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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P7111999-10-26026 October 1999 Informs That Licensee 990330 Response to GL 97-06 Provides Reasonable Assurance That Condition of Licensee Steam Generator Internals Is in Compliance with Current Licensing Bases for Plant ML20217K3571999-10-21021 October 1999 Discusses Use of SONGS as Generic Safety Issue 191 Ref Plant.Future Requests for Info & Addl Coordination Activities Be Handled Through D Evans of Organization.With Diskette ML20217K8541999-10-21021 October 1999 Forwards Revised Pages to ERDS Data Point Library,Per Requirements of 10CFR50,App E,Section VI.3.a.Described Unit 2 & 3 Changes for 2/3R7813 Were Completed on 990924 ML20217L9491999-10-21021 October 1999 Forwards SONGS Emergency Response Telephone Directory, for Oct-Dec 1999 ML20217J8631999-10-15015 October 1999 Forwards Insp Repts 50-361/99-12 & 50-362/99-12 on 990808- 0918.One Violation Identified Involving Inoperability of Emergency Diesel Generator in Excess of Allowed Outage Time ML20217E3221999-10-13013 October 1999 Forwards MORs for Sept 1999 for Songs,Units 2 & 3.No Challenges Were Noted to Psvs for Either Units 2 or 3 ML20217E7671999-10-12012 October 1999 Forwards Rev 62 to NRC Approved Aug 1983, Physical Security Plan,Songs,Units 1,2 & 3, IAW 10CFR50.54(p).Changes,as Described in Encls 1 & 2,do Not Reduce Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20217B5981999-10-0606 October 1999 Informs That Staff Concluded That All Requested Info for GL 98-01, Year 2000 Readiness in Us Nuclear Power Plants, Provided for San Onofre Nuclear Generating Station,Units 2 & 3 ML20216H8741999-09-29029 September 1999 Provides Requested Written Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Lab Testing of Charcoal Adsorber Samples for Creacus & Pacu Satisfies Listed Requirements ML20216H8541999-09-29029 September 1999 Submits Encl Request for Relief from ASME Code,Section III Requirements in 10CFR50.55(a)(3) to Use Mechanical Nozzle Seal Assembly as Alternate ASME Code Replacement at SONGS, Units 2 & 3 for Period of Operation Beginning with Cycle 11 ML20216J2631999-09-28028 September 1999 Forwards Copy of Final Accident Sequence Precursor (ASP) Analysis of Operational Event at Songs,Unit 2,reported in LER 361/98-003 ML20212H4461999-09-28028 September 1999 Forwards Suppl Info,As Discussed with NRC During 990812 Telcon,To Support Risk Informed Inservice Testing & GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20212G5611999-09-24024 September 1999 Informs NRC That SCE Remains Committed to Performing Eddy Current Examinations of 100% of Reactor Vessel Head Penetrations at Songs,Unit 3.Exams Will Not Be Performed During Cycle 11 RFO 05000361/LER-1999-005, Forwards 30-day follow-up LER 99-005-00,describing Loss of Physical Train Separation in Control Room.Any Actions Listed Intended to Ensure Continued Compliance with Existing Commitments1999-09-23023 September 1999 Forwards 30-day follow-up LER 99-005-00,describing Loss of Physical Train Separation in Control Room.Any Actions Listed Intended to Ensure Continued Compliance with Existing Commitments ML20212D9921999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of San Onofre.Nrc Plan to Conduct Core Insps & One Safety Issues Evaluation of MOVs at Facility Over Next 7 Months. Details of Insp Plan Through March 2000 Encl ML20212A4061999-09-14014 September 1999 Forwards Revised Pages to ERDS Data Point Library.Described Unit 2 Changes for 2R7817 & 2R7828 Were Completed on 990818 & Unit 3 Change for 3R7828 Was Completed on 990903 ML20216E6031999-09-10010 September 1999 Provides Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Dtd 990820.Schedule Shown on Attachment 1, Operator Licensing Exam Data, Provides Util Best Estimate Through Cy 2003 ML20217B9011999-09-10010 September 1999 Responds to Which Addressed Concerns Re Y2K Issue & Stockpiling of Potassium Iodide (Ki) Tablets by Informing That San Onofre Nuclear Station Already Completed All Work Required to Be Ready for Y2K Transition ML20211K4191999-09-0303 September 1999 Final Response to FOIA Request for Documents.Documents Listed in App a Being Withheld in Part (Ref FOIA Exemptions 5 & 7) ML20211N0261999-09-0303 September 1999 Forwards Exemption from Certain Requirements of 10CFR50.44 & 10CFR50,app A,General Design Criterion 41 in Response to Util Request of 980910,as Supplemented 990719 & SER 05000206/LER-1999-001, Forwards LER 99-001-00 for Occurrence Re Unattended Security Weapon Inside Protected Area.Single Rept for Unit 1 Is Being Submitted,Iaw NUREG-1022,Rev 1,since Condition Involves Shared Sys & Is Applicable to Units 1,2 & 31999-08-31031 August 1999 Forwards LER 99-001-00 for Occurrence Re Unattended Security Weapon Inside Protected Area.Single Rept for Unit 1 Is Being Submitted,Iaw NUREG-1022,Rev 1,since Condition Involves Shared Sys & Is Applicable to Units 1,2 & 3 ML20211H3321999-08-30030 August 1999 Discusses 1999 Emergency Preparedness Exercise Extent of Play & Objectives.Based on Review,Nrc Has Determined That Exercise Extent of Play & Objectives Are Appropriate to Meet Emergency Plan Requirements ML20211J7151999-08-27027 August 1999 Forwards Insp Repts 50-361/99-09 & 50-362/99-09 on 990627- 0807.Two Violations Being Treated as non-cited Violations ML20211H8561999-08-23023 August 1999 Forwards SE Accepting Licensee 970625 Requests for Relief RR-E-2-03 - RR-E-2-04 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20211J5821999-08-23023 August 1999 Corrected Copy of ,Changing Application Date from 970625 to 990625.Ltr Forwarded SE Accepting Licensee 990625 Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section XI as Listed ML20210V4271999-08-16016 August 1999 Forwards Proprietary Certified Renewal Applications for SROs a Harkness,R Grabo & T Vogt & RO D Carter,Submitted on Facsimile Form NRC-398 & Certified NRC Form 396.Encls Withheld ML20210R6681999-08-13013 August 1999 Forwards Response to NRC RAI Re SCE License Amend Applications 173 & 159 for Songs,Units 2 & 3,proposed Change Number 485,which Requests Addition of SR to TS 3.3.9, CR Isolation Signal ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210Q6451999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for SONGS, Units 2 & 3,per TS 5.7.1.4.There Were No Challenges to Pressurizer Safety Valves for Either Units ML20210P5711999-08-11011 August 1999 Forwards Amend Application Number 189 for License NPF-10 & Amend Application Number 174 to License NPF-15,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Encl Calculation E4C-098 ML20210P4681999-08-11011 August 1999 Forwards COLR for Cycle 10 for Songs,Units 2 & 3,IAW TS Section 5.7.1.5.d, Colr. Changes to COLR Parameters Have Been Conducted IAW Approved COLR Methodologies & All Applicable Limits of Safety Analysis Were Met ML20210P6221999-08-10010 August 1999 Forwards Replacement Pages for Attachments E & F of Amend Application Numbers 168 & 154 for Songs,Units 2 & 3.Pages Are Provided to Correct Errors to Pagination & Headings in 970618 Submittal ML20210N9721999-08-10010 August 1999 Responds to Appeal of FOIA Request for Documents Re Osre Issue.No Osre Visit Scheduled for Sept 1996 at Plant,Per 990722 Telcon.V Dricks,In Ofc of Public Affairs Should Be Contacted Re Osre Issue ML20210N0901999-08-0909 August 1999 Informs That 990312 Application Requested Amends to Licenses DPR-13,NPF-10 & NPF-15,respectively,being Treated as Withdrawn.Proposed Change Would Have Modified Facility TSs Pertaining to SONGS Physical Security Plan ML20210N5051999-08-0909 August 1999 Forwards Cycle 10 Update to TS Bases,Which Have Been Revised Between 980101-990630,per 10CFR50.71(e) 05000361/LER-1999-004, Forwards LER 99-004-00 Re Automatic Tgis Actuation.Event Affected Units 2 & 3 Equally Because Tgis Is Shared Sys. Single Rept Is Being Provided for Unit 2 IAW NUREG-1022, Rev 1.No New Commitments Are Contained in Encl1999-08-0606 August 1999 Forwards LER 99-004-00 Re Automatic Tgis Actuation.Event Affected Units 2 & 3 Equally Because Tgis Is Shared Sys. Single Rept Is Being Provided for Unit 2 IAW NUREG-1022, Rev 1.No New Commitments Are Contained in Encl ML20210L2311999-08-0505 August 1999 Forwards ISI Summary Rept,Including Owners Repts of Repairs & Replacements,For Songs,Unit 3.Rept Covers 970916 Through 990509,date Unit 3 Returned to Service Following Cycle 10 Refueling Outage ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20216D9671999-07-29029 July 1999 Provides Response to RAI to Support Proposed TS Change 460 Re Containment Isolation Valve Completion Time for SONGS, Units 2 & 3.Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak, Encl ML20210C1821999-07-22022 July 1999 Forwards Rept Providing Results of Insp of Eggcrate Tube Supports Done on Secondary Side of Sgs,Using Remote Controlled Visual Equipment ML20210B2451999-07-21021 July 1999 Forwards Response to NRC 990615 RAI Re GL 95-07, Pressure Locking & Thermal Bldg of SR Power-Operated Gate Valves, for Songs,Units 2 & 3 ML20210B9891999-07-20020 July 1999 Ack Receipt of Transmitting Plant Emergency Plan Implementing Procedure SO123-VIII-1, Recognition & Classification of Emergencies ML20209J5241999-07-19019 July 1999 Provides Clarification of Util Intentions Re Disposition of Systems for Which Exemption & TS Changes Were Requested in Licensee .Deferment of Action Re Hydrogen Monitors,Encl ML20210N2881999-07-19019 July 1999 Forwards Rev 61 to Physical Security Plan,Rev 21 to Safeguards Contingency Plan & Rev 20 to Security Force Training & Qualification Plan,Per 10CFR50.54(p),for Plant. Screening Criteria Forms Encl.Plans Withheld ML20210A2911999-07-19019 July 1999 Submits Withdrawal Request Submitted by Ltr Dtd 990312, Requesting NRC Approval of Revs to Physical Security Plan & Safeguards Contingency Plan Tactical Response Plan ML20209G3421999-07-15015 July 1999 Forwards Table of 16 Affected Tube Locations in SG E089, Discovered During Cycle 10 Outage Insp,Which Were Probably Not Examined by Bobbin During Cycle Outage Insp ML20209D8051999-07-12012 July 1999 Discusses Licensee Response to RAI Re GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, Issue on 950519 to Plant. NRC Revised Info in Reactor Vessel Integrity Database & Is Releasing It as Rvid Version 2 ML20209F5681999-07-0909 July 1999 Forwards Insp Repts 50-361/99-08 & 50-362/99-08 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy ML20209C1571999-07-0202 July 1999 Forwards Response to NRC RAI Re SCE Submittal Dtd 980710,re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20196K6721999-07-0202 July 1999 Discusses 990628 Meeting Conducted in Region IV Office Re Status of San Onofre Nuclear Generating Station Emergency Preparedness Program.List of Attendees & Licensee Presentation Encl 1999-09-03
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217L9491999-10-21021 October 1999 Forwards SONGS Emergency Response Telephone Directory, for Oct-Dec 1999 ML20217K3571999-10-21021 October 1999 Discusses Use of SONGS as Generic Safety Issue 191 Ref Plant.Future Requests for Info & Addl Coordination Activities Be Handled Through D Evans of Organization.With Diskette ML20217K8541999-10-21021 October 1999 Forwards Revised Pages to ERDS Data Point Library,Per Requirements of 10CFR50,App E,Section VI.3.a.Described Unit 2 & 3 Changes for 2/3R7813 Were Completed on 990924 ML20217E3221999-10-13013 October 1999 Forwards MORs for Sept 1999 for Songs,Units 2 & 3.No Challenges Were Noted to Psvs for Either Units 2 or 3 ML20217E7671999-10-12012 October 1999 Forwards Rev 62 to NRC Approved Aug 1983, Physical Security Plan,Songs,Units 1,2 & 3, IAW 10CFR50.54(p).Changes,as Described in Encls 1 & 2,do Not Reduce Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20216H8741999-09-29029 September 1999 Provides Requested Written Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Lab Testing of Charcoal Adsorber Samples for Creacus & Pacu Satisfies Listed Requirements ML20216H8541999-09-29029 September 1999 Submits Encl Request for Relief from ASME Code,Section III Requirements in 10CFR50.55(a)(3) to Use Mechanical Nozzle Seal Assembly as Alternate ASME Code Replacement at SONGS, Units 2 & 3 for Period of Operation Beginning with Cycle 11 ML20212H4461999-09-28028 September 1999 Forwards Suppl Info,As Discussed with NRC During 990812 Telcon,To Support Risk Informed Inservice Testing & GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20212G5611999-09-24024 September 1999 Informs NRC That SCE Remains Committed to Performing Eddy Current Examinations of 100% of Reactor Vessel Head Penetrations at Songs,Unit 3.Exams Will Not Be Performed During Cycle 11 RFO 05000361/LER-1999-005, Forwards 30-day follow-up LER 99-005-00,describing Loss of Physical Train Separation in Control Room.Any Actions Listed Intended to Ensure Continued Compliance with Existing Commitments1999-09-23023 September 1999 Forwards 30-day follow-up LER 99-005-00,describing Loss of Physical Train Separation in Control Room.Any Actions Listed Intended to Ensure Continued Compliance with Existing Commitments ML20212A4061999-09-14014 September 1999 Forwards Revised Pages to ERDS Data Point Library.Described Unit 2 Changes for 2R7817 & 2R7828 Were Completed on 990818 & Unit 3 Change for 3R7828 Was Completed on 990903 ML20216E6031999-09-10010 September 1999 Provides Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Dtd 990820.Schedule Shown on Attachment 1, Operator Licensing Exam Data, Provides Util Best Estimate Through Cy 2003 05000206/LER-1999-001, Forwards LER 99-001-00 for Occurrence Re Unattended Security Weapon Inside Protected Area.Single Rept for Unit 1 Is Being Submitted,Iaw NUREG-1022,Rev 1,since Condition Involves Shared Sys & Is Applicable to Units 1,2 & 31999-08-31031 August 1999 Forwards LER 99-001-00 for Occurrence Re Unattended Security Weapon Inside Protected Area.Single Rept for Unit 1 Is Being Submitted,Iaw NUREG-1022,Rev 1,since Condition Involves Shared Sys & Is Applicable to Units 1,2 & 3 ML20210V4271999-08-16016 August 1999 Forwards Proprietary Certified Renewal Applications for SROs a Harkness,R Grabo & T Vogt & RO D Carter,Submitted on Facsimile Form NRC-398 & Certified NRC Form 396.Encls Withheld ML20210R6681999-08-13013 August 1999 Forwards Response to NRC RAI Re SCE License Amend Applications 173 & 159 for Songs,Units 2 & 3,proposed Change Number 485,which Requests Addition of SR to TS 3.3.9, CR Isolation Signal ML20210Q6451999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for SONGS, Units 2 & 3,per TS 5.7.1.4.There Were No Challenges to Pressurizer Safety Valves for Either Units ML20210P5711999-08-11011 August 1999 Forwards Amend Application Number 189 for License NPF-10 & Amend Application Number 174 to License NPF-15,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Encl Calculation E4C-098 ML20210P4681999-08-11011 August 1999 Forwards COLR for Cycle 10 for Songs,Units 2 & 3,IAW TS Section 5.7.1.5.d, Colr. Changes to COLR Parameters Have Been Conducted IAW Approved COLR Methodologies & All Applicable Limits of Safety Analysis Were Met ML20210P6221999-08-10010 August 1999 Forwards Replacement Pages for Attachments E & F of Amend Application Numbers 168 & 154 for Songs,Units 2 & 3.Pages Are Provided to Correct Errors to Pagination & Headings in 970618 Submittal ML20210N5051999-08-0909 August 1999 Forwards Cycle 10 Update to TS Bases,Which Have Been Revised Between 980101-990630,per 10CFR50.71(e) 05000361/LER-1999-004, Forwards LER 99-004-00 Re Automatic Tgis Actuation.Event Affected Units 2 & 3 Equally Because Tgis Is Shared Sys. Single Rept Is Being Provided for Unit 2 IAW NUREG-1022, Rev 1.No New Commitments Are Contained in Encl1999-08-0606 August 1999 Forwards LER 99-004-00 Re Automatic Tgis Actuation.Event Affected Units 2 & 3 Equally Because Tgis Is Shared Sys. Single Rept Is Being Provided for Unit 2 IAW NUREG-1022, Rev 1.No New Commitments Are Contained in Encl ML20210L2311999-08-0505 August 1999 Forwards ISI Summary Rept,Including Owners Repts of Repairs & Replacements,For Songs,Unit 3.Rept Covers 970916 Through 990509,date Unit 3 Returned to Service Following Cycle 10 Refueling Outage ML20216D9671999-07-29029 July 1999 Provides Response to RAI to Support Proposed TS Change 460 Re Containment Isolation Valve Completion Time for SONGS, Units 2 & 3.Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak, Encl ML20210C1821999-07-22022 July 1999 Forwards Rept Providing Results of Insp of Eggcrate Tube Supports Done on Secondary Side of Sgs,Using Remote Controlled Visual Equipment ML20210B2451999-07-21021 July 1999 Forwards Response to NRC 990615 RAI Re GL 95-07, Pressure Locking & Thermal Bldg of SR Power-Operated Gate Valves, for Songs,Units 2 & 3 ML20210A2911999-07-19019 July 1999 Submits Withdrawal Request Submitted by Ltr Dtd 990312, Requesting NRC Approval of Revs to Physical Security Plan & Safeguards Contingency Plan Tactical Response Plan ML20210N2881999-07-19019 July 1999 Forwards Rev 61 to Physical Security Plan,Rev 21 to Safeguards Contingency Plan & Rev 20 to Security Force Training & Qualification Plan,Per 10CFR50.54(p),for Plant. Screening Criteria Forms Encl.Plans Withheld ML20209J5241999-07-19019 July 1999 Provides Clarification of Util Intentions Re Disposition of Systems for Which Exemption & TS Changes Were Requested in Licensee .Deferment of Action Re Hydrogen Monitors,Encl ML20209G3421999-07-15015 July 1999 Forwards Table of 16 Affected Tube Locations in SG E089, Discovered During Cycle 10 Outage Insp,Which Were Probably Not Examined by Bobbin During Cycle Outage Insp ML20209C1571999-07-0202 July 1999 Forwards Response to NRC RAI Re SCE Submittal Dtd 980710,re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20210N9871999-07-0101 July 1999 Appeals Denial of Documents Re Sept 1996 Osre for San Onofre Nuclear Generating Station.Requests Copies of Sept 1996 Osre Rept & Any More Recent Osre Repts ML20209B3571999-06-28028 June 1999 Submits Response to GL 98-01,Suppl 1 Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701. Disclosure Encl ML20209B4831999-06-25025 June 1999 Requests NRC Approval of Six Relief Requests from ASME Code Requirement for Containment ISI Exams.Six Relief Requests, Provided as Enclosures 1-6,are as Listed ML20196A9801999-06-17017 June 1999 Responds to NRC 990420 RAI Re Proposed risk-informed Inservice Testing & GL 96-05 Programs at Songs,Units 2 & 3. Revised Pages to risk-informed Inservice Testing Program, Encl ML20195G8091999-06-14014 June 1999 Forwards Response to RAI Made During 990511 Telcon Re LARs 184 & 170 for SONGS Units 2 & 3.Amend Applications Proposed Restriction on Operation with Channel of RAS or Efas in Tripped Condition ML20195K4201999-06-11011 June 1999 Forwards LERs 99-003-00 & 99-004-00 Re Manual Esfas (Reactor Trips) Due to Problems with Main Feedwater Control.Two Events Are Being Reported Separately Because Actual Causes Are Considered Different & Independent of Each Other ML20195H1561999-06-10010 June 1999 Forwards MORs for May 1999 for Songs,Units 2 & 3.There Were No Challenges to Pressurizer Safety Valves for Either Unit 2 & 3 ML20195E4981999-06-0808 June 1999 Forwards Application for Amends 188 & 173 to Licenses NPF-10 & NPF-15 for SONGS Units 2 & 3,respectively.Amends Would Revise TS 3.5.2,3.1.9,3.7.1 & 5.1.7.5 Re Small Break LOCA Charging Flow & Main Steam Safety Valve Setpoints ML20196L3191999-05-24024 May 1999 Forwards ISI Summary Rept,Including Owners Repts of Repairs & Replacements for Songs,Unit 2.Rept Covers Period of 970916-990226 ML20207A3831999-05-24024 May 1999 Responds to NRC 990326 RAI on DG Srs.Proposed to Add Listed Sentence to TS Bases for SRs 3.8.1.7,3.8.1.12 & 3.8.1.15,as Result of Discussion with NRC During 990427 Telcon ML20211K4261999-05-18018 May 1999 FOIA Request for Documents Re San Onofre OI Repts 4-98-041, 4-98-043 & 4-98-045 ML20206S7161999-05-17017 May 1999 Forwards MORs for Apr 1999 for Songs,Units 2 & 3.There Were No Challenges to Pressurizer Safety Valves for Either Unit 2 or 3 ML20206N4711999-05-13013 May 1999 Provides Info Requested by NRC Re Reduced Pressurizer Water Vol Change Amends Application 172 & 158 for Songs,Units 2 & 3,respectively.Proposed Change Will Reduce Pressurizer Water Level Required for Operability ML20206M7791999-05-13013 May 1999 Informs NRC of Changes Being Made to Emergency Response Data Sys (ERDS) at SONGS Unit 3.Revised Page to ERDS Data Point Library Is Provided in Encl ML20206K6891999-05-11011 May 1999 Forwards Approved Amends to NPDES Permits CA0108073,Order 94-49 & CA0108181,Order 94-50 & State Water Resources Board Resolution ML20206M0681999-05-10010 May 1999 Submits Correction to Info Contained in Licensee to NRC Re Proposed TS Change Number NPF-10/15-475.Stated Info Was Incorrect in That Overtime Provisions Were Not Contained in TR at Time of Was Submitted ML20206H0451999-05-0404 May 1999 Forwards Annual Financial Repts for Listed Licensees of Songs,Units 1,2 & 3.Each Rept Includes Appropriate Certified Financial Statement Required by 10CFR50.71(b) ML20206H1931999-05-0303 May 1999 Forwards 1998 Annual Rept, for SONGS Units 2 & 3 & PVNGS Units 1,2 & 3.SCEs Form 10K Annual Rept to Securites & Exchange Commission for Fiscal Yr Ending 981231,encl ML20206C5151999-04-29029 April 1999 Forwards 1998 Radiological Environ Operating Rept for Songs,Units 1,2 & 3. Annual Radiological Environ Operating Rept Covers Operation of Songs,Units 1,2 & 3 During CY98 & Includes Summaries Interpretations & Analysis of Trends ML20206E5851999-04-29029 April 1999 Forwards Annual Radioactive Effluent Release Rept for 1998 for SONGS Units 1,2 & 3. Also Encl Are Rev 13 to Unit 1 ODCM & Rev 31 to Units 2 & 3 Odcm 1999-09-29
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059C1071990-08-24024 August 1990 Forwards Addenda 10-1A,10-1B & 10-1C to Physical Security Plan.Encls Withheld (Ref 10CFR73.21) ML20059E6951990-08-24024 August 1990 Forwards Rev 30 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20059B8861990-08-22022 August 1990 Advises That Dl Hill Employment W/Util Terminated,Effective 900817.Operator License OP-50333 Expired ML13302B3411990-08-21021 August 1990 Responds to NRC Bulletin 88-010 Re Nonconforming molded-case Circuit Breakers (Mccbs).Affected MCCBs Purchased for Use in safety-related Applications,Including MCCBs Used W/Motor Controllers.Outage Rept Encl,Per 890330 Ltr ML20064A2161990-08-16016 August 1990 Responds to NRC Re Violations Noted in Insp Repts 50-361/90-16 & 50-362/90-16.Reply to Notice of Violation Not Required Due to Sufficient Info Provided in ,Per 900807 Discussion W/R Huey ML13309A9211990-08-14014 August 1990 Forwards Monthly Operating Repts for Jul 1990 for San Onofre Units 2 & 3,revised Unit 2 Monthly Operating Rept for June 1990 & Rev 22 to ODCM ML20058Q2961990-08-14014 August 1990 Forwards Util & June 1990 NPDES Monitoring Rept. W/O Rept ML20058N0371990-08-0909 August 1990 Advises That on 900713,new Land Use Located W/Calculated Dose Greater than Value Currently Calculated.New Location Results in Annual Dose Increase of 27% for Units 2 & 3 & 39% Increase for Unit 1 ML20056A1781990-08-0202 August 1990 Discusses Review of Possibility of Accelerating Schedule for Performing & Submitting Results of Individual Plant Exams for Units 1,2 & 3.Util Believes That Submittal Schedule for Unit 1 Can Be Accelerated to 920102 ML18041A2221990-07-31031 July 1990 Responds to NRC 900518 Ltr Re Violations Noted in Insp Repts 50-206/90-10,50-361/90-10 & 50-362/90-10.Corrective Action: computer-based Mgt Sys Will Be Developed to Permit Incoming Revised Info to Be Matched W/Documents Requiring Review ML20055H9641990-07-27027 July 1990 Responds to NRC Re Violations Noted During Special Safety Sys Functional Insp on 891030-1130.Corrective Action:Util