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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] |
Text
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.OSMU-sacnameNTo MUNICIPAL UTsLITY DISTRICT U 6201 S Street. P.O. Box 15830. Sectemento 0.A 958521830.1916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA AGM/NTS88-217 September 14, 1988 U. S. Nuclear Rcgulatory Commission Attn: Document Control Desk Washington, DC 20555 Docket No. 50 312 Rancho Seco Nuclear Generating Station License Wo. DPR-54 NONCONFORMING MATERIALS
References:
(1) NRC Bulletin No. 88-05, dated May 6, 1988 (2) NRC Bulletin No. 88-05, Supp. 1 dated June 15, 1988 (3) NRC Bulletin No. 88-05, Supp. 2, dated August 3,1988 Attention: George Knighton The Sacramento Municipal Utility District hereby submits tesults of the I investigation concerning material supplied by Piping Supplies Inc. (PSI) or l West Jersey Manufacturing (HJM). The investigation was performed in response to the referenced NRC Bulletins and was terminated in accordance with reference (3) on August 3, 1988. This letter complies with the 120-day report requirement contained in reference (1).
i Attachment I is a description of the investigation performed by the District concerning nonconforming material supplied by PSI and HJM. Attachm9nt !!
provides the test results for those potentially nonconforming materials which the District submitted to an independent testing laboratory. Attachment III is a Justification for Continued Operation for those fittings which, based on test results, do not meet material specification requirements (SA-105).
Members of your staff with questions requiring additional information or clarification may contact Steve Crunk at (209) 333-2935, extension 4913.
8809190261 090914 PDR ADOCK 05000312 fMI Il CANCHO SECO NUCLEAR GENERATING STATION D 14440 Tw n Cit.es Road. Hera'd. C A 95638 9799.(2o9) 333 2935
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- George Knighton AGM/NTS88-217 State of California SS County of Sacramento Bob G. Croley, being first duly sworn, deposes and says: that he is Assistant General Manager, Nuclear Technical Services of Sacramento Municipal Utility District (SMUD), the licensee herein: that he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute this document on behalf of said Itcensee.
.f Bo6 G. Croley Assistant Gener Manager Nuclear Technt al Services Subscribed and affirmed to before me on this M ay of LIblO,1988.
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[:/jpah. renamsc.11tiCHDi ESTER H c MO-VA ( Esther H. Hughes y Q,m .g uenwwocesay Notary Public Na,p u, ce t.m, x n. n u w%, .mswww Attachments cc: A. D'Angelo, NRC, Rancho Seco J. B. Martin, NRC, M41 nut Creek i
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l ATTACHMENT I Description of Investigation a
' Attachment I Page 1 of 4 Description of Investigation A. Historv/Investication Methodolocy The District raceived NRC Bulletin 88-05 on May 13, 1988. The Manager of the Material Control Department became the lead indi-vidual for the investigation begun in response to the Bulletin.
Bulletin 88-05, Tablo 1 identified the Dubose company as the "Purchaser" of concern to the District. Rancho Seco's Material Coding and Classification Unit (CCU) began reviewing Purchase Or-ders (Pos), contracts, certified Material Test Reports (CMTRs),
and the heat number log book, as well as Rancho beco's computer-
- ired material tracking system to perform a comprehensive review of all resources which could identify purchases from Dubose with certifications by West Jersey Manufacturing (WJM) or Piping Sup-plies, Inc. (PSI). The CCU also began r3 searching records to discover purchases fr.)m the remaining vendors (other than Dubose) listed in Table 1. The CCU reviewed 631 Pos.
i As a result of the investigation, the Material CCU investigators i realized that heat numbers were an important tool for the identi-fication of suspect material. On June 20, 1988, the District received Supplement 1 to NRC Bulletin 88-05 which also focused upon heat numbers.
1 Once suspect daterial either failed e,esting or was identified as having no extra on hand for test samples (all suspect material l installed), Nuclear Engineering persocnol performed system walk-downs to identify ths specific use of the material.
The District developed a field test procedure (NDEI-0915) to be used by Quality control Engineers for in situ hardness testing.
The investigation continued entil receipt of NUCLEAR NETWORK mes-sage TI 1677 on August 5, 1988, alerting licensees to the suspen-cion of activity concerning Bulletin 88-05. At that time, all l investigative activities associated with NRC Bulletin 88-05 were l terminated.
B. Q1tgovery/Tastino of Suspect Materigl Review of the 631 Por revealed the presence of nine different l heat numbers for material purchased from PSI through Dubone.
