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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC L-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20217G1071999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Vogtle & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Plans to Conduct Core Insps at Facility Over Next Six Months ML20217G0801999-10-0707 October 1999 Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20217B0141999-10-0101 October 1999 Forwards Insp Repts 50-424/99-06 & 50-425/99-06 on 990725- 0904 at Vogtle Units 1 & 2 Reactor Facilities.Determined That One Violation Occurred & Being Treated as non-cited Violation ML20212J8801999-09-30030 September 1999 Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1 ML20212J8391999-09-30030 September 1999 Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr ML20212F8861999-09-23023 September 1999 Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000 L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999 Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2 L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999 Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2 ML20212E7031999-09-23023 September 1999 Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues ML20212F1111999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20212D0101999-09-15015 September 1999 Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999 Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20212D4581999-09-10010 September 1999 Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant ML20212C8041999-09-10010 September 1999 Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211N8041999-09-0808 September 1999 Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses ML20212C0071999-09-0202 September 1999 Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999 Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211G6851999-08-26026 August 1999 Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999 Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727 ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20210V0881999-08-16016 August 1999 Forwards Insp Repts 50-424/99-05 & 50-425/99-05 on 990620- 0724.No Violations Noted.Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210T2021999-08-0606 August 1999 Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents ML20210Q4641999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC L-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20212F8861999-09-23023 September 1999 Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000 L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999 Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2 L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999 Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2 ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20212D0101999-09-15015 September 1999 Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999 Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999 Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999 Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727 ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-027, Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.51999-07-27027 July 1999 Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.5 ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines ML20210C8011999-07-21021 July 1999 Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001 L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments ML20209H3881999-07-14014 July 1999 Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2 L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed ML20209C4041999-07-0101 July 1999 Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl ML20196J8631999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-249, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-025, Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.211999-06-30030 June 1999 Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.21 L-99-024, Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC1999-06-30030 June 1999 Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC ML20196F9171999-06-21021 June 1999 Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage ML20212J2521999-06-21021 June 1999 Responds to NRC RAI Re Yr 2000 Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701 ML20195F8031999-06-11011 June 1999 Forwards Changes to VEGP Unit 1 Emergency Response Data Sys (ERDS) Data Point Library.Changes Were Completed on 990308 While Unit 1 Was SD for Refueling Outage 1999-09-23
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Georg:a Power Company 40 invemess Center Pa** aay
. Post O*ce Ba 1295 Bmngnam Maoama 35201
- leiephow 205 B77-7122 L
C.K.McCoy Georgia Power i Re P esicent Nudear 7,, ne soumem erac smem ;
August 26, 1993 !
i Docket Nos. 50-424 LCV-0131 -
50-425 U.S. Nuclear Regulatory Commission '
Attn.: Document Control Desk Washington, DC 20555 i f
Vogtle Electric Generating Plant {
Report of Unsatisfactory Performance Testino i Gentlemen: !
In accordance with 10 CFR 26 Appendix A, paragraph 2.8, Georgia Power l Company requires that blind performance test specimens be submitted to the HHS-certified laboratory used to confirm the presumptive positive on-site screens. On July 14, 1993 a presumptive positive sample was forwarded from the Southern Nuclear Operating Company (Southern Nuclear) screening facility at the Vogtle Electric Generating Plant to SmithKline Beecham '
Clinical Laboratories (SKBL) located in Atlanta Georgia for confirmation i testing. (Southern Nuclear is the Fitness-for-Duty contractor for Georgia ;
PowerCompany.) On July 16, 1993 the sample was reported as negative by t the Medical Review Officer. An investigation of the discrepancy was begun ;
immediately upon receipt of the Medical Review Officer report. ;
The subsequent investigation determined that various changes in the Olympus i analyzer used by SKBL had been made to try to ascertain the underlying i cause of the error. SKBL's investigation involved, but are not limited to, i changing a Teflon ferrule inside a reagent valve, a source lamp change and l l a readjustment of the reagent probe and sensor probe.
j Corrective actions by SKBL include requesting a biomechanical engineer !'
representative from the Olympus company to perform a sample probe alignment on the Olympus machine. In addition, SKBL has added a special precision check after every calibration to verify probe alignment and precision in order to prevent reoccurrence of this error. The enclosures contain the .
i corrective action documentation.
