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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20206H4361999-05-0404 May 1999 Safeguards Evaluation Rept Supporting Amend 19 to License SNM-1107 ML20204D6241999-03-10010 March 1999 SER Accepting Application to Transfer & Amend W Matls Licenses,Qa Program Approval & Cocs ML20207J7771999-03-0404 March 1999 Safety Evaluation Supporting Amend 17 to License SNM-1107 ML20198E8471998-12-17017 December 1998 SER Accepting Amend 16 to License SNM-1107 ML20155C5161998-10-0707 October 1998 SER Accepting Amend 15 to License SNM-1107 for Westinghouse Electric Co ML20236Q5681998-07-10010 July 1998 Safety Evaluation Supporting Amend 14 to License SNM-1107 ML20248F5201998-06-0202 June 1998 Safety Evaluation Supporting Amend 13 to License SNM-1107 ML20247N7921998-05-0808 May 1998 SER Accepting Revised Site Emergency Plan for License SNM-1107 ML20217Q9551998-04-29029 April 1998 Safety Evaluation Accepting Amend 12 to License SNM-1107 ML20203C0831998-02-17017 February 1998 SER Accepting Extension of Schedule for Criticality Safety Evaluations Summary Scrubber Sys ML20203A4361998-02-0404 February 1998 SER Accepting Amend 10 to License SNM-1107 to Include Incident Reporting Criteria Approved by NRC ML20198Q2931997-12-30030 December 1997 Safety Evaluation Supporting Amend 9 to License SNM-1107 ML20203C3421997-12-0909 December 1997 SER Accepting Amend 8 to License SNM-1107 ML20199C6001997-10-21021 October 1997 SER Approving Amend 7 to License SNM-1107 ML20212A1571997-10-16016 October 1997 Safeguards Evaluation Rept Accepting W Application to Amend International Safeguards Condition, ML20212A0991997-10-14014 October 1997 Safeguards Evaluation Rept Accepting Licensees Fundamental Nuclear Matl Control Plan Revs ML20137N4571997-03-28028 March 1997 Safety Evaluation Supporting Licensee Fundamental Nuclear Control Plan Revs ML20137G5621997-03-27027 March 1997 Safety Evaluation Supporting Amend 4 to License SNM-1107 ML20058N4621993-12-0707 December 1993 Safety & Safeguards Evaluation Rept Recommending That 931130 Exemption Request for Receipt of Fresh Fuel Assemblies Be Granted ML20059K8671993-11-0909 November 1993 Safety Evaluation Supporting Amend 21 to License SNM-1107 ML20248E3231989-10-0202 October 1989 SER Re Revised Radiological Contingency Plan Dtd 890524. Concludes That Effectiveness of Subj Plan Not Reduced by Revs ML20151Z6311988-08-24024 August 1988 SER Supporting Application for Amend to License SNM-1107, Revising 880812 Radiological Contingency Plan ML20155G6301988-06-0808 June 1988 SER Recommending Amend to License SNM-1107 to Incorporate Revs to Radiological Contingency Plan,Per Westinghouse 880525 Application ML20237K9091987-08-25025 August 1987 SER Supporting 870723 Application & 870814 Suppl for Amend to License SNM-1107,authorizing Shipment of Dry Calcium Fluoride to Offsite Briquettor ML20237J9751987-08-14014 August 1987 SER Recommending Approval of Licensee 870619 & 26 Applications for Amend to License,Expanding Southeast & Southwest Plants ML20234B6371987-06-29029 June 1987 SER Recommending Approval of 870415 Application for Amend to License SNM-1107 to Include UF6 Handling Procedures ML20214J4321987-05-20020 May 1987 Safety Evaluation Supporting Westinghouse 870420,0512 & 13 Applications,Authorizing Release of Industrial Liquid Products (Spent Hydrofluoric Acid) for Reuse at Two Designated Facilities ML20213G2861987-05-12012 May 1987 Safety Evaluation Supporting Amend to License SNM-1107, Authorizing Release of Calcium Fluoride Containing Trace Quantities of Enriched U to Briquette Mfgs to Be Mixed W/ Other Steel Flux Forming Matls ML20209E6551987-04-27027 April 1987 SER Supporting 870401 Application for Amend to License SNM-1107,incorporating Leak Test Requirements for Plutonium Sources ML20207R1951987-03-0606 March 1987 SER Supporting 860922 Application