ML19269E189
| ML19269E189 | |
| Person / Time | |
|---|---|
| Site: | 07000033 |
| Issue date: | 05/17/1979 |
| From: | Ketzlach N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 7906260627 | |
| Download: ML19269E189 (13) | |
Text
~
8((
+
o, UNITED STATES
$,k'e<, [',E NUCLEAR REGULATORY COMMISSION n
WASHINGTON, D. C. 20555
\\f+@(f Docket No. 70-33 OY 17 579 MEMORANDUM FOR:
W. T. Crow, Section Leader Uranium Fuel Fabrication Section Fuel Processing & Fabrication Branch FROM:
Norman Ketzlach Uranium Fuel Fabrication Section Fuel Processing & Fabrication Branch
SUBJECT:
MEETING MINUTES Purpose To discuss format and content of license renewal application of Attleboro, Massachusetts Facility with Texas Instruments, Inc. (TI).
Place and Date USNRC, Silver Spring, Maryland, May 10, 1979.
Attendees NRC - W. T. Crow, N. Ketzlach, and A. '.. Sonng TI - D. Conroy, Manager Manufacturing F. L. Sherman, Manager HFIR Project C. M. Hopper, Manager Nuclear Safety Discussion Copies of an acceptable standard format arm content for an SNM license renewal aplication were given to the TI representatives.
(Copy attached)
The discussion included the following:
1.
Differentiation between license conditions and demonstration sections.
2.
The need for demonstrating the applicability of license conditions.
3.
TI will provide a separate license condition section.
4.
Bioassay program.
2133 269 5.
ALARA requirements.
7906260d27
W. T. Crow 6.
Action levels associated with radiation safety.
7.
Format and content for license renen1 application.
Texas Instruments stated they require several days to determine when they can submit the required supplementary information to their renewal application.
After review of the discussion, Calvin Hopper (TI) notified N. Ketzlach on May 14, 1979 that they shall require three months to prepare and submit the required supplementary infomation to their r.enewal application.
j
/ /
'f-is LL4 Norman Ketzlach Uranium Fuel Fabrication Section F'el Processing & Fabrication Branch D. vision of Fuel Cycle and Material Safety 2133 270 c
,e 4
N 4
- #l4Ww{
STANDARD FORMAT AND CONTENT FOR AN SNM LICENSE RENEWAL APPLICATION 2133 271 O
PART I, LICENSE CONDITIONS Chapter 1, Standard Conditions and Special Authorizations
.~4.n J
1.1 Name 1.2 Location 1.3 License number 1.4 Possession limits isotopes, amounts, chemical and physical form, locations (buildings) 1.5 Definitions 1.6 Authorized activities e.g., production process, laboratory operation, waste disposal, etc.
1.7 Exemptions and special authorizations e.g., monitor alarms, release limits Chapter 2. General Organizational and Administrative Requirements 2.1 General policy of organization
- 2. 2 Responsibilities (functions) and authorities of key positions and organization units for operations (& management) radiation safety 2133 272
. Chapter 2 (Cont'd) nuclear criticality safety industrial safety a
safety committees objectives, composition, frequency of meetings, reporting requirements 2.3 Personnel selection (approval authority) for key positions 2.4 Independence of safety personnel (reporting, lines of authority) 2.5 Education and experience requirements for all key safety and opera-tions groups and positions 2.6 Training new employees general subjects covered appraisal of effectiveness frequency of refresher training records 2.7 Operating procedures responsibility and authority for issuance availability to operators frequency of operating procedure review 2.8 Records types f.hj$ j((jj retention times
- 2.9 Handling of Changes (any changes in equipment or procedures) trip points and responsibilities (approval authorities) physical inspections of changed equipment timing of review s
Chaoter 3, Radiation Protection 3.1 Administrative requirements 3.1.1 Radiation work permit procedures criteria for need opproval authority 3.1.2 Audits (formal and informal) by whon, made frequency to whom submitted follow-up responsibility 3.1.3 ALARA Committee (including commitment to ALARA) membership objective requir ed meeting frequency reports made by whom and to whom 3.2 Technical requirements 2133 2714 3.2.2 Access controls step off pads, change facilities, special clothing, survey meters at exits
.. x 4
Chapter 3 (Cont'd) 3.2.3 Ventilation requirements filter monitoring and change criteria, efficiencies,
~ ~ ~ ~ ~ '
minimum inlet velocities and monitoring frequencies required op values for. boxes 3.2.4 Instrumentation (both survey and counting) requirements for capabilities maintenance - calibration frequencies 3.2.5 Internal exposure 3.2.6 External exposure (dosimetry requirements, survey frequency) 3.2.7 Bioassay program 3.2.8 Air sampling frequency of filter changes (and counting) action points and actions to be taken sampling frequencies
-+"~~
representativeness checks of air sampling 3.2.9 Contamination surveys frequency by area types (e.g., hot, cold, change rooms) surface contamination
- release levels
- action points
- actions to be taken 3.2.10 Respiratory protection 2i33 275 S
. Chapter 4, Nuclear Criticality Safety 4.1 Administrative requirements 4.1.1 Double contingency policy
- ~ -
a 4.1.2 Written procedures and approval authority 4.1.3 Analysis request, criterion for, and position responsible for initiating request 4.1.4 Posting of limits 4.1.5 Internal review requirements ~
criterion for review and timing of analysis and review independence of review (not analyst) and objective inspection of equipment and environs extent of detail in record of analysis 4.1.6 Marking and labeling of SNM 4.1.7 Audits by whom taken and to whom submitted frequency follow up records - reports and to whom submitted 4.1.8 Training and retraining by category of personnel frequency general subject matter covered e
e es mme..
