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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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, _ .___ _,_ -k 175 EAST OLD COUNTRY ROAD = H 4 CKSVI LLE, NEW YORK 11801 MILLARD S. POLLOCM vtCE PRESIDE NT
- NUCLE AR SN RC-8 37 February 10, 1983 Mr. Thomas T. Martin, Director Division of Engineering & Technical Programs U.S. Nuclear Regulatory Commission, Region I King of Prussia, PA 19406
. NRC Inspection No. 82-34 Shoreham Nuclear Power Station-Unit 1 Docket No. 50-322
Dear Mr. Martin:
This letter responds to your letter of January 2, 1983 which forwarded the report of the inspection conducted by repre-sentatives of your office on November 29-Decenber 3, Decembe r 6-10 and December 13-15, 1982.
The inspection was performed to determine the status of the LILCO Quality Assurance Program for operations of the Shoreham facility. Your letter stated that no violations were observed but that there were a number of items that must be addressed and appropriately corrected by LILCO.
The Inspection No. 50-322/82-34 report contains a table (pages i-iiii inclusive) that itemizes the Inspectors' findings.
Following are LILCO's responses to item 21, regarding uncontrolled M&TE Vendor manuals, and to those open itens identified with an asterisk. The responses appear below in the same sequence they are listed on the table. Please note that LILCO has taken excep-j tion to the findings for items 05, 11, 15, 21 and 22. Explanations are provided for all exceptions, and action on item 05 is being performed as suggested.
l The response tine for the issues addrecsed in the report was extended via telephone by Mr. J. C. Higgins, January 26, 1983, and by Mr. D. L. Caphton, February 3, 1983.
I 8312130416 831119 DR ADOCK 05000322 PDR
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_ LONG ISLAND LJOHTING COMf%NY Mr. Thomas T. Martin-February 10, 1983-
-Page Two I. Item: No. 322/82-34-29 para 5.3.1.2.
Issue: ' Verify continuing service contract with qualified A/E is in effect prior to O.L. (Open)
Response
Stone and Webster will continue as the Qualified Architect Engineer of record following the present construction stage of oper-ation. The period 'to Qe covered by Stone and Webster will extend from at least thirty days prior.to fuel load until the first refueling outage, or until another Qualified Architect Engineer has been' engaged.
A program, utilizing the services of Stone and Webster, meets the requirements 'of the referenced FSAR 13.1.1. 3 for a " Continuing Services Contract"'with a qualified Architect Engineer firm prior to fuel load to provide supplementary engineering and consultant support when needed.
The procurement of additional " Continuing Services
. Contracts" with other qualified Architect Engineering firms is being actively. pursued. However, predicated on the acceptability of this interim program, the need for this contract (s) to be in place by fuel . load is no longer a prerequisite.
The above information, presented to the NRC at Bethesda on January. 28, 1983, is fully responsive to the issue and should be' adequate for close-out.
Completion Target Date: 30 days prior to fuel load.
II . - Item: No. 322/82-34-04 para 5.3.1.4 Issue: Licensee must determine which station procedures are in-use and inform station personnel (Open)
Response
Station Procedure SP 12.001.01, "Index and Organization of Station Operations Manual" has been revised to include the term "In Use" oon the Plant _ Procedure Status List (PPSL) for the procedures in use. The PPSL has been updated to indicate those procedures currently in use and will be continuously updated as the status of procedures changes.
Completion Target Date: Completed.
- LONG ISLAND LIGHTING COMPANY Mr. Thomac T. Martin February 10, 1983 Page'Three III. Item: No. 322/82-34-05 para 5.3.1.4 Issue: Summary document needs to be prepared to identify and index source documents to the requirements of ANSI N18. 7-1976 (open)
Response
LILCO takes exception to the finding that a summary document has not been developed as required by ANSI N18.7-1976.
LILCO considers the QA Manual, and specifically Appendix D of the Manual, as a summary document adequate to satisfy the requirements
- found in paragraph 5.1 of the ANSI Standard.
