ML20133C567

Revised Site Decommissioning Plan

ML20133C567
Person / Time
Site:	07000734
Issue date:	12/31/1996
From:	GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML20133C566	List: ML20133C563 ML20133C567
References
NUDOCS 9701070231
Download: ML20133C567 (8)

Text

_ -.

+ %ii L"su l.

1 i

l GENERAL ATOMICS' I

SITE DECOMMISSIONING PLAN SEPTEMBER 1996 (Revised December 1996) jTa' Bas 3?sajp

CENERAL T AFDANCE REVISIONS TO GA'S SITE DECOMMISSIONING PLAN DATED SEPTEMBER 1996 December 1996 Revision - (1) Adds Section 9 " Fire Protection"; Table of Contents and Cover Page Revised to Reflect these Changes.

(2) Page 3-15 revised to show labs 645 mezzanine and labs 645/647 are in Group 8C (not Group 8B).

t I

i I

e

i i

l Y> m 1

l mammes TABLE OF CONTENTS TA B LE OF CONTENTS............................................................... ii LIST OF TAB LES......................................

.............iv LIST OF FIG U RES......................................

iv INTRODUCTION.........................................

...................... I S U M MA R Y

................................................................ S - 1 1

1.

GENERAL INFORMATION AND

SUMMARY

OF D&D EXPERIENCE.............. 1-1 i

1.1 Licensee Name and Address.........................

1-1 l

1.2 Licensee Information.............

1-1 2.

SUMMARY

OF D&D EXPERIENCE........................

2-1 3.

S ITE DESC RIPTION...................................................... 3-1 3.1 Location and Si ze......................................................

3-1 3.2 Topography......................................................... 3 1 l

3.3 GA Facilities...

....................................32 i

3.3.1 GA's Sorrento Electronics Site.................

..... 3-2 i

3.3.2 Room 049 0f B uilding 9......................

............. 3 2 3.3.3 B uildi ng 10.................................

............ 3-3 3.3.4 TRIGA Reactors Building (Building 21).........

......... 3-3 3.3.5 TRIGA Fuel Fabrication Facility (Building 22)............

.... 3-3 3.3.6 Hot Cell Facility (Building 23)....................................... 3-3 1.3.7 low-Level Liquid Filtration Facility (Building 25).......................

3-4 3.3.8 Nuclear Waste Processing Facility (Building 41).........................

3-4 3.3.9 Experimental Area (Building 27).....................................

.3-4 3.3.10 Experimental Area Bunker (Building 27-1).......................

..... 3 -4 j

3.3.11 Linac Facility (Building 30)

... 3-4 3.3.12 NMA Storage " Vault" (Building 31)..................

... 3-5 3.3.13 Inertial Confinement Fusion (Building 33)

.... 3-5 3.3.14 Building 331 (Former HP Lab)

.......3-5 3.3.15 Fusion. Building (Building 34)..........

.. 3-5 3.3.16 Test Tower (Building 35).................................... 3-5 3.3.17 Sorrento Valley A (Building 37).................

.. 3-6 3.3.18 Fuel Production Process Building - Sorrento Valley B (Building 39)........... 3 -6 3.3.19 Calibration Facility (Building 42)..................................... 3-6 3.3.20 Science Laboratories (Building 2)......

............ 3-7 3.3.21 Underground Storage Tanks -Buildings 9,31,21 & Lab 540 of Bldg. 2......... 3-8 4.

DECOMMISSIONING ORGANIZATION, TRAINING AND METHODS USED FOR PROTECTION OF OCCUPATIONAL AND PUBLIC HEALTH AND SAFETY........................ 4-1 4.1 Decommissioning Organization and Responsibilities........

..... 4-1 4.2 Description of Overall Organizational Structux...............

........... 4-1 4.3 Decommissioning safety Responsibilities..............

. 4-1 4.3.1 Industrial Safety / Hygiene.......

......... 4-1 4.3.2 Radiological Safety............................................... 4-2 4.4 Trai n i ng..............................

.........4-2 4.4.1 Radiological Safety / Retraining.................

.........4-2 4.4.2 Equipment Operator Training.......................................

4-3 4.4.3 Safety / Accident Prevention Training.................................... 4-3 l

4.4.4 Hazardous Material Training......................................... L4 i

}

4.4.5 Other Trai ni ng.............................................

4-5 l

4.5 Procedu res....................

..........4-5 i

l r

11 i

m pe-y

-.-v-4w

+

--w e-m*

+ diWNRIEJBL f

AMRANCS 4.6 Schedule...............

... 4-5 4.7 Methods Used for Protection of Occupational and Public Health and Safety.......... 4-5 4.7.1 ALA RA Program................................................... 4-5 4.7.2 Management Positions Responsible for Radiation Protection and Maintaining

-r E x po s u re s................................................... 4 -6 4.7.3 Mcthods for Occupational Exposure Reduction............................ 4-6 4.7.3.1 Work Authorization Approval..............................

4-6 4.7.3.2 Radiation Work Permits................................... 4-7 4.7.4 Control and Storage of Radioactive Materials...

