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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M8851999-10-0808 October 1999 Informs of Staff Determination That Listed Calculations Should Be Withheld from Public Disclosure,Per 10CFR2.790, as Requested in 990909 Affidavit ML20211J7731999-08-31031 August 1999 Forwards Insp Rept 50-312/99-03 on 990802-06.No Violations Noted.Insp Included Decommissioning & Dismantlement Activities,Verification of Compliance with Selected TS & Review of Completed SEs ML20211H7481999-08-13013 August 1999 Forwards Amend 126 to License DPR-54 & Safety Evaluation. Amend Changes Permanently Defueled Technical Specification (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP Level Alarm Switches with Generic Ref 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments ML20195B8511999-05-27027 May 1999 Forwards Change 4 to Rancho Seco Emergency Plan, Incorporating Commitments Made to NRC as Outlined in NRC .Emergency Plan Includes Two Listed Supporting Documents ML20207E9181999-05-27027 May 1999 Informs That Effective 990328,NRR Underwent Reorganization. within Framework of Reorganization,Div of Licensing Project Mgt Created.Reorganization Chart Encl ML20206U7411999-05-18018 May 1999 Provides Summary of 990217-18 Visit to Rancho Seco Facility to Become Familar with Facility,Including Onsite ISFSI & Meeting with Representatives of Smud to Discuss Issues Re Revised Rancho Seco Ep,Submitted to NRC on 960429 ML20206M1611999-05-10010 May 1999 Forwards Listed Proprietary Calculations to Support Review of Rancho Seco ISFSI Sar.Proprietary Encls Withheld ML20206E8591999-04-12012 April 1999 Provides Info Re High Total Coliform Result in Plant Domestic Sewage Effluent Prior to Confluence with Combined Effluent.Cause of High Total Coliform Result Was Broken Flow Rate Instrument.Instrument Was Repaired on 990318 ML20204H6751999-03-19019 March 1999 Forwards Insp Rept 50-312/99-02 on 990309-11.No Violations Noted.Portions of Physical Security & Access Authorization Programs Were Inspected ML20204E4031999-03-16016 March 1999 Submits Rept of Status of Decommissioning Funding for Rancho Seco,As Required by 10CFR50.75(f)(1).Plant Is Currently in Safstor, with Operating License Scheduled to Expire in Oct 2008 ML20204E6661999-03-11011 March 1999 Forwards Rancho Seco Exposure Rept for Individuals That Received Greater than 100 Mrem During 1998,IAW TS D6.9.2.2 & NRC Regulatory Guide 1.16 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 ML20207L1711999-03-10010 March 1999 Informs of Staff Determination That Supporting Calculations & Drawings Contained in Rev 2 of Sar, Should Be Withheld from Public Disclosure,Per 10CFR2.790 NL-99-002, Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3)1999-03-10010 March 1999 Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20207D4431999-03-0101 March 1999 Forwards Annual Radioactive Effluent Release Rept, for Rancho Seco Nuclear Generating Station for 1998 ML20207H6181999-02-18018 February 1999 Provides Attached Metrix & Two Copies of Rancho Seco ISFSI Sar,Rev 2 on Compact Disc,As Requested in 990209 Meeting. First Rounds of RAIs Dealt Primarily with Use of Cask as Storage Cask.Without Compact Disc ML20203D0761999-02-10010 February 1999 Ltr Contract:Task Order 37 Entitled, Technical Assistance in Review of New Safety Analysis Rept for Rancho Seco Spent Fuel Storage Facility, Under Contract NRC-02-95-003 ML20155D4431998-10-27027 October 1998 Forwards Amend 3 to Rancho Seco Dsar,Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode.With Instructions & List of Effective Pages NL-98-032, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1998-09-30030 September 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20237A6031998-08-0707 August 1998 Forwards Insp Rept 50-312/98-03 on 980706-09.No Violations Noted ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements ML20236Q9461998-07-15015 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-02 ML20236J6331998-06-30030 June 1998 Forwards Response to Violations Noted in Insp Rept 50-312/98-02.Corrective Actions:Util Revised RSAP-1003 to Clarify District Security Staff Responsibilities Re Handling & Review of Criminal History Info