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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
Y s
r e
" OWNERS GROUP
- 1 Arkansas Power & IJght Company ANOw1 Toledo Edison Company Dawes Sesse Duke Power Company Orence 9,3. 3 7_ - VaNey Aanherty Sellefonte 9,2 1 Pterede Power t_m_ Crystal INwer 3 r-, washington Pubik Power Supp#y WNPI GPU Nuclear Corporasson Thef-9 System Sacramente htunkipal UtNesy Desertti stancho Seco Sabreck & Macos Company g gglg Working Together to Economically Provide Reliable and Safe Electrical Power Suite 220 ;
January 9, 1986 7910 Woodmont Avenue !
m Bethesda, Maryland 20814 (301)951-3344 Mr. D. G. Eisenhut Deputy Director Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
B&WOG RRG Meeting related to 12/26/85 Rancho Seco Event
Dear Mr. Eisenhut:
The purpose of this letter is to formally document the presentation made to the NRC at your request by the B&WOG Regulatory Response Group on January 8, 1986. A copy of the information presented is attached.
The B&WOG appreciated the opportunity to meet with the NRC to present our preliminary assessment of the generic implications of the recent Rancho Seco transient. We believe the meeting was beneficial.
The actions requested of the B&WOG and agreed upon at the conclusion of the meeting were as follows:
- 1. Efforts are to continue to develop an understanding of the root cause of the Rancho Seco transient.
- 2. Review will be made of the various types of ICS and NNI electrical malfunctions and failures that can lead to problems such as the Rancho Seco transient.
- 3. Near-term training is to be conducted to make all operators aware of the Rancho Seco transient and to review the required actions for dealing with a similar event.
- 4. The B&WOG will submit by February 5, 1986, an Owners Group letter presenting the program to be followed by the operating plants as a result of the January 16, 1986 Executive Committee meeting.
8601140300 860109 ,, _ o. caurcuritim (i.tr =2r>
l PDR ADOCK 05000312 se tu. aounstoni g PDR ass truonAs) arcss (PARA) 0Oh l
ros (w. REGAN)
3 Mr. D. G. Eisenhut January 9, 1986 i
- 5. The B&WOG plans to discuss the program at the previously planned February 5, 1986 NRC/B&WOG meeting.
Consistent with the charter and intended purpose of the RRL, and as stated at the meeting, this completes the actions by the RRG relative to the Rancho Seco transient. Follow-on actions will be handled through the regular B&WOG organization and communication will be through established channels.
Should there be additional significant concerns raised by the NRC staff relative to the Rancho Seco transient between now and the planned B&WOG Executive Committee meeting, please call me prior to the meeting.
Very truly yours,
.T H. B. Tucker, C$' airman B&WOG Executive Committee J
NRC / B&WOG REGULATORY RESPONSE GROUP MEETING
~
TO REVIEW THE DECEMBER 26,1985 RANCHO SECO TRANSIENT JANUARY 8,1986 BETHESDA, MARYLAND B&WOG RRG REPRESENTATIVES:
. Arkansas Power & Light Duke Power Company Florida Power Corporation GPU Nuclear SMUD Toledo Edison
_4 A A. ._.m-__
4 B&WOG RRG MEMBERSHIP AND CHRONOLOGY OF RECENT ACTIVITIES 0 RRG MEMBERSHIP - ALL B&W OPERATING PLANTS ARE MEMBERS 0 RECENT RRG ACTIVITY CHRONOLOGY INDIVIDUAL UTILITY ACTION BEGAN AS SOON AS RANCHO SECO TRANSIENT INFORMATION AVAILABLE.
FIRST RRG TELEPHONE CONFERENCE CALL - 12/31/85; DECISION TO ACTIVATE RRG.
FURTHER INDIVIDUAL UTILITY ASSESSMENT RESULTING FROM RRG TELEPHONE CONFERENCE CALL.
SECOND RRG TELEPHONE CONFERENCE CALL -
1/2/86:
AGREEMENT ON SCOPE OF RRG ACTIVITIES.
THIRD RRG TELEPHONE CONFERENCE CALL -
1/6/86.
