|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M8851999-10-0808 October 1999 Informs of Staff Determination That Listed Calculations Should Be Withheld from Public Disclosure,Per 10CFR2.790, as Requested in 990909 Affidavit ML20211J7731999-08-31031 August 1999 Forwards Insp Rept 50-312/99-03 on 990802-06.No Violations Noted.Insp Included Decommissioning & Dismantlement Activities,Verification of Compliance with Selected TS & Review of Completed SEs ML20211H7481999-08-13013 August 1999 Forwards Amend 126 to License DPR-54 & Safety Evaluation. Amend Changes Permanently Defueled Technical Specification (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP Level Alarm Switches with Generic Ref 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments ML20195B8511999-05-27027 May 1999 Forwards Change 4 to Rancho Seco Emergency Plan, Incorporating Commitments Made to NRC as Outlined in NRC .Emergency Plan Includes Two Listed Supporting Documents ML20207E9181999-05-27027 May 1999 Informs That Effective 990328,NRR Underwent Reorganization. within Framework of Reorganization,Div of Licensing Project Mgt Created.Reorganization Chart Encl ML20206U7411999-05-18018 May 1999 Provides Summary of 990217-18 Visit to Rancho Seco Facility to Become Familar with Facility,Including Onsite ISFSI & Meeting with Representatives of Smud to Discuss Issues Re Revised Rancho Seco Ep,Submitted to NRC on 960429 ML20206M1611999-05-10010 May 1999 Forwards Listed Proprietary Calculations to Support Review of Rancho Seco ISFSI Sar.Proprietary Encls Withheld ML20206E8591999-04-12012 April 1999 Provides Info Re High Total Coliform Result in Plant Domestic Sewage Effluent Prior to Confluence with Combined Effluent.Cause of High Total Coliform Result Was Broken Flow Rate Instrument.Instrument Was Repaired on 990318 ML20204H6751999-03-19019 March 1999 Forwards Insp Rept 50-312/99-02 on 990309-11.No Violations Noted.Portions of Physical Security & Access Authorization Programs Were Inspected ML20204E4031999-03-16016 March 1999 Submits Rept of Status of Decommissioning Funding for Rancho Seco,As Required by 10CFR50.75(f)(1).Plant Is Currently in Safstor, with Operating License Scheduled to Expire in Oct 2008 ML20204E6661999-03-11011 March 1999 Forwards Rancho Seco Exposure Rept for Individuals That Received Greater than 100 Mrem During 1998,IAW TS D6.9.2.2 & NRC Regulatory Guide 1.16 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 ML20207L1711999-03-10010 March 1999 Informs of Staff Determination That Supporting Calculations & Drawings Contained in Rev 2 of Sar, Should Be Withheld from Public Disclosure,Per 10CFR2.790 NL-99-002, Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3)1999-03-10010 March 1999 Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20207D4431999-03-0101 March 1999 Forwards Annual Radioactive Effluent Release Rept, for Rancho Seco Nuclear Generating Station for 1998 ML20207H6181999-02-18018 February 1999 Provides Attached Metrix & Two Copies of Rancho Seco ISFSI Sar,Rev 2 on Compact Disc,As Requested in 990209 Meeting. First Rounds of RAIs Dealt Primarily with Use of Cask as Storage Cask.Without Compact Disc ML20203D0761999-02-10010 February 1999 Ltr Contract:Task Order 37 Entitled, Technical Assistance in Review of New Safety Analysis Rept for Rancho Seco Spent Fuel Storage Facility, Under Contract NRC-02-95-003 ML20155D4431998-10-27027 October 1998 Forwards Amend 3 to Rancho Seco Dsar,Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode.With Instructions & List of Effective Pages NL-98-032, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1998-09-30030 September 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20237A6031998-08-0707 August 1998 Forwards Insp Rept 50-312/98-03 on 980706-09.No Violations Noted ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements ML20236Q9461998-07-15015 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-02 ML20236J6331998-06-30030 June 1998 Forwards Response to Violations Noted in Insp Rept 50-312/98-02.Corrective Actions:Util Revised RSAP-1003 to Clarify District Security Staff Responsibilities Re Handling & Review of Criminal History Info ML20236E8211998-06-0303 June 1998 Forwards Insp Rept 50-312/98-02 on 980519-21 & NOV Re Failure to Review & Consider All Info Obtained During Background Investigation.Areas Examined During Insp Also Included Portions of Physical Security Program ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 IR 05000312/19980011998-03-25025 March 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-01 on 980205 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) ML20202C4641998-02-0505 February 1998 Forwards Insp Rept 50-312/98-01 on 980105-08 & Notice of Violation.Insp Included Decommissioning & Dismantlement Work Underway,Verification of