Samples for seven of the heat numbers were available for off-sita chemical testing; the remaining two heat numbers had no spares available to use as test samples. All suspect matetial identi-fied in this review was located in TDI diesel genera *or support systems.
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- i Attachment I l Page 2 of 4 +
Five of the seven heat numbers met all SA-105 requirements for :
tensile strength, yield strength, hardness, and chemical composi-tion. Two of the heat numbers did not meet the requirements.
Heat number CTY, which consists of 2einch, 150# carbon steel flanges, did not meet tensile strength requirements. Meat numcor 7611, which consists of 12-inch, stainless steel pipe caps, did not meet yield strength requirements. All the heat numbers met ;
chemical composition requirements. (Results from this testing are included as Attachmen1 ;I.) Potential Deviation from Quality (PDQ) 88-1241 was written upon receipt of test results. Follow-ing a system walkdown to identify specific component us6, Lican-sing notified the NRC as specified by Action 4 of the Bulletin.
The two heat numbers identified in PDQ 88-1241 having no samples I available for testing are CND and CMP. This raterial was pur-chased from PSI through Dubose and is installed on the TDI diesel generators. Heat number CND failed to meet requirements at the Shearon Harris plant, as reported on UUCLEAR NETWORK. The Dis- r trict had not performed in situ testing prior to the receipt of f Supplement 2 of Bulletin 88-05 (August 3, 1988). '
A total of 679 hea* numbers of material supplied by WJH or PSI were either iden*,1fied by Rancho Seco or reported by various l utilities through NUCLEAR NETWORK. The CCU investigated these numbers for the existence of suspect material at Rancho Seco.
Each heat number was cross-referenced against coatracts and other documentation. The CCU discovered material with 12 heat numbers identified by other facilities which were supplied to Rancho Seco by WJM/ PSI through subvendors. The 12 heat numbers were docu-mented on three additional PDQs (88-1315, 88-1337, and 88-1401) as documented below.
PDQ 88-1315 listed three heat numbers (1757, 1090, and 04553).
The material was identified as being installed in the TDI diesel radiator cooling water system. It was supplied by ITT Grinnell as part of the diesel radiatort therefore, no spares are avail-able for chemical testing. The District had not performed in situ hardness testing by August 3, 1988.
PDQ 88-1337 listed four heat numbers (A39, A91, E143,3, and A79).
The material was identified as being installed in the TDI diesel fuel oil day tanks. It was supplied by TransAmerica Delaval with attached piping; therefore, no spares are available for chemical testing. The District had not performed in situ hardness testing by August 3, 1988.
. Attachment I !
Page 3 of 4
- PDQ 88-1401 listed five neat numbers (R6842, 04096, 41687, 04020, !
I and A101). The matarial was identified as being installed on
, the diesel generator auxiliary skids. (A detailed system walk-
- down to identify the specific use of the material had not been i performed by August 3, 1988.) The material was supplied by i
TransAmerica Delaval with attached piping assembliest therefe**,
no spares are available for chemical testing. The Distrj not performed in situ hardness testing by August 3, 198' 1
I The field hardness test procedure (NDEI-0915) wnG in t te sw j and approval cycle when NRC Bulletin 88-05 activities s ;s-pended; therefore, no in situ hardness testing was performed j prior to August 3, 1988.
I C. Engineerino Evaluation of_tionconformina Matgr(al
]
As previously stated, two heat numbers of the material tested at
- an independent laboratory did not meet requirements.
Failed hnat number 7611 consists of 12-inch, schedule 40 stain-l less steel pipe caps. The entire stock is available (none are
- installed) and there are no system concerns. The stock has been l placed on hold.
]
Failed heat number CTY consists of eight 2-inch, 150# carbon steel flanges. Four of these flanges are installed in the fuel oil piping for the "A" TDI dierel generator. A fifth flange was scrapped and three have not been issued. Nuclear Engineering evaluated the test results and the use of the flanges in the di&-
, sel fuel oil systen and determined that interim use of the four j flanges is acceptable. The flanges should, however, be replaced i at a future outage with material having proper certifications.
J (See Attachment III for a Justification for continued operation.)
D. Failed /St'spect Material Chain of Purching The following table lists the chain of purchase for failed or suspect (but not tested prior to August 3, 1988) material identi-
- fied in the course of the investigation.
lifA1_1 Rescriptinn Chain of_Purchan_t CND 4-in, 150f flange PSI -> Dubose -> SMUD 6-in, 1500 flange CMP 6-in, 1509 flange PSI -> Dubose -> SMUD
t Attachment I Page 4 of 4 !
