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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
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L1841990-09-20020 September 1990 Informs of Promotion of Jg Wynne to Position of Facility Operations Div Manager,Effective 900827 SNRC-1753, Forwards Rev 5 to Security Training & Qualification Plan.Rev Withheld1990-09-18018 September 1990 Forwards Rev 5 to Security Training & Qualification Plan.Rev Withheld SNRC-1758, Informs That W Uhl Resigned from Util on 900831 & No Longer Needs to Maintain Senior Reactor Operator License 44311990-09-18018 September 1990 Informs That W Uhl Resigned from Util on 900831 & No Longer Needs to Maintain Senior Reactor Operator License 4431 SNRC-1755, Forwards Rev 5 to Safeguards Contingency Plan.Rev Withheld (Ref 10CFR73.21)1990-09-13013 September 1990 Forwards Rev 5 to Safeguards Contingency Plan.Rev Withheld (Ref 10CFR73.21) SNRC-1754, Requests That Annual License Fee for FY91 Be Held in Abeyance Pending Disposition of 900105 Amend Request1990-09-0707 September 1990 Requests That Annual License Fee for FY91 Be Held in Abeyance Pending Disposition of 900105 Amend Request SNRC-1752, Forwards Revised Tech Specs Re Defueled Status of Plant,Per Agreements Reached W/Nrc at 900802 Meeting1990-08-30030 August 1990 Forwards Revised Tech Specs Re Defueled Status of Plant,Per Agreements Reached W/Nrc at 900802 Meeting SNRC-1747, Forwards Semiannual Radioactive Release Rept for First & Second Quarters 1990 & Revised ODCM1990-08-23023 August 1990 Forwards Semiannual Radioactive Release Rept for First & Second Quarters 1990 & Revised ODCM ML20056B5041990-08-21021 August 1990 Forwards Application for Amend to License NPF-82,consisting of License Change Application 8,modifying Tech Specs by Deleting Independent Safety Engineering Group & Associated Controls SNRC-1750, Amends Util 900810 Request for Interim Relief from Tech Spec Limiting Condition for Operation 3.7.1.2.b.3 Associated W/ Plant Svc Water sys-shutdown.Requests That Relief Be Granted Starting 900817 & Ending 9009081990-08-15015 August 1990 Amends Util 900810 Request for Interim Relief from Tech Spec Limiting Condition for Operation 3.7.1.2.b.3 Associated W/ Plant Svc Water sys-shutdown.Requests That Relief Be Granted Starting 900817 & Ending 900908 PM-90-110, Forwards fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.71(d)1990-08-13013 August 1990 Forwards fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.71(d) SNRC-1744, Forwards Rev 1 to, Environ Qualification Rept for Class 1E Equipment for Shoreham Nuclear Power Station Unit 1 Lilco. Provides Technical Justification for Rev1990-08-10010 August 1990 Forwards Rev 1 to, Environ Qualification Rept for Class 1E Equipment for Shoreham Nuclear Power Station Unit 1 Lilco. Provides Technical Justification for Rev SNRC-1743, Advises That Util Eliminated Positions of Outage & Mod Div Manager & Outage Engineer.Safety Significance of Changes Evaluated.No Impact Exist Because Util Contractually Prohibited from Operating Facility1990-08-10010 August 1990 Advises That Util Eliminated Positions of Outage & Mod Div Manager & Outage Engineer.Safety Significance of Changes Evaluated.No Impact Exist Because Util Contractually Prohibited from Operating Facility SNRC-1746, Requests Interim Relief from Limiting Condition for Operation 3.7.1.2.b.3 Re Tech Spec for Plant Svc Water Sys - Shutdown1990-08-10010 August 1990 Requests Interim Relief from Limiting Condition for Operation 3.7.1.2.b.3 Re Tech Spec for Plant Svc Water Sys - Shutdown SNRC-1737, Forwards License Change Application 7 Requesting Amend to License NPF-82,conforming to Guidance of Generic Ltr 88-12 Re Fire Protection Requirements1990-07-20020 July 1990 Forwards License Change Application 7 Requesting Amend to License NPF-82,conforming to Guidance of Generic Ltr 88-12 Re Fire Protection Requirements SNRC-1732, Responds to Generic Ltr 90-03 Re Relaxation of NRC Position in Generic Ltr 83-28,Item 2.2,Part 2 Re Vendor Interface for safety-related Components1990-07-18018 July 1990 Responds to Generic Ltr 90-03 Re Relaxation of NRC Position in Generic Ltr 83-28,Item 2.2,Part 2 Re Vendor Interface for safety-related Components ML20044A9131990-07-0606 July 1990 Forwards Util Response to NRC Bulletin 90-001 Re Loss of fill-oil in Transmitters Mfg by Rosemount.No Model 1153 Series B