ML013230116

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General Atomics Amendment 72: Release of Building 2 Service Corridor Drain Line Trench (TAC L31524) and (2) Linac North Land Area (TAC L31510)
ML013230116
Person / Time
Site: 07000734
Issue date: 11/16/2001
From: Leach M
NRC/NMSS/FCSS/FCLB
To: Asmussen K
General Atomics
References
-RFPFR, TAC L31510, TAC L31524
Download: ML013230116 (15)
v • d • e


Text

November 16, 2001 Dr. Keith E. Asmussen, Director Licensing, Safety & Nuclear Compliance General Atomics P.O. Box 85608 San Diego, CA 92186-9784

SUBJECT:

GENERAL ATOMICS AMENDMENT 72: RELEASE OF BUILDING 2 SERVICE CORRIDOR DRAIN LINE TRENCH (TAC NO. L31524) AND (2) LINAC NORTH LAND AREA (TAC NO. L31510)

Dear Dr. Asmussen:

In accordance with your application dated April 4, 2001, (GA No. 696/CAL-3353) requesting that Building 2 Service Corridor Drain Line Trench be released for unrestricted use and deleted from SNM-696, and your application dated April 30, 2001, (GA No. CAL/696-3366) requesting that the LINAC North Land Area be released for unrestricted use and deleted from SNM-696, and pursuant to Part 70 to Title 10 of the Code of Federal Regulations, Materials License SNM-696 is hereby amended to delete these areas. Accordingly, Safety Condition S-1 has been revised to include the dates of April 4 (Building 2 Service Corridor Drain Line Trench), and April 30, 2001 (LINAC North Land Area).

All other conditions of this license shall remain the same.

Enclosed are copies of the revised Materials License SNM-696 and the Safety Evaluation Report, which includes the Environmental Review.

If you have any questions regarding this matter, please contact Mary T. Adams of my staff at (301) 415-7249 or by e-mail at MTA@NRC.GOV.

In accordance with 10 CFR 2.790 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/NRC/ADAMS/index.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Melvyn N. Leach, Chief Fuel Cycle Licensing Branch Division of Fuel Cycle Safety and Safeguards Office of Nuclear Material Safety and Safeguards Docket 70-734 License SNM-696 Amendment 72

Enclosures:

1. Materials License SNM-696
2. Safety Evaluation Report

November 16, 2001 Dr. Keith E. Asmussen, Director Licensing, Safety & Nuclear Compliance General Atomics P.O. Box 85608 San Diego, CA 92186-9784

SUBJECT:

GENERAL ATOMICS AMENDMENT 72: RELEASE OF BUILDING 2 SERVICE CORRIDOR DRAIN LINE TRENCH (TAC NO. L31524) AND (2) LINAC NORTH LAND AREA (TAC NO. L31510)

Dear Dr. Asmussen:

In accordance with your application dated April 4, 2001, (GA No. 696/CAL-3353) requesting that Building 2 Service Corridor Drain Line Trench be released for unrestricted use and deleted from SNM-696, and your application dated April 30, 2001, (GA No. CAL/696-3366) requesting that the LINAC North Land Area be released for unrestricted use and deleted from SNM-696, and pursuant to Part 70 to Title 10 of the Code of Federal Regulations, Materials License SNM-696 is hereby amended to delete these areas. Accordingly, Safety Condition S-1 has been revised to include the dates of April 4 (Building 2 Service Corridor Drain Line Trench), and April 30, 2001 (LINAC North Land Area).

All other conditions of this license shall remain the same.

Enclosed are copies of the revised Materials License SNM-696 and the Safety Evaluation Report, which includes the Environmental Review.

If you have any questions regarding this matter, please contact Mary T. Adams of my staff at (301) 415-7249 or by e-mail at MTA@NRC.GOV.

