ML20207D761
| ML20207D761 | |
| Person / Time | |
|---|---|
| Site: | 07000824 |
| Issue date: | 07/26/1988 |
| From: | Soong A NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20207D725 | List: |
| References | |
| NUDOCS 8808150464 | |
| Download: ML20207D761 (3) | |
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,.P-JUL 26 m LICENSEE: Babcock & Wilcox Naval. Nuclear Fuel-Division NNFD Research Laboratory FACILITY: Lynchburg,' Virginia
SUBJECT:
SAFETY EVALUATION REPORT, APPLICATION DATED DECEMBER 8, 1987 RE: STORAGE OF RADI0 ACTIVE WASTE IN THE NEW TEMPORARY-STORAGE FACILITY d
I. Background
.By application dated December 8, 1987, as supplemented March 30, and June 20, 1988, the licensee requested authorization for the construction and use of a Temporary Storage Facility (TSF). The TSF construction will provide the licensee with additional storage space for the hot cell waste (high-level radiation) until a licensed disposal facility for high-level waste is identified.
At the present time, the licensee stores the waste onsite in the Annex to Building J. The Annex houses about 100 drums of waste and is full.
. In the December 8,1987 application, the licensee also requested removal of Building C as an authorized place of use for licensed material as it is no longer used for nuclear activity. The licensee has cleaned the Building to '
the levels that are below the NRC guidelines for an unrestricted area.
II. Discussion A. Construction The TSF is an inground array of eight vertical concrete cylinders arranged in two rows of four, with 24 inches of concrete shielding at the top of each cylinder. Each cylinder will be 6 feet in diameter i 13-feet tall, and rests on a common concrete pad. The TSF storage capacity is about 3,000 ft .3 Two separate drainage systems will be ,
installed for the TSF: one system is designed to collect any water :
which might exist inside the cylinders; the other to collect water ;
around the common concrete pad. The water samples will be analyzed
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regularly for the presence of radioactive material.
B. Radiological Safety :
The external radiation level at the top of the concrete shielding is ,
estimated by the licensee to be only a fraction of the regulatory quarterly limits for an occupational worker. Additionally, the TSF 4 is to be located in an isolated fenced area where no routine work will r be conducted. Therefore, the radiation exposure from the TSF should not be a problem to the NNFD-RL workers.
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i 8808150464 880804 PDR ADOCK 07000G24 C PDC
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Babcock & Wilcox 2 R26 M The licensee has proposed a monitoring program to detect any water that might exist in the cylinder before it could enter the groundwater.
The proposed frequency of sampling and analysis for the radioactive material and action level if radioactive material is found, is consistent with existing license requirements and is considered accept-dble for the protection of the environment.
Since only dry containerized waste will be stored, the potential for generating airborne effluents from the stored waste is unlikely.
C. Nuclear Criticality Safety The technical criteria for nuclear criticality safety is in Section 4.2. The licensee has deleted nuclear criticality safety criteria for Buildings A and C which required editorial changes to the remaining criteria. In addition, the dry waste criteria has been established as a separate subsection and expanded to cover storage in the new Temporary Storage Facility.
Dry (no liquid) waste is limited to a maximum 45 grams of SNM in 30 gallon or larger steel containers. Containers will be stored in the radioactive waste storage building or the Temporary Storage F6cility. Containers stored in the waste storage building will be scanned to control the inventory. The fissile content of other containers will be based on a mass balance difference.
Although a measurement of the fissile material in each container is preferred, the high radiation level prevents such a measurement. Mass control which will be based on inventory differences is acceptable because of the limited quantity of SNM in each container, the minimum size of each container, and the neutron poison effect of the steel container.
The licensee's proposed limits and controls provide reasonable assurance that nuclear criticality safety will be maintained.
D. Environmental Impacts In accordance with 10 CFR 51.12, an Environmental Assessment has been prepared for the requested license amendment. This Assessment supports a Finding of No Significant Impact which was published in the Federal Reaister on Friday, July 15, 1988.
E. General Coments Building C has been decontaminated by the licensee, and NRC's survey (conducted by ORAU team, final survey report is pending) confirms that radioactive contamination levels are below the NRC guidelines for a clean area. This proposed licensing action approves the removal of Building C as an authorized place of use for licensed material.
Babcock & Wilcox. 3 JUL 2 61988 F, Reoion II Courents The amendment application was discussed with J. Troup of Region II on January 25, 1988, and he has no objection.
III. Conclusion Based on the above discussion, I believe the amendment can be issued with.
out undue risk to the workers, public, or environment. Approval of the application is recorrended.
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An Liang oong Uranium Fuel Section Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS Approved by:
derry J. Swift, Section Ledder r
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DATE:7/d/88 7/M/88 7/h/88 7L>h8
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OFFICIAL RECORD COPY e
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