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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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[ 'T 'o gg LONG ISLAND LIGHTING COMPANY
/MN** SHOREHAM NUCLEAR POWER STATION P.O. BOX 604, NORTH COUNTRY ROAD e WADING RfVER, N.Y.11792 May 12, 1983 Mr. Richard C. DeYoung, Director SNRC-884 Office of Inspection and Enforcement U.S. Nuclear Regulatory Ccmmission Washington, D.C. 20555 NRC Enforcement Action 50-322/EA 83-20
Dear Sir:
This letter is LILCO's response, pursuant to 10 CFR S 2.201, to the violation set forth in the letter from Mr. James M. Allen, Acting Regional Administrator, Region I, to Long Is-land Lighting Company enclosing a Notice of Violation and Pro-posed Imposition of Civil Penalty, 50-322/EA 83-20. A separate letter will address the imposition of the fine as required by j 10 CFR 9 2.205.
I. FACTS While the statement of facts contained in the Notice of Violation is essentially correct, LILCO believes that a review of additional facts presented herein place the circumstances noted by the ISE inspector in a different perspective. The second paragraph on the first page of the Notice of Violation i
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't 8, May 12, 1983 Page 2 states that " data recorded at 15 minute intervals for the two hour period indicated a range of load values from 3500 KW to 3850 KW." While this statement is true, it is important to note that additional data were available and were actually used and relied upon by the Test Engineer in concluding that the test had met acceptance criteria. The cover letter to the Notice of Violation notes the existence of this data, but LILCO believes that an explanation of the nature and use of these data is important to an evaluation of the circumstances constituting the violation.
A high speed chart recorder (Honeywell Visirecorder) was used during the test as required by various oteps in the approved test procedure. In addition, the test analysis report for the procedure describes the calibration and use of the high i
speed chart recorders in collecting and evaluating data. As l
noted in LILCO's March 't6, 1983 letter (SNRC-859) concerning l
this violation (a copy of which is enclosed as Attachment A),
strip chart data were recorded during the two hour load test and the Test Engineer did rely on those data in making the judgment that the acceptance criteria of the test had been met.
The data obtained during the test are presented in the graph l
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', q May 12, 1983 Page 3 entitled " Emergency Diesel Generator Load Test, Emergency Diesel Generator 102 -- Pt. 307.OO3B (Step 8.5.4)." This graph is enclosed as page 10 to Attachment A to this letter. This graph presents load data versus time for the diesel generator two hour test period. Data plotted on the graph were taken from both the control room indicator and from the Visirecorder strip charts. The Visirecorder data show a general load pro-file ranging from a high load of 3975 KW to a low load of 3650 KW. The Test Engineer properly believed the chart recorder is a more precise indication of the diesel generator load. The appropriateness of the Test Engineer's judgment in this regard is confirmed by the fact that the strip chart recorder has now been designated as the primary instrument to be used in all fu-ture load tests of the diesel. The integrated load profile (i.e., total KW hours) shown on the strip chart recorder for the two hour load test represents a load equivalent of more than 99% of the total load that would result from running the diesel generator for two hours at exactly 3900 KW. LILCO believes these facts are important to understanding why the Test Engineer accepted the diesel generator load test results.
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May 12, 1983 Page 4 II. RESPONSE LILCO admits that the facts, including the information provided above, may constitute a violatien. At the same time, however, LILCO believes these facts provide a basis for recon-sideration of the severity level of the violation. LILCO also believes that where, as here, the licensee's review process is still in progress, this fact should be considered in evaluating whether to cite the applicant for a violation. Mr. Allen's cover letter to LILCO states that the guidance relied on to support the assignment in this instance of Severity Level III is contained in Section C.2 of Supplement II of the NRC's En-forcement Policy (10 CFR Part 2, Appendix C). This section defines a Severity Level III violation as a significant viola-tion involving:
Failure to confirm the design safety re-quirements of a structure or system as a result of inadequate preoperational test program implementation . . . .
The Notice of Violation concludes that LILCO's preoperational test program, as implemented, did not assure that testing was performed in accordance with procedures or that test
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requirements had been satisfied. LILCO believes that the additional information presented below demonstrates that this situation does not represent a " failure to confirm the design safety requirements" of the diesel generator, nor does it rep, resent a failure to perform a test in accordance with proce-dure. Rather, the facts reflect a failure to document proper and reasonable judgments made by the Test Engineer and a fail-ure by reviewers to identify this lack of documentation in the i
review process which was still in progress at the time I&E noted this violation. The following factors are presented for NRC consideration.
