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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 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 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 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 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 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 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 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 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 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 ML20248H2391989-10-0606 October 1989 Requests Exemption from Requirements of 10CFR26 Re Fitness for Duty Programs Based on Present & Future Operational Configuration 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 NL-89-468, Submits Justification for Absence of Functional Testing Requirement in Proposed Tech Spec 4.14(f) Re Snubber Svc Life Monitoring,Per 890517 Request1989-05-30030 May 1989 Submits Justification for Absence of Functional Testing Requirement in Proposed Tech Spec 4.14(f) Re Snubber Svc Life Monitoring,Per 890517 Request ML20247N2601989-05-25025 May 1989 Requests Guidance Re Whether NRC Concurs W/Arbitrator Order Concerning Employee Access to Plant 1990-09-06
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gSMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, Po. Box 15830, Sacramento CA 958521830,(916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CAllFORNIA AGM/NTS88-258 October 7, 1988 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Wcsh.ington, DC 20555 Docket No. 50-312 T'ancho Seco Nuclear Generating Station Licorise No. DPR-54 REr.CTOR VESSEL LEVEL
- NSTRUMENTATION SYSTEM Attention: George Knighton Attachment I is a design report for the Reactor Coolant Inventory Tracking System (RCITS) which will be insthlled during the Cycle 8 refueling outage. The District preposed Inadequate Core Cooling instrumentation to satisfy the NRC Order For Modification of Licenso for Rancho Seco Nuclear Generating Station on April 15 ,- 1983, and supplied additional information requested by the NRC on June 28, 1984. A preliminary design for RCITS was provided by letter dated December 30, 1985 (Attachment II). Por District commitment in a letter dated September 30, 1985, the balance of the RCITS will be installed during the Cycle 8 outago.
The basic design of the system has not changed sinco the descrip-tion of the proposed RCITS was transmitted to the Commission on December 30, 1985. The RCITS Design Basis Report is in prepara-tion; therefore, specific information regarding components may change as a result of final review and approval. ,
I 8810180132 881007 PDR P ADOCK 050003)2 ppy
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RANCHO SECO NUCLEAR GENERATING STATION O 14440 Ten Cities Road, Herald, CA 95638 9709: (209) 333 2935 m
George Knighton AGM/NTS88-258 Members of your staff with questions requiring additional infor-mation or clarification may contact Mr. Steve Crunk at (209) 333-2935, extension 4913.
Sincerely,
, Bob G. Croley Assistant Genera Manager Nuclear Technica Services Attachments cc w/atch: J. B. Martin, NRC, Walnut Creek A. D'Angelo, NRC, Aancho Seco i
. . l George Knighton AGM/NTS88-258 bc:
w/atch w/o atch 2 'l General Manager HS 41
_ __ X Chief Executive Officer, Nuclear HS 209
~
__ AGH, Plant Support Services MS 259 -
__. AGH, Nuclear Technical Services MS 206
__ AGH, Nuclear Power Production MS 254 :
l_ Director, Nuclear Quality MS 271
__. J. , Manager, Nuclear Training MS 296
___ __X _ Manager Licensing MS 298 i l_ _ _ . , Manager, Nuclear Engineering MS 208-6 !
__ Manager, Cost Control Services MS 208-10
__ Manager, Maintenance MS 254
__ Manager, Operations MS 255
__ Hanager, Envir. Hon. & Emer. Prep. MS 292A ,
_ ,_ Manager, Rad. Protection MS 244
,__. Manager, Nuclear Chemistry MS 250
___ __ Manager, Plant Performance MS 258
__ Hanager Safety & Risk Hgmt. MS 40
._._, Plant Support Eng. Manager HS 208-5
_ _ . HSRC Secretary (R. Colombo) HS 256 c _. X Public Information MS 204
_ Surveillance Coordinator MS 278
- l. IIRG HS 298
- l. NAC (4) HS 204
_ T. Baxter :
_ F. Burke (8&W) ,
3 D. Seavers (ANI) !
._ _ LER Files MS 298 !
