ML20054G584
Letter Sequence Other | |
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Administration Questions
Results Other: 05000287/LER-1982-006, Forwards LER 82-006/01T-0.Detailed Event Analysis Encl, 05000287/LER-1982-006-01, /01T-0:on 820430,visual Insp of Internal Auxiliary Feedwater Header in Both Steam Generators Revealed Header Deformation.Caused by Inadequate Design to Withstand Thermal & Pressure Forces.External Header to Be Installed, 05000346/LER-1982-019, Forwards LER 82-019/01X-1, 05000346/LER-1982-019-01, /01X-1:on 820419,during Steam Generator Eddy Current Insp,Some Generator Tubes Adjacent to Auxiliary Feedwater Header Showed Potential Interaction W/Header Support Sys.Caused by Collapse of Steam Bubble in Header, ML20027C424, ML20052A442, ML20053D846, ML20053E437, ML20053E475, ML20054G584, ML20054H506, ML20054J484, ML20058J620, ML20062C407, ML20062N798, ML20065C137, ML20079R108, ML20261N102 | |
MONTHYEARML20261N1021981-06-0505 June 1981
[Table View]Piping Isometric:Main Steam System Ctmt Bldg Steam Gen 1-2 Project stage: Other ML20052A4421982-04-20020 April 1982 RO 82-10:on 820419,insp of B once-through Steam Generator Revealed Deformations Similar to Deformations at Davis Besse.Generator a Will Be Inspected 820420.Analysis Details to Be Forwarded When Completed Project stage: Other ML20052H4161982-05-10010 May 1982 Summary of 820423 Meeting W/Utils in Bethesda,Md Re Auxiliary Feedwater Header Damage in Certain B&W Plants. Agenda Encl Project stage: Meeting 05000287/LER-1982-006-01, /01T-0:on 820430,visual Insp of Internal Auxiliary Feedwater Header in Both Steam Generators Revealed Header Deformation.Caused by Inadequate Design to Withstand Thermal & Pressure Forces.External Header to Be Installed1982-05-14014 May 1982 /01T-0:on 820430,visual Insp of Internal Auxiliary Feedwater Header in Both Steam Generators Revealed Header Deformation.Caused by Inadequate Design to Withstand Thermal & Pressure Forces.External Header to Be Installed Project stage: Other 05000287/LER-1982-006, Forwards LER 82-006/01T-0.Detailed Event Analysis Encl1982-05-14014 May 1982 Forwards LER 82-006/01T-0.Detailed Event Analysis Encl Project stage: Other ML20054G9991982-05-20020 May 1982 Submits Details Re Mod of once-through Steam Generator Auxiliary Feedwater Header,Per NRC Request at 820518 Meeting.Sketches Encl Project stage: Meeting ML20054G5841982-05-20020 May 1982 Submits Addl Info Re Auxiliary Feedwater Header Mod,Per NRC Request.Existing Headers Have Become Distorted Since Original Fabrication.Headers Will Be Replaced & Stabilized to Prevent Further Unacceptable Damage to Steam Generators Project stage: Other ML20053E4751982-05-21021 May 1982 Requests Addl Info in Response to Listed Questions Re Util Responses to Aslab 820415 Memorandum & Order Concerning Repair & Future Operation of HPI Nozzles.Response Requested within 20 Days of Receipt of Ltr Project stage: Other ML20053E4371982-05-21021 May 1982 Submits Agreements Reached During 820518 Discussions Re Anticipated Mods to Steam Generator Auxiliary Feedwater Distribution Headers.Written Work Scope for Attaching Nozzle Flange Prior to Work on Steam Generator Expected Project stage: Other 05000346/LER-1982-019-01, /01X-1:on 820419,during Steam Generator Eddy Current Insp,Some Generator Tubes Adjacent to Auxiliary Feedwater Header Showed Potential Interaction W/Header Support Sys.Caused by Collapse of Steam Bubble in Header1982-05-24024 May 1982 /01X-1:on 820419,during Steam Generator Eddy Current Insp,Some Generator Tubes Adjacent to Auxiliary Feedwater Header Showed Potential Interaction W/Header Support Sys.Caused by Collapse of Steam Bubble in Header Project stage: Other 05000346/LER-1982-019, Forwards LER 82-019/01X-11982-05-24024 May 1982 Forwards LER 82-019/01X-1 Project stage: Other ML20053D8461982-05-26026 May 1982 Interim Deficiency Rept Re Design of Internal Auxiliary Feedwater Header in B&W Steam Generator.Probable Cause of Deformation Is Header Inability to Withstand Temp & Pressure.External Ring to Be Added.Next Rept Due 820730 Project stage: Other