RRG MEETING -
1/7/86.
RRG/NRC MEETING - 1/8/86.
1
NRC/B&WOG RRG MEETING JANUARY 8,1986 AGENDA
- 1. Introduction H.B. Tucker /DPC (10 min) ll. Rancho Seco Transient R.J. Rodriquez/SMUD (15 min)
Ill. Plant-Specific Assessment Results
- Hardware &
Function Comparisons .C.B. Doyel/FPC (45 min)
-- Procedures, Training and J.T. Enos/AP&L (15 min)
Plant Performance IV. Preliminary Conclusions H.B. Tucker /DPC ( 5 min)
& B&WOG Actions e
e
--- .- - .=n . .. . . . .
- s. .
TO OTHER OTSG h
DUAL DRIVE TURBINE BYPASS VALVES
+ b h FROM CONDENSATE STORAGE MOTOR DRIVEN NORMAL AFW CONTROL VLV bM AFW PUMP TANK l
><1 OTSG MAIN THROTTLE MFW [] ^
REGULATING MAIN VALVE BLOCK VLV CONTL ATMOSPHERIC TEAM DUMP VALVES MAIN STEAM SYSTEM PUMP STARTUP (MSS)
CONTROL FEEDWATER SYSTEM (FWS)
Rancho Seco
,; .- SEQUENCE OF EVENTS
SUMMARY
RANCHO SECO TRANSIENT 12/26/85 i INITIAL CONDITIONS: DECEMBER 26,1985 76% REACTOR POWER ICS IN FULL AUTOMATIC CONTROL IlME EVENT l
04:13:47 LOSS OF ICS DC POWER !
VALVES MOVE TO 50% OPEN POSITION TURBINE BYPASS VALVES (TBV) i ATMOSPHERIC DUMP VALVES (ADV) 1 MAIN FEED WATER REGULATING VALVES (MFW) 1 AUXILIARY FEEDWATER VALVES (AFW)
MAIN FEED PUMPS GO TO MINIMUM SPEED 04:14:01 MOTOR DRIVEN AUXILIARY FEEDWATER PUMP (AFW)
STARTS AT 850 psig MAIN FEEDWATER PUMP DISCHARGE PRESSURE 04:14:03 REACTOR TRIPS ON HIGH RCS PRESSURE 04:14:06 TURBINE DRIVEN AUXILIARY FEED PUMP (AFW)
STARTS 04:14:11 AFW FLOW TO BOTH OTSGs l 1
04:14:25 OPERATORS INCliEASE RCS MAKEUP AS PART OF PROCEDURE E,02 " VITAL SYSTEM VERIFICATION" 04:14:30 OPERATORS SENT TO ISOLATE TBVs, ADVs, AND AFW VALVES, OPERATORS RECOGNIZE EXCESSIVE COOLDOWN RATE.
04:15:04 OPERATORS MANUALLY START "B" HIGH PRESSURE l
lNJECTION PUMP (HPI) TO FURTHER INCREASE RCS MAKEUP.
l
, SEQUENCE OF EVENTS
SUMMARY
(CONT'D.)
EME EVENT l
04.16:02 OPERATORS MANUALLY TRIP BOTH MAIN FEEDWATER PUMPS, ACTUAL MAIN FEED FLOW WAS ZERO SINCE 04:14:03.
AFW FLOW APPROXIMATELY 1100 GPM TO EACH STEAM GENERATOR.
04:16:57 SAFETY FEATURES (SFAS) AUTO INITIATION AT RCS PRESSURE OF 1600 psig 04:17:10 OPERATOR SHUTS SFAS ACTUATED AFW VALVES.
04:20:00 PRESSURIZER LEVEL OFFSCALE LOW 04:23:00 TBV AND ADV ISOLATED LOCALLY.
04:23:10 AFW VALVE TO "B" STEAM GENERATOR PARTIALLY CLOSED.
FLOW DECREASED TO "B" STEAM GENERATOR BY 60%.
04:26:22 AFW VALVE TO "A" STEAM GENERATOR CLOSED, OPERATOR BELIEVES VALVE ONLY 80% SHUT.
