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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M4461999-10-20020 October 1999 Forwards Rev 8 to Sequoyah Nuclear Plant Physical Security/ Contingency Plan, IAW 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20217J4151999-10-15015 October 1999 Forwards Request for Addl Info Re Util 990624 Application for Amend of TSs That Would Revise TS for Weighing of Ice Condenser Ice Baskets 05000327/LER-1999-002, Forwards LER 99-002-00 Re Start of Units 1 & 2 EDGs as Result of Cable Being Damaged During Installation of Thermo- Lag for Kaowool Upgrade Project1999-10-15015 October 1999 Forwards LER 99-002-00 Re Start of Units 1 & 2 EDGs as Result of Cable Being Damaged During Installation of Thermo- Lag for Kaowool Upgrade Project ML20217G1141999-10-0707 October 1999 Responds to from P Salas,Providing Response to NRC Risk Determination Associated with 990630 Flooding Event at Sequoyah Facility.Meeting to Discuss Risk Determination Issues Scheduled for 991021 in Atlanta,Ga ML20217B2981999-10-0606 October 1999 Discusses Closeout of GL 92-01,rev 1,suppl 1, Reactor Vessel Integrity, for Sequoyah Nuclear Plant,Units 1 & 2. NRC Also Hereby Solicits Any Written Comments That TVA May Have on Current Rvid Data by 991101 ML20217B8431999-10-0505 October 1999 Requests NRC Review & Approval of ASME Code Relief Requests That Were Identified in Plant Second 10-yr ISI Interval for Both Units.Encl 3 Provides Util Procedure for Calculation of ASME Code Coverage for Section XI Nondestructive Exams ML20217C7101999-10-0101 October 1999 Forwards Response to NRC 990910 RAI Re Sequoyah Nuclear Plant,Units 1 & 2 URI 50-327/98-04-02 & 50-328/98-04-02 Re Ice Weight Representative Sample ML20212J5981999-10-0101 October 1999 Forwards SE Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plnat,Unit 1 ML20212M1081999-09-29029 September 1999 Confirms Intent to Meet with Utils on 991025 in Atlanta,Ga to Discuss Pilot Plants,Shearon Harris & Sequoyah Any Observations & Lessons Learned & Recommendations Re Implementation of Pilot Program ML20216J9351999-09-27027 September 1999 Responds to NRC Re Violations Noted in Insp Repts 50-327/99-04 & 50-328/99-04.Corrective Actions:Risk Determination Evaluation Was Performed & Licensee Concluded That Event Is in Green Regulatory Response Band ML20217A9451999-09-27027 September 1999 Forwards Insp Repts 50-327/99-05 & 50-328/99-05 on 990718- 0828.One Violation Identified & Being Treated as Non-Cited Violation ML20212F0751999-09-23023 September 1999 Forwards SER Granting Util 981021 Request for Relief from ASME Code,Section XI Requirements from Certain Inservice Insp at Sequoyah Nuclear Power Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) ML20212F4501999-09-23023 September 1999 Forwards Amends 246 & 237 to Licenses DPR-77 & DPR-79, Respectively & Ser.Amends Approve Request to Revise TSs to Allow Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20212A1631999-09-13013 September 1999 Forwards W Rept WCAP-15224, Analysis of Capsule Y from TVA Sequoyah Unit 1 Reactor Vessel Radiation Surveillance Program, Rev 0.Errata Sheet Containing Three Correction Pages to WCAP-15224 Also Encl ML20211Q0311999-09-10010 September 1999 Requests Written Documentation from TVA to Provide Technical Assistance to Region II Re TS Compliance & Ice Condenser Maint Practices at Plant ML20216F5441999-09-0707 September 1999 Provides Results of Risk Evaluation of 990630,flooding Event at Sequoyah 1 & 2 Reactor Facilities.Event Was Documented in Insp Rept 50-327/99-04 & 50-328/99-04 & Transmitted in Ltr, ML20211N5681999-09-0101 September 1999 Submits Clarification of Two Issues Raised in Insp Repts 50-327/99-04 & 50-328/99-04,dtd 990813,which Was First Insp Rept Issued for Plant Under NRC Power Reactor Oversight Process Pilot Plant Study ML20211G5881999-08-27027 August 1999 Submits Summary of 990820 Management Meeting Re Plant Performance.List of Attendees & Matl Used in Presentation Enclosed ML20211F8891999-08-25025 August 1999 Forwards Sequoyah Nuclear Plant Unit 1 Cycle 9 Refueling Outage, Re Completed SG Activities,Per TSs 4.4.5.5.b & 4.4.5.5.c ML20211A1851999-08-16016 August 1999 Forwards Proprietary TR WCAP-15128 & non-proprietary Rept WCAP-15129 for NRC Review.Repts Are Provided in Advance of TS Change That Is Being Prepared to Support Cycle 10 Rfo. Proprietary TR Withheld,Per 10CFR2.790 ML20210V1471999-08-13013 August 1999 Forwards Insp Repts 50-327/99-04 & 50-328/99-04 on 990601- 0717.One Potentially Safety Significant Issue Identified.On 990630,inadequate Performance of Storm Drain Sys Caused Water from Heavy Rainfall to Backup & Flood Turbine Bldg ML20211A1921999-08-12012 August 1999 Requests Proprietary TR WCAP-15128, Depth-Based SG Tube Repair Criteria for Axial PWSCC at Dented TSP Intersections, Be Withheld from Public Disclosure Per 10CFR2.790 ML20210Q5011999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006 at Sequoyah Nuclear Plant. Sample Registration Ltr Encl ML20210L4291999-08-0202 August 1999 Forwards Sequoyah Nuclear Plant Unit 2 Cycle 9 12-Month SG Insp Rept & SG-99-07-009, Sequoyah Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept. Repts Submitted IAW TS 4.4.5.5.b & TS 4.4.5.5.c ML20210L1611999-07-30030 