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Category:LICENSE
MONTHYEARML20210U0001999-08-12012 August 1999 Amend 7 to License SNM-1067 for Abb Combustion Engineering Nuclear Power,Inc ML20198R0291997-10-29029 October 1997 Amend 5 to License SNM-1067 for Combustion Engineering,Inc ML20211H7861997-09-30030 September 1997 Amend 4 to License SNM-1067 for C-E,authorizing Use of 1,000 G U-235 Residue to Be Inlcuded for Disposal by DOE Under Fusrap & 150 G U-235 Residual U Oxides ML20133A9391996-12-24024 December 1996 Amend 3 to License SNM-1067 for Combustion Engineering,Inc, Extending Interim Storage Period of Packaged low-level Radwaste from 5 to 10 Yrs ML20132D8301996-12-17017 December 1996 Amend 2 to Matls License SNM-1067 for Combustion Engineering,Inc to Include Methods for Determination of Action Levels for Environ Monitoring Data ML20059C3781993-10-29029 October 1993 Amend 28 to License SNM-1067,decreasing Possession Limits & Removing Authorization to Conduct U-bearing Nuclear Fuel Mfg Operations at Facility ML20056D6891993-08-10010 August 1993 Amend 26 to License SNM-1067,authorizing Revs to Emergency Plan ML20126A6311992-12-17017 December 1992 Amend 25 to License SNM-1067,incorporating Changes to Radiological Contingency Plan ML20058M5671990-08-0909 August 1990 Amend 18 to License SNM-1067 for C-E,authorizing Mod of Ventilation Sys & Condition 9 ML20055J2861990-07-26026 July 1990 Amend 17 to License SNM-1067 for C-E,revising License in Entirety ML20248H8711989-10-0404 October 1989 Amend 15 to License SNM-1067,adding Conditions 30 & 31 to Require Production Manager & Emergency Director to Have Bachelors Degree in Science or Engineering ML20153F7851988-08-29029 August 1988 Amend 14 to License SNM-1067 for C-E,authorizing Use of Listed Matls,Including 500,000 Kg U Enriched to More than 5% W/O U-235 ML20151T0481988-08-11011 August 1988 Amend 13 to License SNM-1067,authorizing Use of Listed Matls Including Total 500,000 Kg U Enriched to Not More than 5.0 W/O U-235 ML20149F7621988-01-0404 January 1988 Amend 11 to License SNM-1067 for C-E,authorizing Use of Listed Licensed Matls,Including 20,500 Kg U-235,10,000 Kg U & 5 Sources Pu-238 1999-08-12
[Table view] Category:SNM & AMEND TO LICENSE (DKT 70S)
MONTHYEARML20210U0001999-08-12012 August 1999 Amend 7 to License SNM-1067 for Abb Combustion Engineering Nuclear Power,Inc ML20198R0291997-10-29029 October 1997 Amend 5 to License SNM-1067 for Combustion Engineering,Inc ML20211H7861997-09-30030 September 1997 Amend 4 to License SNM-1067 for C-E,authorizing Use of 1,000 G U-235 Residue to Be Inlcuded for Disposal by DOE Under Fusrap & 150 G U-235 Residual U Oxides ML20133A9391996-12-24024 December 1996 Amend 3 to License SNM-1067 for Combustion Engineering,Inc, Extending Interim Storage Period of Packaged low-level Radwaste from 5 to 10 Yrs ML20132D8301996-12-17017 December 1996 Amend 2 to Matls License SNM-1067 for Combustion Engineering,Inc to Include Methods for Determination of Action Levels for Environ Monitoring Data ML20059C3781993-10-29029 October 1993 Amend 28 to License SNM-1067,decreasing Possession Limits & Removing Authorization to Conduct U-bearing Nuclear Fuel Mfg Operations at Facility ML20056D6891993-08-10010 August 1993 Amend 26 to License SNM-1067,authorizing Revs to Emergency Plan ML20126A6311992-12-17017 December 1992 Amend 25 to License SNM-1067,incorporating Changes to Radiological Contingency Plan ML20058M5671990-08-0909 August 1990 Amend 18 to License SNM-1067 for C-E,authorizing Mod of Ventilation Sys & Condition 9 ML20055J2861990-07-26026 July 1990 Amend 17 to License SNM-1067 for C-E,revising License in Entirety ML20248H8711989-10-0404 October 1989 Amend 15 to License SNM-1067,adding Conditions 30 & 31 to Require Production Manager & Emergency Director to Have Bachelors Degree in Science or Engineering ML20153F7851988-08-29029 August 1988 Amend 14 to License SNM-1067 for C-E,authorizing Use of Listed Matls,Including 500,000 Kg U Enriched to More than 5% W/O U-235 ML20151T0481988-08-11011 August 1988 Amend 13 to License SNM-1067,authorizing Use of Listed Matls Including Total 500,000 Kg U Enriched to Not More than 5.0 W/O U-235 ML20149F7621988-01-0404 January 1988 Amend 11 to License SNM-1067 for C-E,authorizing Use of Listed Licensed Matls,Including 20,500 Kg U-235,10,000 Kg U & 5 Sources Pu-238 1999-08-12