(1) The design safety requirements of the diesel gen-erator in question were confirmed by the preoperational test which is the subject of this violation. As noted above, the integrated load for the two hour portion of the load test represents in excess of 99% of the two hour load that would be I
achieved had the diesel been maintained at exactly 3900 KW for j two hours. Regulatory Guide 1.108, Revision 1, requires that the preoperational test program demonstrate the full load car-l rying capability of the diesel generators for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, of which two hours must be at a " load equivalent ti the two hour i
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May 12, 1983 Page 6 rating of the diesel. generator." No guidance defines " load equivalent" as that term is used in Regulatory Guide 1.108. In the Test Engineer's judgment, the load profile obtained from the strip chart recorder, which represen~ced in excess of 99% of the integrated two hour load, was a " load equivalent to the two hour rating" of the diesel generator and therefore demonstrated that the test requirements had been met.1/ Thus, the test results. represent a confirmation that diesel generator design safety requirements had been met.
LILCO believes that the Test Engineer should have spe-cifically noted in the test report that the test data observed on the control room load indicator and recorded in Table II of 1/ The term " equivalent," particularly in this context, reasonably connotes more than strict equality or identity; it includes the notion of essential or functional equivalency.
This interpretation makes sense technically because it is not possible to attain the two hour load of 3900 KW without loading the emergency diesel generators on the LILCO grid. Load changes on the grid, which are unavoidable, will cause the die-sel generator load to fluctuate above and below the desired load level. What is important is that the overall results be equivalent to the two hour load rating, though it need not be precisely equal to that rating for the entire two hour period.
The test is, in fact, a better demonstration of generator capa-bility when the unit is allowed to load follow as opposed to operator intervention to maintain near constant 3900 KW load.
May 12, 1983 Page 7 the test procedure did not fall within the specifications required by the test procedure. The Test Engineer's judgment that the strip chart results demonstrated the acceptability of this test should have been documented in the test report. But LILCO also believes that this omission, although it may reasonably constitute a violation, does not merit the Severity Level III designation.
(2) In response to the NRC's initial concerns about the conduct of this test, LILCO agreed to repeat the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> load test for Emergency Diesel Generatur 102. This test has been successfully performed and the results are currently being reviewed. This subsequent test of the diesel generator was "
. conducted using more stringent acceptance criteria than the original test and it resulted in a load equivalent in excess of the two hour rating. A preliminary analysis of these test results indicates that they confirm what had been demonstrated in the original test -- Emergency Diesel Generator 102 does l meet its design requirements.
(3) A significant consideration in determining whether i the facts reported in the Notice of Violation actually i
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e May 12, 1983 Page 8 constitute a violation and, if so, the severity level of that violation, is the status of the review process for the test results. Deficiencies in work or test results that have not received final review are not generally categorized as viola-tions. This principle waa confirmed by recent NRC Staff testi-mony in the Shoreham operating license hearings. Importantly, the facts here demonstrate that this is an instance where the final review had not occurred and, therefore, we are also re-questing reconsideration of the severity level on this basis.
As reported in LILCO's March 16, 1983 letter (Attach-ment A), the review process for the test results in question had not been completed at the time the I&E inspector made his observations. The review process established by LILCO for the preoperational test program consists of reviews by (i) the Test Engineer, (ii) the Joint Test Group, (iii) Operational Quality Assurance, and (iv) the Review of Operations Committee. Each of these groups conducts an independent review. The test results had not been reviewed and accepted by the Plant Staff Review of Operations Committee and, although the test package had been witnessed by an OQA inspector, it had not been finally reviewed by OQA. In LILCO's view, the severity level of the
May 12, 1983 Page 9 violation merits reconsideration in light of I&E's general practice not to cite licensees for violations involving reviews or inspections not yet complete, and the incomplete review status of these test results at the time of the inspection.
The cover letter accompanying the Notice of Violation stated:
It is not clear to us, however, that these additional audit / reviews would have identified the problems. For example, the Chairman of the JTG, which approved the test data, also serves as Chairman of the ROC, and OQA personnel had previously
- reviewed and signed the test procedure.
LILCO believes, however, there is a substantial basis for concluding that these additional, required reviews would have properly documented and dispositioned the discrepancy between the Table II data and the acceptance criteria. First, these are independent reviews designed to ensure that errors and l oversights which inevitably occur in a complex undertaking are l
l identified and corrected. The philosophy reflected in LILCO's l
l review process is consistent with the NRC's traditional view that multi-layer reviews are an effective means of minimizing f
l deficiencies.
