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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
[Table view] |
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J gg LONG ISLAND LIGHTING COM PANY
/##m/ww SHOREHAM NUCLEAR POWER STATION
" P.O. BOX 618, NORTH COUNTRY ROAD e WADING RIVER, N.Y.11792
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December 29, 1982 SNRC-810 Mr. Harold R. Denton, Director
, Office of Nuclear Reactor Regulation
' , U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Safety Evaluation Report Issue No. 8 Dynamic Qualification Shoreham Nuclear Power Station - Unit 1
. s Docket No. 50-322
-' [
Reference:
(1) Letter SNRC-796 LILCO (J.L. Smith) to NRC (H-R. Denton) dated 11/23/82 f
l
Dear M'. .~ Denton :
Ln the above referenced letter, LILCO stated that justifications for int,erim operation for SQRT equipment, whose qualification documentation would not be fully completed by fuel load, would be subalitted by December, 1982. In accordance with that letter, please' find enclosed ten (10) copies of justifications for interim operation for both NSSS and BOP equipment. This information is being submitted in order to facilitate the NRC's staff review and clusaout of SER open issue number 8.
Attachment 1 is a complete listing, by specification and equipment mark number, of equipment for which justifications for interim operation have been provided. Justifications have not been pro-videc' for all outstanding equipment items since LILCO anticipates obtainiaq full qualification documentation for those items prior to fJel load.
k R301040314 '821229 I I
Io FOR ADOCK .05000322 g PDR 1 I - .
J
December 29, 1982 Mr. Denton Page 2 In accordance with R.L. Tedesco's letter to LILCO, dated January 23, 1981, four (4) copies of this submittal are being forwarded directly to Dr. Morris Reich at Brookhaven National Laboratory.
Very truly yours,
)
. L. Smith Manager, Special Projects Shoreham Nuclear Power Station WVB:jm Enclosure cc: J. Higgins All parties Dr. M. Reich (4)
J. F. Etzweiler i
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A'ITIGFlTP 1 JUSTIFICATIG;S FOR IITTERIM OPERATIa1 BOP Scog: .
Sill'-475 ID21*IHLll7A,B Sill-492 1Z93 *PCV010.'\,B 1T48*PCV143,A,B,C,D lT48"PCVl44A,B 1T48
- PO'14 3A, B ,C, D lT48*PCV146A,B NSSS Ecope SDV Solenoid Valvo 1Cll*SCN044 SDV Vent & Dra.in Valves ICll*AOV081/82 IIPCI Turbine 1E41*TU-002 Pater Innge l'onitor Panel lilll*PNL-608 In-Vessel Rick 1FlG* PIE-09
i INIERIM JusunrATION Mark No. 1D21*PNL ll7A,B Conpcrient Name lE Cabinets Systen Name Ibdiation Monitoring Vendor Kaman Instrumentatio'n Spec. No. SH1-475-1.1 Model No. KE-CRC Quantity 2 EQUIPMENT le>.mitMENIS Hot Standby -- - Cold Shutdown Both Neither X ,
Other )( Operation / Post Accident GJALIFICATIN SWbMRY The equignent is scheduled to be seismically tested in January 1983 -
at Acton Environmental Iabs with final test reports due in April 1983.
CD@ONEt7f SAFETY FUNCTION
\' Ccrnponents in these cabinets are not used to achieve safe-shutdown i
nor to mitigate the consequences of an accident. bbnitoring caponents located in these cabinets are used to estimate and evaluate the real or potential radioactive effluent releases and are Reg. Guide 1.97 (Rev. 2) nonitors. Ccxnponents for the High Range Area Radiation Monitors and the Post Accident Effluent bbnitors are located on these cabinets.
Ccrnponent Fhrk Number Cabinet Name .