for Amend to License SNM-1107,revising Columbia Site Emergency Plan ML20209D5941986-09-0303 September 1986 SER Supporting 860808 Application to Amend License SNM-1107 Re Positive Pressure Gloveboxes ML20198S9591986-05-28028 May 1986 SER Recommending Approval of 860423 & 0514 Applications for Amends to License SNM-1107 Re Low Level Matl Transfers & Rev to Site Emergency Plan,Respectively ML20136G7261985-11-18018 November 1985 SER of 851017 Application Re Const & Use of Facilities to Support Expanded Operations.Const Will Have No Adverse Effect on Environ ML20128M8561985-07-18018 July 1985 Safety Evaluation Supporting Amend to License SNM-1107 Re Addition of Uranyl Nitrate Storage Tanks 1999-05-04
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D1421999-09-30030 September 1999 Rev 0 to Cse License Annex Laboratories ML20217D1451999-09-30030 September 1999 Rev 1 to Cse License Annex Final Assembly ML20217D1311999-09-30030 September 1999 Rev 0 to Cse License Annex Ifba Process ML20217M2541999-09-21021 September 1999 Proposed Sequence for Full Scale Exercise - 990921 ML20211K4961999-08-31031 August 1999 Rev 0 to Cse License Annex,Storage of Uranium Bearing Matls ML20211K8191999-08-31031 August 1999 Rev 1 to Criticality Safety Evaluation License Annex Pelleting ML20209C2501999-06-30030 June 1999 Rev 0 to Cse License Annex,Solvent Extraction ML20209C2351999-06-15015 June 1999 Rev 0 to Cse License Annex,Urrs Waste Treatment Sys ML20209C2631999-06-15015 June 1999 Rev 0 to Cse License Annex,Scrap U Processing Sys ML20206S7071999-05-14014 May 1999 Rev 1 to Cse License Annex Hoods & Containments ML20206H4361999-05-0404 May 1999 Safeguards Evaluation Rept Supporting Amend 19 to License SNM-1107 ML20205H2541999-03-31031 March 1999 Rev 0 to Cse License Annex LLRW Processing Sys ML20204D6241999-03-10010 March 1999 SER Accepting Application to Transfer & Amend W Matls Licenses,Qa Program Approval & Cocs ML20207J7771999-03-0404 March 1999 Safety Evaluation Supporting Amend 17 to License SNM-1107 ML20207B0371999-02-28028 February 1999 Rev 0 to Criticality Safety Evaluation License Annex Hoods & Containments ML20198E8471998-12-17017 December 1998 SER Accepting Amend 16 to License SNM-1107 ML20154P4261998-10-16016 October 1998 Cse License Annex,Pelleting ML20155C5161998-10-0707 October 1998 SER Accepting Amend 15 to License SNM-1107 for Westinghouse Electric Co ML20151U0551998-08-31031 August 1998 Rev 0 to Cse License Annex,Cylinder Washing ML20153C7831998-08-12012 August 1998 Rev 1 to Criticality Safety Evaluation License Annex for Integral Fuel Burnable Absorber Fuel Rod Mfg ML20236W8701998-07-31031 July 1998 Criticality Safety Evaluation License Annex Integral Fuel Burnable Absorber Fuel Rod Mfg ML20236W8891998-07-31031 July 1998 Criticality Safety Evaluation License Annex Ammonium Diuranate Fuel Rod Mfg ML20236Q5681998-07-10010 July 1998 Safety Evaluation Supporting Amend 14 to License SNM-1107 ML20248F5201998-06-0202 June 1998 Safety Evaluation Supporting Amend 13 to License SNM-1107 ML20247N7921998-05-0808 May 1998 SER Accepting Revised Site Emergency Plan for License SNM-1107 ML20217Q7611998-05-0101 May 1998 SNM & Source Matl Physical Inventory Summary Rept, for Period Covering 970401-980405 ML20217Q9551998-04-29029 April 1998 Safety Evaluation Accepting Amend 12 to License SNM-1107 ML20203C0831998-02-17017 February 1998 SER Accepting Extension of Schedule for Criticality Safety Evaluations Summary Scrubber Sys ML20203A4361998-02-0404 February 1998 SER Accepting Amend 10 to License SNM-1107 to Include Incident Reporting Criteria Approved by NRC ML20198Q2931997-12-30030 December 1997 Safety Evaluation Supporting Amend 9 to License SNM-1107 ML20203C3421997-12-0909 December 1997 SER Accepting Amend 8 to License SNM-1107 ML20199C6001997-10-21021 October 1997 SER Approving Amend 7 to License SNM-1107 