Letter Sequence Other |
|---|
|
Results
Other: 05000312/LER-1986-020, Forwards Rev 3 to Procedure AP.56, Core Damage Assessment, for Inclusion in NRC Review of post-accident Sampling Sys. Procedure Revised to Correct Discrepancy Noted in LER 86-20, ML20137X776, ML20137X795, ML20151Y962, ML20203P855, ML20215C433, ML20215J722, ML20215L385, ML20215L569, ML20235P297
|
MONTHYEARML20137X7951985-11-22022 November 1985
Notice of Deviation from Insp on 850923-27 & 1007-15
Project stage: Other
ML20137X7761985-11-22022 November 1985
Notice of Violation from Insp on 850923-27 & 1007-15
Project stage: Other
ML20137T5231986-02-0606 February 1986
Forwards Summary of 860116 Meeting Re Lessons Learned from Davis-Besse & Rancho Seco Events
Project stage: Request
ML20151Y9621986-02-0606 February 1986
Forwards post-accident Sampling Sys (PASS) Design Changes Implemented to Correct Capability Deficiencies.Pass Still Meets Requirements of NUREG-0737,Item II.B.3.Clarification of PASS Design Also Encl,Per 860127 Discussions
Project stage: Other
ML20141N8801986-03-13013 March 1986
Forwards Addl Info Re Changes to Facility post-accident Sampling Sys,Per 860218 Meeting W/Nrc & 860220 Telcon.Data Re Induced Gamma Radiation & Accuracy of Portions of Sys Affected by Mods Will Be Provided When Available
Project stage: Meeting
ML20155F3891986-04-11011 April 1986
Documents Commitment Made at 860218 Meeting W/Nrc to Demonstrate Operability of post-accident Sampling Sys Prior to Startup.Scope & Schedule for Test Will Be Provided in Time for NRC Comments to Be Considered
Project stage: Meeting
ML20203P8551986-04-30030 April 1986
Forwards Summary of Test for Chloride & Boron Analysis Employing Appropriately Diluted Test Matrix of post-accident Sampling Sys Equipment,Per 860313 Commitment.Addl Mods to Improve Sys Reliability & Maintainability Also Encl
Project stage: Other
ML20235P2971987-03-13013 March 1987
Rev 3 to Procedure AP.56, Core Damage Assessment
Project stage: Other
ML20215L5691987-05-0404 May 1987
Forwards,For info,bi-weekly Update of Working Copy Status Rept of 870427 post-accident Sampling Sys Mods
Project stage: Other
ML20215J7221987-05-0404 May 1987
Submits Addl Info Re Mods to post-accident Sampling Sys in Effort to Improve Sys Reliability & Provide Alternate Analyses for Boron,Chlorides & Reactor Bldg Atmosphere Radioisotopes.Criterion 10 of NUREG-0737 Satisfied
Project stage: Other
ML20215C4331987-06-0202 June 1987
Forwards Biweekly Update of Working Copy Status Rept of PASS Mods .Work Request Initiated to Repair Leak on Output of Filter F-496 (Er 131281) & Mgt Safety Review Committee Review Completed on 870526
Project stage: Other
ML20215L3851987-06-16016 June 1987
Forwards 870608 Biweekly Update of Working Copy Status Rept of post-accidental Sampling Sys Mods,For Info
Project stage: Other
05000312/LER-1986-020, Forwards Rev 3 to Procedure AP.56, Core Damage Assessment, for Inclusion in NRC Review of post-accident Sampling Sys. Procedure Revised to Correct Discrepancy Noted in LER 86-201987-07-0606 July 1987
Forwards Rev 3 to Procedure AP.56, Core Damage Assessment, for Inclusion in NRC Review of post-accident Sampling Sys. Procedure Revised to Correct Discrepancy Noted in LER 86-20
Project stage: Other
1986-04-30
[Table View] |
|
|---|
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
- _ _ _ _ _ _ _ _ _ _ _ _
l 8suun SACRAMENTO MUNICIPAL UTILITY DISTRICT C P. O. Box 15830, Sacramento CA 95852-1830.(916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CAllFORNIA RJR 86-171 April 30,1986 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTN FRANK J MIRAGLIA JR DIRECTOR DIVISION OF PWR LICENSING-B US NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 DOCKET 50-312 RANCHO SECO NUCLEAR GENERATING STATION UNIT NO. 1 POST ACCIDENT SAMPLING SYSTEM (PASS) - ADDITIONAL INFORMAITON The District's March 13, 1986 letter (RJR 85-97) indicated that the District would perform a test of the PASS equipment using a test matrix similar to the standard test matrix described in the NRC's July 12, 1982 clarification. Using the on-site laboratory equipment, the District completed the test for chloride and boron analysis employing an appropriately diluted test matrix. The test is summarized in Attachment 1.
