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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20212J7481999-09-29029 September 1999 Forwards Insp Rept 50-133/99-02 on 990915.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program HBL-99-011, Forwards 10CFR50.59 Annual Rept of Changes,Tests & Experiments for 980101-981231, for Humboldt Bay Power Plant,Unit 31999-08-27027 August 1999 Forwards 10CFR50.59 Annual Rept of Changes,Tests & Experiments for 980101-981231, for Humboldt Bay Power Plant,Unit 3 HBL-99-014, Forwards Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates,1999-07-23023 July 1999 Forwards Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, ML20209D9981999-07-0808 July 1999 Ack Receipt of Which Transmitted Rev 9 to Physical Security Plan for Humboldt Bay Power Plant,Under Provisions of 10CFR50.54(p).Changes Do Not Decrease Plan Effectiveness,So NRC Approval Is Not Required HBL-99-012, Forwards Rept of Rev 29 to Hbpp Emergency Plan,Effective 990610.Changes in Rev Do Not Decrease Effectiveness of Plan, Per 10CFR50.54(q).Plan Has Been Distributed to Region IV & Is Not Included as Part of Submittal1999-07-0707 July 1999 Forwards Rept of Rev 29 to Hbpp Emergency Plan,Effective 990610.Changes in Rev Do Not Decrease Effectiveness of Plan, Per 10CFR50.54(q).Plan Has Been Distributed to Region IV & Is Not Included as Part of Submittal ML18107A7011999-06-25025 June 1999 Requests Rev of NRC Records to Reflect Change of PG&E Address ML20207E7301999-05-27027 May 1999 Discusses Reorganization of Nrr,Effective 990328 & Forwards Organizational Chart HBL-99-008, Forwards Annual Rept of Occupational Radiation Exposure for 1998. Radiation Exposure Rept Provided on Encl Diskette in Electronic Format of Reg Guide 8.7.Without Encl1999-04-30030 April 1999 Forwards Annual Rept of Occupational Radiation Exposure for 1998. Radiation Exposure Rept Provided on Encl Diskette in Electronic Format of Reg Guide 8.7.Without Encl ML20205L9951999-04-0808 April 1999 Forwards Insp Rept 50-133/99-01 on 990222-25 & 0308.No Violations Identified HBL-99-006, Forwards Annual Radioactive Effluent Release Rept, Covering Period Jan-Dec 1998.Encl 2 Contains Revs 1 & 2 to Safstor ODCM as Required by Specification Section 4.2 of Safstor Offsite Dose Calculation Manual1999-03-31031 March 1999 Forwards Annual Radioactive Effluent Release Rept, Covering Period Jan-Dec 1998.Encl 2 Contains Revs 1 & 2 to Safstor ODCM as Required by Specification Section 4.2 of Safstor Offsite Dose Calculation Manual DCL-99-038, Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f)1999-03-31031 March 1999 Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f) HBL-99-003, Forwards Annual Facility Status & Survey Rept, for Jan-Dec 19981999-03-31031 March 1999 Forwards Annual Facility Status & Survey Rept, for Jan-Dec 1998 ML20202A9831999-01-18018 January 1999 Informs That Modesto Irrigation District No Longer Seeking Addl Interconnection with Pacific Gas & Electric Co at Pittsburg,Ca & Matters First Addressed in 980429 Comments in Opposition to Restructuring of Util Have Now Become Moot HBL-98-021, Forwards Rept Change (Rev 28) to Hbpp Emergency Plan, Effective 981126.Updated Emergency Plan,Not Included as Part of Submittal1998-12-18018 December 1998 Forwards Rept Change (Rev 28) to Hbpp Emergency Plan, Effective 981126.Updated Emergency Plan,Not Included as Part of Submittal ML20195H7631998-11-20020 November 1998 Forwards Insp Rept 50-133/98-04 on 980901-03,1012-17 & 20-22.No Violations Noted.Insp Focused on Activities Associated with Removal of 250 Feet Ventilation Stack HBL-98-013, Forwards 10CFR50.59 Annual Rept of Changes,Tests & Experiments for Jan-Dec 1997. Encl Annual Rept Provides Brief Description of 10CFR50.59 Facility Design Changes, Including Summary of Each SE1998-11-10010 November 1998 Forwards 10CFR50.59 Annual Rept of Changes,Tests & Experiments for Jan-Dec 1997. Encl Annual Rept Provides Brief Description of 10CFR50.59 Facility Design Changes, Including Summary of Each SE ML20154G4441998-10-0101 October 1998 Ack Receipt of Which Transmitted Rev 8 to Physical Security Plan for Humboldt Bay Power Plant,Under Provisions 10CFR50.54.Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required DCL-98-123, Submits Listed Address Changes for NRC Service Lists for Listed Individuals1998-09-0909 September 1998 Submits Listed Address Changes for NRC Service Lists for Listed Individuals HBL-98-015, Forwards Rev 2 to DSAR for Humboldt Bay Power Plant,Unit 3, to Comply W/Decommissioning Rule.Dsar Was Formerly Known as Safstor Decommissioning Plan.Encl 1 Identifies & Describes Rept Changes1998-08-28028 August 1998 Forwards Rev 2 to DSAR for Humboldt Bay Power Plant,Unit 3, to Comply W/Decommissioning Rule.Dsar Was Formerly Known as Safstor Decommissioning Plan.Encl 1 Identifies & Describes Rept Changes DCL-98-108, Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year..1998-08-0707 August 1998 Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year.. HBL-98-009, Submits Info Describing site-specifc Decommissioning Cost Estimates1998-08-0505 August 1998 Submits Info Describing site-specifc Decommissioning Cost Estimates ML20236G0691998-06-19019 June 1998 Forwards Endorsement 123 to Neila Policy NF-228,Endorsement 145 to Neila Policy NF-113,Endorsement 124 to Neila Policy NF-228 & Endorsement 89 to Maelu Policy MF-103 L-98-027, Forwards Rev 8 to Physical Security Plan.Encl 1 Identifies & Describes Plan Changes,Which Indicated W/Rev Bars in Left Margin of Physical Security Plan.Rev Withheld,Per 10CFR2.790(d)1998-06-11011 June 1998 Forwards Rev 8 to Physical Security Plan.Encl 1 Identifies & Describes Plan Changes,Which Indicated W/Rev Bars in Left Margin of Physical Security Plan.Rev Withheld,Per 10CFR2.790(d) HBL-98-011, Forwards Rept of Rev 27 to Hbpp Emergency Plan,Effective 980507,per 10CFR50.4 & 10CFR50.54(q).Updated Plan Has Already Been Distributed to NRC Region IV IAW Hbpp Procedures.W/O Rept1998-06-0404 June 1998 Forwards Rept of Rev 27 to Hbpp Emergency Plan,Effective 980507,per 10CFR50.4 & 10CFR50.54(q).Updated Plan Has Already Been Distributed to NRC Region IV IAW Hbpp Procedures.W/O Rept ML20247R9091998-05-26026 May 1998 Forwards Copy of Transcript of Public Meeting Held by NRC W/Participation by PG&E on 980429 in Eureka,California Re Decommissioning of Humboldt Bay Power Plant ML20236E7681998-05-22022 May 1998 Forwards Insp Rept 50-133/98-03 on 980427-30.No Violations Noted.Insp Included Plans for Future Decommissioning of Facility,Including Removal of Unit 3 Stack & Eventual Dry Cask Storage of Unit 3 Spent Fuel ML20247L3571998-05-18018 May 1998 Clarifies Remark Re Discharge Through Existing Ventilation Stack to Avoid Confusion.Remark Was in Response to Question Re Purpose of Dismantlement & Replacement of Existing Ventilation Stack ML20247F9241998-05-14014 May 1998 Forwards Insp Rept 50-133/98-02 on 980414-15.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program.Determined That Physical Security Program Was Properly Implemented ML20216B7291998-05-12012 May 1998 Expresses Appreciation for Support Provided for Recent Public Meeting Held at Eureka Inn on Decommissioning of Humboldt Bay Power Plant ML20216B6801998-05-11011 May 1998 Expresses Appreciation for Outstanding Support Staff Provided for Recent Public Meeting Held at Eureka Inn on Decommissioning of Humboldt Bay Power Plant ML20217H1161998-04-21021 April 1998 Forwards Annual Rept of Occupational Radiation Exposure, for Employees & Visitors Monitored at Humboldt Bay Power Plant During CY97.Rept on Diskette.W/O Encl ML20216C8681998-04-0808 April 1998 Forwards Amend 32 to License DPR-7 & Safety Evaluation. Amend Revises TS to Implement GL 89-01 & to Incorporate Requirements of Revised 10CFR20 & App I to 10CFR50 HBL-98-008, Forwards Annual Radioactive Effluent Release Rept for 970101-1231. Rept Contains Comparison of Max Calculated Dose to Individual Members of Public W/Numerical Guidelines of 10CFR50 App I1998-03-31031 March 1998 Forwards Annual Radioactive Effluent Release Rept for 970101-1231. Rept Contains Comparison of Max Calculated Dose to Individual Members of Public W/Numerical Guidelines of 10CFR50 App I HBL-98-006, Forwards Annual Facility Status & Survey Rept for 1997. Section a Addresses Facility Status & Section B Presents Results of Monitoring Performed for Radiological Environ Monitoring Program1998-03-31031 March 1998 Forwards Annual Facility Status & Survey Rept for 1997. Section a Addresses Facility Status & Section B Presents Results of Monitoring Performed for Radiological Environ Monitoring Program HBL-98-003, Forwards Corrected TSs Re LAR 96-02,in Entirety W/ Affected Pages Retyped1998-03-13013 March 1998 Forwards Corrected TSs Re LAR 96-02,in Entirety W/ Affected Pages Retyped HBL-98-002, Submits Updated Post-Shutdown Decommissioning Activities Rept for Humboldt Bay Power Plant,Unit 3. Safstor Decommissioning Plan Will Be Considered FSAR for Hbpp1998-02-27027 February 1998 Submits Updated Post-Shutdown Decommissioning Activities Rept for Humboldt Bay Power Plant,Unit 3. Safstor Decommissioning Plan Will Be Considered FSAR for Hbpp ML20203K9691998-02-27027 February 1998 Forwards Insp Rept 50-133/98-01 on 980126-29.No Violations Noted.Major Areas Reviewed as Part of Insp Included Compliance W/Selected TS of License,Review of 1997 Annual Exercise & Evaluation of Facility Re Decommissioning Plan HBL-98-001, Informs That Existing Hbpp PM Program Adequately Meets Requirements of Maint Rule.Summary of Program & Basis for Determining Maint Rule Compliance at Plant,Encl1998-01-26026 January 1998 Informs That Existing Hbpp PM Program Adequately Meets Requirements of Maint Rule.Summary of Program & Basis for Determining Maint Rule Compliance at Plant,Encl ML20198J4791998-01-0707 January 1998 Informs That LL Wheeler Assumed Project Mgt Responsibilities for Humboldt Bay on 971229.LL Wheeler Can Be Contacted at Listed E-mail Address ML20199B3851997-11-13013 November 1997 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-133/97-02 on 971001 HBL-97-016, Responds to NRC Re Violations Noted in Insp Rept 50-133/97-02.Corrective Actions:Correctly Reset Process Water Monitor Warning High & Low Alarms & re-educated All Operators on Proper Method to Set Process Water Monitor1997-10-27027 October 1997 Responds to NRC Re Violations Noted in Insp Rept 50-133/97-02.Corrective Actions:Correctly Reset Process Water Monitor Warning High & Low Alarms & re-educated All Operators on Proper Method to Set Process Water Monitor HBL-97-015, Submits Inventory Changes at Unit 3 from 970401-0930 for Matls Re Enriched U Fuel,Plutonium in Fuel,Fission Counters & Incore Flux Detectors.Encl 2 Provides Data Required by Form DOE/NRC-741.W/o Encl1997-10-0909 October 1997 Submits Inventory Changes at Unit 3 from 970401-0930 for Matls Re Enriched U Fuel,Plutonium in Fuel,Fission Counters & Incore Flux Detectors.Encl 2 Provides Data Required by Form DOE/NRC-741.W/o Encl ML20217D6191997-10-0101 October 1997 Forwards Insp Rept 50-133/97-02 on 970513-0828 & Nov.Nrc Will Use Licensee Response to NOV to Determine Whether Further Enforcement Action Necessary HBL-97-012, Forwards Rept of Rev 26 to Plant Emergency Plan,Effective 970801.Changes Do Not Decrease Effectiveness of Plan1997-08-28028 August 1997 Forwards Rept of Rev 26 to Plant Emergency Plan,Effective 970801.Changes Do Not Decrease Effectiveness of Plan ML20210H4671997-08-0202 August 1997 Requests That NRC Suspend Investigation & Review of Issues Raised by Modesto Irrigation District & Transmission Agency of Northern CA Re Contention That PG&E Had Violated Nuclear License Conditions Known as Stanislaus Commitments ML20149K8321997-07-25025 July 1997 Ack Receipt of Transmitting Rev 7 to Physical Security Plan,Submitted Under Provisions of 10CFR50.54(p). Changes Do Not Decrease Effectiveness of Plan & No NRC Approval Is Required HBL-97-009, Provides Addl Justification to Support TS Change Request Contained in LAR 96-02 ,re Establishment of Radiological Effluents Control Program & in Response to 970416 Telcon1997-06-12012 June 1997 Provides Addl Justification to Support TS Change Request Contained in LAR 96-02 ,re Establishment of Radiological Effluents Control Program & in Response to 970416 Telcon L-97-035, Forwards Info Re Changes to Humboldt Bay Power Plant,Unit 3 Physical Security Plan.Changes Do Not Decrease Safeguards Effectiveness of Plan & Are Submitted Per 10CFR50.54(p). Encls Withheld Per 10CFR2.790(d)1997-04-0909 April 1997 Forwards Info Re Changes to Humboldt Bay Power Plant,Unit 3 Physical Security Plan.Changes Do Not Decrease Safeguards Effectiveness of Plan & Are Submitted Per 10CFR50.54(p). Encls Withheld Per 10CFR2.790(d) L-97-033, Confirms Final Disposition of Specific Hazardous Wastes Shipped to IT Corp Panoche & Vine Hill Facilities from Plant in Jul 19861997-04-0202 April 1997 Confirms Final Disposition of Specific Hazardous Wastes Shipped to IT Corp Panoche & Vine Hill Facilities from Plant in Jul 1986 HBL-97-003, Documents Utils Understanding of Results in Discussions from Meeting W/Nrc Personnel to Discuss Application of New Decommissioning Rule to Hbpp1997-02-20020 February 1997 Documents Utils Understanding of Results in Discussions from Meeting W/Nrc Personnel to Discuss Application of New Decommissioning Rule to Hbpp 1999-09-29
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARHBL-99-011, Forwards 10CFR50.59 Annual Rept of Changes,Tests & Experiments for 980101-981231, for Humboldt Bay Power Plant,Unit 31999-08-27027 August 1999 Forwards 10CFR50.59 Annual Rept of Changes,Tests & Experiments for 980101-981231, for Humboldt Bay Power Plant,Unit 3 HBL-99-014, Forwards Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates,1999-07-23023 July 1999 Forwards Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, HBL-99-012, Forwards Rept of Rev 29 to Hbpp Emergency Plan,Effective 990610.Changes in Rev Do Not Decrease Effectiveness of Plan, Per 10CFR50.54(q).Plan Has Been Distributed to Region IV & Is Not Included as Part of Submittal1999-07-0707 July 1999 Forwards Rept of Rev 29 to Hbpp Emergency Plan,Effective 990610.Changes in Rev Do Not Decrease Effectiveness of Plan, Per 10CFR50.54(q).Plan Has Been Distributed to Region IV & Is Not Included as Part of Submittal ML18107A7011999-06-25025 June 1999 Requests Rev of NRC Records to Reflect Change of PG&E Address HBL-99-008, Forwards Annual Rept of Occupational Radiation Exposure for 1998. Radiation Exposure Rept Provided on Encl Diskette in Electronic Format of Reg Guide 8.7.Without Encl1999-04-30030 April 1999 Forwards Annual Rept of Occupational Radiation Exposure for 1998. Radiation Exposure Rept Provided on Encl Diskette in Electronic Format of Reg Guide 8.7.Without Encl HBL-99-003, Forwards Annual Facility Status & Survey Rept, for Jan-Dec 19981999-03-31031 March 1999 Forwards Annual Facility Status & Survey Rept, for Jan-Dec 1998 HBL-99-006, Forwards Annual Radioactive Effluent Release Rept, Covering Period Jan-Dec 1998.Encl 2 Contains Revs 1 & 2 to Safstor ODCM as Required by Specification Section 4.2 of Safstor Offsite Dose Calculation Manual1999-03-31031 March 1999 Forwards Annual Radioactive Effluent Release Rept, Covering Period Jan-Dec 1998.Encl 2 Contains Revs 1 & 2 to Safstor ODCM as Required by Specification Section 4.2 of Safstor Offsite Dose Calculation Manual DCL-99-038, Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f)1999-03-31031 March 1999 Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f) ML20202A9831999-01-18018 January 1999 Informs That Modesto Irrigation District No Longer Seeking Addl Interconnection with Pacific Gas & Electric Co at Pittsburg,Ca & Matters First Addressed in 980429 Comments in Opposition to Restructuring of Util Have Now Become Moot HBL-98-021, Forwards Rept Change (Rev 28) to Hbpp Emergency Plan, Effective 981126.Updated Emergency Plan,Not Included as Part of Submittal1998-12-18018 December 1998 Forwards Rept Change (Rev 28) to Hbpp Emergency Plan, Effective 981126.Updated Emergency Plan,Not Included as Part of Submittal HBL-98-013, Forwards 10CFR50.59 Annual Rept of Changes,Tests & Experiments for Jan-Dec 1997. Encl Annual Rept Provides Brief Description of 10CFR50.59 Facility Design Changes, Including Summary of Each SE1998-11-10010 November 1998 Forwards 10CFR50.59 Annual Rept of Changes,Tests & Experiments for Jan-Dec 1997. Encl Annual Rept Provides Brief Description of 10CFR50.59 Facility Design Changes, Including Summary of Each SE DCL-98-123, Submits Listed Address Changes for NRC Service Lists for Listed Individuals1998-09-0909 September 1998 Submits Listed Address Changes for NRC Service Lists for Listed Individuals HBL-98-015, Forwards Rev 2 to DSAR for Humboldt Bay Power Plant,Unit 3, to Comply W/Decommissioning Rule.Dsar Was Formerly Known as Safstor Decommissioning Plan.Encl 1 Identifies & Describes Rept Changes1998-08-28028 August 1998 Forwards Rev 2 to DSAR for Humboldt Bay Power Plant,Unit 3, to Comply W/Decommissioning