In accordance with 10 CFR 2.790 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/NRC/ADAMS/index.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Melvyn N. Leach, Chief Fuel Cycle Licensing Branch Division of Fuel Cycle Safety and Safeguards Office of Nuclear Material Safety and Safeguards Docket 70-734 License SNM-696 Amendment 72

Enclosures:

1. Materials License SNM-696
2. Safety Evaluation Report DISTRIBUTION:(Control Nos. R40S and R50S) [CLOSED] Accession No. ML013230116 Docket 70-734 BSpitzberg, RIV FCLB r/f SHO PMDA EFlack MRaddatz WBritz, RIV EGarcia, RIV PLohaus, OSTP C:\Program Files\Adobe\Acrobat 4.0\PDF Output\General Atomics License 72 ~.wpd OFC FCLB C FCLB 2C FCLB 4C OGC FCLB C FCLB C NAME M. Raddatz M.Adams P.Shea 0 LRoché MLeach DATE 11/09/2001 11/09/2001 11/13/2001 11/14 /2001 11/16/2001
  • See Previous Concurrence

NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter I, Parts 30, 31, 32, 33, 34, 35, 36, 39, 40, and 70, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use such material for the purpose(s) and at the place(s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.

Licensee

1. General Atomics 3. License Number SNM-696, Amendment 72
2. P.O. Box 85608 4. Expiration Date December 31, 1989 San Diego, California 92186-9784 5. Docket No.70-734 Reference No.
6. Byproduct Source, and/or 7. Chemical and/or Physical 8. Maximum amount that Licensee Special Nuclear Material Form May Possess at Any One Time Under This License A. Uranium A. Enriched up to 19.99% A. 200 kilograms U-235 U-235 B. Uranium B. Enriched 20 to 100% B. Less than 5000 gm*

U-235 C. U-233 C. Any C. Less than 2000 gm U-233*

D. Plutonium D. Encapsulated and/or D. Less than 2000 gm sealed sources total Pu*

E. Plutonium E. Bred but unseparated E. Less than 1000 gm total Pu*

F. Plutonium F. Plated calibration F. Less than 5 grams source total Pu*

G. Plutonium G. Solutions, precipitates G. Less than 5 grams solids and total Pu*

  • The sum total quantity of strategic special nuclear material possessed at any one time must be less than 5,000 grams computed by the formula:

Grams = grams U-235 in uranium enriched to 20% or more plus 2.5 (grams U-233 + grams plutonium)

NRC FORM 374A 2 U.S. NUCLEAR REGULATORY COMMISSION License Number SNM-696 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 72

9. Authorized place of use: The licensee's San Diego, California site as specified in the aforesaid application and supplements.
10. This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions.

These sections are part of the license, and the licensee is subject to compliance with all listed conditions in each section.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Date: By: Melvyn Leach, Chief Fuel Cycle Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS Washington, DC 20555 (Provided w/Amendment 31)

Enclosures:

1. License Condition for Leak Testing Sealed Plutonium Sources, dtd 4/93
2. License Condition for Plutonium Alpha Sources, dtd 4/93
3. Guidelines for Decontamination of Facilities..., dtd 4/93

