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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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, I LONG ISLAND LIGHTING COM PANY f4d'O seawems SHOREHAM NUCLEAR POWER STATION P.O. BOX 610, NORTH COUNTRY ROAD e WADING RIVER, N.Y.11792 December 30, 1981 SN 8 .
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Mr. H. R. Denton, Director T_j JAN 'T1982% E Office of Nuclear Reactor Regulation '94 ga . . 7',
U. S. Nuclear Regulatory Commission ? ;-e _
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Washington, D.C. 20555 ;s O' a'
EQUIPMENT DYNAMIC QUALIFICATION-SUPPLEMENTAL INFOPMATION SER OUTSTANDING ISSUE NO. 8 SIIOREIIAM NUCLEAR POWER STATION - UNIT 1 DOCKET NO. 50-322
Dear Mr. Denton:
References:
LILCO letter SNRC-564 from Mr. J. P. Novarro to Mr. II . R. Denton, May 15, 1981 LILCO letter SNRC-575 from Mr. J. P. Novarro to Mr. H. R. Denton, May 28, 1981.
Enclosed are fifty-six copies of information which supplements that provided by the referenced letters. Four copies of this submittal are being forwarded directly to Dr. Morris Reich at Brookhaven National Laboratory, in accordance with Mr. R. L.
Tedesco's letter to LILCO dated January 28, 1981.
This information is provided in the two attachments describad below:
Attachment 1 Revision 1 dated November 20, 1981 to the "Requalification Plan for Shoreham Equipment."
go ol .t I/ l 8201110012 811230 !
PDR ADOCK 05000322 l E PDR i
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. December 30, 1981 Page Two l
Attachment 2 Response to requests for additional information, as discussed in a telephone conference call among NRC, Brookhaven National Laboratory, LILCO, and Stone & Webster personnel on September 4, 1981.
These responses are also dated November 20, 1981.
Very truly yours,
- J. - L. Smith Manager, Special Projects Shoreham Nuclear Power Station JFE/pd Enclosures cc: J. liiggins Dr. Morris Reich-Brookhaven National Laboratory l
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Attachment 1 Requalification Plan for Shoreham Equipment Revision 1, November 20, 1981 O
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. t Dockct 50-322 Shorgham Equipm:nt Raqualification Plan Dator November 20, 1981 Revison 1 Long Island Lighting Company Page 1 of 6 .
Equipment Mark Number Description -
Scope Schedule 1B21'FE002 Main Steam Flow Element Vendor Qualification By Analyaio 3/82 (N005) 1B21'RV-093 Vacuum Relief Valve - Test Program Undervsy to Address Valve 3/82 Drywell (SH1-175) Capability to Sustain Valve Cycling Lt. ads During LOCA Chugging 1B31*FE010 Recire. Flow Element Vendor Qaulification by Analysis 3/82 (N013) 1B31*MOV-032 Motor Operated Valve - Perform Deflection Analysis to Verify 12/81 (F031) Recire. Discharge Valve Can Be Closed While Being Subjected to Dynamic Loads. This Function is a New Requirement Resulting From Implementation of the LPCI Modification (Removal of Loop Section logic).