Rule.Dsar Was Formerly Known as Safstor Decommissioning Plan.Encl 1 Identifies & Describes Rept Changes DCL-98-108, Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year..1998-08-0707 August 1998 Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year.. HBL-98-009, Submits Info Describing site-specifc Decommissioning Cost Estimates1998-08-0505 August 1998 Submits Info Describing site-specifc Decommissioning Cost Estimates ML20236G0691998-06-19019 June 1998 Forwards Endorsement 123 to Neila Policy NF-228,Endorsement 145 to Neila Policy NF-113,Endorsement 124 to Neila Policy NF-228 & Endorsement 89 to Maelu Policy MF-103 L-98-027, Forwards Rev 8 to Physical Security Plan.Encl 1 Identifies & Describes Plan Changes,Which Indicated W/Rev Bars in Left Margin of Physical Security Plan.Rev Withheld,Per 10CFR2.790(d)1998-06-11011 June 1998 Forwards Rev 8 to Physical Security Plan.Encl 1 Identifies & Describes Plan Changes,Which Indicated W/Rev Bars in Left Margin of Physical Security Plan.Rev Withheld,Per 10CFR2.790(d) HBL-98-011, Forwards Rept of Rev 27 to Hbpp Emergency Plan,Effective 980507,per 10CFR50.4 & 10CFR50.54(q).Updated Plan Has Already Been Distributed to NRC Region IV IAW Hbpp Procedures.W/O Rept1998-06-0404 June 1998 Forwards Rept of Rev 27 to Hbpp Emergency Plan,Effective 980507,per 10CFR50.4 & 10CFR50.54(q).Updated Plan Has Already Been Distributed to NRC Region IV IAW Hbpp Procedures.W/O Rept ML20247L3571998-05-18018 May 1998 Clarifies Remark Re Discharge Through Existing Ventilation Stack to Avoid Confusion.Remark Was in Response to Question Re Purpose of Dismantlement & Replacement of Existing Ventilation Stack ML20217H1161998-04-21021 April 1998 Forwards Annual Rept of Occupational Radiation Exposure, for Employees & Visitors Monitored at Humboldt Bay Power Plant During CY97.Rept on Diskette.W/O Encl HBL-98-006, Forwards Annual Facility Status & Survey Rept for 1997. Section a Addresses Facility Status & Section B Presents Results of Monitoring Performed for Radiological Environ Monitoring Program1998-03-31031 March 1998 Forwards Annual Facility Status & Survey Rept for 1997. Section a Addresses Facility Status & Section B Presents Results of Monitoring Performed for Radiological Environ Monitoring Program HBL-98-008, Forwards Annual Radioactive Effluent Release Rept for 970101-1231. Rept Contains Comparison of Max Calculated Dose to Individual Members of Public W/Numerical Guidelines of 10CFR50 App I1998-03-31031 March 1998 Forwards Annual Radioactive Effluent Release Rept for 970101-1231. Rept Contains Comparison of Max Calculated Dose to Individual Members of Public W/Numerical Guidelines of 10CFR50 App I HBL-98-003, Forwards Corrected TSs Re LAR 96-02,in Entirety W/ Affected Pages Retyped1998-03-13013 March 1998 Forwards Corrected TSs Re LAR 96-02,in Entirety W/ Affected Pages Retyped HBL-98-002, Submits Updated Post-Shutdown Decommissioning Activities Rept for Humboldt Bay Power Plant,Unit 3. Safstor Decommissioning Plan Will Be Considered FSAR for Hbpp1998-02-27027 February 1998 Submits Updated Post-Shutdown Decommissioning Activities Rept for Humboldt Bay Power Plant,Unit 3. Safstor Decommissioning Plan Will Be Considered FSAR for Hbpp HBL-98-001, Informs That Existing Hbpp PM Program Adequately Meets Requirements of Maint Rule.Summary of Program & Basis for Determining Maint Rule Compliance at Plant,Encl1998-01-26026 January 1998 Informs That Existing Hbpp PM Program Adequately Meets Requirements of Maint Rule.Summary of Program & Basis for Determining Maint Rule Compliance at Plant,Encl HBL-97-016, Responds to NRC Re Violations Noted in Insp Rept 50-133/97-02.Corrective Actions:Correctly Reset Process Water Monitor Warning High & Low Alarms & re-educated All Operators on Proper Method to Set Process Water Monitor1997-10-27027 October 1997 Responds to NRC Re Violations Noted in Insp Rept 50-133/97-02.Corrective Actions:Correctly Reset Process Water Monitor Warning High & Low Alarms & re-educated All Operators on Proper Method to Set Process Water Monitor HBL-97-012, Forwards Rept of Rev 26 to Plant Emergency Plan,Effective 970801.Changes Do Not Decrease Effectiveness of Plan1997-08-28028 August 1997 Forwards Rept of Rev 26 to Plant Emergency Plan,Effective 970801.Changes Do Not Decrease Effectiveness of Plan ML20210H4671997-08-0202 August 1997 Requests That NRC Suspend Investigation & Review of Issues Raised by Modesto Irrigation District & Transmission Agency of Northern CA Re Contention That PG&E Had Violated Nuclear License Conditions Known as Stanislaus Commitments HBL-97-009, Provides Addl Justification to Support TS Change Request Contained in LAR 96-02 ,re Establishment of Radiological Effluents Control Program & in Response to 970416 Telcon1997-06-12012 June 1997 Provides Addl Justification to Support TS Change Request Contained in LAR 96-02 ,re Establishment of Radiological Effluents Control Program & in Response to 970416 Telcon L-97-035, Forwards Info Re Changes to Humboldt Bay Power Plant,Unit 3 Physical Security Plan.Changes Do Not Decrease Safeguards Effectiveness of Plan & Are Submitted Per 10CFR50.54(p). Encls Withheld Per 10CFR2.790(d)1997-04-0909 April 1997 Forwards Info Re Changes to Humboldt Bay Power Plant,Unit 3 Physical Security Plan.Changes Do Not Decrease Safeguards Effectiveness of Plan & Are Submitted Per 10CFR50.54(p). Encls Withheld Per 10CFR2.790(d) L-97-033, Confirms Final Disposition of Specific Hazardous Wastes Shipped to IT Corp Panoche & Vine Hill Facilities from Plant in Jul 19861997-04-0202 April 1997 Confirms Final Disposition of Specific Hazardous Wastes Shipped to IT Corp Panoche & Vine Hill Facilities from Plant in Jul 1986 HBL-97-003, Documents Utils Understanding of Results in Discussions from Meeting W/Nrc Personnel to Discuss Application of New Decommissioning Rule to Hbpp1997-02-20020 February 1997 Documents Utils Understanding of Results in Discussions from Meeting W/Nrc Personnel to Discuss Application of New Decommissioning Rule to Hbpp HBL-97-001, Submits Annual Rept of Changes,Tests & Experiments for Humboldt Bay Power Plant,Unit 3 for Reporting Interval Jan-Dec 19951997-01-28028 January 1997 Submits Annual Rept of Changes,Tests & Experiments for Humboldt Bay Power Plant,Unit 3 for Reporting Interval Jan-Dec 1995 ML20133F8961997-01-0909 January 1997 Responds to NRC Ltr of 961206 Received on 961210 Which Requested Further Info Re Utils Violations of Conditions of Its Nuclear Licenses Designated to Promote & Protect Competition in Bulk Power Market in Northern & Central CA ML20133F8721997-01-0909 January 1997 Acks & Responds to NRC Ltr of 961206 Received by Undersigned on 961210 Requesting Further Info to Document Tancs Assertion,Per Filing on 960429 That Util Has Violated Terms & Conditions of Nuclear Power Project Licenses HBL-96-027, Forwards Application for Amend to License DPR-7 to Relocate Controls & Limitations on RETS & Radiological Environmental Monitoring to ODCM & PCP1996-12-0909 December 1996 Forwards Application for Amend to License DPR-7 to Relocate Controls & Limitations on RETS & Radiological Environmental Monitoring to ODCM & PCP HBL-93-060, Forwards Rev 6 to Pacific Gas & Electric Co Humboldt Bay Plant Unit 3 - Safstor QA Plan1993-10-14014 October 1993 Forwards Rev 6 to Pacific Gas & Electric Co Humboldt Bay Plant Unit 3 - Safstor QA Plan ML20057F7271993-10-0808 October 1993 Forwards LAR 93-02,revising TS Section II, Site, Section V, Monitoring Sys & Section VII, Administrative Controls ML20059C4221993-09-0808 September 1993 Forwards Humboldt Bay Power Plant Updated Newsletter Sent to People Living within Ten Miles of Power Plant During Sept 1993 HBL-93-050, Forwards Rev 3 to Emergency Plan to Include Local Ltrs of Agreements W/Local Hosps,Humboldt County Fire Depts & Local Ambulance Svcs.Informs That Because Plan Incorporated Into Hbpp Plant Manuals,Vol 3,Rev 21 Appears at Top of Each Page1993-08-17017 August 1993 Forwards Rev 3 to Emergency Plan to Include Local Ltrs of Agreements W/Local Hosps,Humboldt County Fire Depts & Local Ambulance Svcs.Informs That Because Plan Incorporated Into Hbpp Plant Manuals,Vol 3,Rev 21 Appears at Top of Each Page HBL-93-005, Forwards Public Version of Rev 2 to Emergency Plan.Vol 3,Rev 20 Appears at Top of Each Page of Rev to Reflect Incorporation of Emergency Plan Into Hbpp Plant Manuals & Current Sys for Maint of Manuals.W/930202 Release Memo1993-01-19019 January 1993 Forwards Public Version of Rev 2 to Emergency Plan.Vol 3,Rev 20 Appears