR-50,revising License Condition 2.C.9 Re Long Range Planning Program ML20069A6731994-05-20020 May 1994 TS Change Request 244 to License DPR-50,requesting Revised CR Trip Insertion Time Testing Acceptance Criterion for Remainder of Cycle 10 for 12 Specific CRs Which Initially Experienced Slow Rod Drop Times During Testing on 940317 1999-08-20
[Table view] |
Text
. . . _. - - - . - - . - - - = _ - .. . _.
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METROPOLITAN EDISON COMPANY suosican. or ae:to uusucununncomaano.,
) TELEPHONE 717 944-4041
- POST OFFICE BOX 480 MIDDLETOWN. PENNSYLVANIA 17057 September 14, 1978 i
b i
e tir. Paul F. Collins U.S. fluelear Regulatory Comission j
Office of fluclear Reactor Regulation ifashington. 0.C. 20555
Dear !!r. Collins:
i Please consider this application for a Senior Reactor Operators License examination i
In accordance with Section 55.10 of 10LFR55, the following information is submitted:
- 1. flanc: Richard W. Zechman h
Age:
- Present Employment
- Supervisor of Training, Metropolitan Edison Company, Three Mile Island ?!uclear Station
- 2. a) Education: -
- 1. Reading Senior liigh School Graduated - Reading, Pa. -
@' % (e .
ormat. ion m th.is record was deleted accordance viith the freedom of Information
- 2. Pennsylv2nia State University
- "Electrica Engineer' t, exemptions k acate College, Pa. f0fA- @ 6 DC O
- 3. State Civil Defense (?/67-3/67) and (11/66-12/66)
Radiological Defense Course Graduated - State College, Pa. y -
s -
- 4. Clase "A" Radionen School (2 weeks)
(1954*; Graduated - Bainbridge, I'd.
- 5. Instructors Training School 781113d54f (4 weeks),(19581 Graduated'
2 155 g OO g 6 960924 DEKOK96-207 PDR
-L-
- 1. U.S. flavy (1954-1962) RM2 Radioman Second Class, Instructor at flaval Reserve Center, Reading, Pa.
- 2. WesternElectric(9/56-9/61)as Senior Electronics Technician, Laureldale, Pa.
- 3. Penn State University (10/63-9/65) as Training Supervisor.
State College, Pa.
- 4. TrainingSpecialist(9/69-8/73)
Metropolitan Edison Company.
Three Mile Island fluclear Station. .
Middletown, Pa.
As Training Specialist. I was responsible for the Administration.
Scheduling and Records Keeping for all Unit I initial staff training programs. This responsibility included establishing and supervising the first Unit I Control Room Operator and Auxiliary Operator training program.
- 5. Administrator Nuclear Technical Training (8/73-11/76)
Metropolitan Edison Company, Three Mile Island Nuck ./ Station ttiddletown, Pa.
As Administrator Nuclear Technical Training. I was directly in-volved in the teaching and Administration of Control Room Operators and Auxiliary Operators. This responsibility included establishing I
and administering new training programs required to meet new AEC(NRC)requirementsandregulations.
- 6. Group Supervisor Technical Training Nuclear (11/76-11/77)
Metropolitan Edison Company.
Three Mile Island Nuclear Station
.iddletown, Pa.
M As Group Supervisor Technical Training, I was responsible for the Administration and Supervision of the Training Department Instructor and Operator Training Programs.
- 7. Supervisor Training - Nuclear (11/77 - present)
Hetropolitan Edison Company, Three Mile Island Nuclear Station j Middletown, Pa.
In my present position as Supervisor of Training. I am respon-sible for the supervision and administration of all training This activities at the Three Mile Island Nuclear Station.
responsiblity includes the Supervision and Administration of the THI training department staff.
2.15s .
l
Previous Senior Operator's License - (50P-750) 3.
' at the Penn State University. State College, Pa.
, 4. License is requested to operate a pressurized water reactor; lietropolitan l Edison Company. Three Mile Island fluclear Station. Unit I. 1
- 5. See attached letter.
- 6. See Enclosure I.
- 7. Medical examination will be forwarded under separate cover.
Sincerely yours.
, Q -fx! =-
P.ichard W. Zechman RWZ/drg 4
Enclosures e
I l
k
i
] '. .