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May 12, 1983 i Page 10 Second, there is specific justification for concluding that additional reviews would have been effective. The review by the Review of Operations Committee is not solely a review by its Chairman. Prior to this violation, LILCO had established a Preoperational Test Results Review Subcommittee (PTRRS) within the Review of Operations Committee to ensure a comprehensive review of all test results. This Subcommittee consists of four highly skilled, technically oriented and experienced members of the plant staff: the Operating Engineer, the Maintenance Engineer, the Reactor Engineer, and the Instrumentation and Control Engineer. These individuals are independent of the LILCO Start-Up organization and the JTG, and their review focuses solely on the technical adequacy of the test results.
Thus, this Subcommittee would have scrutinized the data; it is l reasonable to assume that their review would have disclosed the l discrepancy between the data and the acceptance criteria.
Moreover, si'nce this Subcommittee has no members in common with the Joint Test Group, it constitutes a wholly independent review of the test results.
The existence of review by this Subcommittee also gives a measure of confidence that the absence of the Test Engineer's l
May 12, 1983 Page 11 explanation of his use of strip chart data would have been noted and reviewed. Each member of the Subcommittee receives a full set of the test results and provides comments on the tests. ~The Subcommittee then meets to discuss these comments, and ensures their resolution by the Test Engineer. The results of this Subcommittee review process are subsequently prese:sted to the full Review of Operations Committee as part of a tot al system turnover package for approval. Therefore, LILCO believes that this additional review would have disclosed and documented the Test Engineer's reliance on the strip chart data. LILCO also believes that this Subcommittee, the full Review of Operations Committee and all review groups, when presented with the basis on which the Test Engineer approved the test, would have concurred in his approval.
Finally, the Notice of Violation relies on FSAR para-graph 14.1.1.1 which states that the Joint Test Group reviews and approves completed preoperational tests. FSAR oaragraph 14.1.1.1 does describe the JTG's organizational 1
responsibilities, but FSAR paragraph 14.1.1.4, which describes the evaluation, documentation, and approval process for preoperational test results, is also applicable. This section i
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May 12, 1983 Page 12 makes clear that the final OQA audit of test results and the final acceptance by the Plant Manager, which is accomplished following the ROC review procedure described above, constitute part of the acceptance process for preoperational test results.
Therefore, the JTG review and approval is not the final step in LILCO's review cycle and, 6s described above, important review steps had not yet occurred at the time of the violation.
(4) With respect to I&E's concern that these circumstances indicate a general lack of aggressiveness and at-tention to detail, LILCO believes that the following facts provide confidence in the preoperational test program.
Fifty-three (53) completed test procedures were reviewed by Torrey Pines Technology (TPT) as part of an independent assess-ment of the Shoreham facility performed during 1982. This number represented 100% of the test procedures completed and approved by the Joint Test Group at the time of the independent assessment.2/ The results of the Torrey Pines preoperational test review, which took in excess of 450 manhours to complete, 2/ It should be noted that the diesel generator test involved in this violation had not been completed at the time of the Torrey Pines independent verification.
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May 12, 1983 Page 13 showed no instances where preoperational test results did not meet acceptance criteria. Torrey Pines concluded that the "results of the review indicated that the [preoperational tests] were properly conducted and that the systems tested met the functional requirements of the tests."
In addition, I&E has performed a substantial review involving preoperational tests performed at Shoreham. As of March 4, 1983, I&E inspectors had reviewed 93% of the completed preoperational tests approved by the Joint Test Group. This review has identified no other instances of failure to meet ac-ceptance criteria. Since March 4, 1983, I&E has reviewed five additional completed test procedures and no instances of fail-ure to meet acceptance criteria were identified in these proce-dures. Review by TPT and I&E supports LILCO's view that the preoperational test program at Shoreham is not programmatically deficient and shows that this test program confirms the design safety requirements of structures and systems within the scope of that program.