ML20054J0091982-06-0909 June 1982 Responds to 820608 Telecopy Re Preliminary Description of Stabilization of Steam Generator Internal Auxiliary Feedwater Headers.Util Can Proceed W/Internal Header Stabilization as Described Based on Review & 820609 Telcons Project stage: Other ML20054H5061982-06-21021 June 1982 Requests List of Specific New B&W Steam Generator Auxiliary Feedwater Header Design Details Required for NRC Design Review of New Scheme to Supply Auxiliary Feedwater to Steam Generators Project stage: Other ML20054J4841982-06-23023 June 1982 Requests Addl Info Re Auxiliary Feedwater Header Repair, Reported in LER 82-019,Revision 1.Info Needed 10 Days Prior to Scheduled Restart Project stage: Other ML20054J4821982-06-23023 June 1982 Requests Addl Info Re Auxiliary Feedwater Header Repair, Reported in LER 82-10.Response Should Be Provided 10 Days Prior to Scheduled Restart Project stage: Other ML20062D6171982-07-0101 July 1982 Evaluation,Repair & Replacement of Damaged Internal Auxiliary Feedwater Header at Davis Besse 1,Oconee 3 & Rancho Seco Project stage: Other ML20062C3791982-07-30030 July 1982 Forwards Application for Amend to License NPF-3,revising Tech Spec Table 3.7-3 to Reflect Steam Generator Auxiliary Feedwater Header Mod.Class III Fee Encl Project stage: Request ML20062C3941982-07-30030 July 1982 Application for Amend to License NPF-3,revising Tech Spec Table 3.7-3 to Reflect Steam Generator Auxiliary Feedwater Header Mod.Identification of Snubbers Removed & Relocated During Mod to Header Encl Project stage: Request ML20062C4071982-07-30030 July 1982 Tech Spec Table 3.7-3 Re safety-related Hydraulic Snubbers. Safety Evaluation for Auxiliary Feedwater Header Replacement Encl Project stage: Other ML20062D5971982-08-0303 August 1982 Forwards BAW-1732, Evaluation,Repair & Replacement of Damaged Internal Auxiliary Feedwater Header at Davis Besse 1,Oconee 3 & Rancho Seco, Per 820624 Meeting W/Nrc in Bethesda,Md & NRC 820623 Request.Response Summary Submitted Project stage: Meeting ML20058J6201982-08-0606 August 1982 Forwards Addl Info Re Auxiliary Feedwater Header Repair,In Response to NRC 820623 Request.One Oversize Drawing Encl. Aperture Card Is Available in PDR Project stage: Other ML20062N7981982-08-16016 August 1982 Forwards Info Re Auxiliary Feedwater Header/Steam Generator Mod,In Response to NRC Questions in .Also Discusses Potential for Crack Propagation in Retired Header. Util Will Propose Changes to Tech Specs within 30 Days Project stage: Other ML20065C1371982-09-16016 September 1982 Advises of Delay in Submittal of Proposed Tech Specs Re Auxiliary Feedwater Header Insps Due to Intensive Resource Requirements to Start Up from Refueling Outage.Submittal Expected by 821029 Project stage: Other ML20027C4381982-09-29029 September 1982 Safety Evaluation Supporting Resumption of Power Operations Following once-through Steam Generator Repair & Emergency Feedwater Sys Mods Project stage: Approval ML20027C4241982-10-0606 October 1982 Discusses NRR Actions Taken Under Task Interface Agreement 82-20 for Steam Generator Auxiliary Feedwater Header Damage.Licensee Authorized to Resume Power Operation at Oconee 3 Project stage: Other ML20079R1081983-06-17017 June 1983 Part 21 Rept Re Adequacy of Fittings Supplied by Tube-Line Corp Through Capitol Pipe & Steel Products Co for Use on New Auxiliary Feedwater Headers of Steam Generators.Flanges Not heat-treated as Required by Matl Specs Project stage: Other ML20024D9811983-07-28028 July 1983 Advises That Responsibility for Evaluating Proposed Actions Re IE Bulletin 83-02 Concerning Recirculation Sys Pipe Cracks Transferred to Div of Licensing Project stage: Other 1982-06-23 |
ML20054G584 | |
Person / Time | |
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Site: | Rancho Seco |
Issue date: | 05/20/1982 |
From: | Rodrigues R SACRAMENTO MUNICIPAL UTILITY DISTRICT |
To: | Eisenhut D, Eisenhut D Office of Nuclear Reactor Regulation |
References | |
TAC-48349, TAC-48384, NUDOCS 8206220086 | |
Download: ML20054G584 (4) | |
