ML20058P682
| ML20058P682 | |
| Person / Time | |
|---|---|
| Site: | Claiborne |
| Issue date: | 10/14/1993 |
| From: | LOUISIANA ENERGY SERVICES |
| To: | |
| Shared Package | |
| ML20058P662 | List: |
| References | |
| NUDOCS 9310250148 | |
| Download: ML20058P682 (93) | |
Text
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r Page 1 of 2 Louisiana Energy Services e
Safety Analysis Report Push-Pull Instructions Revision 16 October 14, 1993 y
Remove Insert
" Table of Contents" from SAR " Table of Contents" into SAR Volume I Volume I
- pages vii and x
- pages vii and x
" Table of ontents" from SAR " Table of Contents" into SAR Volume I Volume II
- pages vai and x
- pages vii and x
" Table of Contents" from SAR " Table of Contents" into SAR' I
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volume III Volume III
- pages vii and x
- pages vii and x
" Table of Contents" from SAR " Table of Contents" into SAR Volume IV Volume IV
- pages vii and x
- pages vii and x
" Table of Contents" from SAR " Table of Contents" into SAR Volume V Volume V
- pages vii and x
- pages vii and x
" Table of Contents" from SAR " Table of Contents" into SAR Volume VI Volume VI
- pages vii and x
- pages vii and x
" Table of Contents" from SAR " Table of Contents" into SAR Volume VII Volume VII
- pages vii and x
- pages vii and x Notes:
1)
Each page affected by this revision has the month and year of the revision printed in the lower right hand corner of the page.
2)
The " List of Ef fective Pages" contains the latest revision and date of the revision affecting the page.
3)
All changes or additions to text of each document are indicated by a sidebar (l) in the right hand margin. In the case of deletion of i
- text, the sidebar appears in the right hand margin with a perpendicular line towards the text (i ) indicating where material was deleted.
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PDR ADOCK 07003070 L
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Page 2 of 2 Louisiana Energy Services Safety Analysis Report Push-Pull Instructions Revision 16 October 14, 1993
" Table of Contents" from SAR " Table of Contents" into SAR Volume VIII Volume VIII
- pages vii and x
- pages vii and x
" List of Effective Pages"
" List of Effective Pages"
- pages 1 - 41
- pages 1 - 41 pages 8 2-i through 8.2-14 pages 8.2-i through 8.2-14 Table 8.2-2 Table 8.2-2 pages 11.1-i through 11.1-16 pages 11.1-i through 11.1-14 O
Notes:
1)
Each page affected by this revision has the month and year of the revision printed in the lower right hand corner of the page.
2)
The " List of Effective Pages" contains the latest revision and date of the revision affecting the page.
3)
All changes or additions to text of each document are indicated by a sidebar (l) in the right hand margin.
In the case of deletion of i
- text, the sidebar appears in the right hand margin with a O
perpendicular line towards the text (i ) indicating where material was deleted.
V LOUISIANA ENERGY SERVICES
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SAFETY ANALYSIS REPORT TABLE OF CONTENTS Section Page Number 7.2.2 WASTES REQUIRING OFFSITE DISPOSAL 7.2-5 7.2.3 OTHER HAZARDOUS MATERIALS 7.2-9 8.0 RADIATION PROTECTION
-8.0-1 8.1 RADIATION PROTECTION OBJECTIVES 8.1-1 8.1.1 PHILOSOPHY 8.1-1 8.1.2 RESPONSIBILITIES 8.1-2 8.2 ONSITE CONTAMINATION CONTROL 8.2-1 8.2.1 RADIOLOGICAL ACCESS ZONES 8.2-1 8.2.2 ACCESS AND EGRESS CONTROL 8.2-3 8.2.3 CONTAMINATION AND RADIATION CONTROL 8.2-7 8.2-.4 MAINTENANCE AREAS AND PROCEDURES 8.2-10 8.2.5 DECONTAMINATION PROVISIONS 8.2-13 8.3 EFFLUENT RADIOACTIVITY CONTROL 8.3-1 8.3.1 SEPARATIONS BUILDING VENTILATION 8.3-1 O'
8.3.2 PROCESS VENTS 8.3-2 8.3.3 LIQUID EFFLUENTS-8.3-2 8.4 AREA SURVEILLANCE 8.4-1 8.4.1 AREA RADIATION MONITORS 8.4-1 8.4.2 CRITICALITY MONITORS 8.4-2 8.5 ESTIMATED PERSON-REM OFFSITE EXPOSURES 8.5-1 8.5.1 EFFLUENT AND ENVIRONMENTAL MONITORING PROGRAM 8.5-2 8.5.2 ANALYSIS OF MULTIPLE CONTRIBUTION 8.5-7.
8.5.3 ESTIMATED EXPOSURES 8.5-8 Volume VIII
9.0 INTRODUCTION
9.0-1 9.0.1 GUIDELINES FOR PUBLIC EXPOSURE TO HAZARDOUS CHEMICALS 9.0-1 9.0.2 EVENTS CATEGORIZED BY PREDICTED CONSEQUENCES 9.0-1 9.0.3 APPROACHES USED TO PERFORM EVENT ANALYSES 9.0-2 9.O.4 SIGNIFICANCE OF PLANT DESIGN AND OPERATING FEATURES TO THE EVENT ANALYSIS 9.0-3 9.0.5 URENCO OPERATING HISTORY 9.0-4 9.0.6
SUMMARY
9.0-7
(/
9.1 ABNORMAL OPERATIONS 9.1-1 9.1.1 CENTRIFUGE CONTAINMENT FAILURE 9.1-1 vii October 1993
I l
LOUISIANA ENERGY SERVICES i
[,
SAFETY ANALYSIS REPORT x-TABLE OF CONTENTS Section Page Number PROCEDURES 11.0-1 11.1 ORGANIZATIONAL STRUCTURE 11.1-1 11.1.1 CORPORATE FINANCIAL RESPONSIBILITIES 11.1-1 11.1.2 CORPORATE FUNCTIONS, RESPONSIBILITIES, AND AUTHORITIES 11.1-1 11.1.3 OPERATING ORGANIZATION 11.1-2 11.1.4 PERSONNEL QUALIFICATIONS REQUIREMENTS 11.1-9 11.1.5 TRAINING 11.1-14 11.2 TESTING - PREOPERATIONAL AND OPERATIONAL 11.2-1 11.2.1 OBJECTIVES 11.2-1 11.2.2 PROCEDURE FORMAT 11.2-2 11.2.3 PREOPERATIONAL AND START-UP TESTS 11.2-4 11.2.4 OPERATIONAL TESTING PROGRAM 11.2-6 11.3 TRAINING PROGRAM 11.3-1 11.3.1 PROGRAM DESCRIPTION 11.3-1
()
11.3.2 TRAINING PROGRAM EVALUATIONS 11.3-11 i
11.3.3 ADMINISTRATIVF AND RECORDS 11.3-11 11.4 FACILITY OPERATIONS 11.4-1 11.4.1 FACILITY PROCEDURES 11.4-1 11.4.2 FACILITY RECORDS 11.4-8 11.4.3 REVIEW AND AUDIT ORGANIZATIONS 11.4-11 11.4.4 INTERNAL AUDITS AND INSPECTIONS 11.4-15 11.4.5 INVESTIGATIONS AND REPORTING 11.4-16 11.4.6 MODIFICATIONS TO FACILITIES AND EQUIPMENT.
11.4-17 l
11.5 RESTRICTED DATA SECURITY PROGRAM 11.5-1 11.5.1 SITE AND FACILITY DESCRIPTION 11.5-1 j
11.5.2 SECURITY ORGANIZATION 11.5-1 11.5.3 TYPES OF CLASSIFIED INFORMATION 11.5-2 11.5.4 PERSONNEL SECURITY 11.5-2 11.5.5 SECURITY FACILITIES 11.5-3 11.5.6 SECURITY AREAS 11.5-3 11.5.7 INTRUSION ALARM SYSTEM 11.5-3 11.5.8 PROTECTION OF CLASSIFIED MATTER WHILE'IN USE 11.5-4
- i 11.5.9 SECURITY EDUCATION 11.5-5 11.5.10 CLASSIFICATION IdH) DECLASSIFICATION 11.5-6 O
11.5.11 CONTROL OF CLASSIFIED DOCUMENTS 11.5-6 11.5.12 VISITOR CONTROL 11.5-6 X
October 1993 y
e
l LOUISIANA ENERGY SERVICES
. (],/
/
SAFETY ANALYSIS REPORT TABLE OF CONTENTS Section Page Number 7.2.2 WASTES REQUIRING OFFSITE DISPOSAL 7.2-5 7.2.3 OTHER HAZARDOUS MATERIALS 7.2-9 8.O RADIATION PROTECTION 8.0-1 8.1 RADIATION PROTECTION OBJECTIVES 8.1-1 8.1.1 PHILOSOPHY 8.1-1 8.1.2 RESPONSIBILITIES 8.1-2 8.2 ONSITE CONTAMINATION CONTROL 8.2-1 8.2.1 RADIOLOGICAL ACCESS ZONES 8.2-1 8.2.2 ACCESS AND EGRESS CONTROL 8.2-3 8.2.3 CONTAMINATION AND RADIATION CONTROL 8.2-7 8.2.4 MAINTENANCE AREAS AND PROCEDURES 8.2-10 8.2.5 DECONTAMINATION PROVISIONS 8.2-13 8.3 EFFLUENT RADIOACTIVITY CONTROL 8.3-1 8.3.1 SEPARATIONS BUILDING VENTILATION 8.3-1 8.3.2 PROCESS VENTS 8.3-2 8.3.3 LIQUID EFFLUENTS 8.3-2 8.4 AREA SURVEILLANCE 8.4-1 8.4.1 AREA RADIATION MONITORS 8.4-1 8.4.2 CRITICALITY MONITORS 8.4-2 f
8.5 ESTIMATED PERSON-REM OFFSITE EXPOSURES 8.5-1 8.5.1 EFFLUENT AND ENVIRONMENTAL MONITORING PROGRAM 8.5-2 8.5.2 ANALYSIS OF MULTIPLE CONTRIBUTION 8.5-7 8.5.3 ESTIMATED EXPOSURES 8.5-8 Volume VIII
9.0 INTRODUCTION
9.0-1 9.0.1 GUIDELINES FOR PUBLIC EXPOSURE TO HAZARDOUS CHEMICALS 9.0-1 9.0.2 EVENTS CATEGORIZED.BY PREDICTED CONSEQUENCES 9.0-1 9.0.3 APPROACHES USED TO PERFORM EVENT ANALYSES 9.0-2 9.0.4 SIGNIFICANCE OF PLANT DESIGN AND OPERATING FEATURES TO THE EVENT ANALYSIS 9.0 9.0.5 URENCO OPERATING HISTORY 9.0-4 9.0.6
SUMMARY
9.0-7 9.1 ABNORMAL OPERATIONS 9.1-1 9.1.1 CENTRIFUGE CONTAINMENT FAILURE 9.1-1 vii October 1993 1
l 1
I LOUISIANA ENERGY SERVICES O
SAFETY ANALYSIS REPORT TABLE OF CONTENTS Section Page Number PROCEDURES 11.0-1 11.1 ORGANIZATIONAL STRUCTURE 11.1-1 11.1.1 CORPORATE FINANCIAL RESPONSIBILITIES 11.1-1 11.1.2 CORPORATE FUNCTIONS, RESPONSIBILITIES, AND AUTHORITIES 11.1-1 11.1.3 OPERATING ORGANIZATION 11.1-2 11.1.4 PERSONNEL QUALIFICATIONS REQUIREMENTS 11.1-9 11.1.5 TRAINING 11.1-14 11.2 TESTING - PREOPERATIONAL AND OPERATIONAL 11.2-1 11.2.1 OBJECTIVES 11.2-1 11.2.2 PROCEDURE FORMAT 11.2-2
[
11.2.3 PREOPERATIONAL AND START-UP TESTS 11.2-4 11.2.4 OPERATIONAL TESTING PROGRAM 11.2-6 11.3 TRAINING PROGRAM 11.3-1 11.3.1 PROGRAM DESCRIPTION 11.3-1 0
11.3.2 TRAINING PROGRAM EVALUATIONS 11.3-11 11.3.3 ADMINISTRATIVE AND RECORDS 11.3-11 11.4 FACILITY OPERATIONS 11.4-1 11.4.1 FACILITY PROCEDURES 11.4-1 11.4.2 FACILITY RECORDS 11.4-8 11.4.3 REVIEW AND AUDIT ORGANIZATIONS 11.4-11 11.4.4 INTERNAL AUDITS AND INSPECTIONS 11.4-15 11.4.5 INVESTIGATIONS AND REPORTING 11.4-16 11.4.6 MODIFICATIONS TO FACILITIES'AND EQUIPMENT 11.4-17 11.5 RESTRICTED DATA SECURITY PROGRAM 11.5-1 11.5.1 SITE AND FACILITY DESCRIPTION 11.5-1 11.5.2 SECURITY ORGANIZATION 11.5-1 11.5.3 TYPES OF CLASSIFIED INFORMATION 11.5-2 11.5.4 PERSONNEL SECURITY 11.5-2 11.5.5 SECURITY FACILITIES 11.5-3 11.5.6 SECURITY AREAS 11.5-3 11.5.7 INTRUSION ALARM SYSTEM 11.5-3' 11.5.8 PROTECTION OF CLASSIFIED MATTER WHILE IN USE 11.5-4 11.5.9 SECURITY EDUCATION 11.5-5 11.5.10 CLASSIFICATION AND DECLASSIFICATION 11.5-6
()
11.5.11 CONTROL OF CLASSIFIED DOCUMENTS 11.5-6 11.5.12 VISITOR CONTROL 11.5-6 x
October 1993
i LOUISIANA ENERGY SERVICES
/^
SAFETY ANALYSIS REPORT TABLE OF CONTENTS Section Page Number 7.2.2 WASTES REQUIRING OFFSITE DISPOSAL 7.2-5 7.2.3 OTHER HAZARDOUS MATERIALS 7.2-9 8.0 RADIATION PROTECTION 8.0-1 8.1 RADIATION PROTECTION OBJECTIVES 8.1-1 8.1.1 PHILOSOPHY 8.1-1 8.1.2 RESPONSIBILITIES 8.1-2 8.2 ONSITE CONTAMINATION CONTROL 8.2-1 8.2.1 RADIOLOGICAL ACCESS ZONES 8.2-1 8.2.2 ACCESS AND EGRESS CONTROL 8.2-3 8.2.3 CONTAMINATION AND RADIATION CONTROL 8.2-7 8.2.4 MAINTENANCE AREAS AND PROCEDURES 8.2-10 8.2.5 DECONTAMINATION PROVISIONS 8.2-13 8.3 EFFLUENT RADIOACTIVITY CONTROL 8.3-1 8.3.1 SEPARATIONS BUILDING VENTILATION 8.3-1 8.3.2 PROCESS VENTS 8.3-2 8.3.3 LIQUID EFFLUENTS 8.3-2 8.4 AREA SURVEILLANCE 8.4-1 8.4.1 AREA RADIATION MONITORS 8.4-1 8.4.2 CRITICALITY MONITORS 8.4-2 8.5 ESTIMATED PERSON-REM OFFSITE EXPOSURES 8.5-1 8.5.1 EFFLUENT AND ENVIRONMENTAL MONITORING PROGRAM 8.5-2 8.5.2 ANALYSIS OF MULTIPLE CONTRIBUTION
'8.5-7 8.5.3 ESTIMATED EXPOSURES 8.5-8 Volume VIII 9.O INTRODUCTION 9.0-1 9.0.1 GUIDELINES FOR PUBLIC EXPOSURE TO HAZARDOUS CHEMICALS 9.0-1 9.0.2 EVENTS CATEGORIZED BY PREDICTED CONSEQUENCES 9.0-1 l
9.0.3 APPROACHES USED TO PERFORM EVENT ANALYSES 9.0-2 9.0.4 SIGNIFICANCE OF PLANT DESIGN AND OPERATING FEATURES TO THE EVENT ANALYSIS 9.0-3 9.0.5 URENCO OPERATING HISTORY 9.0 :
9.0.6
SUMMARY
9.0-7 9.1 ABNORMAL OPERATIONS 9.1-1 9.1.1 CENTRIFUGE CONTAINIENT FAILURE 9.1-1 i
vii October 1993 i
LOUISIANA ENERGY SERVICES SAFETY ANALYSIS REPORT TABLE OF CONTENTS Section Pace Number PROCEDURES 11.0-1 11.1 ORGANIZATIONAL STRUCTURE 11.1-1 11.1.1 CORPORATE FINANCIAL RESPONSIBILITIES 11.1-1 11.1.2 CORPORATE FUNCTIONS, RESPONSIBILITIES, AND AUTHORITIES 11.1-1 11.1.3 OPERATING ORGANIZATION 11.1-2 11.1.4 PERSONNEL QUALIFICATIONS REQUIREMENTS 11.1-9 11.1.5 TRAINING 11.1-14 11.2 TESTING - PREOPERATIONAL AND OPERATIONAL 11.2-1 11.2.1 OBJECTIVES 11.2-1 11.2.2 PROCEDURE FORMAT 11.2-2 11.2.3 PREOPERATIONAL AND START-UP TESTS 11.2-4 11.2.4 OPERATIONAL TESTING PROGRAM 11.2-6 l
11.3 TRAINING PROGRAM 11.3-1 11.3.1 PROGRAM DESCRIPTION 11.3-1 0
11.3.2 TRAINING PROGRAM EVALUATIONS 11.3-11 11.3.3 ADMINISTRATIVE AND RECORDS 11.3-11 11.4 FACILITY OPERATIONS 11.4-1 11.4.1 FACILITY PROCEDURES 11.4-1 11.4.2 FACILITY RECORDS 11.4-8 11.4.3 REVIEW AND AUDIT ORGANIZATIONS 11.4-11 11.4.4 INTERNAL AUDITS AND INSPECTIONS 11.4-15 11.4.5 INVESTIGATIONS AND REPORTING 11.4-16 11.4.6 MODIFICATIONS TO FACILITIES AND EQUIPMENT 11.4-17 11.5 RESTRICTED DATA SECURITY PROGRAM 11.5-1 11.5.1 SITE AND FACILITY DESCRIPTION 11.5-1 11.5.2 SECURITY ORGANIZATION 11.5-1 11.5.3 TYPES OF CLASSIFIED INFORMATION 11.5-2 11.5.4 PERSONNEL SECURITY 11.5-2 l
11.5.5 SECURITY FACILITIES 11.5-3 l
l 11.5.6 SECURITY AREAS 11.5-3 11.5.7 INTRUSION ALARM SYSTEM 11.5-3 11.5.8 PROTECTION OF CLASSIFIED MATTER WHILE IN USE 11.5-4 11.5.9 SECURITY EDUCATION 11.5-5 11.5.10 CLASSIFICATION AND DECLASSIFICATION 11.5-6 11.5.11 CONTROL OF CLASSIFIED DOCU1ENTS 11.5-6 11.5.12 VISITOR CONTROL 11.5-6 x
October 1993
LOUISIANA ENERGY SERVICES
[V i
SAFETY ANALYSIS REPORT TABLE OF CONTENTS Section Page Number 7.2.2 WASTES REQUIRING OFFSITE DISPOSAL 7.2-5 7.2.3 OTHER HAZARDOUS MATERIALS 7.2-9 8.0 RADIATION PROTECTION 8.0-1 8.1 RADIATION PROTECTION OBJECTIVES 8.1-1 8.1.1 PHILOSOPHY 8.1-1 8.1.2 RESPONSIBILITIES 8.1-2 8.2 ONSITE CONTAMINATION CONTROL 8.2-1 8.2.1 RADIOLOGICAL ACCESS ZONES 8.2-1 8.2.2 ACCESS AND EGRESS CONTROL 8.2-3 8.2.3 CONTAMINATION AND RADIATION CONTROL 8.2-7 8.2.4 MAINTENANCE AREAS AND PROCEDURES 8.2-10 8.2.5 DECONTAMINATION PROVISIONS 8.2-13 8.3 EFFLUENT RADIOACTIVITY CONTROL 8.3-1 8.3.1 SEPARATIONS BUILDING VENTILATION 8.3-1 O'
8.3.2 PROCESS VENTS 8.3-2 8.3.3 LIQUID EFFLUENTS 8.3-2 8.4 AREA SURVEILLANCE 8.4-1 8.4.1 AREA RADIATION MONITORS 8.4-1 8.4.2 CRITICALITY MONITORS 8.4-2 8.5 ESTIMATED PERSON-REM OFFSITE EXPOSURES 8.5-1 8.5.1 EFFLUENT AND ENVIRONMENTAL MONITORING PROGRAM 8.5-2 8.5.2 ANALYSIS OF MULTIPLE CONTRIBUTION 8.5-7 8.5.3 ESTIMATED EXPOSURES 8.5-8 Volume VIII
