ML20080P705
| ML20080P705 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/02/1982 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Beckham D Office of Nuclear Reactor Regulation |
| References | |
| 5211-82-273, NUDOCS 8310070309 | |
| Download: ML20080P705 (4) | |
Text
-
~
hpBd6 GPU Nuclear Corporation G. U Nuclear
- gess48o e
Middletown Pennsylvania 17057 717 944-7621 TELEX 84 2366 Writer"s Direct Dial Number:
December 2, 1982 5211-82-273 Office of Nuclear Reactor Regulation Attn: Donald K. Beckham Operator Licensing Branch Diviaion of Human Factors Safety U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Licensed Operator Requalification Program our letter L1L 328, dated November 5, 1981, submitted to you the Control Room Operator Requalification Training Program for TMI Unit 1.
On January 6, 1982, during our attendance at a meeting held in Bethesda, the NRC advised licensees that they could modify their Programs to be consistent with the current NRC examination administration.
We have made two changes to our Program to provide this consistency.
These modifications provide a Program that is more effective than the Program submitted in November, 1981, and we have therefore i=plemented them accordingly.
The changes are enclosed with this letter as Attachment 1, which is a listing of the submitted and i
l present Examination Topics Titles, and Attachment 2, the wording of the previous and present Examination Structure.
We will administer exams December 8, 9 & 10, 1982, based on the enclosed Exam Topics.
We anticipate additional Program changes in the near future.
Sincerely, s
i H. D.
dukill Director, TMI-l HDH:NDB:JGB:vj f Enclosures p
1 I I G310070309 821202 PDR ADOCK 05000289 V
PDR GPU Nuclear Corporation is a subsidiary of the General Putlic Utilities Corporation
ATTACHMENT 1 EXAMINATION TOPIC TITLE MODIFICATION (Section 4.5.1.1)
~
PREV!OUS TOPICS PRESENT TOPICS 1)
Theory and Principles of Reactor 1)
Theory and Principles of Reactor Operation Operation 2)
Heat Transfer, Fluid Flow tind 2)
Heat Transfer, Fluid Flow and j
Themodynamics Themodynamics 3)
Features of Facility Design 3)
Features of Facility Design 4)
General and Specific Plant 4)
Nomal Plant Operating Operating Characteristics Characteristics, including Industry Operating Experience 5)
Plant Instrumentation and Control 5)
Plant Instrumentation and Control Systems Systems 6)
Plant Protection System 6)
Plant Protection System 7)
Engineered Safety Systems 7)
Engineered Safety Systems 8)
Radiation Control and Safety 8)
Radiation Control and Safety 9)
Applicable Portions of Title 10, 9)
Deletec Chapter I, Code of Federal Regulations
- 10) Fuel Handling and Core Parameters
- 10) Fuel Handling l
- 11) Nomal, Abnomal and Emergency
- 11) N ormal, Abnormal and Emergency 1
Operating Procedures Operting Procedures
~
l l
(
1 ATTACHMENT 1 (continued)
EXAMINATION TOPIC TITLE MODIFICATION (Section 4.5.1.1)
PREVIOUS TOPICS PRESENT TOPICS
- 12) Technical Specifications 12)
See Item 13
- 13) Administrative Procedures, Conditions 13)
Administrative Procedures, Condition and Limitations and Limitations and Tech. Specs.
- 14) Nuclear Industry Operating Experience 14)
See Item 4 9
e 9
m
..s 1.*
e ATTACHMENT 2 EXAMINATION STRUCTURE CHANGES (Section 4.5.1.1)
Previous Statement The topics shall be grouped.into at least six (6) examination categories for evaluation purposes.
The examination shall be structural so that the level of questioning is consistent with the individual's license level (R0 or SRO).
Present Statement The topics shall be grouped into five (5) examination categories for each license level (R0 and SRO).
The examination shall be structured so that the level of questioning is consistent with the individual's license level (R0 or l
SRO) and current fomat of NRC licensing examination.
i l
l l
_ - - - _ __