July 1999 Forwards Request for Relief RV-4 Re ASME Class 1,2 & 3 Prvs, Per First ten-year Inservice Test Time Interval.Review & Approval of RV-4 Is Requested to Support Unit 1 Cycle 10 Refueling Outage,Scheduled to Start 000213 ML20210G5301999-07-28028 July 1999 Forwards Sequoyah Nuclear Plant Unit 2 ISI Summary Rept That Contains Historical Record of Repairs,Replacement & ISI & Augmented Examinations That Were Performed on ASME Code Class 1 & 2 Components from 971104-990511 ML20211B9661999-07-26026 July 1999 Informs That Sequoyah Nuclear Plant Sewage Treatment Plant, NPDES 0026450 Outfall 112,is in Standby Status.Flow Has Been Diverted from Sys Since Jan 1998 ML20210B2521999-07-14014 July 1999 Confirms 990712 Telcon Between J Smith of Licensee Staff & M Shannon of NRC Re semi-annual Mgt Meeting Schedule for 990820 in Atlanta,Ga to Discuss Recent Sequoyah Nuclear Plant Performance ML20210J1091999-07-10010 July 1999 Submits Suggestions & Concerns Re Y2K & Nuclear Power Plants ML20196K0381999-06-30030 June 1999 Provides Written Confirmation of Completed Commitment for Final Implementation of Thermo-Lag 330-1 Fire Barrier Corrective Actions at Snp,Per GL 92-08 ML20209E4071999-06-30030 June 1999 Forwards Insp Repts 50-327/99-03 & 50-328/99-03 on 990328- 0531.Violations Being Treated as Noncited Violations ML20196J8261999-06-28028 June 1999 Forwards Safety Evaluation Authorizing Request for Relief from ASME Boiler & Pressure Vessel Code,Section XI Requirements for Certain Inservice Inspections at Sequoyah Nuclear Plant,Units 1 & 2 ML20196G7881999-06-22022 June 1999 Informs NRC of Changes That Util Incorporated Into TS Bases Sections & Trm.Encl Provides Revised TS Bases Pages & TRM Affected by Listed Revs ML20196G1801999-06-21021 June 1999 Requests Termination of SRO License SOP-20751-1,for Lf Hardin,Effective 990611.Subject Individual Resigned from Position at TVA ML20195G1821999-06-0808 June 1999 Requests NRC Review & Approval of ASME Code Relief for ISI Program.Encl 1 Provides Relief Request 1-ISI-14 That Includes Two Attachments.Encl 2 Provides Copy of Related ASME Code Page ML20195E9521999-06-0707 June 1999 Requests Relief from Specific Requirements of ASME Section Xi,Subsection IWE of 1992 Edition,1992 Addenda.Util Has Determined That Proposed Alternatives Would Provide Acceptable Level of Quality & Safety ML20195E9311999-05-28028 May 1999 Informs of Planned Insp Activities for Licensee to Have Opportunity to Prepare for Insps & Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20195B3631999-05-21021 May 1999 Requests Termination of SRO License for Tj Van Huis,Per 10CFR50.74(a).TJ Van Huis Retired from Util,Effective 990514 ML20207A5721999-05-20020 May 1999 Forwards Correction to Previously Issued Amend 163 to License DPR-79 Re SR 4.1.1.1.1.d Inadvertently Omitted from Pp 3/4 1-1 of Unit 2 TS ML20206Q8791999-05-13013 May 1999 Forwards L36 9990415 802, COLR for Sequoyah Nuclear Plant Unit 2,Cycle 10, IAW Plant TS 6.9.1.14.c 05000327/LER-1999-001, Forwards LER 99-001-00 Re Condition That Resulted in Granting of Enforcement Discretion,Per Failure of Centrifugal Charging Pump.Condition Being Reported IAW 10CFR50.73(a)(2)(i)(B) & (a)(2)(iv)1999-05-11011 May 1999 Forwards LER 99-001-00 Re Condition That Resulted in Granting of Enforcement Discretion,Per Failure of Centrifugal Charging Pump.Condition Being Reported IAW 10CFR50.73(a)(2)(i)(B) & (a)(2)(iv) ML20206M9341999-05-10010 May 1999 Forwards Rept of SG Tube Plugging During Unit 2 Cycle 9 Refueling Outage,As Required by TS 4.4.5.5.a.ISI of Unit 2 SG Tubes Was Completed on 990503 ML20206K6271999-05-0606 May 1999 Requests Termination of SRO License for MR Taggart,License SOP-21336 Due to Resignation on 990430 ML20206J2061999-05-0404 May 1999 Requests Relief from Specified ISI Requirements in Section XI of ASME B&PV Code.Tva Requests Approval to Use Wire Type Penetrameters in Lieu of Plaque Type Penetrameters for Performing Radiographic Insps.Specific Relief Request,Encl ML20209J0391999-04-27027 April 1999 Forwards Annual Radioactive Effluent Release Rept, Radiological Impact Assessment Rept & Rev 41 to ODCM, for Period of Jan-Dec 1998 ML20206C0841999-04-23023 April 1999 Forwards Insp Repts 50-327/99-02 & 50-328/99-02 on 990214-0327.No Violations Noted ML20206C6541999-04-23023 April 1999 Forwards Response to NRC 990127 RAI Re GL 96-05 for Sequoyah Nuclear Plant,Units 1 & 2 ML20206B9591999-04-20020 April 1999 Responds to 990417 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in Unit 1 TS 3.1.2.2,3.1.2.4 & 3.5.2 & Documents 990417 Telephone Conversation When NRC Orally Issued NOED ML20205S5891999-04-17017 April 1999 Documents Request for Discretionary Enforcement for Unit 1 TS LCOs 3.1.2.2,3.1.2.4 & 3.5.2 to Support Completion of Repairs & Testing for 1B-B Centrifugal Charging Pump (CCP) ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR 1999-09-07