Compliance W/Selected TS & Main & Surveillance Activities Associated W/Sfp ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks ML20198K5391997-10-21021 October 1997 Forwards Insp Rept 50-312/97-04 on 970922-25 & Notice of Violation.Response Required & Will Be Used to Determine If Further Action Will Be Necessary ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility ML20198G8141997-08-22022 August 1997 Forwards Amend 125 to License DPR-54 & Safety Evaluation. Amend Permits Smud to Change TS to Incorporate Revised 10CFR20.Amend Also Revises References from NRC Region V to NRC Region IV ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 ML20149E5031997-07-10010 July 1997 Second Partial Response to FOIA Request for Documents. Forwards Records Listed in App C Being Made Available in Pdr.Records in App D Already Available in PDR ML20148P5161997-06-30030 June 1997 Second Partial Response to FOIA Request for Documents.App B Records Being Made Available in PDR ML20141A1721997-06-17017 June 1997 Forwards Insp Rept 50-312/97-03 on 970603-05.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program 1999-08-31
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195B8511999-05-27027 May 1999 Forwards Change 4 to Rancho Seco Emergency Plan, Incorporating Commitments Made to NRC as Outlined in NRC .Emergency Plan Includes Two Listed Supporting Documents ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments ML20206M1611999-05-10010 May 1999 Forwards Listed Proprietary Calculations to Support Review of Rancho Seco ISFSI Sar.Proprietary Encls Withheld ML20206E8591999-04-12012 April 1999 Provides Info Re High Total Coliform Result in Plant Domestic Sewage Effluent Prior to Confluence with Combined Effluent.Cause of High Total Coliform Result Was Broken Flow Rate Instrument.Instrument Was Repaired on 990318 ML20204E4031999-03-16016 March 1999 Submits Rept of Status of Decommissioning Funding for Rancho Seco,As Required by 10CFR50.75(f)(1).Plant Is Currently in Safstor, with Operating License Scheduled to Expire in Oct 2008 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 ML20204E6661999-03-11011 March 1999 Forwards Rancho Seco Exposure Rept for Individuals That Received Greater than 100 Mrem During 1998,IAW TS D6.9.2.2 & NRC Regulatory Guide 1.16 NL-99-002, Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3)1999-03-10010 March 1999 Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20207D4431999-03-0101 March 1999 Forwards Annual Radioactive Effluent Release Rept, for Rancho Seco Nuclear Generating Station for 1998 ML20207H6181999-02-18018 February 1999 Provides Attached Metrix & Two Copies of Rancho Seco ISFSI Sar,Rev 2 on Compact Disc,As Requested in 990209 Meeting. First Rounds of RAIs Dealt Primarily with Use of Cask as Storage Cask.Without Compact Disc ML20155D4431998-10-27027 October 1998 Forwards Amend 3 to Rancho Seco Dsar,Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode.With Instructions & List of Effective Pages NL-98-032, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1998-09-30030 September 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements ML20236J6331998-06-30030 June 1998 Forwards Response to Violations Noted in Insp Rept 50-312/98-02.Corrective Actions:Util Revised RSAP-1003 to Clarify District Security Staff Responsibilities Re Handling & Review of Criminal History Info ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 NL-97-030, Forwards Endorsement 132 to Nelia Policy NF-0212 & Endorsement 118 to Maelu Policy MF-0075 for Smuds Rsngs1997-05-13013 May 1997 Forwards Endorsement 132 to Nelia Policy NF-0212 & Endorsement 118 to Maelu Policy MF-0075 for Smuds Rsngs ML20138F5321997-04-28028 April 1997 Forwards Response to RAI Re License Amend 192,updating Cask Drop Design Basis Analysis,Per NRC 960510 Request for Addl Info on 960318 Application NL-97-027, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility1997-04-17017 April 1997 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility ML20137W8091997-03-20020 March 1997 Forwards Biennial Update to Rancho Seco Post-Shutdown Decommissioning Activities Rept ML20137S3571997-03-19019 March 1997 Provides Notification of Use of Revised Quality Manual for Activities Re Rancho Seco ISFSI ML20137D0981997-03-18018 March 1997 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1996.Provided IAW TS D6.9.2.2 & Guidance Contained in NRC Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1996 ML20137D1221997-03-18018 March 1997 Submits,Iaw 10CFR20.2206 & TS D6.9.2.1,1996 NRC Form 5 Individual Monitoring Repts for Personnel Requiring Radiation Exposure Monitoring Per 10CFR20.1502 During 1996. W/O Encl NL-97-012, Submits Rept of Listed Current Levels of Property Insurance for Plant,Iaw 10CFR50.54(w)(3)1997-02-11011 February 1997 Submits Rept of