NRC FORM 374A 3 U.S. NUCLEAR REGULATORY COMMISSION License Number SNM-696 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 72 SAFETY CONDITIONS S-1. Authorized use: For use in accordance with statements, representations, and conditions contained in Part II - "License Specifications" dated July 24, 1981, and supplements dated March 16 and December 24, 1982; February 4, November 14, and November 15, 1983; April 10, April 12, June 28, September 4, and September 7, 1984; December 5, 1985; May 23, September 25, and December 10, 1986; December 21, 1987; March 4, March 9 (2), March 22, April 26, August 22, September 8, and November 2, 1988; May 25 and November 17, 1989; June 27, 1990; April 30 and September 27, 1991; March 5, March 18, June 24, and September 10, 1992; January 20, 1995; the "SVA Decommissioning Plan" dated April 1, 1990 (submitted by letter dated March 30, 1990); August 22, 1990 (submitted by letter dated August 24, 1990); June 15, 1992; July 12 and August 23, 1994; Group 6 Laboratories unrestricted use request dated August 12, 1994; March 1, 1995; Group 7 Laboratories unrestricted use request dated December 5, 1995; Group 8B Laboratories unrestricted use request dated August 23, 1996; October 15, 1996; April 30, 1997; Group 9 Laboratories unrestricted use request dated July 17, 1997; Building 30 Laboratories unrestricted use release dated July 25, 1997; and January 29, 1998; Site Decommissioning Plan dated October 11 and December 5, 1996; April 18, 1997; January 15, 1998; Hot Cell Decommissioning Plan dated April 22, 1998, Group 10 Labs dated August 14, Building 27 Roof release dated August 25, and Building 30 - Phase II dated September 4, 1998, October 1, 1998, November 2, 1998 (Buildings 27 and 21), December 22, 1998 (SVB) January 12, February 8, (Buildings 37 and 39, Room 049B), March 23, 1999 (TFFF), March 9, May 17, (Radioactive Waste Storage Tanks), June 23, (Building 35-1, 36, 45, Test Tower Land), July 29, (Sorrento Valley Central Land Area), August 18, (Building 42), August 27, (Building 31-1), September 3, (Group 11 Building 2), and September 8, 1999 (Torrey Pines South); January 26 (Building 27 W, S, and SE Land Areas), January 27 (Building 30 - Phase III), March 10 (Hot Cell Site), March 30 (Sorrento Valley North Land Area), June 16 (Building 2 Laboratories Group 12), August 25 (Building 2 Laboratory Group 13),

October 10 (Building 27 East and Northeast Land Areas), and November 7, 2000 (Torrey Pines Northeast Land Area); January 10, (Area 1 of Sorrento Valley West Land Area), February 15 (Areas 2 and 3 of Sorrento Valley West Land Area), February 23 (TFF Utility Corridor); April 4 (Building 2 Service Corridor Drain Line Trench), and April 30, 2001 (LINAC North Land Area).

S-2. Records of all safety-related reports and analyses shall be retained as follows:

a. Copies of criticality and radiation safety analyses shall be retained for at least 2 years or for 6 months after a project is terminated, whichever is longer.
b. Copies of all other safety-related records (e.g., plant alterations and additions, abnormal occurrences associated with radioactivity releases, audits and inspections, instrument calibrations, ALARA findings, training and retraining, personnel exposures, routine radiation and environmental surveys) shall be retained for at least 2 years or longer if required by regulations.

S-3. Notwithstanding the statements in Section 5.4.2 in the License Specification Volume (Part II), if double batching is not credible, the maximum safe batch size shall be no more than 75 percent of the minimum critical mass independent of the degree of water moderation and reflection. However, when the Th/U atomic ratio is > 3.6 and the H/U < 20, the maximum safe batch size may be increased to 790 g contained U-235 independent of whether double batching is credible.

NRC FORM 374A 4 U.S. NUCLEAR REGULATORY COMMISSION License Number SNM-696 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 72 S-4. The Director QACD, upon recommendation of the appropriate manager within QACD, shall have authority to require immediate termination of activities and/or corrective action in any situation which, in their judgment, could lead to the unnecessary exposure of personnel to ionizing radiation, release of radioactive material, loss or damage of property, or non-compliance with the license or a regulation.

S-5. The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA Committee, shall meet at least annually to review (1) reports of audits and inspections performed since the last ALARA review and (2) employee exposures and effluent release data to determine (a) if there are any upward trends developing in personnel exposures for identifiable categories of workers, types of operations, or effluent releases, (b) if exposures and releases might be lowered in accordance with the ALARA concept, and (c) if equipment for effluent and exposure control is being properly used, maintained, and inspected.

The CRSC evaluation, recommendations, and corrective actions shall be documented and the report shall be sent to the appropriate operations managers and the Vice President, Finance and Administration.