at Top of Each Page of Rev to Reflect Incorporation of Emergency Plan Into Hbpp Plant Manuals & Current Sys for Maint of Manuals.W/930202 Release Memo HBL-90-038, Forwards Decommissioning Financial Assurance Certification Rept,Per 10CFR50.751990-07-24024 July 1990 Forwards Decommissioning Financial Assurance Certification Rept,Per 10CFR50.75 HBL-90-036, Forwards Replacement Page 13-1,further Revising Section 13.2 of 880826 Rev 2 to Physical Security Plan.Rev Adds Specific Source Ref to Commitment Document & Retention of security- Related Documents.Encl Withheld (Ref 10CFR73.21)1990-07-17017 July 1990 Forwards Replacement Page 13-1,further Revising Section 13.2 of 880826 Rev 2 to Physical Security Plan.Rev Adds Specific Source Ref to Commitment Document & Retention of security- Related Documents.Encl Withheld (Ref 10CFR73.21) HBL-89-041, Responds to NRC Re Violations Noted in Insp Rept 50-133/89-02.Corrective Action:High Level Vault Containing Drums of Waste Immediately Posted as High Radiation Area1989-09-11011 September 1989 Responds to NRC Re Violations Noted in Insp Rept 50-133/89-02.Corrective Action:High Level Vault Containing Drums of Waste Immediately Posted as High Radiation Area ML20246E6061989-08-16016 August 1989 Forwards Endorsements 10 & 11 to Nelia Certificate N-74 & Maelu Certificate M-74 & Endorsements 7 & 8 to Nelia Certificate N-76 & Maelu Certificate M-76,respectively DCL-89-201, Discusses Notification to NRC Re Employees Potential Safety Issues,Per NRC .Licensee Sent Clarifying Ltrs to Employees Stating That Employees Free to Contact NRC of Any Safety Concerns W/O Fear of Retribution in Any Form1989-07-28028 July 1989 Discusses Notification to NRC Re Employees Potential Safety Issues,Per NRC .Licensee Sent Clarifying Ltrs to Employees Stating That Employees Free to Contact NRC of Any Safety Concerns W/O Fear of Retribution in Any Form ML20244B9261989-06-14014 June 1989 Submits Certificate of Insurance for Plant,Certifying That Insurance Has Been Effected W/Nuclear Mutual Ltd.Policy Term Is 890401-900401 ML20246J7051989-06-0909 June 1989 Forwards Application for Exemption from Requirements of 10CFR50.54(W) Filed Per 10CFR50.12(a).Application Relates to Utils Request for Reduction in on-site Property Damage Insurance from Current $100,000 to $63,160,000 DCL-89-149, Requests Renewal of Approval of QA Programs for Radioactive Matl Packages1989-05-30030 May 1989 Requests Renewal of Approval of QA Programs for Radioactive Matl Packages ML20244B4881989-04-0707 April 1989 Forwards Endorsement 35 to Maelu Policy MF-103 & Endorsements 65 & 116 to Nelia Policies NF-228 & NF-113, Respectively 1999-08-27
[Table view] Category:UTILITY TO NRC
MONTHYEARHBL-90-038, Forwards Decommissioning Financial Assurance Certification Rept,Per 10CFR50.751990-07-24024 July 1990 Forwards Decommissioning Financial Assurance Certification Rept,Per 10CFR50.75 HBL-90-036, Forwards Replacement Page 13-1,further Revising Section 13.2 of 880826 Rev 2 to Physical Security Plan.Rev Adds Specific Source Ref to Commitment Document & Retention of security- Related Documents.Encl Withheld (Ref 10CFR73.21)1990-07-17017 July 1990 Forwards Replacement Page 13-1,further Revising Section 13.2 of 880826 Rev 2 to Physical Security Plan.Rev Adds Specific Source Ref to Commitment Document & Retention of security- Related Documents.Encl Withheld (Ref 10CFR73.21) HBL-89-041, Responds to NRC Re Violations Noted in Insp Rept 50-133/89-02.Corrective Action:High Level Vault Containing Drums of Waste Immediately Posted as High Radiation Area1989-09-11011 September 1989 Responds to NRC Re Violations Noted in Insp Rept 50-133/89-02.Corrective Action:High Level Vault Containing Drums of Waste Immediately Posted as High Radiation Area ML20246E6061989-08-16016 August 1989 Forwards Endorsements 10 & 11 to Nelia Certificate N-74 & Maelu Certificate M-74 & Endorsements 7 & 8 to Nelia Certificate N-76 & Maelu Certificate M-76,respectively DCL-89-201, Discusses Notification to NRC Re Employees Potential Safety Issues,Per NRC .Licensee Sent Clarifying Ltrs to Employees Stating That Employees Free to Contact NRC of Any Safety Concerns W/O Fear of Retribution in Any Form1989-07-28028 July 1989 Discusses Notification to NRC Re Employees Potential Safety Issues,Per NRC .Licensee Sent Clarifying Ltrs to Employees Stating That Employees Free to Contact NRC of Any Safety Concerns W/O Fear of Retribution in Any Form ML20246J7051989-06-0909 June 1989 Forwards Application for Exemption from Requirements of 10CFR50.54(W) Filed Per 10CFR50.12(a).Application Relates to Utils Request for Reduction in on-site Property Damage Insurance from Current $100,000 to $63,160,000 DCL-89-149, Requests Renewal of Approval of QA Programs for Radioactive Matl Packages1989-05-30030 May 1989 Requests Renewal of Approval of QA Programs for Radioactive Matl Packages ML20244B4881989-04-0707 April 1989 Forwards Endorsement 35 to Maelu Policy MF-103 & Endorsements 65 & 116 to Nelia Policies NF-228 & NF-113, Respectively ML20235J2191989-02-17017 February 1989 Forwards Endorsements,Including Endorsement 3 to Nelia Certificate NW-132,Endorsement 3 to Maelu Certificate MW-73, Endorsement 4 to Nelia Certificate NW-51 & Endorsement 4 to Maelu Certificate MW-135 HBL-88-077, Requests Exemption from Provisions of 10CFR70.51(d) Re Annual Physical Inventory of Spent Fuel.Conducting Physical Inventory Not Necessary to Achieve Underlying Purpose of Rule.Performance of Annual Inventory Satisfies Requirement1988-09-13013 September 1988 Requests Exemption from Provisions of 10CFR70.51(d) Re Annual Physical Inventory of Spent Fuel.Conducting Physical Inventory Not Necessary to Achieve Underlying Purpose of Rule.Performance of Annual Inventory Satisfies Requirement HBL-88-074, Forwards Changes to Rev 2 to Physical Security Plan.Info Withheld (Ref 10CFR73.21)1988-08-26026 August 1988 Forwards Changes to Rev 2 to Physical Security Plan.Info Withheld (Ref 10CFR73.21) HBL-88-066, Forwards Addl Info Re Use of Security Seals on Spent Fuel Storage Pool,Per1988-07-19019 July 1988 Forwards Addl Info Re Use of Security Seals on Spent Fuel Storage Pool,Per HBL-88-055, Requests NRC Concurrence to Utilize Security Seals on Spent Fuel Storage Pool at Plant.Use of Seals Will Simplify Annual Physical Inventory of Spent Fuel Stored in Pool & Minimize Radiation Exposures to Workers & Contamination1988-06-0606 June 1988 Requests NRC Concurrence to Utilize Security Seals on Spent Fuel Storage Pool at Plant.Use of Seals Will Simplify Annual Physical Inventory of Spent Fuel Stored in Pool & Minimize Radiation Exposures to Workers & Contamination ML20154L3411988-05-23023 May 1988 Forwards Replacement Pages for Proposed Safstor Tech Specs, Rev 0,per 880505 Discussions W/Nrc DCL-88-100, Forwards Rev 4 to Humboldt Bay Power Plant Unit 3 Safstor QA Plan. Revs Listed1988-04-21021 April 1988 Forwards Rev 4 to Humboldt Bay Power Plant Unit 3 Safstor QA Plan. Revs Listed HBL-88-026, Forwards Edited Rev 3 to Proposed Safstor Tech Specs, Initially Transmitted on 871116,for NRC Approval & Issuance as Rev 0.Ack of Receipt Requested1988-03-16016 March 1988 Forwards Edited Rev 3 to Proposed Safstor Tech Specs, Initially Transmitted on 871116,for NRC Approval & Issuance as Rev 0.Ack of Receipt Requested HBL-87-066, Forwards Rev 3 to Proposed Tech Specs for Safstor.Revs Reflect Util 870821 Response to NRC Request for Addl Info1987-11-16016 November 1987 Forwards Rev 3 to Proposed Tech Specs for Safstor.Revs Reflect Util 870821 Response to NRC Request for Addl Info ML20236H9691987-10-26026 October 1987 Forwards Endorsement 25 to Maelu Policy MF-103 & Endorsement 55 to Nelia Policy NF-228 HBL-87-054, Forwards Repts Entitled Radioactive Effluent Releases & Waste Disposal from Humboldt Bay Power Plant Unit 3 for Jan-June 1987 & Environ Radiation Study in Vicinity of Humboldt Bay Power Plant,Annual Rept 19861987-08-28028 August 1987 Forwards Repts Entitled Radioactive Effluent Releases & Waste Disposal from Humboldt Bay Power Plant Unit 3 for Jan-June 1987 & Environ Radiation Study in Vicinity of Humboldt Bay Power Plant,Annual Rept 1986 HBL-87-052, Forwards Responses to NRC 870723 Request for Addl Info Re Safstor Tech Specs.Revised Set of Tech Specs Will Be Submitted After NRC Review of Responses1987-08-21021 August 1987 Forwards Responses to NRC 870723 Request for Addl Info Re Safstor Tech Specs.Revised Set of Tech Specs Will Be Submitted After NRC Review of Responses HBL-87-051, Forwards Rev 2 to Physical