9.0 INTRODUCTION
9.0-1 9.0.1 GUIDELINES FOR PUBLIC EXPOSURE TO HAZARDOUS CHEMICALS 9.0-1 9.0.2 EVENTS CATEGORIZED BY PREDICTED CONSEQUENCES 9.0-1
~
9.0.3 APPROACHES USED TO PERFORM EVENT ANALYSES 9.0-2 9.0.4 SIGNIFICANCE OF PLANT DESIGN AND OPERATING i
FEATURES TO THE EVENT ANALYSIS 9.0-3 9.0.5 URENCO OPERATING HISTORY 9.0-4 9.0.6
SUMMARY
9.0-7 l
9.1 ABNORMAL OPERATIONS 9.1-1 9.1.1 CENTRIFUGE CONTAINMENT FAILURE 9.1-1 l
vii October 1993 j
I
i LOUISIANA ENERGY SERVICES I
/
SAFETY ANALYSIS REPORT TABLE OF CONTENTS Section Page Number PROCEDURES 11.0-1 11.1 ORGANIZATIONAL STRUCTURE 11.1-1 11.1.1 CORPORATE FINANCIAL RESPONSIBILITIES 11.1-1 11.1.2 CORPORATE FUNCTIONS, RESPONSIBILITIES, AND AUTHORITIES 11.1-1 11.1.3 OPERATING ORGANIZATION 11.1-2 11.1.4 PERSONNEL QUALIFICATIONS REQUIREMENTS 11.1-9 11.1.5 TRAINING 11.1-14 11.2 TESTING - PREOPERATIONAL AND OPERATIONAL 11.2-1 i
11.2.1 OBJECTIVES 11.2-1 11.2.2 PROCEDURE FORMAT 11.2-2 11.2.3 PREOPERATIONAL AND START-UP TESTS 11.2-4 11.2.4 OPERATIONAL TESTING PROGRAM 11.2-6 11.3 TRAINING PROGRAM-11.3-1 11.3.1 PROGRAM DESCRIPTION 11.3-1
(
11.3.2 TRAINING PROGRAM EVALUATIONS 11.3-11 11.3.3 ADMINISTRATIVE AND RECORDS 11.3-11 11.4 FACILITY OPERATIONS 11.4-1 11.4.1 FACILITY PROCEDURES 11.4-1 11.4.2 FACILITY RECORDS 11.4-8 11.4.3 REVIEW AND AUDIT ORGANIZATIONS 11.4-11 11.4.4 INTERNAL AUDITS AND INSPECTIONS 11.4-15 11.4.5 INVESTIGATIONS AND REPORTING 11.4-16 11.4.6 MODIFICATIONS TO FACILITIES AND EQUIPMENT 11.4-17 11.5 RESTRICTED DATA SECURITY PROGRAM 11.5-1 11.5.1 SITE IJH) FACILITY DESCRIPTION 11.5-1 11.5.2 SECURITY ORGANIZATION 11.5-1 11.5.3 TYPES OF CLASSIFIED INFORMATION 11.5-2 11.5.4 PERSONNEL SECURITY 11.5,
11.5.5 SECURITY FACILITIES 11.5-3 11.5.6 SECURITY AREAS 11.5-3 11.5.7 INTRUSION ALARM SYSTEM 11.5-3 l
11.5.8 PROTECTION OF CLASSIFIED MATTER WHILE IN USE 11.5-4 11.5.9 SECURITY EDUCATION 11.5-5 11.5.10 CLASSIFICATION AND DECLASSIFICATION 11.5-6
()
11.5.11 CONTROL OF CLASSIFIED DOCUMENTS 11.5-6 11.5.12 VISITOR CONTROL 11.5-6 x
October 1993-
LOUISIANA ENERGY SERVICES j'"
SAFETY ANALYSIS REPORT i
TABLE OF CONTENTS Section Page Number 7.2.2 WASTES REQUIRING OFFSITE DISPOSAL 7.2-5 7.2.3 OTHER HAZARDOUS MATERIALS 7.2-9 8.0 RADIATION PROTECTION 8.0-1 8.1 RADIATION PROTECTION OBJECTIVES 8.1-1 8.1.1 PHILOSOPHY 8.1-1 8.1.2 RESPONSIBILITIES 8.1-2 8.2 ONSITE CONTAMINATION CONTROL 8.2-1 8.2.1 RADIOLOGICAL ACCESS ZONES 8.2-1 8.2.2 ACCESS AND EGRESS CONTROL 8.2-3 8.2.3 CONTAMINATION AND RADIATION CONTROL 8.2-7 8.2.4 MAINTENANCE AREAS AND PROCEDURES 8.2-10 8.2.5 DECONTAMINATION PROVISIONS 8.2-13 8.3 EFFLUENT RADIOACTIVITY CONTROL 8.3-1 8.3.1 SEPARATIONS BUILDING VENTILATION 8.3-1
('
8.3.2 PROCESS VENTS 8.3-2
's 8.3.3 LIQUID EFFLUENTS 8.3-2 8.4 AREA SURVEILLANCE 8.4-1 8.4.1 AREA RADIATION MONITORS 8.4-1 8.4.2 CRITICALITY MONITORS 8.4-2 8.5 ESTIMATED PERSON-REM OFFSITE EXPOSURES
'8.5-1 8.5.1 EFFLUENT AND ENVIRONMENTAL MONITORING PROGRAM 8.5-2 8.5.2 ANALYSIS OF MULTIPLE CONTRIBUTION 8.5-7 8.5.3 ESTIMATED EXPOSURES 8.5-8 Volume VIII
9.0 INTRODUCTION
9.0-1 9.0.1 GUIDELINES FOR PUBLIC EXPOSURE TO HAZARDOUS CHEMICALS 9.0-1 9.0.2 EVENTS CATEGORIZED BY PREDICTED CONSEQUENCES 9.0-1 9.0.3 APPROACHES USED TO PERFORM EVENT ANALYSES 9.0-2 9.0.4 SIGNIFICANCE OF PLANT DESIGN AND OPERATING FEATURES TO THE EVENT ANALYSIS 9.0-3 9.0.5 URENCO O"ERATING HISTORY 9.0-4 9.0.6
SUMMARY
9.0-7
()
9.1 ABNORMAL OPERATIONS 9.1-1 9.1.1 CENTRIFUGE CONTAINMENT FAILURE 9.1-1 vii October 1993
\\
LOUISIANA ENERGY SERVICES
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SAFETY ANALYSIS REPORT TABLE OF CONTENTS Section Page Number PROCEDURES 11.0-1 11.1 ORGANIZATIONAL STRUCTURE 11.1-1 11.1.1 CORPORATE FINANCIAL RESPONSIBILITIES 11.1-1 11.1.2 CORPORATE FUNCTIONS, RESPONSIBILITIES, AND AUTHORITIES 11.1-1 11.1.3 OPERATING ORGANIZATION 11.1-2 11.1.4 PERSONNEL QUALIFICATIONS REQUIREMENTS 11.1-9 11.1.5 TRAINING 11.1-14 11.2 TESTING - PREOPERATIONAL AND OPERATIONAL 11.2-1 11.2.1 OBJECTIVES 11.2-1 11.2.2 PROCEDURE FORMAT 11.2-2 11.2.3 PREOPERATIONAL AND START-UP TESTS 11.2-4 11.2.4 OPERATIONAL TESTING PROGRAM 11.2-6 11.3 TRAINING PROGRAM 11.3-1 11.3.1 PROGRAM DESCRIPTION 11.3-1 0
11.3.2 TRAINING PROGRAM EVALUATIONS 11.3-11 11.3.3 ADMINISTRATIVE AND RECORDS 11.3-11 11.4 FACILITY OPERATIONS 11.4-1 11.4.1 FACILITY PROCEDURES 11.4-1 11.4.2 FACILITY RECORDS 11.4-8 11.4.3 REVIEW AND AUDIT ORGANIZATIONS 11.4-11 11.4.4 INTERNAL AUDITS AND INSPECTIONS 11.4-15 11.4.5 INVESTIGATIONS AND REPORTING 11.4-16 11.4.6 MODIFICATIONS TO FACILITIES AND EQUIPMENT 11.4-17 11.5 RESTRICTED DATA SECURITY PROGRAM 11.5-1 11.5.1 SITE AND FACILITY DESCRIPTION 11.5-1 11.5.2 SECURITY ORGANIZATION 11.5-1 11.5.3 TYPES OF CLASSIFIED INFORMATION 11.5-2 I
11.5.4 PERSONNEL SECURITY 11.5-2 11.5.5 SECURITY FACILITIES 11.5-3 11.5.6 SECURITY AREAS 11.5-3 11.5.7 INTRUSION ALARM SYSTEM 11.5-3 11.5.8 PROTECTION OF CLASSIFIED MATTER WHILE IN USE 11.5-4 11.5.9 SECURITY EDUCATION 11.5-5 11.5.10 CLASSIFICATION AND DECLASSIFICATION 11.5-6
()
11.5.11 CONTROL OF CLASSIFIED DOCUMENTS 11.5-6 11.5.12 VISITOR CONTROL 11.5-6 x
October 1993
LOUISIANA ENERGY' SERVICES
[
SAFETY ANALYSIS REPORT TABLE OF CONTENTS Section Page Number 7.2.2 WASTES REQUIRING OFFSITE DISPOSAL 7.2-5 7.2.3 OTHER HAZARDOUS MATERIALS 7.2-9 8.0 RADIATION PROTECTION 8.0-1 8.1 RADIATION PROTECTION OBJECTIVES 8.1-1 8.1.1 PHILOSOPHY 8.1-1 8.1.2 RESPONSIBILITIES 8.1-2 8.2 ONSITE CONTAMINATION CONTROL 8.2-1 8.2.1 RADIOLOGICAL ACCESS ZONES 8.2-1 8.2.2 ACCESS AND EGRESS CONTROL 8.2-3 8.2.3 CONTAMINATION AND RADIATION CONTROL 8.2-7 8.2.4 MAINTENANCE AREAS AND PROCEDURES 8.2-10:
8.2.5 DECONTAMINATION PROVISIONS 8.2-13 8.3 EFFLUENT RADIOACTIVITY CONTROL 8.3-1 8.3.1 SEPARATIONS BUILDING VENTILATION 8.3-1 8.3.2 PROCESS VENTS 8.3-2
(
8.3.3 LIQUID EFFLUENTS 8.3-2 8.4 AREA SURVEILLANCE 8.4-1 8.4.1 AREA RADIATION MONITORS 8.4-1 8.4.2 CRITICALITY MONITORS 8.4-2 8.5 ESTIMATED PERSON-REM OFFSITE EXPOSURES 8.5-1 l
8.5.1 EFFLUENT AND ENVIRONMENTAL MONITORING PROGRAM 8.5-2 i
8.5.2 ANALYSIS OF MULTIPLE CONTRIBUTION 8.5-7 8.5.3 ESTIMATED EXPOSURES 8.5-8 7
Volume VIII
9.0 INTRODUCTION
9.0-1 l
9.0.1 GUIDELINES FOR PUBLIC EXPOSURE TO HAZARDOUS I
CHEMICALS 9.0-1 9.0.2 EVENTS CATEGORIZED BY PREDICTED CONSEQUENCES 9.0-1 9.0.3 APPROACHES USED TO PERFORM EVENT ANALYSED 9.0-2' I
9.0.4 SIGNIFICANCE OF PLANT DESIGN AND OPERATING i
FEATURES TO THE EVENT ANALYSIS 9.0-3 9.0.5 URENCO OPERATING HISTORY 9.0-4 i
9.0.6
SUMMARY
9.0-7
.(
9.1 ABNORMAL OPERATIONS 9.1-1 j
9.1.1 CENTRIFUGE CONTAINMENT FAILURE 9.1-1 vii October 1993 L
?
l l
l LOUISIANA ENERGY SERVICES O
SAFETY ANALYSIS REPORT TABLE OF CONTENTS Section Page Number PROCEDURES 11.0-1 11.1 ORGANIZATIONAL STRUCTURE 11.1-1 11.1.1 CORPORATE FINANCIAL RESPONSIBILITIES 11.1-1 11.1.2 CORPORATE FUNCTIONS, RESPONSIBILITIES, AND 7
AUTHORITIES 11.1-1 11.1.3 OPERATING ORGANIZATION 11.1-2 11.1.4 PERSONNEL QUALIFICATIONS REQUIREMENTS 11.1 11.1.5 TRAINING 11.1-14 11.2 TESTING - PREOPERATIONAL AND OPERATIONAL 11.2-1 7
11.2,1 OBJECTIVES 11.2-1 11.2.2 PROCEDURE FORMAT 11.2-2 11.2.3 PREOPERATIONAL AND START-UP TESTS 11.2-4 11.2.4 OPERATIONAL TESTING PROGRAM 11.2-6 11.3 TRAINING PROGRAM 11.3-1 11.3.1 PROGRAM DESCRIPTION 11.3-1
[
11.3.2 TRAINING PROGRAM EVALUATIONS 11.3-11 11.3.3 ADMINISTRATIVE AND RECORDS 11.3-11 l
11.4 FACILITY OPERATIONS 11.4-1 11.4.1 FACILITY PROCEDURES 11.4-1 11.4.2 FACILITY RECORDS 11.4-8 11.4.3 REVIEW AND AUDIT ORGANIZATIONS 11.4-11 11.4.4 INTERNAL AUDITS AND INSPECTIONS 11.4-15 i
11.4.5 INVESTIGATIONS AND REPORTING 11.4-16 f
11.4.6 MODIFICATIONS TO FACILITIES AND EQUIPMENT 11.4-17 j
11.5 RESTRICTED DATA SECURITY PROGRAM 11.5-1
]
11.5.1 SITE AND FACILITY DESCRIPTION 11.5-1 11.5.2 SECURITY ORGANIZATION 11.5-1 11.5.3 TYPES OF CLASSIFIED INFORMATION 11.5-2 11.5.4 PERSONNEL SECURITY 11.5-2 11.5.5 SECURITY FACILITIES 11.5-3' l
11.5.6 SECURITY AREAS 11.5-3 11.5.7 INTRUSION ALARM SYSTEM 11.5-3 l
11.5.8 PROTECTION OF CLASSIFIED MATTER WHILE IN USE 11.5 j 11.5.9 SECURITY EDUCATION
_11.5-5.
l 11.5.10 CLASSIFICATION AND DECLASSIFICATION 11.5-6 11.5.11 CONTROL OF CLASSIFIED DOCUMENTS 11.5-6 11.5.12 VISITOR CONTROL 11.5-6 y
x October 1993 l
LOUISIANA ENERGY SERVICES'
,C SAFETY ANALYSIS REPORT TABLE OF CONTENTS Section Page Number 7.2.2 WASTES REQUIRING OFFSITE DISPOSAL 7.2-5 7.2.3 OTHER HAZARDOUS MATERIALS 7.2-9 8.0 RADIATION PROTECTION 8.0-1 8.1 RADIATION PROTECTION OBJECTIVES 8.1-1 8.1.1 PHILOSOPHY 8.1-1 8.1.2 RESPONSIBILITIES 8.1-2 8.2 ONSITE CONTAMINATION CONTROL 8.2-1 8.2.1 RADIOLOGICAL ACCESS ZONES 8.2-1 8.2.2 ACCESS AND EGRESS CONTROL 8.2-3 8.2.3 CONTAMINATION AND RADIATION CONTROL 8.2-7 8.2.4 MAINTENANCE AREAS AND PROCEDURES 8.2-10 8.2.5 DECONTAMINATION PROVISIONS 8.2-13.
8.3 EFFLUENT RADIOACTIVITY CONTROL 8.3-1 8.3.1 SEPARATIONS BUILDING VENTILATION 8.3-1 8.3.2 PROCESS VENTS 8.3-2 8.3.3 LIQUID EFFLUENTS 8.3-2 8.4 AREA SURVEILLANCE 8.4-1 8.4.1 AREA RADIATION MONITORS 8.4-1 8.4.2 CRITICALITY MONITORS 8.4 ;
8.5 ESTIMATED PERSON-REM OFFSITE EXPOSURES 8.5 8.5.1 EFFLUENT AND ENVIRONMENTAL MONITORING PROGRAM 8.5-2 8.5.2 ANALYSIS OF MULTIPLE CONTRIBUTION 8.5-7 8.5.3 ESTIMATED EXPOSURES 8.5-8 Volume VIII
9.0 INTRODUCTION
9.0-1 9.0.1 GUIDELINES FOR PUBLIC EXPOSURE TO HAZARDOUS CHEMICALS 9.0-1 9.0.2 EVENTS CATEGORIZED BY PREDICTED CONSEQUENCES 9.0-1 9.0.3 APPROACHES USED TO PERFORM EVENT ANALYSES 9.0-2 9.0.4 SIGNIFICANCE OF PLANT DESIGN AND OPERATING FEATURES TO THE EVENT ANALYSIS 9.0-3 9.0.5 URENCO OPERATING HISTORY 9.0-4
)
9.0.6
SUMMARY
9.0-7 9.1 ABNORMAL OPERATIONS 9.1-1 9.1.1 CENTRIFUGE CONTAINMENT FAILURE 9.1-1 vii October 1993
LOUISIANA ENERGY SERVICES
(~'g SAFETY ANALYSIS REPORT
]
U TABLE OF CONTENTS l
Section Pace Number PROCEDURES 11.0-1 11.1 ORGANIZATIONAL STRUCTURE 11.1-1 11.1.1 CORPORATE FINANCIAL RESPONSIBILITIES 11.1-1 s
11.1.2 CORPORATE FUNCTIONS, RESPONSIBILITIES, AND AUTHORITIES 11.1-1 11.1.3 OPERATING ORGANIZATION 11.1-2 11.1.4 PERSONNEL QUALIFICATIONS REQUIREMENTS 11.1-9 11.1.5 TRAINING 11.1-14 11.2 TESTING - PREOPERAT.!ONAL AND OPERATIONAL 11.2-1 11.2.1 OBJECTIVES 11.2-1 l
11.2.2 PROCEDURE FORMAT
.1.2-2 11.2.3 PREOPERATIONAL AND START-UP TESTS 11.2-4 11.2.4 OPERATIONAL TESTING PROGRAM 11.2-6 11.3 TRAINING PROGRAM 11.3-1 11.3.1 PROGRAM DESCRIPTION 11.3-1
^
11.3.2 TRAINING PROGRAM EVALUATIONS 11.3-11 O
11.3.3 ADMINISTRATIVE AND RECORDS 11.3-11 f
11.4 FACILITY OPERATIONS 11.4 11.4.1 FACILITY PROCEDURES 11.4-1 11.4.2 FACILITY RECORDS 11.4-8 11.4.3 REVIEW AND AUDIT ORGANIZATIONS 11.4-11 11.4.4 INTERNAL AUDITS AND INSPECTIONS 11.4-15 11.4.5 INVESTIGATIONS AND REPORTING 11.4-16 11.4.6 MODIFICATIONS TO FACILITIES AND EQUIPMENT 11.4-17 i
11.5 RESTRICTED DATA SECURITY PROGRAM 11.5-1 11.5.1 SITE AND FACILITY DESCRIPTION 11.5-1
[
11.5.2 SECURITY ORGANIZATION 11.5-1 11.5.3 TYPES OF CLASSIFIED INFORMATION 11.5-2 11.5.4 PERSONNEL SECURITY 11.5-2
'I 11.5.5 SECURITY FACILITIES 11.5-3 11.5.6 SECURITY AREAS 11.5-3 11.5.7 INTRUSION ALARM SYSTEM 11.5-3 11.5.8 PROTECTION OF CLASSIFIED MATTER WHILE IN USE 11.5-4 e
11.5.9 SECURITY EDUCATION 11.5-5 l
11.5.10 CLASSIFICATION AND DECLASSIFICATION 11.5-6
(
11.5.11 CONTROL OF CLASSIFIED DOCUMENTS 11.5-6 11.5.12 VISITOR CONTROL 11.5-6 l
x October 1993 t
i
LOUISIANA ENERGY SERVICES SAFETY ANALYSIS REPORT TABLE OF CONTENTS q
Section Pace Number 7.2.2 WASTES REQUIRING OFFSITE DISPOSAL 7.2-5 7.2.3 OTHER HAZARDOUS MATERIALS 7.2-9 8.0 RADIATION PROTECTION 8.0-1 8.1 RADIATION PROTECTION OBJECTIVES 8.1-1 8.1.1 PHILOSOPHY 8.1-1 8.1.2 RESPONSIBILITIES 8.1-2 8.2 ONSITE CONTAMINATION CONTROL 8.2-1 l
8.2.1 RADIOLOGICAL ACCESS ZONES 8.2-1 8.2.2 ACCESS AND EGRESS CONTROL 8.2-3 8.2.3 CONTAMINATION AND RADIATION CONTROL 8.2-7 8.2.4 MAINTENANCE AREAS AND PROCEDURES 8.2-10 8.2.5 DECONTAMINATION PROVISIONS 8.2-13 8.3 EFFLUENT RADIOACTIVITY CONTROL 8.3-1 8.3.1 SEPARATIONS BUILDING VENTILATION 8.3-1 8.3.2 PROCESS VENTS 8.3-2 8.3.3 LIQUID EFFLUENTS 8.3-2 8.4 AREA SURVEILLANCE 8.4-1 8.4.1 AREA RADIATION MONITORS 8.4-1 8.4.2 CRITICALITY MONITORS 8.4-2 j
8.5 ESTIMATED PERSON-REM OFFSITE EXPOSURES 8.5-1
]
8.5.1 EFFLUENT AND ENVIRONMENTAL MONITORING PROGRAM 8.5-2 1
8.5.2 ANALYSIS OF MULTIPLE CONTRIBUTION 8.5-7 l
I 8.5.3 ESTIMATED EXPOSURES 8.5-8 Volume VIII
9.0 INTRODUCTION
9.0-1 9.0.1 GUIDELINES FOR PUBLIC EXPOSURE TO HAZARDOUS CHEMICALS 9.0-1 9.0.2 EVENTS CATEGORIZED BY PREDICTED CONSEQUENCES 9.0-1 9.0.3 APPROACHES USED TO PERFORM EVENT ANALYSES 9.0-2 j
9.0.4 SIGNIFICANCE OF PLANT DESIGN AND OPERATING FEATURES TO THE EVENT ANALYSIS 9.0-3 9.0.5 URENCO OPERATING HISTORY 9.0-4 9.0.6
SUMMARY
9.0-7
()
9.1 ABNORMAL OPERATIONS 9.1-1 9.1.1 CENTRIFUGE CONTAINMENT FAILURE 9.1-1 vii October 1993
LOUISIANA ENERGY SERVICES SAFETY ANALYSIS REPORT O
TABLE OF CONTENTS Section Page Number PROCEDURES 11.0-1 11.1 ORGANIZATIONAL STRUCTURE 11.1-1 11.1.1 CORPORATE FINANCIAL RESPONSIBILITIES 11.1-1 11.1.2 CORPORATE FUNCTIONS, RESPONSIBILITIES, AND AUTHORITIES 11.1-1 11.1.3 OPERATING ORGANIZATION 11.1-2 11.1.4 PERSONNEL QUALIFICATIONS REQUIREMENTS 11.1-9.