Will Review & Revise Operating & Calibr Procedures by 901031 ML20055H5731990-07-24024 July 1990 Provides Notification of Completion of Installation of Backup Nitrogen Sys Isolation Check Valves & Test Connections at Facility ML20055H2631990-07-23023 July 1990 Discusses Model 3RE-7870 Not Being Declared Operable Due to Lack of Process Flow.Monitor Failed on 900708.Caused by Moisture Intrusion Into Housing.All Affected Components Repaired or Replaced ML20055F1901990-07-0909 July 1990 Informs That Ej Schoonover Employment W/Util Terminated, Effective 900629 ML20044A4121990-06-27027 June 1990 Requests Approval of Use of Plugs Fabricated of nickel-chromiun-iron Uns N-06690 Matl to Plug Tubes in Plant Steam Generators.Change to Use Alloy 690 Tube Plugs Results from Matl Corrosion Consideration ML20056A8841990-06-25025 June 1990 Responds to NRC Forwarding Insp Repts 50-206/90-10,50-361/90-10 & 50-362/90-10.Results of Review of Awareness & Response to Industry Check Valve Concerns & Evaluation of Need to Establish Dedicated Program Provided ML20043H7851990-06-19019 June 1990 Informs That Jl Mullins Employment W/Util Terminated Effective 900608.Operator License OP-50089-2 Expired ML20043H5101990-06-19019 June 1990 Informs That Wk Giffrow Employment W/Util Terminated. Operator License OP-50050-2 Expired ML13304A4861990-06-0404 June 1990 Forwards Evaluation of Unisolable Piping from RCS W/Potential for Leakage Induced Thermal Stresses in Response to NRC Bulletin 88-008 SONGS 2 & 3, in Response to Request ML20043B4911990-05-22022 May 1990 Submits Rept:On 900507,eddy Current Insp of Steam Generator Tubing Completed.Of 2,106 Tubes Inspected in Steam Generator E-088 No Tubes Found Defective.One Tube in Steam Generator E-089 Found Defective & Plugged ML20043B1411990-05-17017 May 1990 Informs That Senior Reactor Operator License No Longer Needed for JW Ryder,Effective 900425.License SOP-50288 Expired on 900425 ML13309A9151990-05-14014 May 1990 Forwards Monthly Operating Repts for Apr 1990 for San Onofre Nuclear Generating Station Units 2 & 3 ML20043A0051990-05-0404 May 1990 Informs of Expiration of WR Seiler Senior Reactor Operator License,Effective 900502 ML20042G6531990-05-0303 May 1990 Forwards Addendum 10-1B to Physical Security Plan.Encl Withheld (Ref 10CFR73.21) ML20042F7101990-05-0202 May 1990 Informs That Gb Swift Transferred to Position Not Requiring Operator License,Effective 900423 & License Expired,Per 10CFR55.55(a) ML20012E8341990-03-29029 March 1990 Advises That Reactor Operator License OP-50072-2 Expired on 900312 & No Longer Needed ML13303B1981990-03-12012 March 1990 Forwards Table Re FSAR Chapter 15 Design Basis Event & Rev 0 to M-89047, Instrument Drift Study San Onofre Nuclear Generating Station Units 2 & 3, in Support of Proposed Change Notices 275 & 280,per NRC Request ML20012B6701990-03-12012 March 1990 Advises That Response to SSFI Repts 50-361/89-200 & 50-362/89-200 Will Be Provided by 900412 Due to Unexpected Diversion of Resources to Address Other Issues Such as Trip of Unit 3 on 900223 & Safety Valve Evaluations ML13304A4591990-03-0707 March 1990 Forwards Rev 0 to M 86420, Spurious Actuation Evaluation Component Cooling Water Sys - Operability Assessment. ML20012B8061990-03-0505 March 1990 Responds to NRC 900205 Ltr Re Violations Noted in Insp Repts 50-361/89-33 & 50-362/89-33.Corrective Actions:Action Taken W/Responsible Supervisor to Ensure That Health Physics Technician Overtime Controlled & Authorized ML13304A4551990-02-16016 February 1990 Forwards Rev 6 to Spent Fuel Pool Reracking Licensing Rept. Encl 1 Lists Summary of Rev 6 Changes & Encl 2 Lists Changes (Insert Pages) to Rev 5 Reracking Licensing Rept ML20006E8801990-02-14014 February 1990 Informs That Dl Daily Employment W/Util Terminated Effective 900209.License SOP-50229-1 Expired ML20006D9661990-02-0707 February 1990 Advises That Listed Individuals No Longer Require Senior Reactor Operator Licenses,Effective on 900117 ML20011E5041990-02-0707 February 1990 Informs of Termination of Rl Sprague Employment W/Util, Effective 900125 ML13303B1871990-01-18018 January 1990 Forwards Rev 5 to Amend Applications 64 & 78 to Licenses NPF-10 & NPF-15,respectively,re Spent Fuel Pool Reracking. New Racks Will Increase Number of Storage Locations in Each Spent Fuel Pool from 800 to 1,542 Elements ML20011F0381990-01-18018 January 1990 Documents Commitment Re Impact of outage-related Overtime, Based on Interview at Site on 900112.Util Will Not Schedule Heavy Use of Overtime for Duration of Refueling Outage for Personnel Addressed by Tech Specs Assigned to Unit ML13303B1791990-01-0808 January 1990 Forwards Amend Applications 70 & 56 to Licenses NPF-10 & NPF-15,respectively,revising Tech Spec 3/4.3.3.5, Remote Shutdown to Increase Interval for Refueling Surveillance Tests to Nominally 24 Months & Max of 30 Months ML13303B1841990-01-0808 January 1990 Forwards Amend Applications 69 & 55 to Licenses NPF-10 & NPF-15,respectively,consisting of Proposed Tech Spec Change NPF-10/15-275 Re Refueling Interval Surveillances ML19332F0631989-12-0505 December 1989 Informs of Termination of MP Mcdonnell Employment W/Util, Effective 891128 ML19332F1181989-12-0505 December 1989 Provides Schedule for Installation of Diverse Emergency Feedwater Actuation Sys at Plant,Per 890808 Commitment. Schedule for Significant Conceptual Engineering Tasks Completed & Major Tasks to Be Completed Summarized ML20005D7331989-12-0505 December 1989 Advises That RW Dougherty Transferred to Position within Util Which Does Not Require Reactor Operator License, Effective 891204.License OP-50193-1 Expired ML19332D8731989-11-27027 November 1989 Responds to NRC 891027 Ltr Re Violations Noted in Insp Repts 50-361/89-24 & 50-362/89-24.Corrective Actions:Temporary Cables Passing Through Doorway Removed & Maint Order Revised & Reissued to Incorporate Creacus Boundary Requirements ML19332D3261989-11-20020 November 1989 Responds to NRC 891027 Ltr Re Violations Noted in Insp Repts 50-361/89-24 & 50-362/89-24.Corrective Actions:Requirements of Tech Spec 3.0.3 Applied & Applicability Reinforced W/Appropriate Personnel ML19332F4321989-11-15015 November 1989 Forwards Addendums 10-1B & 10-1C to Physical Security Plan. Encl Withheld (Ref 10CFR73.21) ML13304A4381989-11-0909 November 1989 Forwards Proprietary WNEP-8926 & Nonproprietary WNEP-8930, San Onofre Units 2 & 3 Fuel Rack Seismic Analysis for Final Pool Layout. Util Application for Withholding Ltr, CAW-89-104,Proprietary Info Notice & Affidavit Also Encl ML13303B1621989-11-0202 November 1989 Forwards Rev 4 to Amend Applications 78 & 64 to Licenses NPF-10 & NPF-15,respectively,re Spent Fuel Reracking & Proposed Tech Spec on Request from Staff Requiring Min Spent Fuel Pool Boron Concentration ML19325D9781989-10-19019 October 1989 Discusses Completion of Steam Generator Tubing Insp.Total of 4,316 Tubes Inspected & 62 Tubes Removed from Svc by Mechanical Plugging.Insp Significantly Exceeded Amount of Tubing Required to Be Inspected ML19325D1881989-10-0606 October 1989 Informs of Termination of Employment of RA Barnes as Licensed Senior Reactor Operator on 890929 ML20248G6821989-09-29029 September 1989 Advises That Wj Kirkpatrick Employment Terminated on 890922 & License Expired ML20248H1101989-09-29029 September 1989 Advises That Wc Kingsley Employment W/Util Terminated, Effective 890915 1990-08-09
[Table view] |
Text
/ ~REOLA ~TR' 'iFRM ION DISTIBUT'J.U
,ACCESS'ION! NOR:81,11-30663f DUC*DArEl- 81~/11/1.1 NOT ARI Z ED: YES', DOCKEfT C FACIQ~:50-361; Slan' Onofrel Nvcleigrt Station,. U'ntt 2i, Sovthern' Cal if orn, 05000361, 50;-362' $an, Onofire;i Nuclear( Sta,6tion, uh4t! 3,0' Souther-nt C6,1forn 050.00 36 2 AUT' 11.N4 ME I AUrHORI 'AFFILIATIOW BASKINXfP.s Southern.. Ca'fOqrnia' Edis .on' Co,,:
RECIP,"4AMEI RECIPIENt AFFLiIATION'
- 'IRAGL~lAlpF. ielhsing. Branch. 3 SUBVE CITI Forwards Pr oprIeit ary. & n onproprieter~ versioni of "Pr'ocess'.