I l- - . EllCLOSURE I TRAIN!flG PROGRN6 i
RECEIVED DY:
Richard U. Zechnan l
The general outline of Mr. Zechman's training follows:
- 1. License Training Program - (mininun 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />) (6/76-present)
Reactor Theory (40 hrs)
- 1. )
- 2. Health Physics (30 hrs)
.' 3. ICS (40 hrs)
) 4. ReactorOperations(40 hrs)
- 5. Systems (NSSS and Balance of Plant) (194 hrs)
G. Procedures (40 hrs)
- 7. Technical Specifications (16 hrs)
- 2. PHR Simulator Training at Babcock and Wilcox Corporation with Startup Certification (80 hrs) (Startup Certification will be forwarded by Babcock and Wilcox Corp).(10/16/78-10/20/78 and 10/23/78 ~ /27/78)
- 3. OntheJobTraining(Minimum 200 hrs)
(Participated in, simulated or discussed the following):
Control Roem:
- 1. Reactor Coolant System Fill snd Vent - including steps to (117, vent, and presseri:e, running of reactor coolant pumps, and heatup to Hot Shutdown condition.
- 2. Reactor Criticality and Power Escalation - Participated in Unit reactor startup, including calculation of estimated critical rod position. Dis-cussed rod withdrawal, chemical shim and necessary rod index for power escalation.
- 3. Power Operations
- 1. Leak Rate Calculations
- 2. Heat Balance Calculations
- 3. Batch Feed Batch Bleed, Feed and Bleed Balance of Plant:
- 1. Fuel Shuffle
- a. Reactor Building
- b. Fuel Handling Building .
p 4 -e
. . /. .
.-D
/ . .
- 2. Insfrument Air Startup/ Operation -
. Service Air Startup/ Operation -
Powdex Operation
- 3. Solid Waste Disposal System Operatten Liquid llaste Disposal System Operation . ,
Gas Haste Disposal System Operation System Lineups
- 4. .
11akeup and Purification -
- a. Letdown .
- b. llakeup' .
- c. Seals .
riuclear Service Closed Cooling fluclear Service River Water Seconda'ry Service River Water Reactor Building Emergency River Water Decay Heat River Water Decay Heat Closed Cooling Water -
Secondary Service Closed Cooling Unter -
Stator Cooling Turbine Lube Oil .
Gland Steam .
Feedwater .
Condensate Ileater Drain , ,
Extraction Steam flain Steam .
t .:v . ..: :v.pp.a.w=i.s;.y%M.aFQ-ks.s&&Q,,{f.Q~y r-0 2.159
Pk LESSON 1PLETIC;l DATE LESSON -
H0DE INSTRUCiGR 1%TERIAL COMPLETED HUMBER SUBJECT (GET DATE Reactor Coolant System NSISS SS c/,,/,f.. 1 NSS.S - SS t////y 2 Reactor Vessel and Intervals Pressurizer, Relief Valves, Heater, RC Lesson Plan SS 4 A,/g 3 Drain Tank Tech.~ Spec. .
RCP, Motor, Seals, and Aux. Lube Oil LessonPlan/ D. Boltz gfufff 4
- Systems and Trips Lectura SS
- t/utsy G OTSG 6 R.C. System Leakage / Activity Linits Tech. Spec. SS c g/43fff to Tech. Spec. SS d
c/.es/s/ 7 R.C. Coolant Leakage Detection ,,
N -
&/29/27 Procedures: SS 8 SS b 1103-5. Prz. Operation a))) 1103-2, RC Fill / Vent 9
c 1202-29, Prz. Fail. SS 10 SS 11 d 1103-6, RCP Oper. -
e 1202-14, Loss of RC Flow -
SS 12 - , .
13 f 1203-16 RCP Motor Emerg. ,
SS y
Written Test ' Lesson'1 - 13 D. Boltz 15 30 or 7/6 Lesson Plan Lcc N. Bro:n 10A flNI D. Boltz Makeup and Purification Lesson Plan Te'c-'-
168 Lesson Plan HP Injection, Interlocks Tcch. Spec.,
Alarms Lesson Plan
' Deccy Heat Removal, Interlocks, Alarm Lesson Plan Lcc N. Cra.:n 17
- Tech. Spcc::.
- , .,. . . ., , g.j ,
LESSON ION DATE ' LESSON .
.' MODE IXSTRUOT:
4-SUBJECT
- - PATERIAL 3ET DATE COMPLETED NUM8ER: ,
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~
. .. . a 18 Core: Flood .
. . tesson Plarr . SS
~y ,
. ~ 19 Rx Building Spray .' . . Lessoh *Plan ' SS W
Proc'.. SS @
20 - Procedures': 1104-2 .
d
. 21 a)jDHR/0TSG1102-13 b
.- Proc. . SS ,.