Listed Current Levels of Property Insurance for Plant,Iaw 10CFR50.54(w)(3) ML20138L1091997-01-29029 January 1997 Informs of Schedule Change Re Decommissioning of Rancho Seco.Incremental Decommissioning Action Plan,Encl NL-97-005, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility1997-01-22022 January 1997 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility NL-96-056, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1996-12-16016 December 1996 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20134E0041996-10-23023 October 1996 Forwards Response to NRC GL 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks ML18102B6871996-08-0606 August 1996 Informs That Util Will Revise Loading & Unloading Procedures & Operator Training as Necessary ML20149E4491994-05-16016 May 1994 Forwards 1993 Annual Rept of Sacramento Municipal Utility District,For Info ML20149E3971994-05-10010 May 1994 Forwards Re Updated Decommissioning Cost Estimate for Rancho Seco & Attached Rept by Tlg Engineering,Inc. W/Svc List ML20059H6731994-01-20020 January 1994 Forwards Revised Rancho Seco Quality Manual, Reflecting Current Rancho Seco Pol Phase Nuclear Organization Changes ML20059E1221994-01-0303 January 1994 Forwards Amend 7 to Long Term Defueled Condition Physical Security Plan.Encl Withheld (Ref 10CFR73) ML20059C1681993-12-22022 December 1993 Forwards Suppl Info to Support Review & Approval of 930514 Proposed License Amend 186 Re Nuclear Organization Changes, Per NRC Request 1999-07-07
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L5431990-09-20020 September 1990 Requests Exemptions from Certain Requirements of 10CFR50.47(b) & 50,App E & Proposes New Emergency Plan That Specifically Applies to Long Term Defueled Condition ML20059J9161990-09-13013 September 1990 Notification of Change in Operator/Senior Operator Status for R Groehler,Effective 900907 ML20059J9221990-09-13013 September 1990 Responds to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2,Part 2, 'Vendor Interface for Safety-Related Components.' No Vendor Interface Exists for Spent Fuel Pool Liner NL-90-442, Forwards Endorsements 13 to Nelia Certificate N-49 & Maelu Certificate M-49,Endorsements 91 & 92 to Maelu Policy MF-75 & Endorsements 103 & 104 to Nelia Policy NF-2121990-09-12012 September 1990 Forwards Endorsements 13 to Nelia Certificate N-49 & Maelu Certificate M-49,Endorsements 91 & 92 to Maelu Policy MF-75 & Endorsements 103 & 104 to Nelia Policy NF-212 ML20059G0791990-09-0606 September 1990 Forwards Supplemental Fitness for Duty Performance Data, Omitted from 900725 Rept Re Random Drug Testing Results ML20059E0031990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept,Jan- June 1990, Corrected Repts & Revs to ODCM ML20059C2491990-08-27027 August 1990 Advises That M Foster & B Rausch Leaving Util Effective on 900810 & 17,respectively & Will No Longer Require Active Operator Licenses ML20056B2591990-08-20020 August 1990 Forwards Long-Term Defueled Condition Security Training & Qualification Plan. Encl Withheld (Ref 10CFR2.790) ML20056B2961990-08-10010 August 1990 Discusses 900731 Meeting Re Future of Util & Closure & Decommissioning of Facility.Request for Possession Only License Pending Before Commission ML20058Q2811990-08-0909 August 1990 Forwards Updated Listing of Commitments & long-range Scope List Items Deferred or Closed by Commitment Mgt Review Group Since Last Update ML20058N0911990-08-0707 August 1990 Notifies of Minor Change in List of Tech Specs Applicable in Plant Defueled Condition.Determined That Surveillance Requirements Table 4.1-1,Item 63 Not Required to Be Included in List of Tech Specs Applicable in Defueled Condition ML20056A1131990-07-30030 July 1990 Apprises of Status of Plans to Use 3 of 4 Emergency Diesel Generators as Peaking Power Supplies & Responds to Questions in .Util Obtained Authorization for Operation of Diesel Generators for No More than 90 Days Per Yr ML20056A2041990-07-30030 July 1990 Provides Response to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. Pressure & Differential Pressure Transmitters 1153 & 1154 Do Not Perform Any safety-related Function in Current Plant Mode ML20055J0311990-07-25025 July 1990 Forwards fitness-for-duty Performance Data for Facility from 900103-0630 ML20055J0331990-07-25025 July 1990 Notifies of Change in Operator/Senior Operator Status. Operators Terminating Employment & No Longer Require License ML20055H8081990-07-24024 July 1990 Forwards Decommissioning Financial Plan for Plant,Per 10CFR50.33(k)(2) & Requests Interim Exemption Re Requirement to Have Full Decommissioning Funding at Time of Termination of Operation,Per 10CFR50.12 ML20055H7561990-07-24024 July 1990 Requests Exemption from Performing Annual Exercise of Emergency Plan,Activation of Alert & Notification Sys & Distribution