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217M4461999-10-20020 October 1999 Forwards Rev 8 to Sequoyah Nuclear Plant Physical Security/ Contingency Plan, IAW 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 05000327/LER-1999-002, Forwards LER 99-002-00 Re Start of Units 1 & 2 EDGs as Result of Cable Being Damaged During Installation of Thermo- Lag for Kaowool Upgrade Project1999-10-15015 October 1999 Forwards LER 99-002-00 Re Start of Units 1 & 2 EDGs as Result of Cable Being Damaged During Installation of Thermo- Lag for Kaowool Upgrade Project ML20217B8431999-10-0505 October 1999 Requests NRC Review & Approval of ASME Code Relief Requests That Were Identified in Plant Second 10-yr ISI Interval for Both Units.Encl 3 Provides Util Procedure for Calculation of ASME Code Coverage for Section XI Nondestructive Exams ML20217C7101999-10-0101 October 1999 Forwards Response to NRC 990910 RAI Re Sequoyah Nuclear Plant,Units 1 & 2 URI 50-327/98-04-02 & 50-328/98-04-02 Re Ice Weight Representative Sample ML20216J9351999-09-27027 September 1999 Responds to NRC Re Violations Noted in Insp Repts 50-327/99-04 & 50-328/99-04.Corrective Actions:Risk Determination Evaluation Was Performed & Licensee Concluded That Event Is in Green Regulatory Response Band ML20212A1631999-09-13013 September 1999 Forwards W Rept WCAP-15224, Analysis of Capsule Y from TVA Sequoyah Unit 1 Reactor Vessel Radiation Surveillance Program, Rev 0.Errata Sheet Containing Three Correction Pages to WCAP-15224 Also Encl ML20211N5681999-09-0101 September 1999 Submits Clarification of Two Issues Raised in Insp Repts 50-327/99-04 & 50-328/99-04,dtd 990813,which Was First Insp Rept Issued for Plant Under NRC Power Reactor Oversight Process Pilot Plant Study ML20211F8891999-08-25025 August 1999 Forwards Sequoyah Nuclear Plant Unit 1 Cycle 9 Refueling Outage, Re Completed SG Activities,Per TSs 4.4.5.5.b & 4.4.5.5.c ML20211A1851999-08-16016 August 1999 Forwards Proprietary TR WCAP-15128 & non-proprietary Rept WCAP-15129 for NRC Review.Repts Are Provided in Advance of TS Change That Is Being Prepared to Support Cycle 10 Rfo. Proprietary TR Withheld,Per 10CFR2.790 ML20211A1921999-08-12012 August 1999 Requests Proprietary TR WCAP-15128, Depth-Based SG Tube Repair Criteria for Axial PWSCC at Dented TSP Intersections, Be Withheld from Public Disclosure Per 10CFR2.790 ML20210L4291999-08-0202 August 1999 Forwards Sequoyah Nuclear Plant Unit 2 Cycle 9 12-Month SG Insp Rept & SG-99-07-009, Sequoyah Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept. Repts Submitted IAW TS 4.4.5.5.b & TS 4.4.5.5.c ML20210L1611999-07-30030 July 1999 Forwards Request for Relief RV-4 Re ASME Class 1,2 & 3 Prvs, Per First ten-year Inservice Test Time Interval.Review & Approval of RV-4 Is Requested to Support Unit 1 Cycle 10 Refueling Outage,Scheduled to Start 000213 ML20210G5301999-07-28028 July 1999 Forwards Sequoyah Nuclear Plant Unit 2 ISI Summary Rept That Contains Historical Record of Repairs,Replacement & ISI & Augmented Examinations That Were Performed on ASME Code Class 1 & 2 Components from 971104-990511 ML20210J1091999-07-10010 July 1999 Submits Suggestions & Concerns Re Y2K & Nuclear Power Plants ML20196K0381999-06-30030 June 1999 Provides Written Confirmation of Completed Commitment for Final Implementation of Thermo-Lag 330-1 Fire Barrier Corrective Actions at Snp,Per GL 92-08 ML20196G7881999-06-22022 June 1999 Informs NRC of Changes That Util Incorporated Into TS Bases Sections & Trm.Encl Provides Revised TS Bases Pages & TRM Affected by Listed Revs ML20196G1801999-06-21021 June 1999 Requests Termination of SRO License SOP-20751-1,for Lf Hardin,Effective 990611.Subject Individual Resigned from Position at TVA ML20195G1821999-06-0808 June 1999 Requests NRC Review & Approval of ASME Code Relief for ISI Program.Encl 1 Provides Relief Request 1-ISI-14 That Includes Two Attachments.Encl 2 Provides Copy of Related ASME Code Page ML20195E9521999-06-0707 June 1999 Requests Relief from Specific Requirements of ASME Section Xi,Subsection IWE of 1992 Edition,1992 Addenda.Util Has Determined That Proposed Alternatives Would Provide Acceptable Level of Quality & Safety ML20195B3631999-05-21021 May 1999 Requests Termination of SRO License for Tj Van Huis,Per 10CFR50.74(a).TJ Van Huis Retired from Util,Effective 990514 ML20206Q8791999-05-13013 May 1999 Forwards L36 9990415 802, COLR for Sequoyah Nuclear Plant Unit 2,Cycle 10, IAW Plant TS 6.9.1.14.c 05000327/LER-1999-001, Forwards LER 99-001-00 Re Condition That Resulted in Granting of Enforcement Discretion,Per Failure of Centrifugal Charging Pump.Condition Being Reported IAW 10CFR50.73(a)(2)(i)(B) & (a)(2)(iv)1999-05-11011 May 1999 Forwards LER 99-001-00 Re Condition That Resulted in Granting of Enforcement Discretion,Per Failure of Centrifugal Charging Pump.Condition Being Reported IAW 10CFR50.73(a)(2)(i)(B) & (a)(2)(iv) ML20206M9341999-05-10010 May 1999 Forwards Rept of SG Tube Plugging During Unit 2 Cycle 9 Refueling Outage,As Required by TS 4.4.5.5.a.ISI of Unit 2 SG Tubes Was Completed on 990503 ML20206K6271999-05-0606 May 1999 Requests Termination of SRO License for MR Taggart,License SOP-21336 Due to Resignation on 990430 ML20206J2061999-05-0404 May 1999 Requests Relief from Specified ISI Requirements in Section XI of ASME B&PV Code.Tva Requests Approval to Use Wire Type Penetrameters in Lieu of Plaque Type Penetrameters for Performing Radiographic Insps.Specific Relief Request,Encl ML20209J0391999-04-27027 April 1999 Forwards Annual Radioactive Effluent Release Rept, Radiological Impact Assessment Rept & Rev 41 