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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20112E8911996-05-24024 May 1996 FOIA Request to Inspect & Copy Original OL Issued by Aec/Nrc for Util & EPP Issued as App B to Plant OL SNRC-2192, Forwards Both Copies,Signed by Util President Cv Giacomazzo, of Amend 7 to Indemnity Agreement B-87.Util Returning Copies Because Effective Date Left Blank1995-05-15015 May 1995 Forwards Both Copies,Signed by Util President Cv Giacomazzo, of Amend 7 to Indemnity Agreement B-87.Util Returning Copies Because Effective Date Left Blank ML20082B9131995-03-13013 March 1995 Submits Corrected Page for Insertion Into Final Rept Re Confirmatory Survey of RB & Phase 4 Systems at Plant ML20081A9321995-03-0707 March 1995 Forwards Final Rept Orise 95/B-81, Confirmatory Survey of Reactor Bldg & Phase 4 Sys Shoreham Nuclear Power Station Brookhaven,Ny ML20081A6531995-03-0707 March 1995 Forwards Final Rept Orise 95/B-80, Confirmatory Survey of Radwaste Bldg,Suppression Pool,Phase 2 Phase 3 Sys,Shoreham Nuclear Power Station,Brookhaven,Ny ML20081A6841995-02-21021 February 1995 Forwards Final Rept Confirmatory Survey of Radwaste Bldg, Suppression Pool,Phase 2 & Phase 3 Sys,Shoreham Nuclear Power Station,Brookhaven,Ny ML20081B5801995-02-21021 February 1995 Forwards Final Rept Confirmatory Survey of Reactor Bldg & Phase 4 Sys Shoreham Nuclear Power Station Brookhaven,Ny ML20081A7001995-01-30030 January 1995 Forwards Rev 1 to Draft Rept Confirmatory Survey of Radwaste Bldg,Suppression Pool,Phase 2 & Phase 3 Sys, Shoreham Nuclear Power Station,Brookhaven,Ny ML20081A7111995-01-30030 January 1995 Forwards Rev 1 to Draft Rept Confirmatory Survey of Reactor Bldg & Phase 4 Sys,Shoreham Nuclear Power Station, Brookhaven,Ny SNRC-2189, Forwards Shoreham Nuclear Power Station Radiological Environ Monitoring Program,Annual Radiological Environ Operating Rept, Jan-June 19941995-01-20020 January 1995 Forwards Shoreham Nuclear Power Station Radiological Environ Monitoring Program,Annual Radiological Environ Operating Rept, Jan-June 1994 SNRC-2188, Responds to NRC Request for Addl Info Re Certain Elevated Levels Found During Phase 4 Confirmatory Survey1995-01-20020 January 1995 Responds to NRC Request for Addl Info Re Certain Elevated Levels Found During Phase 4 Confirmatory Survey SNRC-2187, Forwards Snps Annual Man-Rem Rept, Including Individuals for Whom Personnel Monitoring Provided During CY94,per 10CFR20.407(a) & (B).Rept Also Includes Individuals Identified in 10CFR20.202(a),who Require Monioring1995-01-11011 January 1995 Forwards Snps Annual Man-Rem Rept, Including Individuals for Whom Personnel Monitoring Provided During CY94,per 10CFR20.407(a) & (B).Rept Also Includes Individuals Identified in 10CFR20.202(a),who Require Monioring SNRC-2182, Forwards Final Annual Radioactive Effluent Release Rept for Cy 1994, Including Last Revised Copies of ODCM & Pcp.Rept Prepared for Closeout Purposes as Part of Completion of Plant Decommissioning1994-11-0101 November 1994 Forwards Final Annual Radioactive Effluent Release Rept for Cy 1994, Including Last Revised Copies of ODCM & Pcp.Rept Prepared for Closeout Purposes as Part of Completion of Plant Decommissioning ML20077L3331994-10-25025 October 1994 Forwards Revised Proposed Confirmatory Survey Plan for Reactor Bldg Shoreham Nuclear Power Station Brookhaven,Ny ML20076K3881994-10-20020 October 1994 Forwards Proposed Confirmatory Survey Plan for Reactor Bldg, Shoreham Nuclear Power Station,Brookhaven,Ny,For Review & Comment ML20077M8351994-10-20020 October 1994 Forwards Draft Rept, Confirmatory Survey of Radwaste Bldg, Suppression Pool & Phase 2 Systems,Shoreham Nuclear Power Station,Brookhaven,Ny SNRC-2184, Forwards Shoreham Decommissioning Project Termination Survey Final Rept Phase 4. Portions Withheld1994-10-12012 October 1994 Forwards Shoreham Decommissioning Project Termination Survey Final Rept Phase 4. Portions Withheld SNRC-2185, Summarizes Results from Revised Exposure Pathway Analysis Using Corrected Dcf for External Exposure for Cs-137.Rev 1 to Analysis of Bulk Matl Reconcentration Potential & Possible Exposure Pathways Encl1994-10-0404 October 1994 Summarizes Results from Revised Exposure Pathway Analysis Using Corrected Dcf for External Exposure for Cs-137.Rev 1 to Analysis of Bulk Matl Reconcentration Potential & Possible Exposure Pathways Encl ML20076F9251994-09-26026 September 1994 Forwards Final Rept Orise 94/I-80, Confirmatory Survey of Turbine Bldg,Site Grounds & Site Exteriors Shoreham Nuclear Power Station Brookhaven,Ny SNRC-2183, Forwards Amend 6 to Indemnity Agreement B-871994-09-23023 September 1994 Forwards Amend 6 to Indemnity Agreement B-87 SNRC-2181, Notifies of Equipment Changes to Shoreham Facility Which Have Occurred Subsequent to Rept on Phase I Final Survey Status,Provided in Util .Equipment Changes Described in Encl Table 11994-09-14014 September 1994 Notifies of Equipment Changes to Shoreham Facility Which Have Occurred Subsequent to Rept on Phase I Final Survey Status,Provided in Util .Equipment Changes Described in Encl Table 1 SNRC-2180, Forwards 940829 Memo Entitled, Technical Evaluation of Dusting from Concrete Blocks, Addressing Issue Discussed in