1D21*PNL ll7A A 1D21*RIS 085A Rateneter 1Dll*RIS 134A Kerdc 1Dll*RR 502 Reccxder 1Dll*E/S ll7A Power Supply (for Recorder) 1Dll*E/S ll7B Power Supply (for Rateneter)
Isolation bbdule Digital (2)
Isolation bbdule Analog (2)
- _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -_ a
1 Couponent Mark thanber Cabinet ,
Name 1D21*PNL ll7B B i 1D21*RIS 085B Ratemeter 1Dll*RIS 126A Keric 1Dll*RR 503 -
Recorder 1Dll*E/S ll7C Power Supply (for Recorder) 1Dll*E/S ll7D Power Supply (for Rateneter)
Isolation Module Digital (2)
Isolation Module Analog (2) .
FAILURE CNSEOUENCE AIRLYSIS Failure of a cornponent in one channel would not affect the operaticn of other channels located within the rnh1 net. Each channel is mechanically isolated by barriers and electrically separated by being individually fused with Class lE fuses. Independent canpanent/
channel fusing protects lE power fran damage in the event of short circuiting within the canponents.
In'the event of failure of the High Range Area Badiation Monitors, samples of the containment atmosphere can be obtained using the Post Accident Sampling Systen and analyzcri to estimate extent of core damage. In the event of failure of the Post Accident Effluent
&nitors' components located in the lE cabinets, local iMir'ation and/or grab samples with analysis can be used to estimate releases.
JusnnCATION SIDNAIE The seismic failure of the components on these cabinets would not degrade the safety function of any other component required for safe-shutdown or for IOCA mitigation and would not mislead the operator. In addition, the Post Accident Sampling Systen can be -
usal in assessing the extent of core damage and local indication and/or grab samples can be used for rnd1ntion release assessment.
Basal on these considerations, interim plant oparation is justified.
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EQUIPMENT JUSTIFICATION SQRT Mark No. 1Z93*PCV010A,a Component Name Press Control Valve system !!ame Post Accident Monitoring Vendor Circle Seal Spec. No. 492-1.1 Model No. NCRR20-9020 Quantity 2 EQUIPMENT REQUITIMENTS Ilot Standby Cold S.Nutdowri
QUALIFICATION
SUMMARY
These Circle Seal pressure control valves are being seismically tested at Wyle Laboratories. The testing is expected to be complete and the test report and documentation issued by February, 1903.
COMPONENT SAFETY FUNCTION These pressure control valves regulate the pressure of nitrogen gas to the suppression pool level measuring bubbler system, 1Z93*LT012A, B (range: - 90" to normal water level to + 6"). The bubbler system measures level by measuring the hydrostatic pressure at the open end of a submerged tube. A constant nitrogen supply pressure to the bubbler and differential pressure transmitter is required.
FAILURE CONSEQUENCE ANALYSIS These components employ spring-held diaphragms to regulate the pressure at a pre-set amount , which is determined by an adjustable spring tension. The postulated failure modes due to seismic load include spring failure and/or diaphragm rupture.
If the spring failed or the diaphragm ruptured, the valve would lese its ability to regulate and would fail open. If thin happened, the systcm would see the full supply pressure of 100-145 psig instead of the normal pressure of 60 psig. This would cause a zero shift in the level transmitter, but would not over pressure other components or piping in the loop.
In the event that 1Z93*LT012A, B are impaired or disabled, diverse Class IE level instrumentation (1Z93*LT001A,B) can be used as a backup (range: - 36" to normal water level to + 60"). This range is not as low as that of lZ93*LT012A,B but the suppression pool level is not expected to fall below - 36" so the effect would be minimal. These components have been installed to Category I requirements so they will not experience an external failure that would jeopardize other equipment.
The PVC is self-contained, with no electrical connections so the failure of this valve would not affect any Class IE electrical equipment.
JUSTIFICisTION SUE!ARY As indicated in the Failure Conseduence Analysis, diverse methods for measuring suppression pool level exist, wh'ich could bej d sed in the unlikely event of failure of 1Z93*LT012A,B caused by failure of lZ98*PCV010A,B.
It has been shown in the failure conscquence analysis above, that component failure would not affect any Class IE equipment. Hence interim plant operation is j ur,t i fied .
EQUIPMENT JUSTIFICATION SQRT Mark No. 1T48*PCV 143A,B,C,D Component !!ame Pressure Control Valves System Name Pri. Contain. Atmos. Cntrl. Vendor Circle Seal Spec. ?!o. 492-1.2 Model No. NCRR20-9020 Quantity 4 .