Comtrol) Programi fori Chb~ilfNucleari Sys'?Inc. Cemfent.
11 ific atio Uni -ts,"' per, AM, nd. 214' to- FSAR' Sectti~ on l'.4'.
Propi'1etary version, withhelk1' (ref: 10CFR2,790).Affidavjt! ehci DISTRIBSJT'IN, CODEI:, P30181, COPIES, RECEfIVEO:L(TR- ENC SIZEI.,
TlITLEI: Proprietary Ra~deW, Distrdutl 6n *' Prei o~t NOTES':L( Chandler:all1 FSAR ER, a-miends.1l, cy:J' 1anchettz(Re?916n, V):, 05000361.
D Scaleti u cy all], invir l.4mnto.
Lt Chtindlerall FSAR & MR aimends,1 ctJ HacetRi'gj on; 05000362'.
D. S'calettl :1 zcy All1 envirt info,.,
RECIPIENT! COPIEB RECI P1ENTI 'COPIES, IOt* CDOEJ/NAMEi L.TTR ENCLf 10' CODEVNAMEI Lf~fTR( ENCL' ACTION:,- LMC BR #,3( BC 1, 0' LlIC; SRI #3 LA 11 0-,
ROOD ,: #1 INTERNAki ELO I; .0 ISE! 3' 3 MA 0 NRR DIvRi 1 0.
EXTERNALtv ACRS' *6 tW'i 6 16i LPDRI I 91 NRCI PD.3iI 1 a NI 'SIC 1 -10 N'T~I 150$ 0?1 TOtTALi NUMS4Er't OF'. COP-IES', REQ~UIRED,:. LiTTR , ENCL, ~
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN TELEPHONE MANAGER OF NUCLEAR ENGINEERING, November 10, 1981 (213) 572-1401 SAFETY, AND LICENSING Director, Office of Nuclear Reactor Regulation Attention: Mr. Frank Miraglia, Branch Chief L Licensing Branch No. 3 NOVI2 1981 U. S. Nuclear Regulatory Commission N1 Washington, D.C. 20555 Gentlemen:
Subject:
Docket Nos. 50-361 and 50-362 San Onofre Nuclear Generating Station Units 2 and 3 Amendment 21 to San Onofre Units 2&3 FSAR revised section 11.4 to indicate that in lieu of the installed urea - formalydehyde system, Southern California Edison has contracted with Chem-Nuclear Systems, Inc. (CNSI) to provide the primary means of radwaste solidification utilizing concrete as the solidification medium. Enclosed is a description of the Process Control Program for CNSI's Solidification Units which will form the basis for compliance with the Technical Specification limiting condition for operation on Solid Radioactive Waste.
Please note that three (3) copies of a "Proprietary" and five (5) copies of a "Non Proprietary" version of the program (both NRC MAIL CODE B028) are enclosed along with an affidavit, as required by 10CFR2.790(b), requesting that, and providing reasons for, the Commission withholding the "Proprietary" version of the program from public disclosure.
It is respectfully requested that the proprietary version of Chem-Nuclear Systems, Inc. Document No. SD-OP-003-Rev. D - Process Control Program for CNSI Cement Solidification Units, be withheld from public disclosure by the Commission in accordance with 10CFR2.790(b). If you should have any questions regarding the proprietary nature of the material transmitted herewith, please address these questions directly to:
Gerald P. Motl (803-798-9042)
Director, Field Operations Chem-Nuclear Systems, Inc.
240 Stoneridge Dr. - Suite 100 Columbia, South Carolina 29210 8111130663 811110 77 !
PDR ADOCK 05000361 A PDR A
?ifff
Mr. Frank Miraglia -2 In addition, it is requested that Southern California Edison and San Diego Gas and Electric be provided with a copy of any questions concerning the proprietary nature of this submittal.
If you have any questions or comments regarding the Process Control Program, please contact me.
Very truly yours, Enclosure
TO: U.S. Nuclear Regulatory Commission Washington, D.C.
Attention: Frank Miraglia Re: Chem-Nuclear Systems, Inc. Document SD-OP-003 "Process Control Program for CNSI Cement Solidification Units" AFFIDAVIT SUBMITTED IN SUPPORT QF REQUEST THAT THE ABOVE DOCUMENT BE WITHHELD FROM PUBLIC DISCLOSURE PURSUANT TO 10 C.F.R. S 2.790 STATE OF SOUTH CAROLINA )
)ss.
COUNTY OF RICHLAND )
GERALD P. MOTL states as follows on behalf of Chem-Nuclear Systems, Inc.:
- 1. I am the Director of Field Operations of Chem-Nuclear Systems, Inc. ("CNSI").
- 2. I have reviewed and am familiar with the contents of the document entitled "Process Control Program for CNSI Cement Solidification Units", CNSI Document No. SD-OP-003, and submit this.affidavit in support of the request by Southern California Edison that portions of this document be withheld from public disclosure.
- 3. The information contained in the document provided, as described hereinabove, has been held in confidence by CNSI as follows:
CNSI has always maintained confidentiality with regard to the design and operation of its mobile solidification units. The proprietary information contained in the above document is not available from public sources.
- 4. The information contained in the above document is of a type customarily held in confidence by CNSI, and there is a rational basis for such confidentiality as follows:
CNSI has devoted extensive resources to the development and improve ment of its radioactive waste disposal services. It is customary for CNSI to maintain confidentiality concerning services maintained for particular customers and originators of radioactive waste both for the protection of such originating entities and also to protect the competitive position of CNSI.
- 5. The information described hereinabove was transmitted to'the Commission and received by it in confidence as follows:
The document was forwarded to the Commission along with Southern California Edison's license application.
- 6. The information contained in the above document is not available in public sources as follows:
The document contains a complete description of the CNSI mobile solidification unit, including hardware, chemical usages, and adjustment data, and formulas, all of which are set forth as proprietary information.
- 7. Public disclosure of the document requested to be withheld from such disclosure is likely to cause substantial harm to the competitive position of CNSI as follows:
CNSI has devoted extensive resources to the development and improvement of its radioactive waste disposal services. Release of the above document to the public would afford competitors of CNSI an unfair advantage and would cause substantial harm to the Company and loss of the benefit of past investment of financial resources including engineering costs. Company employees agree, as a condition of employment, to maintain and keep company proprietary information confidential. The information contained in the document is not available through public sources.
- 8. For the reasons set forth in the affidavit, CNSI respectfully requests that the Nuclear Regulatory Commission withhold the above document from public disclosure as permitted under 10 C.F.R. S 2.790(b)4.