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20210U0001999-08-12012 August 1999 Amend 7 to License SNM-1067 for Abb Combustion Engineering Nuclear Power,Inc ML20210F6941999-07-29029 July 1999 Amended Application for Amend to License SNM-1067,reflecting Change to New Organization ML20195D4001999-06-0303 June 1999 Application for Amend to License SNM-1067,transferring All Assets & Liabilities Related to NRC Licensed Activities of Combustion Engineering,Inc to Abb Combustion Engineering Nuclear Power,Inc ML20198R0291997-10-29029 October 1997 Amend 5 to License SNM-1067 for Combustion Engineering,Inc ML20211P7521997-10-17017 October 1997 Application for Amend to License SNM-1067,deleting Bldg 21 as Place of Authorized Possession for Matl Under License SNM-1067 ML20212A4091997-10-17017 October 1997 Supplemental Application for Amend to License SNM-1067, Deleting Bldg 21 as Place of Authorized Possession for Matl. Replacement Pages 1-3,6-3 & 7-1 of Application,Encl ML20211H7861997-09-30030 September 1997 Amend 4 to License SNM-1067 for C-E,authorizing Use of 1,000 G U-235 Residue to Be Inlcuded for Disposal by DOE Under Fusrap & 150 G U-235 Residual U Oxides ML20137Z2121997-04-16016 April 1997 Application for Amend to License SNM-1067,reflecting Proposed Reduction in Activities & Matl Possession Authorization & Transfer of Lab Activities to Windsor Site Broad Scope License ML20133A9391996-12-24024 December 1996 Amend 3 to License SNM-1067 for Combustion Engineering,Inc, Extending Interim Storage Period of Packaged low-level Radwaste from 5 to 10 Yrs ML20132D8301996-12-17017 December 1996 Amend 2 to Matls License SNM-1067 for Combustion Engineering,Inc to Include Methods for Determination of Action Levels for Environ Monitoring Data L-93-061, Revised Application for Amend to License SNM-1067,expanding Residue Enrichment Limit to Include SNM Below 20 W/O U-2351993-12-16016 December 1993 Revised Application for Amend to License SNM-1067,expanding Residue Enrichment Limit to Include SNM Below 20 W/O U-235 L-93-056, Addendum to 931021 Applicaton for Amend to License SNM-1067, Allowing Use of Fire Hoses in Bldg 171993-12-0606 December 1993 Addendum to 931021 Applicaton for Amend to License SNM-1067, Allowing Use of Fire Hoses in Bldg 17 ML20059C3781993-10-29029 October 1993 Amend 28 to License SNM-1067,decreasing Possession Limits & Removing Authorization to Conduct U-bearing Nuclear Fuel Mfg Operations at Facility L-93-042, Application for Amend to License SNM-1067,requesting That Bldgs 6,17 & 21 Be Additionally Exempt from Requirements of 10CFR70.24(a).Informs That It Is Licensee Intent to Deactivate Alarm Sys in Subj Bldgs Upon Approval of Amend1993-10-21021 October 1993 Application for Amend to License SNM-1067,requesting That Bldgs 6,17 & 21 Be Additionally Exempt from Requirements of 10CFR70.24(a).Informs That It Is Licensee Intent to Deactivate Alarm Sys in Subj Bldgs Upon Approval of Amend ML20057C9381993-09-23023 September 1993 Application for Amend to License SNM-1067,changing Total Special Matl Limit for Possession & Use on Lab Facilities Less than 350 Gms U-235 Effective 930930 ML20056D6891993-08-10010 August 1993 Amend 26 to License SNM-1067,authorizing Revs to Emergency Plan L-92-057, Application for Amend to License SNM-1067,reflecting Change Requests,Including Storage Location,Waste Form Which Can Be Stored & Length of Storage Period1992-12-23023 December 1992 Application for Amend to License SNM-1067,reflecting Change Requests,Including Storage Location,Waste Form Which Can Be Stored & Length of Storage Period ML20126A6311992-12-17017 December 1992 Amend 25 to License SNM-1067,incorporating Changes to Radiological Contingency Plan LD-90-081, Application for Amend to License SNM-1067,authorizing Use of Relocated Centrifuge within Controlled Access Area1990-10-25025 October 1990 Application for Amend to License SNM-1067,authorizing Use of Relocated Centrifuge within Controlled Access Area LD-90-071, Application for Amend to License SNM-1067,for Mfg of BWR Fuel Assemblies in Windsor,Ct1990-09-14014 September 1990 Application for Amend to License SNM-1067,for Mfg of BWR Fuel Assemblies in Windsor,Ct ML20058M5671990-08-0909 August 1990 Amend 18 to License SNM-1067 for C-E,authorizing Mod of Ventilation Sys & Condition 9 ML20055J2861990-07-26026 July 1990 Amend 17 to License SNM-1067 for C-E,revising License in Entirety LD-90-045, Application for Amend to License SNM-33,authorizing Approval to Make Necessary Ventilation Sys Mod1990-06-22022 June 1990 Application for Amend to License SNM-33,authorizing Approval to Make Necessary Ventilation Sys Mod ML20248H8711989-10-0404 October 1989 Amend 15 to License SNM-1067,adding Conditions 30 & 31 to Require Production Manager & Emergency Director to Have Bachelors Degree in Science or Engineering LD-89-104, Application for Amend to License SNM-1067,revising Windsor Nuclear Fuel Mfg Facility Organization.Tabulation of Affected Pages & Respective Rev Numbers Encl1989-09-15015 September 1989 Application for Amend to License SNM-1067,revising Windsor Nuclear Fuel Mfg Facility Organization.Tabulation of Affected Pages & Respective Rev Numbers Encl LD-89-081, Application for Amend to License SNM-1067,providing Revised Pages to License Amend,Per NRC 890327 Request1989-07-27027 July 1989 Application for Amend to License SNM-1067,providing Revised Pages to License Amend,Per NRC 890327 Request ML20246B5461989-06-30030 June 1989 Revised Windsor Fuel Fabrication Facility Request for Amend to License SNM-1067,changing Facility Organization LD-89-069, Application for Amend to License SNM-1067,incorporating Rev 0 to Emergency Plan Into License.Once Plan Fully Implemented,Date for Conduct of Emergency Drill Will Be Provided to Nrc.Fee Paid1989-06-30030 June 1989 Application for Amend to License SNM-1067,incorporating Rev 0 to Emergency Plan Into License.Once Plan Fully Implemented,Date for Conduct of Emergency Drill Will Be Provided to Nrc.Fee Paid LD-89-026, Revised Application for Amend to License SNM-1067 Revising Util Organization,Per NRC 890215 Comments.Proposes Formation of Facility Review Group,To Replace in Part, Functions of Nuclear Safety Committee1989-03-0707 March 1989 Revised Application for Amend to License SNM-1067 Revising Util Organization,Per NRC 890215 Comments.Proposes Formation of Facility Review Group,To Replace in Part, Functions of Nuclear Safety Committee LD-89-018, Application for Amend to License SNM-1067,eliminating Requirement for Storage of Shipping Container Arrays Per Specific Transport Index in Shipping Container Storage Area within Bldg 17/21 Security Fence.Fee Paid1989-02-13013 February 1989 Application for Amend to License SNM-1067,eliminating Requirement for Storage of Shipping Container Arrays Per Specific Transport Index in Shipping Container Storage Area within Bldg 17/21 Security Fence.Fee Paid ML20153F7851988-08-29029 August 1988 Amend 14 to License SNM-1067 for C-E,authorizing Use of Listed Matls,Including 500,000 Kg U Enriched to More than 5% W/O U-235 LD-88-084, Amended Application for Amend to License SNM-1067,to Facilitate Orderly Change for Processing U-2351988-08-23023 August 1988 Amended Application for Amend to License SNM-1067,to