Transmitters Installed at Plant SNRC-1735, Submits Organization Changes for WE Steiger & Jd Leonard Effective 9007091990-07-0303 July 1990 Submits Organization Changes for WE Steiger & Jd Leonard Effective 900709 SNRC-1733, Submits QC Div 1990 Staffing Rept,Per Sc Contention 13(d) Settlement Agreement.Actual Manhour Requirements for QC Under Projection Reported for Previous 2 Yrs1990-06-28028 June 1990 Submits QC Div 1990 Staffing Rept,Per Sc Contention 13(d) Settlement Agreement.Actual Manhour Requirements for QC Under Projection Reported for Previous 2 Yrs ML20044A3641990-06-28028 June 1990 Forwards Joint Application for Amend to License NPF-82, Designating Long Island Power Authority as Plant Licensee Upon or After NRC Amends License to Nonoperating Status ML20043F4741990-06-11011 June 1990 Requests Approval of Decommissioning Funding Method Set Forth in Encl Site Cooperation & Reimbursement Agreement Between Lilco & Long Island Power Authority ML20043D5761990-06-0505 June 1990 Requests Interim Relief from Action Requirements of Tech Specs 3.3.7.9,3.7.7.2,3.7.7.3 & 3.7.8 Re Establishing & Maintaining Continuous Fire Watches &/Or Hourly Fire Watch Patrols ML20043C3081990-05-30030 May 1990 Requests Interim Relief from Requirements of License Condition 2.C.(13),pending Dispostion of Util 891215 Request for Exemption from 10CFR50.54 & Amend to License.Condition Concerns Quarterly Emergency Plan Drills ML20043A9721990-05-18018 May 1990 Advises That,Effective 900501,LJ Calone & Ja Notaro Will No Longer Need to Maintain Senior Operator Licenses PM-90-072, Forwards Listed Lers,Updating Original Repts for Corrective Actions Deferred Due to State of Ny - Lilco Shoreham Settlement Agreement1990-05-16016 May 1990 Forwards Listed Lers,Updating Original Repts for Corrective Actions Deferred Due to State of Ny - Lilco Shoreham Settlement Agreement ML20042H0091990-05-14014 May 1990 Forwards Completed Questionnaire for Each Applicable Type of Operational Insp,Audit or Evaluation as Identified,Per Generic Ltr 90-01 ML20042E8241990-04-27027 April 1990 Responds to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow. Licensee Will Not Use Channel Boxes for Second Bundle Lifetime,Therefore,Bulletin Does Not Apply to Facility ML20042E2001990-04-17017 April 1990 Advises That H Carter,M Herlihy,J Reid,J Dunlap & a Burritt Resigned from Util & No Longer Need to Maintain Operator Licenses ML20012F0011990-04-0606 April 1990 Forwards Rev 19 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20012F5391990-04-0606 April 1990 Discusses Layup Implementation Program & Site Characterization Program for Plant.Util Intends to Remove Neutron Instrumentation & Other Selected Reactor Pressure Vessel Internals in Order to Obtain More Accurate Profile ML20012E2821990-03-28028 March 1990 Requests Interim Relief from Requirement That Util Conduct FEMA-graded Exercise of Util Offsite Emergency Response Plan by End of 1990 & That NRC-graded Exercise Be Deferred Pending Review of Proposed Defueled Emergency Plan ML20012E2771990-03-27027 March 1990 Forwards 1990 Internal Cash Flow Projection for Facility,Per 10CFR140.21 ML20012D2071990-03-22022 March 1990 Notifies That Listed Employees No Longer Need to Maintain Listed Senior Reactor & Reactor Operators Licenses ML20012C7781990-03-16016 March 1990 Requests Interim Relief from Certain Requirements Re Emergency Diesel Generators for Plant,Pending Disposition of Util Outstanding Request in 900105 Ltr to Amend License to Create Defueled Facility OL ML20012C6441990-03-15015 March 1990 Forwards 10CFR50.59 Rept for Jan-Dec 1989 & Discusses Rept Format.Title 10CFR50.59 Requires That Rept List Changes Which Did Not Involve Unreviewed Safety Question & Completed During Reporting Period ML20012C7571990-03-15015 March 1990 Forwards Request for limited-scope Exemption from fitness- for-duty Requirements of 10CFR26.Util Also Requests That Exemption Be Granted & Remain in Effect Until NRC Approves Final Disposition of OL ML20012C2271990-03-13013 March 1990 Requests Interim Relief from Primary Containment Leak Rate Testing Requirements of 10CFR50.54(o) & App J,III.D.1-3 Pending NRC Disposition of Lilco 891208 Request for Exemption from Same Requirements ML20012B5111990-03-0707 March 1990 Advises That F Sauerbrun No Longer Needs to Maintain NRC Senior Operator License 10602 Due to Resigning from Position on 900216 ML20012A9571990-02-27027 