S-6. Radiological Work Permits (RWPS) shall be issued for all unplanned or non-routine work with licensed material not covered by a WA. The RWP shall be signed by Health Physics management or a senior staff member before related work can commence. A senior staff member shall be a Health Physics Technician having a minimum of 5 years' experience in radiation safety. An evaluation of the safety effectiveness of the permit shall be made upon completion of the work.

S-7. Radiation safety training, appropriate to the employee's needs, shall be given to all new employees.

S-8. Radiation safety training and indoctrination shall be conducted by the Health Physics Manager or by a similarly qualified individual. The Health Physics Manager may delegate training in that portion of the course to an individual who is uniquely qualified to present it.

S-9. Continuous air sampling shall be conducted in any area where licensed material can become airborne.

S-10. The location of air samplers shall be checked annually and whenever any process or equipment changes are made to verify the representativeness of work area air sampling. In addition, the location of air samplers shall be checked at the commencement of operations in any area that has been shutdown for more than 6 months to verify the representativeness of air sampling.

S-11. The laboratories in which plutonium in a dispersible form may be used shall have exhaust ventilation systems separate from other building exhausts and shall provide dual HEPA filtering of the effluent air.

S-12. Sealed Plutonium sources shall be subject to the leak testing and actions specified in the attached "License Condition for Leak Testing Sealed Plutonium Sources," dated April 1993.

Plutonium alpha sources shall be subject to the actions specified in the attached "License Condition for Plutonium Alpha Sources," dated April 1993.

NRC FORM 374A 5 U.S. NUCLEAR REGULATORY COMMISSION License Number SNM-696 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 72 S-13. The licensee shall prepare and submit to the Chief, Licensing and International Safeguards Branch, Division of Fuel Cycle Safety and Safeguards, NMSS, U.S. Nuclear Regulatory Commission, Washington, DC 20555, a report whenever there is any new residential development within 1 mile around the site that constitutes a significant change in parameters that may be affected by the release of radioactive materials into the environment.

S-14. Deleted by Amendment 14 dated August 3, 1990 (originally numbered S-23 in 1990 - 1992 and renumbered to S-14 in Amendment 23 dated October 7, 1993). The information in License Condition S-23 was incorporated into License Condition S-9 by adding the date of May 25, 1989; License Condition S-9 later became S-1.

S-15. At the end of plant life, the licensee shall decontaminate the site and facilities, authorized as a place of use for special nuclear material, in accordance with the general decommissioning plan submitted by your letter dated July 25, 1986, and its supplement dated October 15, 1986, so that these facilities and grounds can be released for unrestricted use. The corporate commitment that funds will be made available for decommissioning the facility, provided by letter dated September 10, 1986, is hereby incorporated as a condition of the license.

S-16. Release of equipment, facilities, or packages to the unrestricted area or to uncontrolled areas onsite shall be in accordance with the attached "Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material," dated April 1993.

S-17. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and released for general use.

S-18. Notwithstanding the statement in Section 4.2.1.4, Part II of the license, the trip levels will be readjusted after each monthly test of the criticality alarm system if the alarm point fails to activate within approximately 5 seconds, more than once out of four trials.

S-19. Notwithstanding the statements in Section 4.2.1.4, Part II of the license, no material handling shall be allowed in any area in which the required criticality alarm system is inoperative.

S-20. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and released for general use.

S-21. Deleted by Amendment 31 dated September 1995. Fuel elements were shipped back to the licensee on October 3, 1988.

S-22. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and released for general use.

S-23. The licensee shall maintain and execute the response measures described in the Emergency Plan dated October 10, 1997, supplemented by letter dated November 6, 1997; and Revision Date 10/98; or as further revised by the licensee consistent with the provisions of 10 CFR 70.32(I).

NRC FORM 374A 6 U.S. NUCLEAR REGULATORY COMMISSION License Number SNM-696 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 72 S-24. The licensee shall develop individual survey plans for each facility or group of laboratories and provide NRC a 30-day notification, prior to GA initiating a final survey, to allow the NRC to schedule in-process inspections/surveys if required.