4-7 4.8 Health Physics Program..........

4-7 4.8.1 Project Health Physics Program - General............................... 4-7 4.8.2 Audits, inspections, and Management Review........

............ 4 -8 j

4.8.3 Health Physics Equipment and Instrumentation..................

... 4-9 4.8.3.1 Criteria for Selection and Instrumentation for Conduct of Radiation and i

i Contamination Surveys and Personnel Monitoring................ 4-9 4.8.3.2 Storage, Calibration, Testing and Maintenance of Health Physics Equipment i

and Instrumentation.

4-9 4.8.3.3 Specific Health Physics Equipment and Instrument;non. Use and Capabilitie s........................................... 4-10 4.9 Processes & Systems for Handling, Storage, & Disposing of Radioactive Waste..

... 4-10 4.9.1 Conformance to Requirements of 10CFR61,10CFR71, & 10CFR20.2006

.... 4-11 4.9.2 Conformance to Disposal Site Requirements.....

................. 4-12 I

4.9.3 Conformance to State Requirements................................... 4-12 4.9.4 Waste Characterization Projections and Volumes..............

.. 4-12 5.

ANTICIPATED APPROACHES TO DECONTAMINATION AND DECOMMISSIONING..... 5-1 5.1 A PPR O A C H A..............................................

.5-2 L

5.2 APPROACH B 5-4 5.3 APPROACH C..........

................ 5-14 6.

FINAL SURVEY

. 6-1 6.1 Release Criteria for items, Equipment and Facility.........

........ 6-1 6.1.1 Release ofitems and Equipment......

......... 6-1 6.1.2 Release of a Facility.............................................. 6-2 6.1.3 Description of Final Radiation Survey Plan.....

.6-2 6.1.4 Classification of Areas by Contamination Poteatial......................

6-4 6.1.4.1 Scoping or Confirmatory Survey............................ 6-4 6.1.4.2 A ffected Area Surveys.................................... 6-4 6.1.4.3

' Unaffected Area Surveys...

................6-6 i

6.2 Soi! Sampling Plan.....................

....................6-6

[

6.2.1 Release Criteria

............... 6-7 6.2.2 Soil Background Concentrations..

................ 6-7 6.2.3 Affected Areas - Open Land Areas..............

... 6-8 6.2.4 Unaffected Areas - Open Land Areas

........ 6-11 6.2.5 Sample Collection.

............. 6-11 6.2.6 Direct Radiation Measurements...

...... 6-11 6.3 Methods to be Employed for Reviewing, Analyzing, and Auditing Data.

... 6-11 6.3.1 Laboratory / Radiological Measurements Quality Assurance................ 6-1 1 6.3.2 Supervisory and Management Review of Results..................

.6-11 6.4 Final Survey Report..................

...............612 7.

FUN DIN G..................................................

.. 7-1 8.

PHYSICAL SECURITY PLAN AND SPECIAL NUCLEAR MATERIAL ACCOUNTABILITY,. 8-1 iii

1 neannamens T MWMCS 9.

FI R E PROTECTION..................................................... 9-1 1

9.1 Fire Safety.........................

............9-1 i

9.2 Fire Safety Responsibilities.....................

....................9-1 i

9.3 Fire Pre vention.............................

................9-1 9.4 Fire Protection......................

................9-1 9.5 Fire Suppression System Changes.....

................9-2 l

TABLES j

i l

Table S-1 GA Sites to be Decommissioned

... S-2 i

l Table 3-1 Status of Labs in Building 2.......

.........................................3-9

+

Table 4-1 Typical List ofInstruments Used During D&D Projects....

........................ 4-14 Table 6-1 Acceptable Surface Contamination Levels.

............. 6-3 I

Table 6-2 Soil and Concrete / Asphalt Rubble Release Criteria..

................ 6-10

[

i LISTOFFIGURES(notpaged) l i

l Figure 3-1 Main Site and Sorrento Valley Site l

Figure 3-2 Sorrento Electronics Site Figure 3-3 Sorrento Electronics Manufacturing and Supporting laboratories and offices i

Figure 3-4 Building 9 " Hot Suite" Figure 3 5 Building 10 Figure 3-6 TRIGA Reactors Building 21 Figure 3-7 TRIGA Fuel Fabrication Facility Building 22 i

Figure 3-8 Hot Cell Figure 3-9 low-Level Filtration Facility Building 25 i

Figure 3-10 Nuclear Waste Processing Facility Building 41 Figure 3-11 Experimental Area (EA) Building 27 Figure 3-12 Experimental Area -l " Bunker" Building 27-1

[

j Figure 3-13 Relationship between Building 27-1,27,21,23 and 22 i

i Figure 3-14 Building 30/31 Complex Figure 3-15 Building 31 Room 103 NMA Storage Figure 3-16 Inertial Confinement Fusion Building 33 Figure 3-17 Building 33-1 Former HP LAB Figure 3-18 Fusion Site Building 34 j

Figure 3-19 Test Tower Building 35 Figure 3-20 Sorrento Valley A Building 37 l

Figure 3-21 Sorrento Valley B Building 39 Figure 3-22 Calibration Laboratory Building 42 i

Figure 3-23 Science Laboratory Building 2 l

Figure 3-24 Laboratory B Section Building 2 Figure 3-25 Laboratory C Section Building 2 Figure 3-26 Laboratory A Section Building 2 Figure 4-1 Decommissioning Organization i

IV

4<> CENERAL AFOANCS

9. FIREPROTECTION 9.1 Fire Safety Some activities may present potential fire hazards. Flame cutting, welding and grinding are examples of such activities which are likely to occur during Decommissioning Projects. To reduce this potential hazard, a fire safety program will be implemented during active decommissioning activities.