GERALD P. MOTL Director, Field Operations STATE OF SOUTH CAROLINA )
)ss.
COUNTY OF RICHLAND )
On this V5 day of July,.1981, before me personally appeared Gerald P. MotTto me known to be the Director of Field Operations of Chem-Nuclear Systems, Inc., the corporation that executed the foregoing instrument, and acknowledged said instrument to be the free and voluntary act and deed of said corporation, for the uses and purposes therein mentioned, and on oath stated that he is authorized to -execute said instrument.
IN WITNESS WHEREOF, I have set my hand and affixed my official seal the day and year first above written.
ARY BLIC in and r the 5tate of S arlna, resi t 7N REVISIONS REV. DESCRIPTION DATE APPROVED A Complete Rewrite 6/24/81 B Incorporate Changes 9/11/81 C Complete Rewrite 9/29/81 D Incorporate Change Per Change 10/20/81 Request I SP-OP-003-03 Y REVIEW DATE /
REVISION STATUS SHEET 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 REV. 1D D D D D TP D SHEET 18 REV.
PREPAff DATE
'54 , 21-9 el CHEM - NUCLEAR SYSTEMS, INC.
CHECKED TITLE ENGINEER PrCESS CONTML PROGRAM FOR CNSI CEMENT j; ~,; v e.36'e 8 1113 687 e(8 1110ETTDTFICATION UNITS J u(.; .~ ___ _
PDR ADOCK 05000361
~
OU7Y/ 2~ APDR APPROVED CONTRACT NO. DOCUMENT NO. REV. SHEET SD-OP-00 CNSO 1001/8-78
TABLE OF CONTENTS PAGE 1.0 SCOPE 1.1 PURPOSE 3 1.2 APPLICABILITY 3
2.0 REFERENCES
3.0 SYSTEM DESCRIPTION 3.1 PROCESS DESCRIPTION 3 3.2 PROCESS PARAMETERS 4 3.3 MOBILE UNIT DESCRIPTION 4 3.4 SYSTEM OPERATION 5 4.0 REQUIREMENTS FOR SAMPLE VERIFICATION 4.1 GENERAL PRECAUTIONS 6 4.2 RADIOLOGICAL PRECAUTIONS 6 4.3 PREREQUISITES 6 4.4 SAMPLE ACCEPTANCE CRITERIA 8 4.5 REQUIREMENTS FOR SAMPLE VERIFICATION 8 5.0 SAMPLE VERIFICATION 6.0 ADMINISTRATIVE PROCEDURES TABLE 1 - EQUIPMENT REQUIRED FOR TESTING SAMPLES 7 FIGURE 1 - SOLIDIFICATION WORKSHEET 10 FIGURE 5 - LINER AND CASK CALCULATIONS 19 DOCUMENT REV. SHEET SD-OP-003-0 D 2 CNSQ 1002/8-78
1.0 SCOPE 1.1 PURPOSE THE PURPOSE OF THE PROCESS CONTROL PROGRAM FOR CNSI CEMENT SOLID IFICATION UNITS IS TO ESTABLISH A SET OF PROCESS PARAMETERS WHICH PROVIDE REASONABLE ASSURANCE OF COMPLETE SOLIDIFICATION OF LOW LEVEL RADIOACTIVE LIQUID WASTE*
1.2 APPLICABILITY THIS PROCESS CONTROL PROGRAM SHALL BE USED BY ALL PERSONNEL OPERATING THE.CNSI CEMENT SOLIDIFICATION UNIT.
2.0 REFERENCES
2.1 QA-AD-001, CNSI QUALITY ASSURANCE PROGRAM 2.2 CN-AD-019, CNSI ALARA POLICY 2.3 EN-AD-002, CNSI DESIGN CONTROL 2.4 CNSI OPERATING PROCEDURE FOR CEMENT SOLIDIFICATION UNITS, AS APPLICABLE 2.5 NUREG 0472, RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS FOR PWR 2.b NUREG 0473, RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS FOR BWR 2.7 BRANCH TECHNICAL POSITION-ESTB 11-3, DESIGN GUIDANCE FOR SOLID RADIOACTIVE WASTE MANAGEMENT SYSTEMS INSTALLED IN LIGHT-WATER COOLED NUCLEAR POWER REACTOR PLANTS 2.8 ANSI 199, LIQUID RADIOACTIVE WASTE PROCESSING SYSTEMS FOR PRES SURIZED WATER REACTOR PLANTS 2.9 ANSI 197, LIQUID RADIOACTIVE WASTE PROCESSING SYSTEMS FOR BOILING WATER REACTOR PLANTS 2.10 NRC REGULATORY GUIDE 1.143, DESIGN GUIDES FOR RADIOACTIVE WASTE MANAGEMENT SYSTEMS, STRUCTURES, AND COMPONENTS INSTALLED IN LIGHT-WATER-COOLED NUCLEAR POWER PLANTS 3.0 SYSTEM DESCRIPTION 3.1 PROCESS DESCRIPTION THE CNSI CEMENT SOLIDIFICATION UNIT IS SPECIFICALLY DESIGNED TO OPTIMIZE SOLIDIFICATION OF RADIOACTIVE WASTES, EVAPORATOR BOT TOMS, ION EXCHANGE RESIN SLURRIES AND SLUDGES.
DOCUMENT REV. SHEET SD-OP-003 D 3 CNSQ 1602/8-78
THE CEMENT PROCESS MAKES USE OF THE READILY AVAILABLE PORTLAND I CEMENT AND HYDRATED LIME (CA(OH)2) TO SOLIDIFY LIQUID WASTES*
THE PROCESS IS INITIATED BY TRANSFERRING LIQUID WASTE INTO THE CNSI DISPOSABLE LINER* THE WASTE IS THEN CONDITIONED BY DE WATERING OR ADDING CONDITIONING CHEMICALS AS REQUIRED* (CON DITIONING CHEMICALS MAY ALSO BE PRELOADED INTO THE LINER)* WITH CONTINUOUS AGITATION PROVIDED BY THE INSTALLED MIXER BLADES, CEMENT IS ADDED TO DEVELOP A THICK PASTE LIKE SLURRY WHICH WILL SOLIDIFY TO A HARD, WATER-FREE END PRODUCT*
3.2 PROCESS PARAMETERS CEMENT UNDERGOES FOUR SEPARATE REACTIONS DURING ITS CURING TIME WHICH PERMANENTLY COMBINES CEMENT, WATER AND A VARIETY OF IONS FOUND IN WASTE STREAMS TO FORM A STABLE, SOLID CONCRETE END PRO DUCT* CERTAIN CHEMICALS AND METALLIC IONS PRESENT IN THE WASTE ACT AS ACCELERATORS OR RETARDANTS TO THESE REACTIONS. BY PRE TREATING THE WASTE WITH CHEMICALS DESIGNED TO LIMIT OR NEUTRALIZE THESE EFFECTS, A CONTROLLED, ACCEPTABLE CURE TIME CAN BE ACHIEVED AND THE WASTE-TO-ADDITIVE RATIO WILL BE SIGNIFICANTLY IMPROVED*
EACH OF THE REACTIONS IS EXOTHERMIC AND BY CONTROLLING THE SPEED OF REACTION AND MINIMIZING THE TOTAL CEMENT ADDITION BY THE USE OF CERTAIN ADDITIVES, THE HEAT DEVELOPED BY LARGE VOLUME SOLIDI FICATIONS WILL ALSO BE MINIMIZED*
THE SAMPLE VERIFICATION PROCEDURE WILL SERVE TO VERIFY THE EXACT PRETREATMENT REQUIRED TO ACHIEVE THE OPTIMUM WASTE-TO-ADDITIVE RATIO* SOLIDIFICATION RATIOS HAVE BEEN DEVELOPED THROUGH A CNSI RESEARCH AND DEVELOPMENT PROGRAM* HOWEVER, WASTE MAKE-UP AND DENSITY VARIES WIDELY FROM ONE WASTE STREAM TO ANOTHER MAKING THIS VERIFICATION A NECESSARY QUALITY ASSURANCE STEP IN THE EN TIRE SOLIDIFICATION PROGRAM. THE AMOUNT OF ADDITIVES AND CEMENT TO BE USED FOR SAMPLE AND FULL SCALE SOLIDIFICATIONS ARE PROVIDED BY FIGURES 2 THROUGH 5,AS APPROPRIATE.