Facilitate Orderly Change for Processing U-235 ML20151T0481988-08-11011 August 1988 Amend 13 to License SNM-1067,authorizing Use of Listed Matls Including Total 500,000 Kg U Enriched to Not More than 5.0 W/O U-235 LD-88-053, Application for Amend to License SNM-1067,clarifying Enhanced Mgt Team Via Organizational Changes.Fee Paid1988-07-13013 July 1988 Application for Amend to License SNM-1067,clarifying Enhanced Mgt Team Via Organizational Changes.Fee Paid ML20154E4771988-04-30030 April 1988 Application for Amend to License SNM-1067,increasing Weight Percent of Enriched U That Can Be Processed from Less than or Equal to 4.1% to Less than or Equal to 5.0% ML20147C1081988-01-20020 January 1988 Application for Amend to License SNM-1067,authorizing Increase in Weight Percent of Enriched U from Less than 4.1% to Less than 5% U-235.Fee Paid ML20149J6981988-01-0707 January 1988 Application for Amend to License SNM-1067,extending License Expiration Date to 880531.Extension Necessary Due to Restructuring of Radiation Protection Program.Fee Paid ML20149F7621988-01-0404 January 1988 Amend 11 to License SNM-1067 for C-E,authorizing Use of Listed Licensed Matls,Including 20,500 Kg U-235,10,000 Kg U & 5 Sources Pu-238 ML20236H8831987-10-0909 October 1987 Application for Amend to License SNM-1067,eliminating Requirements for Labeling Vessels/Containers W/Radioactive Matl Labels & Revising Number & Location of Criticality Detectors in Bldg 5 & 17 & Calibr of Detectors.Fee Paid ML20205F4601987-03-18018 March 1987 Application for Amend to License SNM-1067,incorporating Changes Discussed at 870219 Meeting W/R Klotz & N Ketzlach. Changes Include Mist Density Calculation for Single Sprinkler ML20205F1581987-03-18018 March 1987 Application for Amend to License SNM-1067,incorporating Changes Discussed During 870310 Telcon ML20204F9991987-03-12012 March 1987 Application for Amend to License SNM-1067,revising Fundamental Nuclear Matls Control Plan Per Agreements Reached During Anticipated Meetings W/R Jackson & D Joy. Final Revised Plan Will Be Submitted on or Before 870615 ML20212D9531987-02-18018 February 1987 Revised Application for Amend to License SNM-1067,providing Certain Addl Changes Agreed Upon During 870128 Meeting W/ Nrc.Fee Paid ML20204F0141987-01-20020 January 1987 Application for Amend to License SNM-1067,changing Info Dealing W/Storage of Loaded Fuel Bundle Shipping Containers (Types 927A & 927C),per 870107 Telcon & Revising Figure 4.2-1.Fee Paid ML20207P2301986-12-17017 December 1986 Application for Amend to License SNM-1067,reflecting Input from Factory Mutual Research Corp Re Mist Density Calculations & Effect on Keff.Fee Sent Under Separate Cover Per 10CFR170.31 1999-08-12
[Table view] |
Text
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q 00 s0) U.S. NUCLE AQ QEGULATo3Y COMMISSION ##0E 1 0' ' AI* E S -n g
, , MATERIALS LICENSE
<; Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Ac g
g Code ( f Federal Regulations, Chapter I. Parts 30,31,3L 33,34,35,39,40 and 70, and in reliance on statements and representations heretofore ;p 3 made by the licensee. a license is hereby issued authonting the beenwe to reccise, acquire, possess, and transfer byproduct, source, and special 'l l nuclear material designated below; to uw such material for the purpose (s) and at the placets) designated below; to deliser or transfer such material )I
- to persorn authorized to receise it in accordance with the regulatiom of the applicable Part(s). This liceme shall be deemed to contain the conditions ;I l specined in Section 1M3 of the Atomic Energy Act of l954, as amended, and is subject to all applicable rules, regulations and orders of the Nuclea l Regulatory Commission now or hereafter in effect and to any conditions specified below, l
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b Combustion Engineering, Inc.