S-25. The licensee must submit for review and approval to NRC residual contamination and characterization data and planned decommissioning procedures for areas where:

1. Decommissioning procedures will be required that have not been used by the licensee in previous decommissioning activities or have not been identified in the Site Decommissioning Plan dated October 11, 1996, as amended December 5, 1996; April 18, 1997; and January 15, 1998;
2. Workers would be entering areas where surface contamination and radiation levels are significantly higher than routinely encountered during previous decommissioning operations;
3. Procedures could result in significantly greater airborne concentrations of radioactive materials than have been present in previous decommissioning operations; or
4. Procedures could result in significantly greater releases of radioactive material to the environment than those associated with previous decommissioning operations.

NRC FORM 374A 7 U.S. NUCLEAR REGULATORY COMMISSION License Number SNM-696 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 72 SAFEGUARDS CONDITIONS SG-1.0 Currently there are no Material Control and Accounting license conditions. The necessary information has been incorporated into an approved Fundamental Nuclear Material Control Plan dated March 1999.

SECTION 1.0 -- FACILITY ORGANIZATION Deleted by Amendment 58, August 1999.

SECTION 2.0 -- FACILITY OPERATION SG-2.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-2.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-2.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-2.4 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SECTION 3.0 -- MEASUREMENTS SG-3.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-3.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-3.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SECTION 4.0 -- MEASUREMENT CONTROL SG-4.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.4 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.5 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.6 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.7 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.8 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

NRC FORM 374A 8 U.S. NUCLEAR REGULATORY COMMISSION License Number SNM-696 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 72 SECTION 5.0 -- INVENTORY SG-5.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-5.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-5.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SECTION 6.0 -- RECORDS AND REPORTS SG-6.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SECTION 7.0 -- INTERNAL CONTROL SG-7.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SECTION 8.0 -- MANAGEMENT SG-8.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SECTION 9.0 -- PHYSICAL PROTECTION REQUIREMENTS FOR FORMULA QUANTITIES OF STRATEGIC SPECIAL NUCLEAR MATERIAL SG-9.1 The licensee shall follow the measures described in the physical protection plan entitled, General Atomics Fixed Site and Transportation Plan for the Protection of Special Nuclear Material of Low Strategic Significance dated July 2000, submitted by letter dated August 1, 2000 (GA No. 696-3261), and as it may be further revised in accordance with the provisions of 10 CFR 70.32(e)

SECTION -10.0 -- TEMPORARY OR ONE TIME CONDITIONS SG-10.1 Deleted by Amendment 31, dated July 1995.

SG-10.2 Deleted by Amendment 31, dated July 1995.

SG-10.3 Deleted by Amendment 31, dated July 1995.

DOCKET: 70-734 LICENSEE: General Atomics San Diego, CA

SUBJECT:

SAFETY EVALUATION REPORT: APPLICATIONS FOR RELEASE OF (BUILDING 2 SERVICE CORRIDOR DRAIN LINE TRENCH AND LINAC NORTH LAND AREA)

BACKGROUND In applications dated April 4, 2001, (GA No. 696/CAL-3353) and April 30, 2001, (GA No.

CAL/696-3366) General Atomics (GA) requested that their license be amended to remove Building 2 Service Corridor Drain Line Trench and LINAC North Land Area from their State and NRC licenses and those land areas be released for unrestricted use. GA provided two reports entitled, Final Radiological Survey Report for Service Corridor Drain Line Trench, dated March 2001, and "Final Radiological Survey Report for LINAC North Land Area, dated April 2001 in support of this request.

During the week of July 16-19, 2001, NRC performed an inspection of both the Building 2 Service Corridor Drain Line Trench and LINAC North Land Area. The inspector determined that the land areas meet the NRC-approved release criteria and can be released for unrestricted use. The results of the inspection are documented in NRC Inspection Report 70-734/01-03, dated 16 October, 2001.