04:26:47 PRESSURIZER LEVEL BACK ON SCALE 04:29:40 OPERATOR ATTEMPTS TO CLOSE AFW VALVE TO "A" OTSG FURTHER. VALVE FAILS OPEN.
04:30:30 OPERATORS BEGIN DEPRESSURIZING RCS TO MOVE OUT OF PTS REGION.
04:33 AFW VALVE TO "B" STEAM GENERATOR IS FULLY CLOSED.
ALL FEEDWATER FLOW TO "B" STEAM GENERATOR IS STOPPED.
l l 04:40:00 ICS DC POWER RESTORED. OPERATORS SHUT AFW VALVES, TBV, AND ADVs FROM CONTROL ROOM. COOLDOWN CEASES l AT 386*F.
1
. ..... . ~ . . , - - . - .
Simplified Functional Relationship.of I&C Systems t
l Safety g Non-Safety RPS NUCLEAR ,
MEASUREMENIS M NEUTRON B0P CHDCS ISOLATION DEVICE FLUX
--> AN NU N C I AT I ON NON-NUCLEAR
--D iSOLAT10N ICS M UREMENTS DEVICE CONTROL OF SELECT RC FLOW >
8 h EL EMENTS ( FW V ALV TO CRD TRIP p & PUMPS. BYP ASS ISOLATION BREAKERS VALVES. TURBINE E DEVICE CRDCS)
. ESFAS BUI LDING > p ICS INPUTS PRESSURE FROM NNI RC PRESSURE E y 4 W
TO HPl e 9 m TO BUILDlHG E
, --> ANNUNCI ATI ON. INDICATION I SOL ATION &
RECOP0 LNG SPRAY NNI .
SG LEVEL
= --> CONTROL OF SELECTED U PROCESS ELEMENTS (PRESSURIZER FW CONTROL 0F INPUT SPRAY & HEATERS, PRlHARY PUMP STATUS E N ELEMENTS EN MAKEUP..PORV)
AUTO -e -> (V ALVES, PUMPS)
CONTROL START
s ---- n - - - - --a- A-4 4 - t ae AREAS BEING EVALUATED BY RRG RELATIVE TO '
RANCHO SECO TRANSIENT O ICS POWER SUPPLIES 0 EQUlPMENT CONTROLLED BY ICS 4
0 CONTROL ROOM INDICATORS
, O BACKUP MEANS OF CONTROL i
0 PROCEDURES AND TRAINING FOR LOSS OF ICS POWER I
l l
l 1
l i
1
ea B&WOG RRG ASSESSMENT OF R/S 12/26/85 TRANSIENT 0 ICS POWER SUPPLIES COMPARED POWER SUPPLY DESIGNS EVALUATED RANCHO SECO INITIATING EVENT i
O EQUIPMENT CONTROLLED BY ICS DETERMINED COMPONENTS CONTROLLED /
AFFECTED BY lCS DETERMINED FAILURE MODES (LOSS OF ICS POWER)
COMPARED FAILURE MODES AT B&W Pi. ANTS IDENTIFIED DIFFERENCES AND POTENTIAL IMPROVEMENT i
.u , + - m- - - - --,-- a
- e ea B&WOG RRG ASSESSMENT OF R/S 12/26/85 TRANSIENT b
0 BACKUP MEANS OF CONTROL
-- AVAILABILITY OF MANUAL CONTROL OF ICS COMPONENTS IN CONTROL ROOM
-- AVAILABILITY OF OTHER BY-PASS CONTROL CIRCUlTS AVAILABILITY OF NON-ICS. COMPONENTS THAT CAN ACCOMPLISH MISSION 0 CONTROL ROOM INDICATORS EVALUATED AVAILABILITY OF DIRECT CONTROL ROOM INDICATION FOR LOSS OF ICS POWER 1
i l
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820 System: CR-3, Davis Besse, Rancho Seco and ANO-1 IE or IE or I. BATTERY BACKED N-l N lE
- 2. VITAL DISTR.
- l. INVERTER WI TH STATIC SW1TCH 1F
- 2. BATTERY BACKED
- 3. REG INST. BUS hMVE ER REG.