Insp Rept 50-332/94-021994-09-0101 September 1994 Forwards 940829 Memo Entitled, Technical Evaluation of Dusting from Concrete Blocks, Addressing Issue Discussed in Insp Rept 50-332/94-02 SNRC-2179, Proposes That Release Criterion for Soil Be Applied to Certain Other Bulk Matls Which Will Remain at Plant Upon Completion of Decommissioning.Analysis of Bulk Matl Reconcentration Potential & Possible Exposure Pathways Encl1994-09-0101 September 1994 Proposes That Release Criterion for Soil Be Applied to Certain Other Bulk Matls Which Will Remain at Plant Upon Completion of Decommissioning.Analysis of Bulk Matl Reconcentration Potential & Possible Exposure Pathways Encl SNRC-2178, Forwards Proprietary Response to NRC Concerns Re Survey Instruments Used for Termination Survey.Extensive Discussion Provided in Interest of Rapidly Bringing Outstanding Concerns to Close.Response Withheld (Ref 10CFR2.790(a)(4))1994-08-17017 August 1994 Forwards Proprietary Response to NRC Concerns Re Survey Instruments Used for Termination Survey.Extensive Discussion Provided in Interest of Rapidly Bringing Outstanding Concerns to Close.Response Withheld (Ref 10CFR2.790(a)(4)) ML20072P1591994-08-17017 August 1994 Forwards Revised, Confirmatory Survey Plan for Radwaste Bldg & Suppression Pool for Plant SNRC-2176, Informs of near-term Completion of Decommissioning of Shoreham Nuclear Power Station & Hereby Respectfully Requests Support in Achieving Timely Termination of Facility possession-only License NPF-821994-08-0404 August 1994 Informs of near-term Completion of Decommissioning of Shoreham Nuclear Power Station & Hereby Respectfully Requests Support in Achieving Timely Termination of Facility possession-only License NPF-82 SNRC-2177, Forwards Rev 3 to Shoreham Decommissioning Project Termination Survey Plan. Portions of Rept Withheld1994-08-0404 August 1994 Forwards Rev 3 to Shoreham Decommissioning Project Termination Survey Plan. Portions of Rept Withheld ML20071L8741994-07-29029 July 1994 Forwards Confirmatory Survey Plan for Radwaste Building & Suppression Pool for Review & Comment SNRC-2175, Provides Notification of Survey Location Changes to Shoreham Facility Which Have Occurred Subsequent to Repts on Phases 1,2 & 3 Final Survey Status Provided in Refs 1,2 & 3 Respectively1994-07-18018 July 1994 Provides Notification of Survey Location Changes to Shoreham Facility Which Have Occurred Subsequent to Repts on Phases 1,2 & 3 Final Survey Status Provided in Refs 1,2 & 3 Respectively SNRC-2173, Forwards Termination Survey Final Rept Phase 3. Proprietary Pages to Rept Also Encl.Proprietary Pages Withheld (Ref 10CFR2.790)1994-06-14014 June 1994 Forwards Termination Survey Final Rept Phase 3. Proprietary Pages to Rept Also Encl.Proprietary Pages Withheld (Ref 10CFR2.790) SNRC-2172, Certifies That All SNM as Irradiated Fuel Permanently Removed from Site & That Decommissioning/Decontamination Work on Biological Shield Wall Complete,In Accordance W/Nrc Approving Amend 11 to Pol NPF-821994-06-0707 June 1994 Certifies That All SNM as Irradiated Fuel Permanently Removed from Site & That Decommissioning/Decontamination Work on Biological Shield Wall Complete,In Accordance W/Nrc Approving Amend 11 to Pol NPF-82 SNRC-2171, Submits Resolution of Items Identified by NRC Region I Project Inspector,Pertaining to Planned Final Draindown & Discharge of Spent Fuel Storage Pool,Following Complete Removal of Irradiated Fuel1994-06-0202 June 1994 Submits Resolution of Items Identified by NRC Region I Project Inspector,Pertaining to Planned Final Draindown & Discharge of Spent Fuel Storage Pool,Following Complete Removal of Irradiated Fuel SNRC-2170, Requests Approval of Proposed Change to Shoreham Decommissioning Plan for Addl Remedial Decontamination of Shoreham Spent Fuel Storage Pool Beyond That Originally Specified in Decommissioning Plan1994-05-20020 May 1994 Requests Approval of Proposed Change to Shoreham Decommissioning Plan for Addl Remedial Decontamination of Shoreham Spent Fuel Storage Pool Beyond That Originally Specified in Decommissioning Plan SNRC-2168, Notification to NRC of Transfer of Device Containing 30 Uci Cs-137 Source.Device Transferred to JW Merkel,Terra Analytics,Inc1994-05-13013 May 1994 Notification to NRC of Transfer of Device Containing 30 Uci Cs-137 Source.Device Transferred to JW Merkel,Terra Analytics,Inc SNRC-2169, Advises of Listed Clarification to Util Re Resignation of Jc Brons from Position of Executive Vice President of Shoreham Decommissioning Project1994-05-11011 May 1994 Advises of Listed Clarification to Util Re Resignation of Jc Brons from Position of Executive Vice President of Shoreham Decommissioning Project ML20029E1731994-05-11011 May 1994 Informs That Based on Recent Discussions Between Officials, Licensee Decided to Retain Organizational Position at Least Until Fuel Removed from Site ML20029D1991994-04-29029 April 1994 Forwards Shoreham Nuclear Power Station Radiological Environ Monitoring Program Annual Radiological Environ Operating Rept Jan-Dec 1993. ML20029D2571994-04-28028 April 1994 Advises That Jc Brons Resigned to Pursue Employment W/ Another Util Co,Effective 940429 ML20029C7111994-04-22022 April 1994 Submits Technical Info on Biological