1C11*AOV-081 Air Operated Valve - Vendor Qualification To follow System
-082 Hydraulic Control Unit Change Decision (F010/F011) 1C11*RV-096 Relief Valve - Rydraulic Item Deleted Due to System Change (F012) Control Unit 1C11'SOV-044 Solenoid Valve-HCU Yendor Qualification To Follow -
(F009) System Change Decision 1C41'TK-150 Tank - SLC Ferform Dynamic Analysit Using Required. 10/81 (A003) Accumulation Response Spectra or Equivalent Dynamic Loads '
1D11'PNL-021 Radiation Monitors And Vendor Testing To Current NRC 3/82
-022 Panels (SH1-332) Criteria and Mark II Loads
-025
-026 -
-027
-061 '
-062
-067
-068
-069
-80 h
I
l Docket 50-322 SHOREHAM EQUIPMENT REQUALIFICATION PLAN DATE: NOVEMBER 20, 1981 i Revision 1 LONG ISLAND LIGHTIFG COMPANY PAGE: 2 of 6 ,
EQUIPMENT MARE NUI!BER DESCRIPTION SCOPE SCHEDULE I 1Dll'Rh-027 Radiation Monitor- ^ Vendor Qualification By Dynamic Analysis 12/81
! ISO-Nozzle (SH1-332) 1 Ell *P-014 Pump And Motor - RHR Perform Dynamic Analysis of The Pump / Motor 3/82 (C002) Combination To Demonstrate Structural Adequacy and Operability To NRC SQRT Criteria 1 Ell'S-114 Strainer (SH1-148) Perform Dynamic Analysis To Mark II Loads G'
-139 and current NRC Criteria lE21* P-013 Pump and Motor - CS Same as for 1 Ell *P-014 (C002) 3/82 (C001) 1E21*S-05T Strainer (SH1-148) Perform Dynamic Analysis to Mark II Loads O And current NRC Criteria 1E32'HC-053 MSIV L23 HTR Vendor Retesting To MK II Loads and current 2/82 (B001) NRC Criteria 1E32*FT037 Flow Transmitter Perform Analysis To Demonstrate Pressure 12/81 (N053)
Boundary Integrity '
lE41'RDbggg Rupture Disc (SH1-340) Vendor Qualification by Burst Test. O Dynamic. Loads Are insignificant. '
1E41*S-055 Strainer (SRl-148) Perform Dynamic Analysis to Mark II Loads G And current NRC Criteria i 1E41'TU-002 Turbine - HPCI Perform Dynamic Qualification Test on a T/82 (C002) SLailar HPCI Turbine, to current NRC SQRT criteria, and Confira Adequacy of Shoreham Turbine by Similarity. Perform Analysis of Hydraulic Piping. 3/82 1E51*P015 RCIC PUMP Vendor Qualification By Dynamic Analysis 12/81 (C001)
C G signifies completion cf document review equipment inspection and compilation of summary and evaluation and SQRT Form.
Dockst 50-322 SHOREHAM EQUIPMENT REQUALIFICATION PLAN DATE: NOVEMBER 20, 1981 Revision 1 LONG ISLAND LIGHTING COMPANY PAGE: 3 of 6 .
EQUIPMEh:
MARK NUMBER DESCRIPTION SCOPE SCHEDULE 1E51*RD-003 Rupture Disc (SH1-3ho) Vendor Qualification By Burst Test G
-004 Dynamic Loads Are Insignificant.
1E51*S-056 Strainer (SH1-148) Perform Dynamic Analysis To Mark II Loads G And Current NRC Criteria.
1F11*T0 g ) Tool - Fuel Prep Machine Perform Dynamic Analysis To MC II Loads And 3/82 ,
Current NRC Criteria 1F11'TU-008 Tool - General Purpose Perform Analysis, Using Required Acceleration 'G (E0ll) Grapple At bpport Hook.
1F13*SL-001 Sling - Dryer And L ce As For 1F11*TU-008 (E011) 0 (E008) Separator 1F13*TO-016 Tool - Reactor Cavity Same As For 1F11*TU-008 (E011) G (E009) Head Strong Back 1F14*TO-029 Tool - Control Rod Same As For 1F11*TU 006 (E011) G (E002) Grapple 1F15'CRN-009 Crane - Refuel Compare To Similar Equipment Already Found To h/82 (E003) Platform Assembly Be Adequate. If Adequacy Cannot Be shown, Perform Dynamic Analysis. .
1F16*CSK-01 Cask - Defective Fuel Same As For 1F16*RAK-11 (E007) (Coupled To h/82 (E009) Storage 1F16'RAK-10 (E004)
F 1F16'RAK-09 Rack - Fuel In RPV Same As For 1F16*RAK-11 (E007), Seismic Loads 3/82 ,
(E006) Only 1F16"RAK-10 Rack - Control Rod Fuel Same As For 1F16'RAK-11 (E007) (Coupled To 3/82 (E004) Storage 1F16'CSK-01 (E009) :
1F16*RAK-11 Rack - New Fuel Storage Compare To Similar Equipment Already Found To 3/8a (E007) Be Adequate. If Adequacy Connot Be Shown, Perform Non-Linear Analysia.