EQUIPMENT REQUIREMENTS Ilot Standby _ Cold Shutilown _ . Both _ Neither X Other X (Pbst Accident Monitoring)
QUALIFICATION
SUMMARY
These Circle Seal pressure control valver are being seismically tested at Wyle Laboratories. The testing is expected tc. Je complete and the test report and documentation issued by February, 1983.
COMPONENT SAFETY PUNCTION These pressure control valves regulate hydrogen reagent gas pressure at 25 psig f rom the 2400 psig hydrogen reagent gas bottic to the 11.,/0 3 analyzer panels 1T48*PNL 06AA,B & IT48*PNL OG9A,B. The analyzer systemis^ required for LOCA nitigation and for compliance with Heg. Guide 1.97 FAILURE CONSEQUENCE ANALYSIS These PCV's cnploy a spring-held diaphragm to regulate the pressure at a preset amount, which is determined ny adjustable spring tension. There is a relief valvo on the outlet side of each valve integrally nounted on the PCV.
Possible post-seismic failure modes include a spring failure or diaphragm rupture, I
a stuck open relief valve, and/or a relief valve that failed to open.
If the spring failed or the diaphragm ruptured, the PCV would lose it's ability to regulate and coula fail open allowing full supply pressure through the valve. If the relief valve is operating correctly, this pressure would be vented, preventing damage to the downstream piping or the analyzer panels. However, if the relief valve failed to open due to seismically-induced damage, the downstream piping and the panels would be exposed to gas pressures of 2400 psig, potentially dan. aging them.
If the relief valve stuck open, the hydrogen gas would vent to the surrounding area, instead of going to the analyzers. The area surrounding these PCV's is sufficiently vented, assuring that the escaping hydrogen gas could not accumulate to an explosive concentration.
Any of these #ailure scenarios cevld cause the analyzers to malfunction or fail entirely. In the event that all analyzers are affected, the capability exists to obtain and analyzc grab samples of the containment atmosphere, with the post-accident sampling system.
There are no electrical connections to these PCV's, so their failure would not affect any Class IE equipment other than the analyzers, or any Class IE power supplies.
These items are installed to Category I requ'rements, i so they will not experience an external failure that would jeopardize other equipment.
JUSTIFICATIOII
SUMMARY
If a failure of thes, components disabled the H /03 analyzing system, grab sample 7
capability would still exist. Failure would noti affect any other IE systems or power supplies. Category I installation will prevent any external failure and resultant damage to other equipment. Ventilation is sufficient in the ar2a of these volves so that gross leakage of hydrogen would not reach explosive levelc. Hence, interita plant operation is justified.
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FEMIPIRE JUSTIFICATION SQIT Fark Ib. 1T48'PCVl44A,B Component Name Press Control Valve System Nano Pri.Contain. Atnos. Cntrl. Vendor Circle Seal Spec. Ib. 492-1.3 Fbdel No. NCRR20-9020 Quantity 2 -
EQUIPPENT RDOUIREMDUS Ilot Standby Cold Shutdown Both Neither _.2L._
Other (Post Iccident bbnitoring)
OUALIFICATION SUWARY.
These Circle Seal pressure control valves are being seisntically tested at Wyle Laboratories. The testing is expected to be ecnplete and the test report and docum2ntation issued by February,1983.
COMPONErF SAETm' FUNCTION These pressure control valves regulate hydrcxJen calibration gas pressure at 25 psig from the 1100 psia hydrogen calibration gas bottles to the 11/0 2 2 analyzer [uncls, lT48*PNL 06dA,B & 1T48*PNL 069A,B. The analyzer systen is reluiral for IDCA mitigation and for (YJapliance with Reg. Guide 1.97.
FAITURE CONSEOUENCE ANAIXSIS These PCV's c: ploy a spring-held diaphragm to regulate the pressure at a pre-set arount, which is determincd by adjustable spring tension. There is a relief valve on the outlet side of each valve integrally nounted on the PCV.
Possible post-seismic failure nodes include a spring failure or dia-phragm rupture, a stuck open relief valve, and/or a relief valve that failed to open.