Shield Wall Blocks to Be Surveyed SNRC-2163, Provides Notification of Equipment Changes to Facility Which Have Occurred Subsequent to Report on Phase I Final Survey Status Provided in Util1994-04-21021 April 1994 Provides Notification of Equipment Changes to Facility Which Have Occurred Subsequent to Report on Phase I Final Survey Status Provided in Util ML20065M3701994-04-20020 April 1994 Responds to NRC Verbal Request for Info Re Estimated Cost for Decommissioning SNRC-2161, Forwards 1994 Internal Cash Flow Projection for Shoreham Nuclear Power Station1994-03-30030 March 1994 Forwards 1994 Internal Cash Flow Projection for Shoreham Nuclear Power Station SNRC-2160, Forwards Financial Info Required by 10CFR50.71(b)1994-03-30030 March 1994 Forwards Financial Info Required by 10CFR50.71(b) SNRC-2148, Forwards Info Supporting Licensee Proposed Amend,Submitted on 941104.Specifically,info Supports Estimates & Conclusions Re Small Quantity of Remaining Radioactive Matl & Low Radiological Significance of Potential Accident Releases1994-03-0808 March 1994 Forwards Info Supporting Licensee Proposed Amend,Submitted on 941104.Specifically,info Supports Estimates & Conclusions Re Small Quantity of Remaining Radioactive Matl & Low Radiological Significance of Potential Accident Releases 1999-10-01
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20112E8911996-05-24024 May 1996 FOIA Request to Inspect & Copy Original OL Issued by Aec/Nrc for Util & EPP Issued as App B to Plant OL SNRC-2192, Forwards Both Copies,Signed by Util President Cv Giacomazzo, of Amend 7 to Indemnity Agreement B-87.Util Returning Copies Because Effective Date Left Blank1995-05-15015 May 1995 Forwards Both Copies,Signed by Util President Cv Giacomazzo, of Amend 7 to Indemnity Agreement B-87.Util Returning Copies Because Effective Date Left Blank ML20082B9131995-03-13013 March 1995 Submits Corrected Page for Insertion Into Final Rept Re Confirmatory Survey of RB & Phase 4 Systems at Plant ML20081A9321995-03-0707 March 1995 Forwards Final Rept Orise 95/B-81, Confirmatory Survey of Reactor Bldg & Phase 4 Sys Shoreham Nuclear Power Station Brookhaven,Ny ML20081A6531995-03-0707 March 1995 Forwards Final Rept Orise 95/B-80, Confirmatory Survey of Radwaste Bldg,Suppression Pool,Phase 2 Phase 3 Sys,Shoreham Nuclear Power Station,Brookhaven,Ny ML20081B5801995-02-21021 February 1995 Forwards Final Rept Confirmatory Survey of Reactor Bldg & Phase 4 Sys Shoreham Nuclear Power Station Brookhaven,Ny ML20081A6841995-02-21021 February 1995 Forwards Final Rept Confirmatory Survey of Radwaste Bldg, Suppression Pool,Phase 2 & Phase 3 Sys,Shoreham Nuclear Power Station,Brookhaven,Ny ML20081A7111995-01-30030 January 1995 Forwards Rev 1 to Draft Rept Confirmatory Survey of Reactor Bldg & Phase 4 Sys,Shoreham Nuclear Power Station, Brookhaven,Ny ML20081A7001995-01-30030 January 1995 Forwards Rev 1 to Draft Rept Confirmatory Survey of Radwaste Bldg,Suppression Pool,Phase 2 & Phase 3 Sys, Shoreham Nuclear Power Station,Brookhaven,Ny SNRC-2188, Responds to NRC Request for Addl Info Re Certain Elevated Levels Found During Phase 4 Confirmatory Survey1995-01-20020 January 1995 Responds to NRC Request for Addl Info Re Certain Elevated Levels Found During Phase 4 Confirmatory Survey SNRC-2189, Forwards Shoreham Nuclear Power Station Radiological Environ Monitoring Program,Annual Radiological Environ Operating Rept, Jan-June 19941995-01-20020 January 1995 Forwards Shoreham Nuclear Power Station Radiological Environ Monitoring Program,Annual Radiological Environ Operating Rept, Jan-June 1994 SNRC-2187, Forwards Snps Annual Man-Rem Rept, Including Individuals for Whom Personnel Monitoring Provided During CY94,per 10CFR20.407(a) & (B).Rept Also Includes Individuals Identified in 10CFR20.202(a),who Require Monioring1995-01-11011 January 1995 Forwards Snps Annual Man-Rem Rept, Including Individuals for Whom Personnel Monitoring Provided During CY94,per 10CFR20.407(a) & (B).Rept Also Includes Individuals Identified in 10CFR20.202(a),who Require Monioring SNRC-2182, Forwards Final Annual Radioactive Effluent Release Rept for Cy 1994, Including Last Revised Copies of ODCM & Pcp.Rept Prepared for Closeout Purposes as Part of Completion of Plant Decommissioning1994-11-0101 November 1994 Forwards Final Annual Radioactive Effluent Release Rept for Cy 1994, Including Last Revised Copies of ODCM & Pcp.Rept Prepared for Closeout Purposes as Part of Completion of Plant Decommissioning ML20077L3331994-10-25025 October 1994 Forwards Revised Proposed Confirmatory Survey Plan for Reactor Bldg Shoreham Nuclear Power Station Brookhaven,Ny ML20077M8351994-10-20020 October 1994 Forwards Draft Rept, Confirmatory Survey of Radwaste Bldg, Suppression Pool & Phase 2 Systems,Shoreham Nuclear Power Station,Brookhaven,Ny ML20076K3881994-10-20020 October 1994 Forwards Proposed Confirmatory Survey Plan for Reactor Bldg, Shoreham Nuclear Power Station,Brookhaven,Ny,For Review & Comment SNRC-2184, Forwards Shoreham Decommissioning Project Termination Survey Final Rept Phase 4. Portions Withheld1994-10-12012 October 1994 Forwards Shoreham Decommissioning Project Termination Survey Final Rept Phase 4. Portions Withheld SNRC-2185, Summarizes Results from