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00CHET $4-322 REVIS10H 1 SHOREMAN EQUIPHENT REQUALIFICf. TION PLAN DATE: HOVEleE3 20. 1981 LCHU ISLAte LIGHTING C0tFANY PAGEs 4 0F 4
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j EQUIPHENT l HANN ttABER DESCRIPTION . SCOPE SCHEDLA.E i
I 1F14mRAN-025 RACH - POISON CtNITAIM IE0151 PERFORM H0H-L1HEMI AHALYSIS. 3/82
\
1911sTH-450 tat 9( - DRA1H SLR9'e 1
-054 QUALIFICATI0H BY WATIC ANALYSIS. 8 REACTOR SUILDitte (SH1-34tl 1H11mPit.-AC1 PANEL HYDROSEM ORYSEM
-ACE AHALYSIS VEte0R TESTING TO CURRENT istC CRITERIA. TO 3/02 QUALIFY SEVERAt. PANELS (CLASS IE COPFCHENTS)
(Sett-It5 )
1H11mPPt.-408 PANEL-PCHER RANGE (P406l REVIEN DTHAHIC QUALIFICATION TEST CH A SINILAR 12/91 HEUTROH CA8INET TEST PANEL. QUALIFY THE SHOREHAM PANEL BY SIttILARITY.
.1 1HtioPtt.-939 PANELS-SCURCE RANGE IP030) C0tFARETOitECENTTESTAteSH0HADEQUACY 12/01 HOLEITOR/INTERtWOIATE DY SIMILAftITY.* t
-031 RANGE H0HITOR
-032 '
-033 1H50eTN-088 TAtet-RSSVS Ate CRAC 445Al.IFICATION SY STATIC ANALYSIS. 's SURGE ISH1-114)
IP41mPtt.-FX1 FD AUXILARY RELAY .
VEte0R TESTIMB THE CLASS IE ELECTRICAL CODPONENTS 3/tt CABINET (SH1-125) TO CURRENT lerc REQUIREHENTS ;
P 1P91sPS-101 PRESSLNit SNITCH
-008 ISH1-398i vel #0R TESTING TO M II LOAOS' Ate CtNIRENT l#tC 1t/01 CRITERIA.
-909
- ~ 1P4tmPS-St1 PRESSURE SHITCH
-922 (SH1-3443 VEle0R TESTING TO M II LOAOS Ale CURRENT letc 1E/e1 CRITERIA.
-994 IP58ePS-195 PRESSimE SMITCH
-113 iSH1-344i VEle0R TESTING To let II LonOS Are CtstRENT lett 1t/01 CRITERIA.
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DOCHET St-3tt SHOREHAM EQUIPHEHT I;EQUni.IFI*-.tTION PLAN
[.EVISICH 1 BATEt HOVEleE3 24, 1961 LONS ISLAte LIGHTINS COlFAMf -
PACE: 5 0F 4 EQUIPHENT HARN lAABER DESCRIPTION SCOPE SCHEDLLE r
1RZ4mPtt.-111 PANEL-LPCI SIP VEle0R TESTItal TO DM II LOADS Ate 5 1
-lit (SH1-439) CURRENT tetC CRITERIA.
-113 t 1RtteTRS-111X TRANSFER SHITCH-
-11tY LPCI-ATS VEte0R TESTIH8 TO IM II LOA 05 Ate CURRENT 1t/41 l #9tC CRITERIA.
p* ISH1-4303 4
1R43aTH-135 TAIM-FUEL OIL QUALIFICATION BY STATIC ANALYSIS. 8 OAY tSH1-119)
IT48sEXJ-49 EXPAHSIOli JOINT 50 VEtt0R 40ALIFICATIGH ST HYDRO-STATIC TEST. 12/91 HYDROGEN REcotBINER DYHANIC LOADS ARE INSIGNIFICANT.
tSH1-4423 VELAH YOHf3 3" - tea HOV'S ESH1-84V)
- VEte0R SUALIFICATICH BY DYH4111C AHmLYSIS lt/e1 TO DM II LOADS Ate CtmRENT letC CRITERIA.
1/t= - 1 1/t* HDV'S ISH1-214) 12/01 1" - ta SMV'S (SH1-1538 12/91 A/D YOMES 19' - 24* HDV'S (SH1-SSAD) vet 90R QUALIFICATION BY DYtthifIC ANALYSIS 12/41 70 PM II LOADS Ate CtmRENT HRC CIIITERIA.
FISHER YONES Yt" A0V'S (SH1-111) VEteOR SUALIFICATISt BY DY1tAHIC ANAL.YSIS 1t/61 TO PM II LOADS Ate CtatRENT tetC CRITERIA.