If the spring failed or the dialdu aga ruptured, the PCV would lose its ability to regulate and could fail open allowing full supply pressure tluccuqh the valve. If the relief valve is ooerating correctly, this pressure would le vental, ncevcntir. m caqe to the Cownstre:n. piping or the analyzer puiels. I lv..'ever , if the relief: valve failcd to open due to
4 seismically-induced damage, the downstream piping and the panels would be exposed to gas pressures of 1100 psig, potentially damag-ing then.
If the relief valve stuck open, the hydrogen cali'> ration gas would vent to the surrounding area, ins' cad of going to the analyzers.
The area surrounding these PCV's is sufficiently ventcxl assuring that the escaping hydrogen gas could not accumulate to an explosive concentration.
2 Any of these failure scenarios could cause the analyzers to malfunction .
or fail entirely. In the event that all analyzers are affectcd, the l' caInbility exists to obtain and analyze grab samples of the containment atmosphere, with the post-accident sampling systen.
There are no electrical connections to these PCV's, so their failure
.l would not affect any Class lE equipment other than the analyzers, or i any Class lE PJaer supplies.
i
- '1hese items are installcx1 to Category I requirements, so they will not
- experience an external failure that would jeopardize other equignent -
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! JUSTIFICATION SIM ARY 4
If a failure of these comI:enents disabled the 11/02 2 analyzing systen, i grab sample catubility would still exist. Failure would not affect any other Class lE systems or pruer supplies. Category I installation j will prevent any external failures and resultant damage to other equiI r i
ment. Ventilation is sufficient in the area of these valves so that gross leakage of hydrogen would not reach explosive levels. IIence, interian plant operation is justified.
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i EQUIP!ENT JUSTIFICATION .
SORP R1rk Ib. 1T48*PCV145A,B,C,D Cauponent Name Press. Control Valve Systcm Mane Pri. Contain. Atnos Cntrl. Vendor Circle Seal Spec. No. 492-1.4 f bdel No. NCRR20-9020 Quantity 4 .
EQUIPMENT REO'JIPSH7PS Ilot Standby (bld Shutdown Doth Neither__X__.
Other (Post Iccident Ibnitoring)
QUALIFICATION SU M I These Circle Seal pressure control valves are being seismically testcd ,
at Wyle laboratories. 'Ihe testing is expected to be cceplete and the test report and docunentation issued by February 1983.
COMPONENT SAFLTI FUNCTIOd These pressure control valves regulate reagent gas pressure at 25 psig from the 2203 psig oxygen reagent gas bottles to the H2 /02 analyzer systen which is required for ICCA mitigation ard for compliance with Reg. Guide 1.97.
FAIIURE CONSEQUEtK'E ANALYSIS l I
1 These IW's cq1oy a spring-held diaphragm to regulate the pressure at a j pre-set annunt, which is deterntinal by adjustable spring tension. There !
I is a relief valve on the outlet side of each valve integrally nounted on the PCV.
Possible post-seis:nic failure neden include a spring failure or diaphrac;m rupture, a stuck opea relief valve, and/or a relief valve that failo-1 to l open.
I If the spring fciled or the diaphragm ruptured, the PCV v.ould lose its ability in regulate, and could fail open allowing full supply pressure through t he valve. If the rolief valve in operating correctly, this prer .m wald Le vented, prewntlna av. ale to the dmnstream piping or the analy/cr pnels. I!cwe/er, if the relief valve t'ailtd to open due to
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1 seismically-induced danage, the downstream piping and the panels would l- be exposal to gas pressures of 2200 psig, potentially damaging thm.
j If the relief valve stuck open, the oxygen reagent gas would vent to i
the surrounding area, instead of going to the analyzers.
l Any of these failure scenarios could cause the analyzers to malfunction or fail entirely. In the event that all analyzers are affected, the capability exists to obtain and analyze grab samples of the containment atnosphere, with the post-accident sampling systm.