Revised Exposure Pathway Analysis Using Corrected Dcf for External Exposure for Cs-137.Rev 1 to Analysis of Bulk Matl Reconcentration Potential & Possible Exposure Pathways Encl1994-10-0404 October 1994 Summarizes Results from Revised Exposure Pathway Analysis Using Corrected Dcf for External Exposure for Cs-137.Rev 1 to Analysis of Bulk Matl Reconcentration Potential & Possible Exposure Pathways Encl ML20076F9251994-09-26026 September 1994 Forwards Final Rept Orise 94/I-80, Confirmatory Survey of Turbine Bldg,Site Grounds & Site Exteriors Shoreham Nuclear Power Station Brookhaven,Ny SNRC-2183, Forwards Amend 6 to Indemnity Agreement B-871994-09-23023 September 1994 Forwards Amend 6 to Indemnity Agreement B-87 SNRC-2181, Notifies of Equipment Changes to Shoreham Facility Which Have Occurred Subsequent to Rept on Phase I Final Survey Status,Provided in Util .Equipment Changes Described in Encl Table 11994-09-14014 September 1994 Notifies of Equipment Changes to Shoreham Facility Which Have Occurred Subsequent to Rept on Phase I Final Survey Status,Provided in Util .Equipment Changes Described in Encl Table 1 SNRC-2180, Forwards 940829 Memo Entitled, Technical Evaluation of Dusting from Concrete Blocks, Addressing Issue Discussed in Insp Rept 50-332/94-021994-09-0101 September 1994 Forwards 940829 Memo Entitled, Technical Evaluation of Dusting from Concrete Blocks, Addressing Issue Discussed in Insp Rept 50-332/94-02 SNRC-2179, Proposes That Release Criterion for Soil Be Applied to Certain Other Bulk Matls Which Will Remain at Plant Upon Completion of Decommissioning.Analysis of Bulk Matl Reconcentration Potential & Possible Exposure Pathways Encl1994-09-0101 September 1994 Proposes That Release Criterion for Soil Be Applied to Certain Other Bulk Matls Which Will Remain at Plant Upon Completion of Decommissioning.Analysis of Bulk Matl Reconcentration Potential & Possible Exposure Pathways Encl ML20072P1591994-08-17017 August 1994 Forwards Revised, Confirmatory Survey Plan for Radwaste Bldg & Suppression Pool for Plant SNRC-2178, Forwards Proprietary Response to NRC Concerns Re Survey Instruments Used for Termination Survey.Extensive Discussion Provided in Interest of Rapidly Bringing Outstanding Concerns to Close.Response Withheld (Ref 10CFR2.790(a)(4))1994-08-17017 August 1994 Forwards Proprietary Response to NRC Concerns Re Survey Instruments Used for Termination Survey.Extensive Discussion Provided in Interest of Rapidly Bringing Outstanding Concerns to Close.Response Withheld (Ref 10CFR2.790(a)(4)) SNRC-2176, Informs of near-term Completion of Decommissioning of Shoreham Nuclear Power Station & Hereby Respectfully Requests Support in Achieving Timely Termination of Facility possession-only License NPF-821994-08-0404 August 1994 Informs of near-term Completion of Decommissioning of Shoreham Nuclear Power Station & Hereby Respectfully Requests Support in Achieving Timely Termination of Facility possession-only License NPF-82 SNRC-2177, Forwards Rev 3 to Shoreham Decommissioning Project Termination Survey Plan. Portions of Rept Withheld1994-08-0404 August 1994 Forwards Rev 3 to Shoreham Decommissioning Project Termination Survey Plan. Portions of Rept Withheld ML20071L8741994-07-29029 July 1994 Forwards Confirmatory Survey Plan for Radwaste Building & Suppression Pool for Review & Comment SNRC-2175, Provides Notification of Survey Location Changes to Shoreham Facility Which Have Occurred Subsequent to Repts on Phases 1,2 & 3 Final Survey Status Provided in Refs 1,2 & 3 Respectively1994-07-18018 July 1994 Provides Notification of Survey Location Changes to Shoreham Facility Which Have Occurred Subsequent to Repts on Phases 1,2 & 3 Final Survey Status Provided in Refs 1,2 & 3 Respectively SNRC-2173, Forwards Termination Survey Final Rept Phase 3. Proprietary Pages to Rept Also Encl.Proprietary Pages Withheld (Ref 10CFR2.790)1994-06-14014 June 1994 Forwards Termination Survey Final Rept Phase 3. Proprietary Pages to Rept Also Encl.Proprietary Pages Withheld (Ref 10CFR2.790) SNRC-2172, Certifies That All SNM as Irradiated Fuel Permanently Removed from Site & That Decommissioning/Decontamination Work on Biological Shield Wall Complete,In Accordance W/Nrc Approving Amend 11 to Pol NPF-821994-06-0707 June 1994 Certifies That All SNM as Irradiated Fuel Permanently Removed from Site & That Decommissioning/Decontamination Work on Biological Shield Wall Complete,In Accordance W/Nrc Approving Amend 11 to Pol NPF-82 SNRC-2171, Submits Resolution of Items Identified by NRC Region I Project Inspector,Pertaining to Planned Final Draindown & Discharge of Spent Fuel Storage Pool,Following Complete Removal of Irradiated Fuel1994-06-0202 June 1994 Submits Resolution of Items Identified by NRC Region I Project Inspector,Pertaining to Planned Final Draindown & Discharge of Spent Fuel Storage Pool,Following Complete Removal of Irradiated Fuel SNRC-2170, Requests Approval of Proposed Change to Shoreham Decommissioning Plan for Addl Remedial Decontamination of Shoreham Spent Fuel Storage Pool Beyond That Originally Specified in Decommissioning Plan1994-05-20020 May 1994 Requests Approval of Proposed Change to Shoreham Decommissioning Plan for Addl Remedial Decontamination of