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MONTHYEARML20138B2131985-10-0404 October 1985 Confirmatory Action Ltr Re 851004 Telcon Concerning Return of Facility to Power Operations After 851002 Reactor Trip. Util Must First Conduct Root Cause Analysis of Trip & Provide Briefing to NRC Before Return to Power Project stage: Other ML20133K5131985-10-11011 October 1985 Notification of Significant Meeting on 851016 W/Util Onsite to Discuss Root Cause Assessment & Readiness for Resumption of Power Operations Following 851002 Reactor Trip Project stage: Meeting ML20133K5891985-10-14014 October 1985 Forwards Action List Providing Util Plan to Resolve Concerns Stemming from 851002 Transient,Per 851010-11 Meetings.Listed Commitments Scheduled for Completion Prior to Restart. Schedule for long-term Items Will Be Submitted by 851118 Project stage: Meeting ML20133K7191985-10-18018 October 1985 Forwards Supplemental Info Re 851002 Transient,Per NRC Request During 851016 Meeting.Info Includes Main Feed Pump Trip Determination,Hpi a Flow Anomaly,Cooldown of RCS, Cooldown Rate,Tech Specs & Revised Action List Project stage: Supplement ML20133P8511985-10-25025 October 1985 Forwards Summary & Supplemental Info Re 851002 Transient, Per 851025 Telcon.Items in Plan Include pre- & post-startup Actions to Determine Root Cause of Event & Initiation of Corrective Programs Project stage: Supplement ML20134A8371985-11-0101 November 1985 Forwards Addendum to Attachment 5,Part Ii,Rev 1 to Auxiliary Feedwater/Main Feedwater Failure Analysis Contained in Project stage: Other ML20138R0971985-11-13013 November 1985 Forwards Rev 2 to Attachment 2 & Addendum NRC-5150 Re HPI a Flow Anomoly,Rev 1 to Attachment 5,Parts I & II Re Auxiliary Feedwater/Main Feedwater Failure Analysis & Attachment 8 Re Oil Levels on safety-related Pumps Project stage: Other ML20138R9291985-11-15015 November 1985 Forwards Latest Rev to Action List,Describing Program Plan to Resolve Concerns Stemming from 851002 Transient.All Startup Required Items Completed.All Power Escalation Items Will Be Completed by Full Power Operation Project stage: Other ML20137H9361985-12-23023 December 1985 Responds to Violations Noted in Insp Rept 50-312/85-30. Corrective Actions:Instrumentation & Control Procedure I.103 Revised to Include Multiplier Link Change Instructions & Pegging Steam Pressure Controller Setpoints Reduced Project stage: Other 1985-10-04
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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
[Table view] |
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.lSMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, P.O. Box 15830, Sacramento, CA 95813; (916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA RJR 85-555 l
November 15, 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 UPDATED PROGRAM PLAN TO RESOLVE ITEMS FROM TRANSIENT OF OCTOBER 2, 1985 In several letters during the period of October 14 thru 25,1985, the District supplied the NRC staff with an " Action List". The " Action List" describes the District's program plan to resolve concerns stemming f rom the transient of October 2, 1985. The District committed to provide a status of the short term items and a completion schedule for those items desigpated as long term by November 18, 1985. Attached to this letter is the latest revision to the " Action List". It is important to note that the District has completed all of the "startup required" items and will have completed all of the " power escalation" items by full power operation.
If you have any questions conerning any of the above items, contact Jerry D leze s i of my staff.
E w R. J. R0 RIGUEZ ,
l ASSISTANT GENERAL 'ANAGER, NUCLEAR Attachment
%g,
-h$kA1'9 J.}
E _-
LEGEND: SU = Startup R:quir:d ,h LT = Long Term
~
STATUS DATE 11-14-85 :
PE = Power Escalation OCTOBER 2, 1985 TRANSIENT TIME 1200 NA = Not Applicable
- ST = Short Term - ACTION LIST -
4 j DESCRIPTION RESPONSIBILITY SCHEDULE STATUS WR No./NCR/ COMMENTS l ETC. ;
! I Post Trip Report J. Field SU Completed NA l II Root Cause Analysis S. Crunk SU Completed
- NA Reviewed by Management i Review Team.*
i j III Aux FW ICS Control
- a. Verify calibration of N. Brock SU Completed 104969, 104972 i appropriate modules. 104973, 104974
, 104975
- b. Reset of Aux FW Valves B. Spencer SU Completed S0-20-85 Crews were trained.
on MFWP Reset.