3.3 MOBILE UNIT DESCRIPTION 3.3.1 THE CNSI CEMENT SOLIDIFICATION UNIT IS A PORTABLE SYSTEM CONTAINING ALL PIPING, SUPPORT, CONTROL AND MONITORING EQUIPMENT NECESSARY TO SOLIDIFY RADIOACTIVE LIQUID WASTE USING THE CEMENT PROCESS*
3.3.2 THE UNIT IS COMPOSED OF SEVERAL PROCESSING SUBSYSTEMS, EACH CONTROLLING A SPECIFIC FUNCTION OF THE CEMENT PRO CESS. THESE SUBSYSTEMS INCLUDE WASTE TRANSFER, CHEMICAL ADDITION, CEMENT CONVEYOR, VENT, AND DEWATER SYSTEMS*
CONTROL FUNCTIONS FOR THE UNIT ARE INCORPORATED INTO THE PNEUMATIC AND MAIN CONTROL PANELS* SERVICE SUPPLIES ARE PROVIDED BY THE UTILITY AND DISTRIBUTED THROUGH THE SERVICE AIR, WATER, AND ELECTRICAL DISTRIBUTION SYSTEMS.
DOCUMENT REV. SHEET SD-OP-003-NP D 4 CNSO 1 O/S-78
3*3.3 MOST OF THE MOBILE UNIT COMPONENTS ARE ARRANGED ON POR TABLE FRAMEWORKS (SKIDS) TO PROVIDE FLEXIBILITY OF OP ERATIONS FOR EITHER INDOOR OR OUTDOOR USE. THE CEMENT CONVEYOR, CONTROL PANEL, PUMP SKID, HYDRAULIC SKID AND FILLHEAD CONTAIN MOST OF THE MAJOR ELEMENTS OF THE MOBILE UNIT*
3.3.4 A CLOSED-CIRCUIT TELEVISION SYSTEM IS AN INTEGRAL PART OF THE MOBILE UNIT AND ALLOWS THE OPERATOR TO MONITOR THE SOLIDIFICATION PROCESS.
3.4 SYSTEM OPERATION 3.4.1 BEFORE BEGINNING ANY WASTE PROCESSING WITH THE CEMENT SOLIDIFICATION UNIT, THE CNSI OPERATOR SHALL COMPLETE A SUCCESSFUL SAMPLE VERIFICATION IN ACCORDANCE WITH THE SAMPLE VERIFICATION PROCEDURE OF SECTION 5.0.
3.4.2 THE SUCCESSFUL SAMPLE SOLIDIFICATION PARAMETERS ARE RECORDED ON A SOLIDIFICATION WORKSHEET (FIGURE 1)*
THESE PARAMETERS ARE AMPLIFIED FOR FULL SCALE SOLIDIFI CATION VALUES TAKEN FROM FIGURES 2 THROUGH 5, AS APPROPRIATE*
3.4.3 ACTUAL FULL SCALE SOLIDIFICATION SHALL THEN BE CONDUCTED IN ACCORDANCE WITH THE MSU OPERATING PROCEDURE (REF.
2.4) USING THE PARAMETERS CALCULATED ON THE BATCH SOLIDIFICATION FORM ON THE BOTTOM OF FIGURE 1.
4 SEQUENCE OF OPERATION THE CONDITIONING CHEMICALS MAY BE PRELOADED INTO THE LINER OR ADDED TO THE WASTE WHILE MIXING. THE ADDITION OF CHEMICALS OR WASTE MAY BE INTERRUPTED AT ANY TIME.
THE MIXER MAY ALSO BE SECURED DURING WASTE OR CHEMICAL ADDITION WITH NO EFFECT ON THE PROCESS, HOWEVER, IT MUST REMAIN IN OPERATION DURING THE CEMENT ADDITION. AFTER CEMENT ADDITION, THE MIXER IS SECURED AND THE PROCESS IS COMPLETE*.
3.4.5 MIXER SPEED THE MIXER SPEED SHOULD BE HIGH ENOUGH TO ALLOW COMPLETE MIXING OF WASTE CONDITIONER AND CEMENT. GENERALLY, THE SPEED WILL BE SET AT 40 RPM WHILE ADDING CONDITIONING CHEMICALS AND 40 To 75 RPM WHEN STARTING CEMENT ADDI TION. THE SPEED WILL BE INCREASED TO 100 RPM AFTER TWO THIRDS OF THE CEMENT HAS BEEN ADDED*
3.4.6 WASTE-TO-CEMENT RATIO (BY VOLUME)
THE NORMAL WASTE-TOCEMENT/CONDITIONER RATIO (BY VOLUME)
WILL BE APPROXIMATELY 2 TO 1 FOR BORIC WASTE AND ABOVE 2.5 TO 1 FOR RESINS, POWDEX AND OTHER SOLIDS
,DOCUMENT REV. SHEET SD-OP-003- D 5.
CNSQ 1o62/8-78
IF ORMAL RATIOS ARE EXCEEDED, CURE lIME MAY BE DELAYED AND THE SOLIDIFIED PRODUCT MAY HAVE FREE-STANDING WATER ON ITS SURFACE*
3.4.7 CURE TIME CURE TIME WILL USUALLY BE 24 To 72 HOURS AND THE TEMPER ATURES MAY RISE DURING THIS TIME TO 2000 F. THE LINER SHOULD BE VENTILATED UNTIL TEMPERATURE STARTS DECREASING INDICATING A COMPLETED REACTION 4.0 REQUIREMENTS FOR SAMPLE VERIFICATION 4.1 GENERAL PRECAUTIONS NOTE: IFDIFFICULTIES ARE ENCOUNTERED WITH ANY PART OF THIS VER IFICATION PROCEDURE OR UNEXPECTED RESULTS ARE OBTAINED, CON TACT THE SOLIDIFICATION MANAGER, PROJECT ENGINEER OR SUPERVISOR.
4.1.1 THE CHEMICALS AND CEMENT USED ARE CONSIDERED NON-TOXIC AND SAFE TO HANDLE, HOWEVER, CARE SHOULD BE USED TO AVOID BREATHING DUST* IF A LIQUID CAUSTIC IS USED FOR SPECIAL APPLICATIONS, FOLLOW THE SAFETY PRECAUTIONS OUT LINED IN THE APPROPRIATE OPERATING PROCEDURE, REF. 2.4.
4.2 RADIOLOGICAL PRECAUTIONS 4.2.1 THE CNSI OPERATOR SHALL BE SUBJECT TO THE APPLICABLE HEALTH PHYSICS AND SAFETY PRECAUTIONS OF THE FACILITY PROVIDING THE RADIOACTIVE WASTE*
4.2.2 LABORATORY GLOVES, FACE SHIELD AND AN APRON SHALL BE WORN WHILE HANDLING, COLLECTING AND TESTING OF ALL SAMPLES*
4.2.3 THE CNSI OPERATOR SHALL ESTABLISH RADIOLOGICALLY CLEAN AND CONTAMINATED ZONES IN THE SAMPLE PROCESS AREA TO PREVENT THE POSSIBLE SPREAD OF CONTAMINATION*
4.3 PREREQUISITES 4.3.1 WASTE RECIRCULATION 4.3.1.1 DUE TO THE IMPORTANCE OF OBTAINING A REPRE SENTATIVE SAMPLE FOR USE IN THE VERIFICATION PROCEDURE, THE WASTE GENERATING FACILITY PER SONNEL SHALL CONFIRM THAT THE CONTENTS OF THE WASTE STORAGE TANK HAVE EITHER BEEN RECIRCU LATED FOR A MINIMUM OF THREE VOLUME,TURNOVERS OR ARE ADEQUATELY MIXED TO ACHIEVE A HOMO GENEOUS MIXTURE*
4.31.2 ANY NUMBER OF MECHANICAL OPERATIONS OF THE WASTE STORAGE TANK MAY NEGATE THE EFFECTS OF
. PREVIOUS RECIRCULATION/AGITATION PERIOD THESE OPERATIONS WOULD INCLUDE THE FOLLOWING:
DOCUMENT REV. SHEET SD-OP-003-NP D 6 CNSQ 1002/8-78
4.31.2.1 INTRODUCTIO F ADDITIONAL WASTE INTO THE STORAGE TANK AFTER RECIRCULATION HAS COMMENCED*
4.3*12.2 SECURING OF RECIRCULATION WHILE
- DRAWING THE VERIFICATION SAMPLE*
4.3*12.3 SHIFTING FROM A RECIRCULATION MODE TO A TRANSFER MODE*
4.3*1.3 IF ANY OF THE SITUATIONS LISTED ABOVE OCCUR, IT WILL BE NECESSARY TO REPEAT THE RECIRCU LATION PROCESS AND SAMPLE VERIFICATION PRO CEDURE OF SECTION 5.0 IN ORDER TO RE-ESTAB LISH THE SOLIDIFICATION PROCESS PARAMETERS*
14.35.2 THE ACTIVITY SUPPLYING WASTE SHALL IDENTIFY THE WASTE PROPERTIES AS FAR AS PRACTICABLE, I*E; OIL CONTENT, DEN SITY, TYPE, ESTIMATED ACTIVITY, DETERGENT CONTENT, ETC*
WASTE CONTAINING OIL ABOVE ONE PERCENT BY VOLUME SHALL NOT BE SOLIDIFIED BY THIS PCP*
4.3.3 EQUIPMENT EQUIPMENT REQUIRED TO USE DURING THE SAMPLE VERIFICATION PROCEDURE IS LISTED IN TABLE 1. THE TABLE INDICATES THE MINIMUM QUANTITY REQUIRED TO BEGIN A VERIFICATION PROCEDURE*
THE CNSI OPERATOR SHALL ENSURE THAT ALL NECESSARY EQUIP MENT IS AVAILABLE OR ADEQUATE SUBSTITUTES ARE AVAILABLE*
THE CNSI OPERATOR SHALL ENSURE THAT ADDITIVES RECEIVED COMPLY WITH THE CHEMICAL COMPOSITION NECESSARY FOR THIS PROCESS.