February 1990 Responds to Generic Ltr 89-19 Re Resolution of USI A-47 on Safety Implications of Control Sys & Generic Ltr 89-21.USIs A-45,A-46,A-47,A-48 & A-49 Completed.Status of USI A-47 Changed from Evaluating to No Changes Necessary ML20011F3841990-02-27027 February 1990 Forwards Semiannual Radioactive Effluent Release Rept,Third & Fourth Quarters of 1989. Rept Includes Info for Each Type of Solid Waste Shipped Offsite During Period & Meteorological & Dose Assessment Data for Entire Yr ML20006G1631990-02-27027 February 1990 Forwards Annual Ltr of Certification of Util Local Offsite Radiological Emergency Response Plan for Facility.Requests That Ltr Be Transmitted to FEMA for Review.Info Covers Emergency Equipment Inventory Sys & Training ML20006F4671990-02-20020 February 1990 Forwards Application for Amend to License NPF-82,revising Tech Specs to Conform to Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent Tech Specs in Administrative Controls Section.... ML20006C2431990-01-31031 January 1990 Informs of Resignation of J Johnson & Expiration of Reactor Operator License 10480,effective on 900101 ML20011E0961990-01-30030 January 1990 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Intends to Indefinitely Defer Implementation of Generic Ltr Recommendations & Requirements for Plant ML20005G9231990-01-22022 January 1990 Forwards Rev 4 to Security Training & Qualification Plan.Rev Withheld ML20006A2671990-01-18018 January 1990 Responds to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Action on Generic Ltr Deferred,Based on Defueled Condition of Reactor.Chlorination Sys Operated to Preclude Biofouling ML20005G2251990-01-12012 January 1990 Reaffirms Commitment Not to Place Nuclear Fuel Back Into Facility Reactor W/O Prior NRC Approval & Advises of Preliminary Steps Taken to Lower Ongoing Costs ML20005F8241990-01-0808 January 1990 Notifies of Termination of Employment of G Good & G Bobka as Licensed Reactor Operators ML20005F1631990-01-0505 January 1990 Forwards Application for Amend to License NPF-82,creating Defueled Facility Ol.Justification for Amend Provided in Encl Rept, Shoreman Nuclear Power Station Defueled Sar. ML20005E6021990-01-0505 January 1990 Forwards Rev to Physical Security Plan Re Fuel Storage in Spent Fuel Pool to Reflect Defueled Facility Ol.Rev Withheld (Ref 10CFR73.21(jj)) ML20005E8131990-01-0303 January 1990 Certifies That Util Developed & Is Implementing fitness- for-duty Program That Meets Requirements of 10CFR26.Program Provides Reasonable Measures for Detection of Persons Not Fit to Perform Activities within Scope of Commission Rules 1990-09-07
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LONG ISLAND LIGHTING COMPANY
- 44'O w SHOREHAM NUCLEAR POWER STATION
,, - . m.s P.O. BOX 618, NORTH COUNTRY ROAD + WADING RIVER, N.Y.11792 June 21, 1982 SNRC-718 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322
Dear Mr. Denton:
Enclosed herewith are sixty (60) copies of information which amplifies and clarifies information previously provided in our letter SNRC-658. These changes clarify details relative to qualifications and training of personnel providing or supporting the fire protection program.
Also included are sixty (60) copies of a revised response to NRC Question 420.39. The original response was made in June 1980.
This response has been revised to reflect changes in management organization and to better correspond to the latest wording of the station procedures covering fire protection.
Revisions since SNRC-658 have been identified with a bar in the right hand margin. Please note that these revised pages are not intended to represent an FSAR rewrite of the sections, but are made ,
to clarify points arising from discussions of SER Item No. 52,
" Management Review". The complete scope of changes to the FSAR sections will be forwarded via a formal FSAR amendment in July.
In addition to the above, LILCO commits to comply with the guidance contained within Regulatory Guide 1.33, Revision 2 dated February, 1978 with the following clarifications: e
- a. The requirements established by ANSI N18.7-1976, paragraphs 4.3, 4.4 and 4.5 shall be governed by commitments made in Section 6 of Shoreham's Technical Specifications,
- b. ANSI N18.7-1976, paragraph 5.2.2(2) is intended to apply to procedural steps such as immediate #f)gjol actions in Shoreham Emergency Procedures.