11.1.5 TRAINING 11.1-14 11.2 TESTING - PREOPERATIONAL AND OPERATIONAL 11.2-1 11.2.1 OBJECTIVES 11.2-1 11.2.2 PROCEDURE FORMAT 11.2-2 11.2.3 PREOPERATIONAL AND START-UP TESTS 11.2-4 11.2.4 OPERATIONAL TESTING PROGRAM 11.2-6 11.3 TRAINING PROGRAM 11.3-1 11.3.1 PROGRAM DESCRIPTION 11.3-1 11.3.2 TRAINING PROGRAM EVALUATIONS 11.3-11 0
11.3.3 ADMINISTRATIVE AND RECORDS 11.3-11 11.4 FACILITY OPERATIONS 11.4-1 11.4.1 FACILITY PROCEDURES 11.4-1 11.4.2 FACILITY RECORDS 11.4-8 11.4.3 REVIEW AND AUDIT ORGANIZATIONS 11.4-11 11.4.4 INTERNAL AUDITS AND INSPECTIONS 11.4-15 11.4.5 INVESTIGATIONS AND REPORTING 11.4-16 11.4.6 MODIFICATIONS TO FACILITIES AND EQUIPMENT 11.4-17.
11.5 RESTRICTED DATA SECURITY PROGRAM 11.5-1 11.5.1 SITE AND FACILITY DESCRIPTION 11.5-1 11.5.2 SECURITY ORGANIZATION 11.5 11.5.3 TYPES OF CLASSIFIED INFORMATION 11.5-2 1
11.5.4 PERSONNEL SECURITY 11.5-2
]
11.5.5 SECURITY FACILITIES 11.5-3 11.5.6 SECURITY AREAS 11.5 11.5.7 INTRUSION ALARM SYSTEM 11.5-3 11.5.8 PROTECTION OF CLASSIFIED MATTER WHILE IN USE 11.5-4' L
11.5.9 SECURITY EDUCATION 11.5-5 11.5.10 CLASSIFICATION AND DECLASSIFICATION 11.5-6
(
11.5.11 CONTROL OF CLASSIFIED DOCUMENTS 11.5-6 11.5.12 VISITOR CONTROL 11.5-6' x
October 1993 1
Fage 1 of 41 Louisiana Energy Services Safety Analysis Report List of Effective Pages October 14, 1993 Pace / Table /Figura Number
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15, 10/12/93 ii 15, 10/12/93 iii 15, 10/12/93 iv 15, 10/12/93 v
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Page/ Table / Figure Number
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F 3.3-4 original, 1/31/91 F-3.3-5 original, 1/31/91 j
F 3.3-6 5, 03/13/92 _
F 3.3-7 original,-1/31/91 F 3.3-8 original, 1/31/91 F 3.3-9 original, 1/31/91 F 3.3-10 5, 03/13/92 F 3.3-11 original', 1/31/91 F 3.3-12 original, 1/31/91
[
F 3.3-13 original, 1/31/91 F 3.3-14 5, 03/13/92 F 3.3-15 original, 1/31/91 i
p 3.4-i 6,
03/31/92 p 3.4-ii 6,
03/31/92
- NOTE:
p=page
[
A= Appendix i
F= Figure
.l O
T= Table
]
i
,=,
Page'8 of 41
'7 N Rev. 10/14/93-0
- U Pace / Table /Ficure Number
- Revision Number, Date of Revision p'3.4-iii original, 1/31/91 l
p 3.4-1 1,
08/16/91 p'3.4-2 original, 1/31/91 p 3.4-3 original, 1/31/91 i
p 3.4-4 original, 1/31/91 p 3.4-5 original, 1/31/91 p 3.4-6 1,
08/16/91 p 3.4-7 6, 03/31/92 p 3.4-8 6, 03/31/92 l
p 3.4-9 6, 03/31/92.
P 3.4-10 original, 1/31/91
.iU p 3.4-11 6, 03/31/92 p 3.4-12 original, 1/31/91 p 3.4-13 original, 1/31/91 i
p 3.4-14 original, 1/31/91 p 3.4-15 original, 1/31/91 p 3.4-16 original, 1/31/91 p 3.4-17 original, 1/31/91 p 3.4-18 original, 1/31/91 1
p 3.4-19 original, 1/31/91 p 3.4-20 6, 03/31/92 T 3.4-1 original, 1/31/91 O
T 3.4-1 (cont'd) original,o1/31/91 T 3.4-2 original, 1/31/91 T 3.4-3 (1 of 2) original, 1/31/91 T 3.4-3 (2 of 2) original, 1/31/91 T 3.4-4 (1 of 2) original, 1/31/91 j
T-3.4-4 (2 of 2) original, 1/31/91 1
T 3.4-5 6, 03/31/92 T 3.4-6 6, 03/31/92' T 3.4-7 6, 03/31/92 l
T 3.4-8 6,
03/31/92.
T 3.4-9 original, 1/31/91
-i T 3.4-10 original, 1/31/91.
1 T 3.4-11 original, 1/31/91 T 3'4-12 original, 1/31/91 T 3.4-13 original, 1/31/91-T 3.4-14 original, 1/31/91-T 3.4-15 original, 1/31/91 T 3.4-15 (cont'd) original, 1/31/91 F 3.4-1 original, 1/31/91
~4 F 3.4-2 original, 1/31/91 F 3.4-3 original, 1/31/91 n
- NOTE:
p=page A= Appendix F= Figure O
T= Table' l
i i
Page'9 of,
/~'
Rev 10/14/93 l
.i Pace / Table /Fioure Number *'
Revision Number, Date of Revision F 3.4-4 original, 1/31/91 F 3.4-5 original, 1/31/91 j
F 3.4-6 original, 1/31/91 i
F 3.4-7 original, 1/31/91 F 3.4-8
. original, 1/31/91 F 3.4-9 original, 1/31/91
.j F 3.4-10 original, 1/31/91 j
F 3.4-11 original, 1/31/91 F 3.4-12 original, 1/31/91 t
F 3.4-13 original, 1/31/91 F 3.4-14 6, 03/31/92 F 3.4-15 original, 1/31/91 l
F 3.4-16 original, 1/31/91 p 3.5-i 14, 07/30/93 p 3.5-ii 14,'07/30/93 p 3.5-iii 14, 07/30/93 p 3.5-1 14, 07/30/93 p 3.5-2 14, 07/30/93 l
p 3.5-3 14, 07/30/93 p 3.5-4 14, 07/30/93
-l p 3.5-5 14, 07/30/93 j
p 3.5-6 14, 07/30/93
[
p 3.5-7 14, 07/30/93 p 3.5-8 14, 07/30/93 p 3.5-9 14,-07/30/93 p 3.5-10 14, 07/30/93 p 3.5-11 14, 07/30/93
-i p 3.5-12 14, 07/30/93 i
p.3.5-13 14, 07/30/93 p 3.5-14 14, 07/30/93 p 3.5-15 14,-07/30/93 p 3.5-16 14, 07/30/93 p 3.5-17 14, 07/30/93 T 3.5-1 original, 1/31/91 T 3.5-2 original, 1/31/91 T 3.5-2 (cont'd) original, 1/31/91 T 3.5-3 original, 1/31/91 T 3.5-4 original, 1/31/91 T 3.5-4 (cont'd) original, 1/31/91" l
T'3.5-5 original, 1/31/91 T 3.5-5 (cont'd) original, 1/31/91 T 3.5-6 original, 1/31/91 T 3.5-7 original, 1/31/91
.i
- NOTE:
p=page A= Appendix F= Figure' g
T= Table
5 Page 10 of;41 Rev. 10/14/93
(
Pace / Table / Figure Number
- Revision Number, Date of Revision ~
l T.3.5-8 original, 1/31/91 T 3.5-9 original,-1/31/91 T 3.5-10 original, 1/31/91 T 3.5-11 original, 1/31/91-T 3.5-12 original, 1/31/91 T 3.5-13 original, 1/31/91 T 3.5-14 original,-- 1/31/91'
-i F 3.5-1 original,.1/31/91 F 3.5-2 original, 1/31/91 F 3.5-3 original, 1/31/91 F 3.5-4 original, 1/31/91 1
F 3.5-5 original, l'/31/91 F 3.5-6 8, 06/30/92 i
F 3.5-7 original, 1/31/91 i
p 3.6-i 10, 07/31/92 p 3.6-ii 10, 07/31/92 p 3.6-iii 6,
03/31/92 p 3.6-iii (cont'd) 6, 03/31/92 p 3.6-1 10, 07/31/92 p 3.6-2 10, 07/31/92
-1 p'3.6-3 10, 07/31/92 j
p 3.6-4 10, 07/31/92 O
p 3.6-5 10, 07/31/92 p 3.6-6 10,.07/31/92 p 3.6-7 10, 07/31/92 p 3.6-8 10, 07/31/92 l
p 3.6-9 10, 07/31/92 p 3.6-10 10, 07/31/92 p 3.6-11 10,:07/31/92 p 3.6-12 10, 07/31/92 p 3.6-13 10, 07/31/92 p 3.6-14 10, 07/31/92 p 3.6-15 10, 07/31/92 i
p 3.6-16 10,.07/31/92 p 3.6-17 10, 07/31/92 p 3.6-18 10, 07/31/92
_i p 3.6-19 10, 07/31/92 p.3.6-20 10, 07/31/92 p 3.6-21 10, 07/31/92 p 3.6-22 10, 07/31/92 p 3.6-23 10, 07/31/92 t
p 3.6-24 10, 07/31/92 l
p 3.6-25 10, 07/31/92-l l
l'
- NOTE:
p=page A= Appendix F= Figure
[
O T= Table i
i J
1
~
Page 11 of 41 Rev.'10/14/93-Pace / Table / Figure Number
- Revision Number, Date of Revision p 3.6-26 10, 07/31/92 l
p 3.6-27 10, 07/31/92:
j p 3.6-28 10,.07/31/92 p 3.6-29 10, 07/31/92
.i p 3.6-30 10,.07/31/92 p 3.6-31 10, 07/31/92 i
p 3.6-32 10, 07/31/92
}
p 3.6-33 10, 07/31/92 i
p 3.6-34 10, 07/31/92 l
p 3.6-35 10, 07/31/92 p 3.6-36 10, 07/31/92 p 3.6-37 10, 07/31/92 p 3.6-38 10,~07/31/92 p 3.6-39 10, 07/31/92 p 3.6-40 10, 07/31/92 p 3.6-41 10, 07/31/92 p 3.6-42 10, 07/31/92 j
p 3.6-43 10, 07/31/92~
j p 3.6-44 10,- 07/31/92 p 3.6-45 10, 07/31/92 i
p 3.6-46 10, 07/31/92
-i p 3.6-47 10, 07/31/92 l
()
p 3.6-48 10, 07/31/92-p 3.6-49 10, 07/31/92-p 3.6-50 10,'07/31/92 i
p 3.6-51 10, 07/31/92 p 3.6-52 10, 07/31/92 p 3.6-53 10, 07/31/92
'I p 3.6-54 10, 07/31/92 p 3.6-55 10, 07/31/92
-l p 3.6-56 10, 07/31/92 s
p 3.6-57 10, 07/31/92 l
p 3.6-58 10, 07/31/92 p 3.6-59 10, 07/31/92 p 3.6-60 10,.07/31/92 p 3.6-61 10, 07/31/92 1
p 3.6-62 10, 07/31/92 p 3.6-63 10, 07/31/92 l
p 3.6-64 10, 07/31/92 p 3.6-65 10, 07/31/92 p.3.6-66 10, 07/31/92 p 3.6-67 10, 07/31/92 j
p 3.6-68 10, 07/31/92 i
i
- NOTE:
p=page A= Appendix O
F= Figure T= Table 1
1
'I
I b
Page 12 of 41 l
Rev. 10/14/93 Pace / Table /Ficure' Number
- Revision Number, Date of Revision
'i p 3.6-69 11 0, 07/31/92 p 3.6-70 10, 07/31/92
-l p 3.6-71 10, 07/31/92 l
A 3.6.1 original',~1/31/91
.j' A 3.6.2 original, 1/31/91 T 3.6-1 (1 of 3)
. original, 1/31/91 T 3.6-1 (2 of 3) original, 1/31/91 T 3.6-1 (3 of 3) original, 1/31/91 T 3.6-2 original,.1/31/91 j
T 3.6-3 original, 1/31/91 1
T 3.6-4 original, 1/31/91 l
T 3.6-5 original, 1/31/91-T 3.6-6 original, 1/31/91' T 3.6-7 original, 1/31/91 i
T 3.6-8 original, 1/31/91 T 3.6-9 (1 of 3) original, 1/31/91 T 3.6-9 (2 of 3) original, 1/31/91 T 3.6-9 (3 of 3) original, 1/31/91 T 3.6-10 original, 1/31/91 T 3.~6-11 (1 of 2) original, 1/31/_o1 T 3.6-11 (2 of 2) original, 1/33/91
}
T 3.6-12' original, _1/31/91 i
T 3.6-13 original, 1/ 3 '.~. / 91
('
T 3.6-14 original, 1/31/91 T 3.6-15 6, 03/31/92 T 3.6-16 10, 07/31/92 -
l T 3.6-17 10, 07/31/92 F 3.6-1 original, 1/31/91 l
F 3.6-2 original, 1/31/91 l
F 3.6-3 original, 1/31/91 F 3.6-4 original, 1/31/91 i
F 3.6-5 original, 1/31/91 F 3.6-6 original, 1/31/91.
l F 3.6-7 original, 1/31/91 F 3.6-8 original, 1/31/91 F 3.6-9 original, 1/31/91 F 3.6-10 original, 1/31/91 i
F 3.6-11 original,:1/31/91 i
F 3.6-12 original, 1/31/91 F 3.6-13 original, 1/31/91 i
F 3.6-14 original, 1/31/91 i
F 3.6-15 original, 1/31/91 l
F 3.6-16 original, 1/31/91
~
[
- NOTE:
p=page A= Appendix-j F= Figure O
T= Table j
I
i Page 13 of 41 Rev. 10/14/93 Pace / Table /Fiqure Number
- Revision Number, Date of Revision P
F 3.6-17 original, 1/31/91 F.3.6-18 original, 1/31/91 F 3.6-19 original, 1/31/91 F 3.6-20 original, 1/31/91.
F 3.6-21 original, 1/31/91 F 3.6-22 original, 1/31/91 F 3.6-23 original, 1/31/91 i
F 3.6-24 original, 1/31/91 F 3.6-25 original, 1/31/91 F 3.6-26 original, 1/31/91 F 3.6-27 original,.1/31/91-F 3.6-28 original,~1/31/91 F 3.6-29 original, 1/31/91 F 3.6-30 original, 1/31/91
.i F 3.6-31 original, 1/31/91 F 3.6-32 original, 1/31/91 F 3.6-33 original, 1/31/91 F 3.6-34 original, 1/31/91 F 3.6-35 original, 1/31/91 F 3.6-36 original, 1/31/91 i
F.'.6-37
-original, 1/31/91 F 3.6-38 original, 1/31/91 F 3.C-39 original,.1/31/91 F 3.6-40 original, 1/31/91 F 3.6-41 (1 of 5) original, 1/31/91 F 3.6 41 (2 of 5) original, 1/31/91 H
F 3.6-41 (3 of 5) original, 1/31/91 F ?. 6-41 (4 of 5) original, 1/31/91 F 3.6-41 (5 of 5) original, 1/31/91 F 3.6-42 6,
03/31/92 F 3.6-43 6, 03/31/92 F 3.6-44 6,
03/31/92 3
F 3.6-45 6,
03/31/92 p 3.7-i original, 1/31/91 p 3.7-1 original, 1/31/91 p 3.7-2 original, 1/31/91 p 3.7-3 original, 1/31/91 l
p 3.7-4 original, 1/31/91 p 3.7-5 original, 1/31/91 Chapter 4
-I
- NOTE:
p=page A= Appendix fg F= Figure
\\Q T= Table s
b
Page 14 of 41
()
Rev. 10/14/93 Page/ Table / Figure Number
- Revision Number, Date of Revision p 4.0-i original, 1/31/91 p 4.0-1 original, 1/31/91 p 4.1-i original, 1/31/91 p 4.1-ii original, 1/31/91 p 4.1-iii original, 1/31/91 p 4.1-1 original, 1/31/91 p 4.1-2 original, 1/31/91 p 4.1-3 original, 1/31/91 p 4.1-4 original, 1/31/91 p 4.1-5 original, 1/31/91 T 4.1-1 (1 of 6) original, 1/31/91 T 4.1-1 (2 of 6) original, 1/31/91 T 4.1-1 (3 of 6) original, 1/31/91 T 4.1-1 (4 of 6) original, 1/31/91 T 4.1-1 (5 of 6) original, 1/31/91 T 4.1-1 (6 of 6) original, 1/31/91 T 4.1-2 (1 of 5) original, 1/31/91 T 4.1-2 (2 of 5) original, 1/31/91 T 4.1-2 (3 of 5) original, 1/31/91 T 4.1-2 (4 of 5) original, 1/31/91 T 4.1-2 (5 of 5) original, 1/31/91 F 4.1-1 6,
03/31/92 7.s
(
p 4.2-i original, 1/31/91 p 4.2-ii original, 1/31/91
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p 4.2-iii original, 1/31/91 p 4.2-1 original, 1/31/91 p 4.2-2 original, 1/31/91 p 4.2-3 original, 1/31/91 p 4.2-4 original, 1/31/91 p 4.2-5 original, 1/31/91 p 4.2-6 original, 1/31/91 p 4.2-7 original, 1/31/91 p 4.2-8 original, 1/31/91 p 4.2-9 original, 1/31/91 p 4.2-10 original, 1/31/91 p4.2-1ggg original, 1/31/91 p 4.2-1z original, 1/31/91 p 4.2-13 original, 1/31/91 p 4.2-14 original, 1/31/91 p 4.2-15 original, 1/31/91 p 4.2-17 original, 1/31/91 p 4.2-18 original, 1/31/91 T 4.2-1 original, 1/31/91
- NOTE:
p=page A= Appendix
(g F= Figure
(/
T= Table i
Page 15 of'41 Rev. 10/14/93 Pace / Table /Fiqure Number
- Revision Number, Date of Revision F 4.2-1 original,'1/31/91 F 4.2-2 original,'1/31/91 F 4.2-2 original, 1/31/91 F 4.2-3 original, 1/31/91 F 4.2-4 original, 1/31/91 F 4.2-5 original, 1/31/91 F 4.2-6 original, 1/31/91 p 4.3-i 8, 06/30/92 p 4.3-ii original, 1/31/91 p 4.3-iii original, 1/31/91 p 4.3-1 original, 1/31/91 p_4.3-2 original, 1/31/91 p 4.3-3 original, 1/31/91 p 4.3-4 original, 1/31/91 p 4.3-5 original, 1/31/91 p 4.3-6 original, 1/31/91 p 4.3-7 8, 06/30/92 p 4.3-8 original, 1/31/91 p 4.3-9 original, 1/31/91 p 4.3-10 original, 1/31/91 p 4.3-11 original, 1/31/91 p 4.3-12 original, 1/31/91 O
p 4.3-13 original, 1/31/91 p 4.3-14 8,
06/30/92__
p 4.3-15 original, 1/31/91 T 4.3-1 (1 of 2) original, 1/31/91 T 4.3-1 (2 of 2) original, 1/31/91 T 4.3-2 (1 of 2) original, 1/31/91 T 4.3-2 (2 of 2) original,-1/31/91 T 4.3-3 (1 of 2) original, 1/31/91 T 4.3-3 (2 of 2) original, 1/31/91 T 4.3-4 original, 1/31/91 T 4.3-5 (1 of 2) original, 1/31/91 T 4.3-5 (2 of 2) original, 1/31/91 T 4.3-6 (1 of 2) original, 1/31/91 T 4.3-6 (2 of 2) original, 1/31/91 T 4.3-7 original, 1/31/91 T 4.3-8 original, 1/31/91 T 4.3-9 original, 1/31/91.