However, to promote convenience and clarity, LILCO is preparing a detailed matrix to cross-reference ANSI N18.7-1976 requirements and specific LILCO procedure number references.
The index will serve as an aid to verify inclusion of the ANSI N18.7 requirements in the appropriate LILCO procedures.
Completion Target Date: April 15, 1983 IV. Item: No. 322/82-34-06 para 5.4.1 Issue: Establish phase in period for LILCO engineering and technical support for safety related activities (Open) ,
Response .
LILCO has developed an interim program for management control of station modifications and engineering support for Shoreham Nuclear Power Station at fuel load. This interim program will transfer project engineering organization and the engineering function, which had been the responsibility of the Manager, Shoreham Construction and Engineering, to the Manager, Nuclear Engineering. Therefore, the same Project Engineering Division which was responsible for the engineering during the construction phase will control the engineering during the operating phase. Throughout this interim period, Stone and Webster Engineering Corporation (SWEC), the qualified Architect Engineer of record for the plant construction, will be retained to supply the necessary engineering support for Shoreham operations.
This interim program will be implemented in accordance with approved administrative procedures which are presently being developed by LILCO and SWEC organizations.
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- LJONG ISLAND L8GHTING COMP %NY
, Mr. Thomas T.iMartin Februarycl0,.1983
.Page Four On January 28, 1983, LILCO presented a summary of this
' interim program to. NRC representatives 1from the Offices of Nuclear i Reactor Regulation and. Inspection and Enforcement and received verbal concurrence'for this management approach to the control of engineering support at fuel load. In addition, LILCO committed to provide a letter transmittal by mid-February documenting the hecessary changes to the FSAR.
s LILCO. anticipates that this interim program will be ready for NRC ~ Inspection and Enforcement review by mid-to-late April--1983 and will be in effect until no later than the first refueling . outage. This time interval will constitute the phase-in
. period during which the LILCO engineering and support organizations
. ..w ill be -able to complete the necessary programs and procedures to allow LILCO to perform engineering and design activities within its own organizations.
t 1 Completion Target Date: April 30, 1983
~
V. Item: No. 322/82-34-03 para 4.2.3.3.4 Issue: Audits must be performed to assess plant readiness for operations (Open)
Response
1 The NRC inspector noted in~ paragraph 4.2. 3. 3.4 that LILCO had' already scheduled three separate readiness audits. The present
! status of these audits follows:
- 1. A. QA audit was conducted January 24-February 4, 1983 to determine readiness of offsite organizations to 1 support the station during operations. Preliminary
' analysis of the results indicates that all organi-zations are either adequately prepared or will be
! prepared and phased into their support roles by means
- of the interim program for management control of
- station modifications and engineering support that L is described in Response IV.
l 2. The NRB/QA audit to evaluate LILCO readiness for fuel load was started on January 21, 1983. However, the
[
audit has been interrupted because of the revised fuel load date. -It will be resumed at a time more consis- ,
tent with the fuel load schedule. Present plans are to' complete the audit in March or April, 1983, in time to effect any required corrective action prior to fuel load.
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- LON'O ISLAND UGHTING COMPANY Mr. Thomal T. Martin February 10, 1983 Page Five
- 3. The QA Department audit to determine the plant staff's readiness to operate the station in accordance with the LILCO QA Program will be completed during March or April, 1983, in advance of fuel load.
Completion Target Date : 1. February 4, 1983
- 2. April 30, 1983
- 3. April 30, 1983 VI. Item: No. 322/82-34-14 para 6.4.4 Issue: Tagout forms in use which are not specified in the procedure (Open)
Response
Although the log forms in use in the Control Room differed in format from those specified in the Station Procedure, they contained the same information and therefore caused no inadequacies in the control of maintenance activities or component operations. Furthermore, Section 3.5 of the procedure designated the forms appended therein as
" samples" and therefore did not specifically preclude the use of forms with different formats.