Security Plan & Changes.Changes Do Not Decrease Effectiveness of Plan & Submitted Per 10CFR50.54(p).Plan & Changes Withheld (Ref 10CFR73.21)1987-08-18018 August 1987 Forwards Rev 2 to Physical Security Plan & Changes.Changes Do Not Decrease Effectiveness of Plan & Submitted Per 10CFR50.54(p).Plan & Changes Withheld (Ref 10CFR73.21) HBL-87-047, Forwards Rev 3 to Custodial Safstor Facility QA Plan.Changes Include Clarification of Sections Re Packaging & Transportation,Fire Rating of Storage Containers,Audit Frequency & Ref to Reg Guide1987-07-30030 July 1987 Forwards Rev 3 to Custodial Safstor Facility QA Plan.Changes Include Clarification of Sections Re Packaging & Transportation,Fire Rating of Storage Containers,Audit Frequency & Ref to Reg Guide HBL-87-020, Forwards Change Pages for Rev 1 to Facility Physical Security Plan to More Accurately Describe Certain Provisions of Plan.Encl Withheld (Ref 10CFR73.21)1987-04-30030 April 1987 Forwards Change Pages for Rev 1 to Facility Physical Security Plan to More Accurately Describe Certain Provisions of Plan.Encl Withheld (Ref 10CFR73.21) HBL-87-015, Forwards Proposed Rev 2 to Safstor Tech Specs.Rev Includes Changes to Chemistry Limits on Spent Fuel Storage Pool & Requirements for Surveillance Program for Boral Matl of Spent Fuel Assembly Containers1987-03-20020 March 1987 Forwards Proposed Rev 2 to Safstor Tech Specs.Rev Includes Changes to Chemistry Limits on Spent Fuel Storage Pool & Requirements for Surveillance Program for Boral Matl of Spent Fuel Assembly Containers ML20207R4571987-03-13013 March 1987 Forwards Endorsements 52 & 110 to Nelia Policies NF-228 & NF-113,respectively HBL-87-006, Forwards Public Version of Rev 7 to Corporate Emergency Response Plan Implementing Procedure 3.2, Corporate Communications Dept & County of Humboldt Contingency Plan, Nuclear Reactor,Humboldt Bay. W/870310 Release Memo1987-02-26026 February 1987 Forwards Public Version of Rev 7 to Corporate Emergency Response Plan Implementing Procedure 3.2, Corporate Communications Dept & County of Humboldt Contingency Plan, Nuclear Reactor,Humboldt Bay. W/870310 Release Memo HBL-87-002, Forwards Response to 861230 Request for Addl Info on Emergency Plan Supporting Util Proposed Safstor Decommissioning Plan1987-01-20020 January 1987 Forwards Response to 861230 Request for Addl Info on Emergency Plan Supporting Util Proposed Safstor Decommissioning Plan DCL-87-006, Requests That Technical Correspondence Be Addressed to Author at Listed Address,Per Encl .Encl NRC Re Results of Peebles Electrical Machines Insp Mistakenly Addressed to Jo Schuyler1987-01-12012 January 1987 Requests That Technical Correspondence Be Addressed to Author at Listed Address,Per Encl .Encl NRC Re Results of Peebles Electrical Machines Insp Mistakenly Addressed to Jo Schuyler HBL-86-039, Forwards Rev 1 to Proposed Physical Security Plan,Based on Discussions W/Nrc & Description of Changes.Encls Withheld (Ref 10CFR73.21)1986-11-17017 November 1986 Forwards Rev 1 to Proposed Physical Security Plan,Based on Discussions W/Nrc & Description of Changes.Encls Withheld (Ref 10CFR73.21) HBL-86-035, Forwards Alternatives & Issues for Extended Storage of Spent Nuclear Fuel from Humboldt Bay Power Plant,Unit 3 & Extended Fuel Storage in Existing Onsite Humboldt Bay Unit 3 Storage Pool. Ack of Receipt Requested1986-10-29029 October 1986 Forwards Alternatives & Issues for Extended Storage of Spent Nuclear Fuel from Humboldt Bay Power Plant,Unit 3 & Extended Fuel Storage in Existing Onsite Humboldt Bay Unit 3 Storage Pool. Ack of Receipt Requested HBL-86-032, Forwards PG&E Responses to Public Comments on Des for Decommissioning Humboldt Bay Unit 3. Ack Receipt of Matl on Encl Ltr Requested1986-10-20020 October 1986 Forwards PG&E Responses to Public Comments on Des for Decommissioning Humboldt Bay Unit 3. Ack Receipt of Matl on Encl Ltr Requested HBL-86-029, Notifies That No Operator Licensing Exams Planned for Facility,As Util in Process of Decommissioning & Placing Unit in Safstor Mode for long-term Storage,Per Generic Ltr 86-14.Related Correspondence1986-09-24024 September 1986 Notifies That No Operator Licensing Exams Planned for Facility,As Util in Process of Decommissioning & Placing Unit in Safstor Mode for long-term Storage,Per Generic Ltr 86-14.Related Correspondence HBL-86-027, Forwards Radioactive Effluent Releases & Waste Disposal, Jan-June 1986 & Environ Radiation Study in Vicinity of Humboldt Bay Power Plant,Eureka,Ca,Annual Rept 19851986-08-28028 August 1986 Forwards Radioactive Effluent Releases & Waste Disposal, Jan-June 1986 & Environ Radiation Study in Vicinity of Humboldt Bay Power Plant,Eureka,Ca,Annual Rept 1985 HBL-86-026, Forwards Comments on Des for Decommissioning of Humboldt Bay Power Plant,Unit 3.Fission Chamber Strings Cut Up to Separate Chambers & Minimize Stored Waste Vol1986-08-14014 August 1986 Forwards Comments on Des for Decommissioning of Humboldt Bay Power Plant,Unit 3.Fission Chamber Strings Cut Up to Separate Chambers & Minimize Stored Waste Vol DCL-86-186, Informs of Reorganization & Reinstatement of Util Onsite Project Engineering Group.Changes Listed1986-06-30030 June 1986 Informs of Reorganization & Reinstatement of Util Onsite Project Engineering Group.Changes Listed HBL-86-023, Requests Approval for Offsite Disposal of Listed Very Low Radwastes as Produced,W/O Individual Authorization.Util Will Sample Wastes & Monitor Radioactivity Per NRC Approved 831027 & 840407 Transmittals.Fee Paid1986-06-17017 June 1986 Requests Approval for Offsite Disposal of Listed Very Low Radwastes as Produced,W/O Individual Authorization.Util Will Sample Wastes & Monitor Radioactivity Per NRC Approved 831027 & 840407 Transmittals.Fee Paid ML20211B9971986-06-0202 June 1986 Forwards Endorsement 108 to Nelia Policy NF-113 HBL-86-019, Forwards Rev 2 to Safstor QA Plan. Section 2.0 Revised to Reflect Applicable Organization Changes,Section 3.1.3, Insps Added to Describe Applicable Insp Requirements & Section 3.1.4, Nonconformance Control Revised1986-05-23023 May 1986 Forwards Rev 2 to Safstor QA Plan. Section 2.0 Revised to Reflect Applicable Organization Changes,Section 3.1.3, Insps Added to Describe Applicable Insp Requirements & Section 3.1.4, Nonconformance Control Revised HBL-86-020, Forwards Errata to 860313 Rev 1 to Proposed Safstor Tech Specs,Including Revised Figure VII-1, Offsite Organization Chart & Page VII-101986-05-23023 May 1986 Forwards Errata to 860313 Rev 1 to Proposed Safstor Tech Specs,Including Revised Figure VII-1, Offsite Organization Chart & Page VII-10 ML20198B9061986-05-16016 May 1986 Forwards Application to Amend License DPR-7,consisting of License Amend Request 86-02,upgrading Stack Gas Monitoring Sys & Reducing Number of Condensate Demineralizer Beds.Fee Paid HBL-86-018, Suppls 840730 Decommissioning Amend Request for License DPR-7 to Perform Mods Re Upgrading Spent Fuel Storage Pool, Pool Cover & Redundant Level Monitors & Replacing Stack Monitor to Reflect possession-only Status1986-05-16016 May 1986 Suppls 840730 Decommissioning Amend Request for License DPR-7 to Perform Mods Re Upgrading Spent Fuel Storage Pool, Pool Cover & Redundant Level Monitors & Replacing Stack Monitor to Reflect possession-only Status ML20205P0711986-05-14014 May 1986 Forwards License Amend Request 86-01 to License DPR-7, Modifying Security Plan to Reflect possession-only Status of Plant.Security Plan Supporting Decommissioning & Safstor Withdrawn.Fee Paid ML20210L3051986-04-15015 April 1986 Forwards Endorsements 48 & 107 to Nelia Policies NF-228 & NF-113,respectively & Endorsement 19 to Maelu Policy MF-103 HBL-86-006, Forwards Rev 1 to Safstor QA Program & Description of Rev1986-03-14014 March 1986 Forwards Rev 1 to Safstor QA Program & Description of Rev HBL-86-005, Forwards Rev 1 to Tech Specs for Decommissioning of Humboldt Bay Power Plant Unit 3. Rev Incorporates Util Commitments in Response to Questions During NRC Review of Decommissioning Plan1986-03-13013 March 1986 Forwards Rev 1 to Tech Specs for Decommissioning of Humboldt Bay Power Plant Unit 3. Rev Incorporates Util Commitments in Response to Questions During NRC Review of Decommissioning Plan HBL-86-004, Forwards No Significant Hazards Determination,Per Generic Ltr 86-03,supporting 831216 License Amend Request LAR 83-01, Amending License DPR-7 to Delete Requirements of Item E.2e of 760521 Order for Mod of License Re Seismic Network1986-03-0707 March 1986 Forwards No Significant Hazards Determination,Per Generic