T 4.3-10 original, 1/31/91 T 4.3-11 original, 1/31/91 T 4.3-12 original, 1/31/91 T 4.3-11 original, 1/31/91 l
- NOTE:
p=page A= Appendix F= Figure i
O T= Table
-l
-l
l 4
-l 0
Page 16 of 41-Rev. 10/14/93 Pace / Table / Figure Number
- Revision Number, Date-of Revision j
l T 4.3-12 original, 1/31/91
-l T 4.3-13 original, 1/31/91-l T 4.3-14 original, 1/31/91
.i T 4.3-15 original, 1/31/91 T 4.3-16 6, 03/31/92 T 4.3-17 6, 03/31/92 T 4.3-18 8, 06/30/92 T 4.3-19 original, 1/31/91 F 4.3-1 original, 1/31/91 p 4.4-i-15, 10/12/93 l
p 4.4-li 15,.10/12/93 p 4.4-iii 15, 10/12/93 1
p 4.4-1 15, 10/12/93 j
p 4.4-2 15, 10/12/93 l
p 4.4-3 15, 10/12/93 p 4.4-4 15, 10/12/93 p 4.4-5 15, 10/12/93 p.4.4-6 15, 10/12/93 p 4.4-7 15, 10/12/93 p 4.4 15, 10/12/93 p 4.4-9 15, 10/12/93 i
p 4.4-10 15, 10/12/93 4
fg
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p 4.4-11 15, 10/12/93 p 4.4-12 15, 10/12/93 p 4.4-13 15,.10/12/93 p 4.4-14 15, 10/12/93 T 4.4-1 15, 10/12/93 T 4.4-2 15, 10/12/93
- e T 4.4-3 15, 10/12/93 T 4.4-4 14, 07/30/93 F 4 4-1 original, 1/31/91
!}
p 4.5-i 15, 10/12/93 p 4.5-ii 15, 10/12/93 p 4.5-1 15, 10/12/93 i
p 4.5-2
'15, 10/12/93 p 4.5-3 15, 10/12/93 p 4.5-4 15, 10/12/93 p 4.5-5 15, 10/12/93 p 4.5-6 15, 10/12/93-p 4.5-7 15, 10/12/93 p 4.5-8 15, 10/12/93 p 4.5-9 15, 10/12/93 p 4.5-10 15, 10/12/93
- NOTE:
p=page A= Appendix F= Figure O'
5 T= Table
i Page'17 of 41.
~{
Rev. 10/14/93 Pace / Table /Ficure Number
- Revision Number, Date of Revision.
p 4.5 15, 10/12/93 p 4.5-12 15, 10/12/93 l
T 4.5-1 14,-07/30/93 i
T 4.5-2 14, 07/30/93 1
T 4.5-3 14, 07/30/93 p 4.6-i 13, 05/20/93 p 4.6-ii 13, 05/20/93 p 4.6-iii 13, 05/20/93 p 4.6-1 13, 05/20/93 l
p 4.6-2 13, 05/20/93 p'4.6-3 13, 05/20/93' p 4.6-4 13, 05/20/93 p 4.6-5 13, 05/20/93 p 4.6-6 13, 05/20/93 j
T 4.6-1 13, 05/20/93 l
F 4.6-1 13, 05/20/93 i
F 4.6-2 13, 05/20/93 p 4.7-i
.6, 03/31/92 i
p 4.7-1 original, 1/31/91 p 4.7-2 original, 1/31/91-i p 4.7-3 6, 03/31/92 p 4.7-4 original, 1/31/91 l
Chapter 5 p 5.0-i original, 1/31/91 p 5.0 original, 1/31/91 p 5.1-i 14, 07/30/93 r
p 5.1-ii 14, 07/30/93-p 5.1-1 14, 07/30/93 l
p 5.1-2 14, 07/30/93 p 5.1-3 14, 07/30/93
+
p 5.1-4 14, 07/30/93 i
p 5.1-5 14, 07/30/93 p 5.1-6 14, 07/30/93 p 5.1-7 14, 07/30/93 p 5.1-8 14, 07/30/93 p 5.1-9 14, 07/30/93 l
F.5.1-1 original, 1/31/91 j
F 5.1-2 6,
03/31/92 l
F 5.1-3 original, 1/31/91 F 5.1-4 original, 1/31/91 l
l
- NOTE:
p=page A= Appendix F= Figure O
T= Table s
r Page 18 of:41 Rev. 10/14/93 Page/ Table /Ficure Number
- Revision Number,'Date of Revision F 5.1-5 original, 1/31/91 F 5.1-6 6, 03/31/92 F 5.1-7 6,
03/31/92-p 5.2-i 14, 07/30/93 p 5.2-ii 14, 07/30/93 p 5.2-iii 14, 07/30/93 p 5.2-iv 14, 07/30/93 p 5.2-1 14, 07/30/93 p 5.2-2 14, 07/30/93' p 9.2-3 14, 07/30/93 p 5.2-4 14, 07/30/93' p 5.2-5 14, 07/30/93 l
p 5.2-6 14, 07/30/93 p 5.2-7 14, 07/30/93 p 5.2-8 14, 07/30/93 p 5.2-9 14, 07/30/93 p 5.2-10 14, 07/30/93 p 5.2-11 14, 07/30/93 p 5.2-12 14, 07/30/93 p 5.2-13 14, 07/30/93 p 5.2-14 14,_07/30/93 p 5.2-15 14, 07/30/93 s
p 5.2-16 14, 07/30/93 p 5.2-17 14, 07/30/93 p 5.2-18 14, 07/30/93 p 5.2-19 14, 07/30/93 p 5.2-20 14, 07/30/93
+
p 5.2-21 14, 07/30/93 p 5.2-22 14, 07/30/93 p 5.2-23 14, 07/30/93 p 5.2-24 14, 07/30/93-p 5.2-25 14, 07/30/93 p 5.2-26 14, 07/30/93 p 5.2-27 14, 07/30/93 p 5.2-28 14 07/30/93 p 5.2-29 14, 07/30/93 p 5.2-30 14,_ 07/30/93 p 5.2-31 14, 07/30/93 p 5.2-32 14, 07/30/93 p 5.2-33 14, 07/30/93' p 5.2-34 14, 07/30/93 p 5.2-35 14, 07/30/93 p 5.2-36 14, 07/30/93
- NOTE:
p=page A= Appendix 0
F= Figure T= Table
l, Page 19 of 41 a]
Rev. 10/14/93 AuJ I
Pace / Table / Figure Number
- Revision Number, Date of Revision ~
3 T 5.2-1>
14, 07/30/93 1
T 5.2-2 15, 10/12/93-a T 5.2-3
'14, 07/30/93 i
F 5.2-1 8, 06/30/92 F 5.2-2 original, 1/31/91 l
F 5.2-3 original, 1/31/91 F 5.2-4 original, 1/31/91 j
F 5.2-5 original, 1/31/91 i
F 5.2-6 original, 1/31/91 F_5.2-7 original, 1/31/91 F 5.2-8 original, 1/31/91' F 5.2-9 original, 1/31/91 F 5.2-10 original, 1/31/91 i
F 5.2-11 original, 1/31/91 F 5.2-12 original, 1/31/91' l
F 5.2-13 original, 1/31/91 F 5.2-14 original, 1/31/91 F 5.2-15 original, 1/31/91-F 5.2-16 original, 1/31/91 j
F 5.2-17 original, 1/31/91 F 5.2-18 original, 1/31/91 1
F 5.2-19 original, 1/31/91 1
O F 5.2-20 6, 03/31/92 F 5.2-21 original, 1/31/91 F 5.2-22 original,-1/31/91-F 5.2-23 original, 1/31/91 F 5.2-24 original, 1/31/91
~j F 5.2-25 original,.1/31/91 F 5.2-26
' original, 1/31/91
,i F 5.2-27 original, 1/31/91 F 5.2-28 original, 1/31/91 F 5.2-29 original, 1/31/91 F 5.2-30 original, 1/31/91 F 5.2-31 original, 1/31/91 F 5.2-32 original, 1/31/91 F.5.2-33 original, 1/31/91 Ji F 5.2-34 original, 1/31/91
'i F 5.2-35 original, 1/31/91
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F 5.2-36 original, 1/31/91 l
F 5.2-37 original, 1/31/91 F 5.2-38 original, 1/31/91
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F 5.2-39 original, 1/31/91 F 5.2-40 original, 1/31/91
- NOTE:
p=page l
A= Appendix F= Figure O
T= Table a-.
e a
p
)
Page 20 of 41 Rev. 10/14/93-Pace / Table / Figure Number *-
Revision Number, Date of Revision-F 5.2-41 original,'1/31/91 F 5.2-42 original, 1/31/91 F 5.2-43 original, 1/31/91 F 5.2-44 original, 1/31/91 F 5.2-45 original, 1/31/91 p 5.3-i 6,
03/31/92
(
p 5.3-ii 6,
03/31/92
~
p 5.3-iii 6,
03/31/92 p 5.3 original, 1/31/91 p 5.3-2 original, 1/31/91 p 5.2-3 original, 1/31/91 p 5.3-4 6,
03/31/92 p 5.3-5 6, 03/31/92 p 5.3-6 original, 1/31/91 i
p 5.3-7 original, 1/31/91 p 5.3-8 6, 03/31/92 p 5.3-9 6,
03/31/92 p 5.3-10 6,
03/31/92 l
p 5.3-11 6, 03/31/92 p 5.3-12 6, 03/31/92 A'
T 5.3-1 6, 03/31/92 T 5.3-2 6,
03/31/92 O
T 5.3-3 (1 of 2) 6, 03/31/92 i
T 5.3-3 (2 of 2) 6,-03/31/92 F 5.3-1 original, 1/31/91' F 5.3-2 original, 1/31/91 F 5.3-3 original, 1/31/91 F 5.3-4 original, 1/31/91-F 5.3-5 original, 1/31/91 F 5.3-6 original, 1/31/91 F 5.3-7 original, 1/31/91 F 5.3-8 original, 1/31/91 F 5.3-9 6, 03/31/92 i
F 5.3-10 6, 03/31/92 F 5.3-11 6,
03/31/92 F 5.3-12 6,
03/31/92 p 5.5-1 original, 1/31/91 p 5.5-1 original, 1/31/91-Chapter 6 6.0-1 original, 1/31/91 i
- NOTE:
p=page A= Appendix
/'
F= Figure T= Table i
T Page 21 of'41.
- Rev. 10/14/93 Pace / Table / Figure Number
- Revision Number, Date of Revision-p 6.0 original, 1/31/91 p 6.1-i original, 1/31/91
- p 6.1-ii original, 1/31/91 p 6.1-iii original, 1/31/91; p 6.1-1 original, 1/31/91 p 6.1-2 6,.03/31/92 p 6.1-3
.6, 03/31/92
. P 6.1-4 original, 1/31/91 y
p 6.1-5 original, 1/31/91 p 6.1-6 original, 1/31/91 p 6.1-7 original,:1/31/91 p 6.1-8 original, 1/31/91 T 6.1-1 original, 1/31/91
.{
T 6.1-2 (1 of 2) original, 1/31/91 T 6.1-2 (2 of 2) 8, 06/30/92 F 6.1-1 original, 1/31/91 p 6.2-i 15, 10/12/93 p 6.2-ii 15, 10/12/93 p 6.2-iii 15, 10/12/93 p 6.2-1 15, 10/12/93 p 6.2-2 15, 10/12/93 p 6.2-3 15, 10/12/93 O
p 6.2-4 15,'10/12/93-p 6.2-5 15, 10/12/93:
p 6.2-6 15, 10/12/93 p 6.2-7 15, 10/12/93 p 6.2-8 15, 10/12/93 p 6.2-9 15, 10/12/93 p 6.2-10 15, 10/12/93
. p 6.2-11 15, 10/12/93 p 6.2-12 15, 10/12/93 p 6.2-13 15, 10/12/93 p 6.2-14 15, 10/12/93 p 6.2-15 15, 10/12/93 p 6.2-16 15, 10/12/93 p 6.2-17 15, 10/12/93 p 6.2-18 15, 10/12/93 p 6.2-19 15, 10/12/93 p 6.2-20 15, 10/12/93 p 6.2-21 15, 10/12/93 p 6.2-22 15, 10/12/93 p 6.2-23 15, 10/12/93 p 6.2-24 15, 10/12/93
- NOTE:
p=page A= Appendix F= Figure 0
T= Table
Page 22 of 41
(~]
Rev. 10/14/93
%)
Pace / Table / Figure Number
- Revision Number, Date of Revision p 6.2-25 15, 10/12/93 p 6.2-26 15, 10/12/93 p 6-2-27 15, 10/12/93 p 6-2-28 15, 10/12/93 p 6-2-29 15, 10/12/93 p 6.2-30 15, 10/12/93 p 6.2-31 15, 10/12/93 p 6.2-32 15, 10/12/93 T 6.2-1 15, 10/12/93 T 6.2-2 15, 10/12/93 T 6.2-3 15, 10/12/93 T 6.2-4 15, 10/12/93 T 6.2-5 15, 10/12/93 T 6.2-6 15, 10/12/93 T 6.2-7 15, 10/12/93 T 6.2-8 15, 10/12/93 T 6.2-9 15, 10/12/93 T 6.2-10 15, 10/12/93 F 6.2-1 original, 1/31/91 F 6.2-2 original, 1/31/91 F 6.2-3 original, 1/31/91 F 6.2-4 original, 1/31/91
()
F 6.2-5 original, 1/31/91 F 6.2-6 original, 1/31/91 F 6.2-7 original, 1/31/91 F 6.2-8 original, 1/31/91 F 6.2-9 original, 1/31/91 p 6.3-i 14, 07/30/93 p 6.3-ii 14, 07/30/93 p 6.3-iii 14, 07/30/93 p 6.3-iv 14, 07/30/93 p 6.3-1 14, 07/30/93 p 6.3-2 14, 07/30/93 p 6.3-3 14, 07/30/93 p 6.3-4 14, 07/30/93 p 6.3-5 14, 07/30/93 p 6.3-6 14, 07/30/93 p 6.3-7 14, 07/30/93 p 6.3-8 14, 07/30/93 p 6.3-9 14, 07/30/93 p 6.3-10 14, 07/30/93 p 6.3-11 14, 07/30/93 p 6.3-12 14, 07/30/93
- NOTE:
p=page A= Appendix F= Figure 0
T= Table
P Page 23 of.41 f[^ '.
Rev. 10/14/93 ~
\\~
Pace / Table / Figure Number
- Revision Number, Date of Revision p 6.3-13 14, 07/30/93 p 6.3-14 14, 07/30/93
-p 6.3-15 14, 07/30/93 p 6.3-16 14, 07/30/93 p 6.3-17 14, 07/30/93 p 6.3-18 14,'07/30/93 j
p 6.3-19 14, 07/30/93 p 6.3-20 14, 07/30/93
~I p 6.3-21 14, 07/30/93' p 6.3-22 14, 07/30/93 p 6.3-23 14, 07/30/93 p 6.3-24 14, 07/30/93 l
p 6.3-25 14, 07/30/93 i
p 6.3-26 14, 07/30/93 i"
p 6.3-27 14, 07/30/93 p 6.3-28 14, 07/30/93 p 6.3-29 14, 07/30/93 p 6.3-30 14, 07/30/93 l
p 6.3-31 14, 07/30/93 p 6.3-32 14, 07/30/93 j
p 6.3-33 14, 07/30/93 i
p 6.3-34 14, 07/30/93
[
O p 6.3-35 14, 07/30/93 i
p 6.3-36 14, 07/30/93 p 6.3-37 14, 07/30/93 p 6.3-38 14, 07/30/93 p 6.3-39 14,_07/30/93-p 6.3-40 14, 07/30/93 p 6.3-41 14, 07/30/93 p 6.3-42 14, 07/30/93 p 6.3-43 14, 07/30/93 p 6.3-44 14, 07/30/93 p 6.3-45 14, 07/30/93 p 6.3-46 14, 07/30/93 p 6.3-47 14, 07/30/93 p 6.3-48 14, 07/30/93 i
p 6.3-49 14,.07/30/93 p 6.3-50 14, 07/30/93 p 6.3-51 14, 07/30/93 l
p 6.3-52 14, 07/30/93 j
p 6.3-53 14, 07/30/93 p 6.3-54 14, 07/30/93 p 6.3-55 14, 07/30/93 j
l
- NOTE:
p=page A= Appendix l
F= Figure T= Table i
Iq l
1
Page 24 of 41 j
Rev. 10/14/93 Pace / Table / Figure Number
- Revision Number, Date of Revision-
-j p 6.3-56 14, 07/30/93.