Shoreham Spent Fuel Storage Pool Beyond That Originally Specified in Decommissioning Plan SNRC-2168, Notification to NRC of Transfer of Device Containing 30 Uci Cs-137 Source.Device Transferred to JW Merkel,Terra Analytics,Inc1994-05-13013 May 1994 Notification to NRC of Transfer of Device Containing 30 Uci Cs-137 Source.Device Transferred to JW Merkel,Terra Analytics,Inc SNRC-2169, Advises of Listed Clarification to Util Re Resignation of Jc Brons from Position of Executive Vice President of Shoreham Decommissioning Project1994-05-11011 May 1994 Advises of Listed Clarification to Util Re Resignation of Jc Brons from Position of Executive Vice President of Shoreham Decommissioning Project ML20029E1731994-05-11011 May 1994 Informs That Based on Recent Discussions Between Officials, Licensee Decided to Retain Organizational Position at Least Until Fuel Removed from Site ML20029D1991994-04-29029 April 1994 Forwards Shoreham Nuclear Power Station Radiological Environ Monitoring Program Annual Radiological Environ Operating Rept Jan-Dec 1993. ML20029D2571994-04-28028 April 1994 Advises That Jc Brons Resigned to Pursue Employment W/ Another Util Co,Effective 940429 ML20029C7111994-04-22022 April 1994 Submits Technical Info on Biological Shield Wall Blocks to Be Surveyed SNRC-2163, Provides Notification of Equipment Changes to Facility Which Have Occurred Subsequent to Report on Phase I Final Survey Status Provided in Util1994-04-21021 April 1994 Provides Notification of Equipment Changes to Facility Which Have Occurred Subsequent to Report on Phase I Final Survey Status Provided in Util ML20065M3701994-04-20020 April 1994 Responds to NRC Verbal Request for Info Re Estimated Cost for Decommissioning SNRC-2160, Forwards Financial Info Required by 10CFR50.71(b)1994-03-30030 March 1994 Forwards Financial Info Required by 10CFR50.71(b) SNRC-2161, Forwards 1994 Internal Cash Flow Projection for Shoreham Nuclear Power Station1994-03-30030 March 1994 Forwards 1994 Internal Cash Flow Projection for Shoreham Nuclear Power Station SNRC-2148, Forwards Info Supporting Licensee Proposed Amend,Submitted on 941104.Specifically,info Supports Estimates & Conclusions Re Small Quantity of Remaining Radioactive Matl & Low Radiological Significance of Potential Accident Releases1994-03-0808 March 1994 Forwards Info Supporting Licensee Proposed Amend,Submitted on 941104.Specifically,info Supports Estimates & Conclusions Re Small Quantity of Remaining Radioactive Matl & Low Radiological Significance of Potential Accident Releases SNRC-2145, Provides Comments Prepared by Util on Draft NUREG/CR-5849, Manual for Conducting Radiological Surveys in Support of License Termination1994-03-0808 March 1994 Provides Comments Prepared by Util on Draft NUREG/CR-5849, Manual for Conducting Radiological Surveys in Support of License Termination SNRC-2157, Forwards 1993 Rept of Personnel & Man-Rem by Work & Job Function. 1993 Personnel Exposures Extremely Low as Majority of Radioactivity Removed from Site1994-02-28028 February 1994 Forwards 1993 Rept of Personnel & Man-Rem by Work & Job Function. 1993 Personnel Exposures Extremely Low as Majority of Radioactivity Removed from Site SNRC-2158, Submits Notification of Pending Change to Decommissioning Plan Submitted 901229.Safety Evaluation for Change Encl1994-02-28028 February 1994 Submits Notification of Pending Change to Decommissioning Plan Submitted 901229.Safety Evaluation for Change Encl SNRC-2156, Forwards Annual Radioactive Effluent Release Rept for 1993. Latest Revised Copies of Offsite Dose Calculation Manual & Process Control Program Also Encl as Apps to Rept1994-02-25025 February 1994 Forwards Annual Radioactive Effluent Release Rept for 1993. Latest Revised Copies of Offsite Dose Calculation Manual & Process Control Program Also Encl as Apps to Rept ML20067C9271994-02-22022 February 1994 Forwards Fitness for Duty Program Performance Data for Period of Jul-Dec 1993 SNRC-2144, Forwards Vols 1-4 to Shoreham Decommissioning Project Termination Survey Final Rept. Twenty Proprietary Pages of Rept Withheld (Ref 10CFR2.790)1994-02-0404 February 1994 Forwards Vols 1-4 to Shoreham Decommissioning Project Termination Survey Final Rept. Twenty Proprietary Pages of Rept Withheld (Ref 10CFR2.790) 1996-05-24
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. ORISE '
. CAK RlLKat tr 4 5fl T Ui t' IOR SCIF NCE AND E DUC AT K >N October 20,1994 Mr. David Fauver Division of Waste Management - NMSS .
U.S. Nuclear Regulatory Commission ,
One White Flint North 11555 Rockville Pike Rockville, MD 20852 SUlUECT: PROPOSED CONFIRMATORY SURVEY PLAN FOR TIIE REACTOR BUILDING, SIIOREIIAM NUCLEAR POWER STATION, BROOKIIAVEN, NEW YORK [ DOCKET FILE NO. 50-322] ,
Dear Mr. Fauver:
Enclosed is the subject document for your review and comment. Comments you may have will be incorporated into the fm' al plan. Attachment A of the document contains the spending plan for this project. Please do not hesitate to contact me at (615) 576-5073 should you have any -
questions.
Sincerely, Timoth itkus Environmental Project Leader ,
Environmental Survey and Site Assessment Program TJV:rde Enclosure cc: R. Uleck, NRC/NMSS/TWFN 7F27 D. Tiktinsky, NRC/NMSS/TWFN 8A23 c. . ,,._ . . ,.