I
- c. Revise procedures for B. Spencer SU Completed NA Temporary change to III b. Operating Procedure A.51. i I
l d. Evaluate design of AFW V. Lewis ST To be NA l valve reset on restart Completed 3
of WW Pump or RCP. 11/22/85 :
I ,
j 1. Revise AFW valve N. Brock SU Completed R-0196 ;
- control logic for l loss of MFW pumps. f i
- October 14 commitment for review by MRT completed. Finalized Root Cause Analysis still in progress.
t i :
z = : . ; -- - --
- -.z;; =. - - - . . . .
~
i.)
l LEGEND: SU = Startup-Required j LT = Long Term
.PE = Power Escalation OCTOBER 2, 1985 TRANSIENT STATUS DATE 11-14-85 TIME 1200 1
1
-j NA = Not Applicable
.; ST' = Short Tem - ACTION LIST -
-l DESCRIPTION RESPONSIBILITY SCHEDULE STATUS WR No./NCR/ C0fMENTS ETC.
! IV HPI "A" Inject Line flow l indication
- a. Write and perfom J. Field SU Completed STP-180
)
Special Test Procedure.
i
! -b. Perfom calibration N. Brock SU Completed 105228 l check of FT-23807.
j c. Resolve flow anomaly and J. Field SU Completed S-5103,
- prepare Summary Report. S-5150, Rev. 2
- d. Write and perfom a 2nd J. Field SU Completed STP-184
_. ) Special Test Procedure.
l l e. Infom operators of M. Hieronimus SU Completed SO 22-85 characteristic of
~i flow indication.
l
)' f. Recalibrate HPI flow N. Brock SU Completed 105422, 105424 transmitters so actual 105478, 105421 l flow is greater than indicated.
V Pegging Steam Controls
- a. Detemine adequacy of J. Field SU Completed NA l- pegging steam setpoints
- and FW heater relief 8 valve setpoints.
s 8
3 1 .
fj j LEGEND: SU = Startup R:quirId LT = Long Term STATUS DATE 11-14-85 3
~l PE = Power Escalation OCTOBER 2, 1985 TRANSIENT TIME 1200 l NA = Not Applicable 1 ST = Short lem - ACTION LIST -
J DESCRIPTION RESPONSIBILITY SCHEDULE STATUS WR No./NCR/ COMENTS j ETC.
1 V b. 1. Verify setpoints of R. Lawrence SU Completed 104541, 104544 All setpoints as per
, . 2nd and 4th Point 104542, 104543 Process Standards.
heater shell relief 104562, 104563 valves. '
- 2. Reset 4th point R. Lawrence SU Completed 104581, 104583 Revised setpoint values .
! heater shell reliefs 104582, 104584 per V a. ;
j to new setpoint ,
values. ;
) c. Verify setpoints of all R. Lawrence PE To be 104573, 104575 Will require use of hydro i secondary system relief Completed 104574, 104576 assist on valves without i
- valves which could 11/19/85 recent setpoint history. ,
j cause rapid cooldowns/ *
, other FW heater shell rel ief s.
l
- d. Detemine appropriate R. Lawrence LT To be To be done as part of PM
- periodic test program Completed program upgrade.
1 (i.e., either PM or SP 6/1/86 i Program) and implement i same for all secondary relief valves.
}
i e. Resolve report of MSR J. Field SU Codipleted NA Resolved that MSR Reliefs i
Reliefs lifting after did not lift.
l Rx/ Turbine trip.
t
- f. Establish criteria for V. Lewis LT To be l process setpoint Completed determination. 2/1/86 ,
l J.
I LEGEND: SU = Startup R:: quired LT = Long Term STATUS DATE 11-14-85 i PE = Power Escalation OCTOBER 2, 1985 TRANSIENT TIME 1200 NA = Not Applicable ST = Short Tenn - ACTION LIST -
DESCRIPTION RESPONSIBILITY SCHEDULE STATUS WR No./NCR/ CCMMENTS ETC.