\\
p.6.3-57 14, 07/30/93 p 6.3-58 14, 07/30/93 t
p 6.3-59 14, 07/30/93 p 6.3-60 14, 07/30/93 P 6.3-61 14, 07/30/93
'[
p 6.3-62 14, 07/30/93 p 6.3-63 14, 07/30/93 l
p 6.3-64 14, 07/30/93 1
p 6.3-65 14, 07/30/93 p 6.3-66 14, 07/30/93 p 6.3-67 14, 07/30/93 p 6.3-68 14, 07/30/93 p 6.3-69 14, 07/30/93 p 6.3-70 14, 07/30/93 T 6.3-1 (1 of 6) original, 1/31/91 T 6.3-1 (2 of 6) original, 1/31/91 T 6.3-1 (3 of 6) original, 1/31/91 T 6.3-1 (4 of 6) original, 1/31/91 T 6.3-l' (5 of 6) original, 1/31/91 l
T 6.3-1 (6 of 6) original, 1/31/91
+
T 6.3-2 (1 of 2) original, 1/31/91 O
T 6.3-2 (2 of 2) original, 1/31/91 T 6.3-3 (1 of 2) original, 1/31/91 T 6.3-3 (2 of 2) original, 1/31/91 T 6.3-4 (1 of 6) original, 1/31/91
.l T 6.3-4 (2 of 6) original, 1/31/91 i
T 6.3-4 (3 of 6) original, 1/31/91 T 6.3-4 (4 of 6) original, 1/31/91 J
T 6.3-4 (5 of 6) original, 1/31/91-T 6.3-4 (6 of 6) original, 1/31/91 T 6.3-5 (1 of 5) original, 1/31/91 l
T 6.3-5 (2 of 5) original, 1/31/91 j
T 6.3-5 (3 of 5) original, 1/31/91 T 6.3-5 (4 of 5) original, 1/31/91 i
T 6.3-5 (5 of 5) original, 1/31/91 1
T 6.3-6 (1 of 7) original, 1/31/91 T 6.3-6 (2 of 7) original, 1/31/91 l
T 6.3-6 (3 of 7) original, 1/31/91 l
T 6.3-6 (3 of 7) original, 1/31/91 T 6.3-6 (4 of 7) original, 1/31/91 T 6.3-6 (5 of 7) original, 1/31/91 T 6.3-6 (6 of 7) original, 1/31/91 I
i
- NOTE:
p=page A= Appendix I
F= Figure O
T= Table
-l
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i e
r
l Page 25 of 41 Rev. 10/14/93 O~
Pace / Table /Ficure Number
- Revision Number, Date of' Revision T 6.3-6 (7 of 7) original, 1/31/91 l
T 6.3-7 (1 of 4) original, 1/31/91 T 6.3-7 (2 of 4) original, 1/31/91 l
T 6.3-7 (3 of 4) original, 1/31/91 T 6.3-7 (4 of 4) original, 1/31/91
~
T 6.3-8 (1 of 3) original, 1/31/91 T 6.3-8 (2 of 3) criginal, 1/31/91 T 6.3-8 (3 of.3) original, 1/31/91 T 6.3-9 original, 1/31/91' t
T 6.3-10 (1 of 6) original, 1/31/91 T 6.3-10 (2 of 6) original, 1/31/91 T 6.3-10 (3 of 6) original, 1/31/91 T 6.3-10 (4 of 6) original, 1/31/91 T 6.3-10 (5 of 6) original, 1/31/91 T 6.3-10 (6 of 6) original, 1/31/91
.l T 6.3-11 (1 of 3) original, 1/31/91 T.6.3-11 (2 of 3) original, 1/31/91 i
T 6.3-11 (3 of 3) original, 1/31/91 T 6.3-12 original, 1/31/91' l
T 6.3-13 (1 of 2) original, 1/31/91 1
T'6.3-13 (2 of 2) original, 1/31/91
)
T 6.3-14 original, 1/31/91 O
T 6.3-15 (1 of 2) original, 1/31/91 T 6.3-15 (2 of 2) original, 1/31/91 T 6.3-16 (1 of 34) original, 1/31/91 T 6.3-16 (2 of 34) original, 1/31/91 T 6.3-16 (3 of 34) original, 1/31/91 T 6.3-16 (4 of 34) original, 1/31/91 T 6.3-16-(5 of 34) original, 1/31/91 i
T 6.3-16 (6 of 34) original, 1/31/91
~
T 6.3-16 (7 of 34) original, 1/31/91 T 6.3-16 (8 of 34) original,- 1/31/91 T 6.3-16 (9 of 34) original,- 1/31/91 T 6.3-16 (10 of 34) original, 1/31/91 1
T 6.3-16 (11 of 34) original, 1/31/91 T 6.3-16 (12 of 34) original, 1/31/91' T 6.3-16 (13 of 34) original, 1/31/91-T 6.3-16 (14 of 34) original, 1/31/91 T 6.3-16 (15 of 34) original,.1/31/91 T 6.3-16 (16 of 34) original, 1/31/91 l
T 6.3-16'(17 of 34) original, 1/31/91 T 6.3-16 (18 of 34) original, 1/31/91 T 6.3-16 (19 of 34) original, 1/31/91 i
1
- NOTE:
p=page A= Appendix F= Figure O
i T= Table j
.]
'I 4
I Page 26 of 41' Rev. 10/14/93 Page/ Table / Figure Number
- Revision Number, Date of Revision I
t T 6.3-16 (20 of 34) original, 1/31/91 T 6.3-16 (21 of 34) original, 1/31/91 T 6.3-16 (22 of 34) original, 1/31/911 T 6.3-16 (23 of 34) original, 1/31/91 T 6.3-16 (24 of 34) original, 1/31/91 i
T 6.3-16 (25 of 34) original, 1/31/91~
l T 6.3-16 (26 of 34) original, 1/31/91 T 6.3-16 (27 of 34) original, 1/31/91 T 6.3-16 (28 of 34) original, 1/31/91 if T 6.3-16 (29 of 34) original, 1/31/91 T 6.3-16 (30 of 34) original, 1/31/91 l
T 6.3-16 (31 of 34) original, 1/31/91 l
T 6.3-16 (32 of 34) original,-1/31/91 T 6.3-16 (33 of 34) original, 1/31/91 T 6.3-16 (34 of 34) original, 1/31/91 i
F 6.3-1 (1 of 2) 6, 03/31/92 F 6.3-1 (2 of 2) original, 1/31/91 F 6.3-2 original, 1/31/91 F 6.3-3 original, 1/31/91 l
F 6.3-4 original, 1/31/91
}
F 6.3-5 (1 of 2) original, 1/31/91 l
F 6.3-5'(2 of 2) original, 1/31/91 O
F 6.3-6 (1 of 2) original, 1/31/91 F 6.3-6 (2 of 2) original,.1/31/91 F 6.3-7 original,1/31/91 F 6.3-8 (1 of 2) original,-1/31/91 F 6.3-8 (2 of 2) original, 1/31/91-F 6.3-9 original, 1/31/91 j
F 6.3 original,-1/31/91 j
F 6.3-11 6,
03/31/92 l
F 6.3-12 6, 03/31/92 p 6.4-1 14, 07/30/93 i'
p 6.4-ii 14, 07/30/93 p 6.4-iii 14, 07/30/93 p 6.4-iv 14, 07/30/93 p 6.4-v 14, 07/30/93 p 6.4-vi 14, 07/30/93 p 6.4-1 14, 07/30/93 i
p 6.4-2 14, 07/30/93 p 6.4-3 14, 07/30/93 p 6.4-4 14, 07/30/93 p 6.4-5 14, 07/30/93 p 6.4-6 14, 07/30/93.
1
- NOTE:
p=page A= Appendix 0
F= Figure T= Table i
I
.f
- ~.,. ~ -
Page 27'of 41 l
(~'s Rev. 10/14/93 i \\ >I
]
Page/ Table /Fiqure Number
- Revision Number, Date of Revision p 6.4-7 14, 07/30/93-p 6.4-8 14, 07/30/93 p 6.4-9 14, 07/30/93~
p 6.4-10 14, 07/30/93 p 6.4-11 14, 07/30/93 p 6.4-12 14, 07/30/93
'l p 6.4 14, 07/30/93 p 6.4-14 14, 07/30/93 p 6.4-15 14, 07/30/93 p 6.4-16 14, 07/30/93 p 6.4-17 14, 07/30/93 p 6.4-18 14, 07/30/93 P 6.4-19 14, 07/30/93 p 6.4-20 14, 07/30/93 p 6.4-21 14, 07/30/93 p 6.4-22 14, 07/30/93 p 6.4-23 14, 07/30/93 p 6.4-24 14, 07/30/93 p 6.4-25 14, 07/30/93 p 6.4-26 14, 07/30/93 p 6.4-27 14, 07/30/93 p 6.4-28 14, 07/30/93
_O-p 6.4-29 14, 07/30/93 p 6.4-30 14, 07/30/93 p 6.4-31 14, 07/30/93 p 6.4-32 14, 07/30/93
-p 6.4-33 14, 07/30/93 p 6.4-34 14, 07/30/93 p 6.4-35 14, 07/30/93 p 6.4-36 14, 07/30/93 p 6.4-37 14, 07/30/93 p 6.4-38 14, 07/30/93 p 6.4-39 14, 07/30/93 p 6.4-40 14,.07/30/93 p 6.4-41 14, 07/30/93 p 6.4-42 14, 07/30/93 p 6.4-43 14, 07/30/93 p 6.4-44 14, 07/30/93 p 6.4-45 14, 07/30/93 p 6.4-46 14, 07/30/93 p 6.4-47 14, 07/30/93 p 6.4-48 14, 07/30/93 p 6.4-49 14, 07/30/93 j
- NOTE:
p=page A= Appendix F= Figure v
O T= Table t
. - ~
r
- {
-i Page 28 of 41-U Rev. 10/14/931 j
Page/ Table / Figure Number
- Revision Number, Date of Revision j
p 6.4 14, 07/30/93 P 6.4-51 14, 07/30/93 El, 07/30/93-4
'p 6.4-52 p 6.4-53 14, 07/30/93 1
p 6.4-54 14, 07/30/93-p 6.4-55 14, 07/30/93 p 6.4-56 14, 07/30/93 a
.p 6.4-57 14, 07/30/93 i
p 6.4-58 14, 07/30/93~
-p 6.4-59 14, 07/30/93
~ t p 6.4-60 14, 07/30/93 p 6.4-61 14, 07/30/93 p 6.4-62 14, 07/30/93 i
p 6.4-63 14, 07/30/93 p 6.4-64 14, 07/30/93
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p 6.4-67 14,1 07/30/93 l
p 6.4-68 14, 07/30/93 p 6.4-69 14, 07/30/93 p.6.4 14, 07/30/93-p 6.4-71 14, 07/30/93 O
p 6.4-72 14,.07/30/93 p 6.4-73 14, 07/30/93~
l p 6.4-74 14,.07/30/93-p 6.4-75 14, 07/30/93 p 6.4-76 14, 07/30/93 f
p 6.4-77 14, 07/30/93 j
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p-6.4-79 14, 07/30/93 j
p 6.4-80 14, 07/30/93 p-6.4-81 14, 07/30/93 p 6.4 14,-07/30/93 p 6.4-83 14, 07/30/93 p 6.4-84 14, 07/30/93_
p;6.4-85 14, 07/30/93 p 6.4-86 14, 07/30/93 p 6.4-87 14,~07/30/93 p 6.4-88 14, 07/30/93-j p 6.4-89 14, 07/30/93 p 6.4-90 14, 07/30/93 p 6.4-91 14, 07/30/93 1
p 6.4-92 14, 07/30/93 q
e
-l
- NOTE:
p=page A= Appendix F= Figure i
O T= Table' j
~1 I
Page 29 of 41
?
1 Rev. 10/14/93 Pace / Table / Figure Number
- Revision Number, Date of Revision-p'6.4-93 14, 07/30/93 j
p 6.4-94 14, 07/30/93 p 6.4-95 14, 07/30/93 9
p 6.4-96 14,- 07/30/93
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p 6.4-103 14, 07/30/93 p 6.4-104 14, 07/30/93 p 6.4-105 14, 07/30/93 p 6.4-106 14, 07/30/93 p 6.4-107 14, 07/30/93 p 6.4-108 14, 07/30/93 i
p 6.4-109 14, 07/30/93 1
p 6.4-110 14, 07/30/93 p 6.4-111 14, 07/30/93 p 6.4-112 14, 07/30/93 p 6.4-113 14, 07/30/93 p 6.4-114 14, 07/30/93 p 6.4-115 14, 07/30/93 p 6.4-116 14, 07/30/93 p 6.4-117 14, 07/30/93 p 6.4-118 14, 07/30/93 p 6.4-119 14, 07/30/93 p 6.4-120 14, 07/30/93 p 6.4-121 14, 07/30/93 p 6.4-122 14, 07/30/93 p 6.4-123 14, 07/30/93 p 6.4-124 14, 07/30/93 p 6.4-125 14, 07/30/93 p 6.4-126 14, 07/30/93 p 6.4-127 14, 07/30/93 p 6.4-128 14, 07/30/93 p 6.4-129 14, 07/30/93 p 6.4-130 14, 07/30/93 i
p 6.4-131 14, 07/30/93 p 6.4-132 14, 07/30/93 p 6.4-133 14, 07/30/93 p 6.4-134 14, 07/30/93 p 6.4-135 14, 07/30/93
- NOTE:
p=page A= Appendix F= Figure 0
T= Table l
i
Page 30 of 41 Rev. 10/14/93 Pace / Table / Figure Number
- Revision Number, Date of Revision p 6.4-136 14, 07/30/93.
p 6.4-137 14, 07/30/93 p 6.4-138 14, 07/30/93 p 6.4-139 14, 07/30/93 1
T 6.4-1 original, 1/31/91
~
T 6.4-2 original, 1/31/91 T 6.4-3 original, 1/31/91 T 6.4-4 original, 1/31/91 T 6.4-5' original, 1/31/91 T 6.4-6 original, 1/31/91 T 6.4-7 original; 1/31/91 T 6.4-8 original, 1/31/91 T 6.4-9 original, 1/31/91 T 6.4-10 original, 1/31/91 T 6.4-11 original, 1/31/91 T 6.4-12 original, 1/31/91 T 6.4-13 original, 1.'31/91 F 6.4-1 original, 1/31/91 F 6.4-2 original, 1/31/91 F 6.4-3 original, 1/31/91 F 6.4-4 original, 1/31/91 F 6.4-5 6, 03/31/92' O
F 6.4-6 original, 1/31/91-F 6.4-7 original, 1/31/91 F 6.4-8 original, 1/31/91 4
F 6.4-9 original, 1/31/91 F 6.4-10 original, 1/31/91 F 6.4-11 (1 of 2) original, 1/31/91 F 6.4-11 (2 of 2) original, 1/31/91 F 6.4-12 original, 1/31/91 F 6.4-13 original, _1/31/91 F 6.4-14 original, 1/31/91 F 6.4-15 original, 1/31/91 F 6.4-16 original, 1/31/91 F 6.4-17 original, 1/31/91 F 6.4-18 original, 1/31/91 F 6.4-19 original, 1/31/91 F 6.4-20 (1 of 3) 6, 03/31/92 F 6.4-20 (2 of 3) original, 1/31/91 F 6.4-20 (3 of 3) original, 1/31/91 F 6.4-21 original, 1/31/91 F 6.4-22 original, 1/31/91 F 6.4-23 original, 1/31/91
.{
-i
- NOTE:
p=page A= Appendix F= Figure l
O
\\
T= Table
-1 Page 31 of 41 Rev. 10/14/93
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Pace / Table /Fiqure Number
- Revision Number, Date of Revision F. 6.4-24 (1 of 4) 8, 06/30/92 F 6.4-24 -(2 of 4) 8, 06/30/92.
F 6.4-24 (3 of 4) 8, 06/30/92 l
F 6.4-24 (4 of 4) 8, 06/30/92 F 6.4-25 8, 06/30/92 F 6.4-26 8, 06/30/92 F 6.4-27 original, 1/31/91 4
F 6.4-28 original, 1/31/91 F 6.4-29 original, 1/31/91 F 6.4-30 original, 1/31/91 F 6.4-31 6,
03/31/92 F 6.4-32 original, 1/31/91 F 6.4-33 original, 1/31/91 F 6.4-34 8, 06/30/92 F 6.4-35 (1 of 6) 8, 06/30/92 i
F 6.4-35 (2 of 6) 8, 06/30/92 F 6.4-35 (3 of 6) 8, 06/30/92 t
F 6.4-35 (4 of 6) 8, 06/30/92 F 6.4-35 (5 of 6) 8, 06/30/92 F 6.4-35 (6 of 6) 8, 06/30/92 F 6.4-36 8,
06/30/92' F 6.4-37 8, 06/30/92 O
F 6.4-38 8, 06/30/92-F 6.4-39 original, 1/31/91
]
F 6.4-40 6,
03/31/92 F 6.4-41 8, 06/30/92.
p 6.5-i 14, 07/30/93 p 6.5-1 14, 07/30/93 p 6.5-2 14, 07/30/93 p-6.5-3 14, 07/30/93 p 6.5-4 14, 07/30/93 p 6.6-1 original, 1/31/91 I
p 6.6-1 original, 1/31/91 p 6.7-i original, 1/31/91 p 6.7-1 original, 1/31/91 p 6.8-i original, 1/31/91 p 6.8-ii 6, 03/31/92 p 6.8-1 6, 03/31/92 i
p 6.8-2 6, 03/31/92 F 6.8-1 (1 of 4) original, 1/31/91 F 6.8-1 (3 of 4) original, 1/31/91 '
j F 6.8-1 (2 of 4) original, 1/31/91 l
F 6.8-1 (4 of 4) original, 1/31/91.
' '~ msX-q f
- NOTE:
p=page A= Appendix F= Figure 0
T= Table l
J 1
q
-l t
Page 32 of~41 l
O Rev. 10/14/93 Pace /TabIe/Ficure Number
- Revision Number, Date of Revision l
F 6.8-2 (1 of 3) 6, 03/31/92 i
F 6.8-2 (2 of 3) original, 1/31/91 I
F 6.8-2 (3 of 3) original, 1/31/91 F 6.8-3'(1 of 4) original,.1/31/91 F 6.8-3 (2 of 4) original, 1/31/91 1
F 6.8-3 (3 of 4) original, 1/31/91 F 6.8-3 (4 of 4) original, 1/31/91 F 6.8-4 (1 of 3) original, _1/31/91 F 6.8-4 (2 of 3) original, 1/31/91 F 6.8-4 (3 of 3) original, 1/31/91 F 6.8-5 (1 of 3) original, 1/31/91 F 6.8-5 (2'of 3) original, 1/31/91 F 6.8-5 (3 of 3) original, 1/31/91 F 6.8-6 (1 of 4) original, 1/31/91 F 6.8-6 (2 of 4) original, 1/31/91-F 6.8-6 (3 of 4) original, 1/31/91 F 6.8-6 (4 of 4) original, 1/31/91' l
F 6.8-7 (1 of 3) original,-1/31/91 F 6.8-7 (2 of 3) original, 1/31/91 i
F 6.8-7 (3 of 3) original, 1/31/91~
F 6.8-8 (1 of 3) original, 1/31/91 l
F 6.8-8 (2 of 3) original, 1/31/91' O
F 6.8-8 (3 of 3) original, 1/31/91 F 6.8-9 (1 of 3) original, 1/31/91 F 6.8-9 (2 of 3) original, 1/31/91 F 6.8-9 (3 of 3) original, 1/31/91
-l F 6.8-10 (1 of 4) original, 1/31/91 F 6.8-10 (2 of 4) original, 1/31/91 i
F'6.8-10 (3 of 3) original,: 1/31/91 i
F 6.8-10 (4 of 4) original, 1/31/91 F 6.8-11 (1 of 3) original, 1/31/91 F 6.8-11 (2 of 3) original, 1/31/91
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F 6.8-12 (3 of 4) 6, 03/31/92
.i F 6.8-12'(4 of 4) 6, 03/31/92' l
I Chupter 7 p 7.0-i original, 1/31/91 l
p-7.0-1 original, 1/31/91 l
i
- NOTE:
p=page i
A= Appendix F= Figure
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O T= Table
l t
Page 33 of 41 Rev. 10/14/93 Page/ Table / Figure Number
- Revision Number, Date of Revision p 7.1-i 8,
06/30/92 p 7.1-ii 8, 06/30/92 p 7.1-1 8, 06/30/92 t
p 7.1-2 8, 06/30/92 p 7.1-3 8, 06/30/92 P 7.1-4 original, 1/31/91 p 7.1-5 8, 06/30/92 p 7.1-6 8, 06/30/92 p 7.1-7 8, 06/30/92 p 7.1-8 8, 06/30/92 p 7.1-9 8, 06/30/92 p 7.1-10 8, 06/30/92 p 7.1-11 8, 06/30/92 p 7.1-12 8, 06/30/92 p 7.1-13 8, 06/30/92 p 7.1-14 8, 06/30/92 1
p 7.1-15 8, 06/30/92
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T 7.1-1 8,'06/30/92
'i T 7.1-2 8, 06/30/92 T 7.1-3 8,
06/30/92 T 7.1-4 8, 06/30/92 l
T 7.1-5 8, 06/30/92 0
T 7.1-6 8,
06/30/92 T 7.1-7 8, 06/30/92 p 7.2-i 8, 06/30/92 p 7.2-ii 8, 06/30/92 p 7.2-111 original, 1/31/91.
.p 7.2-1 8, 06/30/92 p 7.2-2 8, 06/30/92 p 7.2-3 8, 06/30/92 j
p 7.2-4 8, 06/30/92 1
p 7.2-5 8, 06/30/92
.p 7.2-6 original, 1/31/91 1
p 7.2-7 8, 06/30/92 p 7.2-8 8, 06/30/92 l;
p 7.2-9 8, 06/30/92 T 7.2-1 13, 05/20/93
+
T 7.2-2 8, 06/30/92 l
T 7.2-3 8, 06/30/92 Chapter 8
'{
p 8.0-i-original, 1/31/91
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p=page A= Appendix
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T= Table-l f
1 t
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'I Page 34'of 41 i
L.