It" A0V'S tSH1-172) <
It/81 2" PCW'S ISH1-3101
- 12/01 ta - 4a TCV'S (SH1-310)
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12/81 10" - It" TCV'S ISH1-4233 1t/81 PRATT YCHES 4" - 20" HOV'S (SH1-197)
- VEte0R GUALIFICATIOtt BY DYHAMIC ANALYSIS 1t/91 TO IN II LOADS Ate CURRENT F5tC CRITERIA.
~ GRIPMEL YONES 1" - 4" HOV'S (SN1-203) VEte0R QUALIFICATION BT DYHAHIC AHat.YSIS 1t/91 TO DM II LOADS Ate CtBIRENT HRC CRITERIA. .
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DOCHET 50-322 SHOREMAH EQUIPMENT REQUAl.!rICATIcit PLAtt DATE MOVEteE2 29, 1981 REVIS1tM 1 LOHs ISLAND t.IGHTINS COPFAHT PAGEt 4 0F 4 ROUIPflENT ltARM NtASER DESCRIPIICH SCOPE SCHEDULE TOPES
~
TONES 3/4" - 4* A0V'S (SH1-3141 VEte00 QUALIFICATI0H BT OYttAHIC AHALYSIS 12/81 TO IN II LOAOS Ate CURPENT tetc CRITERIA.
3 4* - 16* PCV'S (SH1-318) 12/81 la LCV'S (SH1-3IS) 1t/61 L!ttITORQUE 3" - 20* IIDV'S (SH1-84WD OPERATORS QUALIFICATION ST DYNAHIC TESTING TO DH II LOADS Ate CURRENT CRITERIA.
2/82 It* - 29' lev'S :SH1-seAOI i
2/82 da - te* Hov'S IS11-1911
'2/82 la - 4* rWS (SH1-tes) 2/82 1/t* - 1 1/2" Il0V'S tSH1-2191 '
2/82 1= - ta lev'S (SH1-tS31 2/82 SETTIS ft* A0W'S ISH1-1111 VEle0R SUALIFICATI0tt BT DYttANIC M4AI.TSIS. 1t/01 OPERATORS
, lea A0V'S 43M1-112) 12/s1
[
t BECH ta PCW'S (SH1-31tl . VEtOOR QUALIFICATION ST OYHANIC TESTING lt/e1 l CPERATORS
' TO IN II LOADS Ate CtNtRENT CRITERIA.
ta - 4" TCV'S (SN1-3101 12/e1 COPES 3/4" - 4" A0V'S (SN1-314) VEICOR QUALIFICATI0ft BT DYHAlfIC TEST!HS It/41 OPERATORS TO IN II LOAOS Are CURRENT CRITERIA.
4* - It* PCV'S ISett-310) (LIIIIT SalITCH Are 30LEtl0109 ' 1t/01 la LCV'S ISH1-310) 4 -
12/91
,,JISHER 19" - It* TCV'S (SH1-423)
OPERATORS VEte04 QUALIFICATION 8T OYttAttIC TESTING 1t/41
~ To tH II LOAOS Ate CURRENT CRITERIA.
l (LIMIT SMITCH Ate SOLEleIDI
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a i Attachment 2 s.
j Responses to Raquests for Additional Information i
j Shoreham Nuclear Poiner Stagion 4
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- November 2d, 1981 i
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1 SQRT Audit Item 8 1C41*P-024 (C41C001), SLC Pump and Mot'or The effects of dynamic coupling between the pump and motor as they may affect operability have been addressed analytically. The attached General Electric Company report, entitled " Interaction Effects Analysis of the SLC Pump & Motor" dated October 29, 1981, shows that dynamic coupling does not affect the operability of this assembly. Furthermore, the effects of dynamic coupling on the required function vill be considered for all similar pairs of equipment. -
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SHOREHAM flUCLEAR POWER STATION
. INTERACTI0fi EFFECTS ANALYSIS-0F SLC PUMP & MOTOR OCTOBER 29, 1981 This documer.t was prepared from a study entitled "Shorehain Coupling Effect Report, SLC Pump / Motor" dated 10/22/81, prepared by P. V. Vo and approved by J. S. Mokri, General Electric Company 4
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An analysis has been perfomed to evaluate the interaction between the Shoreham Standby Liquid Control (SLC) pump and motor. The extent of this interaction was detemined by assuming the SLC pump shaft and motor shaft are disconnected, and then calculating the relative displacement of the shaft center lines when subjected to dynamic and static loads, themal displacement, and initial misalignment.