to ODCM, for Period of Jan-Dec 1998 ML20206C6541999-04-23023 April 1999 Forwards Response to NRC 990127 RAI Re GL 96-05 for Sequoyah Nuclear Plant,Units 1 & 2 ML20205S5891999-04-17017 April 1999 Documents Request for Discretionary Enforcement for Unit 1 TS LCOs 3.1.2.2,3.1.2.4 & 3.5.2 to Support Completion of Repairs & Testing for 1B-B Centrifugal Charging Pump (CCP) ML20204H0161999-03-19019 March 1999 Resubmits Util 990302 Response to Violations Noted in Insp Repts 50-327/98-11 & 50-328/98-11.Corrective Actions:Lessons Learned from Event Have Been Provided to Operating Crews ML20205B1091999-03-19019 March 1999 Submits Response to NRC Questions Concerning Lead Test Assembly Matl History,Per Request ML20204E8251999-03-0505 March 1999 Forwards Sequoyah Nuclear Plant,Four Yr Simulator Test Rept for Period Ending 990321, in Accordance with Requirements of 10CFR55.45 ML20207E6851999-03-0202 March 1999 Responds to NRC Re Violations Noted in Insp Repts 50-327/98-11 & 50-328/98-11.Corrective Actions:Lessons Learned from Event Have Been Provided to Operating Crews ML20207J1171999-01-29029 January 1999 Forwards Copy of Final Exercise Rept for Full Participation Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific to Sequoyah NPP ML20202A7141999-01-20020 January 1999 Provides Request for Relief for Delaying Repair on Section of ASME Code Class 3 Piping within Essential Raw Cooling Water Sys 05000327/LER-1997-013-02, Forwards LER 97-013-02 Re Addl Conditions Identified During Performance of Corrective Actions.Details Added to Revs for Two Fuses,Not Included in Surveillance Program1999-01-11011 January 1999 Forwards LER 97-013-02 Re Addl Conditions Identified During Performance of Corrective Actions.Details Added to Revs for Two Fuses,Not Included in Surveillance Program ML20198S7141998-12-29029 December 1998 Forwards Cycle 10 Voltage-Based Repair Criteria 90-Day Rept, Per GL 95-05.Rept Is Submitted IAW License Condition 2.C.(9)(d) 05000327/LER-1998-004, Forwards LER 98-004-00,providing Details Concerning Inability to Complete Surveillance within Required Time Interval1998-12-21021 December 1998 Forwards LER 98-004-00,providing Details Concerning Inability to Complete Surveillance within Required Time Interval ML20198D5471998-12-14014 December 1998 Requests That License OP-20313-2 for Je Wright,Be Terminated IAW 10CFR50.74(a).Individual Retiring ML20197J5541998-12-10010 December 1998 Forwards Unit 1 Cycle 9 90-Day ISI Summary Rept IAW IWA-6220 & IWA-6230 of ASME Code,Section Xi.Request for Relief Will Be Submitted to NRC Timeframe to Support Second 10-year Insp Interval,Per 10CFR50.55a ML20196F9841998-11-25025 November 1998 Provides Changes to Calculated Peak Fuel Cladding Temp, Resulting from Recent Changes to Plant ECCS Evaluation Model ML20195H7891998-11-17017 November 1998 Requests NRC Review & Approval of Five ASME Code Relief Requests Identified in Snp Second ten-year ISI Interval for Units 1 & 2 ML20195E4991998-11-12012 November 1998 Forwards Rev 7 to Physical Security/Contingency Plan.Rev Adds Requirement That Security Personnel Will Assess Search Equipment Alarms & Add Definition of Major Maint.Rev Withheld (Ref 10CFR2.790(d)(1)) 05000328/LER-1998-002, Forwards LER 98-002-00 Re Automatic Turbine & Reactor Trip, Resulting from Failure of Sudden Pressure Relay on B Phase Main Transformer1998-11-10010 November 1998 Forwards LER 98-002-00 Re Automatic Turbine & Reactor Trip, Resulting from Failure of Sudden Pressure Relay on B Phase Main Transformer ML20195G5701998-11-10010 November 1998 Documents Util Basis for 981110 Telcon Request for Discretionary Enforcement for Plant TS 3.8.2.1,Action B,For 120-VAC Vital Instrument Power Board 1-IV.Licensee Determined That Inverter Failed Due to Component Failure ML20155J4031998-11-0505 November 1998 Provides Clarification of Topical Rept Associated with Insertion of Limited Number of Lead Test Assemblies Beginning with Unit 2 Operating Cycle 10 Core ML20154R9581998-10-21021 October 1998 Requests Approval of Encl Request for Relief ISI-3 from ASME Code Requirements Re Integrally Welded Attachments of Supports & Restraints for AFW Piping ML20155B1481998-10-21021 October 1998 Informs That as Result of Discussion of Issues Re Recent Events in Ice Condenser Industry,Ice Condenser Mini-Group (Icmg),Decided to Focus Efforts on Review & Potential Rev of Ice condenser-related TS in Order to Clarify Issues ML20154K1581998-10-13013 October 1998 Forwards Rept Re SG Tube Plugging Which Occurred During Unit 1 Cycle 9 Refueling Outage,Per TS 4.4.5.5.a.ISI of Unit 1 SG Was Completed on 980930 ML20154H6191998-10-0808 October 1998 Forwards Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 COLR, IAW TS 6.9.1.14.c 05000328/LER-1998-001, Forwards LER 98-001-00 Providing Details Re Automatic Turbine & Reactor Trip Due to Failure of Sudden Pressure Relay on B Phase Main Transformer1998-09-28028 September 1998 Forwards LER 98-001-00 Providing Details Re Automatic Turbine & Reactor Trip Due to Failure of Sudden Pressure Relay on B Phase Main Transformer 1999-09-27
[Table view] Category:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC
MONTHYEARML20245B3981989-05-0808 May 1989 Discusses Technical & Safety Concerns Re Flow & Pressure Drop Calculations for RWCU & Feedwater & Condensate Sample Panels at Plant ML20245B4081989-03-10010 March 1989 Requests Response to 881014 & 890119 & 23 Ltrs Re Technical & Safety Concerns at Plant ML20245B4091989-01-23023 January 1989 Refers to Re Corrosion Inhibitors in Closed Water Sys at Plant.Last Sentence on First Page of Ltr Should Be Changed to Read One Example Is Loss of Air Cooling to Shutdown Board Rooms at Sequoyah ML20245B4101989-01-19019 January 1989 Requests That Jg Partlow Pursue Completion of Engineering Assignment of ED Buggs at Plant Concerning Corrosion Inhibitors for Closed Water Sys.Draft Engineering Rept Recommending Corrosion Inhibitors for Closed Water Sys Encl ML20245B4121988-10-14014 October 1988 Informs of Several Technical Concerns Expressed While at Util & Requests That Jg Partlow Pursue Resolution of Listed Concerns ML20151P0021988-05-18018 May 1988 Requests Consideration of Listed Points Re Proceeding Under 10CFR2.206 Instituted by NRC Per for Relief in Matter of Facility ML20237L7171987-08-21021 August 1987 Forwards Comments on Plant Revised Cable Test Program. Industry Experience Adequate to Refute TVA Claims.Nrc Agreement W/Test Program Would Establish Lower than Necessary Stds as Precedents for Industry ML20238B2421987-08-13013 August 1987 FOIA Request for Final Summary Rept of Investigation by NRC Ofc of Inspector & Auditor of Allegations Re Facility & Related Witness Statements & Documentation ML20147G7821987-04-0808 April 1987 Submits List of Questions Which Should Be Addressed Prior to & After Restart of Plant ML20207T2381987-02-18018 February 1987 FOIA Request for Rept on Odds of Large Radioactive Release at Us Commercial Nuclear Reactors,Including Surry,Peach Bottom,Sequoyah,Grand Gulf & Zion ML20211A0111986-08-22022 August 1986 FOIA Request for Records on Browns Ferry & Sequoyah, Including Current Timetable for Correcting Technical & Engineering Problems & Expected Annual Costs for Capital Improvements ML20197C4281986-08-22022 August 1986 FOIA Request for Eight Categories of Documents,Including Current Timetable for Correcting Technical & Engineering Problems & Expected Annual Costs for Operating & Maint of Facilities ML20126E5691985-01-28028 January 1985 FOIA Request for Source Term Event Trees Prepared by Sandia for Subj Plants ML20117J4101984-11-19019 November 1984 FOIA Request for Science Applications,Inc SAI-01382-147LJ, Preliminary Assessment of Core Melt Probability in Cold Shutdown Following Postulated LOCA at Sequoyah Nuclear Plant Be Placed in PDR ML20105B9581984-07-11011 July 1984 FOIA Request for Five Categories of Documents Re Proposed Hydrogen Control Rule & Proposed Glow Plug Igniter Concept for Sequoyah ML20102A3531984-07-11011 July 1984 FOIA Request for W Butler 810407 Memo Re H2 Combustion, Evaluation of Glow Plug Igniter Concept for Use in Sequoyah Nuclear Plant, & M Berman 830524 Memo Re Mod of Nuclear Reactor Containment Atmosphere ML20028D9551982-11-10010 November 1982 FOIA Request for Ten Categories of Documents ML20063D5681982-07-0202 July 1982 FOIA Request for Five Documents Re Sys Interaction in LWR, Inadvertent Containment Spray for Primary Sys Blowdown, Biweekly Rept for LER Screening Project & LER Analysis & Summary ML20002B6431980-12-0505 December 1980 Requests Notification of Final Order Re Intervenor 801016 Exceptions to NRC 801008 Initial Decision Denying Petition to Revoke OL ML20008E8491980-10-16016 October 1980 Forwards Petition for Review of Directors Decision Under 10CFR2.206 Denying Revocation of Ol.License Conditions Imposed on Facility Are Inadequate.Supporting Info Encl ML19280A6161980-09-0808 September 1980 Commends Commissioners for Denying Facility full-power License Until Hydrogen Buildup Issue Has Been Resolved Beyond Any Doubt.No Compromise Too Expensive for Prevention of Another near-devastating Event Such as TMI ML19338F5941980-09-0202 September 1980 Submits Comments on Class 9 Subcommittee 800828 Meeting Re Hydrogen Problem.Convenience Should Not Be Only Criteria for Igniter Location ML19320B1371980-07-0101 July 1980 Requests That 800624 Fr Notice Be Reissued to Correct Implication That Farm (Tnrc) Owns Facility & Allegation That Plant Is Unable to Withstand Hydrogen Burn Pressure ML19309B0181980-02-29029 February 1980 Opposes Recent Licensing of Plant.Urges NRC to Reverse Decision & Resume Moratorium of Licensing Until Kemeny Commission Recommendations Have Been Implemented ML19275B8601980-02-20020 February 1980 Requests Per 10CFR2.206,public Hearing in Knoxville,Tn Prior to Granting of License to Fuel Facility ML19290D7611980-02-15015 February 1980 Favors Delay in Issuance of Ol,Since Nc Area Surrounded by Nuclear Plants.Newspaper Articles Encl ML19296C7711980-02-14014 February 1980 Supports Chattanoogans for Safe Energy Petition for Public Hearing in Chattanooga,Tn Before NRC Permits Fuel Loading at Plant ML20126C4901980-02-14014 February 1980 Speaks Strongly Against Opening Plant So Close to Largely Populated Area.Nrc Should Be Financially Responsible & Liable Should Accident Occur ML19284A8311980-01-25025 January 1980 Discusses Fueling & Low Power Testing Prior to Issuance of Ol.Requests Public Meeting in Chattanooga,Tn Before Further NRC Action Re TVA Request ML19294B4001980-01-25025 January 1980 Expresses Concern Re NRC Jurisdiction Over TVA as Another Federal Agency.Requests Public Hearing Before Util Allowed to Proceed W/Low Power Testing ML20148C1821980-01-21021 January 1980 Forwards Ja Desrosiers Reported Lost by Nrc. Submits List of Addl Incidents Supporting OL Denial. Reiterates Request for Public Hearing Near Chattanooga,Tn Before OL Issuance ML20148C1911979-12-18018 December 1979 Requests That Public Hearing Be Held Near Chattanooga,Tn Before Issuance of Ol.Urges Denial of Util Request for low- Power License.Submits List of Facility Design Deficiencies ML19329D3261971-03-15015 March 1971 Confirms 710208 Decision Withdrawing as Intervenor & Witness in Midland & Shoreham Hearings.Certificate of Svc Encl 1989-05-08