Howeve r, in order to provide clarification and consis-tency of forms, SP 12.011.01, Station Equipment Clearance Permits, was revised (Revision 9) and approved 1/11/83. Appendix 12.2, SECP Log Book, and Appendix 12.11, Equipment Information Card Log, were changed so that the log forms specified in the procedure are used in the Control Room.
Completion Target Date: Completed VII. Item: No. 322/82-34-21 para 8.4.3 Issue: Uncontrolled M&TE Vendor manuals in M&TE lab (Open)
Response
LILCO does not concur that vendor technical manuals maintained in the M&TE laboratory need to be controlled copies.
They are not used to perform M&TE calibrations. The calibrations are performed in accordance with formally approved procedures.
t ONG ISLAND LIGHTING COMPANY Mr. Thoman T. Mnrtin February 10, 1983 Page Six LILCO will, however, study the need to control these manuals. Meanwhile, they have been removed from the laboratory until such time that the study is completed.
Completion Target Date: Completed VIII. Item: No. 322/82-34-22 para 8.4.4 Issue: Poor work practices and environmental conditions in the M&TE lab (Open)
Re sponse LILCO takes exception to the finding that poor work practices are used in the M&TE laboratory and that poor environ-mental conditions exist.
At the time of inspection, the laboratory was undergoing physical expansion. This expansion, requiring the cutting of an opening three feet in width through a cinder block wall, resulted in an unusual amount of dust. In addition, the expansion neces-sarily caused the room to be in some disarray. Immediate steps were taken to clean the shop and reorganize the furniture, benches and shelves, which actions have been completed. A regular clean-ing schedule has been established to ensure continued cleanliness.
Work practices did not deteriorate during the expansion of the calibration laboratory. As the inspector noted in paragraph
- 8. 3. 2. 5 of this report, proper calibration techniques are utilized by qualified personnel with calibration standards traceable to the National Bureau of Standards.
Instruments requiring dust protection are segregated from the shop environment. For example, dead weight tester weights are stored in separate metal boxes. Of course, not all instruments require dust protection. For example, the electronic standards and test gauges that LILCO uses do not require special dust protection.
Regarding environmental control, a 24-hour a day circular chart monitors and records the temperature and humidity in the M&TE shop. The ventilation system supplying the M&TE shop is part of the Office and Service Building system that is maintained at proper temperature and humidity levels. In addition, a separate air conditioning unit, supplying the M&TE room only, maintains environmental control of the room.
Completion Target Date: Completed.
h LONG BSLAND LJGMTING COMPANY Mr.. Thomas T. M2rtin February.10, 1983 J - Ppge Seven IX. Item: No. 322/82-34-23 para 10.4.1 Issue: QA record files not properly controlled (Open)
Response
.The inspector was concerned that access to QA record files in an interim storage area was not adequately controlled. Since that time, the QA record files have been significantly reduced at that location, and they will be eliminated entirely when Records t Management SR-2 has been relocated to the Office and Service Building.
. Station Procedures SP 12.008.02 and SP 12.008.04 have been revised to reflect direct input of Plant Staff records into SR-2.
Approval and effective dates are pending.
Completion Target Date: April 15,.1983 i
e X. Item: No. 322/82-34-01 para 4.2.3.3.2 Issue: QAP-S procedures need to clarify use of words "should".and "may" and more clearly describe requirements and activities (Open)
Response i-LILCO has carefully reviewed the use of "should" and "shall" in the past. In response to the NRC's request, however, the LILCO QA Department and OQA Section are reviewing and will continue to review the OQA procedures and instructions for possible clarity in i the use of the words "should," "shall," and "may. " In addition, i the procedures will be reviewed for. proper references and consistency with terms used in QAPs.
m' i If further revisions are prepared, they will be distributed for comment to the Plant Manager and the QA Department Manager in accordance with-QAP-S-05.2, " Operational Quality Assurance (OQA) 3 Procedure Development." If necessary, the procedures will be revised in accordance with QAP-S-5.2.