8206280379 820621 DR ADDCK 05000322 PDR FC-893 5
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June 21, 1982 '
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SNRC-718 ,
Page 2
- c. In reference to ANSI N18.7-1976, paragraph.5.2.13.~2, the LILCO QA Manual allows and controls-the release of certain specific nonconforming items, which could ;
be caused by documentation deficiencies, to be
- installed but not operated. The conditional release does.not change _the documentation requirement,'but allows for installation prior to all required docu- '
mentation arriving on site.
Based on the information contained in and attached to this letter, i LILCO feels that SER Item.52 can now be closed. Should you have any questions, please contact this office.
Very truly yours, J. L. Smith Manager, Special Projects Shoreham Nuclear Power Station RSII:mp Attachments cc: 'J. liiggins All parties V
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13.2.1.2.4 Training for Maintenance Personnel Personnel assigned to the Maintenance section possess a high degree of manual dexterity and ability and are determined to be capable of learning and applying basic skills in maintenance operations through entry level testing. Personnel assigned to supervisory positions have, as a minimum, three (3) years experience in one or more crafts. All maintenance personnel participate in the Mechanic Training Program which consists of the following segments:
- 1. Maintenance Skills Training
- 2. Power Plant Training
- 3. Advanced Mcchanic Training The Maintenance Skills Training Course is 12 weeks in duration and consists of classroom and laboratory instruction in basic mechanic skills, shop mathematics, millwright skills, machinist skills, uolding skills, and basic electricity. Satisfactory student performance is documented through the administration of oral or wri tten examinations, or observance of skills development by a qualified instructor. The Maintenance Skills Training Program is administered by The Long Island Lighting Company.
The Power Plant Training Course is approximately 4 weeks in duration and consists of classroom training in Station procedures related to maintenance, Station administrative policies and documents, and SNPS Systems Familiari?.ation Training. Also provided is on-the-job training which includes the performance of preventive maintenance or maintenance repair on plant systems during the preoperational test program (initial staff only).
Evaluation of participant performance during this segment is through use of either written examinations, oral examinations, or supervisory observance of satisfactory skills development.
Advanced mechanic training consists of vendor supplied training in the maintenance and repair of particular plant systems and components. Examples of such short duration courses are; DeLaval Diesel Maintenance, Recirculation Pump Seal Maintenance, Target Rock Relief Valve Maintenance, Control Rod Drive Maintenance, et al. Courses range in duration from 1 to 10 days and may be administered by the equipment vendor or qualified Long Island Lighting personnel. Student performance in the courses listed may be evaluated through instructor observance of satisfactory skills development.
The three segments of training described in detail above will qualify these personnel to perform normal maintenance on plant equipment including fire protection equipment maintenance and inspection.
13.2.1.2.4.1 Rgqualification Training for Maintenance Personnel Requalification training for maintenance personnel consists of refresher training associated with the General Employee Training Program and periodic supervisory led reviews and discussions of the following topics:
- 1. Scheduled and completed maintenance courses
- 2. Scheduled maintenance (rehearsals)
- 3. Completed maintenance (review)
In addition, all maintenance personnel will participate in a continuing program of self study of the following materials:
- 1. New or revised SNPS procedures related to maintenance
- 2. Descriptions of plant modifications related to maintenance
- 3. Event and experience reports related to mTintenance Requalification training exists on a continuous basis and includes supervisory review of the program components described above.
1 13.2.1.2.5 Training for Fire Protection Staff Members Personnel responsible for the implementation of the Station Fire Protection Program will receive Fire Brigade Training (as described in Section 13.2.1.2.6 below) and Fire Protection Technology Training. Both programs will be taught by plant training staff with assistance from suitable vendors. Fire Protection Technology Training will include the following topics:
- 1. Station building layout and fire protection cystem design.
- 2. Design of and maintenance on fire detection, suppression, and extinguishing equipment.
- 3. Fire prevention techniques and procedures.
13.2.1.2.6 Training for Fire Brigade Members Personnel who make up the Station Fire Brigade will be trained via a program of classroom instruction, practice sessions, and drills prior to their official assignment to the Fire Brigade.
The training vill be provided by qualified individuals knowledgeable and experienced in fighting the types of fires that
could occur in the plant and in using the types of equipment availabic at Shoreham. The classroom phace will be taught by plant training staff in conjunction with Suffolk Country Fire Training Center and suitable vendors and will include the following topics:
- 1. Fire hazard identification by location and fire type, including locations where breathing apparatus is required.
- 2. Familiarization with plant layout, including routes for ingreso and egress as well as locations of all fixed and portable fire fighting equipment.