of Public Info Brochures,Per 10CFR50.12 Requirements ML20055F8421990-07-13013 July 1990 Forwards Application for Proposed Decommissioning of Plant. Util Needs Relief from Equipment Maint,Surveillance,Staffing & Other Requirements Not Necessary to Protect Public Health & Safety During Defueled Condition ML20055G9821990-07-12012 July 1990 Advises That Environ Exposure Controls Action Plan Will Be Provided by Sept 1990,per Insp Rept 50-312/90-02 ML20055E5111990-07-0606 July 1990 Notifies of Change in Operator/Senior Operator Status for D Rosenbaum & M Cooper,Effective 900622 & 29,respectively ML20055C3541990-02-14014 February 1990 Forwards Updated Response to Insp Rept 50-312/88-30. Calculations for Liquid Effluent Monitors Completed & in Use & Rev to Reg Guide 4.15 in Procedure RSAP-1702 Scheduled to Be Completed & Implemented by Apr 1990 ML20055C3511990-02-14014 February 1990 Forwards Addl Info Re 900306 Response to NRC Bulletin 88-003, Inadequate Latch Engagement in Hfa Type Latching Relays Mfg by Ge. Util Will Replace Only Relays Found Not to Meet Insp Criteria ML20248H2571989-10-0606 October 1989 Responds to NRC Re Addendum to Safety Evaluation Supporting Amend 92 to License DPR-54 Re Reactor Vessel Vent Valve Testing.No Testing of Reactor Vessel Vent Valves Will Be Performed ML20248H2391989-10-0606 October 1989 Requests Exemption from Requirements of 10CFR26 Re Fitness for Duty Programs Based on Present & Future Operational Configuration ML20248A8271989-09-25025 September 1989 Requests Permission to Submit Next Amend to Updated FSAR W/Decommissioning Plan Submittal.Extension Will Allow District to Incorporate Plant Closure Status in SAR Update to Reflect Plant Conditions Accurately ML20248D4611989-09-13013 September 1989 Responds to 890906 Request for Assessment of Util Compliance W/Ol & Associated Programs & Commitments,Per 10CFR50.54(f). Staffing Requirements for Emergency Preparedness Will Not Be Violated & Future Shortfalls Will Be Remedied ML20247G1991989-09-11011 September 1989 Requests Extension for Time Period Equivalent to That of Current Shutdown.Extension Would Result in Revised Final Expiration Date of Not Earlier than 900318.Plant Would Not Be Brought Above Cold Shutdown W/O NRC Prior Concurrence ML20247H3551989-09-0707 September 1989 Informs That Util Stands by Commitments of 890621 & 0829 Re Implementation of Closure Plan in Safe & Deliberate Manner in Compliance W/License & W/All Applicable Laws & Regulations ML20247H5541989-09-0101 September 1989 Responds to Violations Noted in Insp Rept 50-312/89-14. Corrective Actions:Stop Order on Fuel Movement Issued & Action Plan Generated on 890908 to Address Broader Issues 05000312/LER-1988-010, Forwards Rev 1 to LER 88-010,due to Change in Commitment Date for re-evaluating Fire Zones.Date Changed to 901001. Zones re-evaluated in Conjunction W/Mods to Fire Detection Annunciator Sys1989-08-23023 August 1989 Forwards Rev 1 to LER 88-010,due to Change in Commitment Date for re-evaluating Fire Zones.Date Changed to 901001. Zones re-evaluated in Conjunction W/Mods to Fire Detection Annunciator Sys ML20246A4011989-08-16016 August 1989 Forwards Rev 5 to Inservice Testing Program Plan. Changes Identified Consistent W/Guidance Provided by Generic Ltr 89-04 NL-89-593, Forwards Plant Closure Organizational Charts & Administrative Procedure RSAP-0101,per 890802 Request1989-08-15015 August 1989 Forwards Plant Closure Organizational Charts & Administrative Procedure RSAP-0101,per 890802 Request ML20245H4781989-08-10010 August 1989 Requests Exemption from Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs Because on 890607,util Board of Directors Ordered That Plant Cease Operation ML20245H1781989-08-0909 August 1989 Notifies of Change in Operator/Senior Operator Status. J Dailey & J Reynolds Terminated Employment on 890721 & 890802,respectively ML20245L1831989-08-0808 August 1989 Informs That Official Correspondence Must Be Directed to Listed Individuals Due to Reorganization of Util Following 890606 Election ML20247L9221989-07-26026 July 1989 Provides Revised Response to NRC Re Violations Noted in Insp Rept 50-312/88-33.Corrective Action:Portable Shield Walls Inspected Every 6 Months to Ensure All Safety Factors Met & Area Surveys Conducted on Weekly Basis ML20247M4121989-07-24024 July 1989 Requests Exemption from 10CFR50,App E,Section IV.F.2 to Allow Util Not to Perform Annual Emergency Plan Exercise for 1989.Request Results from Transitional Mode of Plant from Operating Plant to Plant Preparing for Decommissioning NL-89-541, Requests That Completion Date for Addl Training of Personnel Involved in Performing Work on Environ Qualified Equipment Be Extended from 890616 to 8912151989-07-14014 July 1989 Requests That Completion Date for Addl Training of Personnel Involved in