Since the March 13, 1986 letter, the District has been making additional modifications to PASS to improve the system reliability, maintainability, analytical accuracy and ALARA. These modifications do not change the analytical concepts or methods of the PASS System. The attached Design Change Notices (DCN), DCN #13 to M575, Sheet 1, and DCN #8A to M575, Sheet 2, show these changes.
The redesign of the Sample Collection and Analysis System (SCAS) shown on DCN #8A, provides for replacement of all metal seated valves with soft seated valves. These new valves are designed to accommodate particulates in the fluid system, and have built-in compensation for wear without degredation of their leak tightness. This valve replacement should significantly improve the reliability of the system.
The revisions to improve maintainability include a complete rearrangement of all of the hardware in the SCAS cabinet. This rearrangement provides easier access with quick removal capability for all components that may require maintenance or calibration.
Other improvements to the PASS System includes:
The redesign of the piping s'/ stem to separate the Reactor Building atmospheric analytical syste.n from the reactor coolant liquid analytical system; i 8605080252 860430 00 PDR ADOCK 05000312 l P PDR
/ l DISTRICT HEADQUARTE9S O 6201 S Street, Sacramento CA 95817-1899
s Frank J Miraglia April 30,1986
)
i
- Tho. modification of fluid flow paths to minimize dead legs and other conditions that could. lead to misrepresentative samples;
"* The replacement of certain components of the ion chromatograph to improve its resolution as well as improving the overall accuracy of the system and;
- The reduction of the, total inventory of contaminated liquid in the SCAS at' any time in order to significantly reduce exposure to both 0perations and Maintenance personnel.
The above enhancements do not. alter the capability of the Rancho Seco PASS to meet the criteria as discussed :in.the District's February 6 and March 13, 1986' letters. However, the changes implemented under the Rancho Seco PASS Improvement Program will effectively improve the reliability and accessibility of the PASS System while significantly reducing personnel exposure. -
If you have any questions, please contact Jerry Delezenski of my staff at (2 333-2935 extension 4909.
ty -
R. J. R00 GdEZ ASSISTANT GENERAL AGER, NUCLEAR Attachments (5) n 3
Attachment 1 RJR 86-171 PREPARATICN AND ANALYSIS OF TEST MATRIX FOR PASS A chemical matrix was prepared with approximately those concen-trations suggested by the NRC. The minor changes in concentration were a result of stoichiometric limitations for the reagents used.
Two parameters, pH and conductivity, were measured on the undiluted matrix; however, no accuracy data are applicable for these measure-ments. A diluted portion of the matrix was analyzed for Cl and Boron by I.C., with the appropriate accuracy data included. Listed below are the concentrations of each component for the matrix:
Ion Succested oom Actual opm Reacent Used Grams / Liter B 2000 2000 H3B03 11 439 Li+ 2 2 Li 70H.H 2O 0.0349 NH4 + 5 1.2 * .0196 K+ 20 12 * .0623 Cs+ 250 250 CsNO3 .367 Ba2+ 10 10 Ba(NO3 )2 .0190 La3+ 5 13 .0349 Ce4+ 5 5 (NH4)2C e(NO3 )6 .0196 Cl- 10 10 LaCl3 .7H20 .0349 I- 40 40 KI .0523 NO3 - 150 136 * -
- reagent (s) listed with other ion Anticipated analyses for the PASS in its present configuration are pH and conductivity on undiluted sample (in-line); Cl and Boron analyses on diluted (grab) sample using compensatory measures. The dilution can range between 500:1 to 1500:1.
The dilution used for this test was 625:1. A Boron and chloride '
- standard of known concentration of approximately the same concen
- tration as the test matrix was analyzed in conjunction with the test matrix. The discrepancy (%) is noted between experimentally determined concentrations and concentrations expected (listed as actual).
Listed below are the results of the analyses: ,
pH =.5.62 (on undiluted matrix) .
conductivity = 778 pS (on undiluted matrix)
Boron = 3.05 ppm for 1/625 diluted sample) : Actual = 3.2 ppm discrepancy = -4.7%
Cl = 15.7 ppb (for 1/625 diluted sample) : Actual = 16 ppb discrepancy = -1.9%.
i 1
e n s,- ,en, ,- ..n-- ,,n,. ,- ,n.., ,,, , , ~ ~ ,-, - , . - - - - . - - - - , - ~ - ~ - . - -,
[*~ = l
- l a- l' as e = l I e l ' (Wppkg i +a '
, 9_"0 i.'a -
j '
k
{g I a a E yM i q,,
s g ,,, _ ...