Ltr 86-03,supporting 831216 License Amend Request LAR 83-01, Amending License DPR-7 to Delete Requirements of Item E.2e of 760521 Order for Mod of License Re Seismic Network ML20140E7281986-01-23023 January 1986 Forwards Endorsement 106 to Nelia Policy NF-113 HBL-85-061, Submits Rept Re Investigation of Radwaste Shipments for Which Notification of Receipt Not Received within 20 Days After Transfer.Formal Notification of Receipt of 851118 & 19 Shipments Received on 851211 & 10,respectively1985-12-20020 December 1985 Submits Rept Re Investigation of Radwaste Shipments for Which Notification of Receipt Not Received within 20 Days After Transfer.Formal Notification of Receipt of 851118 & 19 Shipments Received on 851211 & 10,respectively HBL-85-059, Forwards Rev 1 to Humboldt Bay Power Plant Unit 3 - Safstor QA Plan, Replacing Attachment 4 of 840731 Decommissioning Plan.Basis for & Description of Approach Included1985-12-13013 December 1985 Forwards Rev 1 to Humboldt Bay Power Plant Unit 3 - Safstor QA Plan, Replacing Attachment 4 of 840731 Decommissioning Plan.Basis for & Description of Approach Included HBL-85-058, Cancels 851203 & 10 Advance Notifications of Nuclear Waste Shipment.Advance Notification Not Needed Since Quantity of Radioactive Matl Contained in Shipment Does Not Exceed Quantities Listed in 10CFR71.97(b)(3)1985-12-12012 December 1985 Cancels 851203 & 10 Advance Notifications of Nuclear Waste Shipment.Advance Notification Not Needed Since Quantity of Radioactive Matl Contained in Shipment Does Not Exceed Quantities Listed in 10CFR71.97(b)(3) 1990-07-24
[Table view] |
Text
v PACIFIC GAS AND E LE C T RIC C O M PANY h @?b'/5i i
{ 77 BEALE STREET
- SAN FR ANCISCO, C ALIFOR NI A 94106 . (415)781-4211
- TWX 910-372 6587 d AMES D. SHIFFE R wct paissotwY ucuo . . " "'**
June 17, 1986 PGandE Letter No.: HBL-86-023 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Docket No. 50-133, OL-DPR-7 Humboldt Bay Power Plant, Unit 3 Very Low-Level Radioactive Haste Disposal
Dear Mr. Denton:
On October 27, 1983, Pacific Gas and Electric Company (PGandE) requested approval to dispose of low-level radioactive contaminated waste at a Class I disposal site for hazardous waste. The waste included oil and sludge from an onsite oily water separator (OHS) and is classified as hazardous under Federal Resource Conservation and Recovery Act and State of California regulations.
The NRC Staff reviewed PGandE's request and concluded on May 7, 1984, that the proposed transfer of the waste to the IT Corporation's Benicia, California disposal site was acceptable. The waste was transferred in September 1984. '
On April 25, 1985, PGandE requested a similar approval for disposal of low-level radioactive contaminated wastewater treatment pond sludge and fossil fueled boiler firebox waste. This approval was granted by the NRC on ,
September 3, 1985. Shipment of the waste is pending at this time.
Regulations applying to the operation of the wastewater treatment ponds and the OHS system require that accumulated waste material be removed and that the ponds be inspected annually. In anticipation of cleaning out the OHS system, 1 a sample of the sludge was taken to determine if any residual contamination i was present. Gamma spectroscopy analysis of the sample indicated that the present level of radioactive contamination was approximately 2 pCi/gm of Cs-137 and Co-60, respectively, the principal isotopes present. This is less than the level of radioactive contamination in the sludge transferred in September 1984. The source of the present radioactive contamination appears I to be residual material remaining in the OHS following sludge removal and also I residual material present in the drain systems supplying the OHS. The OHS l effluent flows to the wastewater treatment ponds, thereby providing a possible !
route for radioactive contamination to reach the ponds. The detection of very low levels of radioactive contamination in the OHS and wastewater treatment pond systems in the future is expected due to the very low-level detection limits of the present plant instrumentation. \
pw ADOCK~05000133 ~0-as 41 kC.C., c c4fcC4 g450.oo
\
Mr. H. R. Denton i PGandE Letter HBL-86-023 '
June 17, 1986 Page 2 PGandE expects to generate the following quantities of wastes that may require NRC approval prior to disposal under 10 CFR 20.302(a): l HASTE TYPE QUANTITY Hastewater Treatment Pond Sludge 57,000 kilograms / year Olly Hater Separator Sludge 3,800 kilograms / year Boiler Firebox Haste 500 cubic feet (generated infrequently)
The levels of radioactivity in the wastes are expected to decrease progressively with time and to be less than the values stated below.
Co 60 <10 pCi/gm Cs 137 <10 pC1/gm Sr 90 <1 pCi/gm Transuranic alpha activity <10% of total activity.
In accordance with 10 CFR 20.302(a), PGandE requests approval to dispose of /
the subject wastes as produced without individual authorization. PGandE cill
~
sample the waste and ensure that the radioactivity in the waste does not exceed the levels evaluated in the radiological assessments presented in our earlier submittals which were appreved by NRC (refer to Attachments I and II). Furthermore, if greater than background levels of radioactivity are detected in the wastes, PGandE will adhere to the NRC approved disposal procedure for the wastes. Solid material will be transported directly to IT Corporation's Benicia, California disposal site using approved hazardous waste haulers. Sludges will be transported to IT Corporation's Martinez, California site, placed in evaporation ponds, and evaporated to a suitable dryness. The resulting dried materials will be buried in the Benicia hazardous waste landfill . Final coverage of the landfill will consist of a multilayered, impervioJs, soil cover at least 30 inches thick.
Additional information regarding this application is provided in the following ,
three enclosures:
Enclosure 1 - Evaluation of Radiological Hazard - Oily Hater Separator Sludge Enclosure 2 - Evaluation of Radiological Hazard - Hastewater Pond Sludge and Boiler Firebox Haste Enclosure 3 - Evaluation of the Environment at IT Corporation Class I Disposal" Sites L
l Mr. H. R. Denton !
PGandE Letter HBL-86-023 June 17, 1986 .
Page 3 l An application fee of $150 is provided pursuant to 10 CFR 170. !
Questions regarding this application should be directed to Mr. Rudy Uba at !
(415) 972-6577. '
Kindly acknowledge receipt of this material on the enclosed copy of this !
letter and return it in the enclosed addressed envelope. .
Sincerely, t Enclosures (3) cc: P. B. Erickson l J. B. Martin i Humboldt Distribution '
Service List 0873S/0045K/RHS/1401 m
PGandE Letter No.: HBL-86-023 ENCLOSURE 1 EVALUATION OF RADIOLOGICAL HAZARD OILY WATER SEPARATOR SLUDGE Excerpted from October 27, 1983 letter from J. O. Schuyler, V.P. Nuclear Power Generation, Pacific Gas and Electric Company, to H. R. Denton, Director Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory i Commission,
Subject:
Humboldt Bay Power Plant, Unit No.
3 Very Low-Level Radioactive Haste Disposal.
I l
0873S/0045K
ENCLOSURE 1 EVALUATION OF RADIOLOGICAL HAZARD OILY HATER SEPARATOR SLUDGE The radiological hazard from the contaminated sludge was evaluated for several dose pathways and scenarios, both normal and accidental. The evaluation was based on the isotopic analysis reported in Table I. This analysis identified four radionuclides with concentrations above those found in a control sample of soil from Eureka, California -- cobalt-60, cesium 134, cesium-137, and thorium-234. After correction for background levels, conversion to a volume basis, and averaging, the nuclide concentrations in the sludge are:
Concentration Conc. over Background Ratio Nuclide (uCi/cc) (uCi/cc) to MPCw.i
~
Co-60 7.85 x 10-6 7.83 x 10-6 .262 Cs-134 9.09 x 10-8 7.89 x 10-8 .002 Cs-137 4.55 x 10-6 4.52 x 10-6 ,113 Th-234 5.66 x 10-7 2.41 x 10-7 .012 The background levels were removed so that the concentration of each nuclide could be compared with the maximum permissible concentration above background (MPC) reported in 10 CFR 20, Appendix B, Table II. The HPC in water for insoluble species was used for comparison because the sludge has no credible airborne pathway, and because the sludge is a precipitated sediment and therefore insoluble. Average rather than maximum values were used because the sludge hauling truck holds far more than one bed, and because the truck will be filled alternately from beds in OHS #1 and OHS #2.