- 3. Methods and equipment appropriate to each type of fire, including electrical fires, cable and cable tray fires, hydrogen fires, flammable liquid fires, waste / debris fires, and record file fires.
- 4. Indoctrination in the Plant Fire Protection' Program.
Each Fire Brigade member will be trained to accomplish any of the positions of responsibility under Brigade Leader. This approach provides the flexibility necessary in a small brigade of varying membership.
The actual assignment of specific duties will be made on the spot by the Brigade Leader.
- 5. Proper use of respiratory protection, communication, lic;hting and portable ventilation equipment.
- 6. Review of the plant Pre-fire Plans, which identify the preferred fire fighting equipment to be used in each specific identified fire hazard area. Training will also include a revicu of proper equipment and procedures to be used for the balance of the site.
- 7. Review of pertinent modifications, additions, or changes to the Plant Fire Protection Plan or fire fighting equipment.
- 8. Methods for fighting fires in buildings or tunnels.
- 9. Toxic and corrosive characteristics of expected combustion products.
- 10. Station evacuation signals and routes.
Practice sessions will be held at the Suffolk County Fire Training Center and will allow Fire Brigade members to train on actual fires. Each Fire Brigade member will attend at least one practice session per year and will don protective equipment (including respiratory protection) at 1 cast once per year.
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Preplanned drills will be performed at least once per three months for each Fire Brigade, with each Fire Brigade member attending a minimun of two dril]s per year. At least one of these drills per year, per Fire Brigade, will be unannounced. At least one of these drills per year per Fire Brigade, will be on a backshift. At least one drill per year will involve the participation of the Wading River Fire Department onsite.
The drills will conform to the established plant fire fighting plans where possible and will include operating fire fighting equipment where practical. The drill should include on site operation of self-contained breathing apparatus, communication equipment, and portable and/or installed ventillation equipment.
The drills will be critiqued in order to assess fire alarm effectiveness, response time and equipment selection, placement, and usage, a well as the leader's direction of the effort and each member's response. Unsatisfactory drills shall be repeated within 30 days.
13.2.1.2.6.1 Fire Brigade Refresher Instruction All Station Fire Brigade personnel will be provided with at least four sessions of refresher instruction each year. These will be scheduled such that the topics will be repeated at least every two years, with appropriate updates in the detailed course material.
13.2.1.2.7 Fire Brigade Chief Trajning Candidates for the position of Fire Brigade Chief will receive appropriate training. This training will include Fire Brigade Training (as described in Section 13.2.1.2.6), and Fire Brigade Leadership Training, designed to teach direction and coordination of fire fighting activities. Both programs will be taught by plant training staff with assistance from suitable vendors.
13.2.1.2.8 shift Technical Advisor Training Personnel assigned as Shift Technical Advisors participate in an integrated program of theoretical and practical instruction. The components of this program are the following:
- 1. Basic theory
- 2. Plant specific theoretical training
- 3. Plant systems / procedures training
- 4. Plant accident / transient analysis training
- 5. Mitigating core damcge training C. ?lanagerentzSupervisor nkills training
The Basic Theory training segment consists of university level course. work. presented by the, Polytechnic Institute of New York or.
similar accredited institutions. Courses are offered on the graduate level and are presented to those candidates who have not received previous university level instruction related to the following topics:
- 1. Basic fundamentals of nuclear and reactor engineering
- 2. Radiation protection
- 3. Thermodyn6mics
- 4. Heat transfer
- 5. Principles of fluid mechanics Courses are presented in a classroom instructional format with written examinations used to measure student performance.
Plant specific theoretical training is provided'in the form of The General Electric Station Nuclear Ungineer Training Course.
The course is S weeks in duration and consists of classroom instruction in fuel' loading, startup testing, power distribution j control, fuel exposure, isotopic' content, cycle length
! . predictions and discharge requirements. Student performance.is -
i evaluated through the administration of-mid course and final written examinations.
I Plant systems / procedures training consists of classroom instruction in SNPS specific systems and procedures. ' Included as i instructional topics are:
- 1. Nuclear Steam Supply Systems and their operation
- 2. BWR steam cycle systems and their operation
- 3. Station general operating procedures .
f 4. Station general administrative procedures ,
! The course is 8 weeks in duration, i.s administered by SNPS
- personnel-and uses periodic written examinations as the means for evaluating student performance.
l Shift Technical Advisor candidates are provided with accident /
transient analysis training'through participation in a 4 week simulator' training course. The initial course is provided by the
, General Physics Corporation utilizing the Limerick Simulator Facility. Basic plant operations including plant startup and chutdown will be demonstrated. In addition, Shift Technical
!- - ndvisor candidates will observe various plant accident and~
transient scenarios concurrently with the examination of the technical aspects of each event in the classroom. Evaluation of i
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student performance will be accomplished through the administration of written and oral examinations.