Rev. 10/14/93 Pace / Table / Figure Number
- Revision Number, Date of Revision p 8.0-1 7, 05/29/92
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p 8.1-i 14, 07/30/93 1
p 8.1-1 14, 07/30/93 1
p 8.1-2 14, 07/30/93
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p 8.2-iii 16,-10/14/93 p 8.'2 16, 10/14/93
- l p 8.2-2 16, 10/14/93 p 8.2-3 16, 10/14/93 p 8.2-4 16, 10/14/93 p 8.2-5 16, 10/14/93 p B.2-6 16, 10/14/93 p 8.2-7 16, 10/14/93 i
p 8.2-8 16, 10/14/93 p 8.2-9 16, 10/14/93-p 8.2-10 16, 10/14/93
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p 8.2-14 16, 10/14/93 l
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T 8.2-5 14, 07/30/93 T 8.2-6 14, 07/30/93 i
F 8.2-1 (1 of 3) original, 1/31/91 F 8.2-1 (2 of 3) original, 1/31/91 F 8.2-1 (3 of 3) original, 1/31/91
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p 8.4-iii 15, 10/12/93 q
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p=page i
A= Appendix l
F= Figure O
T= Table l
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- Revision Number, Date of Revision p 8.4-1 15,.10/12/93 p 8.4-2 15, 10/12/93 T 8.4-1 (1 of 4) 14, 07/30/93 T 8.4-1 (2 of 4) 14, 07/30/93 T 8.4-1 (3 of 4) 14, u//20/43 T 8.4-1 (4 of 4) 14, 07/30/93 F 8.4-1
. original, 1/31/91 l
p 8.5-i 15, 10/12/93 p 8.5-ii 15, 10/12/93 i
p 8.5-iii 15, 10/12/93 z;
p 8.5-1 15, 10/12/93 P 8.5-2 15,-10/12/93 p 8.5-3 15, 10/12/93 p 8.5-4 15, 10/12/93 p 8.5-5 15, 10/12/93 p 8.5-6 15, 10/12/93 p 8.5-7 15, 10/12/93 p 8.5-8 15, 10/12/93 p 8.5-9 15, 10/12/93 i
p 8.5-10 15, 10/12/93
.i p 8.5-11 15, 10/12/93 p 8.5-12 15, 10/12/93 O
p 8.5-13 11 5, 10/12/93 T 8.5-1 14, 07/30/93 T 8.5-2 14, 07/30/93 T 8.5-3 14, 07/30/93 i
T 8.5-4 (1 of 3) 14, 07/30/93 T 8.5-4 (2 of 3) 14, 07/30/93 T 8.5-4 (3 of 3) 14, 07/30/93 T 8.5-5 (1 of 3) 14, 07/30/93 T 8.5-5 (2 of 3) 14, 07/30/93 T 8.5-5 (3 of 3) 14, 07/30/93 T 8,5-6 (1 of 3) 14, 07/30/93 T 8.5-6 (2 of 3) 14, 07/30/93 T 8.5-6 (3 of 3) 14, 07/30/93 F 8.5-3 14, 07/30/93 Chapter 9 p 9.0-i 13, 05/20/93 p 9.0-ii 13, 05/20/93 p 9.0-1 13, 05/20/93
.p 9.0-2 13, 05/20/93 i
- NOTE:
p=page A= Appendix j
O-F= Figure
~
T= Table u
Page 36 of 41' l
2 Rev. 10/14/93 Pace / Table /Ficure Number
- Revision Number, Date of Revision i
p 9.0-3 13, 05/20/93 p 9.0-4 13, 05/20/93 p 9.0-5 13- 05/20/93 l
p 9.0-6 13, 05/20/93 p 9.0-7 13, 05/20/93 p 9.0-8 13, 05/20/93
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p 9.1-iii 13, 05/20/93 p 9.1-iv 13, 05/20/93 p 9.1-v 13, 05/20/93 p 9.1-1 13, 05/20/93 p 9.1-2 13, 05/20/93
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p 9.1-3 13, 05/20/93 1
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p 9.1-15 13, 05/20/93 i
p 9.1-16 13, 05/20/93 p 9.1-17 13, 05/20/93 1
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-i p.9.1-27 13, 05/20/93-p 9.1-28 13, 05/20/93 p 9.1-29 13, 05/20/93-i p 9.1-30 13, 05/20/93 i
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p=page-A= Appendix i
F= Figure 0
T= Table j
l l
2 Page 37 of 41 Rev. 10/14/93 Pace / Table / Figure Number
- Revision Number,'Date of'artision l
p 9.1-31 13; 05/20/93 p 9.1-32 13, 05/20/93 p 9.1-33 13, 05/20/93 p 9.1-34 13, 05/20/93 p 9.1-35 13, 05/20/93 p 9.1-36 13, 05/20/93 p 9.1-37 13., 05/20/93
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p 9.2-i 13, 05/20/93 p 9.2-ii 13, 05/20/93 p 9.2-iii 13, 05/.70/93 p 9.2.1 13, 05/20/93 p 9.2-2 13, 05/20/93 P 9.2-3 13, 05/20/93 O
p 9.2-4 13, 05/20/93 p 9.2-5 13, 05/20/93-p 9.2-6 13, 05/20/93 p 9.2-7 13, 05/20/93 p 9.2-8 13, 05/20/93 p 9.2-9 13, 05/20/93 p 9.2-10 13, 05/20/93 p 9.2-11 13, 05/20/93 p 9.2-12 13, 05/20/93 p 9.2-13 13, 05/20/93 p 9.2-14 13, 05/20/93 p 9.2-15 13, 05/20/93 p 9.2-16 13, 05/20/93 p 9.2-17 13, 05/20/93 p 9.2-18 13, 05/20/93 p 9.2-19 13, 05/20/93 p 9.2-20 13, 05/20/93 p 9.2-21 13, 05/20/93 p 9.2-22 13,_05/20/93 p-9.2-23 13, 05/20/93 p 9.2-24 13, 05/20/93
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p=page A= Appendix-F= Figure O
T= Table
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Page 38~of_41 Rev. 10/14/93 e
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Pace / Table / Figure Number
- Revision Number, Date of Revision
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p 9'.2-25 13, 05/20/93 p 9.2-26 13, 05/20/93.
p 9.2-28 13, 05/20/93 p 9.2-29 13, 05/20/93
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p 9.2-31 13, 05/20/93
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F 9.2-1 13, 05/20/93-F 9.2-2 13, 05/20/93-F 9.2-3 13, 05/20/93 i
i F 9.2-4 13,_05/20/93 F 9.2-5 13, 05/20/93 F 9.2-6 13, 05/20/93 F 9.2-7 13, 05/20/93
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Chapter 10 i
p 10.0-i 13, 05/20/93 p 10.0-ii 13, 05/20/93
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p-10.7-3 13, 05/20/93-i
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p=page A= Appendix F= Figure gl O
T= Table
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Page 39 of 41 Rev. 10/14/93 Pace / Table /Fiqure Number
- Revision Number, Date of Revision p 10.8-1 13, 05/20/93 p 10.9-1 13, 05/20/93 p 10.10-1 13,: 05/20/93
.i P 10.10-2 13, 05/20/93 p 10.11-1 13, 05/20/93 p 10.12-1 13, 05/20/93 p 10.12-2 13, 05/20/93-p 10.13-1 13, 05/20/93 p 10.14-1 13, 05/20/93 4
p 10.15-1 13, 05/20/93 p 10.16-1 13, 05/20/93 i
p 10.17-1 13,'05/20/93 p 10.18-1 13, 05/20/93 p 10.18-2 13, 05/20/93 p 10.18-3 13, 05/20/93 p 10.19-1 12, 10/23/92 p 10.19-2 13, 05/20/93 p 10.19-3 13, 05/20/93 T 10.1-1 13, 05/20/93 i
T 10.1-2 13, 05/20/93 T 10.1-3 13, 05/20/93 T 10.1-4 13, 05/20/93 Chapter 11 p 11.0-i 3,
1/9/92 l
p 11.0-1 3, 1/9/92 p 11.1-i 16,.10/14/93 p 11.1-ii 16, 10/14/93 1'
p 11.1-1 16, 10/14/93 p 11.1-2 16, 10/14/93 p 11.1-3 16, 10/14/93 p 11.1-4 16, 10/14/93 p 11.1-5 16, 10/14/93 p 11.1-6 16, 10/14/93 1
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p=page-l A= Appendix' F= Figure O.
T= Table l
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n Page 40.of 41 Rev. 10/14/93 Page/ Table / Figure Number
- Revision Number, Date of-Revision p 11.1-14 16, 10/14/93 T 11.1-1 14, 07/30/93 T 11.1-2 14, 07/30/93 T 11.1-3 14, 07/30/93.
p 11.2-i 14, 07/30/93 p 11.2-ii 14, 07/30/93 p 11.2-1 14, 07/30/93 p 11.2-2 14, 07/30/93 p 11.2-3 14, 07/30/93.
p 11.2-4 14, 07/30/93
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T 11.2-2 (page 5 of 5) 14,'07/30/93 p 11.3-i 14, 07/30/93 p 11.3-1 14, 07/30/93' p 11.3-2 14, 07/30/93 p 11.3-3 14, 07/30/93 p 11.3-4 14, 07/30/93 p 11.3-5 14, 07/30/93 p 11.3-6 14, 07/30/93 p 11.3-7 14, 07/30/93 p 11.3-8 14, 07/30/93 p 11.3-9 14, 07/30/93 p 11.3-10 14, 07/30/93 p 11.3-11 14, 07/30/93 p 11.3-12 14, 07/30/93-p 11.4-i 14, 07/30/93 p 11.4-1.
14, 07/30/93 p 11.4-2 14, 07/30/93.
p 11.4-3 14, 07/30/93-p-11.4-4 14, 07/30/93-p 11.4-5 14, 07/30/93-p-11.4-6 14, 07/30/93-
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p=page_.
A= Appendix f
F= Figure T= Table
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p 11.4-9 14, 07/30/93 s
p 11.4-10 14,.07/30/93 p 11.4-11 14, 07/30/93 p 11.4-12 14,'07/30/93 p 11.4-13 14, 07/30/93 p 11.4-14 14, 07/30/93 p 11.4-15 14, 07/30/93 p 11.5-i 15,:10/12/93 p 11.5-1 15, 10/12/93 p 11.6-i original, 1/31/91 p 11.6-1 original, 1/31/91 p 11.7-i original, 1/31/91-p 11.7-1 original, 1/31/91 p 11.8-i 15, 10/12/93 p 11.8-ii 15, 10/12/93 p 11.8-1 15, 10/12/93 i
p 11.8-2 15, 10/12/93 p 11.8-3 15, 10/12/93 p 11.8-4 15, 10/12/93 p 11.8-5 15, 10/12/93 O
p 11.8-6 15,'10/12/93 p 11.8-7 15, 10/12/93
't p 11.8-8 15,'10/12/93 p 11.8-9 15, 10/12/93 p 11.8-10 15, 10/12/93 p 11.8-11
.15, 10/12/93 p 11.8-12 15, 10/12/93 p 11.8-13 15, 10/12/93 p 11.8-14 15, 10/12/93 p 11.8-15 15, 10/12/93 p 11.8-16 15, 10/12/93 p 11.8-17 15, 10/12/93-
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T 11.8-1 (1 of 2) 15, 10/12/93 T 11.8-1 (2 of 2) 15,.10/12/93 i
T 11.8-2 15, 10/12/93
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-s i
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- NOTE:
p=page A= Appendix F= Figure O
T= Table i
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- t TABLE OF CONTENTS l
8.2 ONSITE CONTAMINATION CONTROL 8.2-1 8.2.1 RADIOLOGICAL ACCESS ZONES 8.2-1 8.2.1.1 Description of Zones 8.2-1 8.2.2 ACCESS AND EGRESS CONTROL 8.2-3 l
8.2.2.1 Design Basis 8.2-3 8.2.2.2 Radiation Protection Awareness 8.2-3 j
8.2.2.3 Protective Clothina and Eculement 8.2-4 8.2.2.4 Personnel Monitorinq
~8.2-5
- B.
- 2.2.5 Monitor Stations 8.2-6 8.2.2.6 Locker Rooms 8.2-6
. i 8.2.3 CONTAMINATION AND RADIATION CONTROL 8.2-7.
8.2.3.1 Desian Basis 8.2-7 8.2.3.2 Procedures 8.2-8.
+
8.2.3.3 Instrumentation 8.2-9 8.2.3.4 Limits 8.2-9 8.2.4 MAINTENANCE AREAS AND PROCEDURES 8.2-10 8.2.4.1 Facilities 8.2-11' 8.2.4.2 Exposure Limits 8.2-13 8.2.4.3 Exposure Estimates 8.2-13 8.2.5 DECONTAMINATION PROVISIONS 8.2-13 j
8.2.5.1 Desian Basis 8.2.;
8.2.5.2 Separations Building 8.2-14 8.2.5 3 Final Decontamination and Decommissionina 8.2-14
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i l
- i
'l 1
l r
8.2-i October 1993
)
1 u
a w
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+ -.
.nu.
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LIST OF TABLES
]
8.2-1 Estimated Dose Rates i
8.2-2 Administrative Radiation Exposure Limits j
8.2-3 Estimated Individual Exposures 8.2-4 Capenhurst (BNFL) URENCO. Facility Exposure Histories 8.2-5 Almelo (UCN) URENCO Facility Exposure Histories i
1 8.2-6 Gronau (Uranit) URENCO Facility Exposure History i
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8.2-ii October 1993
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4 LIST OF FIGURES.
8.2-1 Radiological Access Zones R
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8.2.1 RADIOLOGICAL ACCESS ZONES i
Radiological access zones within the facility have been t
established to 1) control the spread of contamination,-2) control access to radiation areas to avoid unnecessary exposure to personnel to radiation, and 3) to control access to radioactive-l' sources present in the facility.
Table 8.2-1 lists general dose rate. estimates for the facility.
These dose estimates were prepared based upon historical data from the operating Urenco l
centrifuge enrichment facilities.
Areas associated with higher i
dose rates may be restr.icted from public access, as determined by r
facility management.
Areas where CEC personnel spend substantial amounts of time will be designed to minimize the exposure received when routine tasks are performed - this design will use the ALARA principle.
8.2.1.1 Description of Zones
)
The projected radiological access zones are shown on Fi~gure 8.2-1.
Facility management may elect to make each zone more i
restrictive as to the radiation levels specified herein.
A 1
description of each type of' zone is listed below.
i Unrestricted area:
(Zone I)
Designation for areas adjacent to the facility site where LES does not normally exercise access O_
control.
This area could be accessed by members of the public, l
indigenous wildlife, or by facility personnel.
In accordance i
with 10 CFR 20.1003, this is considered to be an unrestricted area which is governed by the limits in 10 CFR 20.1301.
These i
limits for an unrestricted area are 0.1 rem (1 mSv) per year and j
2 mrem / hour (0.02 mSv/ hour).
1 Restricted area:
(Zone II)
Designation for areas that are controlled by the licensee but do not meet the radiation area, high radiation area, or airborne area criteria.
These are areas within the facility where the CEC staff is expected to work continuously and where potential radiation hazards (radiation and contamination) do not require access control.
Examplesaof this include the office areas, rest rooms, and conference rooms.
This area could also be accessed by visiting members of the public.
r Radiation area:
(Zone III)
Designation for restricted areas l
that are defined by 10 CFR 20.1003 as Radiation Areas - an area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent'in excess of 5 mrem / hour (0.05 mSv/ hour) at 30 cm from the radiation source.or.
l' from any surface that the radiation penetrates.
This is designated as the Radiation Control Area (RCA) of the facility.
Examples of this include storage areas for the UF6 Handling Area of the Separations Building and the Blending Area.
8.2-1 October 1993
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Radiation Control Zone (RCZ):
An area within the RCA that.may be
(~%
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temporary or permanent.
RCZ's are established at locations where any of the following-conditions exist:
)
Airborne Radiation:
6 230% of the weighted Derived Air Concentration (DAC) listed in 10 CFR Part 20, Appendix B to SS 20.1001-20.2401, for specific radionuclides.
25.0 E-14 pCi/ml for alpha emitters not listed to 10 CFR Part 20, Appendix B to SS 20.1001-20.2401, or unknown alpha emitters.
i an individual present in the area without respiratory
[
protection equipment could exceed, during the hours'an individual is present in a week, an intake of 0.6% of-the Annual Limit on Intake (ALI) or 12 DAC hours, as defined in 10 CFR SS 20.1003.
Alpha Contamination:
2 within an RCA, 25000 DPM/100 cm 2
outside an RCA, 2200 DPM/100 cm O-The purposes of the RCZ are to inform workers of the hazard and prevent the spread of the contamination.
Examples of RCZ's could s
be the contaminated equipment workshop, the radiochemistry laboratory, and roped-off areas for facility maintenance.
High radiation area:
Designation for restricted areas that are defined by 10 CFR 20.1003 as High Radiation Areas - an area,-
accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 0.1 rem (1 mSv) in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm from the radiation source or from any surface that the radiation penetrates.
No examples of-this are.
expected during routine operation of the facility.
This designation is provided here for the purposes of emergency.
situations (drills and actual).
Airborne radioactivity area:
-Designation for areas that are defined by 10 CFR 20.1003 as Airborne Radioactivity Areas - a room, enclosure, or area in which airborne radioactive materials, composed wholly or partly of licensed material, exist in concentrations that 1) exceed the Derived Air Concentrations (DAC's) listed in Appendix B of 10 CFR 20 or.2) to--such a degree that an individual present in the area without respiratory protective equipment could exceed, during the hours an individual-is present in a week, an intake of 0.6 percent of the annual.
limit of intake (ALI) or 12 DAC-hours.
Note that entry into this j
(s 8.2-2 October 1993 1
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area does not. automatically require the wearing of a respirator.
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Potential airborne areas could occur in laboratories processing
(
wastes.
These areas are to be posted as RCZ's.
8.2.2 ACCESS.AND EGRESS CONTROL 8.2.2.1 Design Basis
+
Because there are no high radiation areas in the facility,.there t
will be no areas where access will be physically prevented due to radiation level.
Access control will be by administrative-q methods.
Access to certain areas may be physically prevented for security reasons (see the CEC Physical Security Plan for a' description of facility security).
Personnel that have not been trained in radiation protection procedures will not be allowed access to the RCA without escort by trained personnel.
Access to and egress from the RCA is through one of the monitor stations at the RCA boundary.
These monitor station locations' j
are shown on Figure 8.2-1'(sheet 2 of 3).
Access to and egress
!j from each RCZ is specifically controlled.
As a minimum, a monitor (frisker), step-off pad and container for any discarded i
protective clothing are provided at the egress point from the RCZ to prevent the spread of contamination.
'I l
8.2.2.2 Radiation Protection Awareness O
The RCA and RCZs will be' clearly identified by physical means
.l' such as placarding or boundary marking, so that facility personnel can identify these areas and act appropriately.
This f
identification will be done in accordance with 10 CFR 20.1902.
i The radiation and contamination levels from the most recent t
survey will be clearly noted on each posting.
i All personnel whose-duties require:
a.
working with radioactive material, b.
entering radiation areas (RCA's, RCZ's), or 1
c.
directing the activities of others working with radioactive materials or entering radiation areas (RCA's, RCZ's) will be trained on LES ALARA philosophy and radiation protection
. procedures in order to provide the facility with trained and qualified radiation workers. - This training will take the' form of initial and requalification phases.
This training shall include, l
but not be limited to the following:
a.
proper use of-protective clothing (for employees that will be working in contaminated areas or airborne radioactivity areas) 1
'i 8.2-3
. October 1993
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proper use of respirators (for employees that have been' fit-i tested and physically qualified to wear a respirator)
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c.
radiation dose limits d.
individual responsibilities for ALARA and exposure control e.
proper interpretation of radiation signs and radiation work permits f.
good housekeeping habits g.
prohibition of eating, drinking, smoking in RCA's, RCZ's t
h.
proper wearing of external dosimetry devices i.
concepts of time-distance-shielding to minimize exposure j.
awareness of higher contamination or radiation areas and how to minimize exposures in these areas k.
review of historical doses received, if available, for specific jobs or areas of the facility 1.
comparisons of radiation risks to those encountered i
elsewhere The initial phase occurs after employment but prior to the employee working in an RCA.