-ms -
i'l, i 9, I .o ; n ., ;
. a .
e0 "FIF l 1
i y, !{ !Jj d .
~
ib TNS k
l @ =
l r zu_ g Kgd. e 0 - -];
..S .
g k g
-- , , g r--
t (pK----- 2 i e <
n gi j
c4
I ar , i,n[g u .
e Tt, -
==
b
J ll gg (- ,
$ i n' [ .
.- l(d4 8 y y
] --- b j,9 ,
,EA ii!n
- p
- . - . . - $--- S "st Jj ; "
Na zi
- l .
t t.
(r ..N. i,
- g, i,!
--ila p-y -
ia c, l 5
, / t !.
e:
, y w .
eii
!, +d [-b 4 ll*
s
.:e f, s , .. -
.._ _.h,. .
. M_
,v , , I-
- r. -
, b<a,y, y e _..
e
., a a e, g
- .s ---m.,a ..- = > ~ ~ . - t in 3
- : s,i g f.?I o r r i'~i-?
l [e) .
Pkr ,
l ,rT i,%
, , 8 r
} Q R& - *-- . .
,t i .,
i
- : i , v
>j a[i* )> h(- > iiii
- l e~=/ 1 i c i
) ,i, : l:!.Li
- ;-la*-....a y'y C, 4 .,
N -D-f I -- *Cw "I I~
r
- ,,d e 6' e1 5 '
a i i
=
E
. . yh. :+
.n,, ;
- l'%g}
4
% t ka l1-~
,3 Ilg nr i
a s.h i
F LG - eius
[,$. :=dj? ;
l 5 !./
u-a@ 4 bl ~
q <-)- ;> g g ; j
= G l
,n %p----); : * : -
i E l, r b T l $.m i 8
=
E c ..
i ", .
e 4
- n. i )y.....1 l,
=
kd m.
d, i.
W. 4, '.
j g ,
- a 5 l qal ()1l
- = : .
g 3 p c:n til.)'
E hji [dp i T$ $ :.Il 'lt -u -
sc r >
n 33
-1
I 5
h i!)I l-B I
,.....-.-----c..----==--..-..===-...-== t
1 g ,
. . s . . = , - , . .
E ll L l ! I g E 4
!q 7 ' ;I 3 i
l i,p ll I!a .I 4 ii ' pli ni l;g n 1 !! i, 1
ijy"!)
- f. i ill *g i if Ij ij Q
}Rc i . {'$ t.4 e
3 5
=
r<
I Tr d, ,
- . 4 a3c% L'4
- !. a o il r Y 2 Ia ch t i? Ai E
,<c<y \
~ - m!i [Ff . l -
' T i d.4 ;
2 '-
49j}j l e a a,s -p;.j.l.
L
=
)e gs jd s
af et r i
, ,,a
! =
.. *, s I I $x t i I '
'['
i t op, n g g L aw i l -l .m.t g ':sw/ i9'i -
h KU s M. .
ini 3
- e ()3%u Ql k
+ 1 3'e'Q : -~+
=
s : hxa $81 ll l
$p 'w d a / e _t
,{II a
= p -_a ' - - - - ,
c.
. ,u Q
'[y j g _
._____ i 2 r_ ,._ __
! $ _ ,@y! 4H_ ,t_:
9 1-I -
i 1,F7.,_.w. gie\P J.
- m :. - c, s m
_jP,e Fi .} u kp
( 3I :t
, e. *4
- g a u Aa> i eini i p gm 3 l
u u d,e--+en. r r I,, g+ 7;;
- 24 s a, .
r *.
- I!' $f [d
[',"; [ T a;
'I md; 3 K w - -
I i ;
E 3 3 ,_
a
'i ,
(3 N
_ ,y ,
v n
,r .
O
_fQ ,. .
fjk_ r-------
-ilh,l-- i
-)..u i @'a m--
- , 1 ,i ,f . , I 7, 0J
,J/. , Q, jh.,, c, I . {.!
j a-
.. . ,. ~
"5h
.p,
,j wl-,. ! '1a G a-41 y . L, ,,. l i g. - . I ' r- _M
~~
-ga .
