ML20129F516

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Partially Withheld Application for Senior Operator for R Zechman
ML20129F516
Person / Time
Site: Three Mile Island  Constellation icon.png
Issue date: 09/14/1978
From: Zechman R
METROPOLITAN EDISON CO.
To: Collins P
Office of Nuclear Reactor Regulation
Shared Package
ML20125B444 List: ... further results
References
FOIA-96-207 NUDOCS 9610040166
Download: ML20129F516 (9)


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'
  • Philadelphia, Pa.

2 155 g OO g 6 960924 DEKOK96-207 PDR

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  • b) Experience:
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

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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 .

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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 .

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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::.

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LESSON ION DATE ' LESSON .

.' MODE IXSTRUOT:

4-SUBJECT

- PATERIAL 3ET DATE COMPLETED NUM8ER: ,

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. .. . a 18 Core: Flood .

. . tesson Plarr . SS

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. ~ 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'

  • 27 h Pr.oc. . .

, 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 ..'.

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  • b) Rx Prot Sys 1105-2 -

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

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, ' 40 . '

. . j . '. -*. ,.f)LoS8of.}rltCoo1.-B - 1202,-17..<

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.41 - Written Exara ', -

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43 CRD Mech /Electr.ical -

.' NSSS

_ Lee C. Har r t

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f..  : .i l ' . * . .* - LP,. -[ '. {. , .. ss

.i. - LESSON INST.RUC70r, .

LESSON - - l

' MATERIAL MODE

TION DATE -

SUBJECT NUMBER; . ,

fDATE CC.SPLETED -

LP [ SS/Lec D. Boltz ,

45 - ICS/ Transients, ', ,

.s .

- Proc.

  • 46 '

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

  • 61

- Turbine & Aux .

'tP .

Lee  ? .

- 61A - Diesel Gen / Aux . .

. . l LP  : .

SS

62 -

Main". Steam LP

SS Aux Steam - .; , ..

  • 63 -

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.LP,,j,, SS l

. 64 c. , Copderisath Sys , ' , ~ ., , ,,5 , ., '> , , .

  • LP. :.. ... *,

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SS l'ecdwater Sys : - -

..- 65

,LP .

Cec  ? j EFW. Pumps / Aux . .

  • '66 ,

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.3 .- Lee  ?

Rad Monitoring.

- LP 67..-

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asetny,P?o:va ..

- Lesso,q

. 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 . .

  • Proc.

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 .

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. e Fuel Handling *- '

1.P. .

..l 105 '

N l Fuci Handling Proc. 1502-1 Pro,c.,

, 106 . ,

107 NRC Exam ,

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