ML20236E8211998-06-0303 June 1998 Forwards Insp Rept 50-312/98-02 on 980519-21 & NOV Re Failure to Review & Consider All Info Obtained During Background Investigation.Areas Examined During Insp Also Included Portions of Physical Security Program ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 IR 05000312/19980011998-03-25025 March 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-01 on 980205 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) ML20202C4641998-02-0505 February 1998 Forwards Insp Rept 50-312/98-01 on 980105-08 & Notice of Violation.Insp Included Decommissioning & Dismantlement Work Underway,Verification of Compliance W/Selected TS & Main & Surveillance Activities Associated W/Sfp ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks ML20198K5391997-10-21021 October 1997 Forwards Insp Rept 50-312/97-04 on 970922-25 & Notice of Violation.Response Required & Will Be Used to Determine If Further Action Will Be Necessary ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility ML20198G8141997-08-22022 August 1997 Forwards Amend 125 to License DPR-54 & Safety Evaluation. Amend Permits Smud to Change TS to Incorporate Revised 10CFR20.Amend Also Revises References from NRC Region V to NRC Region IV ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 ML20149E5031997-07-10010 July 1997 Second Partial Response to FOIA Request for Documents. Forwards Records Listed in App C Being Made Available in Pdr.Records in App D Already Available in PDR ML20148P5161997-06-30030 June 1997 Second Partial Response to FOIA Request for Documents.App B Records Being Made Available in PDR ML20141A1721997-06-17017 June 1997 Forwards Insp Rept 50-312/97-03 on 970603-05.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program 1999-08-31
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195B8511999-05-27027 May 1999 Forwards Change 4 to Rancho Seco Emergency Plan, Incorporating Commitments Made to NRC as Outlined in NRC .Emergency Plan Includes Two Listed Supporting Documents ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments ML20206M1611999-05-10010 May 1999 Forwards Listed Proprietary Calculations to Support Review of Rancho Seco ISFSI Sar.Proprietary Encls Withheld ML20206E8591999-04-12012 April 1999 Provides Info Re High Total Coliform Result in Plant Domestic Sewage Effluent Prior to Confluence with Combined Effluent.Cause of High Total Coliform Result Was Broken Flow Rate Instrument.Instrument Was Repaired on 990318 ML20204E4031999-03-16016 March 1999 Submits Rept of Status of Decommissioning Funding for Rancho Seco,As Required by 10CFR50.75(f)(1).Plant Is Currently in Safstor, with Operating License Scheduled to Expire in Oct 2008 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 ML20204E6661999-03-11011 March 1999 Forwards Rancho Seco Exposure Rept for Individuals That Received Greater than 100 Mrem During 1998,IAW TS D6.9.2.2 & NRC Regulatory Guide 1.16 NL-99-002, Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3)1999-03-10010 March 1999 Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20207D4431999-03-0101 March 1999 Forwards Annual Radioactive Effluent Release Rept, for Rancho Seco Nuclear Generating Station for 1998 ML20207H6181999-02-18018 February 1999 Provides Attached Metrix & Two Copies of Rancho Seco ISFSI Sar,Rev 2 on Compact Disc,As Requested in 990209 Meeting. First Rounds of RAIs Dealt Primarily with Use of Cask as Storage Cask.Without Compact Disc ML20155D4431998-10-27027 October 1998 Forwards Amend 3 to Rancho Seco Dsar,Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode.With Instructions & List of Effective Pages NL-98-032, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1998-09-30030 September 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements ML20236J6331998-06-30030 June 1998 Forwards Response to Violations Noted in Insp Rept 50-312/98-02.Corrective Actions:Util Revised RSAP-1003 to Clarify District Security Staff Responsibilities Re Handling & Review of Criminal History Info ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 NL-97-030, Forwards Endorsement 132 to Nelia Policy NF-0212 & Endorsement 118 to Maelu Policy MF-0075 for Smuds Rsngs1997-05-13013 May 1997 Forwards