C-2 Power Systems
- 3. Ucense number SNM-1067 Amendment No. 25
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, . 1000 Prospect Hill Road 1 Windsor, Connecticut 06095 4. Expiration date May 31, 1988 l
- 5. Docket or l Reference No 70-1100 jl,
- 6. Byproduct, source, and/or 7. Chemical and/or physical 8, Maximum amount that hcensee
_lX i special nuclear material form may possess at any one time jf l under this license
!n A. Uranium enriched to A. Oxide powder, pellets, A. 500,000 kilograms I I
not more than rods, and finished fuel total uranium 8 j
l 5.0 w/o U-235 assemblies I
i B. Uranium enriched to B. Any B. 4,800 grams contained lt
- less than U-235 !g l 20 w/o U-235 )n W 3
C. Natural and/or depleted uranium C. Any C. 10,000 kilograms total uraniura j j
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-4 D. Pu-238 D. Encapsulated D. 5 sources, each ll
! neutron sources containing less I
! than 2.0 grams Pu-238 %
E. Pu E. Any E. 160 micrograms j i
as analytical j samples e i
F. Uranium enriched in F. Contained in F. 20 sources, each lI j
the U-235 isotope encapsulated U38 sources 0 containing less than 1.7 grams j:,
-U-235 y
- lls G. Uranium enriched to G. Residues G. 1,000 g U-235 p j or greater than II 20 w/o U-235 )
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i, 70-1100 :p lF DEC 17 992. ;p
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- 9. Authorized use:
4 For use in accordance with statements, repre a ntations, and conditions contained in Part I and Chapter 8', Part !!, of the lh.mee's revised . )
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- fh} application dated May 14, 1982, and supplements dated March 23, Septe wr 16,' and )
October 4,1982; September 16, and October 5,1983; April 5, June 19, Sept nber 12, ,P d and November 30, 1984; May 16, July 25, September 23, and December 16, 1985; ?
k5 March 18, May 19, June 20 and November 6,1986; January 20, February 18, March 16, July 24, and December 15, 1987; January 7, August 16, and August 19, 1988; June 23, September 15, December 11, December 13, and December 20, 1989; June 1, June 22, j
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September 14, October 17, and October 25, 1990; February 13, and March 5, 1991; and l April 8, May 27, June 24, June,26, and July 20, 1992. 4)p j!,
% 10. Authorized place of use: The licensee's existing facilities approximately 5 miles q northwest of Windsor, Connecticut, as described in the referenced application.
!l11. Reserved. $s i
l 1
- 12. Reserved, j
l 13. Reserved.
% 14. Notwithstanding the statements mde in Section.3.2.5 of the revised application dated ll 9! May 14, 1982, by June 30, 1983, the licensee shall evaluate the individual's internal P
$ exposure to airborne radioactivity based on breathing zone sampling data which are l f@ obtained by continuous sampling for the period of his presence in the w the unciad radioactive material is handled.1 If permanently mounted air sampling c equipment is used to determine the breathing zone. air concentration levels, the- $
1)
A licensee shall evaluate its representativeness at least once every 12 months and )
$ whenever any licensed process or equipment change is made, j If V 15. When the monitoring of airborne concentration of radioactivity is required as j specified in 10 CFR 20.103, the air concentration-of radioactivity in the Nuclear 4
Laboratories shall be analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />'after each operating shift. )>
$16.Thelicenseeshallconductaleaktestonallencapsulatedsourcesin-accordancewithl>
{4 the attached Annex A, " License Condition for leak Testing Sealed Source Which Contains Alpha Emitter."
j k g6 if 17. Notwithstanding the statements made in Section 3.2.8.2 and Section 3.2.8.3 of page %
P I.3-14 and page I.3-15, respectively, of the application, revision 2, dated April 6,_ }
K 1982, release of equipment and material from the plant to offsite for unrestricted I
% use or from contaminated to clean areas onsite shall be in accordance with the attached Annex P dated July 1982.
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- 18. The instruments measuring the liquid-waste level in each dilution tank prior to 1 A(8 discharge to the Farmington River shall be calibrated at least annually. )
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Amendment No. 25 l .
. MATERIALS LICENSE g , ,,
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4 DEC 1719g2 h5 I
't (4 19. Notwithstanding revision 2 dated Aprilthe 6, statements 1982, all wastes in Section 5.1.3, page contaminated with 1.5-2 of thematerial radioactive application, to t
( levels in excess of limits specif %d in Annex B shall be packaged in accordance with lI k the requirements of 10 CFR 71 and disposed of at a licensed radioactive burial F ground. j f 20. The licensee shall take the following action on plant gaseous effluent releases: )
f 4 (a) If the radioactivity in the plant gaseous-effluents exceeds 18 #Ci gross alpha activity in total uranium per calendar quarter; the licensee shall, .within 30 f'it i days, prepare and submit _to the Commission a report'which identifies the cause 1 A for exceeding the limit and the corrective actions to-be taken by the licensee to h reduce release rates. If the parameters important tocaidose assessment change, a y(
@ report shall be submitted within 30 days which describes the changes in I
/ parameters and includes an estimate of the resultant change in dose commitment. t 4 The report or petition should be submitted to the Director, Office of Nuclear 'l p
i Material Safety'and Safeguards, with a copy to the Administrator of Region 1.