DISCUSSION Building 2 Service Corridor Drain Line Trench The Building 2 Service Corridor Drain Line Trench is located in GAs Sorrento Valley Site, below Building 2 (see Figure 1 of the Final Radiological Survey Report for Service Corridor Drain Line Trench for exact location). Building 2 was used to house GAs Science Laboratories which were involved mainly in research and development. Under normal operations, liquid radioactive waste was not permitted to be discharged into the sanitary sewerage system. However, trace quantities could enter the sewerage system by the washing of glassware or other materials and supplies. As a result of this, and because the sewer drain lines were old, the sewerage system was assumed to be contaminated (and measurements confirmed that a few portions of the system were contaminated). Consequently, the drain lines were removed and disposed of as radioactive waste. GA provided a report titled, Final Radiological Survey Report for Service Corridor Drain Line Trench, dated March 2001, documenting the results of extensive and comprehensive radiological measurements completed in this area. GAs surveys demonstrate that the trench meets NRC-approved criteria for release to unrestricted use. NRC performed a confirmatory survey of Building 2 Service Corridor Drain Line Trench on July 16-19, 2001, and documented the results of this survey in Inspection Report 70-734/01-03, dated October 16, 2001. All confirmatory area survey measurements were below the respective release limits.

The NRC inspector also collected soil samples at various locations within the trench. These samples were split and analyzed independently by the licensee and by NRCs laboratory. The NRCs confirmatory measurements, using the criteria in NRC Inspection Procedure 84525, Quality Assurance and Confirmatory Measurements, found the results to be in agreement and thus verified the licensees determination that this area meets the criteria established in the Site Decommissioning Plan for unrestricted release.

LINAC North Land Area GA completed final radiological surveys and measurements demonstrating that the land area identified as the LINAC North Land Area meets the criteria for unrestricted use. GA documented the results of these surveys in a report titled, "Final Radiological Survey Report for LINAC North Land Area, dated April 2001. This report documents the results of extensive and comprehensive radiological measurements completed in this area. GAs surveys demonstrate that the area meets NRC-approved criteria for release to unrestricted use. NRC performed a confirmatory survey of the LINAC North Land Area on July 16-19, 2001, and documented the results of this survey in Inspection Report 70-734/01-03, dated October 16, 2001. All confirmatory area survey measurements were below the respective release limits. The NRC inspector also observed the licensees staff collect 10 soil samples at locations specified by the inspector. These 10 samples were split and analyzed independently by the licensee and by NRCs laboratory. The NRCs confirmatory measurements, using the criteria in NRC Inspection Procedure 84525, Quality Assurance and Confirmatory Measurements, found the results to be in agreement and thus verified the licensees determination that this area meets the criteria established in the Site Decommissioning Plan for unrestricted release.

ENVIRONMENTAL REVIEW Release of the Building 2 Service Corridor Drain Line Trench and LINAC North Land Area is consistent with the Site Decommissioning Plan approved by Amendment 45 to GAs license, issued April 20, 1998. The environmental impacts of release of the land areas were addressed in the Environmental Assessment (EA) issued to support Amendment 45. Associated with that EA were a Finding of No Significant Impact and a Notice of Opportunity to Request a Hearing, published in the Federal Register on April 27, 1998 (63 FR 20671). Accordingly, further environmental review is not needed for this action.

CONCLUSION The NRC staff has determined that removing Building 2 Service Corridor Drain Line Trench and LINAC North Land Area from GAs NRC license is in accordance with their approved Site Decommissioning Plan and meets regulatory requirements. Therefore, staff concludes that there is reasonable assurance that the proposed action will not adversely impact upon the health and safety of the public or the environment.

Approval of the amendment application is recommended.

NRC Region IV has no objection to this action.

PRINCIPAL CONTRIBUTORS:

Michael Raddatz Mary Adams

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