The last column of the table above (Ratio to HPCw,1) shows that if the sludge were a liquid instead of a semi-solid, it could be discharged without 10 CFR 20 restrictions.
Normai Non-Accident Exoosure Rates The highest exposure rate of any normal scenario is found one meter from tne mid-point of the tank truck hauling the sludge. Using the concentrations listed above (including background) and the dimensions of the largest sludge hauling truck, this rate was estimated as .0048 mrem /hr. Other exposure rates, e.g., to the truck driver and the disposal site workers, are far lower. Thus, external radiation exposure from the sludge was determined to be insignificant. There are no normal scenarios that result in internal exposure.
Accidental Excosure Rates Two accident scenarios were examined for their dose potential. The first was a postulated spill during sludge handling or transport. The second was the postulated leaching of the material from the waste disposal facility.
0873S/004SK 1-1
~
In the first scenario, a sludge spill would pose a potential hazard to the driver, and also to the public in the vicinity if the spill were not confined. The hazard to people on the scene would not credibly lead to an inhalation or ingestion exposure, and any surface contamination could be washed off without consequence. If the spill were unconfined, contamination of a drinking water source could occur. The internal dose to an individual after drinking such contaminated water was estimated by comparing the nuclide concentrations in the sludge to those given in 10 CFR 20, Appendix B, Table II, as shown in the above table. The average waste is assumed to contaminate a drinking water source. The nuclide concentration in the water is conservatively estimated to be 1% of that in the sludge, due to dilution and the insolubility of the sludge. Thus, it is estimated that the whole body dose to an individual, from a chronic exposure to this drinking water, would be 0.4% of the Part 20 limit, or 2.0 mrem / year.
Finally, potential release of the contaminated sludge from a Class I disposal facility was considered with respect to radiological impact. As in the ,
previous scenario, contamination of drinking water is the principal pathway.
Tne dose to an individual drinking contaminated water would differ from the previous scenario in two ways. First, the sludge would be diluted by other wastes (non-radioactive) present in the disposal facility. This would be in addition to the dilution provided by the drinking water source. Second, the disposal facility contains natural and engineered barriers to prevent offsite release of the wastes which reduce both the probability and consequences of such a release. These two differences indicate a lower radiological exposure for the disposal facility release than for the transportation spill accident.
We estimate this dose to be less than 1 mrem / year to an individual.
0873S/0045K 1-2 l
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(
TABLE I ,
i ISOTOPIC ANALYSIS OF OILY HATER SEPARATOR SLUDGE (conc. in4Ci/gm, /'- density of medium, gm/cc)
Date of Analysis 11/04/82 i TOTAL
- 1 OHS #2 ONS #1 OHS #2 OHS ACTIVITY Soil Sample Isotope Bed /-1.03 Bed /'-1.03 S_ ump /'-1.007 Sumo /-1.007 mci )
- From Eureka l 1.9010.06x10-6 9.86 0.1x10-6 1.86 0.06x10-6 9.28 0.7x10-7 155.0 2.6 0.54x10-8 137Cs 1.4 0.37x10-8 7.34 1.4x10-8 1.55 0.3x10-7 5.43 2.2x10-8 <1.38x10-8 3.1 134Cs 1.64+0.07x10-6 1.72 0.02x10-5 1.99 0.1x10-6 7.96+0.2x10-6 267.8 <3.9x10-9 60co 19.3 3.19 0.48x10-7 234Th 5.33 3.1x10-7 <5.38x10-7 4.75 3.4x10-7 <7.55x10-7 3.69 1.6x10-7 <2.97x10-7 <4.19x10-7 <4.14x10-7 5.47+0.71x10-7 226Ra -
212Pb 1.77 0.3x10-7 2.24 0.4x10-7 1.53 0.3x10-7 <3.44x10-8 2.32 0.09x10-7 214Pb 1.99 0.5x10-7 3.34 0.9x10-7 2.23 0.6x10-7 NOT DETECTED 2.14 0.16x10-7 2.27 0.8x10-7 NOT DETECTED NOT DETECTED NOT DETECTED 2.87 0.38x10-7 228Ac 8.8 0.6x10-8 20871 6.62il.6x10-8 6.62 2.9x10-8 3.62 1.5x10-8 NOT DETECTED 2.09 0.3x10-7 4.23 1.3x10-7 1.75 0.3x10-7 NOT DETECTED 2.78 0.79x10-7 214Bi 40g 3.50 0.3x10-6 3.62 0.3x10-6 2.55 0.3x10-6 <l.22x10-7 2.58 0.12x10-6 Gross alpha ** 1.4+0.2x10-6 0.7+0.2x10-6 Approximate Height, gm 1.46x107 1.17x107 4.28x106 4.28x106 3.486x107 i
i
- Approximate Volume, cc 1.42x107 1.14x107 4.25x106 4.25x106 3.41x107
- 0f nuclides found above the background sample concentrations.
a
- Analysis was performed using " Standard Methods for the Examination of Hater and Hastewater," Part 703 for gross alpha (Published by American Public Health Association, American Hater Horks Association and Hater Pollution Control Federation).
4 i
l 0873S/0045K 1-3
PGandE Letter No.: HBL-86-023 ENCLOSURE 2 EVALUATION OF RADIOLOGICAL HAZARD WASTEWATER POND SLUDGE AND BOILER FIREBOX WASTE Excerpted from April 25, 1985 letter (PGandE Letter No.:
HBL-85-016) from J. D. Shiffer, VP Nuclear Power Generation, to H. R. Denton, Director Office of Nuclear Reactor Regulation, U. S. Nuclear Regulatory Commission,
Subject:
Humboldt Bay Power Plant, Unit No. 3 Very Low-Level Radioactive Waste Disposal.
f 0873S/0045K
ENCLOSURE 2 1 EVALUATION OF RADIOLOGICAL HAZARD WASTEHATER POND SLUDGE AND BOILER FIREBOX HASTE A composite sample of each waste was analyzed for radioactivity. The following nuclides and activities were detected:
ACTIVITY IN ACi/am(I)
DATE OF ANALYSIS 12/27/84 HASTEWATER TREATHENT FIREBOX ISOTOPE POND SLUDGE DEPOSITS -
K-40(2) 3.19 .86 x 10-6 3.68 .44 x 10-6 Co-60 1.06 .14 x 10-6 5.15 .52 x 10-7 Sr-90 <1.0 x 10-7 3.39 2.10 x 10-7 Cs-134 1.28 .40 x 10-7 <3.0 x 10-8 Cs-137 6.11 .43 x 10-6 3.90 .35 x 10-7 U-233, 234 1.20 .14 x 10-6 1.23 .14 x 10-6 U-235, 236 3.88 7.76 x 10-8 6.17 1.42 x 10-8 U-238 9.38 1.12 x 10-7 1.28 .14 x 10-6 Pu-238 7.94 3.81 x 10-9 9.40 5.92 x 10-9 Pu-239, 240 2.42 .68 x 10-8 9.40 5.92 x 10-9 Ra-226 4.48 1.03 x 10-7 2.39 0.17 x 10-6 (1) Dry weight activity, 171. solids content.
(2) Naturally occurring nuclide, not included in dose calculations.
0873S/0045K 2-1 i
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Four exposure pathways were examined and several dose calculations were l performed. Results are given below. The four pathways are:
o External exposure from surface-deposited waste o External exposure from a transport truck o Ingestion of food grown at disposal site o Inhalation of resuspended solids at disposal site External Exoosure from Surface-Decosited Haste A hypothetical employee of the disposal site was assumed to stand on the disposal field. He is exposed for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per year. A plane radiation source was modeled using Reference 1, to calculate dose. The surface activity of this source was calculated assuming the top 10 cm of sludge or firebox deposits contribute all the surface dose. Self-shielding of the sludge or firebox deposits was not taken into account. Self-shielding would reduce the calculated dose. The estimated annual doses from the sludge and fire deposits ,
were 0.75 mrem and 0.45 mrem, respectively.
External Exoosure from a Transoort Truck The dose rate around a 5,000 gallon tank truck, filled with the wastes, was calculated. The truck was modeled as a cylindrical radiation source. The dimensions are, radius: 0.9 m, length: 7.6 m. A dose rate of 0.01 mR/hr was calculated at 100 cm from the midpoint of the length. Similarly, the dose rate around a 20-ton dump truck filled with firebox deposits to a height of 0.61 m was calculated. The truck was modeled as a rectangular radiation source with dimensions of 6.1 m length, and 2.4 m width. A dose rate of
.00004 mR/hr was calculated at 100 cm from the midpoint of the length. Based
! on this calculation, this pathway will not lead to significant exposure of any individual or group.
Incestion of Food Grown at Discosal Site It is not necessary to calculate doses from this pathway. The absorption of radionuclides by the plant roots would be an inefficient mechanism of radiation exposure. At most, a small percentage of the deposited radionuclides would be absorbed by plants in one growing season. Furthermore, the fraction of material taken up declines rapidly in subsequent growing seasons. An area that had enough soil contamination to produce unacceptable doses by plant uptake and ingestion of food plants would be forbidden already by other restrictions, including, for example, external irradiation.1/
Thus, the dose from this pathway would be a small fraction of the doses from the other three pathways.