The results show that the displacements due to both continuous and intemittent loads between the two center lines of the pump and motor shafts do not exceed the allowable limit for cont.inuous loading of the coupling hardware used to join the shaf ts. This result for continuous loading resolves the coupling concerns of the SLC pump and motor for all loading conditions.
RWH:hmc/9H 10/29/81 O
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i The SQRT analysis of the Shoreham SLC pump and motor has previously been perfortned separately for both the pump and motor during the faulted condition. The motor and pump have not yet been dynamically analyzed or tested as a complete assembly for functional operation under all loading i conditions. A static analysis has therefore been performed to calculate
{ displacements of the pump and motor shaft center lines under dynamic and
- static loads to determine whether they exceed the allowable limits of j the coupling hardware which joins the shafts together.
l The calculated natural frequency of the motor is 239 bz and the pump is j
136 hz. The fundamental frequency of either the pump or motor, when attached by the coupling hardware, has been calculated to be higher then
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the 2PA frequency of 100 hz. Therefore, a static approach can be used ;
{ to calculate relative displacements.
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Several physical aspects of the pump and motor that affect the -
calculational method were considered, usir.g conservative assumptions, as i
)
follows:
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- 1. i.oads were considered to be acting in the worst direction; that is, l the hydrodynamic, seismic and nozzle loads were pointed in the same direction (i.ncluding both horizontal and vertical directions) and i
perp1ndicular to the shaft center line.
l 2. The pump and motor were each considered to be a rigid body. '
i Therefore, the total forces were applied at the center of gravity 1 of the pump and motor.
- 3. The stiffness values of the pump 'end motor are much higher than for i the cbupling hardware so that the applied forces acting on the pump '
! cannot be transmitted to the motor or vice v;rsa. Thus, the i analysis can be made separately on the pump and motor.
T 1 4. The most flexible parts of the pump or motor are the legs attaching j
the pump or motor to the base plate. The static deflections of
! pump or motor legs were calculated separately for both the
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i horizontal loads and the vertical loads. Also calculated separately was the linear thermal expansion on the pump or motor legs due to the temperature difference between the ambient
- temperature and the full operating temperature. The total linear 1
nisalignment of the pump and motor shafts, due to the leg ;
deflections, was then determined by adding up the components. I
- 5. The vertical loads can cause an angular misalignment of the shafts due to a deflection of the base plate, assuming that no grout
- exists under the base plate. This assumption is very conservative' l
since the steel mid-supports under the base plate, which have an
! effect similar to grout, were neglected.
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, u The results of the calculations are listed below:
Linear Misalignment Due to applied hydrodynamic, seismic and 0.004 inches static loads (faulted condition) l Due to thennal expansion 0.0004 inches Due to initial misalignment when connected 0.004 inches Total (faultedconditions) 0.0084 inches Ancular Misalignment
- Based on all loads acting on flexible 0.06*
base plates (faulted condition)
The coupling hardware used is a Thomas coupling, Type 226DBZ-A. The installation instructions for this hardware state that the maximum allowable misalignment variatien is 0.012 inches for the coupling to operate continuously. The maximum allowable angular misalignment is 0.5' based on discussions with the coupling manufacturer. .Therefore, it is concluded that the linear and angular misalignments between the ceriter lines of the SLC pump and motor shafts, due to dynamic and static loads, thermal expansion, and initial misalignment, do not exceed the allowable limits of the coupling hardware.-
RWH:hme/91 10/29/B1 .
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. , _ . __ _ _ _ . . _ . . . _l SQRT Audit Item 17 -
1331*ADV-082, Air-Operated Valve l
~
The dynamic accelerations acting at the operators of valves 1831*AOV-081 and 082 were derived from the analysis,of the current piping and support design configuration. Valve accelerations will be confirmed based on an "as-built" review of the piping systems after all support installations are complete.
The SQRT summaries will be finalized upon evaluation of the "as-built" systems.
SQRT Audit Item 18 IE11*PC7003, Pressure Control Valve At the time of the site audit, questions were raised regarding the installa-tion standards for instrument tubing, such as is attached to this valve.
It is our understanding that this issue was satisfactorily resolved with the I
SQRT reviewers at a meeting on September 3, 1981. at Brookhaven National i
Laboratory. The Shoreham instrument tubing installation standard and sup-porting computer calculations were reviewed and found acceptable at that meeting.