Within the past two months, Southern Nuclear has experienced five l unsatisfactory performance testing events. All events were blind i performance samples, provided by ElSohly Laboratories, involving false '
negative reports on either amphetamines or cannabinoids. An investigation '
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I U. S. Nuclear Regulatory Commission Page 2 i was conducted on two of these events by Southern Nuclear for the Joseph M.
- Farley Nuclear Plant. Reports on all events either have been and will be i transmitted to the NRC in accordance with the regulations. Southern i Nuclear's Corporate Quality Services in cooperation with a consulting i toxicologist, Dr. Chris Frings, conducted a follow-up audit on August 2, i 1993 of SKBL's investigation of the events and subsequent resolutions. The j report of the audit was satisfactory. ;
In addition, SKBL has identified and corrected the interference issue with' l amphetamine as reported to the NRC by Georgia Power on July 2, 1995. The !
laboratory has changed from a DB-5 to a DB-1 column in the gas !
chromatograph to separate amphetamine and B-phenethylamine. These reports !
are also enclosed. i In addition, the findings and supporting documents by SKBL and E1Sohly f Laboratories are enclosed. This letter-is considered to satisfy the ;
reporting requirements of 10 CFR 26 Appendix A, paragraph 2.8. !
Should you have v i m tions, please advise.
l Respectfully submitted, l W
C. K. McCoy_ i Enclosures CKM/JMG ,
cc: Georaia Power Company J. B. Beasley, General Manager - Plant Vogtle U. S. Nuclear Reaulatory Commission. Washinoton DC D. S. Hood, Licensing Project Manager .Vogtle 1
Q. S. Nuclear Reaulatory Commission. Reaion 11 i S. D. Ebneter, Regional Administrator B. R. Bonser, Senior Resident Inspector - Vogtle LCV-0131
i l
r i .-
s l
! FALSE NEGATIVE THC SUhBIARY REPORT--
August 9,1993 l Specimens: 817844G 867883G !
877678G Results Reported: Negative i
Expected Results: THC l i
Reason: These specimens all screened borderline negative initially. All QC was !
acceptable. Other blind THC specimens submitted by the client were I correctly reponed as positive. Repeat analysis of problem specimens by j immunoassay and GC/MS gave positive results. This data suggested (
random outliers were being generated since QCs were acceptable. A !
special protocol to recreate these " fliers" was initiated to determine the cause. By looking at precision oflarge numbers of repeat analyses (n = ;
80 or 50) we were able to reproduce and verify that random fliers were indeed being generated, although statistical precision was acceptable.
i Using this special precision protocol we were able to investigate, in a stepwise fashion, potential causes of random outliers. The items f investigated, but determined n9.1 to be the cause of these outliers, were:
l :
l UV12mp i Valve seals ,
Analytical unit companson Instrument comparison j Channel comparison Optics Specimen aging / handling l THC absorption to sample cups j Water Purity (pH and bacterial contamination)
Mixing bar function Reagent equilibration )
l I
l
SmithKImo B:ccham.
l ClinicalLaboratories !
1 I
i August 9,1993 :
l
~
Ms. Sheree Carter ]
Health Services Coordinator Southern Nuclear Operating Company P.O. Box 1295 Birmingham, Alabama 35201 j
Dear Sheree:
Now that our investigations are complete, I am writing to respond to the concerns brought up in your letter of June 16,'1993.
As requested, we did perform audits and fax reports weekly to Paul Bizjak for a period of one month.
The second false negative amphetamin-e (V931494) was included in the overall investigation since both were due to the same interference as explained in the enclosed summary report. I l previously forwarded the report from Doctors and Physicians Laboratory.
l l The problem with channel one on the Olympus was originally attributed to a reagent valve seal.
(which was replaced as explained in my letter of June 10,1993 to Paul). Further investigations were devised employing a protocol to recreate the symptom / problem by using large batches of repeat analyses. This is explained in detail in the enclosed summary report. We were successful -l in capturing real-time evidence of the sympton. This allowed us to investigate stepwise every.
aspect of the testing procedure, both instrument and reagent-dependent, that could generate a change in performance. The problem was fmally isolated and identified as sample probe alignment.