ML20212A1571997-10-16016 October 1997 Safeguards Evaluation Rept Accepting W Application to Amend International Safeguards Condition, ML20212A0991997-10-14014 October 1997 Safeguards Evaluation Rept Accepting Licensees Fundamental Nuclear Matl Control Plan Revs ML20137N4571997-03-28028 March 1997 Safety Evaluation Supporting Licensee Fundamental Nuclear Control Plan Revs ML20137G5621997-03-27027 March 1997 Safety Evaluation Supporting Amend 4 to License SNM-1107 ML20058N4621993-12-0707 December 1993 Safety & Safeguards Evaluation Rept Recommending That 931130 Exemption Request for Receipt of Fresh Fuel Assemblies Be Granted ML20059K8671993-11-0909 November 1993 Safety Evaluation Supporting Amend 21 to License SNM-1107 ML20248E3231989-10-0202 October 1989 SER Re Revised Radiological Contingency Plan Dtd 890524. Concludes That Effectiveness of Subj Plan Not Reduced by Revs ML20151Z6311988-08-24024 August 1988 SER Supporting Application for Amend to License SNM-1107, Revising 880812 Radiological Contingency Plan ML20155G6301988-06-0808 June 1988 SER Recommending Amend to License SNM-1107 to Incorporate Revs to Radiological Contingency Plan,Per Westinghouse 880525 Application ML20237K9091987-08-25025 August 1987 SER Supporting 870723 Application & 870814 Suppl for Amend to License SNM-1107,authorizing Shipment of Dry Calcium Fluoride to Offsite Briquettor ML20237J9751987-08-14014 August 1987 SER Recommending Approval of Licensee 870619 & 26 Applications for Amend to License,Expanding Southeast & Southwest Plants ML20234B6371987-06-29029 June 1987 SER Recommending Approval of 870415 Application for Amend to License SNM-1107 to Include UF6 Handling Procedures ML20214J4321987-05-20020 May 1987 Safety Evaluation Supporting Westinghouse 870420,0512 & 13 Applications,Authorizing Release of Industrial Liquid Products (Spent Hydrofluoric Acid) for Reuse at Two Designated Facilities ML20213G2861987-05-12012 May 1987 Safety Evaluation Supporting Amend to License SNM-1107, Authorizing Release of Calcium Fluoride Containing Trace Quantities of Enriched U to Briquette Mfgs to Be Mixed W/ Other Steel Flux Forming Matls ML20209E6551987-04-27027 April 1987 SER Supporting 870401 Application for Amend to License SNM-1107,incorporating Leak Test Requirements for Plutonium Sources ML20207R1951987-03-0606 March 1987 SER Supporting 860922 Application for Amend to License SNM-1107,revising Columbia Site Emergency Plan ML20209D5941986-09-0303 September 1986 SER Supporting 860808 Application to Amend License SNM-1107 Re Positive Pressure Gloveboxes ML20198S9591986-05-28028 May 1986 SER Recommending Approval of 860423 & 0514 Applications for Amends to License SNM-1107 Re Low Level Matl Transfers & Rev to Site Emergency Plan,Respectively 1999-09-30
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MAY 2 0.1987.
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FCUF:EYS -
- DOCKET NO:
70-1151 i.
LICENSEE:
Westinghouse Electric Corporation I
FACILITY:
Commercial Nuclear Fuel Division
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j-Columbia : South Carolina m
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SUBJECT:
SAFETY EVALUATION REPORT, APPLICATION DATED APRIL.20, 1987 i
i' AS~ REVISED MAY,13, 1987, AND SUPPLEMENT DATED MAY'12, 1987, RE APPROVAL-FOR THE REUSE'0F SPENT HYDROFLUORIC ACID UNDER CONTPOLLED CONDITIONS
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BACKGROUND 4.
l By application dated April 20, 1987, and; supplement dated May 12,~1987, Westinghouse Electric Corporation requested an amendment to License No.
i SNM-1107 to authorize the release of industrial liquid products, i.e...
l spent hydrofluoric acid (HF), for reuse at two designated facilities. By letter dated May 13, 1987, Westinghouse superseded the April'20.-application.'
The spent HF acid solution contains trace. quantities of uranium.3 The.two.