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. l SQRT Audit Item AB ._
1Tk6'AOD OkO. Air-Operated Damper Information previously provided regarding the operability of this air-operated damper indicated functional test leakage amounts greater than 6 m. The Vendor has confirmed that this is incorrect. The actual test leak rate was less than 6 seem (meter lower limit) and the marimum allowable leakage for satisfactory actuator operation is 15 seca. The Vendor's revision to its qualification test report reflecting this fact is attached. (3 Pages) 0 4
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t l Stone & Webster Engineering Corp. Date: October 23, 1981 245 Sum =er Street Boston, Massachusetts 02107 Subj ect - Job Name
! Attention:
Shoreham Nuclear Power Station Mr. T. M. Jacobs Unit #1 Lead Control Encineer J.O. #11600.00/P.O. #346920 MCC P0NERS Job No.: .
- , 510-N-5049 Gentlemen: --
~
h*c are sending you C herewith; under separate cover the following items: '
Three (3) copies of Revision A to Wyle Laboratories Report
$44540-1 (10/8/81) for the environmental qualification of safety related instruments and devices for the Shoreham Station.
1 l
These are submitted C for approval; C for your use for correctien.
Remarks: 1. Please discard the pages involved and replace wi'th the attached revised pages. .
Reference:
E. J. Brabazon (S&W) le Eter to W. A. Roberts (MCC Powers) dated September 9, 1981.
MCC POWERS TRANSMITTAL NO. P-llo Please address your reply to: MCC POWERS
, cc: Mr. R. Plant (S&W) 0 West Fargo Avenue
, Mr E. J. Brabazon (S*W) 60077 Mr. C. C. Klapes -(S&W-w/ encl)
J. A. Harmon Attn: E. R. Tagare I
W. A. Roberts J. Hartgenbush Telephone 312/677-9580 File
- MCC POWERS A UNIT OF MARK CONTROLS CORPORATION
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TABLE Il
SUMMARY
OF FUNCTIONAL TESTS AND OPERATIONAL CllECKS (CONTINUED)
FUNCTIONAL T'E $ T $ OP[8611pMAL CilFCES .
Results. Post- Post- Post-Dasellne Final Aging, Radiat5on Selsmic Test item hequirements Section i Sec.ilon IX Sect. Ill - Sect. V, Sect. VII A femperature Transmitter o 4.66 1 15 VOC output across Barber-Coleman Co., terminals "TXI" and " CON" with '
TSP-8101 1000-ohm resistor across both "lSA
(item No. 15T terminals. 4.73 VOC 5 90 VOC j Xi X X o Less than l VOC output across terminals "TXI" and "COM" with j Jumper across both'"lSA" terminals .28 VOC .21 VOC -
I o 4 VOC output across "0Pl" and '
"COM" with Jumper across "4" and "5". ~
4.33 VOC 4.3 VOC-I o Less than I VOC output across "M+" ,
I and "H " with Jumper across "4" and "5". , 1.997 VOC 1 96 VOC Q*a o More than 11 VOC across "TXI" and IE "C0H" with "lSA" terminals open. 13 22 VOC 12.82 VOC g.
f~ o less than 2 VOC across "0Pl" and h(
j "COM" with "lSA" terminals open. l.45 VOC l.40 VOC .
.?
Electric Actuator, o When actuated, did shaft turn Raymond Control smoothly through 90*f Yes Yes X X X
$ Y 'I*** R-24 g "[*'g
, o Verify return to original position when power removed. Yes Yes o Output torque should be 300 1 IS Inch pounds. 834 In-lb 775 in-Ib s
(See N0A #1, Ap i. I,Section I.)
o inlet pressure at which shaft @
Air Cylinder Actuator, ,
G begins to rise. ,
22.5 psi 23 psi ~
Centerline, Inc., X X X 32046-6 o Pressure must be 55 + 5 pel at '
3 (Item No. 17)
=
, 3 3/4" stroke. 56.5 pel 55 psi o Leakage must not exceed ISsece <6 seem (meter A'
<6 seem (meter at 80 psi. , ,
lower;llelt) lower limit)
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SQRT Audit Iten: A9 _
1Tk6* MOD-035. Motor-Operated Damper This motor-operated damper is mounted on a support frame which has a cal-
,._,_._._ culated fundamental _ frequency of 24 Ez. Therefore, the input acceleration ~ ~ ~ ~ ~ ~
i for damper stress and deflection calculations should be obtained from the greatest value of floor spectra at 24 Ez and above,.and with a multimode i
factor of 1 5 applied. Review of the Vendor's analysis shova adequate
-.. margins in the blade stress and deflection under these loads, i.e., 1.5 ~-
times the spectral acceleration at 24 Ez.