Heat i Description chain of Purchama '
i CFY 2-in, 1500 flange PSI -> Dubose -> SMUD (
t 7411 12-in, SS pipe cap PSI -> Dubose -> SMUD !
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1757 8-in, 1506 flange MJM -> ITT Grinnell -> SMUD l l
1090 4-in, 1500 flange WJM -> ITT Grinnell -> SMUD l I
04553 6-in, 1500 flange WJM -> ITT Grinnell -> SMUD A39 3-in, 1500 flange WJM -> Capitol Pipe & Steel -> r TransAmerica Delaval -> SMUD f l l A91 2-in, 1509 flange WJM -> Capitoi Pipe & Steel -> L I TransAmerica Delaval -> SMUD E1413 1 1/2-in, 1500 flange WJM -> Capitol Pipe & Steel -> f TransAmerica Lelaval -> SMUD !
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A79 1-in, 1506 flange WJM -> Capitol Pipe & Steel ->
TransAmerica Delaval -> SMUD R6442 3-in, 1506 flange WJM -> TransAmerica -> SMUD f
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04096 4-in, 1506 flange WJM -> TransAmerica -> SMUD (
41687 8-in, 1500 flange WJM -> TransAmerica -> SMUD 04020 5-in, 1500 flange WJM -> TransAmerica -> SMUD A101 5-in, 1500 flange WJM -> TransAmerica -> SMUD l 1 I I
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ATTACHMENT II Laboratory Test Results !
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t.ABORATORY CERTIFIC ATE Anamet Laboratories, Inc.
m . . n .- - . u a e . ~ ~ e. e w ,o o i. ........,, i.,,,......,,
Laboratory Number: 688.138 Purchase Order RQ-88-08-26278 S/N: 48961 June 13, 1988 Date Submitted: June 21, 1988 Date Reported:
Saoramento Municipal Utility Dist.
Rancho Seco Nuclear Generator Station Atta: Jim Holbrook 14440 Twin Cities Road Ke sid, CA 95638-9799 __
SUBJEC*_
Seven fittings were submitted for chemical analysis, tensile1. and hardness testing. The samples ass identified in Appendix Recuirements SPECTRCCHEMICAL ANALYSIS A5TM A 152-du, Iruported in wt! 5) F304 h Max.
Heat Heat Mark: #104839 #A10u0 0.01 - 0.08 (C) 0.06 18.00 20.00 Carbon 18.95 18.81 Chromium (Cr) 1.57 - 2.00 Mangenese (Mn) 1.64 Information (Mo) 0.24 0 37 11.00 Molyedenum 10.45 8.00 (NL) 10.51 0.040 Nickel 0.025 0.022 -
1.00 Phospnorus (?) 0 30 (31) 0.59 0.030 S licon O.018 0.024 .
Sulfur (S) ,
, _ Requirements X57M A uC3-au, WP304
, Min. Max.
Heat Merk: A7611
- 0.08
(
(C) 0.006 18 0 20.0 Carton 19 63 2.00 Chromium (Cr) 1.05 Fanganese (Mn) 0.15
- nformatten Molybdenum (Mo) 8.00 11.0 (N1) 9 96 0.045 Nickel 0.024 1.00 Phosphorus (P) 0.50 (Si) - 0.030 tilicon (5) <0.005 f ulfur lff
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LA80R Af oRY CERTIPic ATE Anamet Laboratories, Inc.
HaTCaiO. L' AWomesta Lab. No. 688.138 Page 2 Recuirements SPECTRCCHEMICAL ANALYSIS ( coritinu ed ) ASTM A 105-53.
-Su Min. Mar.
Heat Heat Heat f4s rk : dCFW
- AXSX du1971_
(A1) <0.005 <0.005 0.03 Information A'uminum 0.18 0 34 - 0 35 faroon ( C) 0.28 0.11 Information (Cr) 0.04 0.12 Chrcmium 0.0u 0.18 0.20 Information Copper ( Cu) O.88 0.60 1.05 Manganese (Mn) 0 99 1.23' Information (Mo) <0.005 0.02 0.05 Holyedenum 0.03 0.09 0.13 Information Nickel (N1) 0.009 - 0.040 Phospnorus (P) 0.007 0.013 0.35 (S1) 0.12 0.23 0.21 -
Silicon 0.019 0.013 - 0.050 Scirur (S) 0.010 Information (V) <c.005 0.06 <0.005
'la n a dium
- Product Analysis - Requirements: Manganese - 0.505 Minimuri and 1 35 % Maximum. Beauirements~
A5ME SA-105,
'77 Ed.,
78 Add.
Min._ Max.