Similar Documents at Rancho Seco | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M8851999-10-0808 October 1999
[Table view]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 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 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 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 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) 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 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 IR 05000312/19980021998-07-15015 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 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation 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 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 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 1999-08-31 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
[Table view]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 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 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 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 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) 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 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 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 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 ML20029E4601994-05-12012 May 1994 Forwards Response to NRC Bulletin 94-001, Potential Fuel Pool Drain-Down Caused by Inadequate Maint Practices at Dresden Unit 1. Util Plans to Move Spent Fuel Into Proposed Rancho Seco ISFSI by 1998 ML20149E3971994-05-10010 May 1994 Forwards Re Updated Decommissioning Cost Estimate for Rancho Seco & Attached Rept by Tlg Engineering,Inc. W/Svc List NL-94-008, Forwards Endorsement 118 to Nelia Policy NF-0212 & Endorsement 106 to Maelu Policy MF-00751994-04-28028 April 1994 Forwards Endorsement 118 to Nelia Policy NF-0212 & Endorsement 106 to Maelu Policy MF-0075 ML20029D3531994-04-28028 April 1994 Forwards Documents S11-25-003, Update of 1991 Decommissioning for Rancho Seco Nuclear Generating Station 1999-07-07 Category:TELEGRAMS-CORRESPONDENCE MONTHYEARML20024E3281983-08-0303 August 1983
[Table view]Telecopy of Suppl to 830715 Response to NRC Re Emergency Preparedness Deficiencies.Outline of Training Modules for Emergency Plan Implementing Procedures Encl ML20054G5841982-05-20020 May 1982 Submits Addl Info Re Auxiliary Feedwater Header Mod,Per NRC Request.Existing Headers Have Become Distorted Since Original Fabrication.Headers Will Be Replaced & Stabilized to Prevent Further Unacceptable Damage to Steam Generators ML20150F3381979-07-28028 July 1979 Notifies of Change of Location for 790801 Hearing in Sacramento,Ca 1983-08-03 Category:UTILITY TO NRC MONTHYEARML20059L5431990-09-20020 September 1990
[Table view]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 ML20055J0331990-07-25025 July 1990 Notifies of Change in Operator/Senior Operator Status. Operators Terminating Employment & No Longer Require License ML20055J0311990-07-25025 July 1990 Forwards fitness-for-duty Performance Data for Facility from 900103-0630 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 ML20043G9521990-06-12012 June 1990 Notifies of Organizational Changes.Svc List Should Be Revised as Listed ML20043G5701990-06-12012 June 1990 Forwards NSHC for long-term Defueled Condition of Plant for Security Plan,Per Util .As Discussed W/Nrc During Telcon,Determination Made That NSHC Needed to Be Processed in Support of Security Plan ML20043E8191990-06-0606 June 1990 Requests Withdrawal of 900510 Request for Exemption from GDC 17, Electric Power Sys. Util Understands That Formal Exemption Not Required,Based on Discussions W/Nrc.Info on Plans Re Diesel Generator Operation Also Provided ML20043E1691990-05-25025 May 1990 Forwards Refinement List of Tech Specs Applicable in Defueled Condition,Per .Unless NRC Differs W/ Approach,Conduct of Activities in Defueled Condition Will Proceed Until Amend 182,Rev 1 Approved 05000312/LER-1990-001, Forwards Errata to LER 90-001-00,re Inoperable Radioactive Gaseous Effluent Monitoring Instrumentation