I ,l*Ee
$lj }
~
/
l by d' L i rc}
y ! I' ihA 5
% v) e l';iUn@k;k@,@;:
'o- i 8 il i
b e i 3
a p m,L 9
e ,
3
- - 3@.
2 a {. = = , ~.
-.n
. 3 <
e g
xf Hga,pv2 S
i 1
i a- 'n.am ,
- n
i i
P e '
s -
g, i i
. : , _c ,
I .c l
~
. 8 i !o a s .
'a.
e >e ;di y o .
30u., 6h[ f u
}
e
,6' ,jkI g I s -.
Ndhg1-!i!!
4, ,--+ %, ,
i
' f) (il>
,3,A ,
i o.. ;lI n L.i
.i.. !. e.
i, Igi g
jIn a i
i
- d. . liIf ^
- 1 v
l l
l .
l .
l .l = -
l -
.-----_.___._____-___,)
. ,- [.' :f' -
~
o.
7- j. % j ,
- ; y y b 5l l Ii !@
[y ,
kE 44 .
c ,g 3 .- ., .
- g. g w. ; ,li 1- F
- , d; -
d "1p .,
- 1!':8i s 5 x
.c 23 L 9 y... n: J, z : "# . c -
.. 6< g ::h l
- (
Q1 y
-al
. .j _
- - ;- p 'y~
j Sm # t '
(Q
. . , y 8k g -
l 1
y d\
g ij !
N hh sk i _
bg. o m,gi (phi!h j ?t --
Eg1, y
, n, m s% 1\4 N\ i
~
r 1
@f xx n( x x x x
_l.
1 ;g l
=
7 Qg'Et N ).g.
\t N N N Ny x e i' a
, . i9 \ % As N glg ri H
.,N N N N*)c..,> X
- ~
5 l 3 \ \ 8 I 1
-h h * \ \ -
ed N
N N a\w '
\im =c ',il
. g3
, ,1.
im x et i 't..en ,
41 u,
- n ,s : x D, a
, /
@ \.
x1l. f ,. N e
s ,s.
r ,.. ,
. . <<o s s .s i
.e
,t -a g 54 :
ly if ( l UM _ .% h- : 8: "~l f'~~
'N,y) st t! ? > ~ . = @19 ,\
~
j Q i i
! I D @ i!!/ Y ,s h>i'x b[,o--.\ yg. a t \ 3 3 i
E [ji' "
[
"' I uf MT1
\N h, $ , 5 7I k~
p3 \{
i k ..
1h
- ,iA \g;o j q!q>j.! = i N -
o ry- !
-l - - -
.I I I I I I I 1 I I
=- e > e
- i . m o , o j .
. ahi" I fi h l V
fiNr i t! !,
1Q1
- ~-
y p2 l 0
)' j,
. is.
a i. g m's .
.2 a ;_,j J h*
i <0
@If L;a l c@ --
;;; 3g ;g 0 d a 'r ima 2-- ,I a i = 33 .g
!, s t Et t i g c e
- r-
@c v3 a.
.I
!y sf -
= 30 3
q '
9 s g m* 2
[ild kii pe i
- -;j g" 9-s E o
., u- z
, a ! 4 ~
, f !;!
E - I' d') s l ,5' $5 i
,$g9- 5
>s h'=g y ,,
l i
! t t
r
'*kh < -
,j[ .
O
-g I i i
h i.
l i 1
g i!fjd r ---
~
U II 4 - Tg ivr4)} 4-@' 4
s l' , -
-f~ ' t
'il %h _o- @o-3!i- : I .
v i s Ib-h $ , l \
%' s e pj i
), em S ispj *
,1 u + Ea =:, : ill J c
4 y'g* *
;[e r i
Tg d@j b
i >
A94 '
?a ; ,. :,-- w ba - se o ;
k si i i h ! y 4 Qg3 () h .
!dr 2 fk "1 w .7x-T ,
,,5 m,g.
45 tr m -
v -
x s e
, s h kt b>l+ , I [) I -
. []!!
~
_Iml!11IM._. ill 31
=
l g ;!
)<:'aund
~
-t
* ~4 -e- !.u. g y
!%UAsid l<
a
- d. >> 46 '
_ : h. 4r! I
a
! !(6lljf).mdPQ,ih3 ripe p,a gsg: s' q 1,, ,
F- 3 g #y $ ppm a
e g ia ,
-J 2
M54 %s W m ets 1 4 s g; 3 1h S 1 ;
I 'lkI!!!I!$l!pslik !$ 0 O lhhih.fi -
I}}