Requalification training occurs at 12-15 month intervals after the most recent initial or requalification training.
1 The Health Physics Manager is responsible for establishing and maintaining the awareness training for all appropriate personnel, i
including contractor personnel who may be working at the facility.
Records shall be maintained for each employee documenting the training date, scope of the training, identity of the trainer (s), any test results and other associated i
information.
8.2.2.3 Protective Clothina and Equipment i
i The proper use of protective clothing and equipment can minimize internal and external exposures to radioactivity.
Personnel working in areas that are classified as airborne radioactivity areas or in areas where removable surface contamination is-i greater than 1000 dpm/100 cm beta-gamma'or greater than 20 2
2 dpm/100 cm alpha must wear appropriate protective clothing.
If i
i the areas containing the surface contamination-can'be isolated from adjacent work areas via a barrier such that dispersible
,i material is not likely to be transferred beyond it, (with associated signs indicating the level and identity of 8.2-4 October 1993
4 l
contamination), personnel working in the adjacent area are not i
required to wear protective clothing.
Health Physics management and associated technical staff are responsible for determining the need for protective clothing in each work area.
Areas requiring protective clothing shall be i
indicated by posting signs at all area entry points.
8.2.2.4 Personnel Monitoring 8.2.2.4.1 External Monitoring External exposures are received primarily from the radiation j
decay products of uranium-238.
Most notably these' progeny are Th-231 (several gammas, all low energy.and low abundance), Th-234' (several gammas, most low abundance and low energy),.and Pa-234 and Pa-234m (many gammas, variable abundance, low and high energy).
The Pa-234m is the primary progeny gamma source and is expected to contribute to a significant portion of the external exposure.
Workers will receive training (see Section 8.2.2.2) regarding ALARA concepts such as time-distance-shielding to minimize their exposures.
All personnel whose duties require them to enter the RCA will wear individual external dosimetry devices.
An example of this-is the thermoluminescent dosimeter (TLD).
External dosimetry; devices will be evaluated at least quarterly to ascertain external exposures.
Administrative limits on radiation exposure are provided in Table 8.2-2.
If 25% of the annual administrative limit (i.e., 250 mrem) is I
exceeded in any quarter, then an investigation shall be performed and documented to determine what types of activities may have contributed to the worker's external exposure.
The-administrative limit already reflects ALARA principles,_so this action level is appropriate.
This investigation may_ include, but not be limited to procedural reviews, efficiency studies of the-air handling system, cylinder storage protocol, and work l
practices.
8.2.2.4.2 Internal Monitoring Internal exposures for all personnel wearing external _ dosimetry =
1 devices will be evaluated via body burden analysis, urinalysis, or an equivalent technique.
Internal doses will be evaluated i
annually.
Continuous air monitoring in airborne radioactivity areas may be performed to complement the bioassay program.
Alarm setpoints on
.i the continuous air monitors in the airborne radioactivity areas:
i may be used to provide an indication that internal exposures may.
be approaching the administrative limit.
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8.2-5 October 1993
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m If the annual administrative limit is exceeded as determined from
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bioassay results, then an investigation shall be performed and-(
documented to determine what types of activities may have contributed to the worker's internal exposure.
The administrative limit already reflects ALARA principles, so this action level is appropriate.
This investigation may include, but not be limited to procedural reviews, efficiency studies of the-j air handling system, and work practices.
8.2.2.4.3 Evaluation of Doses i
Dose evaluations may be performed at more frequent intervals and 1
should be performed when reasonable suspicion exists regarding an abnormal exposure.
The internal and external exposure values l
will be summed in accordance with 10 CFR 20.'1202.
B.2.2.5 Monitor Stations j
Monitor stations are the entry and exit points for the RCA.
i Monitors are provided to detect radioactive. contamination on personnel and their personal items, including hard hats.
All personnel are required to. monitor themselves, any hand-carried personal items, and hard hats prior to exiting-the RCA.
Radiation protection managtment is responsible for. monitor
[
station provision and maintenance.
Projected monitor station i
locations are shown on Figure 8.2-1 (sheet 2 of 3).
These locations shall be evaluated and changed accordingly to reflect O
changes in the RCA locations in the facility.
l 8.2.2.6 Locker Rooms
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Men's and women's locker rooms are provided for personnel to change into appropriate. work clothing and store personal belongings. The following facilities and activities are provided for in the locker room area 7
Shower Rooms _- men's and women's shower rooms are provided as a-I place for personnel to wash / clean up after work.
These shower rooms are not intended for personnel decontamination.
Restrooms - men's and women's-restrooms are provided.
These rooms are not for personnel decontamination.
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First Aid Station
- a first aid station is provided to. treat injured personnel.
i Personnel Decontamination Area
- a personnel decontamination area is provided to handle cases of accidental radioactive i
contamination.
A handwashing sink and a shower are provided for contamination removal.
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8.2-6 October 1993 l
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Information Area - an information area is provided to notify
/' '.
personnel of information'important to radiation protection..
Radiation' Work' Permits will be posted informing personnel of radiation levels and contamination control procedures'for various activities.
A current copy of the personnel Radiation Dose Record will be posted.
Storace - storage areas are provided for the following items:
a.
anti-contamination clothing b.
respiratory protection equipment c.
shower rooms supplies d.
health physics supplies 8.2.3 CONTAMINATION AND RADIATION CONTROL 8.2.3.1 Desion Basis The goal of maintaining occupational internal and external.
radiation exposures ALARA includes individual doses and_the collective dose of the entire working population.
8.2.3.1.1 Internal Exposures Because the radionuclides present in this facility under routine operations are primarily alpha, beta and low-energy gamma emitters (see Table 6.2-10), the potential for significant.
internal' exposure is greater than that for external exposure.
Parameters important to determining internal doses are:
the quantity of radioactive material taken into the body, a.
b.
the chemical form of the radioactive material, c.
the type and half-life of radionuclide involved, and d.
the time interval over which the material remains in the body.
The principal modes by which radioactive material can be taken into the body are:
l a.
inhalation, j
t b.
ingestion, c.
absorption through the skin, and d.
injection.through wounds.
i 8.2-7 October 1993 j
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t 8.2.3.1.2 External Exposures
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The potential for significant external exposure to personnel under routine operating conditions is.less significant than that for internal. exposures.
This is primarily due to the nature of
?
the radionuclides present in the facility.
l Parameters important in determining dose from external exposures are:
i a.
the length of time the worker remains in the radiation j
- field, 1
l b.
the intensity of the radiation field, and q
i c.
the portion of the body (whole vs. partial) receiving the
[
dose.
.{
Historical data from European facilities of similar construction l
show relatively low doses compared to nuclear power plant doses.
8.2.3.1.3 LES Philosophy
{
f The LES philosophy for radiation protection is reflected in the l
establishment of a Radiation _ Protection Program that has the j
specific purpose of maintaining occupational radiation exposures l
This program will include written procedures,. periodic i
i assessments of work practices and internal / external doses.
received, work plans and the personnel and equipment required to help implement the ALARA goal.
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8.2.3.2 Procedures l
i Procedures are provided in the following areas to administrative 1y control personnel radiation exposure:
-l a.
Operation j
f b.
Design c.
Maintenance d.
Modification t
t e.
Decontamination
.f f.
Surveillance f
g.
Procurement i
8.2-8 October 1993 t
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P 8.2.3.3 Instrumentation hr t
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Two basic types of personnel monitoring equipment are used at the CEC.
These are 1) count rate meters
(" friskers"), and 2) hand and foot monitors.
l 8.2.3.3.1 Friskers These typically consist of a hand-held Eberline HP 210/260 (or equivalent) probe connected to an RM-14 (or equivalent) count rate meter.
Instructions for the use of these instruments are posted in a prominent location near the instrument.
Hand held l
friskers are typically placed in locations where conditions i
restrict the use of other monitors or for short-term use at
-temporary RCZs.
8.2.3.3.2 Hand and Foot Monitors These typically consist of multiple detectors arranged to monitor only hands and feet.
Instructions for the use of these monitors are prominently posted on or near the instrument.
Hand and foot monitors are used in applications where " pass-throughs" are frequent and where hand and foot monitoring is the major requirement.
8.2.3.4 Limits O\\
The following contamination and radiation control limits are established:
Contamination - a Contaminated Area is defined in accordance with l
Regulatory Guide 1.86 as any area where loose radioactive material is found at or above the following levels:
1000 dpm/100 cm2 beta / gamma 20 dpm/100 cm2 alpha j
Airborne Radioactivity - this has been defined in Section 8.2.1.1-of this document.
4 An RCZ shall be established and posted at all entrances to areas exceeding the radiation / contamination limits specified in-Section 8.2.1.1 for RCZs.
Small contamination areas (i.e.,
less than 1/4-of the room) may be roped off-or otherwise segregated'from the i
rest of the area.
Appropriate clothing and/or other equipment will be used to minimize exposure and prevent the spread of contamination.
Provisions for monitoring contamination and i
airborne activity levels are discussed in Section 8.4.
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8.2-9 October 1993 e
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8.2.4 MAINTENANCE AREAS AND PROCEDURES
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A major portion of the total radiation exposure of personnel is received _during maintenance of equipment.
Exposures are minimized by designing processes and equipment that contain s
radioactive material to require as little maintenance as possible.
Additional exposure reductions are achieved by:
a.
removing as much radioactive material as possible from the equipment and the area prior to maintenance, thereby reducing the intensity of the radiation field, and b.
providing adequate space for ease of maintenance reducing' the length of time required to complete the task, thereby reducing the time of exposure, and preparing and using procedures that contain specifications c.
for tools and equipment needed to complete the job, and j
d.
proper job planning, including practice on mockups, and e.
reviews of previous similar jobs, and f.
identification and communication of the highest contamination areas to the workers prior to the start.of work.
A specialized decontamination and maintenance area is provided in the Technical Services Area of the Separations Building.
The following activities are routinely performed in the-Decontamination Workshop:
a.
Decontamination of the following equipment used in contact t
with uranium hexafluoride:
1.
Pumps 2.
Valves 3.
Flexible connectors 4.
Traps 5.
Sample manifolds 6.
Sample bottles 7.
Instruments 8.
Miscellaneous piping sections 4
b.
Decontamination of the following equipment used in the-Separations Building to process effluents:
1.
Waste handling pumps 2.
Waste' handling valves 3.
Waste handling tools 4.
Miscellaneous piping sections 5.
Miscellaneous equipment 8.2-10 October 1993 t
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Decontamination of scrap metal items in lieu of disposing ~of~
the item as radioactive waste.
8.2.4.1 Facilities 8.2.4.1.1 Contaminated Equipment Workshop The Contaminated Equipment Workshop, including the Contaminated Workroom, is designed to provide an area to disassemble equipment contaminated with radioactive material.
The majority of the work done in this area involves pumps, valves, and other equipment that is used in the Separations Building to handle uranium hexafluoride.
r The workshop consists of the following areas:
a.
A general disassembly area for disassembling slightly contaminated equipment that will produce no airborne contamination.
A glovebox is provided in this area for the disassembly of small components such as instruments.
The i
following equipment is provided in this area:
1.
Drill press
-j 2.
Lathe i
3.
Milling machine
+
4.
Arbor press 5.
Hand tools b.
Three contaminated disassembly rooms with special ventilation for the disassembly of contaminated equipment. _This equipment typically consists of UF6 pumps and valves.
8.2.4.1.2 Decontamination Workshop The Decontamination Workshop consists of two identical process train arrangements.
Each train consists of the following:
a.
Solvent degreasing station b.
Hot citric acid bath with ultrasonic agitation c.
Hot rinse water bath with ultrasonic agitation d.
Monorail for immersing the components Each of the baths is 450 gallons and is adequate for all normal decontamination needs.
Also provided are two smaller citric acid and rinse water baths for handcleaning of'small components.
A wet blast cabinet is provided for cleaning adhering contamination from' components.
l 8.2-11 October 1993 i
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A dedicated area is provided for disassembly and decontamination of sample bottles.
This area contains a fume hood, a sink, and I
O work benches.
Rim ventilation is provided on all baths, a vent connection is provided on the wet blast cabinet, and a-fume hood is provided for sample bottle decontamination. All'of these are connected to l'
the Gaseous Effluent Ventilation System ("GEVS") to control-possible airborne radioactive contamination.
8.2.4.1.3 UF6 Equipment Workshop j
The UF6 Equipment Workshop provides an area to assemble and test f
components that will be used in UF6 service.
Contaminants that react with UF6, such as hydrocarbon oils, are specifically i
excluded from this workshop.
Typically all components that are-handled in this area are either decontaminated or are new.
The I
following types of tools are provided in the UF6 Equipment Workshop:
. l a.
Drill press i
f b.
Lathe c.
Milling machine d.
Grinders e.
Hand tools
[
f.
Band saw l
t g.
Arbor press t
h.
Degreasing equipment 8.2.4.1.4 Mechanical Workshop The Mechanical Workshop provides an area to perform maintenance on non-contaminated mechanical equipment. This equipment is
[
either from a non-contaminated part of the facility or has been decontaminated in the Decontamination Workshop.
The.following j
types of tools are provided in the Mechanical Workshop:
I a.
Drill press b.
Lathe
- l c.
Milling machine' d.
Grinders 8.2-12 October 1993 3
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Hand tools n
v f.
Welding equipment g.
Band saw h.
Arbor press i.
Degreasing equipment j.
Refrigerant recovery equipment 8.2.4.1.5 Electrical Workshop The Electrical Workshop provides an area to perform maintenance on electrical equipment and instruments that are not contaminated.
This equipment is either from a non-contaminated-part of the facility or has been decontaminated in the Decontamination Workshop.
8.2.4.2 Exposure Limits LES administrative personnel exposure limits have been set below the limits specified in 10 CFR Part 20.
This provides assurance that legal radiation exposure limits will.not'be exceeded and that ALARA criteria are emphasized.
The administrative exposure limits are shown in Table 8.2-2.
8.2.4.3 Exposure Estimates Estimates of the radiation exposure of personnel, as a result of normal operation, are shown in Table 8.2-3.
i These estimates are based upon worker exposure histories from similar facilities in Europe.
European data is included;in Tables 8.2-4, 8.2-5, and 8.2-6.
l 8.2.5 DECONTAMINATION PROVISIONS 8.2.5.1 Desian Basis Exposures to personnel who must work around and service aquipment containing radioactive material can be reduced by removing the radioactive material from the equipment, to the. extent reasonably l
possible, prior to servicing.
Surface contamination should be removed to minimize its spread to other areas of the facility.
Surfaces can be decontaminated more expeditiously if they are-smooth, nonporous and free of cracks,-crevices and sharp corners.
Where necessary, special coatings have been specified for facility equipment to improve surfaces for decontamination.
(
8.2-13
. October 1993 5
3 8.2.5.2 Separations Buildinq
' Decontamination facilities and procedures for the Technical Services Area of the Separations Building are discussed in j
.Section 8.2.4. For the remaining areas of the Separations Building decontamination requirements involve only localized performed that involves opening a uranium-containing system.
All clean-up at areas where maintenance has been or is being decontamination of components removed from their systems for.
maintenance is performed in Technical Services Area facilities.
No other areas of the facility will normally require decontamination.
i 8.2.5.3
-Final Decontamination and Decommissionina-l Final decontamination and decommissioning of the facility is discussed in Section 11.8.
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l TABLE 8.2-2 Administrative Radiation Exposure Limits (a,b)
Conditions of Exposure Administrative Limit Total Effective Dose Equivalent i rem / year j
internal + external (routine operations)
(a)
Excludes accident situations.
(b)
No routine extremity or skin monitoring is required.
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7
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f October 1993
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I i
TABLE OF CONTENTS 11.1 ORGANIZATIONAL STRUCTURE 11.1-1 f
11.1.1.
CORPORATE FINANCIAL RESPONSIBILITIES 11.1-1 11.1.2 CORPORATE FUNCTIONS, RESPONSIBILITIES, AND AUTHORITIES 11.1-1 11.1.3 OPERATING ORGANIZATION 11.1-2 l
11.1.3 1 CEC Orcanization 11.1-2 11.1.3.2 Shift Crew Composition 11.1-8 l
11.1.3.3 Facility Safety Review Board (FSRC) 11.1-8 11.1.3.4 Approval Authority For Personnel Selection 11.1-9
.I 11.1.4 PERSONNEL QUALIFICATIONS REQUIREMENTS 11.1-9 11.1.4.1 Minimum Oualifications 11.1-9 11.1.4.2 Facility Personnel Oualifications 11.1-14 4
11.1.5 TRAINING 11.1-14 i
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LIST OF. TABLES
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11.1-1 Louisiana Energy Services Organization L
- 11.1-2 Louisiana Energy Services Construction and Operating l
Organization p
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11.1-3 Louisiana Energy Services Claiborne Enrichment Center l
Operating Organization t
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11.1 ORGANIZATIONAL STRUCTURE 11.1.1' CORPORATE FINANCIAL RESPONSIBILITIES LES is a limited partnership.
It has been formed to provide uranium enrichment services for commercial nuclear power plants.
The partnership is outlined in detail in Section 1.1.6.
LES is responsible for the design, quality assurance, construction and operation of the facility.
The President of LES reports to the LES Management Committee.
This Committee is composed of representatives from the four general partners of LES
- Urenco Investments, Inc., Claiborne Fuels L.P.,
Graystone Corporation, and Claiborne Energy Services, Inc. -Table 11.1-1 outlines this relationship.
11.1.2 CORPORATE FUNCTIONS, RESPONSIBILITIES, AND l
AUTHORITIES g
LES is responsible for the design, quality assurance, construction, testing, start-up and operation of the CEC.
LES has contracted Urenco to prepare the reference design for the facility, while Fluor Daniel, Inc. and Duke Engineering &
Services, Inc. are contracted to further specify structures and systems of the facility, including responsibility for specifying l
the materials and equipment.
j i
O Preparation of construction documents and construction itself are contracted to qualified contractors.
LES has direct
.i responsibility for preoperational testing, initial start-up, operation and maintenance of the facility.
Urenco will design, manufacture and deliver to the site the i
centrifuges necessary for facility operation.
In addition, Urenco is supplying technical assistance and consultation for the facility.
Urenco has a great deal of experience in the gas centrifuge uranium enrichment process since it operates three gas centrifuge uranium enrichment sites in Europe.
Urenco is-conducting technical audits of the design activities of Duke Engineering & Services and Fluor Daniel to ensure the design of v
the Claiborne Enrichment Center is in accordance with the Urenco i
reference design information, j
As the facility nears completion, LES will staff the facility to ensure smooth transition from construction activities to i
operation activities.
Urenco, who has been operating gas centrifuge enrichment facilities in Europe for over 16 years, has l
personnel who are integrated into the organization to provide technical support during initial startup of the facility.
j
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11.1-1 October 1993 I
i
l
~I 11.1.3 OPERATING ORGANIZATION The operating organization for LES is shown.in Tables 11.1-2 and
.l 11.1-3.
The positions shown are functional and may not correspond to actual titles.
The CEC is staffed at sufficient j
levels prior to operation to allow for training, procedure development, and other pre-operational activities.
l 11.1.3.1 CEC Orcanization j!
The functions and responsibilities of the facility supervisory staff are described in the succeeding paragraphs.
'i a)
CEC Manager i
The CEC Manager reports to the LES President and has direct' l
responsibility for operation of the facility in a safe, reliable
-l and efficient manner.
The CEC Manager is responsible for proper selection of CEC staff for all key positions including positions on the Facility Safety Review Committee.
The CEC Manager is l
responsible for the protection of the facility staff and the general public from radiation and chemical exposure and/or any i
other consequences of an accident at the facility and also_ bears the responsibility for compliance with the facility license.
The CEC Manager or designee (s) have the authority to approve and i
issue Department Directives and procedures.
i
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b)
Quality Assurance Manager The Quality Assurance (QA) Manager reports to the CEC Manager and is responsible for implementing the Quality Assurance Program'for i
the facility.
This includes responsibility for ensuring all activities at the facility affecting quality are performedLin j
accordance with appropriate regulations, codes and standards.
l This position is independent from other management positions at the facility to ensure the QA Manager has access to the CEC Manager for matters affecting quality.
In addition, the QA Manager has the authority and responsibility to contact directly-the QA Director and/or LES President with any Quality Assurance l
concerns.
c)
Operations Superintendent i
The Operations Superintendent reports to the CEC Manager and has j
the responsibility of directing the day-to-day operation of the facility.
