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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] |
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Southem Califomia Edison Company:q <p ,
P. O. BOX 800 .
2244 WALNUT GROVE AVENUE ROS EM EAD. CALIFORNIA 98770 n En~ Erw e e^$'"N WCE
- RESIDENT November 3,1986 m r** <
3:3 303-840a U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. J. B. Martin, Regional Administrator
Dear Sir:
Subject:
Docket No. 50-362 IE Inspection Report No. 50-362/86-24 Response to Notice of Violation San Onofre Nuclear Generating Station, Unit 3 Mr. R. A. Scarano's letter of October 3,1986, issued IE Inspection Reports 50-206/86-35, 50-361/86-26 and 50-362/86-24, and forwarded a Notice of Violation (NOV) resulting from the July 28 through August 1 and August 11 through 15, 1986, inspection conducted by Messrs. H. S. North and J. E. Russell. In accordance with the requirements of 10 CFR 2.201, I Enclosure A to this letter contains the SCE response to the alleged violation. {
SCE was in compliance with all applicable regulations and procedural requirements regarding the respiratory protection requirements for the work performed on valve 531208MR135 under Radiation Exposure Permit 83001 on January 3, 1985. Although the retained records alone are not sufficiently definitive to conclusively show all the details of what occurred, SCE is certain beyond any reasonable doubt that work was not performed in violation of the Radiation Exposure Permit. The basis for our position does not rely on any single record but rather is based on the preponderence of evidence as discussed in detail in Enclosure B, " Statement of Fact and Circumstances."
SCE requests the NRC withdraw the alleged violation.
Very truly yours, vWh
Enclosures:
As stated cc: F. R. Huey (USNRC Senior Resident Inspector, Units 1, 2 and 3) 8612090861 DR 861203 ADOCK 05000362 PDR
. J2Wl 2
h ENCLOSURE A Response to the Notice of Violation contained in Appendix A to R. A. Scarano's letter of October 3, 1986.
Appendix A to Mr. Scarano's letter of October 3, 1986, states:
" Technical Specification 6.8.1 specifies that written procedures shall be established, implemented and mr.intained. Procedure 50123-VII-9.9, Revision 3, Radiation Exposure Permit Program, specifies in Section 6.3.3 that all personnel covered by the REP must follow the requirements specified in the REP. Radiation Exposure Permit 83001 required use of a respirator while working on Valve S31208MR135.
" Contrary to the above requirement, an individual performed work on Valve S31208MR135 under REP 83001 on January 3, 1985, and did not wear a respirator as required by the Radiation Exposure Permit.
"This is a Severity Level IV Violation (Supplement IV)."
RESPONSE
- 1. Denial of Violation Based on careful review of the evidence, and on the sworn statements of individuals involved, SCE denies that an individual performed work on valve S31208MR135 under Radiation Exposure Permit (REP) 83001 on January 3, 1985, without wearing a respirator as required by REP 83001.
- 2. Basis for Denial .
SCE, as discussed in detail in Enclosure B, believes that the preponderance of evidence demonstrates the allegation is false. As a result of an extensive investigation into this matter, SCE has determined the following facts:
- The Alleger was accompanied by a contract HP technician, who provided a sworn affidavit that he wore a respirator and would not
. have permitted any individual whom he accompanied to perform the job without a respirator.
- The Health Physics computer data system ORAD archive on the Alleger's respirator use documents that the A11eger had a respirator in his possession for his task under REP 83001.
- Records indicate that the Alleger's nasal swabs did not show contamination, which should have been present had he not worn a respirator.
- The need for a respirator on REP 83001 was clearly established by a previous radiation survey. Available HP foremen and technicians have stated it was " common knowledge" that a respirator was required for entry into this area, and that they are not aware of any confusion regarding REP 83001. No HP personnel recall denying the Alleger a respirator.
i 1
? ENCLOSURE A
- 2. Basis for Denial (Continued)
The Alleger made no statement to his supervisor, who has provided a sworn affidavit, regarding any unusual health physics / radiological activities or concerns about the work under REP 83001. Over 18 months have transpired since the work under REP 83001.
