Safety Evaluation Supporting Amend 13 to License SNM-1107ML20248F520 |
Person / Time |
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Site: |
Westinghouse |
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Issue date: |
06/02/1998 |
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From: |
Adams M NRC |
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To: |
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Shared Package |
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ML20248F493 |
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References |
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NUDOCS 9806040308 |
Download: ML20248F520 (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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UNITED STATES g
Ig NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20555-0001
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70-1151 LICENSEE:
Westinghouse Electric Corporation Commercial Nuclear Fuel Division Columbia, South Carolina
SUBJECT:
SAFEGUARDS EVALUATION REPORT: SUBMITTAL DATED DECEMBER 18,1997, REVISIONS TO FUNDAMENTAL NUCLEAR MATERIAL CONTROL PLAN BACKGROUND By cover letter dated December 18,1997, Westinghouse submitted three revised Chapters 2.0, 4.0, and 6.0 of the facility's Fundamental Nuclear Material Control (FNMC) Plan. The revision of the Plan was made to address modifications of measurement standards limits and proposed practices for the laundry measurement system. The revision was requested pursuant to the provisions of 10 CFR 70.34 since the proposed changes were dealing with modified practices.
By letter dated May 29,1998, Westinghouse submitted additionalinformation regarding the criticality safety basis of the laundry.
DISCUSSION Westinghouse submitted various changes to its FNMC Plan, which affected the text of three chapters. All revisions are made by section with a new designated date and revision number.
These Plan changes are summarized as follows:
Control limits of working calibration standards are revised and updated for
. nondestructive astay (NDA) methods (gamma spectrometer and SAM-II), resulting from routine statistical analysis of pooled measurement data points throughout the material balance period.
l The use of a nominal factor in grams U-235 per unit mass for contaminated laundry will replace the current measurement system in which each individual container of laundry is measured by NDA. The laundry measurement system is a non-key or non-accountability measurement system, which is classified as not contributing to the standard error of inventory difference. The use of a nominal factor is justified since documented evaluation studies showed consistent results agreed within the l
uncertainties, current controls are in place to prevent unintentional commingling of nuclear material with contaminated laundry, and the nominal factor is determined and updated on an annual basis with representative laundry containers. In addition, the use of a nominal factor is consistent with the acceptance criteria discussed in Section 2.5 of NUREG-1065 (Rev. 2, December 1995), " Acceptable Standard Format and Content for the Fundamental Nuclear Material Control (FNMC) Plan Required for Low-Enriched Uranium Facilities."
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All of the proposed changes have been previously discussed with the NRC MC&A licensing reviewer, and upon review of these submitted changes, they were found to be acceptable.
CRITICALITY SAFETY REVIEW The Criticality Safety Basis for Laundry submitted on May 29,1998, stated that: (1) there are no
. pockets in the protective clothing, which could collect SNM, (2) the dirty clothing is stored away from substantial quantities of SNM, (3) the historical NDA assay results show 0.36 g U-235 per laundry bag, but, the new FNMC plan will use a factor of 1.0 g per laundry bag, (4) normally there are no more than fifty bags in storage, for a total of 50 g U-235 using the new factor, and (5) based on the existing CSE for storing drums, the laundry could be piled / stored in an unlimited fashion and still not present any adverse condition for criticality.
The use of the NDA factor of 1.0 g U-235 per bag assumes a worst case of 2.7 times the amount of SNM expected. Also, assuming six times the number of bags that is normally present, there would be 300 g U-235, which is below the safety limit. It is unlikely that this situation would arise.
Because the NDA factor will be reevaluated annually using data collected from both historical and future readings and, based on the new factor, the criticality safety limit will not be exceeded, the staff have concluded that an accidental criticality in the laundry area is not credible.
l ENVIRONMENTAL REVIEW The staff have determined that the proposed activities involve safeguards plans and material accountability, which are categorically excluded from the requirements to prepare a site-specific environmental assessment. Therefore, in accordance with 10 CFR 51.22(c)(12), neither an environmental assessment nor an environmental impact statement is warranted for this action.
CONCLUSION l
The staff concludes that an accidental criticality in the laundry area is not credible. The staff concludes that the licensee's FNMC Plan revision is acceptable, and that the revised Plan contains L
appropriate and necessary commitments to satisfy applicable MC&A regulations specified in 10 l
CFR 74.31. Therefore, Safeguards License Condition SG-1.1 has been revised to incorporate the
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revised Plan.
b The Operations Branch (FCOB) inspection staff has no objection to this proposed action.
EHINGlP.ALCDfiTBlBUIQBS Thomas N. Pham Susan Chotoo ^
q Harry Felsher b
b
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