< ark: Heat
- CTY 0.04 Information Aluminum (A1) - 0.35 Iarton (C) 0.20 Information (Cr) 0.04 Chromium 0.02 information Copper ( Cu ) 0.60 1.05 Manganese (Mn) 0.93 Information Molyoconum <0.005
( Mo )
- 0. 0 ? Information Nickel (M1) - 0.0u0 Phosphorus (P) 0.019 - 0.35 Silicon (51) 0.21 - 0.050 Sulfur (S) 0.019 a.fr
l LA8oR AToRY CE ATiflC ATE Anemet Laboratories, Inc s*.tvw A A0. C A UPomest A Page 3 Lab. No. 688.138 ;
1 Requirements TENSILE TES;
~~ ASTM A 152.gu, F30u Mark: Heat Heat
- 1G4839 #A1040 Diameter of Specimen: 0 357 In. 0 35 4 In .
0.100 Sq.:n. 0.0984 Sq.In.
Area Tensile Strength: Su300 Psi 76700 Psi 75000 Psi Min.
Yield Strength f 0.2% offset: 38800 Psi 3u300 Psi 30000 Psi Min.
Elongation in 40 Gage: 61 1/25 65% 301 Min.
Reduction of Area: 70.4% 74.7% $01 Min.
Recuirements A5TN A 403-64 WP304 Mark: Heat
- 7611 Diameter of Specimen 0.249 Inches Area:
0.0487 Square Inches 71nsile Strength: 79600 Psi 75000 Psi Min.
~
Yield Strengt h 0.25 Offset: 28500 Psi 30000PsiMih El ngetto in Ga g el 97 455 Min.
Roduction of Area: 85 25 35% Min.
Requirements _
A5ME 5A-105, Marks Heat '77 Ed.,
ACTY
'73 Add.
Diameter of Specimen: 0 349 Inches 0 In:hes A" y -
Tensile Strength: 66400 Psi 70000 Psi Min.
Yield Strengtn 0.2% offset or 36000 Psi Min.
0 5% E.U.L: u1800 Psi 225 :41 n .
Elongation in iD Cages 36 1/24 59 65 305 Min.
Reduction of Area:
Py3 &h' i 1
T'.-i LAgo A AfoRY CERflFICATE Anarnet Laboratories. Inc.
naVWam0 C ALipome.i A Page 4 Lab. No. 68 8.138 TENSILE TEST (continued)
Mark Heat Heat Heat 4ASXS #41971 dC[W Diameter of Specimen: 0.251 In. 0 349 In. 0 356 Ir..
0.0495 Sq.In. 0.0957 Sq.:n. 0.0995 Sq.In.
Area 79800 Psi 84100 Psi gu200 Pai Tensile Strength:
Yield Strength i 0.2% offset 42900 Psi 55400 Psi 51000 Psi Clongation in 4D Oage: 32% 27% 23%
Roduction of Area: 64.2% 65 9% 50.7% .
Requirements: Ultimate Tensile Strength - 70000 Psi Minimum, Yield Strength 8 0.2f Of fset - 36000 Psi Minimum, Elongation in uD onge - 22% Minimum and Reduction of Area - 301 Minimum per ASTM A 105-33, -84 3RINELL HARDNESS TEST (3GC0 <g. load; 10mm ball)
Soecimen Result Ht. #AXSX 152 HB Ht. #41971 183 HB Mt. #CTW 183 HS Mt. dCTY 137 HS Requirement: 187 HB Max. per ASTM A 105-83, -84 and ASME SA-105, '77 Ed. with '78 Addenda.
7his testing was performed in accordance with the purchase order and, with the exception of the tensile results on Mt. #7611 and #CTY, the results meet the listed requirements.
Submitted by:
.C Ohu~
E. A. foreman 3c/bn6*738 Manager, Ouality Control Y ($
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LAsom Af oRY oERTIFICATE Anamet Laboratories, Inc.
H AVWA RD, C A(lPQ ANie Lab. No. 688.138 Page 5 APPENDIX _1 Item No. 1, Distribution / Stock Code du72501, 1 each Flange, slip-On, 3F, 6" 15Cv S.S. ASTM A 182, r30s. Heat 4103839 (198t), SMUD Stock Iode 8702495 Item No. 2, Distribution / Stock Code du72501, 1 each Pipe Cap, 12" Sch.
40 S.S. ASTM A 403, WP304 Suttweld, Heat #7611 (1984),# SMUD Stock '
Code
~^
N 1 each riange, slip-on, It em No . 3, Distribution / Stock Code duT2501, 3" 1500 RF, S.S., ASTM A 182, F304, Heat dA1040 (1984), SMUD Stock Code 702512.