INVERTER
- 4. AUXil PWR. DISTR. STATIC BUS STATIC
- SWITCH F -~ SWITCH .
L... - .!
1 r IP 120 VAC 120 V AC BACKUP PREFERRED POWER POWER SYSTEM CABINET AC CIELD LOADS o o ABT SI - --
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-24 ! ++
+24 VDC l VDC
-- ., u POWER MONITOR T0:
RECO RDERS
-24 6 + I N DI C ATORS V DC g( ,
y H/A STATIONS AUX RELAYS f__ %
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-24 V0C +24 VDC BUS BUS
721 System TMI-1 ES RE
= . - - - , INVERTER REG.
BUS.
REG.
BUS.
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I (l i (I l l EMERG EMERG FAN AUTO HAND 1
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1Ptr1 r E 1r 1r 1r 1r 1 ,
1 SW r _. _ L _ _q 5e il NSTRUMEN TAT 103 ICSF CONTROLS lNNI L__7__J I
721 System Oconee I
125 VDC BUS 125 VDC BUS l l
ISOLATING & TRANSFER 118 VAC REGULATED BUS i DIODES i
INVERTER TRANSFER SWITCH e b N.C.
ELECTR0 /HECHANICAL TRANSFER SWITCH N.C. MANUAL SW
/-
'N.O.'
I I I (I (I (,I
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(l l I I EMERG EMERG FAN AUTO HAND l l l
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l l \ SELECTED
! \ CONTROLS 1rir1r 1r 1r 1r 1r 1r %*-
I e I SW SELECTED r- -
L__ 5 P CONTR0tS 11MSTRUMENTATIO ICSF CONTROLS lNNI L - T-i
-J SELECTED l HD I C ATI ONS l
__ ,a__, , , 4-, -- -.u 4 .s - ..a ,. --
a O
EQUIPMENT CONTROLLED BY ICS (ORIGINAL DESIGN) l TURBINE BYPASS VALVE (TBV) 1 ATMOSPHERIC DUMP VALVE (ADV)
EMERGENCY FEEDWATER CONTROL VALVE STARTUP FEEDWATER VALVE (SUV)
MAIN FEEDWATER VALVE (MFW)
MAIN FEEDWATER PUMP TURBINE GOVERNOR -
CONTROL RODS MAIN TURBINE GOVERNOR l
l
\
b
POSITIONS OF KEY VALVES AND SYSTEMS .
FOLLOWING: LOSS OF ICS DC POWER
~. .
RANCHO DAVIS CRYSTAL SECO BESSE RIVER ANO-1 OCONEE TNI-l EQUIPMENT BAILEY BAILEY BAILEY TYPE 820 820 BAILEY BAILEY BAILEY 820 820 721 721 TBPV 50% 0% 0% 50% N/A N/A ADV 50% On N/A N/A N/A N/A EFW CONTROL 50% N/A N/A VALVES N/A N/A N/A STARTUP FW 50% 50% 50% 50%
FLOW PATH N/A N/A MAIN FW 0% 0% 0% 0%
FIDW PATH N/A N/A MF PUMP 2600 RPM 4690 RPM 4200 RPM GOVERNOR MIN SPEED N/A N/A ROD CONTROL TO MANUAL TO MANUAL TO MANUAL TO MANUAL N/A N/A MAIN TURBINE AS IS AS IS AS IS AS IS coVERNOR N/A N/A DOES PLANT NO YES YES YES HAVE MSIVs? NO YES eps e-d
POSITIONS OF KEY VALVES AND SYSTEMS ?