'Ihere are no electrical connections to these PCV's, so their failure .
would not affect any Class 1E equiprent other than the analyzers, or any Class lE pcuer supply.
l These itms are installed t$' Category I . requirements, so they will not
! experience an external failure that wo,uld jeopardize other equipuent.
l JUSTIFICATION SUWARY If a failure of these components disabled the 11 2/02 analyzing system, grab sample capability would still exist. Failure would not affect any other Class lE systms or power supplies. Category I installation will l prevent any external failure and resultant dannge to other equipnent.
Ilence, interim plant operation is justifio3.
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EQUIPb223 JUSTIFICATION SORT bhrk No. lT48*PCVl46A,B Component Name Press Control Valve System Narre Pri. Contain. Atoms.Cntrl. Vendor Circle Seal Spec. No. 492-1.5 bbdel No. NCRR 20-9020 Quantity 2 -
EQUIPMEB7P REQUIRF167fS Hot Standby Cold Shutdown _ Both Neither _ X Other (Post Iccident bbnitoring)
OUALIFICATION SUteARY These Circle Seal pressure control valves are being seismically tested at Wyle Labaratories. The testing is expected to be complete and the test report and docunentation issued by February 1983.
CUTCXMF S7 Jim' FLUCTION These pressure control valves regulate oxygm gas pressure at 25 psig from the 2200 psig oxygen calibration gas bottles to the H 2/02 analyzer Innels, 1T48* pNL 068A,B and IT48*PNL 0691s,B. The analyzer system is require 3 for I(JCA mitigation and for ccmpliance with Reg. Guide 1.97.
FAILUPS CONSEOUENCE IM\INSIS i
These PCV's cnploy a spring-held diaphracm to regulate pressure at a pre-set anount, which is detemined by adjustable spring tension. There is a relief valve on the outlet side of each valve integrally nounted on the PCV.
Possible post-seisntic failure trades include a spring failure or diaphragm rupture, a stuck op'n relief valve, and/or a relief valve that failed to 01cn.
If the spring failcxl or the diaphragm rupturcx1, the PCV muld lose its ability to renulate, and muld fail opon allc'.s'ing full r,upply pressure j through the va}ve. ]f tha relief valve is operatina corrcctly, this l pressure wahl be ventcx1, pre- ating damge to the dc;*.astream piping or l
o the analyzer panels. However, if the relief valve failed to open due to seismically-induced damage the downstream piping and the lunels vm]d be exposed to gas pressures of 2200 psig, potentially danuging thcm. If the relief valve stuck open, the oxygen gas would vent to the surrounding area, instead of going to the analyzers.
Any of these failure scenarios could cause the analyzers to mal-function or fail entirely. In tha event that all analyzers are affected, the capability exists to obtain and analyze grab samples of the containacnt atnosphere, with the post-accident sampling -
system.
There are no electrical connections to these PCT s, so their failure would not affect any Class lE equipnent
- other than the analyzers, or any Class lE power supplies.
These itcsns are installed to Category I requirements, so they will not experience an external failure that would jeopardize other equip-ment.
JUSTIFTCATION SUDRRY If a failure of these components disab1cd the H 2/92 analyzing systcm, grab sample capability would still exist. Failure would not affect any other Class lE systcns or pcraer supplies. Category I installation will prevent external failure and resultant damage to other equipment.
llence, interim plant operation is justified.
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JUSTIFICATION FOR INTERIM OPEPATION IWE: SDV Solenoid Valve MPI/ MARK NO. : Cll-F009/lCll*SOV044 SAFETI FUNCTIQ4:
'Ib open, pennitting air to vent fran the air supply header, thereby closing the CRD vent pnd drain valves.
FAILURE 10 DES:
Fail Open (deenergized) X Fail Closo:1 (energized)
Ioss of Po'er X Ioss of Air loss of Pressure Integrity _
Ioss of Structural Integrity Distortion of bbunting An evaluation of the solenoi:1 valve, and the control rod drive hydraulic control systan in which it is used, showc that the only credible failures which affcct this nonnilly closed valve's afety functions are " fail open" and " loss of power". Other failures i."e judged by General Electric to not be credible under worst case dynamic lt %i.ng conditions, or are subordinate to " fail open".