To solve the problem, the sample probe was aligned to extend 1-2 mm beyond the liquid level sensor. The manufacturer only requires that the probe be level with the sensor. In channel one, i the probe was actually found to be 1-2 mm shorter than the sensor, which is consistent with the more frequent occurrence of these random outliers on this channel. Since adjusting the probe in all analytical units, random suppression in all channels has been eliminated. Data are still being collected to monitor this.
. P.o. Box 50122 + Atlanta, GA 30302 + (404) 934-9205
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Letter - Carter Page 2 To prevent reoccurrence of this incident, weekly maintenance of the Olympus now includes a "special" precision check after recalibration to verify probe alignment and precision.
This problem was isolated to the probe alignment and was nR1 related in any way to the use of extender with the Syva EMIT kits. We have verified that this would have occurred even if we .
used the manufacturer's recommended reconstitution protocol.
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The enclosed summary repons are included for your review. If you need any additional detail, please let me know. I hope that this report to you exemplifies our commitment to excellence !
and service. ],
Sincerely, r )
I ,
Michael S. Feldman, Ph.D.
Technical Manager - Substance Abuse Testing l
SmithKline Beecham Clinical Laboratories - Atlanta
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I ENCLOSURE I
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l i FALSE NEGATIVE AMPHETAMINES
SUMMARY
REPORT
! August 9,1993 i
Specimens: 781969G 811391G Results Reported: Negative
! Expected Results: Methamphetamine Amphetamine Reason: All QC criteria for the confirmation load was acceptable. Methamphetamine was detected by GC/MS at a concentration of 2046. A compound which appeared to be amphetamine was detected at a concentration 2358. However, there was an interference with the 91 m/z fragment of amphetamine. Consequently, not all identification criteria for amphetamine were satisfied and, due to the
" amphetamine ru!c" (positive methamphetamine requires amphetamine), both methamphetamine znd amphetamine were reported as negative.
S-phenethylamine is a natural putrification product of phenylalanine normally found in fresh urine at levels of about 30 ng/ml, which is much lower than our detection limit. The compound is structurally similar to amphetamine and they share extraction and chromatographic properties. Our method, at the time, could not adequately separate these compounds, and, since they both generate a 91 m/z ion fragment, interference would exist if the phenethylamine concentration increased to a high enough level. In theory, this could happen if pooled human urine is used over a period of time to make up QC materials.
Resolution: Since this is likely to be a recurring issue, we took the position that our method needs to achieve separation between amphetamine and S-phenethylamine, without introducing other chromatographic problems. We were able to achieve this by changing our chromatographic method to utilize a DB-1 (dimethylpolysiloxane) column rather than a DB-5 (5% phenyl-methylpolysiloxane) column. The daily retention time standard will include phenethylamine to document resolution daily.
Appendixes A. Original chromatograms of 781969G and 811391G showing interference on DB-5.
B. Chromatograms of 781969G and 811391G showing acceptable chromatography.
C. Section of the SOP that documents the change to DB-1.
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, APPENDIX' A- l Original chromatograms of 781%9G and 811391G showing interference on DB-5. l I
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Amphetamine confirmation >
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- C : \HPCHEM\ 1 \ DATA \ AM 0510 \M 051012 . D
.<rator : JGB fAcquired : 10 May 93 7: 2 pm using AcqMethod NEWAMP.M on MSD-13 j Sample Name: 7 819 69G j Misc Info :
Vial Number: 12 CurrentMeth: C:\HPCHEM\1\ METHODS \NEWAMP.M cphetcmine-D5 [STD1 i
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i a n i 6 e i l2.89 3.14 2.89 3.14 2.89 3.14
! Merged 144.00 123.10 l
'nmphetamine f fi! '
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, , < r l2.89 3.16 2.89 3.16_ 2.89 . 3.16 2.89 3.16 Merged 140.10 91.10 118.10 Compound Signal RT Resp Ratio Limits Conc.
l Amphetamine-D5 IST) 144.001 2.90l 36925l 100.0% l- 333.0 1 123.101 2.901 162121 43.9 36.2- 54.2 l Amphetamine l 140.10] 2.93l 2428051 100.0% l 2358.7 j 91.10j 2.93] 107 8 0 8 l 44.4 36.7- 55.1 l 118.10l 2.931 201712l 83.1 69.1- 103.7 lb Amphetamine Response Ratio j.......................................................................