. Chapter 4 (Cont'd) 4.2 Technical Requirements 4.2.1 Preferred approach to design a
4.2.2 Basic assumptions 4.2.3 Analytical methods and validatica references 4.2.4 Data sources 4.2.5 Safety margins - individual units 4.2.6 Tables of limit values 4.2.7 Interaction criteria 4.2.8 Fixed poisons - criteria for use 4.2.9 Structural integrity policy and review requirements 4.2.10 Special controls (e.g., zoning for fire protection) 4.2.11 Criticality alarm system Chapter 5, Environmental Protection 5.1 Effluent control systems commitments sanitary wastas cooling water airborne liquid solid
. Chapter 5 (Cont'd) 5.2 Effluent and environmental monitoring commitments
' ' ' ' ~
frequency of sampling and analysis, type samples, a
location of sampling points components analyzed, radio!ogical and nonradiological for airborne, liquid, other (e.g., soil, vegetation) action levels and actions to be taken records Chapter 6, Special Process and Industrial Safety Requirements Chauter 7, Decommissioning Plan Chapter 8, Emergency Plaa S
e
9 8-Part II, Safety Demonstration Chapter 1, Overview of the Operation Corporate information, including financial qualifications
~ -"-
Summary of operating objective _and process Site description Location of buildings onsite Maps History (brief) of license Chapter 2,Facilitydescription(processdetailsinChapter8)
Plant layout Utilities, including emergency power and systems connected to emergency power Heating, ventilation and air conditioning Waste disposal Chemical storage Security Fire protection (including evidence of insurability with one of nuclear insurance pools and conformance to a building code)
- .. Chaoter 3, Oraanization and Personnel Unit functions (including safety committees)
Organization charts Organization procedures
~ ~ = -
a Functions of key positions Specifics on education and experience of key personnel Chapter 4. Radiation Protection Procedures and Equipment Procedures Work rules Posting and labeling Personnel monitoring Surveys Reports and records Instruments Protective clothing Dosimetry Chapter 5, Occupational Radiation Exposures Description of exposure control program, detailed review of exposure records and records of airbone concentrations (over the last two year period) to show conformance to ALARA commitment as regards exposures of operating personnel (tables and graphs of levels versus time) 2133 280 O
,. Chantor 6, Environmental Safety - Radioloaical & Non-Radioloaical Description of releases, controls, monitoring tables and/or graphs of levels discharged (historical) to show commitment to ALARA as regards w
discharges to the environment a
Chapter 7, Nuclear Criticality Safety Description of administrative and technical procedures including references to data sources and validation of analytical methods Chapter 8 Process Description and Safety Analyses Step-by-step description of process (including auxiliary operations, waste disposal, etc.) with an accompanying process, industrial, radiological and nuclear criticality safety analysis for each step include plans showing location of criticality detectors and alarms (and describe equipment)
,,.4 The chapter should illustrate application of the methods in Part I, Chapter 4.0, Section 4.2.
Chapter 9, Accident Analyses Descriptions of scenarios and resulting impacts Onsite and offsite flow limiting events were determined 2133 281
~
.