- 3. Licensing Correspondence Tracking MS 286 ,
L PRC Secretary (R. Colombo) MS 256 l l_ RIC File 1A.200 MS 224 .
_ Special Report Files MS 298 !
. _ Tech. Spec./PA Files MS 298
_ NOV/N00 Files MS 286 l
_ _ Licensing Verification MS 286 l l_ Elizabeth Gebur HS 298 3 Jerry Delezenski HS 298 I
___ BHOG T.S. Committee (8) 1_ Paul 80sakcwski, Proj. Mgr. (RCITS) MS 270 e um_
~ _ _ . _ _ _ _ _ _ _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ .
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Attachment I Reactor Coolant Inventory Tracking System Design Report a
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. s Attachment I Page 1 of 3 I. Systed Purpose The Reactor Coolant Inventory Tracking System (RCITS) provides a reliable and unambiguous indication of reactor coolant inventory trending with the reactor coolant pumps (RCPs) either running or tripped. The system meets the intent of NUREG-0737, Item II.F.2, "Instrumentation for Detection of Inadequate Core Cooling" and the requirements for a Reg. Guide 1.97 Category 1 variable (ex-cept for RCP motor current).
II. System Description The RCITS measures three parameters for reactor coolant inventory trending:
- l o Differential pres ~e (DP) across the vertical run of the t hot legs (tot leg avel) - QA Class I; o DP across the upper region of the reactor vessel (RV level)
- QA Class I; and o RCP motor current - QA Class II.
Hot Lea Level Measurement The hot leg level measurement instrumentation was installed dur-ing the Cycle 7 outage and the unscheduled outage commencing '
December 26, 19R5.
Reactor Vessel Level Measurement The RV level measurement indicates reactor coolant inventory trends when the RCPs are not operating. The RV level measurement ranges from the top of the RV head to the center of the cold leg.
The design requires the removal of the central control rod drive nechanism (CRDM) to penetrate the RV head for the top RV pressure tap. An existing tMp on the Loop A cold leg for level transmit-ter LT-21046 will la modified and used as the lower pressure tap.
The central CRDM and associated control rods will be replaced by a standpipe assembly. The assembly will have flanged connections on each and and will be bolted to the CRDM housing flange. Two manual shut-off valves will be installed in the standpipe assem-
- bly to provide isolation capability. In addition, a manual valve
, for venting the assembly during filling of the Reactor Coolant System will also be installed. A small piping subassembly will be included to which instrument lines will be attached. Supports to meet seismic and ASME code requirements will be installed as necessary.
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Attachment I Page 2 of 3 The standpipe assembly will be ASME Class 1 from the face of the CRDM housing flange through the second rc(.ucer, and will be manu-factured from 304 stainless steel. The rest of the assembly (in-cluding the piping subassembly) will be ASME III, Class 2. The supports for tha standpipe and subassembly will mee'c the require-ments of ASME Section III, Subsection NF. The standpipe will be insulated to prevent excessive heat loss to surrounding CRDMs.
Two DP transmitters (one per channel) will be used to provide re-dundancy. Each will be powered independently by QA Class I instrumentation power. The transmitters will be located inside containment and will be qualified to withstand the normal, abnor-mal, and post accident conditions in accordance with the environ-mental qualifications program. They will be installed in insula-ted enclosures to protect them from temperature transients during a design basis event and to improve their performance. The DP transmitters will withstand the pressure conditions imposed on the diaphragm of the transmitters when the RCPs are running and will be fully recoverable when the RCPs are stopped.
The design includes density compensation for level measurements due to temperature effects on process liquid density. The QA Class I incore temperature (T-incore) will be used in temperature compensation. Density compensation on the reference legs (ver-tical runs) is not required because the reference legs (instru-ment lines) will be insulated with 2-inch thick insulation to maintain the temperature of the reference legs relatively con-stant. The maximum temperature rise of the reference legs has been calculated to be approximately 8 F0 above normal containment atmospheric temperature when subjected to the temperature tran-rients during a design basis event. The sencing lines will be installed to seismic Class I requirements.