Endorsement 132 to Nelia Policy NF-0212 & Endorsement 118 to Maelu Policy MF-0075 for Smuds Rsngs ML20138F5321997-04-28028 April 1997 Forwards Response to RAI Re License Amend 192,updating Cask Drop Design Basis Analysis,Per NRC 960510 Request for Addl Info on 960318 Application NL-97-027, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility1997-04-17017 April 1997 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility ML20137W8091997-03-20020 March 1997 Forwards Biennial Update to Rancho Seco Post-Shutdown Decommissioning Activities Rept ML20137S3571997-03-19019 March 1997 Provides Notification of Use of Revised Quality Manual for Activities Re Rancho Seco ISFSI ML20137D0981997-03-18018 March 1997 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1996.Provided IAW TS D6.9.2.2 & Guidance Contained in NRC Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1996 ML20137D1221997-03-18018 March 1997 Submits,Iaw 10CFR20.2206 & TS D6.9.2.1,1996 NRC Form 5 Individual Monitoring Repts for Personnel Requiring Radiation Exposure Monitoring Per 10CFR20.1502 During 1996. W/O Encl NL-97-012, Submits Rept of Listed Current Levels of Property Insurance for Plant,Iaw 10CFR50.54(w)(3)1997-02-11011 February 1997 Submits Rept of Listed Current Levels of Property Insurance for Plant,Iaw 10CFR50.54(w)(3) ML20138L1091997-01-29029 January 1997 Informs of Schedule Change Re Decommissioning of Rancho Seco.Incremental Decommissioning Action Plan,Encl NL-97-005, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility1997-01-22022 January 1997 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility NL-96-056, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1996-12-16016 December 1996 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20134E0041996-10-23023 October 1996 Forwards Response to NRC GL 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks ML18102B6871996-08-0606 August 1996 Informs That Util Will Revise Loading & Unloading Procedures & Operator Training as Necessary ML20149E4491994-05-16016 May 1994 Forwards 1993 Annual Rept of Sacramento Municipal Utility District,For Info ML20149E3971994-05-10010 May 1994 Forwards Re Updated Decommissioning Cost Estimate for Rancho Seco & Attached Rept by Tlg Engineering,Inc. W/Svc List ML20059H6731994-01-20020 January 1994 Forwards Revised Rancho Seco Quality Manual, Reflecting Current Rancho Seco Pol Phase Nuclear Organization Changes ML20059E1221994-01-0303 January 1994 Forwards Amend 7 to Long Term Defueled Condition Physical Security Plan.Encl Withheld (Ref 10CFR73) ML20059C1681993-12-22022 December 1993 Forwards Suppl Info to Support Review & Approval of 930514 Proposed License Amend 186 Re Nuclear Organization Changes, Per NRC Request 1999-07-07
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L5431990-09-20020 September 1990 Requests Exemptions from Certain Requirements of 10CFR50.47(b) & 50,App E & Proposes New Emergency Plan That Specifically Applies to Long Term Defueled Condition ML20059J9161990-09-13013 September 1990 Notification of Change in Operator/Senior Operator Status for R Groehler,Effective 900907 ML20059J9221990-09-13013 September 1990 Responds to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2,Part 2, 'Vendor Interface for Safety-Related Components.' No Vendor Interface Exists for Spent Fuel Pool Liner NL-90-442, Forwards Endorsements 13 to Nelia Certificate N-49 & Maelu Certificate M-49,Endorsements 91 & 92 to Maelu Policy MF-75 & Endorsements 103 & 104 to Nelia Policy NF-2121990-09-12012 September 1990 Forwards Endorsements 13 to Nelia Certificate N-49 & Maelu Certificate M-49,Endorsements 91 & 92 to Maelu Policy MF-75 & Endorsements 103 & 104 to Nelia Policy NF-212 ML20059G0791990-09-0606 September 1990 Forwards Supplemental Fitness for Duty Performance Data, Omitted from 900725 Rept Re Random Drug Testing Results ML20059E0031990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept,Jan- June 1990, Corrected Repts & Revs to ODCM ML20059C2491990-08-27027 August 1990 Advises That M Foster & B Rausch Leaving Util Effective on 900810 & 17,respectively & Will No Longer Require Active Operator Licenses ML20056B2591990-08-20020 August 1990 Forwards Long-Term Defueled Condition