TABLE 1 EQUIPMENT REQUIRED FOR TESTING SAMPLES 600-1000 ML CONTAINERS WITH LIDS (6) CHEMICALS TO BE USED SHOULD BE STIRRING DEVICES (5) TAKEN FROM THE FULL SCALE PIPETTES (2) SOLIDIFICATION CHEMICALS AND ARE PIPETTOR LISTEDON THE RESPECTIVE FIGURE 0-2120F THERMOMETER FOR EACH WASTE FORM PH PAPER: WIDE RANGE (1*0 TO 11*0)
NARROw RANGE (8.0 TO i2.O)
U-600 OR U-1000 GM TRIPLE BEAM BALANCE IF LIQUID CAUSTIC IS USED:
50 ML BURET (2)
RING STAND BURET CLAMP (2)
MARKING PEN SAMPLE HEATING OVEN, THERMOSTATICALLY CONTROLLED FROM 1000 F TO 1800 F.
DOCUMENT REV. SHEET SD-OP-003-NP D 7 CNSQ 1002/8-78
4.4 SAMPLE ACCEPTANCE CRITERIA IN ORDER TO ENSURE ACCEPTABLE SOLIDIFICATION HAS OCCURRED, THE CNSI OPERATOR SHALL CONFIRM THAT ALL ACCEPTANCE CRITERIA ARE MET AS FOLLOWS:
4.4.1 VISUAL INSPECTION OF THE MIXTURE AFTER CEMENT ADDITION WILL CONFIRM THAT THE MIXTURE IS HOMOGENEOUS WITH NO FREE WATER ON THE SURFACE*
4.4.2 VISUAL INSPECTION OF THE END PRODUCT AFTER HARDENING IS A UNIFORM, LIQUID FREE, FREE STANDING MONOLITH*
4.4.3 THE END PRODUCT RESISTS PENETRATION WHEN PROBED WITH A PENCIL SIZE PROBE.
4.5 REQUIREMENTS FOR SAMPLE VERIFICATION 4.5.1 VERIFY THAT ALL MATERIAL LISTED IN TABLE 1 IS AVAILABLE AND READY TO USE IN THE AREA SELECTED BY THE UTILITY FOR SOLIDIFICATION SAMPLING*
4.5.2 REFER TO FIGUREs 2 THROUGH 5, AS APPLICABLE, WHEN CONDUCTING SAMPLE VERIFICATION* USE THE SOLIDIFICATION WORK SHEET, FIGURE 1, FOR ALL SAMPLE SOLIDIFICATIONS*
4.5.3 SAMPLE REQUIREMENTS 4.5.3.1 A SAMPLE SHALL BE SOLIDIFIED PRIOR TO FULL SCALE SOLIDIFICATION OF WASTE* IF THERE IS NO CHANGE IN THE CHEMICAL COMPOSITION OF THE WASTE AS VERIFIED BY THE UTILITY, TEST RE SULTS AND FULL SCALE SOLIDIFICATIONS WILL BE CONSIDERED REPRODUCIBLE* THEREAFTER, A SAM PLE SOLIDIFICATION WILL BE CONDUCTED PRIOR TO THE TENTH BATCH SOLIDIFIED FROM THE SAME SOURCE OF WASTE*
4.5.3.2 THE CNSI OPERATOR SHALL ENSURE THAT THE SAM PLE IS REPRESENTATIVE (I*E) THOROUGHLY MIXED)
AND THAT THE SAMPLE LINE IS PROPERLY PURGED PRIOR TO DRAWING THE PCP SAMPLE*
5.0 SNIPLE VERIFICATION 5.1 CALCULATE AND RECORD THE AVAILABLE INFORMATION ON FIGURE 1 FOR ALL WASTE TYPE SAMPLE VERIFICATIONS.
5.2 USE THE APPROPRIATE FIGURE (FIGURES 2 THROUGH 5) FOR THE SAMPLE AND FULL SCALE CALCULATIONS*
DOCUMENT REV. SHEET SD-OP-003-NP D 8 CNSQ 1002/8-78
NOTE: WASTE SOLIDIFIED ON A SMALL SCALE WILL CURE MUCH SLOWER BECAUSE OF THE EXCESSIVE SURFACE TO VOLUME RATIO FOR HEAT TRANSFER. SAMPLE STORAGE IN AN APPROVED CONSTANT TEMPERA TURE OVEN WILL ENABLE A MORE MEANINGFUL EVALUATION ON AN OVERNIGHT BASIS.
6'.0 ADMINISTRATIVE PROCEDURES 6.1 MAINTENANCE OF RECORDS 6.1.1 THE CNSI OPERATOR SHALL FORWARD A COPY OF ALL COMPLETED SAMPLE VERIFICATION FORMS TO THE MANAGER, SOLIDIFICATION SERVICES FOR REVIEW FOLLOWING COMPLETION OF LINER SOLIDIFICATION*
6.1.2 FIGURE 1 SHOULD BE USED AS A COVER SHEET WHEN FORWARDING RECORDS*
DOCUMENT REV. SHEET 9 SD-0P-003-NP D 9 CNSQ 1002/8-78
FIGURE 1 SOLIDIFICATION WORKSHEET OPERATOR DATE UTILITY WASTE TYPE/DESCRIPTION:
(CONCENTRATION, RESIN TYPE, DENSITY, ETC*)
SAMPLE SOLIDIFICATION SAMPLE VOLUME ML CEMENT (PORTLAND 1)
SAMPLE EVALUATION: (TIME DESCRIPTION, ACCEPTABLE, ETC.)
BATCH SOLIDIFICATION WASTE VOLUME WASTE ALARM CEMENT HIGH LEVEL*
CEMENT ALARM
- HIGH LEVEL ALARM SET 2 INCHES BELOw LINER Top NOTE: THE CEMENT LEVEL ALARM IS A REDUNDANT PROTECTIVE DEVICE.
THE EXACT AMOUNTS OF CEfIENT ADDED WILL BE MONITORED BY THE IQAn n F IrnPIITF DOCUMENT REV. SHEET SD-OP-OuS-NP D 10 CNSQ 1002/8-78
FIGURE 5 LINER AND CASK CALCULATIONS LI NER L21-300 L14-195 L14-170 L8-120 L7-100 L6-80 DIAMETER 82" 76" 74" 61" 74.5" 58" HEIGHT 104.5" 75.5" 69.37" 71.5' 37" 54" VOLUME 317 196 174 120 93 82 USEABLE VOLUME )11 190 169 116 88 79 (2" SAFETY FACTOR)
FT /IN 3.05 2.62 2.52 1.69 2.52 1.53 WEIGHT 2400 1850 1550 1250 1400 1100 CASK PAYLOAD 27250 17700 14000 20000 13000 7500 DOCUMENT REV. SHEET SD-OP-003-NP D 18 CNSO 1002/8-78