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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
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
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
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
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
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
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
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
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
ML20248H2391989-10-0606 October 1989
Requests Exemption from Requirements of 10CFR26 Re Fitness for Duty Programs Based on Present & Future Operational Configuration
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
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
1990-09-06
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esuun SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, P.O. Box 15830, Sacramento, CA 95813; (916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA RJR 85-470 September 30, 1985 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION HUGH L THOMPSON JR DIRECTOR DIVISION OF LICENSING U S NUCLEAR REGULATORY COMMISSION WASHINGTON D C 20555 DOCKET 50-312 RANCHO SECO NUCLEAR GENERATING STATION UNIT NO. 1 NUREG 0737-SUPPLEMENT 1 - STATUS OF OPEN ITEMS FOR IMPLEMENTATION At the request of the NRC Rancho Seco Project Manager, Syd Miner, the District is attaching a more detailed discussion concerning its schedule for installation of instrumentation considered acceptable by Reg. Guide 1.97.
The District understands that the NRC requires this information to prepare a confirmatory order for those remaining open items from NUREG 0737 -
Supplement 1. The District provided the NRC Staff with a status of those items on July 9, 1985 (RJR-85-326).
The attachment in this letter is an expansion of Attachment 1 of the District's July 9, 1985, letter. It describes the current status of the equipment, and its scheduled status for Cycle 8 and 9 startup. The District developed this schedule using the Living Schedule process.
If you have any questions concerning the above, contact Jerry Delezenski at Rancho S o.
R. J. R0 RIGUEZ ASSISTANT GENERAL MANAGER, NUCLEAR Attachment h
8510080203 850930 I PDR ADOCK 05000312 F PDR
RG L97 Attachment DETAILED IMPLEMENTATION SCHEDULE A. Previously Scheduled Variables
- 1. Core Exit Temperature Current Status: To meet existing commitments, the District installed Core Exit Thermocouples during the recent Cycle 7 refueling outage. The new thermocouples are qualified up to the Class I multiplexers. Temperature is displayable on IDADS (all points) & the SPDS (average of 5 highest points). Both IDADS and the SPDS are fully operational, but neither is currently qualified. The District's Control Room Design Review Group is currently evaluating the incorporation of individual Core Exit Thermocouples into SPDS.
Cycle 8 Status: The District will display Individual Core Exit thermocouple inputs SPDS.
Cycle 9 Status: With the SPDS upgrade (see Item B4), the District will have qualified Core Exit Temperature indication.
- 2. Coolant Inventory (Hot Leg Level)
Current Status: To fulfill established commitments, the District installed Hot Leg Level instrumentation prior to Cycle 7 Startup. -The new instruments are qualified from the sensor up to the Class 1 multiplexers. IDADS, which is fully operational, but not qualified, can display the data on command. At this time, the level instrumentation does not compensate for process temperature, nor has the District insulated the sensing lines to minimize post-accident thermal effects. However, the District has scheduled the insulation of the sensing lines to coincide with the phased implementation of the Emergency Feedwater Initiation & Control (EFIC) modification. The schedule for the insulation work allows the District to minimize radiation exposures as well as to optimize planning and resource commitments.
Cycle 8 Status: The SPDS will display the Hot Leg Level indication. Process temperature compensation will be operational in both IDADS and SPDS, and the sensing line insulation will be complete.
Cycle 9 Status: With the SPDS upgrade (see Item B4), the District will have qualified Hot Leg Level indication.
- 3. Coolant Inventory (Reactor Vessel Level)
Current Status: The District is finalizing design and initiating procurement of a Reactor Vessel Level (trending)
System.
0737ATTA Page 1
1 4 Cycle 8 Status: The District has scheduled the installation of 1 the instrumentation and will provide qualified signals to the Class 1 multiplexers for indication on IDADS and SPDS.
Cycle 9 Status: The District will have qualified indication with the SPDS upgrade (see Item B4).
Discussion: The District has pursued exemption requests concerning the need for Reactor Vessel Level instrumentation.
d Although the NRC staff has recently denied
- the exemption 1 request, the District still believes the recent Once Through Integral System (0 TIS) testing justifies the District's '
position. However, the District is proceeding with design and procurement to complete installation prior to Cycle 8 Startup.
Due to procurement difficulties in obtaining the heated junction thermocouple system, the District has altered its design approach and is pursuing a delta pressure (dP) system.
- NRC letter from H. Thompson to R. Rodriguez (SMUD) dated August 20, 1985
- 4. Steam Generator Level Current Status: The District has procured qualified full range instrumentation and is proceeding with the system design.
Indication of 0TSG level is presently available on IDADS, SPDS, and on the NNI from instrumentation qualified up to the isolation equipment. Compensation in the SPDS and NNI is non-qualified..
Cycle 8 Status: The District will have the new full range instrumentation qualified and installed from the sensor to the Class 1 multiplexer, and displayed on the SPDS.
Cycle 9 Status: The District will have qualified indication with the SPDS upgrade (see Item B4).
