ML19347E010
| ML19347E010 | |
| Person / Time | |
|---|---|
| Site: | 07001308 |
| Issue date: | 11/28/1980 |
| From: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Dawson D GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 8104140619 | |
| Download: ML19347E010 (9) | |
Text
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UNITED STATES gs
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NOV 2 81980 Docket No. 70-1308 co License No. SUM-1265
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ATTN:
Mr. D. M. Dawson 1
77 Licensing / Transportation, MC 861
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Spent Fuel Services Operation Y4'2
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San Jose, California 95125 Gentlemen:
As indicated to you at our meeting on November 20, 1980, the NRC staff has developed a branch position with respect to the elements of an acceptable program for operator certification under 10 CFR Part 72, Subpart I.
I am enclosing a copy of our branch position for your consideration.
Based on our discussions, we understand that your training program will utilize appropriate regulatory guides, such as Regulatory 'luides 8.10 and 8.13.
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As noted to you at the November 20, 1980 meeting, there were three typographical errors in the listing c,f the pertinent sections of 10 CFR Part 72 in the third paragraph of our letter dated November 12, 1980.
In the table below we show the errors and the corrected version.
November 12 Version Corrected Version 72.14(c) 72.14(e)(2) 72.33(4) 72.33(b)(4) 72.72(c) 72.72(e)
If you have any questions regarding these matters, please let us know.
Sincerely, Leland C. Rouse, Chief Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety
Enclosure:
Branch Position cc: See attached list.
C s "n t o 69
o cc: Mr. Thomas H. Parks County Clerk Grundy County Morris, Illinois 60450 Mr. Leroy Stratton Bureau of Radiological Health Illinois Department of Public Health Springfield, Illinois 62706 Illinois Institute of Natural Resources 309 West Washington Street Chicago, Illinois 60606
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
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GENERAL ELECTRIC COMPANY
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(GE Morris Operation Spent Fuel
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Storage Facility)
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SERVICE LIST Andrew C. Goodhope, Esq., Chairman Edward Firestone, Esq.
Atomic Safety and Licensing Board Legal Operation 3320 Estelle Terrace General Electric Company Wheaton, MD 20906 175 Curtner Avenue Mail Code 822 Dr. Linda W. Little San Jose, CA 95125 5000 Hermitage Drive Raleigh, NC 27612 Mr. Everett Jay Quigley R. R. 1 Box 378 Dr. Forrest J. Remick Kankakee, IL 60901 305 East Hamilton Avenue State College, PA 16801 Atcmic Safety and Licensing Board Panel Susan N. Sekuler, Esq.
U.S. Nuclear Regulatory Commission Dean Hansell, Esq.
Washington, DC 20555 Office of the Attorney General 188 West Randolph Street Atomic Safety and Licensing Appeal Sutie 2315 Panel Chicago, IL 60601 U.S. Nuclear Regulatory Commission Washington, DC 20555 Ronald Szwajkowski, Esq.
Matthew A. Rooney, Esq.
Decketing and Service Section Mayer, Brown & Platt Office of the Secretary 231 South LaSalle Street U.S. Nuclear Regulatory Commission Chicago, IL 60604 Washington, DC 20555 Ms. Bridget Little Rorem Essex IL 60935 i
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GENERAL PLAN FOR OPERATOR CERTIFICATION A.
Licensee Responsibilities S.
NRC Responsibilities 1.
Licensing 2.
Inspection and Enforcement A.
Licensee 1.
Organize Program
- a. -Identify certifying officer and training officer b.
Provide qualifications of certifying officer (minimum) c.
Describe training areas d.
Describe testing rationale
- 1) Level of question
- 2) Passing grade
- 3) Criteria for re-testing (with retraining)
- 4) Frequency.of testing
- 5) Method for introducing plant changes
- 6) Written
- 7) Wal k-thru e.
Annual statement on job performance 2.
Submit to NRC (Licensing) for approval 3.
Implement program O
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- B.
NRC.
'1.
Licensing
- a.. Develop general acceptance criteria -
- b. ~ Review program against known criteria or other similar program c.
Approve program, if acceptable 2.
Inspection'and Enforcement Inspect program periodically against acceptance criteria
' a.
b.
Observe examinations and operator testing c.
Compare performance with expectation from training
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BRANCH TECHNICAL POSITION 1.
Certifying Officer a.
Plant Manager or his designee
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b.
Minimum Qualifications 1)
Five years experience in industrial with at least three years in nuclear fir.1d l
- 2) Bachelor's degree in science or engineering or equivalent
- 3) Close familiarity with plant 2.
Training and Testing a.
Must cover general areas b.
Record'of hours trained and subjects covered c.
Written examination
- 1) Samples of actual examination submitted to Chief, Advanced Fuel and Spent Fuel Licensing Branch (Proprietary) l l
- 2) Taken at least biennally l
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- 3) 70% passing grade (overall initially) j
- 4) Must get 80% in each area in subsequent tests a)
If less than 70% in any area, accelerated retraining required and cannot operate b)
If less than 80% but greater than 70%, retraining required d.
Operating test (walk-thru)
- 1) Written statement on strength and weaknesses with possible recommendation for additional training or retesting 3.
Job Performance a.
General Performance
-1) Specific radiological duties performed
- 2) Approximate time at each duty 3)
Evaluation of job performance by supervisor b.
Possible suggestions for retraining areas l
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- 4. '. Physical Capcbility
- a.. Complete physical biennially (AllSI Standard 11546 1976)-
b.
Vision or other impairments noted with statement on non-interference
-with work.
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- 5.. Records a'.
Records maintained on each individual for five years
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- 1) Medical
-2) Tests
- 3) Training' Record
- 4) Job performance record l
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BRANCH. TECHNICAL' POSITION CERTIFICATION OF OPERATORS AT INDEPENDENT.
SPENT FUEL STORAGE INSTALLATIONS General Areas to be Covered l.
Radiological Safety 2.
Equipment Design and Operating Characteristics
-3.
Management Systems and Procedures 1.
Rad! alogical Safety a.
Types of radiation-
'b.
. Principles'of radiation protection
- 1) Concept of ALARA
- 2) Time, distance, shielding
- 3) Contamination control
- 4) Radiation detection
- 5) Protective clothing and respiratory protection 2.
Equipment Design and Operating Characteristics a.
Cask design and handling
- 1) Cranes
- 2) Tools b.
Storage. racks
- 1) Criticality
- 2) Heat transfer S
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2-c.
Cooling and water cleanup systems d.
Ventilation system e.
Water leak detection f.
Instrumentation and Controls
- 1) Water level and temperature
- 2) Cooling flow rate
- 3) Cleanup system flow rate and pressure drops
- 4) Crane controls
- 5) Air and radiation monitors 3.
Management Systems and Procedures a.
General Organization b.
Operator Responsibilities c.
Technical Specifications
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d.
0perating Procedures e.
Emergency Procedures e
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