The output of the transmitters will be connected to the QA Class I Anatec multiplexer system for level trending indications on the QA Class I Safety Parameter Display System (SPDS) and QA Class II Interim Data Acquisition and Display System (IDADS). Isolation for IDADS is provided for in the multiplexers. IDADS has trend recording capability.
A sketch of the RV level measurement system is shown in Figure 1.
A proposed Inadequate Core cooling display is shown in Figure 2.
RCP Motor Current RCP motor current monitors (QA ClLas II) provide trending indica-tion of the voids in the RCS with the RCPs running. The RCP motor current signal is used to infer the average density of liquid (or two-phase liquid / vapor) which passes through the pump.
Coolant tenperatare at the inlet is used to infer the density of each individual phase of the fluid as it passes through the pump,
Attachment I Page 3 of 3 ,
RCP motor current measurement uses Class II current transducers (one for each RCP) which provide an analog signal proportional to RCP motor current. The curront transducers will be connected to existing Class II current transformers and installed in the same compartment as existing 6.9kV switchgear supplying power to the RCPs.
The current transducer output signals will be fed into a Class II i Anatec multiplexer located in the same switchgear room as the transducers. The signals will be processed by IDADS to present on-demand percent void indications for the RCPs. IDADS also has on-demand trending and recording capability. Void fraction indi-cation will be available on IDADS whenever the RCPs are running.
i A sketch of the RCP motor current measurement system is shown in i Figure 3.
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i Attachment II District Letter of December 30, 1985 1
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RJR 85-578 Cocamber 30, 1985 l
l OIRECTOR CF NUCLEAR REACTOR REGULATICN ATTN HUCH L ThCP.PSCN JR j i
OIVISION OF LICENSING !
U S NUCLEAR REGULATCRY CCf1MISSICN '
WASHINGTCN OC 20555 j I
00CXET 50-312 <
RANCHO SECO NUCLEAR GENERATING STATION UNIT NO. 1 . .
NUREG 0737 ITEM II.F.2 INADEQUATE CORE C00LLW (ICC)
.h Sy letter dated. April 15, 1983, the District proposed ICC instrumentation to !
satisfy your Order For Modification of License for Rancho Seco Nuclear Cenerating Station, dated December 10, 1982. On June 28, 1984, the District i responded to your Request for Additional Information, dated t,ugust 24, 1983.
In these submittals, the District identified a heated junction thermocouple .,
system (hJTCS) as the preferred method for reactor vessel coolant inventory .;
trending. A differential pressure (CP) system was identified as an option.
Due to the recent availability of qualified higher accuracy transmitters and procurement difficulties with the HJTCS, the District has reevaluated the options and decided to pursue the DP system.
The attachment to this letter provides a design description for the precosed reactor coolant inventory tracking sy: tem (RITS). This information supersedes the reactor vessel level measurement lystes description provided by the District's April 15, 1983 and June 28, 1984 submittals. The previous descriptions of the balance of the ICC instrumentation, including hot leg level, are still valid.
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RJR-85-573 December 30, 1985 Hugh L. Thompson. Jr. -2 The District remains committed to install the balance of the RITS '
instrumentation during the Cycle 8 refueling outage, as reiterated in our letter of September 30, 1985.
4 If you have any questions concerning the above, please contact Robert Little at (916) 732-6021. ,
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d R. J. Rt RIGUE j ASSISTANT GENERAL MANAGER, I
- NUCLEAR Attachment bc: 0. K. K. Lowe R. J. Rodriguez I f
i R. P. Cubre' L. R. Xeilman '
R. A. Dieterich V. C. Lewis (2)
R. W. Colombo (2) t J G. A. Coward L. G. Schwieger (2) G. C. Andognini (MS 39) i i Syd Miner (NRC, Bethesda) J. Eckhardt (NRC, Ranch)
P. G. Delezenski Fourth Floor Files L l
Eng. Files-Plaza 50 Licensing Files (MS 32)
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AtQ3chment REACTOR CCCLANT INVENTORY TRENOUJG SYSTEM l The reactor coolant inventory tracking system (RITS) is designed The RITS to will provide unambiguous indication of reactor coolant inventory trending.with the reactor coolan provide inventory trending indicationThe system is being designed to meet the intent of either running or tripped.