V g. Review plant for proper V. Lewis LT To be application of criteria. Completed 5/1/86
} h. Add setpoints for R. Colombo LT To be AP.152
- FSL-32243, 32244, and Completed
- 32453 to Process 12/1/85 l Standards.
1 VI "A" Main Feedwater Pump seal water and controls
- a. Repair linkage on N. Brock SU Completed 104965, 105378 l controller.
- b. Check common mode N. Brock LT To be NA Looking for common mode 1 failure possibility on Completed relations to VI a.
j controller linkage. 12/15/85 j VII Main Feed Pump Trip Event
- a. Perform test to duplicate J. Field NA Deleted STP-181 Test not required.
j low vacuum condition.
- b. Install monitoring N. Brock SU Completed
I
- c. Verify "as built" wiring C. Linkhart SU Completed 102722 Plant drawings accurately of "A" FWP trip circuits. show "as built" l configuration.
}
l 1
i I
l
i
.1 -
I j LEGEND: SU = Startup R: quired '
.)
LT = Long Term -
STATUS DATE 11-14-85 PE = Power Escalation OCTOBER 2, 1985 TRANSIENT TIME 1200 NA = Not Applicable ST = Short Terin - ACTION LIST -
, DESCRIPTION RESPONSIBILITY SCHEDULE STATUS WR No./NCR/ COM4ENTS
'i '
ETC.
-l VII d. Check setpoints of trip N. Brock PE Completed 102716, 102721
. devices. 102718, 103272 102720, 103273
- e. Compile history of FW N. Brock ST Completed NA pump control problems.
i i f. Check end play on main R. Lawrence SU Completed 102719 Acceptable.
} shaft of "A" MFW Pump.
j g. Obtain L0 sample from R. Lawrence SU Completed 103269, 102719 Normal. '
j "A" and "B" MFW Pump and i have analysis performed.
i !
- h. Verify "as built" wiring C. Linkhart SU Completed 105686 Acceptable; elementaries of "B" FWP trip circuits. are correct. S-5119 written. i i
i 1. Install Trip Circuit C. Linkhart LT To be Requires pump out of I' i Alarm Lights. Completed service.
{ During Cycle j 8 Refueling 1 Outage l
VIII Main Condenser Loss of Vacuum Event l a. Update drawings to R. Lawrence SU Completed R-0177
! reflect "as built" conditions of MSR relief sealing steam.
1
g i
}!
i LEGEND: SU = Startup R; quired <
j LT = Long Term STATUS DATE 11-14-85
~
. PE = Power Escalation OCTOBER 2, 1985 TRANSIENT TIME 1200 NA = Not Applicable ST = Short Tem - ACTION LIST -
DESCRIPTION RESPONSIBILITY SCHEDULE STATUS WR No./NCR/ COMMENTS ETC.
! VIII b. Revise procedure (s) to B. Spencer SU Completed NA Temporary change to
! show MSR relief sealing Operating Procedure A.49 steam valves. written.
l ,
l c. Determine whether B. Spencer SU Completed NA Revision 12 to Operating sealing steam procedures Procedure A.49.
are adequate and usable.
- d. Review / analyze perfom- J. Field LT To be NA ance of the gland steam Completed
, condenser. 7/1/86 1
- e. Investigate when/why MSR B. Spencer SU Completed NA Investigation unable to
) sealing steam valve was to ascertain when/why ,
l closed. valve was closed.
I
{ f. Determine whether MSR R. Lawrence LT Completed NA Review shows adequate Relief Sealing Steam for restart.
l System works as designed.
i'
- g. Initiate WR for rework R. Lawrence LT Completed 104113 Work Request written to be t of leaking MSR relief reworked at the next
, val ve. refueling outage.
I
- h. Resolve setpoint error S. Carmichael SU Completed 105116 Reset to proper value.
of main turbine low vacuum trip.
l 1. Correct / upgrade docu- R. Lawrence LT To be i mentation for Completed I maintenance on turbine 1/1/86 j trip block.
l l
- _ _ _ - - _ . _ . q l
LEGEND: SU = Startup Required j LT = Long Ters -
STATUS DATE 11-14-85
'I PE = Power Escalation OCTOBER 2,.1985 TRANSIENT TIME lau j NA = Not Applicable :
i ST = Short Tem - ACTION LIST - i J
DESCRIPTION RESPONSIBILITY SCHEDULE STATUS WR No./NCR/ COPMENTS
- ETC.