Performing Work on Environ Qualified Equipment Be Extended from 890616 to 891215 ML20246P4011989-07-14014 July 1989 Informs That Evaluation of Contracts & Agreements Identified No Restrictions on Employee Ability to Provide Info About Potential Safety Issues to NRC NL-89-547, Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 1061989-07-0606 July 1989 Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 106 ML20246A9751989-06-30030 June 1989 Advises That Concerns Addressed in Generic Ltr 89-08 Inapplicable,Since Util Intends to Defuel Reactor.Generic Ltr Will Be Reviewed Prior to Placing Facility in heatup-cooldown Operational Mode for Return to Power ML20246A5171989-06-30030 June 1989 Forwards Rancho Seco Closure Plan, Per 890621 Request for Addl Info Re Plan CEO-89-289, Notifies of Change in Operator/Senior Operator Status.Listed Operator/Senior Operator Terminated Employment on Listed Effective Date1989-06-27027 June 1989 Notifies of Change in Operator/Senior Operator Status.Listed Operator/Senior Operator Terminated Employment on Listed Effective Date NL-89-526, Lists Discrepancies Noted in Amend 109 to License DPR-54,per 890615 Discussion W/S Reynolds.Tech Specs Encl1989-06-22022 June 1989 Lists Discrepancies Noted in Amend 109 to License DPR-54,per 890615 Discussion W/S Reynolds.Tech Specs Encl ML20245H4181989-06-21021 June 1989 Discusses Util Plans Re Overall Closure of Plant,Per 890615 Meeting W/Nrc.Util Will Request Appropriate Changes to Tech Specs to Reflect Defueled Mode & Will Evaluate & Request Changes to Emergency Plan ML20245D9281989-06-21021 June 1989 Discusses Activities Underway Re Plan for Closure of Plant Discussed During 890615 Meeting W/Region V.Util Intends to Continue Use of Essential Programs,Such as Preventive Maint Program,For Sys within Scope of Closure Process ML20245A0981989-06-16016 June 1989 Responds to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. No Westinghouse Plugs Used at Plant ML20248B5751989-06-0202 June 1989 Advises That Util Anticipates That Final Analysis of Thermal Striping Will Conservatively Support Surge Line Lifetime Significantly Longer than June 1994 Date,Per NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification NL-89-468, Submits Justification for Absence of Functional Testing Requirement in Proposed Tech Spec 4.14(f) Re Snubber Svc Life Monitoring,Per 890517 Request1989-05-30030 May 1989 Submits Justification for Absence of Functional Testing Requirement in Proposed Tech Spec 4.14(f) Re Snubber Svc Life Monitoring,Per 890517 Request ML20247N2601989-05-25025 May 1989 Requests Guidance Re Whether NRC Concurs W/Arbitrator Order Concerning Employee Access to Plant 1990-09-06
[Table view] |
Text
. ._ ._. - . _ _ _ _ _ - - _ _ _ .
F .
- f. , ,
MSMUD asce,ygg SACHAMENTO MUNICIPAL UTILITY DISTRICT O P. O. Box 15830, Sacramento CA 958521 ,(916) 452-3211 I
l AN ELECTRIC SYSTEM SERVING THEg fpF CALIFORNIA GCA 87-633 1981 OCT 21 A 11: 15 0CT 2 01987 U, S. Nuclear Regulatory Commission Attn: J. B. Martin, Regional Administrator
. Region V Office of Inspection and Enforcement 1450 Maria Lane, Suite 210 Halnut Creek, CA 94596 DOCKET NO. 50--312 RANCHO SECO NUCLEAR GENERATING STATION LICENSE NO. DPR-54 NRC INSPECTION 50-312/87-03, ULTRASONIC RESULTS OF THE PRESSURIZER SUPPORT LUGS
Dear Mr. Martin:
l By letter dated May 18, 1987, the Sacramento Municipal Utility District responded to a Notice of Violation concerning welds not positively identified on a system drawing. The District also responded to inspector's comments concerning the ISI Program, and committed to report findings and any corrective actions identified by the Babcock & Hilcox company review of ultrasonic results of the pressurizer support lugs. This Babcock & Hilcox report is attached.
Also, as a result of this inspection, the ISI engineer reviewed the UT test i report (ISI Figure C2.1.36 for weld 26121-33-BH). A 60* scan report was part l of the package and the required limited scan documentation was completed.
However, to ensure.that any other discrepancies in the UT test reports would not go undetected, the ISI engineer reviewed all UT test reports for the 1986 f outage. This included 36 Class 1 limited exam test reports and 32 Class 2 limited exam test reports. Of these 69 limited exams performed, three (3) inconsistencies were noted. These inconsistencies were mainly documentation errors. Specifically, the inconsistencies were:
a) Failure to identify whether the limited scan was applicable to the 0*
or 45' scan. (Fig. C2.1.13) .
i b) Checking that a limited scan was applicable for the 0*, 45*, and 60* j exam when only a 0* and 45' scan was performed. (Fig. C2.1.14) ;
f c) Checking no limited scan on the test data sheet but including limited scan documentation for the exam. (Fig. C2.1.85) 8711020475 871020 !