(5) As noted above, LILCO believes that the cause of this violation was the Test Engineer's failure to document the
May 12, 1983 Page 14 judgments he made in determining the acceptability of the diesel generator load test. Although the Joint Test Group review of these results did not note the discrepancy between the raw data and the acceptance criteria, that review was, nonetheless, quite extensive. The review process generated ex-tensive comments on the completed test package. In fact, the package was subjected to two rounds of review by the Joint Test Group to ensure that all comments made by the members of the Joint Test Group had been adequately addressed. Significantly, therefore, this review was not merely a formality or a cursory review; it was a substantial one. The oversight of the Joint Test Group in.this particular instance is not an indication of inattention to the Shoreham test program. Rather, there has been significant involvement by the Joint Test Group in diesel generator testing since it began. An important example of this involvement is the action taken in November 1982 by the Joint Test Group to add an extended 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> test run on all three
, emergency diesel generators to provide further assurance that i
the engines will operate as designed. These runs are conducted at a load consistent with that expected during a long-term LOCA event.3/ The decision to conduct these additional tests 3/ All three of the emergency diesel generators have now suc-cessfully completed these 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> runs. The test data are cur-rently undergoing review.
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- , i, May 12, 1983 Page 15 preceded I&E's identification of the concerns reported in this Notice of Violation. Thus, LILCO management has aggressively pursued, identified and resolved problems associated with the reliability of the diesel generators.
III. CAUSE As already noted, the cause of this violation was the Test Engineer's failure to document a discrepancy between the Table II data and the acceptance criteria and the judgment made in determining the acceptability of the diesel generator load Had the Test Engineer's judgment been fully documented, test.
his decision would have been reviewed by the JTG. LILCO is confident that the JTG would have approved his decision to accept the test. An additional cause of the violation was the failure by the OQA inspector and the JTG to note the potential discrepancy in their respective reviews. Although these over-sights are undesirable, additional reviews were still required i
by LILCO's procedures, as described in the FSAR, before final acceptance of the test and LILCO believes this additional review would have disclosed the discrepancy.
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- . 1 May 12, 1983 Page 16 IV. LILCO CORRECTIVE ACTION AND RESULTS AND ACTION TAKEN TO PREVENT RECURRENCE (1) LILCO agreed to conduct again all testing of Emer-gency Diesel Generator 102 under PT-307.003B, including the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> load test run to confirm the ability of that diesel gener-ator to operate successfully under maximum service conditions.
This re-test has been successfully completed using even more stringent load limitations than the original test. Although the test package review cycle has not been completed for this re-test, preliminary analysis indicates that the results meet the test criteria and demonstrate that Emergency Diesel Genera-tor 102 can carry a load in excess of the two hour load equiva-lent.
(2) LILCO's March 16 letter also reported that the following corrective action had been taken:
(a) The Start-Up Manager reviewed the concerns expressed in the original inspection report with the Shoreham Start-Up Staff (including the Test Engineers and Start-Up Management), the Joint Test Group and the ROC-PTRRS. The review stressed the need to document adequately any judgments made during testing. The review also emphasized that test reviewers must ensure that raw data is reviewed to ensure it supports the conclu-sions stated in the test procedure and Test a
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May 12, 1983 Page 17 Analysis Report and that adequate justification is presented for any test ex-ceptions noted.
(b) The OQA Engineer reviewed the in-spection report with the OQA inspectors in-volved in the test in question as well as other OQA inspectors involved in the diesel generator test program emphasizing the need to verify the acceptability of the test results.
Following the issuance of the Notice of Violation on April 12, LILCO conducted an additional review session for personnel from all organizations involved in the preoperational test program, including LILCO Start-Up, Operational Quality Assurance and the Plant Staff Review of Operations Committee. This session in-cluded a review of the violation, stressing the need for atten-tion to detail when performing, witnessing and/or reviewing preoperational tests. The presentation also emphasized the im-portance of documenting test exceptions and any judgments made in conducting the test to ensure proper engineering disposition l of any deviations from requirements. This documentation will also ensure that these judgments are brought to the attention l
of reviewers for their consideration.
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4 May 12, 1983 Page 18 (3) As mentioned in the Preventive' Action section of LILCO's March 16, 1983 letter, four preoperational tests that had not yet received complete review were reviewed by a certi-i fied Level III Test Engineer (from Stone & Webster, Boston).
The Emergency Diesel Generator 102 electrical preoperational test package was one of the procedures reviewed. This test package is the same one that is the subject of the Notice of Violation. The review of this package disclosed that during a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> test of fuel oil booster pump capacity conducted by the same test engineer, one data point was 3400 KW -- 50 KW low.