FOLLOWING LOSS OF ICS AC POWER RANCHO DAVIS CRYSTAL '
SECO BESSE RIVER ANO-1 OCONEE TMI-1 EQUIPMENT CAILEY BAILEY BAILEY TYPE 820 820 BAILEY BAILEY BAILEY 820 820 721 721 TBPV 50% 0% 0% 50% 0% 0%
- ADV 50% 0% N/A N/A N/A N/A i
EFW CONTROL 50% N/A VALVES N/A N/A N/A
STARTUP FW 50% 50% 50%
i FLOW PATH 50% 50% 50%
MAIN FW 0% 0%
FLOW PATH 0% 0% 50%' 0%
MF PUMP AS-IS AS-IS GOVERNOR AS-IS AS-IS AUTO TRIP 4100 RPM ON LOSS OF
~
ICS POWER RCD CONTROL AS-IS AS-IS AS-IS AS-IS AUTO TRIP ON AS-IS TRIP OF MF PUMPS MAIN TURBINE AS-IS' AS-IS AS-IS AS-IS AUTO TRIP ON AS-IS TRIP OF MF PUMPS DOES PLANT NO YES YES HAVE MSIVs? YES NO YES
POSITIONS OF KEY VALVES AND SYSTEMS FOLLOWING, LOSS OF ICS DC POWER RANCHO DAVIS CRYSTAL-SECO BESSE RIVER ANO-1 OCONEE TMI-1 EQUIPMENT BAILEY. BAILEY BAILEY TYPE 820 820 BAILEY BAILEY 820 820 721- BAILEY TBPV-- 721 50%' '0% 0% 50%
- N/A N/A ADV 50% On N/A N/A N/A
._ N/A EFW CONTROL 50% N/A VALVES N/A N/A N/A N/A STARTUP FW 50%*** 50% **
FIAW PATH 50% *** 50 % *** N/A N/A MAIN FW 0% 05 FLOW PATH 0% 0%
N/A N/A MF PUMP 2600 RPM GOVERNOR 4690 RPM 4200 RPM MIN SPEED- N/A N/A ROD CONTROL TO MANUAL TO MANUAL TO MANUAL TO MANUAL N/A N/A QURBINE AS IS AS IS AS IS R AS IS N/A N/A D 1 NO YES YES YES NO YES *
- SFRCS MAIN FEED PUMP TRIP
. . _ , . , _ A , _ -_ - - - - w CONTROL ROOM INDICATIONS
- FOR LOSS OF ICS POWER RANCHO DAVIS INDICATION SECO BESSE CR-3 ANO-1 OCONEE TMI-1 ANNUNCIATOR X X X X X X LOSS OF llGHTS X X X X X X ON HAND / AUTO STATIONS 4 PLANT X X -- --
X --
COMPUTER POWER STATUS LIGHT -- --
X X --
X BLOWN FUSE --
X X --
X --
INDICATOR EVENTS -- --
X -- -- --
RECORDER i- ICS INVERTER X X --
X X X
POSITIONS OF KEY VALVES AND SYSTEMS FOLLOWING LOSS OF ICS DC POWER RANCHO DAVIS CRYSTAL SECO BESSE RIVER ANO-1 OCONEE- TMI-1 EQUIPMENT BAILEY BAILEY BAILEY TYPE 820 820 BAILEY BAILEY BAILEY 820 820 721 721 TBPV 50% 0% 0% 50% N/A N/A ADV 50% On N/A N/A N/A N/A EFW CONTROL 50% N/A. N/A VALVES N/A N/A N/A STARTUP FW 50% 50% 50%
FLOW PATH 50% N/A N/A MAIN FW 0% 0% 0%
PLOW PATH 0% N/A N/A MF PUMP 2600 RPM 4690 RPM GOVERNOR 4200 RPM MIN SPEED N/A N/A ROD CONTROL TO MANUAL TO MANUAL TO MANUAL TO MANUAL N/A N/A MAIN TURBINE AS IS AS IS AS IS ,
GOVERNOR AS IS N/A N/A DOES PLANT NO YES YES HAVE MSIVs? YES NO YES
~~
4 Q
, ANTICIPATED RESPONSE TO LOSS OF ICS POWER ANO-1 T=0 LOSS OF ICS DC POWER
-- TBV GOES TO 50% .