FAIUJRE EITIrP:
A. Effect on Prinnry Use Valve fails open, and hence safe, on loss of pcrer, permitting air to vent inn the air supply header. This closes the SDV vent and drain valves.
B. Secondary Effect Water accunulation in the SDV instrument volume.
DISCUSSION AND CONCLUSION:
The SDV solenoid valve is designed to fail safe on loss of power facilitating closure of the vent and drain valves. This is considered to be the only credible failure mode which the solenoid valve can experience. Any water accumulation in the SDV instrunent volune will be. detected by level switches nounted on the instrument volune. If the level exceeds a predetennined setpoint, tle reactor ,
will scram autonut.ically.
Therefore, interim operation with this valve does not pose a safety Inzard.
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JUSTIFICATIGJ IDR INTEIG4 OPEPATIQ4 NNE: SDV Vent and Drain Valves MPL/ MIRK No.: Cll-F010/F0ll/lCll*IOV081/82 SAFETY FUNCTIGJ:
To close, isolating the scram discharge volume fran the radwaste drain syntan.
FAIIDPC IDDES: '
Fail Open Fail Closed X Ioss of Power Ioss of Air X loss of Pressure Integrity loss of Structural Integrity Distortion of Ibunting These valves are air olcratod. Therefore, " loss of power" does not apply. "Ioss of air" causes the valves to close, subordinating this failure mie to " fail closed". Other fallure nodes identifio-1 which could cause the valve to fail open have been evaluated and judgod by Concral Electric to be not crcdible under worst case dynamic loading conditions.
FAIIDIE EFFErf:
A. Effect on Prjnttry Use If the valves fail closcd, there will be SDV water acctmulation.
l B. Socorrlary Effect l None DISCUS 3 ION IND CONCLUSION:
'1hc FDV vent and drain valves are designcd to fail safe on loss of air which is considero:1 to be the on'.y crefitle failure nrde. Imv water acetmulation in the SDV instrtment voltra2 will be detectcd by level switches nounted on the insLrtm2nt voline. If the level excecds a proleterinincd setroint, the reactor will scram autaratically.
Therefore intc.zim plant operation with the SOV valves not fully qualificd is justificd.
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- JUSTIFICATION FOR INTERIM OPERATION NAME: HPCI Turbine MPL/bbrk No.: E41-C002/lE41*'IU-002 SAFETY FUNCTION:
To supply high pressure emergency cooling water to the reactor pressure .
vessel, in order to maintain reactor core temperatures within specifi-cation limits.
FAILURE MODES: .
Fail Open Fail Closed Loss of Power X Loss of Air Loss of Pressure Integrity X Loss of Structural Integrity X Distortion of Mounting X
" Fail open or closed", and " loss of air" are failure modes which are not, by their nature, applicable to this high pressure steam turbine.
The remaining failure modes, however, are credible under worst case dynamic loading conditions.
FAILURE EFFECT:
A. L: 'ect on Primary Use Failures could cause flow rate of emergency cooling water to be less than required to maintain reactor core temperatures within specification limits.
B. Secondary Effect None DISCUSSION AND CONCLUSION:
A HPCI turbine, similar to the Shoreham turbine, has just recently been subjected to a dynamic test which envelopes Storcham requirements.
Preliminary indications are that the turbine performed within RWH:Im:im/130-24 12/1/82
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specification limits both during and after the dynamic. events. These ,
preli.minary indications will be confirmed by post test analysis and reporting of the test data.
Based on the above test, interim operation of the HPCI turbine poses no safety hazard at the Shoreham Plant. In addition, in the unlikely t
event of failure of the HPCI Turbine, alternate EOCS systcras (e.g.
ADS, MIR, Core Spray) are available and would safely shut down the reactor.
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JUSTIFICATION FOR INTERIM OPERATION NAME: ;
Power Range Monitor Panel MPIAMK NO.: Hll-P608/lHll*PNL-608 SAFETY FUNCTION:
Provide purposes.information on power level of reactor for monitoring and control Initiate rod block or scram signals when required.