Training in methods for mitigating core damage for Shift Technical Advisors is described in section 13.2.1.2.9.
Each Shift Technical Advisor candidate will participate in a one week management / supervisory skills course presented by the Long Island Lighting Company or qualified vendor. The course will include training in techniques associated with leadership, motivation, proble.m solving, decision making, and organizational management under stress. Evaluation of student performance in this course will be accomplished through che administration of written and/or oral examinations.
13.2.1.2.8.1 Shift Technical Advisor Requalification Training The Shift Technical Advisor Requalification Training Program is tuo (2) weeks in duration and is administered annually by the Long Island Lighting Company or qualified vendor. The program consists of a pne week classroom segment and a one week simulator segment. The classroom segment includes presentations related to the following topics:
- 1. A review of plant transient and accident analysis emphasizing the Shift Technical Advisor's role in accident assessment
- 2. A review of plant related industry and licensee event reports
- 3. A review of major plant modifications and procedure changes affecting the Shift Technical Advisor position.
The simulator training segment will consist of control manipulations and observance of plant transient / accident response. The simulator training segment will be conducted on the Limerick simulator or an equivalent facility.
- Written examinations will be administered annually to provide a basis for determining Shift Technical Advisor knowledge and to assist in defining topics for which additional training is required.
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13.2.1.2.9 Tra ining for Mitigating Core Damage The Mitigating Core Damage Training Program provides shift Technical Advisors and ope-ating personnel, from the Plant Manager through the operations chain to licensed operators, instruction related to degraded core recognition and methods for recovery from the degraded core condition. Managers and technicians in the instrumentation and control, health physics, and radicchemistry sections will participate in the program to a degree commensurate with their responsibilities. The course is one week in duration and is administered by the Long Island l Lighting Company, The General Electric Company, or other
- qualified organizations. The course serves to draw together specific concepts and is considered the second phase of a two phase program. The first phase consists of participation in selected portions of those programs which constitute the Licensed Operator Training Program (13. 2.1.1 ) . The follouing course components are included
- 1. Core cooling mechanics / accident recognition: topics included are; adequate core cooling, heat sources, core cooling mechanisms, and inadequate core cooling recognition.
2 Core damage mitigation: topics included are; fixed / movable nuclear instrument use, degraded core effects on coolant chemistry, process instrument response, corrosion effects, gas generation sources.
and accident environment dose determination.
- 3. Core transient identification and damage mitigation through use of emergency procedure guidelines.
The course is administered in a standard classroom format accompanied by instructor guided procedural walk-throughs.
Evaluation of student performance is accomplished through administration of written examinations and instructor evaluation of student use of procedural guidelines.
13.2.1.2.10 Training for Support Engineering Personnel Support engineering personnel are assigned based on previous academic training and experience related to the assignment.
Following assignment, personnel participate in the following additional programs to a degree commensurate with responsibility.
- 1. General Employee Training (when rcsigned to the plant site)
- 2. Plant systems familiarization training The General Employee Training Program is described in section 13.2.1.3.
Plunt systems familiarization training for support engineering personnel is accomplished through participation in selected portions of the licensed operator training program (13.2.1.1.5),
or the Shift Technical Advisor Training Program (13.2.1.8) associated with plant systems. The degree of participation in these classroom programs is based on the systems familiarization needs of each individual to complete particular job assignments.
13.2.1.2.10.1 Requalification Training for Support Engineering Personnel Requalification training for support engineering personnel will consist of refresher training associated with the General Employee Training Program (13.2.1.3) and self study of the following materials:
- 1. New or revised SNPS procedures related to Uupport Engineering Staff assignments or responsibilities
- 2. Descriptions of plant modifications requiring review by the Support Engineering Staff
- 3. Event and operating experience reports requiring review by the Support Engineering Staff Requalification training will exist on a continuous basis and will includc supervisory review of the self-study program described above.
13.2.1.3 General Employee Training The SNPS General Employee Training Program provides general plant and Station orientatior, information to Long Island Lighting Company employees (permanent and temporary), contracted employees, and visitors, so that they are able to complete a wide range of general tasks in a safe and competent manner. The General Employce Training Program is divided into three categories to best fit the needs of all personnel assigned to the Shoreham Nuclear Power Station. These categories are:
- 1. Permanent station personnel
- 2. Temporary station personnel
- 3. Contracted personnel Each listed category participates in the General Employee Training to the extent warranted by position or assignment. The complete program includes the following topics:
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- 1. . General description of the station and facilities i
I 2. Station Security Program and procedures
, 3. Station Fire Protection Program, including evacuation
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routes and signals, fire and fire hazard reporting, and basic. fire fighting equipment.