-- STARTUP FEEDWATER VALVE GOES TO 50%
-- MFW PUMP RUNBACK TO MINIMUM SPEED
-- MFW BLOCK AND LO-LOAD BLOCKS GO TO 0%
-- ADV REMAIN AT 0%
O PLANT RESPONSE MFW FLOW DECREASING RCS PRESSURE INCREASING
-- SG LEVEL DECREASING T=8 sec. RX TRIP ON HIGH PRESSURE TURBINE TRIP ONE MFW PUMP TRIPS (OPERATOR CLOSES MSIVs PER PROCEDURE)*
0 PLANT RESPONSE RCS TEMPERATURE DECREASING RCS PRESSURE DECREASING STM GENERATOR PRESSURE INITIALLY INCREASING STM GENERATOR LEVEL DECREASING ;
(WILL GET EFIC EFW ACTUATION ON l LO-LEVEL IN ~ 30 SEC.)
I TO FURTHER EVALUATE TRANSIENT, IT IS ASSUMED
) OPERATOR DOES NOT PERFORM THIS ACTION.
w g-.m-, .-- ,---,w-- ,
ANO-1 RESPONSE (Cont'd) l T=12 mins: SG PRESSURE DROPS BELOW 600 PSI l
-- EFIC MSLI ACTUATION MAIN STEAM LINE ISOLATION VALVES CLOSE
-- MAIN FEEDWATER ISOLATION VALVES CLOSE i
-- ADV BLOCK VALVE OPENS '
-- ADVs CLOSED (PRESSURE LESS THAN SETPOINT) 0 PLANT RESPONSE RCS PRESSURE INCREASING RCS TEMPERATURE STABILIZES
-- SG PRESSURE INCREASING
-- SG LEVEL MAINTAINED AT EFIC SETPOINT T=20 mins: SG LEVEL RETURNS TO SETPOINT EFW VALVES BEGIN TO MODULATE TO CONTROL LEVEL
-- ADV's BEGIN TO MODULATE TO CONTROL PRESSURE O PLANT RESPONSE RCS TEMPERATURE INCREASING RCS PRESSURE STABILIZED
-- SG LEVEL STABLIZED AT SETPOINT l -- SG PRESSURE STABILIZED AT SETPOINT I
ALL PARAMETERS RETURNING TO HOT SHUTDOWN CONDITIONS.
l PRELIMINARY PROCEDURE ASSESSMENT RESULTS 0 PROCEDURES EXIST IN ALL PLANTS FOR DEALING WITH THE SYMPTOMS AND CONSEQUENCES OF LOSS OF ICS POWER.
O ABNORMAL TRANSIENT OPERATING GUIDELINES (ATOG) TECHNICAL BASIS DOCUMENT IS SOUND; PRELIMINARY ASSESSMENT OF R/S TRANSIENT DOES NOT INDICATE NEED TO REVISE.
i 0 CLARIFICATION OF CRITERIA REGARDING WHEN TO TAKE CERTAIN SPECIFIC ACTIONS MAY BE APPROPRIATE.
O FURTHER DETAILED REVIEW IS APPROPRIATE AND IS UNDERWAY.
. . a
' 'E s U '
, .s . .-
IN. A 1 %
PROCEDURE ASSESSMENT y
O' CONSIDERATION GIVEN TO:
PROCEDURES FOR DEALING WITH TRANSIENTS
,, INITIATED BY THE LOSS 'OF ICS POWER l -
s
-- THE EXPECTED, RESPONSE OF ICS CONTROLLED EQL,ilPMENT AND.THE RESULTANT EFFECT ON ON THE NSS PROCEDURES FOR DEALING WITH THE RESTORATION OF ICS POWER 3--
- ,, -ROLE OF ABNORMAL TRANSIENT OPERATING c; GUIDELINES (ATOG)
- s. .
e O fdDFIRAL APPROACH:
i
' REVIEW OF PROCEDURE CONTENT ,
OPERATOR INTERVIEWS '
4 s
\
s
--_-,e-. ..,_. ..,e xw-- , ,-
FOLLOW-ON B&WOG PROCEDURES AND TRAINING REVIEW IN
. RESPONSE TO THE 12/26/85 RANCHO SECO TRANSIENT
- 1. REVIEW OF TRAINING RECORDS TO ASSURE THAT OPERATORS HAVE RECEIVED TRAINING ON THE LOSS OF ICS POWER SUPPLY EVENT AND IF THE INDIVIDUAL HAS NOT, WILL SCHEDULE THE INDIVIDUAL FOR TRAINING.