Not Reported in Semiannual Radioactive Effluent Release Rept Due to Procedural Deficiencies,To Include Rept Date1990-05-0202 May 1990 Forwards Errata to LER 90-001-00,re Inoperable Radioactive Gaseous Effluent Monitoring Instrumentation Not Reported in Semiannual Radioactive Effluent Release Rept Due to Procedural Deficiencies,To Include Rept Date ML20042F3421990-04-26026 April 1990 Forwards Long Term Defueled Condition Security Plan.Plan Withheld (Ref 10CFR2.790) ML20042F6121990-04-26026 April 1990 Forwards Rancho Seco Emergency Plan Change 4 Long-Term Defueled Condition. New Plan Includes Provisions Necessary for Protection of Onsite Personnel & for Protection of Public Via Communication W/Offsite Agencies ML20034C4081990-04-24024 April 1990 Forwards Rev 5 to Sections 1 & 8 of Plant Emergency Plan,Per NRC Requesting Two Changes ML20042E0941990-04-10010 April 1990 Advises That Util Intends to Submit EIS Associated W/Plant Decommissioning After Submittal of Decommissioning Plan ML20033G5981990-03-30030 March 1990 Forwards Mods to Plant Operator Training Program Submitted on 891228,in Response to Requesting Addl Info ML20012E2211990-03-23023 March 1990 Forwards Amend 18 to Physical Security Plan.Encl Withheld (Ref 10CFR73.21) ML20012B8731990-03-0909 March 1990 Provides Status of Inservice Insp & Inservice Testing Programs.Util Does Not Intend to Continue Normal Test Schedule for Pumps & Valves in Sys Not Required by Tech Specs to Be Operable NL-90-030, Forwards Endorsements 94,95 & 96 to Nelia Policy NF-212, Endorsements 82,83 & 84 to Maelu Policy MF-75,Endorsements 10 & 11 to Nelia Certificate N-49 & Maelu Certificate M-49, Respectively & Endorsements 5,6,14 & 15 to Master Policy 11990-02-21021 February 1990 Forwards Endorsements 94,95 & 96 to Nelia Policy NF-212, Endorsements 82,83 & 84 to Maelu Policy MF-75,Endorsements 10 & 11 to Nelia Certificate N-49 & Maelu Certificate M-49, Respectively & Endorsements 5,6,14 & 15 to Master Policy 1 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 ML20033F1661990-02-14014 February 1990 Forwards Revised Pages to Sections 1-8 of Rev 4 to Emergency Plan,Per NRC 900206 Telcon Request.Summary of Changes Listed,Including Deletion of Ref to Accidents Not Exceeding Alert Classification ML20006F1451990-02-13013 February 1990 Revises 891212 Exemption Request Re Requirements for Simulation Facility Training & Testing.Requested Exemptions Commensurate W/Nuclear Safety Requirements W/Plant in Defueled Condition ML20033E3471990-02-12012 February 1990 Advises of Change in Operator/Senior Operator Status for H Coomes,Effective 900205 ML20006D6771990-02-0808 February 1990 Requests Limited Scope Exemption from Requirements of 10CFR26 Fitness for Duty Programs.Util Currently Implementing Program in Accordance W/Enforcement Discretion Granted in Commission NL-90-023, Forwards Endorsements 95 & 83 to Nelia Policy NF-212 & Maelu Policy MF-75,respectively,Endorsements 10 & 11 to Certificates N-49 & M-49 & Endorsements 5,6,14 & 15 to Maelu Policy 11990-02-0707 February 1990 Forwards Endorsements 95 & 83 to Nelia Policy NF-212 & Maelu Policy MF-75,respectively,Endorsements 10 & 11 to Certificates N-49 & M-49 & Endorsements 5,6,14 & 15 to Maelu Policy 1 ML20006D0201990-02-0202 February 1990 Requests Exemption from Simulator Training & Testing Requirements of 10CFR55.11 While Plant in Defueled Mode.In Present Defueled Condition,Use of Simulator to Ensure Skills & Abilities Re Plant Operations Irrelevant ML20011E1711990-01-30030 January 1990 Forwards Rev 0 to NDP-039, Sys Required to Support Defueled Mode, & Rev 1 to TSAP-4124, Sys Layup Program. Sys Categories at Facility Include,Operable,Available,Prudent to Operate & Layup ML19354E4441990-01-22022 January 1990 Advises That Actions Requested by NRC Bulletin 89-003 Not Applicable to Station Since Station Currently in Defueled Shutdown Condition.Util Took Action to Disallow Temporary Storage of Fuel Assemblies W/O Approval of Reactor Engineer ML20005G2571990-01-12012 January 1990 Responds to NRC Re Violations Noted in Insp Rept 50-312/89-18.Violation