- 4. . Radiological health'and safety including applicable
- portions of 10CFR 19 and 10CFR 20 1
-5. Quality assurance
- 6. Industrial health.and safety j 7. Station emergency plan and implementing procedures The General Employee Training Program is presented in modular form by.Long Island Lighting Company personnel. Each module consists of video tape / slide'or live instruction presentations
, related to each listed topic. Instructor led discussions follow each_ topic presentation to clarify; areas of difficulty. Student performance is documented through administration of a written examination covering applicable topics. Personnel permanently
! assigned to the Shorehnm Nuclear Power Station who require unescorted access to all Station areas, participate in General Employee Training which includes all topics. Personnel permanently assigned to the Shoreham Power Station whose work i assignments involve admittance to Station administration i'
buildings only, participate in the program to the extent necessary to assure safe execution of their duties.
l Long Island Lighting Company Personnel temporarily' assigned but ~
requiring unescorted access to'all Station. areas participate in all-topics of the General Employee Training Program. Temporarily assigned personnel whose work assignment involves. admittance to~
Station administration buildings only, participate in the' program to the extent necessary to assure safe execution of their duties.
Contracted personnel assigned to.the Shoreham Nuclear Power-Station requiring unescorted access to-all Station areas, participate in all topics of.the General Employee Training Program. Contracted employees whose work assignments involve
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admittance to Station administration buildings only, participate in the program to the extent necessary to assure safe execution of'their duties.. Contracted personnel who will be continuously escorted by qualified Station personnel while working within the Station. boundary for short' periods of time, will not be required ,
to participate in the General Employee Training Program.
l An annual evacuation drill will be performed'in conjunction with l
the emergency plan in' order to ensure its effectiveness.
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13.2.1.3.1 Security Personnel Fire Protection Training In addition to training required to carry out their normal tasks, security personnel will be trained in the following areas related to the Station Fire Protection Program:
- 1. Entry procedures for Wad _ng River Fire Department
- 2. Crowd Control (exiting personnel during an evacuation).
- 3. Fire llazard reporting.
13.2.1.3.2 Wading River Fire Department Personnel Training The Wading River Fire Department may be called in to assist the SNPS fire brigade in an emergency. In order that Fire Department personnel uay safely carry out their tasks, they will be trained in the following areas:
- 1. Site security entry and exit procedure
- 2. Health physics (basic radiation principles and practices and typical radiation hazards).
- 3. Station layout familiarization
- 4. Station fire fighting procedures applicable to the Wading River Fire Department.
This training will be performed under the direction of the plant training staff.
In addition to the above training, one station fire drill per year will involve assistance from the Wading River Fire Department.
13.2.1.3.3 General Employee Refresher Training Personnel who receive instruction in the following General Employee Training Program topics, receive repeat instruction and are examined on these topics annually as part of the refresher training progrum:
- 1. Radiological health and safety including applicable portions of 10CFR 19 and 10CFR 20
- 2. Station emergency plan and implementing procedures
- 3. Station Fire Protection Program including evacuation routes and signals, fire and fire hazard reporting, and basic fire tighting equipment.
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Request 420.39:
Your description in Sections I.A. and I.B. of your " Fire Hazards Analysis Report" does not provide adequate information on your fire protection organization for us to complete our review.
Therefore, please provide the following information:
(1) You state that prior to fuel loading the Vice President, Project Management will have overall responsibility for the fire protection program and that after fuel loading the responsibility will transfer.to the Vice President, Operations. Describe the offsite position that has direct responsibility for implementing the provisions of the fire protection program. This should include the responsibility for formulation, implementation, and assessment of the effectiveness of the fire protection program and activities such as fire drills and training conducted by the fire brigade and plant personnel.
(2) Describe who has overall responsibility for the fire protection program at the facility. Describe any delegation of this responsibility for the fire protection program such as maintenance of fire protection equipment and systems, testing of fire protection equipment, fire safety inspections, fire lighting procedures, and fire drills.
(3) Describe the authority of your fire brigade leader relative to that of your Watch Engineers.
Response
(1) The Vice President-Nuclear is responsible for the safe and reliable operation of the Shoreham Nuclear Power Station. He is the offsite official who has overall management responsibility for the establishment, implementation and effectiveness of the SMPS Fire Protection Program. He provides technical direction to the Plant Manager to whom he has delegated these responsibilities.