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(b) In the event that the calculated dose to any member of the public in any f
A consecutive 12-month period is about to> exceed:the limits specified in 40 CFR 190.10, the licensee shall take-immediate steps to reduce emissions so as to
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>j comply with 40-CFR 190.10. As provided in--40 CFR 190.11, the licensee may ;I j i pj
- petition the Nuclear Regulatory Commission'for a variance from the requirements of 40 CFR 190.10. If a petition-for aLvariance is anticipated,.the licensee (
h q shall submit the' request at least 90 days prior;to exceeding the limits specified 5 c in 40 CFR 190.10. 4 4 4 t=
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}l 21.Contingency The licensee shall maintain Plan (Emergency Plan) submitted and to theexecute Commissionthe' response on November 13, 1990measu
[
j (containing pages dated June 30, 1989, and November 13,-1990),- September 3, 1992, and p 4 November 23, 1992. The licensee.shall maintain implementing procedures for the p
/ Emergency Plan as necessary to implement the = Plan'. The licensee shall make no changei t
-% in the Plan that would decrease the response effectiveness of the Plan without prior 1 i Commission approval as evidenced by a license amendment. The licensee shall maintain
! records of changes that are made to the Plan without prior app l l years from the date of the change and shall furnish the Chief, Fuel Cycle Safety !g i
i Branch, Division of Industrial and Medical Nuclear Safety, NMSS, U.S. Nuclear g.
Regulatory Commission, Washington, DC 20555, a report containing a description of f j each change within 6 months after the change is made, j
On or before June 30, 1991, the licensee shall expand its Emergency Plan to include l the criteria and methodology for the emergency response for all affected employees at p L the Windsor site, g t
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'4' SUPPLEMENT AnY SHEET
70-1100 ;,,
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DEC 17 1992 i
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'l 22. At the end of plant life, the licensee shall decontaminate the facility and site in accordance with the general decommissioning plan submitted with the renewal application dated May 14, 1982, so that these facilities and grounds can be released
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i for unrestricted use. The financial commitment assuring funds for decommissioning, @'p, i submitted by letter dated March 23, 1982, is hereby incorporated as a condition of
}l the license. )?
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.! 23. Upon discovery of residues at the licensed facility containing uranium enriched to g
W more than 19.99 wt percer.t U-235, action shall be initiated within 30 days to remove the material from the premises in a timely manner.
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>4 24. Notwithstanding the statement made in Section 1.6 of the application dated November 30, 1904, the licensee shall separate the residues in batches no larger than 350 g
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i I! contained U-235 and shall maintain a minimum separation of 12 feet between batches.
! 4
! 25. Reserved. 4
(.1 4 4 4 26. Hydrogenous materials shall not be stored on pellet storage tables or pellet storage )
racks where nuclear criticality safety is based on 4-inch safe slab limits.
{l {4 a'ql 27. Hydrogenous materials shall not be stored between trays of fuel rods on storage racks W k
or shelves where nuclear criticality is based on 6-inch safe slab limits. )
j
- A
{28. Reserved. : .
i
- 29. Reserved. @
- 30. Reserved.
l+ !q>i l$ 31. The Emergency Director shall have, as a minimum, a bachelor's degree in science or f _
j engineering, followed by 5 years experience in management positions in the nuclear i j industry. l 7 !F
- 32. The individual identified in the June 24, and July 20, 1992, letters, who will $
conduct the audits of the radiological p otection program, is hereby exempted
- from the degree requirements contained in Part I, Section 2.2.4, of the license %j
- application. j
,; !b FOR THE NUCLEAR REGULATORY COMMISSION g Original Signed By k DEC 171992 By John W. N. Hickey
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(4 Date @
li Division of Industrial and M
_ k n,[uFg Medical Nuclear Safety Washington, DC 20555 lg l
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