NUREG 0737, Item II.F.2.
'he RITS measures three parameters for reactor coolant invesory trending determination:
4 .
differential pressure (DP) across the vertical run of the hot legs (hot leg level);
e CP across the upper region reactor vessel (RV level); and
. RCP motor ocwer.
Hot Leo level Measurement The hot leg level portion of the RITS is described in tha Oistrict's .
submittals of April 15, 1H3 and June 28, 1984.
RV Level deasurement The RV level measurement providis an indication of reactor coolant inventory k, trending when the RCPs are not operating, The RV level measurement ranges from the top of the reactor vesse to the center of the cold leg. ,.
control drive mechanism to provide a penetration in the RV head for location 6 of the top RV pressure tap. The existing tap on the Loop A cold leg i
p Use of the l
l (discharge of RCP P-2108) will be used as a lower pressure tap. .
j existing cold leg tap provides the following benefits: l
. elimination of sirgle failure concerns relative to use of the tap on decay i I
heat drop line common with the hot leg CP transmitters; ard i ,
- lower personnel exposure over installing a new hot leg tap. i l
Two OP transmitters (one per channel) will be used to provide redurdancy.
Each transmitter will be powered independently by Class 1 instrumentation power. The DP transmitters will be located inside containment and will bo qualified to withstand the normal, abnormel, and post accident conditions,ThG OP in accordance with the District's environmental qualification program. !
i transmitters will be qualified to withstand the overpressure conditions l l
imcosed on the diapt.ragm of the transmitters when the RCPs are running andThe !
) will be fully recoverable when the RCPs are stopped.
installed in an insulated enclosure to protect them from temcerature l transients during design basis events and to improve treir perforstnce.
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The design includes density corcensation for level measurements due to temperature ef fects on process liquid density. Consity comconsation on *.he esference legs (vertical runs) is not required because the sensing lines will !
be insulated with 1" thick insulation to maintain the temperature of the reference legs relatively constant. The maximum tempe'rature'rf'se of tne reference legs is anticipated to be 10*F above normal containment at.nospheric temcorature (120*F) when subjected to the temperature transients during a design basis event.
The output of the transmitters will ba connected to the Class 1 sultiplexer system for the level irdications on the safety parameter display systea (SPOS) and the interim data acquisition and display system (ICA03) CRTs. Isolation .
For ICA05 is provided in the multiplexers. IDAOS is the primary display system for ICC and has trend recording capability showing the level-time history of representative RV level readings.
Primary (IDADS) and backup (SPOS) display channels are electrically ,
independent. IDA05 is gewered from battery backed Class 2 power source and '
SPOS will be powered from a Class 1 power source. ,SPOS mod!fications will be implemented per the t.iving Schedule ard in accordance with Reg. Cuide 1.97 and CRCR recommendations.
A skatch of the RV level portion of the RITS is'shown in Figure 1.
9CP Motor Power .
RCP motor power and pump inlet temperature measurements will be used by the i*G RITS to trend the reactor coolant void fraction when one, or more, of the RC'2s ?
is operating.
RCP power measurement requires the use of 3-phase Watt-transducers (Class 2),
one for each RCP, to provide an analog signal proportional to RCP actor .
power. Watt-transducers will use existing Class 2 current and potential
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transformer signals and will be self pcared. The transducers will be high quality commercial grade components and will be installed in the same ,
environment as the existing 6.9kV switchgear supplying power to RCPs.
The output from the transducers will be fed into Class 2 sultiplexers located in the same switchgear roca. The Watt-transducers' signals will be processed in IDADS (Primary display) to provide percent void indication for each puma via CRT on demand. !0A05 also has trend capability and recording capability on demand. Since IDADS is powered from a battery backed Class 2 peser source and the RCP actors are powered from a Clas: 2 power source, the percent void indication will be available on IDAOS CRT whenever the RCPs are running.
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