Security Training & Qualification Plan. Encl Withheld (Ref 10CFR2.790) ML20056B2961990-08-10010 August 1990 Discusses 900731 Meeting Re Future of Util & Closure & Decommissioning of Facility.Request for Possession Only License Pending Before Commission ML20058Q2811990-08-0909 August 1990 Forwards Updated Listing of Commitments & long-range Scope List Items Deferred or Closed by Commitment Mgt Review Group Since Last Update ML20058N0911990-08-0707 August 1990 Notifies of Minor Change in List of Tech Specs Applicable in Plant Defueled Condition.Determined That Surveillance Requirements Table 4.1-1,Item 63 Not Required to Be Included in List of Tech Specs Applicable in Defueled Condition ML20056A2041990-07-30030 July 1990 Provides Response to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. Pressure & Differential Pressure Transmitters 1153 & 1154 Do Not Perform Any safety-related Function in Current Plant Mode ML20056A1131990-07-30030 July 1990 Apprises of Status of Plans to Use 3 of 4 Emergency Diesel Generators as Peaking Power Supplies & Responds to Questions in .Util Obtained Authorization for Operation of Diesel Generators for No More than 90 Days Per Yr ML20055J0311990-07-25025 July 1990 Forwards fitness-for-duty Performance Data for Facility from 900103-0630 ML20055J0331990-07-25025 July 1990 Notifies of Change in Operator/Senior Operator Status. Operators Terminating Employment & No Longer Require License ML20055H7561990-07-24024 July 1990 Requests Exemption from Performing Annual Exercise of Emergency Plan,Activation of Alert & Notification Sys & Distribution of Public Info Brochures,Per 10CFR50.12 Requirements ML20055H8081990-07-24024 July 1990 Forwards Decommissioning Financial Plan for Plant,Per 10CFR50.33(k)(2) & Requests Interim Exemption Re Requirement to Have Full Decommissioning Funding at Time of Termination of Operation,Per 10CFR50.12 ML20055F8421990-07-13013 July 1990 Forwards Application for Proposed Decommissioning of Plant. Util Needs Relief from Equipment Maint,Surveillance,Staffing & Other Requirements Not Necessary to Protect Public Health & Safety During Defueled Condition ML20055G9821990-07-12012 July 1990 Advises That Environ Exposure Controls Action Plan Will Be Provided by Sept 1990,per Insp Rept 50-312/90-02 ML20055E5111990-07-0606 July 1990 Notifies of Change in Operator/Senior Operator Status for D Rosenbaum & M Cooper,Effective 900622 & 29,respectively ML20055C3511990-02-14014 February 1990 Forwards Addl Info Re 900306 Response to NRC Bulletin 88-003, Inadequate Latch Engagement in Hfa Type Latching Relays Mfg by Ge. Util Will Replace Only Relays Found Not to Meet Insp Criteria ML20055C3541990-02-14014 February 1990 Forwards Updated Response to Insp Rept 50-312/88-30. Calculations for Liquid Effluent Monitors Completed & in Use & Rev to Reg Guide 4.15 in Procedure RSAP-1702 Scheduled to Be Completed & Implemented by Apr 1990 ML20248H2391989-10-0606 October 1989 Requests Exemption from Requirements of 10CFR26 Re Fitness for Duty Programs Based on Present & Future Operational Configuration ML20248H2571989-10-0606 October 1989 Responds to NRC Re Addendum to Safety Evaluation Supporting Amend 92 to License DPR-54 Re Reactor Vessel Vent Valve Testing.No Testing of Reactor Vessel Vent Valves Will Be Performed ML20248A8271989-09-25025 September 1989 Requests Permission to Submit Next Amend to Updated FSAR W/Decommissioning Plan Submittal.Extension Will Allow District to Incorporate Plant Closure Status in SAR Update to Reflect Plant Conditions Accurately ML20248D4611989-09-13013 September 1989 Responds to 890906 Request for Assessment of Util Compliance W/Ol & Associated Programs & Commitments,Per 10CFR50.54(f). Staffing Requirements for Emergency Preparedness Will Not Be Violated & Future Shortfalls Will Be Remedied ML20247G1991989-09-11011 September 1989 Requests Extension for Time Period Equivalent to That of Current Shutdown.Extension Would Result in Revised Final Expiration Date of Not Earlier than 900318.Plant Would Not Be Brought Above Cold Shutdown W/O NRC Prior Concurrence ML20247H3551989-09-0707 September 1989 Informs That Util Stands by Commitments of 890621 & 0829 Re Implementation of Closure Plan in Safe & Deliberate Manner in Compliance W/License & W/All Applicable Laws & Regulations ML20247H5541989-09-0101 September 1989 Responds to Violations Noted in Insp Rept 50-312/89-14. Corrective Actions:Stop Order on Fuel Movement Issued & Action Plan Generated on 890908 to Address Broader Issues 05000312/LER-1988-010, Forwards Rev 1 to LER 88-010,due to Change in Commitment Date for re-evaluating Fire Zones.Date Changed to 901001. Zones re-evaluated in Conjunction W/Mods to Fire Detection Annunciator Sys1989-08-23023 August 1989 Forwards Rev 1 to LER 88-010,due to Change in Commitment Date for re-evaluating Fire Zones.Date Changed to 901001. Zones re-evaluated in Conjunction W/Mods to Fire Detection Annunciator Sys ML20246A4011989-08-16016 August 1989 Forwards Rev 5 to Inservice Testing Program Plan. Changes Identified Consistent W/Guidance Provided by Generic Ltr 89-04 NL-89-593, Forwards Plant Closure Organizational Charts & Administrative Procedure RSAP-0101,per 890802 Request1989-08-15015 August 1989 Forwards Plant Closure Organizational Charts & Administrative Procedure RSAP-0101,per 890802 Request ML20245H4781989-08-10010 August 1989 Requests Exemption from Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs Because on 890607,util Board of Directors Ordered That Plant Cease Operation ML20245H1781989-08-0909 August 1989 Notifies of Change in Operator/Senior Operator Status. J Dailey & J Reynolds Terminated Employment on 890721 & 890802,respectively ML20245L1831989-08-0808 August 1989 Informs That Official Correspondence Must Be Directed to Listed Individuals Due to Reorganization of Util Following 890606 Election ML20247L9221989-07-26026 July 1989 Provides Revised Response to NRC Re Violations Noted in Insp Rept 50-312/88-33.Corrective Action:Portable Shield Walls Inspected Every 6 Months to Ensure All Safety Factors Met & Area Surveys Conducted on Weekly Basis ML20247M4121989-07-24024 July 1989 Requests Exemption from 10CFR50,App E,Section IV.F.2 to Allow Util Not to Perform Annual Emergency Plan Exercise for 1989.Request Results from Transitional Mode of Plant from Operating Plant to Plant Preparing for Decommissioning NL-89-541, Requests That Completion Date for Addl Training of Personnel Involved in Performing Work on Environ Qualified Equipment Be Extended from 890616 to 8912151989-07-14014 July 1989 Requests That Completion Date for Addl Training of Personnel Involved in Performing Work on Environ Qualified Equipment Be Extended from 890616 to 891215 ML20246P4011989-07-14014 July 1989 Informs That Evaluation of Contracts & Agreements Identified No Restrictions on Employee Ability to Provide Info About Potential Safety Issues to NRC NL-89-547, Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 1061989-07-0606 July 1989 Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 106 ML20246A9751989-06-30030 June 1989 Advises That Concerns Addressed in Generic Ltr 89-08 Inapplicable,Since Util Intends to Defuel Reactor.Generic Ltr Will Be Reviewed Prior to Placing Facility in heatup-cooldown Operational Mode for Return to Power ML20246A5171989-06-30030 June 1989 Forwards Rancho Seco Closure Plan, Per 890621 Request for Addl Info Re Plan CEO-89-289, Notifies of Change in Operator/Senior Operator Status.Listed Operator/Senior Operator Terminated Employment on Listed Effective Date1989-06-27027 June 1989 Notifies of Change in Operator/Senior Operator Status.Listed Operator/Senior Operator Terminated Employment on Listed Effective Date NL-89-526, Lists Discrepancies Noted in Amend 109 to License DPR-54,per 890615 Discussion W/S Reynolds.Tech Specs Encl1989-06-22022 June 1989 Lists Discrepancies Noted in Amend 109 to License DPR-54,per 890615 Discussion W/S Reynolds.Tech Specs Encl ML20245H4181989-06-21021 June 1989 Discusses Util Plans Re Overall Closure of Plant,Per 890615 Meeting W/Nrc.Util Will Request Appropriate Changes to Tech Specs to Reflect Defueled Mode & Will Evaluate & Request Changes to Emergency Plan ML20245D9281989-06-21021 June 1989 Discusses Activities Underway Re Plan for Closure of Plant Discussed During 890615 Meeting W/Region V.Util Intends to Continue Use of Essential Programs,Such as Preventive Maint Program,For Sys within Scope of Closure Process ML20245A0981989-06-16016 June 1989 Responds to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. No Westinghouse Plugs Used at Plant ML20248B5751989-06-0202 June 1989 Advises That Util Anticipates That Final Analysis of Thermal Striping Will Conservatively Support Surge Line Lifetime Significantly Longer than June 1994 Date,Per NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification 1990-09-06