Discussion: These new instrument loops, which re-transmit the data to IDADS & SPDS, supply data to EFIC. The District has ,
recently modified its design to include this portion of EFIC in Phase 1 of MOD 001 (as shown on the Living Schedule). Thus, the operators will now have full range data qualified to the Class 1 multiplexer displayed at Cycle 8_Startup rather than Cycle 9 as previously scheduled.
- 5. Steam Generator Pressure Current Status: The District is continuing with the design and procurement of qualified instruments for 01SG pressure.
Unqualified indication of OTSG pressure is accessible on IDADS, SPDS, and NNI instrumentation.
0737ATTA Page 2
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Cycle 8 Status: The District will install qualified instrumentation from the sensor to the Class 1 multiplexer, which will be displayed on the SPDS.
Cycle 9 Status: The Control Room operators will have qualified indication with the SPDS upgrade (see Item B4).
Discussion: These new instrument loops, which re-transmit the data to IDADS and SPDS, supply data to EFIC. The District has recently altered its design to include this portion of EFIC into Phase 1 of MOD 001 (as shown on the Living Schedule).
Therefore, as with the OTSG level instrumentation, the Control Room operators will have data qualified to Class 1 multiplexers displayed in the Control Room prior to Cycle 8 Startup rather than Cycle 9 as originally scheduled.
- 6. Containment Area Radiation Current Status: The District has installed qualified Containment Area Radiation indication to the Class 1 multiplexers. The data is displayable on both IDADS and SPDS.
Cycle 9 Status: The District will have qualified indication with the SPDS upgrade (see Item B4).
t
- 7. Primary System Safety Relief Valve Positions Current Status: The District has installed qualified valve
. position instrumentation with input to the Class 1 multiplexers. The data is displayable on IDADS. The District i considers this item complete.
- 8. Emergency Ventilation Damper Positions Current Status: Although previously scheduled for Cycle 8, the District installed qualified emergency ventilation dampers during the recent Cycle 7 refueling outage. Indication is available on the IDADS computer. This item is complete.
< B. Additions to Living Schedule Subsequent to the September 14, 1984 transmittal of its RG 1.97 analysis to the NRC, the District added other RG 1.97 items to its Living Schedule. The analysis, as required by NUREG 0737, was necessary to evaluate the District's comparison and position with RG 1.97. Only after completion of this task, requiring the expenditure of over 8,000 manhours, could the District identify the need for these additional modifications. These items include:
- 1. RCS Hot Leg Temperature Current Status: The Control Room operators have non-qualified indication available from IDADS, SPDS, and the NNI. Separate Class I instrumentation feeds the RPS for trip functions.
i 0737A1TA Page.3
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Cycle 8 Status: The District will extend the already qualified loops which feed the RPS to the Class 1 multiplexers.
Cycle 9 Status: The District will have qualified indication L with the SPDS upgrade (see Item B4).
- 2. Pressurizer Level Density Current Status: The Control Room operators currently have unqualified compensated indication available through the NNI.
They also have qualified uncompensated indication available through IDADS and SPDS.
Cycle 8 Status: The District will install qualified RTD's to allow qualified compensation in IDADS and SPDS. The loops (level and temperature) will be qualified up to the Class 1 multiplexers.
Cycle 9 Status: The District will have qualified indication 2
with the SPDS upgrade (see Item B4).
- 3. Estimation of Atmospheric Stability Present Status: The specified accuracy of presently installed equipment complies with the criteria of RG 1.97 and RG 1.23.
The District has made improvements in the instrument loop circuitry to assure that this accuracy can be met with normal maintenance. Recent experience (over the past few months) is encouraging. Region V and the NRC Meteorological Staff are following this progress closely. Design is under way to improve the data communications link between the Met Tower and IDADS to reduce signal degradation and thereby further improve overall 4 accuracy.
. Cycle 8 Status: The District will have a functional data
. communication link.
- i. 4. SPDS Upgrade Present Status: The SPDS is currently functional and displays most of the Category 1 RG 1.97 variables. The exceptions are:
- Core Exit Thermocouples Hot Leg Level Reactor Vessel Level Compensated Pressurizer Level
- Condensate Storage Tank Level The District wil1 perform a human factors review of the RG 1.97 display following- 4completion of the District's Control Room Design Review (CRDR) effort (Scheduled for 12/31/85). As noted in the 9/84 submittal, the District has seismically qualified all equipment except for the CRT's and control panel cabling.
Although the system is partially redundant, power is not Class 1.
0737ATTA Page 4
Cycle 8 Status: The District will qualify additional Category 1 variables to the Class 1 multiplexers and display them on the SPDS. The District will also human engineer all displays.
Cycle 9 Status: The District will modify SPDS to provide:
Full redundancy (2 channels) 1E Power Necessary seismic qualification Indication of all Category 1 variables Discussion: The District believes that use of the SPDS for the ,
display of RG 1.97 Cateaory 1 variables, will result in improved human factors and an integrated approach to post accident monitoring and recovery at Rancho Seco. The extended schedule is a result of the 4-5 man years of additional effort necessary to complete this project.
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