It em No . 4, Distribution / Stock Code #472501, 1 each Cap, Pipe, 8" Sch.
80 SW CS, ASTM A 105-84, Heat #AXSX, SMUD Stock Code #036926.
1 each, Flante, slip-on, Item No. 5, Distribution / Stock Code 4u72501,dCTV Carbon Steel, SMUD Stock 3" 1500 RT, ASTM A 105-83, Sch. So, Heat Code 70127 .
1 each, riange. 2" -
Item No. 6, Distribution / Stock Code #472501, #CTY, carbon steel 77 150d. SW RF, ASME III ND (C13) SA-105, Heat edition - 78 Addenda, SMUD Stock Code #1133u5.
Ites No. 7, tock Code su72501, 1 each Flange, slip-on, 5" - 1504 RF, CS, ASTM A 105, Heat #41971 (198u), SM')D stock code 1702395 fy Sff
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ATTACHMENT III Justification for Continued operation
y _
Attachment III Page 1 of 2 Justification for Continued Operation This Justification for Continued Operation was previously submit-ted with District letter CEO 88-092.
A. Purcose Four flanges were installed in the "A" TDI diesel generator fuel oil system which do not meet specification requirements. Engi-neering determined that operation of "A" TDI diesel generator may continue with these flanges in the fuel oil system.
The flanges were identified as part of an investigation being performed in response to NRC Bulletin 88-05. This Bulletin deals with nonconforming materials supplied by West .7ersey Manufactur-ing and Piping Supplies, Incorporated.
B. Affected System / Safety Function of Affected System This Justification for Continued Operation affects the Emergency Generator System (USAR Section 8.2.3.1.2), specifically TDI die-sel generator GEA2.
The safety function of the Emergency Diesel Generators is to automatically supply the associated 4160V AC Nuclear Service buses upon loss of voltage or SFAS actuation. The Emergency Die-sel Generators supply all AC loads necessary to ensure continued operation of essential reactor and station auxiliary equipment.
The District installed the TDI diesel generators to support the additional electrical loads resulting from "TMI modifications."
The Emergency Diesel Generator System consists of two independent and redundant trains with a Bruce-GM diesel (GEA/GEB) and a TDI diesel (GEA2/GEB2) in each train. In Train A, GEA supports bus 4A and GEA2 supports bus 4A2. Similarly, in Train B, GEB sup-ports bus 4B and GEB2 supports bus 4B2. Each train alone is suf-ficient to accomplish the safety function.
C. Effects on Safety Function / Analysis of Effects The heat number of the material in question is CFY. This mater-ial consists of 2-inch, 150# carbon steel flanges. These flanges are ASME III ND (C13), SA-105 material. A total of eight flanges with heat number CFY were received on site; three are in stock, one was scrapped, and the remaining four were installed in the "A" TDI diesel generator fuel oil system (two in each of two lines).
Attachment III Page 2 of 2 The maximum calculated combined pipe stress level for code com-pliance for the "A" TDI diesel fuel oil lines is less than 6000 psi. This figure results in a stress ratio on the fuel oil lines of less than 0.25 (Actual Stress / Allowable Stress). The maximum allowable pressure for a 150#-rated flange at a design tempera-ture of 125 0 F is approxima*ely 255 psig, whereas the design pres-sure of the system is only 100 psig. Hence, there exists a con-servative margin of safety of over 50%.
The actual tensile strength of the sample was 66,400 psi (see test results, Attachment II). The required tensile strength is 70,000 psi. This results in a reduction in tensile strength of 5.14%. Based on this slight reduction in strength of the flange, when compared to the conservative margin of safety which remains, Engineering has determined that an adequate margin of safety exists to assure the integrity of the fuel oil system and justify the interim use of the flanges. The final disposition is to replace the degraded flanges with materials having proper certi-fication at the next availabic outage.
D. Summary Four flanges were installed in the "A" TDI diesel generator fuel oil system which do not meet specification requirements. The District identified these flanges as part of the investigation required by NRC Bulletin 88-05.
This Justification for Continued Operation affects the Emergency Generator System TDI diesel generator GEA2. The TDI diesel gen-erators support the additional electrical loads resulting from "TMI modifications."
The heat number of the material in question is CFY. This mater-ial consists of 2-inch, 150# carbon steel flanges. These flanges are ASME III ND (Cl3), SA-105 material. Based on the minimal re-duction in measured strength of the flange when compared to the conservative margin of s&fety which remains, the Engineering evaluation concludes that an adequate margin of safety exists to justify the interim use of the flanges.