PDR ADOCK 05000312 G PDR I
RANCHO SECO NUCLEAR GENERATING STATION O 1444o Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935
, {, .
GCA 87-633 J.B. Hartin None of the inconsistencies-are of a technical nature. Corrections will be made in the final report which will be submitted 90 days following completion of all examinations. Several more examinations need to be performed, the final being the RCS Hydrostatic Test which will be performed during Start-Up.
Please contact me if you have any questions. Members of your staff with questions requiring additional information or clarification may contact Jack Uhl at (916) 452-3211, extension 4376.
Sincerely, l
/hhaday>an Gi Car Andognini Chief Executive Officer, Nuclear Attachment cc: G. Kalman, NRC, Bethesda (2) (w/atch)
A. D'Angelo, NRC, Rancho Seco ( " )
F. J. Miraglia, NRR, Bethesda ( "
)
-~ .
' " a t" * *- '
- l. - r-NucleN Power Division J He, .OCbCUCk & WIlCOX. - Spechi Products and Integrated Fiedd Services I# : a McDermott company 3110 Odd Fellows Road Lynchburg, VA 24501 =
(804) 847 3700
' June 12, 1987 M-87-205 l Mr.'J.- H. Uhl '
Rancho Seco Nuclear' Generating Station !
14440 Twin Cities Road Her~ald, CA 95638
Subject:
. Review of Ultrasonic Results of-the Pressurizer
' Support Lugs
Reference:
SMUD contract 6507 B&W Reference 702-0487
, 1
Dear'Mr. Uhl:
This letter is written in response to your request that B&W
' review an unresolved item (50-312/87-03-02) identified during a recent NRC audit of the SMUD ultrasonic inspectionLresults'for the 1983 and'1985 outages on the pressurizer support lugs. The details of the NRC: observations.are as follows. ;
Review,of' ultrasonic inspection results for the pressurizer' i support lugs (Report Numbers85-006, 85-007,85-010, and 1
'85-0014) revealed that additional indications'have been-detected since the 1983 outage. The inspection results
-show that-some of'the new' indications 1are close to previously reportedLindications suggesting possible dimensional changes. Fracture mechanics analyses have been performed by the site ISI contractor and the licensee has !
filed the reports. However, the reports do not address the i following concerns: j
- 1. Are these indications growing as reported and if they are, what is the rate of growth? !
)
- 2. If these new indications are fabrication welding indications not detected before, do they require 4 further evaluation to determine why these indications I were not detected before? !
This is an unresolved item pending licensee's action relating 1to the above concerns and NRC review (50-312/87-03-02).
t
_----_l- _ - . _ _ - -
.l, ,,b ,
. .a . .
L' " ej i c. "
- MR.'J.-H. URL
- PAGE TWO- ,p -
L-L
- l; During-the'1985 evaluation ofcthe 1985 examination data,.the L1983; data' wast reviewed to access changes?from the previous examination. The,following table provides a cross reference for ;
thel 1983'andl1985 evaluation reports.
- 1983 Report 1985 Report LUG' AXIS' 183-017.85-006 X-Y 183-029'85-007 Y-Z
.83-032 85-010- W-XE 83-018, 85-014: Y !
Attachments '1 =through 4 review the 1985 ' evaluations and .
addresses the NRC concerns as' indicated by Questions 1 and 2.
' above. Attachment S'provides information on the measured limits of location and sizing errors for ultrasonic. inspections. This-attachment is : supporting information regarding B&W conclusions addressed in Attachments 1 through 4'.-
. If you have any questions, please feel free to contact either myself (804)'847-3742, or Mike ac er (804) 847-3788.
. i q ery ruly rs,
~~
a u
i 1
y%)
ennis M. Turner Contracts & Proposals dmc i dmt-1710 I cc D Mixa JT Janis G Cranston i
Attachments - Evaluation Report 85-006/83-017 +
{
- ' Evaluation Report 85-007/83-029 ;
Evaluation Report 85-010/83-032 ;
Evaluation Report 85-014/83-018 '
Measured Limits of Location and Sizing Errors M'995~W gee W."
A__-E..____u_ ---_
}. :;l[ .
l ATTACHMENT 1 '
EVALUATION REPORTS 85-006/83-017 : -X-Y AXIS LUG 3
The 1983 - data ! reported a total of'28 indications on this' weld I L from' the 450' and 600' angle beam . examinations . During'the 1985 examination :a total of 29 indications' were reported. In l
comparison, . the' 1983s.and 1985 . data matched exactly 'with the l exception of' indication numbers 207,.417, and 418.