L Moreover,. LILCO has already reviewed each of the procedures specifically listed in 4.2.3.3.2. In. sone instances, LILCO is making
. changes from permissive to mandatory language for clarity and in some instances there will be no changes. Even in those instances where LILCO.has decided to make changes,the changes do not affect the ways i the procedures had .been interpreted and implemented. In each of the instances where a change was made from permissive to mandatory
' language, there was no regulatory requirement, FSAR commitment or QA -Manual commitment that required the use of the mandatory language.
The changes were voluntarily made by LILCO to enhance clarity.
Completion. Target Date: March 31, 1983 f.
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- LONG ISLAND LIGHTING COMPANY
. Mr. Thomas T. Martin February 10, 1983 Page Eight XI. Item: No. 322/82-34-11 para 6.4.1 Issue: Maintenance program procedures not adequate (Open)
Re sponse LILCO takes exception to the finding that maintenance program procedures are inadequate. LILCO believes that the procedures adequately implement the maintenance program. The maintenance program complies with ANSI N18.7-1976 paragraphs 5.1 and 5.2.7.1 by use of the Maintenance Work Requests (MWR) Program, SP 12.013.01.
This Program includes detailed maintenance planning allowing evalu-ation of the use of special processes, when necessary, and the use of proper equipment and materials in performing the necessary tasks.
This program also allows for an assessment of maintenance-related potential hazards to personnel and equipment.
The Program is a computerized, state-of-the-art process, using on-line CRT displays that allow prompt access at various plant locations, including the Control Room. This allows constant monitor-ing of on-going maintenance activities throughout the plant.
Each safety-related MWR, prior to action, is reviewed by the relevant Section Head, the Watch Engineer, and OQA Engineer.
This ensures the use of proper procedures in performing the maintenance.
The inspector notes in paragraph 6.4.1 that maintenance procedures do not adequately define:
(1) Types of documents to be assembled in the work package.
(2) All pre-planning considerations which must be addressed by the maintenance coordinator (e.g., such as pre-planning checklist)
(3) Definition of the types of maintenance activities which can be performed without a procedure (Although the MWR makes this evaluation, it does not provide a basis on which the decision is made)
(4) Criteria for determining which housekeeping zones are applicable to specific types of maintenance activities (Although the MWR provides for selecting a housekeeping zone, neither the 'tSVR procedure nor the housekeeping pro cedure (SP 12. 02 3. 01) provides a basis for making this decision)
LONO BSLAND LIGHTING COMPANY Mr. Th:mac'T. Martin February 10, 1983 P, age Nine (5) Criteria for maintenance of system cleanliness and for cleaning and/or flushing of systems (These criteria are specified in SP 12.023.02; however the MWR does not refer to this procedure)
(6) Definition as to what documents will be incorporated into the final maintenance activity record (Currently SP 12.013.0 states that the maintenance record consists of the MWR and associated documents used for performance of the work, but it does not define these documents)
Response to Items (1) and (2) above:
Since the MWR is the authorization document, all work procedures, inspections, and permits are assembled with the controlling document.
Step 22 of the MWR form requires the identification of specific work procedures. In addition, the MNR form provides a pre-planning checklist that requires, among other things, step-by-step consideration of procedures, permits, inspections, and tagging that may be required to perform the described maintenance-related task. Qualified maintenance personnel, knowledgeable in both
, administrative and maintenance procedures and maintenance / repair techniques, engage in this step-by-step process.
In addition, in compliance with SP 12.013.01 the information detailed on the MWR is reviewed by section supervision prior to the assignment of the work. Upon assignment and receipt of the MWR package, the foreman is responsible for reviewing the package and all pertinent data, plans, and schedules. He is also responsible for notifying all relevant sections of the maintenance scheduling and personnel assignments.