VIII j. Include placement / B. Spencer SU Completed Temporary change to l removal of MSR relief Operating Procedure B.3 valve covers in written.
procedures.
4 l k. Fabricate new MSR relief R. Lawrence ST To be i valve covers. Completed i 12/15/85 i
i
- 1. Include main turbine R. Colombo ST To be
} trip setpoints in Completed j Process Standards. 12/1/85 1
i m. Develop design improve- V. Lewis LT To be Living Schedule will ment to reduce leakage Included in determine final completion of MSR relief valves. Living date.
j Schedule
- by 1/1/86 i
i IX Condensate /FW Oscillation J. Field SU Completed NA-l l
l X ICS Tuning f a. Prepare ICS/Feedpump N. Brock PE Completed STP-657 Approved by PRC 10/18/85.
.i tuning STP.
?
I
- b. Perform tuning as plant N. Brock PE To be Based upon achieving full i conditions pemit. Completed power prior to this date and j 12/1/85 allowing 2 days of tuning at 100 percent power.
t
_a------- _ _---------------- .
t LEGEND: SU = Startup Required LT = Long Tern STATUS DATE 11-14-85 -
t PE = Power Escalation OCTOBER 2, 1985 TRANSIENT TIME 1200
! NA = Not Applicable ST = Short Term - ACTION LIST -
DESCRIPTION RESPONSIBILITY SCHEDULE STATUS WR No./NCR/ COMMENTS ETC.
X c. ATc Control N. Brock LT To be Completed 12/15/85 4
XI Valve Identification Program
- a. Develop list of selected B. Spencer SU Completed To incigde Operating systems for Operations Procedures A.37, walkdown. A.49,A.41, A.42, A.50, A.46, A.34, A.38, A.40, A.51, A.47, A.28, A.39, A.53, A.6.
. b. Operations crew to walk B. Spencer SU Completed
- down systems to identify valves not on prints.
- c. Prepare NCRs on findings, B. Spencer SU Completed NCRs written. Temporary revise procedures as changes to procedures necessary, and tag valves. written. Valves tagged.
- d. Update drawings D. Abbott LT To be (P and ids). Completed 4/1/86
- e. QA Surveillance H. Canter SU Completed No's. 492,
, 488 I
I i,
i
1 ,
i
- I LEGEN0: SU = Startup R:: quired *
, LT = Long Ters -
STATUS DATE 11-14-85 l OCTOBER 2, 1985 TRANSIENT TIME 12U0 t
! PE = Power Escalation i NA = Not Applicable ST = Short Tem - ACTION LIST -
DESCRIPTION RESPONSIBILITY SCHEDULE STATUS WR No./NCR/ C0fMENTS6 ETC. -
XII "B" Feedwater Line Leak R. Lawrence SU Completed 104548, 104564 Report addressing the
- Reactor Building. 104560, 104572 cause and the repair done.
I 102095, 104569 Material meets applicable
- l 104567, S-5090 code. l 1 S-5111, S-5093 i 1 i XIII P-319 Bearing Failure t
- a. Pump Repair R. Lawrence SU ' Compl eted !
n .
Surveillance History and
- b. Maintenance History R. Lawrence SU Completed l l Cause of Failure / Post Repair Test
} Corrective Action ;
I c. QA Surveillance J. Jewett SU Completed No. 485 !
1
- d. Provide oiling B. Rausch SU Completed TS 85-1033 To include safety related I l instructions pumps. How to determine ;
l level. How to maintain oil i level. Pump specific
'li instructions, j t
i e. Past practice on LO B. Spencer SU Completed Level. '
il l f. Investigate whether R. Lawrence SU Completed HLC 85-067 No level change was made.
l "Nomal" level was ;
changed. t l
[ g. 48-Hour Endurance Run J. Field SU Completed STP-182 1 l 1
1
_ :_ . - . . - - , 1 . 2. - - - . -
3
_ _ _ ~
j . -
(
LEGEND: SU = Startup Required 4 i LT r Long Term -
STATUS DATE 11-14-85 i
i PE = Power Escalation OCTOBER 2, 1985 TRANSIENT . TIME 1200 l l NA = Not Applicable '
)
ST = Short Ters - ACTION LIST -
i i
DESCRIPTION RESPONSIBILITY SCHEDULE STATUS WR No./NCR/ C0fMENTS ETC.