FAILURE MODES:
Fail Open X '
Fail Closed X Loss of Power X Loss of Air loss of Pressure Integrity Loss of Structural Integrity X Distortion of Mounting X j The PRM panel does not use air or pressure retaining parts. However, all otherconditions.
loading failure modes listed are credible under worst case dynamic FAILURE EFFECT:
A. Effect on Primary Use loss of electrical power would automatically stran the reactor.
Other failures could cause erroneous reactor power level readings leading to automatic or manual control actions different than desired. An erroneously high reactor power reading is fail-safe since the control system will take action to lower power. An erroneously low power reading could lead to control system commands to increase power. However, in this instance there are single
- failure proof backup systems which will automatically scram the reactor.
1 In particular, should reactor power increase to excessively high levels, scram will automatically occur on high reactor pressure. As a last resort, the main s;eam radiation monitors will automatically scram the reactor should they detect high an radiationpower excessive levelsexcursion.
which might result from fuel danage caused by
< Because of built-in redundancy and j electrical reading are low. safeguards, the chances of an erroneous power level I
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B. Secondary Effect
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None -
DISCUSSION AND CONCLUSION: '
The power range monitoring panel has been successfully qualified to IEEE 344-1971 standards. During testing, the panel was subjected to a resonance search followed by single axis, single frequency vibration over a range of 1-33 Hz. Six runs were made, two in each direction at ~
different table accelerations. These six runs were cot:rised of front-to-back at 0.69 and 1.89, side-to-side at 0.69 a d 1.89, and vertical at 0.49 and 1.29 The test data indica *te more than one resonance exists in each of the three orthogonal axes. However, 'since the resonance frequencies are widely spaced, and the second resonance in each axis is at or close to the ZPA frequency rather than in a region of response 2.plification, the probability of multi-mode excitation is low and single frequency testing is acceptable.
IEEE 344-1975 requires the equivalent of 5 OBE tests fcilowed by one SSE test. Although random motion OBE/SSEs were not perfor ed in the P608 test, it might be possible to take credit for the ZPA input frequency sweeps since single frequency tests generally provide rcre severe test response than multi-frequency tests. However, it woulc ba necessary to verify that the test duration was at least equal to the " strong motion portion" of the SSE in order to account for vibration build-up. No data on test duration can be found in the P608 test report and so it appears that the 1975 requirements cannot be verified, even thcugh the test duration was most likely greater than required.
Because of the lack of confirmatory data on test duraticn, and also because of an anomalous power supply failure due to a rechanical arm which physically inpacted the power supply midway throu;h the test, a retest of the H11-P608 panel to IEEE 344-1975 standards is planned.
(The mechanical arm has been redesigned).
The testing performed M date1 demonstrates that the poner range monitoring panel has a high level of seisnic capabilities. Therefore, interim plant operation with the power range monitoring panel not fully qualified to the IEEE 344-1975 standards is justified.
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JUSTIFICAT10fi FOR INTERIM OPERATION HAME: In-Vessel Rack MPLAWM Ib. : F16-E006 /lF16*lFE-09 SAFETY FUNCTION:
Support fuel bundles inside reactor during refueling. -
FAILURE MODES:
Fail Open.
Fail Closed Loss of Power Loss of Air Loss of Pressure Integrity loss of Structural Integrity X Distortion of Mounting X The in-vessel rack is a passive frame type structure. It does not open, close, use power and air, or retain pressure. The only failure modes that are credible under worst case dynamic loadings are loss of st ructural integrity and distortion of mounting.
FAILURE EFFECT:
A. Ef fect on Primary Use Loss of structural integrity, or distortion of mounting, could permit up to four fuel bundles to fall down upon the tcp of the reactor core during refueling, j B. Secondary Effect l None l
i DISCUSSIGN AND CONCLUS10":
The in-vessel rack is used during refueling only, as a convenient i
t in-vessel parking place for fuel bundles. It is not used during the initial fuel loading. Ample time is available before the first refueling cutage to perfonn the required nonlir: ear analysis to qualify the Shorehan in-vessel rack to the SQRT criteria. Even if it is not qualified by the first refueling outage, refueling could proceed without the use of this rack.
Therefore, interim cperation befcrc the in-vessel rack is qualified poses no safety hazard, i
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