OQA reviews this entire process to ensure compliance with both administrative and maintenance procedures. This OQA review is performed for all safety-related MWR's.
Response to Item (3) above:
Various maintenance procedures cover both specific and generic maintenance activities. There are also many potential maintenance activities for which it is impossible to have a specific procedure for each activity or to define each activity that may be
-accomplished without a procedure.
. \
" Lomo esLAmo uownNG COMIENY Mr. Thomas T. Martin
- February 10, 1983 Page Ten Hence, the need ~ for generic procedures. The enormous number' of potential maintenance activities is also the reason for the system to include the flexibility for some activities to be done without a procedure. This practice is consistent with the practice at other licensed and operating plants.
Response to Items (4) and (5) above:
Housekeeping Zones are established by the Maintenance Engineer in order to maintain the cleanliness criteria established by the.ASME Code. The type Zone established, i.e. Zone I, II, III or IV, is determined by the work activity, as defined by the Maintenance Work Request (MWR) .
SP 12.023.02, " Pressure Boundary Integrity and Cleanliness,"
defines the criteria for system cleanliness and for cleanliness /
flushing. These _ criteria are ASME requirements. SP 12.023.01
- " Station Housekeeping," is a checklist item on the MWR and references It is also used to maintain cleanliness and specify
~
SP 12.023.02.
cleanliness criteria established by SP 12.023.02.
Response to Item (6) above:
The MWR serves as a guide for the collection of all
' . documents used in performing the work. The documents used to i perform the work, defined prior to job initiation, are required l by SP 12.013.01 to be included in the final work package. In i accordance with paragraph 10 of SP 12.013.01, support procedures and associated documentation required to complete the maintenance i task may be included. . The MWR will reference these procedures, j In addition, LILCO is currently preparing a nuclear management system control manual. This manual will more clearly delineate the policy and organization that are corporately in place to better understand the expected interfaces between departments and divisions.
In conclusion, it appears that this observation resulted from a misunderstanding by the NRC I & E inspector as to the nature, j scope and purpose of the maintenance program procedures, particularly 1 dhe maintenance work requests. The above information should be adequate to close out this item No. 322/82-34-11.
!. Completion Target Date: April 30, 1983 (for policy and l I
organization portion)
XII. Item: No. 322/82-34-15 para 7.4.1 Issue: I&C program procedures not adequate (Open)
Response
LILCO takes exception to this finding for the following reasons:
r LONG 198 AND LIGHTING COMRANY Mr. Thomac T. Martin February 10, 1983 Page Eleven
- 1. In paragraph 7.4.1, the Inspector states, "I&C does extensive troubleshooting, but there are no procedural definitions as to when corrective maintenance procedures must be used and when troubleshooting without a procedure can be per-formed." To the contrary, LILCO has a mechanism for determining when troubleshooting without a procedure is permissible. All troubleshooting is covered by an MWR. In reviewing the MWR, the work done without a procedure will be reviewed and approved.
- 2. Paragraph 7. 4.1 states further that "many activities performed by I&C are not defined in the procedure.
Based on the above, the inspector considered the activities specified in procedures SP 12.003.01 and 12.013.01 inadequate to define the overall I&C program." LILCO does not agree with this comment in that SP 12.003.01 defines the responsibilities of the I&C Section by specifying the duties of the I&C Engineer. While specific activities are not listed, the procedure clearly indicates that all activities associated with the calibration, repair, and testing of any station instrumentation and controls is the responsibility of the I&C Engineer. Other procedures, job descriptions, and corporate position analysis help define the I&C rzogram.
LILCO is currently preparing a nuclear management system control manual. This manual will more clearly delineate the policy and organization that are corporately in place to better understand the expected interfaces between departments and divisions.
Completion Target Date: April 30, 1983 (for policy and organization portion) l XIII. Item: No. 322/82-34-16 para 7.4.2 l Issue: T.S. related instruments not properly i defined or controlled (Open)
Response
l A draft procedure has been prepared and is presently in the review and comment cycle. It identifies T.S. related instrumentation, specifies calibration requirements, and controls data sheets and subsequent changes.