~
- 2. CONFIRMATORY REVIEW OF THE ATOG TECHNICAL BASES DOCUMENT WILL BE PERFORMED. '
- 3. REVIEW OF THE PLANT-SPECIFIC PROCEDURES FOR ,
IMPLEMENTING ATOG.
L
- 4. REVIEW PLANT-SPECIFIC PROCEDURES FOR RESTORATION OF ICS POWER.
l
- 5. ISSUE INFORMATION TO FAMILIARIZE OPERATORS WITH THE RANCHO SECO EVENT.
l l
i
. . . - , . - - - - , - - . . - - , . , - . . _ _ - . - . . - - - - - , - - - . - . . . . . - - . - - - ~ - - - - - - . - - - , - - ~ . - - - - - - , , - -
4 CONCLUSIONS OF RRfa ,
0 DUE TO PLANT DIFFERENCES, A TRANSIENT INITIATED BY LOSS OF' POWER TO ICS, SUCH AS THE RANCHO SECO EVENT, AT ANY B&W PLANT OTHER THAN RANCHO SECO WOULD RESULT IN MUCH LESS SEVERE TEMPERATURE CHANGES.'
O
-DUE TO SIM,1LARITIES, THE RRG HAS CONCLUDED THAT ADDITIONAL REVIEW OF THE RANCHO SECO EVENT SHOULD BE UNDERTAKEN AS MORE COMPLETE INFORMATION IS MADE AVAILABLE FROM INVESTIGATIONS BY NRC, SMUD, OR OTHER SOURCES. THE INTENT OF THIS REVIEW SHOULD BE TO IDENTIFY ACTIONS TO BE TAKEN BY B&WOG MEMBERS TO REDUCE THE FREQUENCY AND MAGNITUDE OF TRANSIENTS.
/
0 THEREFORE, AS CHAIRMAN OF THE B&WOG EXECUTIVE COMMITTEE, I HAVE INSTRUCTED THE CHAIRMAN OF THE B&WOG STEERING COMMITTEE TO DEVELOP A PROPOSED PROGRAM OF REVIEW AND PRESENT THAT TO.THE B&WOG EXECUTIVE COMMITTEE AT A MEETING JANUARY 16,1986.
l j AT THAT MEETING WE WILL DETERMINE THE SCOPE AND l SCHEDULE OF REVIEW WITH THE INTENT OF INCORPORATING THE ACTIONS STEMMING FROM THE RANCHO SECO TRANSIENT INTO THE REVIEWS AND ACTIONS CURRENTLY UNDERWAY AS A RESULT OF THE DAVIS BESSE L EVENT OF JUNE 9,1985.
+
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r . _ . - . _ . . _ .. __
i .
l CONCLUSIONS OF RRG (Cont'd) 0 THE GENERAL DIRECTION OF B&WOG PROGRAMS FOR l REDUCING TRANSIENTS AND SCRAMS IS SOUND AND WILL l CONTINUE. EMPHASIS IS BEING GIVEN TO THE SECONDARY l PORTION OF THE PLANTS. BOTH THE RECENT DAVIS BESSE AND RANCHO SECO TRANSIENTS RE-EMPHASIZE THE IMPORTANCE OF THIS DIRECTION. THE RELATIVE PRIORITY l
AND SCHEDULE OF THESE EXISTING PROGRAMS IS BEING '
RE-EVALUATED.
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O INCREASED NRC FAMILIARITY WITH EXISTING AND .
PLANNED B&WOG ACTIONS RELATIVE TO TRANSIENT REDUCTION IS APPROPRIATE. ALTHOUGH MUCH OF THIS ACTIVITY INVOLVES THE NON-SAFETY RELATED PORTIONS .
OF THE PLANT, THE B&WOG INVITES NRC INPUT ON THESE .
l PROJECTS. THE ESTABLISHED MODES OF COMMUNICATION REGARDING B&WOG PROGRAMS ARE APPROPRIATE FOR THESE INTERACTIONS.
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