L. Pittiglio, NRC/NMSS 7F27 - '"
R. Nimitz, NRC/ Region I PMDA, NRC/NMSS/TWFN 8A23 J. Beck, ORISE/ESSAP E. Abelquist, ORISE/ESSAP File /273 9410310248 941020 PDR Apock c5000322 W PDR P O. BOX 117, OAK ROGE, TENNE 55EE 378310117 Monoged ond operovd by Ook Ridge Associated Universaes for the U S. Department of Energy j
l PROPOSED CONFIRMATORY SURVEY PLAN FOR TIIE REACTOR BUILDING SIIOREIIAM NUCLEAR POWER STATION BROOKIIAVFN, NEW YORK INTRODUCTION v
The Long Island Lighting Company (LILCO) constructed a boiling water reactor known as the Shoreham Nuclear Powar Station (SNPS). The plant was designed to provide a gross electrical output of 849 Megawatts and achieved initial criticality in February 1985. The U.S. Nuclear Regulatory Commission (NRC) License No. NPF-82 (NRC Docket File No. 50-322) issued for the facility allowed reactor operations at power levels not to exceed 5% of full power. Iow power testing in accordance with the license then commenced in July 1985 and continued intermittently until January 1989, at which time power generating operations were terminated.
The total reactor operating history was equivalent to 2.03 effective full power days of fuel exposure. The irradiated fuel, which was a standard low enrichment (2 to 3% uranium-235) uranium fuel, was subsequently removed from the reactor vessel and placed into the spent fuel poolin August 1989.
Various reactor components, piping systems, and other equipment became radiologically contaminated as a result of reactor operation. The primary contaminants which have been identified during characterization studies include iron-55, cobalt-60, nickel-63, and smaller quantities of tritium, carbon-14, nickel-59, manganese-54, zinc-65, and europium-152.2 The Long Island Pawer Authority (LIPA) was established to decommission the facility and release the site for r.nrestricted use. The LIPA Decommissioning Plan was approved for implementation by the NRC in June 1992 and willinclude ' decontamination or removal of Prepared by the Environmental Survey and Site Assessment Program, Energy / Environment Systems Division, Oak Ridge Institute for Science and Education, under interagency agreement (NRC Fin. No. A-9076) between the U.S. Nuclear Regulatory Commission and the U.S.
Department of Energy.
Renaw INMeg October 20.1994 hhp \pinwohouhamercham.003
contaminated portions of the reactor and other plant systems and equipment. A major consideration of the decommissioning plan is to maintain the integrity, when possible, of plant structures and systems. The decommissioning and termination surveys are being conducted in phases. Phase 1 included the termination survey of the internal components of the main turbine, the Turbine Building, site grounds, and exterior site structures. Phases 2 and 3, included the Reactor Building Suppression Pool, Phase 2 systems and the Radwaste Building. Phase 4 addresses the remaining portions of the Reactor Building.
The NRC Headquarters' Division of Waste Management has requested that the Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) conduct confirmatory c diological surveys of t1e SNPS decommissioning project. ESS AP has completed the confirmatory survey of the turbina internal components, the Turbine Building, site grounds, exterior site structures, Radwaste Building, Suppression Pool, and Phase 2 systems. The results of which are the subject of separate final or in process reports.2.3 1
SITE DESCRIPTION l
The SNPS is located in the Town of Brookhaven, New York on the north shore of Long Island, approximately 80 km (50 mi) east of 12 Guardia Airport and the confluence of the East River and Long Island Sound (Figure 1). The SNPS is located on a 32.4 ha (80 ac) portion of a larger 202 ha parcel ofland owned by the LILCO. The site is bounded on the north by Long Island Sound, on the east by the Wading River Marshland, on the west by other LILCO property, and on the south by Route 25A. A cyclone fence encloses the 8 ha site secured area. Within this boundary are the buildings and grounds classified as the Restricted Area, also known as the power block, where radiological controls were necessary (Figure 2). Each of the buildings that have been or will be addressed during the confirmatory process are located here and are shown on Figure 2 as the Turbine Building, the Reactor Building, and the Rad Waste Building.
Construction of the Reactor Building is predominately structural steel and concrete. Total floor space of the building is approximately 7,800 m2 (84,000 ft )2 divided among 8 levels at elevations 8'-0", 40'-0", 63'-0", 78'-0",112'-0",128'-9",150'-0", and 175'-0". The Reactor Building Reactar bklass October 20,1944 2 h:\essaptplanninhoreham\shorcharn 003
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housed the nuclear steam supply system which included the Reactor Pressure Vessel and its associated auxiliary and safety systems. Major structural components included the primary containment system, spent fuel storage pool, dryer / separator pool, polar crane and building !
sumps. The major auxiliary and safety systems included the reactor core isolation cooling, high pressure coolant injection, core spray, stand by liquid control, reactor water cleanup, fuel pool cooling and clean-up, and primary containment atmospheric control systems.
LIPA has classified plant systems and building surfaces into two categories which are basal on the potential for residual contamination. The two area categories referred to as affected or unaffected are defined as follows: "affected areas are those areas of the SNPS that are potentially contaminated or have known contamination, or a system which circulated, stored or processed radioactive materials such that they could become contaminated, or experience, neutron activation, or where records indicated spills or other occurrences may have resulted in contamination; unaffected areas are ' hose portions of the SNPS that are not expected to contain residual radioactivity." Area classification was determined by radiological use history, environmental monitoring activities, and the results of a previous characterization survey.
Affected and unaffected areas are further subdivided into survey units. Survey units are categorized as structures (Hoors, walls, ceilings, and exterior surfaces of piping and equipment),
plant systems (equipment and piping internals), and outdoor areas (grounds and building exteriors). In addition, affected survey units also have sub-classifications as suspect or non-suspect, and may also be classified as alpha affected if i-volved with fuel handling or storage.
OIUECTIVES The objectives of this confirmatory survey are to provide independent document reviews and radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's procedures and termination survey results.