Completion Target Date: March 1, 1983 XIV. Item: No. 322/82-34-17 para 7.4.3 Issue: IST program not established (Open)
- Response l
l SP 12.027.01, " ASME Section XI Pump and Valve Inservice l Testing Program", under development prior to the I&E Inspection,
p LONG ISLAND WGHTING COMPANY Mr..Thomap T. Martin February 10, 1983 Page Twelve was not yet completed when the inspection took place. The new administrative control procedure, has since been drafted and is now in the review cycle.
The IST procedure currently in effect, SP 21.010.01, "ASME Section XI Inservice Testing of Pumps," will be revised to reflect the requirements of the administrative control procedure.
Completion Target Date: April 30, 1983 XV. Item: No. 322/82-34-19 para 8.4.1 Issue: M&TE program procedure inadequate (Open)
Response
The experience gained during the time that the M&TE Program has been in effect has resulted in minor changes in the program's implementation that have improved the overall quality of the program. Each specific change in implementation was not recorded in a revision to SP 41.003.01 since the overall philosophy and guidance of the procedure was not altered.
A draft revision of SP 41.003.01 has been prepared and is in the review cycle. The revised version addresses the concerns described in paragraph 8.4.1.
Completion Target Date: February 15, 1983 XVI. Item: No. 322/82-34-25 para 11.4.2 Issue: Method must be established to assure T.S.
changes are implemented by station procedures (Open)
Response
At the time of the inspection, LILCO was in the process of establishing measures to assure that technical specification L changes would be implemented by station procedures. Those measures and resolution of this observation consist of three parts:
- 1. NOSD procedure No. 30 entitled "Shoreham Document Control Program" is currently being revised to ensure the control and distribution of copies of the Shoreham technical specifications.
- 2. NOSD Procedure 06 entitled " Maintenance, Revision ,
Approval and Control of License Documents" is currently being revised to describe the steps to be taken to revise or amend the Shoreham technical specifications.
- 3. The Plant Staff Technical Support Group is currently
- writing a station procedure that will provide a l
I I
LONG ISLAND LJGef71NG COMPANY Mr. Thomac T. Martin February 10, 1983 Page Thirteen description outlining the detailed steps taken to ensure that amendments to the Shoreham Technical Specifications will be properly incorporated into applicable station procedures.
Completion. Target Dates: 1. April 1, 1983
- 2. March 15, 1983
- 3. May 1, 1983 XVIII. Item: No. 322/82-34-12 para 6.4.2 Issue: Plant specific training of outside mechanics must be established (open)
Response
LILCO is presently updating SP 31.001.01. The revision addresses the plant-specific training of contractors, mobile maintenance teams, and other outside workers who will be performing maintenance work on plant systems.
Completion Target Date: April 15, 1983.
Very truly yours, M.I M. S. Pollock Vice President-Nuclear cc: Mr. J. Higgins All Parties
,. e'
.. . e STATE OF NEW YORK )
- ss.:
COUNTY OF NASSAU )
MILLARD S. POLLOCK, being duly sworn, deposes and says that I am a Vice President of Long Island Lighting Company, the owner of the facility described in the caption above. I have read the table of unresolved issues and other open items dated January 3, 1983, and also the response thereto prepared under my direction dated February 10, 1983. The facts set forth in said response are based upon reports and information provided to me by the employees, agents, and representatives of Long Island Lighting Company responsible for the activities described in said table and in said response. I believe the facts set forth in said response are true.
MILLARD S. POLLOCK Sworn to before me - this
/ N ' day of N --'t y , 1983.
L Aw @U CDCA LEE CUVEROS Notary Pch::, Chta of flew York f:0. EC-nl:::C3 Quc!!!,cd la f:.::::u Coun*y -
Commiccion expires f. ar. 30,19.[
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