'Indic ation' : number 207 was not recorded. during the 1983 examination,, either because- it did not exceed the- recording criteria;of 50 percent DAC or it-may have been overlooked. The data recorded for ' indication number - 207 corresponds to .a reflector l(No. 420) recorded-in 1983 and 1985 and, therefore, it is not considered a new. target -
just- mo're data on an existing reflector. Indication number. 207 was recorded with a 450 , angle beam ~ and number 420 was recorded 'with a 600 angle beam. The recorded amplitude for indication number 207 is .80 percent of DAC. The length was measured at .60 inches and the throughwall )
dimension was .50 inches. The recorded dimensions for indication numbee 420 remained . the same for both the 1983 and 1985 l
. examinations. .
The.other changes reported in 1985 concerned indication numbers 417 and~418. The table shown below provides a comparison between the 1983 and.1985 data. ,
1983 Data 1985 Data Indication No. 417 Amplitude ~ 63% 80%
\' Length , .4" .2" .i Throughwall .15" .15" C
. Indication No. 418 Amplitude 70% 70% !
Length .25"- .55" Throughwall .25" .25" The magnitude .of the changes shown for indications 417 and 418 are within - the : limits of repeatability that can be reasonably ;
expected'using the Section XI examination procedures. The exact i reason that indication number 207 was not recorded in 1983 cannot
-be identified. However, based on the fact none of the other ;
indications- changed from 1983 to 1985, it is highly improbable l that the changes noted suggest any growth at all. It is more !
. probable that the minor changes in data are attributed to repeatability limitations which are inherent with the ultrasonic j examination process. Since there is no reported growth, the indication growth rate is considered to be zero. For the 3
l purposes of the 1985 evaluations, the impact of these reported '
. changes were conservatively evaluated as if they represented '
changes in the indication. sizes. As indicated in Evaluation Report 85-006, a worse-case evaluation determined that the
]
indications were bounded by the fracture analysis performed in i 1983.
1 i
l j
,i . b ATTACHMENT 2 EVALUATION REPORTS 85-007/83-029 : Y-Z AXIS LUG t The 1983 data reported a total of eight indications on this weld f rom ' the 450 and 600 angle beam examinations. During the 1985 examination, a total of nine indications were reported.
In comparison, the 1983 and 1985 data matched exactly with the exception of indication numbers 202 and 402.
' Indication number 202 was not recorded during the 1983 examination either because the amplitude response did not exceed the 50 percent DAC recording criteria or it may have been overlooked. The data recorded for indication number 202 corresponds to the combined indications 404 and 405 which were recorded during both the 1983 and 1985 o'utages. Indication 202 was recorded with a 450 angle beam and indications 404 and 405
- were recorded with a 600 angle beam. The maximum amplitude recorded
.65 for; indication 202 is 63 percent of DAC with a length of inches and a throughwall of .35 inches. The recorded dimensions the 1983 andfor 1985indications outages. 404 and 405 remained the same for both The other change reported involved indication number 402. A comparison of the 1983 and 1985 results is'as follows:
1983 Data 1985 Data Indication No. 402 gAmplitude 56% 56%
Length .2" .4" Throughwall .3" .3" i
As was the case for Evaluation Reports 85-006/83-017, the magnitude of the changes shown for indication 402 is within the limits of repeatability that can be reasonably expected using the Section XI examination procedures. It cannot be determined why indication 202 was not recorded in 1983. 'Each of the items mentioned above are possible explanations. However, based on the fact 1985, the,tit indications 404 and 405 did not change from 1983 to is unlikely that the addition of indication 202 represents or indicates any growth. As previously stated, the minor changes in data are attributed to repeatability limitations which are inherent with the ultrasonic examination process.
Since there is no reported growth, the indication growth rate is considered to be zero. For the purposes of the 1985 evaluations the impact of these reported changes were conservatively evaluated as if they represented changes in the indication sizes.
As indicated in Evaluation Report 85-007, a worse-case evaluation determined that the indications were bounded by the' fracture analysis performed in 1983.
i lr lhl .
ATTACHMENT 3 EVALUATION REPORTS 85-010/83-032 : W-X AXIS The 1983. data reported a total of seven indications on this weld from the 450 and 600 angle beam examinations. During the 1985 examination a total of eight indications were reported.
comparison, the 1983 and 1985 data matched exactly with the In '
exception of indications 402, 403, and 406.