22
.. c)DHR/LPI11044
. *2 roc.* : .
SS N 23 - '
CF 1104-1 Proc.' SS 24 d)g o Rx Bldg Spray 1104-5 Proc.' * *
. - SS i
Proc..*
SS 25 t f/SolBoronCont.1103-4 .- Proc. -ss .
26 9/ChemAdd 1104-47 A/B'
, SS ij ) LossLoss of of RCS DH Makeup 121202-35 . Proc.,03 .
55 28 I
29' Written Test .
." D. Golt: '
- 1/78 30 Oral Exam - -
N. Brown l
.4/78 .
31 RPS .
' Lesson Plan Lcc D. oolt: j 32 . . Lesson, Plan Lee N. Brow v, E.SAS .- .
u . . .
3 ,._ . 33 Intermediate Cooling System Les. son Plan Lee ny - -
W8 34 In'st & Service. Air J. .. Lesson Plan ' Lec.
54 t
5 ,=, .
35 - Procedures: a) Inst. Air 1104 - ,- Proc.. -
SS r 0- 36 ..'.
-
Proc. . SS c) Servic'e Air l'104-42 l' I
- 37 * '..
Proc. SS aE - 38 .
. 'd) Loss of Serv. Air 1202-3G Proc. SS
.. gg- *39..' l. '. . ' c). Int Cooling 1104 ,~,'- l Proc. SS i
=> .
, ' 40 . '
. . j . '. -*. ,.f)LoS8of.}rltCoo1.-B - 1202,-17..<
,= .
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- .41 - Written Exara ', -
.y, f73 - . . .
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43 CRD Mech /Electr.ical -
.' NSSS
_ Lee C. Har r t
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LESSON - - l
' MATERIAL MODE
- TION DATE -
SUBJECT NUMBER; . ,
fDATE CC.SPLETED -
LP [ SS/Lec D. Boltz ,
45 - ICS/ Transients, ', ,
.s .
- Proc.
Tape / Lee l Procedures:* a)I ICS Transients - ' Proc 47 - -
b
- SS c ) 1105-9, CRD. Proc'< - .
48 .
.- Proc. .~ . SS g l 49 .- d >.1202-8..tRD Failures * '
SS ,a
- e) 1102-1 Plant Heatup - .. P. roc.;. .
5Q Proc., SS ,.4 51 I f;) 1102-2 Pl'a'nt Startup g i 1102-4 Po'wer Oper. '
Proc. -
SS N
52 .
Proc . :.*- .. SS 53 : .
hh *SS 1, ) 1102-10L Plant'Cooldown Plant Shutdokn -
Proc.- -
54 } 1102-111103-8 Approach to froc Cri.tical.' -
.- SS
' 55 Proc., SS !
56 {kl 1203-28 Hydrogen Purgo Proc.,' SS 1 1203-1 Load Re,jection
.- 57 . - m 1202-4 Reactor Trip Proc. . SS
- - 57A 58 n - - D. Goltz ,
58 Written Test ,
7a '
D. Daltz Oral Test : . . ,
59 , *
'73 60 5.tartup' Cert At Simulator
- 10/20 .
i- . . .
tec ?
- 1:PT
- Turbine & Aux .
'tP .
Lee ? .
- 61A - Diesel Gen / Aux . .
. . l LP : .
SS
- 62 -
Main". Steam LP
SS Aux Steam - .; , ..
. .e ,, : . ..
.LP,,j,, SS l
. 64 c. , Copderisath Sys , ' , ~ ., , ,,5 , ., '> , , .
l- . . i. . .- . . . .- - . .-
- SS l'ecdwater Sys : - -
..- 65
,LP .
Cec ? j EFW. Pumps / Aux . .
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Rad Monitoring.
- LP 67..-
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. a :TIO.'; DATE LESSON .
P TERIAL MODE 95I-RUMBER; SUBJECT . .
- 55CATE C0i!FlusD . . .
2 . .
ReactivityBaiance 1103-15 ~
P. roc , ,
99~ . Proc. ,
100 - Heat Dalknee 1103-16 . .
101 Computer 1105-10 .
Proc,.
102 Rad Waste "Proc 1104-27 ,
" 1104-28 .
" . . " /.1104-29'A,B,C.D.E,I,P & S. ,.*.., ,
t
.c. . .
.loi )(ritten Test p 1 104 Oral Test .
.. g -
. e Fuel Handling *- '
1.P. .
..l 105 '
N l Fuci Handling Proc. 1502-1 Pro,c.,
, 106 . ,
107 NRC Exam ,
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