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6621 Wachese Lane
. Knoxville, Tennnessee 37912 August 21, 1987 iir. James Keppler, Director Office of Special Projects U. S. Nuclear Regulatory Commission i
i East West Towers West W ashington, D. C. 20555 Lear Mr. Keppler:
Reference:
Letter from R. Gridley to NRC, "SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 - REVISED TEST PROGRAM,"
dated July 31, 1987.
Per requests from you and Mr. B. D. Liaw, I am providing the enclosed comments on the referenced test program.
I do not believe the NRC should accept.the program as submitted.
There is adequate industry experience to refute a number of TVA's' claims.
To agree with TVA's test program, the NRC would be establishing lower than necessary standards as precedents for the industry.
Sincerely, kall v k.00 Dallas R. Hicks Enclosure cc:
(1) Dr. Henry Myers Committee on Interior and Insular Affairs (2) Mr. Peter Stockton Subcommittee on Oversight and Investigations Committee on Energy and Commerce 1
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i COMMENTS ON TVA'S PROPOSED CABLE TEST PROGRAM, DATED JULY 31, 1987
REFERENCES:
- 1. NRC Letter, B. J. Youngblood to S. A. White, " Evaluation of Sequoyah Units 1 and 2 Cable pulling and Bend Radii Concerns,"
dated March 9, 1987, and the enclosed Technical Evaluation Report (TER) by Franklin Research Center, dated February 19, 1987.
- 2. Meeting between NRC and TVA in Bethesda concerning cable j
testing on July 13, 1987, and the resulting transcript.
- 3. TVA letter, R. Gridley to NRC, "SEQUOYAH NUCLEAR PLANT (SQN)
UNITS 1 AND 2 - REVISED TEST PROGRAM," dated July 31, 1987.
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1 COMMENTS ON REFERENCE 3 ARE AS FOLLOWS:
- 1. In the second paragraph of page 2 of the letter, TVA stated:
"In particular, it was apparent that the test voltages utilized were higher than necessary to verify the integrity of the cable.
In addition, this testing, which was performed without the introduction of water, was able to detect damage that was insignificant when compared with the type of damage postulated in the technical evaluation report (TER) for pullbys and jamming.
Previously, it had been inferred that only in the presence of water."y de high potential testing such damage could be detected b I do not agree that the test voltages were higher than necessary i
to verify the integrity of the cable.
It just happens that the insulation was already degraded to a level such that lower level of voltages could have possibly detected the damage.
TVA's statements concerning the voltage level and the lack of use of water are misleading and are apparent attempts to justify a position not to use sufficiently high voltages and water immersion of cables as has been recognized as a need for qualification and required by the industry.
The fact that a cable insulation fails at a lower voltage and without water is absolutely no reason or justification to lower the voltage and to eliminate water immersion.
Other cable insulations may be unacceptable in integrity of insulation capability but at higher integrity than that of the subject failed cables.
They would be detected by the conditions of higher voltage and water immersion.
- 2. In the third paragraph of page 2 of the letter, TVA stated:
"As a result of the above, TVA concluded that continued testing, conducted at the original parameters, could potentially impact plant safety and, furthermore, could result
COMMENTS ON TVA'S PROPOSED CABLE TEST PROGRAM Page 2 in the replacement of acceptable cable with no increase in plant safety."
This statement is erroneous and misleading.
Cables in the 600 volt class that are in good condition should withstand 20,000 volts or higher.
This is recognized by the industry and is included in IEEE Standards 141 and 241, both being recommended practice manuals produced by IEEE.
TVA tried to make a case in the July 13, 1987, meeting in Bethesda that degradation of cable insulation after manufacture may occur in shipping, handling, and in the instal}ation process, as well as in aging.
While this is true, the degradation should not be so great that slightl that half (10,800 volts) the above level (20,000+ volts) y more could not be withstood.
It is well understood that the TVA process for handling and installing cabling was extremely deficient in many l
areas such as follows:
receipt and inspection, storage, handling, installation, testing, and quality assurance.