- Revised pages of the SQRT and Summary and Evaluation forms are attached reflecting the correct required acceleration loads and the associated minimum margin- of safety. . . . .
O
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.. QUALIFICATION SIDefARY AND EVALUATION .
4 l 1. Component Name Volume Control Demoers including Electric Operator and Limit Switch i
i
- 2. Mark Numbers IT46*F.OD-034 A&B -
) 3. Qualification Documentation i.
! A.
)i Qualification Sumary of Equipment (SQRT form). including required response spectra if applicable.
- Raclosed. -
1 i
B. Reference Documents in the Central File Package J !
j Referance Document Revisico.
Number Identification or Date Organization / Title / Subject 1 AMV Model Revision 0
> American Wruing and Ventilati: g DAA-P-7402 29 March 77 Seismic Analysis Report 2 Uyle Report l . . No. 44340-1 24 June 80 Wyle Laboratories (Huntsville)
-- 3 Wyle Report i
No. 44057-1 30 May 78'
! C.' Additional Supporting Documents not in taa Nuclear Environmental Qualification Central Tile !?ackage I Reports.
j Document Revision
- ID No. or Date Organization / Title / Subject i .
- SNRC-535 March 5, 1981 LILCD Seismic Qum7Hication Review - response to Raquest for Additional Information, Response 271.4 SEl- 319 Revisimi 3 Stone & Webster specification for automatic 6 March 81 temperature contral-systems for heatings ventil-
{ ating, and air conditioning.
l 4. Shoreham Requirements (dynamic loads, functional requirements) 1 The l'0D is used to control secordary enntaineert air tempe ature and volume and j must function after a faulted event. -
. . . The subject eqdipment must be capable of withstanding the combined horizontal .
and vertical loadings for the upset and faulted conditions as described in Ref. 3.A.
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- 5. Demonstrated capability (from qualification report) -
- 1. The seismic smalysis report for the mechanical portion of the damper demonstrates that
', the calculated stresses and deflections are significantly less (margin of safety > 3 9) than the specified allowables for .75g horir.ontal and .513 vertical upset and faulted
- 2. The seismic test reports for the electric operator and limit switch demonstrated ac-ceptability to acceleration levels higher than these specified by the horizontal and vertical 3RS. Post-paismic functional testing wcs performed. No salfunction or spurious operation were evident. -
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- 6 Rationale fer Qualificstion j ,
iSRI-319 i .
- c. Appracch (analysis, test, bath) Item (2) i L __....
1.. Qualification of,dcapers was by static analysis utilizing hand calculation methods to l____ deteraire frequency (and associated g-value) and resultant stresses. Blade deflectionst 4
cicarances were calculated.
i j 2. Quclification of the electric actuator and limit switch was by biaxial multi-frequency random m.otion tests, as:plitude controlled et 1/3 octave bandwidths over the range of
~
f i to 250 Mr. Randw signals were simultaneous and independent (phase-incoherent).
i The limit switch was subjected to 5 CBE and 2 SSE tests in each orientation. The electric actuator waa: subjected to 6 SSE tests in each orientation. Low-level resonanes
- search tests were employed.-
i b. Response to Loads (including high-frequency considerations) 1 1. ,.
j The mechanical portion of damper is anlayzed to .75g horizontal and .51 vertical ,
.versus a required 2.0g horizontal and 1.5g vertical for faulted conditions. (obtained c--- ' by applying a smilti-mode factor of 1.5 to the RRS of Raf. 3.A. at frequency of -~
' damper = 241!:.)- Since r:argins of safety identified by stress analysis are high.
j' (3.9), the damers are considered qnmitfied td these standards. . .Natur&1* Frequency of the blade = 630 Hz (Raf. 3.B.1). Therefore, the blade stiffness, when coupled .
with the support stiffness does not result in a lower overall natural frequency.
The g loading at the base'can be also used in the damper blade analysis. Margdn j ' of aafety is based on far.ited loads & upset allowables. '
1 1 2.