Indication 406 was not recorded during the 1983 examination either because it did not exceed the 50 percent DAC recording criteria or it may,have been overlooked.
related to any other indication. recorded inThis 1983indication is not or 1985. This indication had an amplitude measurement of 63' percent DAC, just over the recording threshold. The length was recorded at .5 inches and the throughwall was measured at .4 inches. Although this was recorded as a new indication in 1985, it probably existed in 19,83 but was not recorded due to one of the reasons stated above. ,
Indications 402 and 403 did change from 1983 to 1985 according to the recorded data. The following table shows a comparison of that data. l 1983 Data 1985 Data '
Indication 402 Amplitude 70% 100%
Length
.4" .9" i Throughwall .4" .7" Indication 403 7
Amplitude 50% 63%
Length .15" .6" Throughwall 0 .6" As previously stated, the magnitude of the changes shown for 1 these indications is considered to be within the limits of repeatability that can be reasonably expected using the Section XI examination procedures. These indications are in the same general proximity as the rest of the indications (several larger than 402 and 403) which did not show any dimensional changes. If detectable growth were occurring, it is expected that the l i
remaining none.
indications would also have had some change - there was Since there is no reported growth, the idication growth rate is considered .to be zero. For the purposes of the 1985 evaluations, the impact of these reported changes were conservatively evaluated as if they represented changes in the l indication sizes. As indicated in Evaluation i Report 85-010, a i worse-case evaluation determined that the
)
indications were bounded by the fracture analysis performed in 1983. i I
1 1
m- ;
,e . - 1 ATTACHMENT 4 EVALUATION REPORTS 85-014/83-018 : Y AXIS .
The 1983 data reported . a total of 42 indications on this weld from the 450 and 600 angle beam examinations. During the 1985 i examination a total of 43 indications were reported.; In '
comparison, the 1983 and 1985 data matched exactly with the exception of indications 217 and 409.
j Indication 217 was not recorded during the 1983 examination ,
either because it did not exceed the recording threshold of 50 percent DAC or because it may have been overlooked. The maximum amplitude of this indication was 63 percent of DAW with a length of .4 inches and a throughwall measurement of .25 inches. There is no direct ~ association of this indication with any other j recorded indication; however, it is in.close proximity to other indications. Although indication 217 was not recorded in 1983, )-
it probably existed but was not recorded due to one of the reasons state,d above.
Indication number 409 did experience a slight change in recorded dimensions from 1983 to 1985. The following table provides a comparison of the data.
1983 Data 1985 Data Indication No. 409 Amplitude 63% 63% j Length .35" .45" Throughwall .30" .30" The magnitude of change for this indication is considered to be p within the limits of repeatability that can reasonably be expected using the Section XI examination procedures. Since there is no reported growth, the indication growth rate is considered to be zero. For the purposes of the 1985 evaluation, the impact of these reported changes were conservatively evaluated as if they represented changes in the indication sizes.
As indicated in Evaluation Report 85-014, a worse-case evaluation determined that the indications were bounded by the fracture mechanics analysis performed in 1983.
I l
' fW . - .
t l
L ' t. c ATTACHMENT 5 i MEASUREDLLIMITS OF LOCATION AND SIZING ERRORS:
lTheLvariationsin' data'shown in these evaluations:are'within the limits.of repeatability for!ASME Section XI UT procedures. _An excerpt from a paper. entitled "The Evaluation of the PISC'II Round Robin tests". presented atlthe.8th International' Conference on NDE in.the Nuclear-Industry'shows.the' magnitude'ofJvariations for defect location and sizing that were observed during PISC-II. Figure 5 from this article is presented. This figure-shows the distribution of location and sizing errors for-the defects-in ona of ?.he plates.
.The. upper-lleft diagram indicates the: error for location in!-the Y 1
-dimension. . The mean error is .63" with a standard deviati~n ~o of' 1.5".. The upper'right diagram indicates.the error-for location
'in the Z1 dimension. The mean error is .16" with a standard deviation of'.62". The lower left diagram indicates the error
'for. sizing in the'Y direction. The'mean error is .26" with a ?
istandard deviation of 1.9". The lower right diagram indicates' the error for' sizing in the Z direction. The mean error is .41" i with a standard deviation of 1.1".- i I
\
3-1 i
i l
I i
, 2 ,v . . . .,
t N0ZZLE PLATE No. 3 t
no............. m ......... ...
n i. ELY an. Ell .
m .
- n. -is.1 . ::::. n.
- 2.s .
l 202. , 2:2. .
.5= 38.1 -
5 13.5 1 174. ,174 .
111 in .
116. .116 '
_ ]
97 . Sr7. -
n SS. . 52. . 'I
~ ~
, 29. - -
, 22. -
0 -
'O- l---
-Cb -4 0-23 0 ' 20 40' ED 40520 0 23 40 Co (m)
'J10 ' \ ... . .
20c EST 2x. ESI l. .
I ,
- m. n- c .5 . 2n. n- 10.4 .
ns. . =m .
201
_ s. 4 s .0 s. 27.c
,2CM. .
1 170 . 17C. .
13C. -
, 14. -
102. , 1 C2 ca. . ca. -
- n. --
. m. .
' 0 -5 Y 0 a
-120 40 o so 1 20 -12o -a3 ~ o s i20 (m) i i
Figure 5 :
- f. Distribution of location and si- ,
ding errors for the defects.
l.
l' t.