- 3. Corrective Steps Which Have Been Taken and The Results Achieved Notwithstanding that SCE believes this allegation is baseless and unsubstantiated, SCE, in reviewing this issue, identified enhancements made to the HP program either prior to, or subsequent to, the allegation and following the alleged event. These actions include:
(1) Administrative controls on the documentation of worker respiratory protection used during REP entries were strengthened prior to becoming aware of the allegation; (2) SCE issued a notice on October 31, 1986, which will be periodically reissued, to HP personnel to remind them of the importance of their sensitivity to a worker's concerns regarding REP requirements; and, addressing those concerns prior to commencement of work activities; and, (3) the existing counseling program has been expanded to include all radiation workers.
- 4. Corrective Steps Which Will Be Taken To Avoid Further Violations No corrective steps to avoid further violations are necessary in regard to this allegation.
- 5. The Date When Full Compliance Will Be Achieved SCE was in full compliance with all applicable regulations and procedures for the respiratory protection requirements for work performed on valve S31208MR135 under REP 83001 on January 3, 1985, 2
1
j ENCLOSURE B Statement of Fact and Circumstances
Background
San Onofre Unit 3 was returned to service in early December 1984 following a steam generator repair outage. At the time of the Unit 3 restart, Unit 2 had been shut down two months for its first refueling. Upon Unit 3 resuming operation in December 1984, airborne activity from gaseous fission products occurred whenever leaks developed in valves associated with the Unit 3 letdown system. The gaseous fission products were present in the Reactor Coolant System as a result of fuel cladding defects.
During the first 2 days of January 1985, several leaking valves in the Unit 3 side of the 24' level pipechase were identified. Attempts were made to mitigate the resulting airborne activity by: (1) identifying the leaking valves and initiating appropriate repairs; and (2) hanging a herculite barrier across Room 206 between the Unit 2 and Unit 3 ends of the pipechase, thereby attempting to confine airborne radioactive gases to the Unit 3 end.
Initial Attempt to Repair Valve MR135 Valve S31208MR135 (MR135), located in the 24' level pipechase, was identified as leaking on January 2,1985, and Maintenance Order (M0) 85010116 was written to repair the valve. The M0 instructions were " attempt to tighten leak (sic) pipe cap".
Boiler and Condenser (B&C) mechanic, Mr. Dan Reed, was assigned to correct the condition noted in the M0. He attempted to initiate work on the M0 the .
evening of January 2, 1985, but found that due to radiological condition (known airborne contamination in the 24' level pipechase area), he was not permitted by HP at the HP Control Point to perform work under the Radiation Exposure Permit (REP) for " Minor Maintenance", REP 82151. This was because the REP did not require sufficient dosimetry, protective clothing, or respiratory protection equipment. Therefore, at 0100 on January 3, 1985, Mr. Reed submitted a request for a new REP specifically for this M0. A new REP, 83001, was issued, which required that a survey be performed upon each entry and that protective clothing (PCs), special dosimetry and a respirator be worn, in addition to varying field dosimetry, plastic rainsuit and extra booties and gloves.
Mr. Reed obtained his PCs, dosimetry and a respirator and at 0715 entered the 24' level pipechase under REP 83001 to repair valve MR135. Mr. Reed was accompanied by an HP Technician, Mr. M. Greene, who took air samples specifically in preparation for the entry by Mr. Reed. Mr. Greene and Mr. Reed both wore respirators in accordance with REP 83001.5 Mr. Greene's radiation survey was documented as Survey #5003-14. The air sample results 5 NOTE: Mr. Greene provided a sworn affidavit that they both wore respirators in accordance with REP 83001. Mr. Reed's respirator useage is also recorded in the Health Physics computer ORAD archive.
Health Physics technicians, because they make many entries per shift, have not recorded their individual entries in order to minimize unnecessary paperwork. Therefore, HP technician respirator ,
useage documentation is not available in ORAD. '
1
,- ENCLOSURE B Initial Attempt to Repair Valve MR135 (Continued) were: 85% MPC particulate activity, 51% MPC iodine activity, and 123% MPC noble gas. Furthermore, Mr. Greene noted "... boron covers virtually the whole valve, vv is approximately 8 feet from floor,10" wide boron lined river on floor (water) leading to nearest drain hole."
