Safety & Safeguards Evaluation Rept Recommending That 931130 Exemption Request for Receipt of Fresh Fuel Assemblies Be GrantedML20058N462 |
Person / Time |
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Site: |
Westinghouse |
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Issue date: |
12/07/1993 |
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From: |
NRC |
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To: |
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Shared Package |
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ML20058N457 |
List: |
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References |
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NUDOCS 9312220029 |
Download: ML20058N462 (2) |
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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
[Table view] |
Text
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NUCLEAR REGULATORY COMMISSION
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W ASHINGTON. D.C. 20555-0001 l
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g ; 0 7 1993 DOCKET:
70-1151 LICENSEE: Westinghouse Electric Corporation Columbia, South Carolina
SUBJECT:
SAFETY AND SAFEGUARDS EVALUATION REPORT: APPLICATION REQUEST DATED NOVEMBER 30, 1993, RE EXEMPTION REQUEST FOR RECEIPT OF FRESH FUEL ASSEMBLIES Backaround for business considerations, the General Electric Company (GE) (Wilmington, North Carolina) desires to ship (from time to time) fresh fuel assemblies to Westinghouse for the sole purpose of interim storage pending final shipment to a GE reactor customer. The assemblies will be shipped and stored on flatbed trailers.
Each Model RA2/RA3 shipping package (containing two assemblies) will be tamper-safe sealed by GE.
Upon receipt, Westinghouse will visually l
inspect the shipments for package and tamper-safe seal integrity.
Unless there is evidence of degradation of shipping package integrity. Westinghouse will not remove or alter the configuration of the shipping containers on the fl at beds.
No more than 250 GE fuel assemblies will be present at any given time, Discussion Relative to these particular assemblies, Westinghouse has requested exemptions from the requirements of (1) conducting contamination surveys of the external surfaces of the shipping containers, (2) opening the shipping containers to perform an item count verification, and (3) conducting certain physical inventory activities on such assemblies if present at the time of an annual Westinghouse physical inventory.
Under normal special nuclear material receiving situations, Westinghouse is required to monitor the external surfaces of received packages for radioactive contamination, and to open the packages to perform an item count verification. To check for contamination on the external surfaces of the fuel assembly shipping packages, Westinghouse personnel would have to unfasten hold-down chains and physically move the shipping containers.
Since the special nuclear material in question is contained in encapsulated fuel rods, which are rigidly held together as assemblies, there is no real need to perform contamination surveys unless there is evidence of container damage.
Likewise, as long as the integrity of container seals are verified, there is no need to open the packages to verify that each contains two assemblies.
This will, of course, be done by the reactor f acility when the shipment is completed.
Also there is no need to physically verify the identity and special nuclear material content of each assembly at the time of a Westinghouse physical inventory.
Westinghouse will assure that no more than 250 such interim stored assemblies are present at any given time so as to avoid a need for criticality alarm i
9312220029 931209 PDR ADOCK 0700 1
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J monitors in the yard area where the flatbed trailers will he stored.
Although these fuel assemblies will be stored in a re ady to ship status (on 7
flatbed trailers), the physical and administrative cantrols governing the release of fuel assemblies for shipment are suffici'snt to preclude an i
unauthorized truck driver from transporting such ft el in an unauthorized i
manner.
Categorical Exclusion 1
1 Based on the information submitted by Westinghouse, the staff has determined l
l that the granting of the requested exemptions will not adversely affect the j
public health and safety or the environment; nor will it adversely affect the
(
common defense and security; and is otherwise in the public interest.
Accordingly, the staff has determined that the criteria in 10 CFR 51.22(c)(il) for categorically excluding an action from an environmental review has 'c.en 2
met. Therefore, neither an Environmental Assessment nor an Environmental Impact Statement is necessary for this proposed action.
Conclusion / Recommendation The staff concludes that the requested exemptions should have no adverse i
affect on the public health and safety or on the environment and that they i
will not reduce the effectiveness of the licensee's safety and safeguards l
1 programs. Hence, the staff recommends that the requested exemptions be granted.
Principal Contributor Donald P Joy
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