{
The electric operator and limit switch are also qualified vtth high asrgins of sefaty as the testing input used for both the horizontal ZPA and vertical ZPA
{
was 5 g's compared to a required .6g's as shown by RRS .in Raf. 3.A. Also, the electric actuator was subjected to a conservative number of SSE level tests (6 SSE levels). Therefore, the operator and limit switch exceed the requirements of these standards.
, - - - - ~ ?
j c. Operability * .
j
- 1. Operability of the dnaper is demonstrated by a deflection analysis of the damper blades j
4' which shout a deflection of 0.0 inch versus a .028 inch allowable.
j
- 2. The electric operator was electrically energized'and monitored for any change in state.
The limit switch was monitored for contact chatter / spurious operation (approx. 2msecs).
} Testing results including post-test results verified functional capability to these
! standards.
j .
- d. Fiald vs Qualification Mounting .
All bolting pceterns/ hole sizes utilized for testing the operator ard limit switch are the same as the field mounting. The damper assembly, limit switch mountieg bracket and blade
- j operator .aounting bracket qualif1' cation mountings are the same as the field mounting. . -
Reviewer's
Conclusions:
Based on the vendor's stress analysis report (Ref.1) aad subsequent test report (Raf. 2 & 3), it is concluded that the volume coatrol dampers will perform the required function, as describ.id, and thereby meets the 'equirements specified for the combi .ed hydrodyncaic crJ seismic loads.
8
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SH1- 319 Item ( 2 )
III. Is Ecuipeent Available for Inspection in the plant: [I] Tes [ ]No IV. Equipment. Qualification Method:
[1] Test [ ] Analysis [ ] Combination of Test and Analysis Qualification Report *: h4 ,,.4 e t..+ . ,,, wu e.~...a N'urments (No. Title and Date) 44540-1 LIMIT SWITCH 6/24/80 Coarpany that Prepared Report: Vvle Labs Ccapany that Reviewed Report: MCC Powers V. Vibration Input Required:
I. Loads considered: a. [ ] Seismic only
- b. [ ] Hydrodynamic only
~
- c. [I] Combination of (a) and (b)
- 2. Method of Combining RRS: [] Absolute f,um g] SRSS [ ~~I
'(other, specify)
- 3. Required Response Spectra (attach the graphs): I
- 4. Damping Corresponding to RRS: Upset 25 Faulted AI
- 5. Required Accelerat' ' in Each Direction:[]ZPA [I] Other> ARS S 24HZ x 1.5 (specify)
~
Upset S/S = 1.5 F/B = 1.5 V= 1.0 Faulted S/S = _ 2.0 F/B = 2.0 V= 1.5
- 6. Were fatigue effects or other vibration leads :onsidered?
[I]Tes [ ] No If yes, describe loads considered and bow they vere treated in overall qualificatf.on program: To the extent t 4m1 ed by im.w.197q
- NOTE- If more than one report, complete Items IV through VII for each report.
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4 SH1- 319 Item ( 2 ) _.. _ .. .
VII. If Qualification by Analysis, then complete
- 1. Method of Analysis:
[ ] Static Analysis [I] Equivalent Static' Analysis
[ ] Dynamic Analysis: [ ] Time-History [ ] Response Spectrum 2... Natural Frequencies in Each Direction (Side / Side, Front /Back, Vertical):
I. . ..
S/S =__ >60 Hz F/B = > 60 Hz V= # 60 Hz ._
- 3..-.Model Type
- []3D [ ]2D [ ]lD
[]FiniteElement
~ ~
[] Beam [X] Closed Form Solution
- 4. [ ]Compurer Codes
- N/A Frequency Range and No. of modes considered: N/A
[X]HandCalculations -
4
- 5. Method of_ Combining Dynamic Responses: [3AbsoluteSun [)SRSS Algebraic t {I]Other:
(specify)
Sa.Inhtg-level: thset E .75 y .51 Faulted E .75 Y .51 i
i
- 6. Damping: Upset 21 Faulted I.% Basis for the damping used: RGl.61
- 7. Support Consideratiosa in the model
- Service Conditions
- 8. Critical Structural Elements:
A. Governing I,oad Service Total
- Identification I,ocation Stress 4 or Response I,evel Stress Allow
. All Stresses well below allouable (Factor of Safety 3.9)
Based on using recuired e = 2.00 =2.67 Horj M = 2.94 Ve r impat g .75 51 - - -
, _ . . B . _ .. _
Maximim Allowable Deflection Maximum Critical to Assure Functional Deflection I,ocation Operability
. 000" Blade .028" l
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