Engineering was deficient and there was a general lack of engineering oversight for the installation, check-out, and handling and storage of cabling.
One could write extensively about the abuses and mishandling of cabling at TVA.
For brevity, one can conclude that the process was flawed in virtually every area and any subsequent claims by TVA to the contrary are misleading.
]
- 3. In the last paragraph of the letter, TVA stated:
"In addition to the program described herein, a cable test program will be established that will be consistent with Inspection and Enforcement (IE) Notice 86-49.
The program will also address low-voltage cables.
The purpose will be to demonstrate margins above the system design basis.
This program will be described to NRC within six months after restart of SQN unit 2 and will be implemented by the end of the SQN unit 2 cycle 4 refueling outage."
IE Notice 86-49 does not state much and does not define specific requirements.
Its intended compliance by TVA means little to the resolution of the cable problems, even though TVA has made a big deal here and in the July 13 meeting that they will comply with I
this notice.
There is a major problem included in TVA's assumptions for getting NRC's approval of a promise to develop a test program in the future.
The NRC should not be approving a program that is not yet developed by TVA.
Restart should not be allowed on such a basis.
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- 4. TVA's statements in Item 1 of Enclosure 1 to the letter are misleading and do not show conservatism.
One cannot make a case for conservatism on an isolated item when the overall process was flawed as discussed in Item 2 above.
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COMMENTS ON TVA'S PROPOSED CABLE TEST PROGRAM Page 3
- 5. In Item 2 of Enclosure 1 to the letter, TVA stated:
"Recent interviews of electricians who had actually performed the cable installation at Sequoyah, conducted by the NRC/ Consultants, indicated a thorough understanding of the cable installation process and the relevant concerns.
These interviews substantiated conformance to proper construction practices used throughout the industry and utilization of the engineering approved installation procedures and specification and confirmed the presence of a Quality Control Inspector on all Class 1E cable pulls.
In addition, the close working relationship between construction and engineering was outlined including the evaluation made before each Class 1E pull to determine the best method of installation, which included determining the direction of the pull and the need for manual assistance at pull points to reduce tensions.
The testimony in these interviews was contrar to Watts Bar Nuclear Plant employee concerns in this area.y' These statements raise more questions.
It is recommended that the NRC obtain the documentation on these interviews and investigate the degree of accuracy therein.
Considering the overwhelming problems resulting from poor practices discussed in Item 2 above, one can only conclude that the above statements are misleading.
People can have a thorough understanding during or after the fact of performing tasks, but still do sloppy and unacceptable work.
The measure of acceptability is the end product, and in this case, it is unacceptable.
- 6. In Item 3 of the Enclosure to the letter, TVA begins to state their proposed position to use a test voltage based on " specific minimum environmentally qualified insulation thickness for the vcitage rating and insulation type and manufacturer."
This position is weak and it does nothing to support TVA's seeking to establish an adequate margin.
In fact, when one uses the minimum of anything, there is no existence of margin.
This position does not provide confidence that adequate margins will exist and it is not one that should be the foundation for setting an industry precedent.
Further, the NRC staff assumes, from TVA's claims, that " minimum environmentally qualified voltage" is acceptable because it was the basis for Sequoyah's Operating License.
I disagree, and I further challenge the NRC and TVA to prove this.
- 7. In Item 3 of Enclosure 1 to the letter, TVA stated:
"As such, use of the f actory test voltage at this stage in the I
life of SQN cables may damage cables that are otherwise acceptable and inhibit a root cause determination of any test failures."
This position has no basis.
It entirely misses the reason for testing.
Known damage exists at TVA and has been verified by testing, and the very reason for testing is to find the extent of problems and replace the defective cabling, thus obtaining a high
COMMENTS ON TVA'S PROPOSED CABLE TEST PROGRAM Page 4 confidence level for the quality of installed cabling and its ability to permit the plant to operate and shutdown safely.
Any cabling that cannot meet the tests should not be left in the plant, but should be replaced.
- 8. In Enclosure 1 of the letter and during the meeting specified in Reference 2, TVA and its consultants quoted a number of IEEE standards.
Although a senior member of IEEE and several of its societies, I do not believe that all of these standards are sufficient by themselves; for example, they inadequately address 600 volt cabling.
Referencing these standards and stating an intent in meeting them means little and does not solve the problems at Sequoyah.
The NRC should carefully review the IEEE l
and ICEA standards for cabling and should note the voltages in j
ICEA S-68-516, Revision 7, Table 3-1 (IPCEA S-68-516, Enclosed).
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- 9. In Enclosure 2 of the letter, TVA refers to the use of PVC cable insulation.
Why has the NRC not required TVA to replace the PVC at SQN, especially ir view of the disastrous l
results from the Browns Ferry fire and all of the subsequent PVC restrictions?
How can the NRC continue ~to allow plants to contain PVC without having replacement programs and schedules in place to replace all PVC eventually?
- 10. In Enclosure 2 of the letter, TVA explains its cable selection / sampling criteria.
More time has been spent on this than would have been taken to test all of the cabling that is subject to damage.
- 11. In Enclosure 2 of the letter and in the meeting specified in Reference 2, TVA tries to make a case for not testing all cables i
in water.
This is contrary to commitments described to me by Mr.
Raughley and Dr. Fox in a meeting in Knoxville on June 23, 1987.
TVA now states that they will wet the cables on a case-by-case basis, but "It is not intended or expected that the cables will remain submersed throughout the test."
To wet cables without keeping them immersed makes no sense and will have no intended immersion effect.
Either TVA tests the cables wet (immersed) or dry.
There is no middle ground that could be remotely justified on this issue.
Yes, it was a ridiculous suggestion to wet test cables in all areas, but this latter proposal is even more ridiculous.
The NRC should require wet immersion testing to the degree necessary to resolve the concerns and disallow the TVA approach.