This small discrepancy had no effect on the acceptability of the test results because the small difference in load has no measurable input on the pump's acceptance criteria. The accep-tance criteria is pump discharge pressure which has been shown to vary only .7 psi between 3000 KW and 3500 KW and is well within the required pressure range of 20-35 psi. Nevertheless,
- because this minor deviation involved the same test package and the same test engineer as were involved in the Notice of Viola-( tion, LILCO decided to re-review all approved preoperational and acceptance test procedures for which this Test Engineer was responsible. LILCO has determined that this Test Engineer was l
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J May 12, 1983 Page 19 respo,sible for four approved acceptance tests. These four
- acceptance tests will be re-reviewed.
Two of the other three tests were reviewed and all comments on these test results have been satisfactorily resolved.
1 A review of the-third test has identified a comment relating to the test objective. This comment is being fully evaluated and will be discussed with I&E when the evaluation is completed.
(4) The diesel generator preoperational test program r t
uses comprehensive and complex test procedures to verify that the Emergency Diesel Generators will perform as intended. Be-cause these procedures are complex, the Joint Test Group has, in the past, requested that Test Engineers address certain issues'at Joint. Test Group meetings. LILCO has decided.to extend this practice and require that the responsible Test Engineer attend the relevant portions of all future Joint Test
, Group meetings addressing diesel generator preoperational tests. This practice has been used successfully by LILCO on a case-by-case basis in the past for other types of test proce-dures, i
i (5) As explained in LILCO's response, strip chart data
. are taken as part of the diesel generator load tests. To fa-cilitate and improve the review of diesel generator electric load test results recorded on strip charts, LILCO now prepares
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May 12, 1983 Page 20 a graphical presentation of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> load test data, similar to the graph attached to LILCO's March 16 response. The charts are attached to the test package for review.
J (6) In order to ensure a comprehensivo technical review by the Operational Quality Assurance organization, the following steps will be modified in the OQA review process for preoperational tests:
, (a) Review of all future preoperational test results to confirm that acceptance criteria have been met will be m<dified to require the review be conducted by the Operational Quality Assurance Engineer, or one of his two principal assistants, the Quality Assurance Engineer or the Quality Control Engineer. Further, this review will specifically require a review of all ,
strip charts, tables and graphs related to Section 10.0, Acceptance Criteria Review, of the preoperational tests. This review will be documented by the review-l er's signature and date on Section 10 of the test pro-i
! cedure and all charts, tables and graphs.
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May 12, 1983 Page 21 (b) In addition to the current OQA audit checklist requirements for preoperational tests, LILCO will add specific checklist items to ensure the above additional reviews have been conducted.
(7) Significantly, LILCO took actions responsive to the concerns raised in this violation even before it was iden-tified by I&E. As noted, the LILCO Joint Test Group added a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> test of the diesel to give further assurance that the die-sel will be capable of operating under accident conditions.
The decision to take this action was made in November 1982, prior to the time the NRC identified the concerns discussed in this inspection report. This underscores LILCO's commitment to ensure reliable operation of the Emergency Diesel Generators.
Also, prior to the identificati n of the NRC's concern in this matter, LILCO recognized the need to ensure thorough and timely review of completed test procedures during the busy period prior to fuel load. In November 1982, ROC still had to review over half of the total preoperational tests prior to fuel load.
Therefore on December 10, 1982 LILCO created the Preoperation Test Results Review Subcommittee of the ROC already discussed.
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May 12, 1983 ,
Page 22 i V. DATE WHEN FULL COMPLIANCE WILL BE MET l i
l LILCO's Preoperational Test Program is in full compli-ance with all NRC requirements. Program changes and commit-ments made by the various organizations will be complete by June 15, 1983.
We appreciate the careful-consideration we know you
- will give this response. i a
l 1 i Very truly yours,
)
Wil.iam J. Museler i
. Director, Office of Nuclear cc: J. M. Allen J. Higgins M. S. Pollock i All Pacties
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e, _a 1
COMMONWEALTH OF MASSACHUSETTS )
- ss.:
COUNTY OF SUFFOLK )
WILLIAM J. MUSELER, being duly sworn, deposes and says that I am Director of the Office of Nuclear, Long Island Lighting Company, the owner of the Shoreham Nuclear Power Station. I have read the Notice of Violation and Proposed Im-position of Civil Penalty dated April 12, 1983, and also the responses thereto prepared under my direction dated May 12, 1983. The facts set forth in the response to the Notice of Vi-olation and the response to the Proposed Imposition of Civil Penalty are based upon reports and information provided to me by the employees, agents and representatives of Long Island Lighting Company responsible for the activities described in said Notice of Violation and in said response. I believe the facts set forth in said response are true.
WILE (DAM J. A MUSELER Sworn to before me this
/,7,A day of May, 1983
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