When attempting to perform the repair, Mr. Reed was unable to reach the valve and noted this fact as a comment on the M0 "...but could not get to cap. I am too big. Dan Reed.". Since the leak remained, another, smaller individual was selected to work on the valve.
Second Entry for Valve MR135 Repair At 1441 on January 3,1985, a second B&C mechanic (the A11eger), entered the 70' level HP control point on REP 83001 and began preparations (i.e.,
obtaining appropriate dosimetry, respiratory protection and donning protective clothing) to enter the 24' level pipechase. The A11eger entered the pipechase at 1515, accompanied by Mr. Patrick Corbett, contract HP Technician2 .
Mr. Corbett performed airborne radioactivity sampling, specifically for the Alleger, as Mr. Greene had done for Mr. Reed, with similar airborne activity results: 55% MPC particulates; 205% MPC Iodine; and, 532% MPC noble gas.
The record of the Alleger's entries and exits on January 3,1985, were recorded in the Health Physics computer data system ORAD archive. For his entry at 1441 under REP 83001, the Alleger's entry into Job Location Code (JLC) 404, the 24' level pipechase, was tracked by use of an Individual MPC-hr Tracking Card (IMTC) or personnel log, which was used as the source document from which data were entered into the ORAD. The data entries into the ORAD are separate and independent from any requirements listed in the REP (i.e.,
the ORAD does not use the REP as a source document). The Alleger's record in ORAD is as follows:
Time Respirator Enter Exit JLC' Type
- 1441 1515 598 04 1515 1535 404 (Blank) 1535 1536 404 04 1535 1700 598 04 8 JLC - Job Location Code:
598 - Radwaste Building common area 404 - Radwaste Building 24' Elevation (location of valve)
- Respirator Type - 04 used to identify MSA Ultra View respirator with High Efficiency Particulate Air (HEPA) cartridge 8 NOTE: Mr. Corbett provided a sworn affidavit that, for work performed in the 24' level pipechase area, he wore a respirator and he would not have permitted the B&C mechanic (A11eger) to perform the job without a full face respirator.
2
- o. .
,. ENCLOSURE B Second Entry for Valve MR135 Repair (Continued)
The 34-minute period 1441 to 1515 is considered a reasonable time for job preparation and donning protective clothing. The 20-minute period 1515 to 1535 was for the actual work performed on valve MR135 at location 404. The ORAD data documents that the A11eger had a respirator in his possession at the start (1441) and conclusion (1535) of his task, confirming REP 83001 required a full face respirator.
The 1515 to 1535 entry for respirator type is blank; however, this entry was corrected by the ORAD computer clerk by adding a one minute record from 1535 to 1536. Making a second entry was the only method of correction available to the computer operator (the system would not accept a correction once data was entered). Therefore, the ORAD correction record of 1535 to 1536 was in full compliance with HP ORAD computer practices.
It is important to note that no other valid reason exist:; for this computer entry, since no worker would re-enter the work area for 1 minute wearing a respirator. In further support of the one-minute record being a correction to the previous 1515 to 1535 entry, is that the period 1535 to 1536 is " double counted" by being contained in the subsequent entry period of 1535 to 1700. If ,
the one-minute record were not a correction, the next entry wou d have been 1536 to 1700.
Post Repair Activities The A11eger and Mr. Corbett exited the pipechase at 1535. The 24' level HP Log noted that the valve was still leaking approximately 1 drip /second at the time of exit.
Upon reaching the 70' level HP Control Point, all personnel are required to check themselves for inadvertent contamination by radioactive material. When the A11eger performed this " frisk," he discovered facial contamination. Facial contamination has been found to occur as a result of improper removal of a person's respirator (i.e., when " pulled off" improperly, any material on the exterior edges of the mask will fall on or be dragged across the face). The HP Technicians at the control point completed a Personnel Contamination / Injury Report in accordance with established procedures.
As reported on the contamination form, the external skin of the nose was contaminated to 500 cpm. This external skin contamination was reduced to 200 cpm by decontamination and further reduced to 100 cpm by allowing decay of short-lived isotopes (the counts decreased with time). The short lived radioisotopes are typically daughters of noble gases; the key characteristic of this type of external skin contamination is the very short halflife (Rb-88,17 minute halflife). Therefore, for the Alleger's contamination, time was used to permit radioactive decay. The skin dose was conservatively estinated to be less than 1 mrem.