The fire safety program will consist of employee awareness, fire prevention, and fire protection.

The goal of the program is to reduce the likelihood of fire and to minimize the effect of a fire should one occur.

9.2 Fire Safety Responsibilities GA's General Emergency Plan provides for effective control of emergency situations throughout the GA complex. It describes the actions to be taken in the event of a fire. The facility Emergency Response and Recovery Director (ERRD) is responsible for control of emergency responses to fire, operation and maintenance of fire alarm and major fire suppression systems, and coordination of outside support. Emergency response personnel will receive training and instruction in fire prevention and fire protection 9.3 Fire Prevention Fire prevention on decommissioning projects will include utilization of good housekeeping practices, proper control and storage of flammable materials, use of cutting and burning permits, the presence of fire watches for selected activities (as needed), fire safety instruction to

)

emergency response personnel. Fire safety inspections including the inspection and maintenance of fire suppression devices will be conducted routinely.

When using an ignition source, e.g., cutting. >velding or grinding, a cutting or burning permit is required. The permit will be issued and controlled in accordance with the National Fire Protection Association (NFPA) Code NFPA-1, Appendix H. In cases where a fire watch is j

required, fire watchers will be trained in the fire causes and types, fire extinguisher selection and use, and specific fire watch duties and responsibilities.

q Fire suppression equipment will be inspected monthly and general fire safety walkdowns of facilities will be conducted periodically on a frequency commensurate with the fire potential in

{

the area. Areas requiring cutting and burning permits will be inspected before the start of work.

{

i 9.4 Fire Protection Personnel will sound the fire alarm by (1) word of mouth to co-workers in the area, (2) activating the fire alarm pullbox, and/or (3) telephoning x2000, the GA Emergency Telephone Number.

The Facility En ergency Response Team Personnel will provide initial response to any local fire alarm. That response is limited to evacuating the area and an attempt to confine or control an 9-1

1 CENB5fA&

T AFOANCS incipient firr 'mtil off-site fire departments arrive.

Each facility has portable Gre extinguishers available in the area. All buildings are near fire hydrants that are capable of supplying water to fire hoses. Wet pipe fire sprinkler systems are in Buildings 2 (Science Laboratories Building), Building 22 (TRIGA Fuel Fab Facility), Building 34 (Fusion Facility), Building 39 (SVB Pilot Plant), Building 41 (Nuclear Waste Processing Facility), Building 42 (Calibration Facility) and the Sorrento Electronics Facility in Mira Mesa.

The ERRD will take control of the scene and will determine if outside support is needed. If outside support is required, GA Security will notify the appropriate outside organization and provide assistance to them as necessary.

9.5 Fire Suppression System Changes During active decommissioning projects, recon 0guration and even removal of some of the fire suppression equipment may be needed. In that event, temporary fire suppression will be made available. These activities will be performed at the latest possible point in each facility.

Proposed system reconfiguration and/or removal of equipment will be reviewed and approved by GA Facilities Engineering and appropriate outside organizations will be advised as necessary prior to perfoquing the work. Whenever a portion of a fixed fire suppression system must be deactivated, replacement capability will comply with the requirements of the OSHA General Industry Standard for Portable Fire Extinguishers (29 CFR 1910.158), the OSHA Construction Industry Standard, Subpart E on Fire Protection (1926.150) and NFPA Standard No.10, Standard for Portable Fire Extinguishers.

9-2

CENEFFAL N

TABLE 3-1 STATUS OF LABS IN BUILDING 2 l

Number Lab Has the Lab GROUPNO.

COMMENTS No.

Been Released?

REI EASI:D IN 135 637 YES 8B 637 & 639 ARE A COMBINED LAB -

INCLUDES MEZZANINE 136 639 YES 8B 637 & 639 ARE A COMBINED LAB -

INCLUDES MEZZANINE 137 64I YES 1

641 & M3 ARE A COMBINED LAB -

INCLUDES MEZZANINE 138 64?

YES 1

641 & 643 ARE A COMBINED LAB -

INCLUDES MEZZANINE 139 645 NO 8B & 8C LAB 6AS RELEASED IN GROUP 8B, MDlANINE RELEASED IN GROUP 8C 140 647 YES 3 & 8C INCLUDES MEZZANINE - GROUP 3 &

8C 141 649 YES 3 & 8A 142 651 YES 3 & 8A 3-15