a Denied & Violation B Ack.Corrective Actions:Controls for Environ Pollution Reanalyzed I-131 in Water Sample Using Correct Efficiency Factor for Instrument ML20005F1791990-01-0808 January 1990 Responds to NRC Re Violations Noted in Insp Rept 50-312/89-15.Util Denies Alleged Violations on Basis That Removing Auxiliary Fuel Handling Bldg to Facilitate Testing Performed Considered Consistent W/Plant Work Practices ML20005F0351990-01-0303 January 1990 Certifies Implementation of fitness-for-duty Rule,Per 10CFR26 ML20005E4121989-12-27027 December 1989 Suppls NRC Summary of Util Plans to Close & Decommission Facility & Identifies Subjs Needing Further Discussion.Four Phases Listed,Including First Phase Re Relief from Existing Commitments ML20005D8751989-12-0707 December 1989 Forwards Util Cooling Tower Basin Sludge Sample.Activity Confined to Natural Isotopes & Cs-137 at Level of 2.058E-7 Uci/Gm,Based on Gamma Spectroscopy & Tritium Analysis ML20005F2561989-10-23023 October 1989 Forwards 1989 Annual Plant Exercise Scenario,Per IE Info Notice 85-055.Counties & State Will Not Be Officially Participating Since Biennial Participation Evaluted Last Yr 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 1990-09-06 |
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E SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street Box 15830, Sacramento, Califomia 95813; (916) 452-3211 May 20, 1982 ATTN: Mark Padovan DIRECTOR OF NUCLEAR REACTOR REGULATION ATTN: DARRELL G EISENHUT, DIRECTOR DIVISION OF LICENSING U S NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 DOCKET NO. 50-312 LICENSE NO. DPR-54 AUXILIARY FEEDWATER HEADER MODIFICATION (SUPPLEMENT)
This letter supplements the response of our previous letter pertaining to details of the Auxiliary Feedwater Header Modification.
Mr. M. Padovan re-quested R. Colombo to furnish an " overview" concerning the above mentioned modifications today.
This letter should provide that request.
The existing internal Auxiliary Feedwater Headers have become distorted since original fabrication. They must be replaced in order to provide the capability to inject Auxiliary Feedwater into the Steam Generators. They must also be stabilized to ensure that they remain in place and cause no further unacceptable damage to the internals of the Steam Generators.
The internal Auxiliary Feedwater Header will continue to serve as an extension of the Upper Cylindrical Baffle (Steam Shroud) to prevent high velocity steam crossflow near the mid-span of an unsupported length of steam generator tube.
The replacement design incorporates an external Auxiliary Feedwater Header, and six new penetrations through the Steam Generator Shell and through the Upper Cylindrical Baffle (Steam Shroud).
Stabilization of the internal Auxiliary Feedwater Header requires access at several points around the header.
In order to ensure that loose parts are eliminated or captured, access is required to eight equally spaced header support / fixation locations around the Steam Generator. Two of these locations are accessible from the Steam Generator secondary side manway.
In full consideration of all of the above, it is prudent to add six penetra-tions to the Steam Generators in order to:
ON
- 1) provide Auxiliary Feedwater injection,
- 2) provide access for internal header stabilization,
- 3) provide access for header support bracket and pin stabilization or removal.
P f h p 11 O
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8206220086 820520 PDR ADOCK 05000312 P
PDR AN ELECIRlt SYSTEM SERVING MORE THAN 600 000
'N THI HfAPi 0F cal!FOFNeA These six new penetrations in each Steam Generator will be machined through the Steam Generator Shell and through the Upper Cylindrical Baffle (Steam Shroud). They will be machined to accept a suitable gasket and a flanged closure. A ring of threaded holes will be drilled and tapped into the Steam Generator Shell to provide closure at each penetration.
If you have any questions concerning this reply, please contact Ron Colombo at Rancho Seco.
gfyv. 4)
R. J. Rodriguez Manager of Nuclear Operations