3
. i
,. ENCLOSURE B Post Repair Activities (Continued)
A nasal swab of the inside of the nose for internal contamination was obtained prior to decontamination activities and the results were negative. The absence of activity on the nasal swab is significant because had the A11eger not worn a respirator, detectable levels of contamination should have been found on the nasal swab. Calculations have shown that detectable levels of particulateTshould still have been present on the nasal swab had the Alleger failed to wear his respirator.
In accordance with procedures regarding facial contamination, a whole body count was required. The Alleger received a whole body count at 1811 on January 3, 1985.
The " action point" for initiating further HP investigation is 1% of the Maximum Permissible Organ Burden (MP08). Procedures require a more extensive body count (lay down counter) if an isotope exceeds 1% MPOB, or a dose evaluation if the level exceeds 5% MP08. For the A11eger's January 3,1985 count, Co-58 was detected at approximately 0.7% MP08, which is below any action level. Since the effective halflife of Co-58 in the human body is 8.4 days, no significant reduction in the detectable level of the isotope would have occurred between the time of first detection (frisking) and the time of the body count (less than 0.9% difference assuming contamination occurred at 1535, and body count at 1811). In any event, since the level detected was not significant and was orders of magnitude below allowable exposure limits, nc further action was necessary or taken.
SCE Investigation into the Allegations -
SCE has reviewed the NRC inspection report 50-362/86-24 and has thoroughly investigated its allegations:
I. A11eger was denied use of a respirator On October 21, 1986, SCE legal counsel met with the Alleger and his attorney. The Alleger again stated he had been denied the use of a respirator. However, the A11eger did not know the name of the HP person (s) who denied him the respirator, nor did he believe he would be able to identify them from pictures of HP staff obtained from site badge photographs. The Alleger further stated that the Technician who accompanied him on REP 83001 (he could not identify him) did not wear a respirator either.
As previously discussed, the ORAD documents that the A11eger had a respirator for work performed on January 3, 1985, under REP 83001.
The A11eger was accompanied by a contract HP technician who has provided a sworn affidavit that he wore a respirator and would not permit any individual whom he accompanied to perform the job without a respirator (this directly contradicts the Alleger's statement that the HP technician did not wear a respirator).
4
i; ENCLOSURE B 2 I. A11eger was denied use of a respirator (Continued)
If the Alleger had not worn a respirator, he would have had detectable levels of particulate activity on his nasal swab. Since no activity was present and he had a respirator issued to him as .
discussed above, we corclude the A11eger wore a respirator. .-
As documented by the ORAD archive for Mr. Reed and the sworn affidavit obtained from Mr. Greene, both individuals wore respirators for the 0715 entry. Therefore, it would be inconsistent for HP to change the respirator requirement of the REP subsequent to s the 0715 entry. "',t SCE discussed with the on duty HP Foreman the need for a respirator for the 24' level pipechase. The HP General Foreman on duty
- January 3, 1985, Mr. S. Jones, provided a sworn affidavit that he ,
was fully aware of Mr. Greene's survey (performed prior to the <
Alleger's entry), and based on that data he would not have permitted any work on the MR135 valve under REP 83001 without the use of a respirator; nor does he believe any confusion resulted from his correction on the REP. _
Discussions with available HP personnel who were on duty on ..
January 3, 1985, established: (a) personnel did not recall denying anyone a respirator; and (b) personnel recalled it was " common knowledge" that work performed during January 1985 in the Unit 3 end of the 24' level pipechase required a respirator due to the airborne activity and boric acid crystals. On the contrary, HP personnel .
state they would not have permitted personnel to enter the area -
without a respirator, nor would they have entered the area ,
themselves without one. It is inconceivable that an HP technician ~
t would wear a respirator and not require accompanying personnel.to wear one. ,
The Alleger's supervisor, Mr. J. Kipfstuhl, provided a sworn .
affidavit that the A11eger never made any statement (s) regarding any -
unusual health physics / radiological activities or concerns about the j work on MR135 under REP 83001.
Therefore, there is a preponderance of evidence that the A11eger wore a respirator.