This includes such activities as ensuring the correct-and safe operation of the handling of UFs, and the periodic l
testing of equipment to ensure-safe and efficient operation.
In the event of the absence of the CEC Manager, the Operations l
Superintendent may assume the responsibilities and authorities of j
the CEC Manager.
i i
11.1-2 October 1993 i
1
.i i
i e
d)
Integrated Scheduling Superintendent
)
The Integrated Scheduling (IS) Superintendent reports to the CEC.
I Manager and has the responsibility of directing the scheduling of enrichment operations to ensure smooth production at the facility.
This includes such activities as ensuring proper' feed material and maintenance equipment is available for the facility.
The IS Superintendent is also responsible for providing administrative and human resource services to the facility.
In the event of the absence of the CEC Manager, the IS Superintendent may assume the responsibilities and authorities of-the CEC Manager.
e)
Maintenance Superintendent The Maintenance Superintendent reports to the CEC Manager and has the responsibility of directing and scheduling maintenance activities to ensure proper operation of the facility.
This includes activities such as repair and preventive maintenance of facility equipment.
In the event of the absence of the CEC Manager, the Maintenance Superintendent may assume the responsibilities and authorities of the CEC Manager.
f)
Compliance Superintendent The Compliance Superintendent reports to the CEC Manager and has the responsibility of directing the activities that ensure the i
facility maintains compliance with appropriate regulations and conformance with applicable codes.
This includes activities i
associated with physical security,. classified matter and information, licensing, emergency preparedness, safeguarding of
~
special nuclear material and compliance with environmental regulations.
In the event of the absence of the CEC Manager, the-l Compliance Superintendent may assume the responsibilities and i
authorities of the CEC Manager.
g)
Technical Support Superintendent P
The Technical Support (TS) Superintendent reports to the CEC Manager and has the responsibility of providing technical support to the facility.
This includes activities associated with health physics, criticality safety, chemistry, industrial safety and engineering and computer support.
In the event of the absence of the CEC Manager, the Technical Support Superintendent may assume-the responsibilities and authorities of the CEC Manager.
h)
Security Manager The Security Manager reports to the Compliance Superintendent and has the responsibility for directing the activities of security personnel to ensure the physical protection of the facility.
The Security Manager is also responsible for the protection of
(
11.1-3 October 1993 l
)
i P
classified matter and information at_the facility and obtaining
/~
-proper security clearances for' facility personnel and support
(,,T/
personnel.
In matters involving physical protection of the facility or classified matter, the Security Manager has direct access to the CEC Manager.
i)
Safeguards Manager The Safeguards Manager reports to the Compliance Superintendent and has the responsibility for ensuring the proper implementation l
of the Fundamental Nuclear Material Control (FNMC) Plan.
This position is separate from and independent of the operations, maintenance, and technical support departments to ensure a definite division between the safeguards group and the other departments.
In matters involving safeguards, the Safeguards I
Manager has direct access to the CEC Manager.
j)
Emergency Preparedness Manager l
The Emergency Preparedness Manager reports to the Compliance Superintendent and has the responsibility for ensuring the facility remains prepared to react and respond to any emergency situation that may arise.
This includes emergency preparedness training of facility personnel, facility support personnel, the j
training of, and coordination with, offsite emergency response.
1 organizations, and conducting periodic drills to ensure facility l
personnel and offsite response organization personnel training-is
'I maintained up to date.
k)
Health Physics Manager The Health Physics Manager reports to the Technical Support Superintendent and has the responsibility for implementing the health physics program.
These duties include the training of personnel in use of equipment, control of radiation exposure of personnel, continuous determination of the radiological status of the facility, and conducting the radiological environmental monitoring program.
During emergency conditions the Health Physics Manager's duties shall also include:
providing Emergency Operations Center personnel information and recommendations concerning chemical and radiation levels at the facility.
gathering and compiling outsite and offsite radiological and chemical monitoring data, making recommendations concerning actions at the facility-f and offsite deemed necessary for limiting exposures to.
facility personnel and members of the general public, and 11.1-4 October 1993 i
i 1
taking prime responsibility for decontamination activities.
In matters involving radiological protection, the Health Physics Manager has direct access to the CEC' Manager..
1 1)
Projects Manager The Projects Manager reports to the Technical Support
{
Superintendent and has the responsibility for the implementation of facility modifications and the approval of facility procedures i
and modifications for criticality safety.
The Projects Manager also provides engineering support as needed to support facility j
operation and maintenance.
This support includes performance testing of systems and equipment.
m)
Chemistry Manager l
The Chemistry Manager reports to the Technical Support Superintendent and has the responsibility for maintaining chemical labs and other chemical support facilities for the CEC.
This includes the analysis of environmental samples for chemical characteristics (e.g.,
temperature, pH).
l n)
Industrial Safety Manager The Industrial Safety Manager reports to the Technical Support-l O
Superintendent and has the responsibility for maintaining the facility's fire protection systems and other systems ti.at allow
~
for the safe operation of the facility in accordance with Occupational Safety and Health requirements.
t o)
Performance Manager l
The Performance Manager reports to the Technical Support l
Superintendent and has the responsibility for coordinating and maintaining testing programs for the facility.
This includes i
testing of systems and components to ensure the systems and components are functicning as specified in design documents.
p)
Licensing Manager The Licensing Manager reports to the Compliance Superintendent and has the responsibility for coordinating facility activities i
to ensure compliance is maintained with applicable Nuclear Regulatory Commission (NRC) requirements.
The Licensing Manager is also responsible for ensuring abnormal events are reported to i
the NRC in accordance with NRC regulations.
q)
Environmental Compliance Manager l
i The Environmental Compliance Manager reports to the Compliance Superintendent and has the responsibility for coordinating
)
11.1-5 October 1993 i
.1
-)
facility activities to_ ensure all local, state and federal i
environmental regulations are met.
This includes submission of
'~
periodic reports to appropriate regulating organizations of i
effluents from the CEC.
i r)
Community Relations The Community Relations Manager reports to the Compliance l
Superintendent and has the responsibility for providing information about the CEC and LES to the public and. media.
During an abnormal event at the facility, the Community Relations j
Manager ensures that the public and media receive accurate and up-to-date information.
l s)
Maintenance Engineering Manager The Maintenance Engineering Manager reports to the Maintenance Superintendent and has the responsibility for providing maintenance support for equipment and systems at the CEC.
This includes preventive maintenance for appropriate equipment to ensure systems and equipment at the facility operate safely and as designed.
t)
Maintenance Technicians Manager The Maintenance Technicians Manager reports to the Maintenance j
Superintendent and has the responsibility for providing i
O maintenance support for equipment and systems at the CEC.
This includes periodic inspection and adjustment of equipment and systems at the CEC to ensure systems and' equipment at the facility operate safely and as designed.
i u)
Production Scheduling Manager The Production Scheduling Manager reports to the Integrated Scheduling Superintendent and has the responsibility for l
developing and maintaining production schedules for enrichment services.
v)
Cylinder Handling Manager i
The Cylinder Handling Manager reports to the Integrated Scheduling Superintendent and has the responsibility for ensuring that cylinders of uranium hexafluoride are received and dispatched correctly at the CEC.
t w)
Warehouse and Materials Manager The Warehouse and Materials Manager reports to the Integrated Scheduling Superintendent and has the responsibility for ensuring spare parts and other materials needed for operation of the CEC j
are ordered, received, inspected and stored properly.
11.1-6 October 1993 l
I
R x)
Administration Manager The Administration Manager reports to the Integrated Scheduling s
-Superintendent and has.the responsibility for ensuring support functions such as accounting, word processing and document.
control are'provided for the CEC.
y)
Human Resource Manager The Human Resource Manager reports to the Integrated Scheduling Superintendent and has the responsibility for ensuring adequate staffing and training is'provided for CEC employees.
z)
Operations Engineering Manager
}
i The Operations Engineering Manager reports to the Operations Superintendent and has the responsibility for ensuring safe operation of enrichment equipment and support equipment.
This' includes the development of operating procedures for the CEC.
aa)
Operations Shift Technicians Manager The Operations Shift Technicians Manager reports to the Operations Superintendent and has the responsibility for ensuring 4
safe operation of enrichment equipment and support equipment. The-Operations Shift Technicians Manager directs personnel in order j
to provide enrichment services in a safe,-efficient manner.
ab)
Quality Assurance Inspectors Supervisor The Quality Assurance Inspectors Supervisor reports to the j
Quality Assurance Manager and has the responsibility.for performing inspections related to the implementation of the LES i
Quality Assurance Plan.
ac)
Quality Assurance Auditors Supervisor i
The Quality Assurance Auditors Supervisor reports to the Quality j
Assurance Manager and has the responsibility for performing
^
audits related to the implementation of the LES Quality Assurance Plan.
i ad)
Quality Assurance Technical Support Supervisor i
The Quality Assurance Technical Support SupervisorLreports to the Quality Assurance Manager.and has the responsibility for providing technical support related to the implementation of the f
LES Quality Assurance Plan.
I i
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11.1-7 October 1993 i
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i 11.1.3.2 Shift Crew Composition i
The minimum operating shift crew consists of a Shift Supervisor, one control room operator, one Health Physics technician, and one operator for each of the plant units.
11.1.3.3 Facility Safety Review Committee (FSRC)
The CEC facility maintains a Facility Safety Review Committee (FSRC) to assist with the safe operation lof the facility.
11.1.3.3.1 Facility Safety Review Committee (FSRC)
The Facility Safety Review Committee (FSRC) shall report to the CEC Manager and shall provide technical and administrative review and audit of CEC operations which could impact plant worker and public safety.
The scope of activities reviewed and audited by the FSRC shall, as a minimum, include the following:
Radiation protection Nuclear criticality safety control Hazardous chemical safety Industrial safety including fire protection Environmental protection ALARA policy implementation Changes in facility design or operations l
The FSRC shall conduct at least one facility audit per year for the above areas.
The Facility Safety Review Committee shall be composed of at least five (5) members, including the Director.
Members of the FSRC may be from the LES corporate office or CEC technical staff.
The five members shall include experts on operations and all i
safety disciplines (criticality, radiological, chemical, i
industrial).
The Director, members and alternate members of the Facility Safety Review Committee shall be formally appointed by the CEC Manager, shall have an academic degree in an engineering t
or physical science field; and, in addition, shall have a minimum of five (5) years of technical experience, of which a minimum of three (3) years shall relate directly to one or more of the safety disciplines (criticality, radiological, chemical, industrial).
The Facility Safety Review Committee shall meet at least once per calendar quarter during the period of initial operation.
(The period of initial operation is defined on a plant unit basis.
It includes first-time operation of a plant unit beginning with initial fill of the first cascade until 1 month after steady-state operation of that unit's last cascade.)
Subsequent to the period of initial operation, the meeting frequency shall not be 11.1-8 October 1993
i less than three (3) each calendar year with a_ maximum interval'of-
- 180 days between any two consecutive meetings.
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Review meetings shall be held within 60 days of any incident which is_ reportable to the NRC.
These meetings may be' combined with regular meetings.
Following a reportable incident, the FSRC l
shall review the incident's causes, the responses,- and both specific and generic corrective actions to ensure resolution of the problem is implemented.
A written report of each FSRC meeting and audit shall be forwarded _to the station manager and superintendents within 30 days and be retained for at least three years.
l 11.1.3.4 Approval Authority For Personnel Selection
{
The assignment of individuals to the position of Superintendent and manager, and to positions on the FSRC, shall be approved by
'[
the CEC Manager.
Assignments to all other staff positions shall be made within the i
normal administrative practices of the CEC.
11.1.4 PERSONNEL QUALIFICATIONS REQUIREMENTS 11.1.4.1 Minimum Oualifications The minimum qualification requirements for the facility functions that are directly responsible for its safe operation shall be as outlined below.
The nuclear experience of each individual shall l
be determined-to be acceptable by the CEC Manager.
" Responsible nuclear experience" for these positions shall include (a) esponsibility for and contributions towards support of facility (s) in the nuclear fuel cycle (e.g.,
- design, construction, operation, and/or decommissioning), and (b) experience with chemical materials and/or processes.
Different experience requirements may be approved by the CEC Manager only as specified for key positions.
Key positions are identified on the CEC Proposed License Conditions.
Approval of different requirements shall be done in writing and only on a case by. case basis.
a)
CEC Manager The CEC Manager shall be appointed by the President of LES as the.
i overall manager of the Claiborne Enrichment Center.
This appointment reflects confidence in the individual's ability as an t " Jctive programs and business manager.
The CEC Manager shall t-nowledgeable of the enrichment process, enrichment process controls and ancillary processes, criticality safety control and radiation protection program concepts as they apply to the-overall safety of a nuclear facility.
The CEC Manager shall l
(
11.1-9 October 1993 j
1
-i have, as a minimum, a bachelor's degree (or equivalent) in an T
engineering or scientific field and six years of responsible
,,/
nuclear experience.
b)
Quality Assurance Manager The Quality Assurance (QA) Manager shall have a minimum of eight i
years of appropriate, responsible nuclear experience in'the implementation of a quality assurance program, y
c)
Operations Superintendent r
The Operations Superintendent shall hold a bachelor's degree (or.
equivalent) in an engineering or scientific field and have a
]
minimum of eight years of appropriate, responsible nuclear experience.
y d)
Integrated Scheduling Superintendent T
The Integrated Scheduling (IS) Superintendent shall have a i
i minimum of eight years of appropriate, responsible nuc'. ear experience.
y e)
Maintenance Superintendent The Maintenance Superintendent shall hold a bachelor's degree (or equivalent) in an engineering or scientific field and have a O
minimum of eight years of appropriate, responsible. nuclear g
experience.
-j
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I f)
Compliance Superintendent The Compliance Superintendent shall hold a bachelor's degree l
(or equivalent) in an engineering or scientific field and have a minimum of eight years of appropriate, responsible nuclear experience.
_l
+
g)
Technical Support Superintendent The Technical Support (TS) Superintendent shall hold a bachelor's.
j degree (or equivalent) in an engineering or scientific field and have a minimum of eight years of appropriate, responsible nuclear experience.
_j h)
Security Manager The Security Manager shall have a minimum of five years of experience in the management of physical security at a facility requiring security capabilities similar to those required for the l
CEC.
No credit for academic training may be taken toward fulfilling this experience requiremene.
f 11.1-10 October 1993 i
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=-a t
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i)
Safeguards Manager
)
,/.
The Safeguards Manager shall have a minimum of five years of 1
experience in the management of a safeguards program for special.
nuclear material, including responsibilities for material control, material accountability, and physical security.
No j
credit for academic training may be taken'toward fulfilling this i
experience requirement.
1 j)
Emergency Preparedness Manager i
i The Emergency Preparedness Manager shall have a minimum of five' 1
years of experience in the implementation of. emergency plans and-procedures at a nuclear facility.
No credit for academic training may be taken toward fulfilling this experience requirement.
I k)
Health Physics Manager i
The Health Physics Manager shall have a minimum of five years of i
appropriate, responsible experience jn the implementation of a I
health physics program at a nuclear facility.
y 1)
Projects Manager The Projects Manager shall hold a bachelor's degree (or equivalent) in an engineering or scientific field and have a-minimum of five years of appropriate, responsible nuclear experience.
The Projects Manager shall also have at least one year of direct experience in the-administration of nuclear criticality safety reviews.
L Within the Projects group shall be at least one individual with a minimum of two years experience in the implementation of'a 1
criticality safety program.
This individual shall hold a bachelor's degree (or equivalent) in an engineering or scientific j
field and have successfully completed a training program, i
appropriate to the scope of operations, in the physics of l
criticality and in associated safety practices.
Should changes to the facility be proposed which require new.
nuclear criticality safety analyses, trained individuals shall j
perform the analyses.
Trained individuals with at least two years of experience in analyses and criticality safety program implementation shall independently review and approve the 1
^!
analyses.
The independent reviewer (s) shall possess a BS degree (or equivalent) in an engineering or scientific field m)
Chemistry Manager i
The Chemistry Manager shall have a minimum of five years of-appropriate, responsible nuclear experience.
Q.
11.1 October 1993-l I
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)
i n)
Industrial Safety Manager
(
(
The Industrial Safety Manager shall have a minimum of five years.
I of appropriate, responsible experience in implementing and supervising an industrial _ safety program, including fire protection.
y o)
Performance Manager The Performance Manager shall have a minimum of five years of-appropriate, responsible experience in implementing and supervising a nuclear performance program.
q p)
Licensing Manager The Licensing Manager shall have a minimum of five years of appropriate, responsible experience in implementing and supervising a nuclear licensing program.
y q)
Environmental Compliance Manager The Environmental Compliance Manager shall have a minimum of five years of appropriate, responsible experience in implementing and supervising a nuclear environmental compliance program.
y r)
Community Relations Manager The Community Relations _ Manager shall have a minimum of three-years.of appropriate, responsible experience in implementing and-supervising a community relations program.
s)
Maintenance Engineering Manager The Maintenance Engineering Manager _shall have a minimum of.five years of appropriate, responsible experience in implementing and.
supervising a nuclear maintenance program.
q-t)
Maintenance Technicians Manager The Maintenance Technicians Manager shall have a minimum of five years of appropriate, responsible experience in implementing'and supervising a nuclear maintenance program.
y u)
Production Scheduling Manager The Production Scheduling Manager shall have a minimum of three years of appropriate, responsible experience in implementingLand supervising a continuous production scheduling program.
11.1-12 October 1993
+
.=.
I v)
Cylinder Handling Manager
.i r
The Cylinder Handling' Manager shall.have a minimum of three-years
'^
of appropriate, responsible experience in implementing and supervising a continuous production' scheduling program.
w)
Warehouse and Materials Manager The Warehouse and Materials Manager shall have a minimum of three years of appropriate, responsible' experience in implementing and supervising a purchasing and inventory program.
i x)
Administration Manager The Administrative Manager shall have a minimum of three years of appropriate, responsible experience in implementing and '
supervising administrative responsibilities at an industrial facility.
f y)
Human Resource Manager The Human Resource Manager shall have a minimum of three years.of appropriate, responsible experience in implementing and supervising human resource responsibilities at an industrial facility.
J z)
Operations Engineering Manager
~!
The Operations Engineering Manager shall have a minimum of five
+
years of appropriate, responsible experience in implementing and supervising a nuclear operations program.
y aa)
Operations Shift Technicians Manager The Operations Shift Technicians Manager shall have a minimum of five years of appropriate, responsible experience in implementing and supervising a nuclear operations program.
Q ab)
Quality Assurance Inspectors Supervisor The Quality Assurance Inspectors Supervisor shall have a minimum of five years of appropriate, responsible experience in 1
implementing and supervising a nuclear-Quality Assurance program.y ac)
Quality Assurance Auditors Supervisor The Quality Assurance Auditors Supervisor shall have a minimum of-l five years of appropriate, responsible experience in implementing and supervising a nuclear Quality Assurance program.
-[
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11.1-13 October 1993
.l r
i 9
7
_..,,y
ad)
Quality Assurance Technical Support Supervisor The Quality Assurance Technical Support Supervisor shall have a minimum of five years of appropriate, responsible experience in implementing and supervising a nuclear Quality Assurance. program.-j 11.1.4.2 Facility Personnel Oualifications The qualifications of'the individuals assigned to the key facility positions outlined in section 11.1.3 will be provided to the NRC by LES as soon as they are available and before receipt of nuclear material at the facility.
Development and maintenance of qualification records and training programs are the responsibility of the Human Resource Manager.
11.1.5 TRAINING Formal planned training programs shall be established for CEC employees.
Indoctrination training shall be provided to all l
employees within 30 days of reporting.to work, and shall address safety preparedness for all safety disciplines (criticality, radiological, chemical, industrial), ALARA practices, and emergency procedures.
In depth training programs shall be e
provided to individuals depending on job requirements in the i
I areas of radiological safety (for all personnel with access to.
restricted areas) and in criticality safety control.
Nuclear criticality safety training shall satisfy the requirements of
()
ANSI /ANS 8.20 - 1991 " Nuclear Criticality Safety Training."
Retraining of personnel previously trained shall be performed'for radiological and criticality safety at least-annually, and shall:
include updating and changes in required skills.
The training program shall include methods for verifying training effectiveness, such as written tests, actual demonstration of skills, and where required by regulation, maintaining a current and valid license demonstrating qualification.
Changes to training shall be implemented if indicated due'to incidents potentially compromising safety, or if changes'are made to facilities or processes.
Records of training successfully completed shall be maintained in accordance with Section 11.4.2 for all personnel.
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11.1-14 October 1993
_