XIII h. Identify all safety R. Lawrence SU Completed NA .
related pumps which j utilize slinger rings.
- 1. Oil level indication for V. Lewis SU Completed S-5120, S-5124 P-318, 319, 482 A and B, S-5114, S-5115
, and 261 A and B. S-5117, S-5118 i
j j. Root Cause S. Crunk SU Completed
- Reviewed by Management Review Team.
l l k. Inspect rings in pumps R. Lawrence SU Completed 102096, 102097 j which have been 102099 previously disassembled.
i 1
XIV Loss of Aux Steam Event
] a. Prepare Report M. Nickerson SU Completed TS 85-1021 I
- b. Root Cause S. Crunk LT To be NA Included in RC 85-021.
Completed i 12/15/85 f c. Investigate Aux Boiler C. Linkhart SU Completed NA j Power Supply.
5
- d. I and C analysis of N. Brock LT Completed XIV c.
- Review by MRT completed. Finalized Rcci Cause Analysis still in progress.
l 1
1 1
4.
LEGEND: SU a Startup R:quir:d .-e '
LT = Long Term STATUS DATE 11-14-85 TRh PE = Power Escalation DCTOBER 2, 1985 TRANSIENT TIME 1200 Gb NA = Not Applicable :,0 ST = Short Term - ACTION LIST - f r, -
DESCRIPTION RESPONSIBILITY SCHEDULE
STATUS WR No./NCR/ COMMENTS ETC.
XV Training
- a. Lessons Learned F. Thompson LT To be NA Review and if determined i<
Completed necessary, revise lesson a 4/1/86 plans.
- b. Training on Item III.b B. Spencer SU Completed NA SO 20-85 (Instructions / '.
Recommendation) ,; ,
- c. Training on pumps / motor M. Hieronimus SU Completed SO 24-85 oiling
- d. Training on Item III.d.1. B. Spencer SU Completed SO 23-85 Crews trained prior to -
going on shift.
XVI Procedure Adequacy
- a. E0Ps D. Comstock SU Completed NA Rule 4 and E.05 revised. .
- b. Normal Procedures D. Comstock LT To be NA To include Operating Completed Procedures B.1, B.2, B.3, 3/1/86 and B.4.
- c. Identify operator actions M. Hieronimus LT Active NA Problem Feedback Report not specifically Program System initiated by addressed in procedures. Operations 10/10/85.
- d. Monitor operation D. Comstock PE Completed NA procedures during SU.
- e. Evaluate operator D. Comstock SU Completed NA performance during the '
trip.
Is
- q t
i LEGEND: SU = Startup R:quir:d LT' = Long Tenn -
STATUS DATE 11-14-85 PE = Power Escalation OCTOBER 2,1985 TRANSIENT TIME Izuu NA = Not Applicable ST = Short Term - ACTION LIST - .
DESCRIPTION RESPONSIBILITY SCHEDULE STATUS WR No./NCR/ COMENTS ETC. <
XVII Health Physics / Emergency Plan
- a. Health Physics aspects. F. Kellie SU Completed FWK 85-202 No !!ealth Physics impact.
$ b. Emergency Plan B. Spencer SU Completed NA Emergency Plan did not 1 utilization. require activation.
XVIII RCS Overcooling
- a. Tech Spec Review R. Colombo SU Completed NA
- b. B and W Evaluation J. Field SU Completed NA B and W letter, SMUD-85-222, dated Oct. 4, 1985, " Structural Integrity j of Pressure Boundary Components are Suitable for Continued Power Operation.
l XIX Preventive Maintenance Program t for Non-safety Related
]
Equipment
! a. Description of existing R. Lawrence SU Completed NA j program. .
- b. Planned improvements. R. Lawrence LT Requires NA i 11/30/85
- response to NRC.
1 1
1 1