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0 2 4 6 Amount Ratio Resp Ratio = 9.28e-001
- Amt RF Rel Std Dev = 1.1% [ Curve Fit: Avg RF AM051012.D Mon May 10 19:33:06 1993 Page 2
Amphetamine Confirmation File : C:\HPCMEM\1\ DATA \AM604\AM060018.D Operator : DBS Acquired : 4 Jun 93 10:53 pm using AcqMethod NEWAMP.M on MSD-13 Sample Name: 1811391G [5]
Misc Info :
Via1 Number: 18 CurrentMeth: C:\HPCHEM\1\ METHODS \NEWAMP.M Amphetamine-D5 XSTD1 .
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2.71 3.07 2.71 3.07 2.71 3.07 Merged 144.00 123.10 Amphetamine 1
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_ _ 4 t 2.71 3.08 2.71 3.08 2 1 3.08 2.71 3.08 .
Merged 140.10 91.10 118.10 Compound Signal RT Resp Ratio Limits Conc.
Amphetamine-D5 IST) 144.00l 2.84l 450631 100.0% l 333.0 l 123.101 2.841 19281l 42.8 33.5- 50.3 l A=phetamine l 140.10l 2.86l 576101 100.0% 1 2517.)
l 91.10l 2.86l 23259l 40.4 33.0- 49. l- .
l 118.10l 2.861 46557l 80.8 64.0- 96.0 ,
Amphetamine Response Ratio 5-0 1 4 4 0 2 4 6 Amount Ratio Resp Ratio = 8.46e-001
- Amt RF Rel Std Dev = 2.4% Curve Fit: Avg RF AM060018.D FIi Jun 04 23:04:00 1993 Page 2
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. APPENTIX B ;
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Chromatograms of 781969G and 811391G showing acceptable chromatography. l l
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False Negative THC Summary Report Page 2 8/4/93 l l Reagent dispensing i Reagent recipes j (SBCL vs reagent manufacturer's recommended reconstitution) ;
The problems was not determined to be specific to an analytical unit or channel, j
, although one channel exhibited more fliers than others, which was consistent with l l close examination of the probe alignment on that channel. Our investigation into sample dispensing uncovered the need to adjust the sample probe so that it' extends 1-2 mm beyond the liquid level sensor (this goes beyond the instrument
, manufacturer's specification.) It was found that short sampling was occurring :
without instrument detection. This could occur if the sensor made contact with ,
! the sample and the probe did not (the instrument did not know it was not picking )
up enough sample). The instrument is designed to signal a problem if the sensor failed to make contact with the liquid in the sample cup. Since the meniscus of I the liquid in the sample cup is not flat but concave, it was determined that it is l possible for a " properly aligned" sample probe to short sample occasionally, depending on where within the sample cup the sensor and probe made contact l with the meniscus. l l
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Resolution: To solve the problem, the probe was adjusted to extend 1-2 mm beyond the sensor to insure its immersion into the sample. Since this adjustment, we have genented more than 10 consecutive days of special precision data (n = 50 each day) which indicates that the random outliers have been eliminated. These sets l also included precision on a portion of the specimen, forwarded by Sheree Carter on July 22,1993, which was a part of the same lot of material that generated the false negative results. We will continue to collect precision data for an additional 2 weeks. We will modify our weekly instrument maintenance to include a special !
precision check to monitor probe alignment.
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In addition, the investigation showed that specifications for the optical system that j are more stringent than the manufacturer's recommendation also help eliminate I random " fliers". All of these new specifications have been incorporated into the laboratories SOP.
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i SUET 1ARY OF FALSE NEGATIVE INVESTIGATION 1 l l l l I l l SPECIMEN # ORIGINAL RESULT DATE REPEAT RESULTS DATE GC/MS RESULT l 817644G 0.980 6/3 1.034 6/5 200 ng/mi 1.091 7/16 :
567883G 0.879 7/9 1.058 7/14 142 ng/mi I (1.11)* 1.079 7/76 877678G 0.999 7/15 1.163 7/17 139 ng/mi j 831665G 1.269 6/12 1.042 7/14 '
l (1.14)* 1.011 7/16 207 ng/ml r
844673G 1.106 6/22 1.051 7/14 155 ng/ml (1.12)* 1.062 7/16 I I 1
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- (Resuh reported by SNOC) l Recalculated using SBCL ratio l l
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Amphetamine confirmation
! File : C : \HPCHEM\1 \ DATA \AM0731 \AM731009 . D .
l Operator, : GMK Acquired : .