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RESPONSIBILITY Work described in this survey plan will be performed under it airection of Jack Beck, Acting Program Director and Tim Vitkus, Project Leader of ESSAP. The cognizant site supervisor has the authority to make appropriate changes to the survey plan with the approval of the NRC site representative. Deviations to this survey plan will be documented in the site log book.
DOCUMENT REVIEW ESSAP will review LIPA's release records for those survey units selected for confirmatory survey. Review of additional release records will be dependent upon findings as the surveys progress. Documents will be reviewed for adequacy, accuracy, completeness, and consistency.
Data will be reviewed for appropriateness of et .ulations and interpretations relative to the guidelines.
PROCEDURES A survey team from ESSAP will perform independent visual inspections, measurements, and sampling of survey units associated with the Reactor Building. Table 1 lius the survey units selected for confirmatory surveys. Of the total,11 were selected randomly and 19 were selected by the NRC site representative. Field survey activities will be conducted in accordance with the applicable sections of the ESSAP Survey Procedures and Quality Assurance Manuals. Spo-!C procedures are listed on pages 8 and 9 of this plan. The foilowing procedures apply to survey units selected for independent confirmatory surveys. Additionalinformation regarding selection of confirmatory survey units and the implementation of this plan may be found in the general site confirmatory survey plan.'
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1 SURVEY PROCEDURES 1
Reference System The reference systems established by LIPA will be used by ESSAP for referencing measurement and sampling locations. The grid size or reference interval established by LIPA for a given survey unit was dependent upon the classification of the survey unit (affected vs. unaffected) and surface (floor, lower wall, upper wall, ceiling, or equipment).
Surface Scans Surface scans for alpha, beta, and gamma activity, will be performed over 100% of floor and lower wall surfaces and up to 50% of equipment surfaces, within each structural survey unit.
Additional scans will be performed over portions of upper wall, ceiling, and system surfaces as well as locations, such as drains, where material may have settled or accumulated. Locations of elevated direct radiation detected by scans will be marked for further investigation. Scans will be performed using gas proportional, GM, ZnS, and/or Nal detectors coupled to ratemeters or ratemeter-scalers with audible indicators.
Surface Activity Measurements For each structural survey unit, ESSAP will perform a minimum of thirty direct measurements for total beta surface activity. ESSAP will also perform additional direct measurements at locations of elevated direct radiation detected by surface scans. At measurement locations, where the average NRC surface contamination guideline is exceeded, the size of the contaminated area and the average activity in the contiguous 1 m2 area will also be determined. ,
1 Total alpha surface activity measurements will also be performed at each direct measurement l l
location when a selected survey unit is classified as alpha affected or if alpha contamination is identified by surface scans. Measurements will be performed using GM, gas proportional, and/or ZnS detectors coupled to ratemeter-scalers. A smear sample for determining removable activity level will be collected from each direct measurement location.
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Exnoste_Itate Measurements Exposure rate measurements will be performed within each survey unit, excluding system interiors, at each accessible floor direct measurement location. All exposure rates will be measured at 1 m above surfaces using a pressurized ionization chamber (PIC). Background exposure rates were previously determined during the confirmatory survey of the Turbine Building.'
DATA EVALUATIONS AND COMPARISONS The results of each survey unit sampled will be statistically tested. The goal of the test is to determine, with a given confidence level, that the LIPA survey data is not biased low compared to ORISE. The null hypothesis will be that in a survey unit, surface activities as calculated by LIPA are greater than or equal to those determined by ESSAP, i.e., H : #UPA b MI3 SAP. This hypothesis will be tested at the 95% confidence level (0.05 level of significance). If the hypothesis is rejected at that confidence level, the alternative hypothesis will be accepted i.e.,
H:3 MurA < #iwe. The test statistic, t, will be calculated using the following equation:
l Xg -X i t= 1 2 f (ng-1)S2 (y _3)3 NE+NL
\ NE*NL ~2 g NEL i where:
Xt Is the LIPA surface activity mean for a survey unit X, Is the ESSAP surface activity mean for the same survey unit nt. Is the number of LIPA direct measurement data points nn Is the number of ESSAP direct measurement data points Si , Su Are the standard deviations.
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i The calculated i is then compared to the critical value of Student's t-distribution (one-tailed) for l the appropriate degrees of freedom at the 95% confidence level (0.05 level of significance). If the Ho: Fura h Frm, is rejected, then ESSAP will evaluate additional options and alternatives i and confer with the NRC as to the recommended approach.
GUIDELINES The applicable Regulatory Guide 1.86 guidelines are those for beta-gamma emitters and the alpha contamination guidelines are those for uranium and associated decay products. The beta-gamma guidelines are:
Total Activity 5,000 B-y dpm/100 cm2, averaged over 1 m 2 15,000 B-y dpm/100 cm2 , maximum in a 100 cm2 area Removable Activity 1,000 B-y dpm/100 cm2 The alpha guidelines are:
Total Activity 5,000 a dpm/100 cm2, averaged over 1 m2 15,000 a dpm/100 cm2 , maximum in a 100 cm2 area Removable Activity 1,000 a dpm/100 cm2 1
The NRC has approved site-specific allowable surface contamination guidelines for H-3 and Fe-55, particularly in activated concrete and steel.3 These guidelines are: l nea,, w . c%,2o. im 7 a:se p# i w .es.m . sores.m s 003
Total Activity 200,000 dpm/100 cm2 , averaged over 1 m 2 600,000 dpm/100 cm2 , maximum in a 100 cm2 area 4 Removable Activity 1,000 dpm/100 cm 2 The evposure rate guideline currently being used by the NRC is 5 R/hr above background, measared at 1 m above the surface.'