The Chairman of the Nuclear Review Board is responsible for assuring that independent review and audit of the SNPS Fire Protection Program is conducted by the QA Department under the cognizance of the NRB in accordance with SNPS Technical Specifications. This independent review and audit assesses the effectiveness of the SNPS Fire Protection Program, the training of the station Fire Brigade, and the fire drills conducted at the station.
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(2) The Plant Manager has the direct responsibility for formulating, implementing, administering and periodically assessing the effectiveness of the Fire.
Protection Program including fire drills and fire training of the fire brigade and plant personnel. 'He is also directly responsible for the effective coordination of the fire protection program with the station emergency plan to assure that a single point of' control and contact will exist for all fire contingencies. The Plant Manager's fire safety responsibilities are delegated as follows:
(a) Fire Protection Program Manager (Maintenance Engineer) is responsible for:
(i) Periodic inspection to: minimize the amount of combustibles in and around the-plant;. determine the effectiveness of
, housekeeping practices; assure that all i fire protection systems / equipment, emergency lighting, communication equipment, fire stops, penetration seals
, and fire-retardant coatings are in a t-fully operational condition; assure-1 prompt and effective corrective actions are taken to correct unsafe conditions.
5 NOTE:- Respiratory protection equipment for.the 4
station fire brigade shall be maintained ,
by the Health Physics Engineer.-
(ii) Development of the' fire fighting training program for operating plant personnel, the Station Fire-Brigade and' the Wading River Fire Department. In conjunction with the training program, he shall be responsible for conducting-fire drills to determine how well the .
training' objectives have been mot. He.
shall be responsible for critiquing.the t fire drills and practice-sessions to
- pin-point deficient areas.
(iii) Testing and maintenance of. fire protection. systems and equipment to assure maximum operational capability.
(iv) Reviewing and evaluating proposed work
, . activities to identify potential transient fire loads, or increased i
sources, and ensuring sufficient fire fighting equipment is moved into an area with temporarily increased fire loading.
(v). Implementation of a program for indoctrination of all plant contractor ,
personnel in. appropriate. administrative procedures which implement the fire protection program, and the emergency.
procedures relative to fire protection.
(vi)- Implementation of a program for' instruction of personnel on the. proper handling of accidental' events such as leaks or spills of flammable materials that are related to fire protection.
(b) Fire Protection Supervisor shall under the direction of the Fire Protection Manager be responsible.for:
(i) Organizing and implementing all Fire' Protection activities at the Shoreham Nuclear Power Station in accordance with the.SNPS Fire Protectin Program and- r Procedures.
(ii) The application of administrative controls to minimize fire hazards throughout the Shoreham plant site.
(iii) Coordination of all technical aspects of the SNPS Fire Protection Program training.
(iv) Supervision of Fire Brigade supervisory "
1 and contract personnel in. fire protection activities except'at the
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scene of an actual emergency.
(v) Ensuring all commitments to.all Federal and Local Regulatory Agencies associated l with fire protection activities at SNPS -
l are adhered to.
I (vi) Direction and coordination of' activities l involving outside agencies (Insurance,
. Mutual, and Fire Departments, etc.) in matters pertaining.to SNPS Fire i Protection under the direction'of The-Fire Protection-Program Manager.
(vii) Review of new installat' ions, or. requests for.new equipment / material to ensure appropriate restrictions or limitations required by the SNPS Fire Protection Program are met and applicable fire.
precautions are taken.
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- e (c) The Quality Assurance Manager and the Operating Quality Assurance Engineer are responsible.for assuring that the LILCO QA Program as it relates to the Shoreham Fire Protection ~ Program is implemented.- They assure by means of reviews, inspections, surveillance, and sudits.that design, procurement, installation, testing, and administration controls are established and implemented. They report'results to cognizant management.
(d) The SNPS Training Coordinator is responsible for implementing the training requirements of~the fire training program and assuring that plant-personnel and fire brigade personnel receive the appropriate training.
(e) The Fire Brigade Chief is responsible for directing firefighting efforts within the SMPS protected. area and switchyard.
(3) The on-shift Watch Engineer has direct responsibility for the' safe operation of the plant. His immediate subordinate is.the watch supervisor, who also is-the Fire Chief. All fire brigade members including the Fire Brigade Chief are selected such that.theirl normal~
station duties do not prevent'immediate response to a fire.
L (4) Additional details on organization, training, etc. are included in Section 6 of the Shoreham-Technical Specifications and the Station' Procedures,. (SP) listed 1
below:
(a)- SP 39.500.01 - Organization.and Administration of Fire Protection Program (b) SP 39.500.02 - Fire Briga'de Organization, Response, Practice and Drills-
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(c) SP 39.500.03 - Fire Protection Program Training 4
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