One solution would be to remove section(s) of cabling and conduit (all intact after having been cut on both ends).
Then take it outside the plant, seal one end, fill with water, and high-pot test it.
Compare this with the results of dry testing.
- 12. In Item 2 at the bottom of p ge 3 of Enclosure 2 of the letter, TVA states:
"If the cables fail the high-voltage test, the NRC will be notified promptly."
COMMENTS ON TVA'S PROPOSED CABLE TEST PROGRAM Page 5 The NRC should witness all tests to assure that testing is done i
I in accord with TVA's commitment.
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- 13. In Enclosure 2 of the letter, TVA provides cable acceptance criteria and what TVA will do if they have failures.
The NRC must reject this plan.
If failures occur, no options should be f
given.
All items must be tested prior to restart and all failed j
items must be replaced.
TVA's sampling is unacceptable and must be disallowed by the NRC.
)
The referenced sampling basis, hypergeometric likelihood density function method, as well as any number of other statistical sampling bases, is not applicable to the subject at hand.
Sampling theory, including the referenced one, assumes that a controlled activity is occurring such as manufacturing of like items on an assembly line.
Cable installation by different crews, in different configurations of conduit arrangements and sizes, with different mixes and sizes of cables, and with different plant environments does not allow classification in the same category as an assembly line type of operation.
For this reason, small samples cannot be used to make conclusions about large populations of cabling.
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- 14. In Enclosure 3 of the letter, TVA references construction specification G-38, which has been deficient from the beginning.
Further, too much detail is spent on selection of conduits rather than in testing all of them.
Also, TVA states that cable selection criteria will be documented in a calculation.
When will it be done?
It would not have to be done if TVA would eliminate the sampling philosophy.
- 15. TVA has stated that IEEE 383-1974 was not the code of record with the implication that it did not have to f ollow it then or now.
This is ridiculous for a plant that had such a long construction time with delay after delay, operating for a while, now shutdown for serious problems, and not wanting to agree that j
IEEE 383-1974 is required to solve problems.
Who is kidding whom?
It would be irresponsible for the NRC to allow TVA to proceed on less than IEEE 383-1974.
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- 1. Reference 1 included a welcome review of the TVA cabling situation.
The meeting specified in Reference 2 set the right tone from the NRC viewpoint and served to put TVA on notice that TVA was not resolving serious concerns.
The NRC and Franklin Research Center are to be commended for both.
- 2. During a meeting with me on June 23, 1987, TVA personnel highlighted their cable testing program in an apparent effort to resolve questions I had raised.
Less than three weeks later, during the meeting specified in Reference 2, TVA told the NRC a very different story concerning their cable testing plans.
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COMMENTS ON TVA'S PROPOSED CABLE TEST PROGRAM Page 6 s
- 3. The NRC must witness all testing for some of the reasons given in Item 2 above.
- 4. The sampling mentality at TVA is unacceptable.
I believe that all cables in conduit must be tested and the failed items must be replaced prior to restart.
- 5. The NRC must insist on a periodic testing plan, with an acceptably short period of time between testing, for continuing the testing of all plant cables in conduits throughout the plant life.
This will assure that degraded cabling will be found and replaced.
- 6. The original test voltages used by TVA (in testing in which failures occurred) are not excessive and will not cause damage to 3
cabling that is in acceptable condition.
If cabling fails at J
that level, 240 volts / mil of insulation thickness (not minimum environmental qualification insulation thickness), then it should be replaced.
- 7. Water immersion testing must be included as part of the testing as described herein.
TVA's plan on this is unacceptable.
- 8. The pla ' cabling inventory should be checked for its qualified 11fe.
All cabling that is late in its qualified life should be replaced without testing.
- 9. In the meeting specified in Reference 2, and elsewhere, TVA tried to equate what they are doing with normal acceptance require testing and they referenced IEEE standards that only(600 volt) megger testing at 500 or 1000 volts for low voltage cabling.
They also tried to make a case for service condition versus rating.
The fact that all IEEE standards do not include adequate information for testing for known problems does not allow one to conclude that high potential testing is inappropriate for 600 volt insulation.
This is an area where TVA is misrepresenting the real reason for the need for high potential cable testing.
- 10. TVA's and its consultants' not being aware of any 240 volt per mil testing, as stated in the transcript of the July 13 meeting, raises questions as to the quality of the TVA consultants' advice.
This level of testing for 600 volt cabling has been used as a means of finding problems and replacing bad cabling.
The NRC should poll the nuclear utilities and possibly other industrial companies to see how they maintain confidence in their cable insulation levels through testing and at what levels and frequency of testing.
The NRC should also ask if any of them have any work in progress to update their current practices.
Certainly, the questionnaire should include the TVA type situation in which cable degradation is known or highly suspected and the utility or industrial would be trying to find the extent of degraded insulation.
i COMMENTS ON TVA'S PROPOSED CABLE TEST PROGRAM Page 7 11.
The TVA NSRS Report I-85-06-WBN, " Investigation of an Employee Concern Regarding Cable Routing, Installation, and Inspection at Watts Bar Nuclear Plant," by Mr. Mansour Guity, dated July 8, 1985, and the Technical Evaluation Report (Reference 1) by Franklin Research Center are in concert with my knowledge of the TVA cable situation.
Both of these provide substantial information to dispute TVA's claims of conservatism and good practices having been followed in cabling installation at TVA.
SUMMARY
The issue of cable testing is more far-reaching than the Sequoyah plant.
The NRC decision on this issue and the methodology to be used will be referenced as a major precedent.
Therefore, the relaxation or softening of requirements for immediate needs of economics and schedule of restart for Sequoyah should be overridden by the bigger issue of setting a precedent and the establishment of an NRC position.
The NRC staff has indicated that the NRC must be fair with TVA.
The NRC can be fair and tough as a regulator, but fairness and economics must follow safety which should have the highest priority.
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