2 Aug 93 3:24 pm using AcqMethod NEWAMP.M on MSD-13 i Sample Name: RB1969G l Misc Info :
Vial Number: 9 CurrentMeth: C:\HPCHEM\1\ METHODS \NEWAMP.M Amphetamine-D5 ESTD1
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2.97 e
3.25 i
2.97 3.25 2.97 .e25 3
Merged 144.00 123.10 IAmphetamine
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2.99 3.27 2.99 3.27 2.99 3.27 2.99 3.27 Merged 140.10 91.10 118.10 i
l l Compound Signal RT Resp Ratio Limits Conc.
l l Amphetamine-D5 IST) 144.00l 3.11) 43841] 100.0%- l 333.0 l 123.10l 3.11l 17948] 40.9 33.7- 50.5 l l
Amphetamine l 140.10l 3.13] 262857] 100.0% l '2161.1 l 91.101 3.13] 122967l 46.8 39.0- 58.6 l l 118.10l 3.13l 206848l 78.7 64.6- 97.0 l t
! Amphetamine Response Ratio 2________________________________________________ _______._________________ -
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0 2 4 6 Amount Ratio 1
Resp Ratio = 9.24e-001
- Amt RF Rel Std Dev = 2.4% Curve Fit: Avg RF AM731009.D Mon Aug.02 15:34:33 1993 Page 2 l
! . Amphetamine confirmation File : C:\HPCHEM\1\ DATA \AM0731\AM731010.D Operator : JMK ,
l Acquired- : 2 Aug 93 3:41 pm using AcqMethod NEWAMP.M on MSD-13 l l Sample Name: B11391G l Misc Info :
! Vial Number: 10 CuzIentMeth: C:\HPCHEM\1\ METHODS \NEWAMP.M Amphetamine-D5 STD1
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)t 3 2.99 3.27 2.99 3.27 2.99 3.27 2.99 3.27 Merged 140.10 91.10 118.10 Compound Signal RT Resp Ratio Limits Conc.
Amphetamine-D5 IST) 144.00l 3.11) 41369l 100.0% l 333.0 l 123.10l 3.11l 16725l 40.4 33.7- 50.5 l Amphetamine l 140.101 3.13l 268576l 100.0% l 2340.1 I l 91.10l 3.13l 124749l 46.4 39.0- 58.6 l l l 118.10l 3.13l 210717l 78.5 64.6- 97.0 l '
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l Amphetamine I
Response Ratio
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0 2 4 6 Amount Ratio Resp Ratio = 9.24e-001
- Amt RF Rel Std Dev = 2.4% Curve Fit: Avg RF AM731010.D Mon Aug 02 15:51:54 1993 Page 2
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APPENDIX C l l
Section of the SOP that documents the change to DB-1.
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.. Amphetamine / Methamphetamine Analysis by GC/MS v2.2 Page 4 of 15 1
- 15. Transfer the derivatized extracts to GC/MS autosampler vials and cap immediately. l l !
INSTRUMENT PARAMETERS Hardware ,
Gas Chromatograph - 5890 HP Mass Selective Detector - 5970 HP Autoinjector - 7673 HP l Data System - DOS l
l Analytical Column - DB-1 Q&W or equivalent) _
15 meter I
0.25 mm ID 0.25 pm film thickness i Carrier Gas - Helium (ultra pure) 60 psi Regulated pressure Gas Chromatograph Linear Velocity 55 cm/sec. @ 200*C Split Vent - 12 milmin +2 l
Septum Purge - 2 mL/ min 0.2 .
Injection Liner - 4 mm ID split /splitiess, with silanized glass wool Septum - Low bleed septum - any brand l
( Autoinjector Injection volume -2 l Injection mode - Fast l Sample viscosity -0 Sample wash -0 Sample pump -2 Solvent wash A - 5 Methanol Solvent wash B - 5 Isooctane NOTE: Wash / Waste vials should be replaced every 40 injections.
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Approved by: Date:
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