TENTATIVE CONFIRMATORY SCIIEDULE Phase III: ' Reactor Br.ilding Surveys Document Review October 1994 Confirmatory Survey October 31 through November 11,1994 Sample Analysis November 1994 l
Draft Report January 31,1995 l
LIST OF CUR. RENT PROCEDURES TO BE USED IN TIIE SURVEY Applicable procedures from ORISE ESSAP Survey Procedures Manual (Revision 8; December 31,1993) include:
Section 5.0 Instrument Calibration and Operational Check-Out 5.1 General Information i 5.2 Electronic Calibration of Ratemeters 5.3 Gamma Scintillation Detector Check-Out and Cross Calibration 5.4 Alpha Scintillation Detector Calibration and Check-Out i 5.5 GM Detector Calibration and Check-Out 5.6 Proportional Detector Calibration and Check-Out 5.7 Pressurized Ionization Chamber Calibration and Check-Out 5.8 Floor Monitor Check-Out 5.10 Field Measuring Tape Calibration Reactor IWidmg - (X1ober 20,1944 8 h: \essap\planserchamuhoreham.003
Section 7.0 Scanning and Measurement Technigres 7.1 Surface Scanning 7.2 Alpha Radiation Measurement 7.3 Beta Radiation Measurement .
l 7.4 Gamma Radiation (Exposure Rate) Measurement j l
Section 8.0 Sampling Procedures 8.7 Determination of Removable Activity 8.9 Sample Identification and Labeling i
l Section 9.0 Integrated Survey Procedures
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9.2 General Survey Approaches and Strategies I
Section 10.0 Health and Safety and Control of Cross Contamination Section 11.0 Quality Assurance and Quality Control l
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TABLE 1 REACTOR BUILDING SURVEY UNITS SELECTED FOR CONFIRMATORY SURVEY SIIOREIIAM NUCLEAR POWER STATION BROOKIIAVEN, NEW YORK Survey Affected (A)/ Structure /
Survey Unit Name Unit / Component Unaffected (U) System PC004 Primary Containment - 63' NW A structure
.PC005 Sub-Pile Room A structure PC007 Primary Containment - 78' NE A structure PC008 Primary Containment - 78' SE A structure PC011 Primary Containment - 109' NE A structure RB004 Reactor Building - 8' SE A structure RB006 Reactor Building - 8' SW A structure I RB014 Reactor Building - 40' SW A structure RB037 Reactor Building - 78' SW A structure RB038 West Accumulator Aisle A structure RB057 Fuel Pool Clean-up Pumps Room A structure RB061 RWCU Regen /Non-Regen HTX's Room A structure RB068 Spent Fuel Storage Pool A structure RB071 x01 Reactor Cavity - 150' A structure RB072 x01 Dryer / Separator Storage Pool A structure RB073 x02 Bioshield Wall Blocks (Concrete) A structure RB073 x03 Bioshield Wall Blocks (Steel) A structure RB103 Reactor Building - 175' A structure RB106 Reactor Building - 175' A structure RB109 Polar Crane A structure i l
SU001 Reactor Assembly Lower Bowl A system i SU002 Nuclear Boiler Main Steam Relief Valve A system !
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i TABLE 1 (Continued) j 1
RE.kCTOR BUILDING SURVEY UNITS SELTETED FOR CONFIRMATORY SURVEY S!10REHAM NUCLEAR POWER STATION BROOKHAVEN, NEW YORK ;
Surver Survey Unit Name Anected (A)/ Stmetud Unit / Component Unaffected (U) System SU004 CRD Hydraulic Control A system SUO14 x05 #953 Misc. Embedded Drain Piping A system 1G11-TK-190 SUO14 x12 RB Porous Concrete Sump #19 or 20 A system SUO23 Misc. Building Storm Drains A system SUO58 Reactor Primary Containment A system SUO60x09 Fuel Pool Cooling Room A system SUO60x 13 RWCU Valve Chambers Room A system SUO60x23 Reactor Building Air from Drywell A system IT46-ADV-039A SUO60x24 Reactor Building Vent Dump A system I
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REFERENCES
- 1. Long Island Lighting Company, "Shoreham Nuclear Power Station Site Characterization Program Final Report," May 1990.
- 2. T. J. Vitkus, ORISE, " Confirmatory Survey of the Turbine Internal Components, Shoreham Nuclear Power Station, Brookhaven, New York," July 1993.
- 3. T. J. Vitkus, ORISE, " Confirmatory Survey of the Turbine Building, Site Grounds, and Site Exteriors, Shoreham Nuclear Power Station, Brookhaven, New York," September 1994.
- 4. Ixtter from T. J. Vitkus, ORISE to D. Fauver, U.S. Nuclear Regulatory Commission,
" Final Confirmatory Survey Plan from the Shoreham Nuclear Power Station, Brookhaven, New York [ Docket File No. 50-322]," November 4,1993.
- 5. Ietter from C.L. Pittiglio, U.S. Nuclear Regulatory Commission, to A.J. Bortz, Iong Island Power Authority, subject " Approval of a Modification of Facility Release Criteria for Tritium and Iron-55 Surface Contamination at Shoreham Nuclear Power Station, Unit 1," June 7,1994.
- 6. U.S. Nuclear Regulatory Commission, " Guidance and Discussion of Requirements for an Application to Terminate a Non-Power Reactor Facility Operating License," Revision 1, September 1984.
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} Name of Laboratory: Oct-94 Mar-95 Oak Ridge institute for Science and Education RFTA Est. Project Cost Title of Project 93-02 $176,150.00 Shoreham Reactor Building NRC Fin Number ORISE Number A9076 1286.02 fWten2???&s@%n952%%221M%i%W9%f1%<%si5 ; 3 o'929&??%%Pmk%M999??%MW*MN*sWhl 5 COST ELEMENTS Oct-94 Nov-94 Dec-94 Jan-95 Mar-95 Direct Costs $37,950.00 $83,250.00 $6,500.00 $700.00 $1,500.00 Indirect Costs-(G&A, DOE Factor) $13,500.00 $29.650.00 $2,350.00 $250.00 $500.00 Total Estimate Costs $51,450.00 $112,900.00 $8,850.00 $950.00 $2,000.00 Project Completion 27.53 % 92.53 % 98.21 % 98.83 % 100.00%l w
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