Inhalation of Resusoended Solids at Discosal Site Plant employees working at the disposal site are susceptible to internal exposures if resuspended solids are inhaled. Dosp; from this pathway were calculated using a resuspension factor gf 10-7/ c M', dose conversion factors, and breathing rates for adults 4/. Solids from the top 1.0 cm of sludge would be available for resuspension. Horker exposure is 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per 0873S/0045K 2-2
year. Exposure to the sludge would result in a committed annual dose of 3.1 mrem to the lungs and 3.3 mrem to the bone. Exposure to the firebox deposits would give an annual dose of 7.4 mrem to the lungs and 7.0 mrem to the bone.
References
- 1. U.S. NRC, Reactor Safety Study, Hash-1400, Appendix VI, Pages 8-9 to 8-14.
- 2. U.S. NRC, Regulatory Guide 1.109, March 1976.
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4 0873S/0045K 2-3
PGandE Letter No.: HBL-86-023 ENCLOSURE 3 EVALUATION OF THE ENVIRONMENT AT IT CORPORATION CLASS I DISPOSAL SITES Excerpted from April 25, 1985 letter (PGandE Letter No.:
HBL-85-016) from J. D. Shiffer, VP Nuclear Power Generation, to H. R. Denton, Director Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission,
Subject:
Humboldt Bay Power Plant, Unit No. 3 Very Low-Level Radioactive Haste Disposal.
i i
0873S/0045K l
ENCLOSURE 3 EVALUATION OF THE ENVIRONMENT AT IT CORPORATION CLASS I DISPOSAL SITES This enclosure provides environmental information on the proposed disposal of the Humboldt Bay Power Plant sludga at IT Corporation's Class I disposal facilities as outlined in 10 CFR 20.302(a). It is expected that the waste will be processed at IT Corporation's Martinez, California site where solid will be separated from liquid waste. The liquid will be evaporated to atmosphere. The solids, including heavy metals, will be buried at IT Corporation's Benicia, California Disposal site. This enclosure includes:
o a description of the proposed manner and conditions of disposal; o an evaluation of the disposal site environment, including its topography, geology, and meteorology; o an analysis of groundwater and surface water flows in the general area, and their uses; o a description of nearby land,uses and facilities; o a description of procedures and plans for minimizing the risk of unexpected or hazardous exposure, including the site's emergency plan, its closure plan, and its post-closure plan.
The information contained in this enclosure, unless otherwise referenced, was either provided directly to PGandE by IT Corporation as is contained in the
" Operation Plan for Hazardous Waste Class I Disposal Site at Benicia (Site Operation Plan)" or submitted by IT Corporation to the State of California Department of Occupational Health Services in August 1983.
Manner and Conditions of Discosal (at Martinez. California Site)
Unless PCB is detected, liquid sludges will be treated at IT Corporation's Martinez Treatment plant where heavy metals will be precipitated. A centrifuge will then be utilized to separate the solid and liquid phases.
Solids will be hauled to Benicia for disposal and liquids discharged to the Martinez solar evaporation ponds.
Liquid sludges containing acceptable levels of PCBs will be discharged directly to Benicia's evaporation ponds. To protect against overflows during heavy rains, the evaporation and storage ponds at Martinez and Benicia are required to maintain a freeboard specified in the facility's Haste Discharge Requirements. Once a pond is filled, the contents will be evaporated to a
" dryness" condition with the consistency of a heavy moist solid. Therefore, there can be no evolution of dust from these " dried" bottoms. Finally, the bottoms will be transferred to the landfill, covered with clean fill, and compacted.
l 0873S/0045K 3-1
Toooaraohv The Benicia disposal site is located in a region of low hills between San Pablo Bay and the Suisun Marsh. The site elevation is above the flood plain and ranges from approximately 280 feet to 850 feet above sea level. The site is reached by a single private road which branches off a secondary road two miles from Interstate Highway 680. Figure 1 shows the location and topography of the site.
Geoloav The disposal site is underlain by marine sedimentary beds of Cretaceous age.
The beds consist primarily of impermeable, shaley claystones interbedded with thin lenses of sandstone and limestone. The sandstone is very fine-grained, of low to moderate hardness, and blocky. Because the fractures in the sandstone are tight below the weathered zone, the sandstone is believed to j have a very low permeability along fractures and bedding planes, as well as .
through the grain. Thus, all of the permeability (basicallylessthan10gnderlyingstrataareofverylow cm/sec). This is an essential feature of the site.
The Cretaceous claystone has weathered into a permeable zone varying in thickness from a few inches to several feet. The weathered zone grades upward into a clay topsoil, which meets the stability and permeability requirements of the State Hater Resources Control Board if compacted to 90% of maximum density.
Meteorology Climate and air quality at the disposal site are greatly influenced by westerly and northwesterly winds blowing from San Pablo Bay and the Sonoma Valley. A wind rose map for the site is attached. The site is in the Bay Area Air Quality Management District, which maintains monitoring stations in Concord, nine miles from the site.
Groundwater Hydroloav No aquifer is presently underlying the site.1/ The water bearing zones below the surface have very low permeabilities and do not yield significant.
water to wells or springs. Therefore, groundwater flows should be slow, and migration of fluids to any unidentified deep water bearing zones below the investigated depth would require very long periods of time.
Chemical analysis has shown that the water in monitoring wells is similar to water extracted from the soil, and is unaffected by the waste from the pond nearest the wells. This indicates that the chemical makeup of the groundwater is determined by the petrochemistry, not by leaching from the waste ponds.
I As defined by the EPA in 40 CFR 260.
0873S/0045K 3-2 l
No usable groundwater underlies the site, and the only wells on or near the site are monitoring wells.
Surface Water Hydroloav The site is contained in a single watershed, which is interrupted by a lower site dam for containment of all wastes in the event of pond containment failure. The dam is approved, certified, and inspected by the California Bureau of Dam Safety.
The site receives approximately fourteen inches of rainfall per year. Runoff from all waste handling areas is contained within the onsite surface impoundments until evaporated. Runoff from non-waste areas is diverted around the disposal areas to the lower site dam or to an offsite drainage system.
The water behind the lower site dam is tested, treated if necessary, and discharged under a National Pollutant Discharge Elimination System permit.
The offsite drainage system is sampled monthly to verify water quality. .
No public or private water supply is connected to the facility, or fed from the site's watershed. t Nearby Land Uses and Facilities The disposal site is situated 3/4 mile from the nearest public roadway. It is i surrounded by two barbed wire fences, one around the active portion and the other around the buffer zone. The access road and the active portion fence i'
are posted with signs. Access is controlled by a key card gate in the buffer zone fence. The private access road then passes in front of the facility office in view of the office personnel. The gate is padlocked when the site is unattended. The facility office and maintenance building are the only structures on site. Both are located 100 feet from the nearest waste pond.
The area around the disposal site is wooded and generally uninhabited. There is a small farm 0.6 miles from the edge of the site, at the mouth of the next canyon to the west. Interstate Highway 680 passes one mile east of the site boundary at its closest point. There are an oil refinery and industrial parks approximately 1.5 miles south of the site. The nearest urban center is the town of Benicia (population 18,233), approximately four miles south of the site.
! Emeraency Resoonse
- The Site Operation Plan includes a " contingency plan" to minimize hazards to human health and the natural environment while responding to any emergency.
The plan includes:
o a facility description; o names, telephone numbers, and pager numbers of the emergency coordinators; i
t 0873S/0045K 3-3
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o names and telephone numbers of nearby public agencies with emergency response roles; o procedures for response to releases, fires, explosions, personal !
injuries, and equipment damage; o procedures for cleanup and restart after a release; o locations of fire extinguishers, telephones, and protective equipment; o specifications and instruction manuals for protective equipment; o checklist for inspections after any severe natural phenomenon or event;
)
o site evacuation plan. .
Closure and Post-Closure Plans ;
The Site Operation Plan provides a site closure plan which was developed in '
accordance with state and federal regulations. The closure plan is intended to minimize long term control and maintenance of hazardous material, and to eliminate all threats to human health or the natural environment. i As the landfill expansion occurs, most of the ponds will be emptied and incorporated into the expanded landfill areas. The closure of the landfill area will be a continuous process over the 35 year design life of the facility. Pond areas which are outside of the final footprint of the landfill will be decontaminated. Closure will be performed on an annual basis on those portions of the landfill that have reached maximum elevation. Final coverage of the landfill will consist of the following components in descending order:
Soil Cover Geotextile Drainage Layer Synthetic Cover Liner Clay Cover Post-closure activities will continue for thirty years after closure. A written post-closure plan has also been designed by the site operator in accordance with state and federal regulations to maintain the integrity of the certified compliance of closure. The activities will consist of quarterly groundwater monitoring, maintenance and monitoring of the waste containment systems, and annual report to the state and Environmental Protection Agency.
0873S/0045K 3-4 l
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Topogrsp. - Orientation: On the ocuth oide of a hill clong e.ain ridgelina
,y*n s,couchern Solano County. The local topography forces the prevsiling vest-southwest vinds to shift to vest-northwest.
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! WIND STATION S-08 riGuat IT BENICIA FACILITY ,
b DESIGNED BY : ORAWN bye NVIROSCIENCE
- SCALEe 1:24000 g PROJECT NO 8 5145 - l D AT E e 1 1 8 4 _'
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$ IT Corp. - Benicia Facility FIGURE h Wind Rose - wind Station S-08 X DESIGNED BY e DR AWN BY JNS CK: SJZ
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k PROJECT NO ' 514 5 SCALE: -
l DATE e 11-15-84 J
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