II. A_11eger notation on M0 documented denial of respirator As stated in the NRC inspection report, the wording on the MO states:
. . . Also: A respirator should be worn as there are boron -
crystals approx. 1" thick covering this VV and connecting pipes. It is not possible to avoid stirring up airborne contamination." The NRC inspection report further states, "With respect to his (A11eger) notation, beginning with the word 'Also:' was meant as a warning to l others who might be called upon to work on that specific valve or in
, c 1
5 i
, - . - , , - , , . - - ---,,,.c .~v . - - . , . . , , - - - , - , , , . , - , ,
---w.- ---- , - - - -, - - , - - - --c,., . - - - - . - - - - - - -
,- ENCLOSURE B J II. Alleger notation on M0 documented dental of respirator (Continued) that area." This caution on boric acid crystals could as easily be interpreted as a fact that should be known (similar to the notes on the presence of boric acid crystals in Mr. Greene's 0715 survey results) and net as difficulty in obtaining a respirator.
Therefore, the specific wording of the M0 neither supports nor rejects the allegation that the Alleger was denied a respirator.
~
III. A correction on the REP caused confusion The NRC inspection report states that REP 83001, which was used for both Mr. Reed and the Alleger's entry, contained a correction, as follows: "In the Section V - Respiratory Equipment, portion of the REP, the block indicating Full Face Particulate had been checked and footnoted with a circled 3. Footnote circled 3 in the REP Section VI - Special Instructions to Workers specified, ' required for entry into Unit 3 side of pipe chase'. The circled 3 in the Section V and the circled 3 footnote in Section VI had been lined out and initialed by the then HP Foreman, Individual 'B'."
The NRC report concludes "... the interviews with the HP Foreman, s Individual 'B', and the job coverage technician, Individual 'E',
indicate that a respirator was both required and would have been used... It appears that as the result of confusion concerning the requirements of REP 83001, no respirator was issued or used contrary to the requirements of REP 83001."
In the sworn affidavit obtained from the HP General Foreman (Individual 'B'), he states that he deleted the footnote on respirator usage in the Unit 3 end of the pipechase to ensure that a respirator would be worn at the specific jobsite. The HP Foreman t further states: he remembers this job because of the physical condition of the area (boric acid crystals); and recalls specifically discussing with other HP technicians immediately
)-
after ("tailboard") the Greene/ Reed entry, the necessity for respiratory protection for future entries. Both the HP Foreman and the HP Technician covering the job, in the sworn affidavits obtained
- state that they were not confused by the correction to the REP.
S.CE, because of the length of time (18 months) since the incident, has not been able to contact all HP personnel who were on duty on January 3, 1985; however, of those persons contacted, none has ixpressed confusion as to whether the 24' level pipechase would have raquired a respirator. '.
During the day on January 3, 1985, prior to the A11eger's entry the
" computer" record copy (i.e., the "hard copy" original of the REP is posted and a copy is used to enter a computerized version of the REP into the HP computer system) of REP 83001 was changed and the REP respirator requirement was erroneously deleted. Although the ORAD a chive documentation that the Alleger wore a respirator is
. unaffected by this condition (0 RAD does not utilize the original or computer copy of the REP), it may be that the computer data entry clerk (not an HP technician) was confused by the correction when 6
__ __ _ , . , , _g_... - . , . . . - . _ , _ ,
a, ,
ENCLOSURE B j III. A correction on the REP caused confusiort (Continued) he/she entered the REP into the computer system. Notwithstanding I.
the computer clerk's apparent confusion, no HP technicians who would V have controlled the job have expressed any confusion regarding this correction.
Therefore, SCE considers the NRC statement that confusion existed on the part of the HP Foreman and HP lechnician, to be mistaken.
! . IV. A11eger spent an hour straightening aut mistakes on the REP The NRC inspection report; states "...under 'the Work Done section of the M0 85010116 the Alleger made the following entry: 'obtained proper REP 8300-1 had to wait I hour to have std-6 (refers to t special dosimetry package) made up, also had to wait another hour trying to straighten out mistakes on REP'". The NRC report further states ".. .with respect to his notation on M0 85010116, he stated that the one hour he spent, ' ...trying to straighten out mistakes on the REP', whs expended in attempting to obtain a respirator for the work from the radiation protection staff."