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facilities that use the HF acid solution-'are the. Brush-Wellman,-Incorporated, j
at Elmore, Ohio, and the Western Zirconium at Ogden, Utah.
DISCUSSION i
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The spent HF acid will be reused at the two facilities under controlled
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conditions. Prior to the transfer of this acid from Westinghouse, each 1
shipment will be representative 1y sampled and analyzed, and the following an:1 maximum. permissible concentrations shall not be exceeded, 1.
The uranium content in the HF acid shall not exceed. 3 ppm by weight. -
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2.
The uranium-enrichment in the HF acid shall not exceed S percent U-235 by weight.
l' 3.
The HF in the acid solution shall not exceed 50 percent by weight.
3 The estimated volume of. this aqueous HF acid is less than 50,000 gallons per.
year with a maximum uranium quantity of about'334 gm.
used in the following manner:'
'. The'HF acid will be L
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O Westinghouse Electric Corp. SER 2
% 2 0 1987 A.
Brush-Wellman Facility The HF' acid is used in the extraction process for beryllium. After extraction, the' reduction process converts the metal fluoride produced from the aqueous hydrogen fluoride to pebbles or metal. The trace quantities of uranium are expected to be co-reduced along with the beryllium in this process and ends up in the final metal product. The trace quantities of uranium in the final product will have no adverse effect. Only a small portion of the trace uranium follows the liquid waste stream which is then impounded in a tailings pond. The trace
' levels of uranium are diluced by magnesium fluoride (generated at about 2-3 million 1bs. per year) and aqueous fluoride-containing solutions in the tailings pond.
The aqueous portion of the pond is maintained at a pH greater than 8, and it is expected that the uranium reaching the pond will be precipitated. The maximum uranium content in the precipitated sludge is estimated to below 1 pCi/gm which is well below the 30 pCi/gm limit for unrestricted release as specified in NRC's Branch Technical Position for the disposal of uranium and thorium wastes.
There is no release of process liquids to surface water. During the production of beryllium pebbles, there are no processes in which volatile uranium compounds might be produced. No transfer of uranium to the in-plant atmosphere or to the surrounding areas as dust or gaseous species is expected to occur.
B.
Western Zirconium Facility Diluted HF acid is used to pickle zirconium products in aqueous baths where HF is diluted by about 9 to 1 with nitric acid. After the pickling step, the zirconium products are rinsed with deionized water. The trace uranium is expected to remain in the aqueous phase to the next step in the neutralization process where slaked lime is added to the liquid waste. Other Western Zirconium aqueous wastes are added to tnis stream prior to neutralization, resulting in a total dilution of approximately 1,000 to 1.
Neut;alized wastes are transferred to an evaporation lagoon for long-term storage. The calcium chloride sludge generated in the lagoon is about 32,000 lbs. per years. This does not provide much dilution as described in the Brush-Wellman facility. As a precaution, the licensee is committed to collect a composite sludge sample from the lagoon on a cuarterly basis, and the sludge will be analyzed for isotopic uranium with an action level of 15 pCi (total uranium) per gram of dry sludge.
If the total uraniun in the sludge sample exceeds 30 pC1/gm, the NRC Regional Office shall be notified within N days after completion of the analysis. This is to ensure tha no adverse effect would occur from radioactivity for the ultimate disposal of the sludge.
In addition, no lagoon lionid waste will be discharged to the surface water. The proposed use of HF aci Western Zirconium is not expected to result in a significant celease os anium in the air effluent.
i3AY 0 01987
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Westinghouse Electric Corp. SER 3
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CONCLUSION / RECOMMENDATION The reuse of the spent HF acid at the above-mentioned facilities is under controlled conditions. Trace quantities of uranium left in the waste stream are contained in the lagoon systems such that uranium will not enter into -
any food, beverage, or other commodity designed for ingestion by humans..
Additionally, the acid used in the processes is controlled to minimize the release of radioactivities to the atmosphere. Therefore, it is not expected that the licensee's proposed program has significant impact to the environment.
Approval of the proposed license amendment action is recommended.
The Region II Project Inspector has no objection to this action.
' Original Signed By; Edward Y. Shum Uranium Fuel Section.
Fuel Cycle Safety Branch Division of Fuel Cycle, Medical.
Academic, and Commercial Use Safety Original Signed By:
Approved by:
Leland C. Rouse, Chief Fuel Cycle Safety Branch
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