SCE had obtained from the ORAD entry record for the Alleger, that prior to inititting work on MO 85010116, he had entered the radwaste building from-1335 to 1351, under REP 82152, " Minor Maintenance."
Upon exiting the radwaste building at 1351, the A11eger may have spent time getting his next assignment (M0 85010116). From his 1351 exit on the prior job until he re-entered radwaste to initiate MO 85010116 at 1441, only 50 minutes elapsed. From the ORAD data, the A11eger then spent 34 minutes (1441 to 1515) danning protective gc clothing and traveling to the job location. Therefore, the Allegee's statement that he spent two hours getting dosimetry and
" straighten out mistakes on the REP" is inconsistent with his documented entry / exit times. In fact, he apparently spent less than an hour (expected time) getting ready for the job.
V. Alleger received a bloody' nose during decontamination As stated in the NRC inspection report, the Alleger stated "...that the nasal swabbing resulted in a bloody nose. Individual 'F' (the HP Technician who performed the decontamination) stated that while he could not recall the specific event, his activities in this respect had never resulted in a bloody nose." SCE obtained a sworn affidavit from the HP Technician (Individual 'F') confirming his statemant to the NRC that he never caused anyone a bloody nose while performing decontamination activitie=.
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- ENCLOSURE B VI. A11eger was held at the Control Point for 2 - 2 1/2 hours The NRC inspection report states "The A11eger stated during the July 30, 1986, interview that he had been held at the access control point because of the contamination for 2 to 2 1/2 hours, until a health physics representative on an oncoming shift directed him to go to the whole body counter." SCE reviewed the ORAD data for the Alleger and Mr. Corbett, which documented that the job-was completed at 1535 and the A11eger was released from the Control Point at 1700. Therefore, the maximum time was only 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 25 minutes.
This time included removing the respirator and protective clothing, returning the special dosimetry, frisking, decontamination, and completing the personnel decontamination report. Therefore, the A11eger's statement that he spent 2 to 2 1/2 hours at the control point is inconsistent with his documented entry / exit times.
VII. A11eger was overexposed The NRC inspection report states "The letter, dated July 21, 1986, specified that .. 2 (The A11eger) was exposed to radiation in excess of regulatory limits." SCE examined the A11eger's exposure records, and provided them to the NRC. As further discussed in the NRC inspection report, "The licensee concluded that a total of 0.68 effective MPC hours exposure occurred. However, if a respirator had not been used, the exposure could have been increased to 0.86 MPC hours. Exposures of up to 40 MPC hours per week are permissable as specified in 10 CFR 20.103... In regard to the second allegation with respect to the exposures in excess of regulatory limits, the !
allegation is not substantiated." -
Summary
- 1. Documentation from ORAD archives coupled with sworn affidavits obtained from the HP Foreman and the accompanying HP technician refute the l
allegation that the A11eger was denied use of a respirator.
~2. Interviews with participating personnel (HP foremen and technicians) establish that sufficient awareness and data (from Mr. Greene's 0715 radiological survey) was available to establish an obvious, clear requirement for a respirator. SCE believes, as supported by statements and affidavits from HP personnel, that no confusion existed among the HP technicians anc loremen regarding the REP respiratory requirements.
- 3. No detectable activity was present on nasal swabs; had the A11eger not worn a respirator, particulate activity should have been detected.
- 4. The Alleger was not overexposed to radioactive materials. In fact, his exposures were a small fraction of allowable exposure limits.
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Oa s e ENCLOSURE B Summary (Continued)
- 5. The A11eger is not considered credible as demonstrated by:
(1) his apparent misstatements on receiving a bloody nose, being held 2 - 2 1/2 hours for decontamination decay, and spending 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> getting dosimetry and straightening out mistakes on the REP; (2) the contradictory evidence, discussed above, from sworn affidavits obtained from other individuals; (3) that he never expressed any concern to his supervisor regarding work performed on valve MR135 nor on any aspects of his health and personnel protection against radiation from this event; and, (4) that it took 18 months for the A11eger to express any concern to SCE, and when the A11eger did so it was through a Workman's Compensation Claim against SCE for disability benefits due to the psychiatric trauma of being denied a respirator and being overexposed.
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