[Table view] |
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$SMUD SACRAMENTO MUNICIPAL UTluTY DISTRICT C P. O. Box 15r330, Sacramento CA 95852-1830,(916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA JEW 87-455 March 30,1987 Director of Nuclear Reactor Regulation Attention: Frank J. Miraglia, Jr.
Division of PWR Licensing-B U S Nuclear Regulatory Commission Washington D C 20555 Docket 50-312 Rancho Seco Nuclear Generating Station Unit #1 REGULATORY GUIDE 1.97 IMPLEMENTATION STATUS
Dear Mr. Miraglia:
As requested by the Rancho Seco Project Manager, the District has reviewed the status of Regulatory Guide 1.97 implementation. In preparing this status report a review of the previous documentation was performed and resulted in the chronological listing found as Attachment 1 to this submittal. Retracing these documents reveals that the District's September 14, 1984 letter provided the dates for each of the twelve items which, at that point in time, had not yet been installed. The scheduled completion dates were determined using the District's Living Schedule. All of the original 12 open items have been, or will be, implemented prior to restart of the unit with the exception of the coolant inventory variable (14). As noted on Attachment 2 this represents an acceleration of the original schedule on several of these items.
On August 19, 1985 the staff provided an interim report on the District's .
Regulatory Guide 1.97 positions and requested additional information on eleven variables. The letters which followed this request provided additional justification as well as committing to install or upgrade several additional variables listed in Attachment 2 (6, 35, 47, 57, 62A, 45). The implementation of these new variables was scheduled as noted in Attachment 2 and all but one were subsequently accelerated per the staff's request. This brief outline and l the chronology provided in Attachment 1 provides indication that the District has been responsive, timely and cooperative with the staff in resolving the Regulatory Guide 1.97 issue. The implementation schedules provided in Attachment 2 are based on current priorities and the resources available for implementation. Therefore, the District considers the schedule described in Attachment 2 to be reasonable and acceptable for implementation of the remaining Regulatory Guide 1.97 variables.
8704060109 870330 g PDR ADOCK0500g2 P ;
8lt DISTRICT HEADQUARTERS O 6201 S Street, Sacramento CA 95817-1899 m
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. Frank J. Miraglia, Jr. March 30,1987 JEW 87-455 The staff also requested justification for interim operation without each of the variables currently scheduled for Cycle 8. Attachment 3 provides the information for each of these variables as requested.
During the performance of this review the District discovered the staff has accepted a Category 3 containment temperature monitor (SMUD Variable #57) on another Docket. A review of the particulars in that case, provided as Attachment 4, has indicated that the staff's acceptance is equally applicable to the District. Based on this review and the recent staff decision, the District intends to provide Category 3 containment temperature indication as originally committed in our July 13, 1984 letter.
Attachment 5 contains revision 4 to the District's Regulatory Guide 1.97 position paper originally submitted to the staff on September 14, 1984. The changes are mostly typographical with the exception of the changes to variables 26 and 17. These changes delete tag numbers of instruments which are non-qualified backups to the listed instruments. In addition, the change made to variable 55 provides consistency with the information in Attachment 4.
If there are any questions contact John Atwell of my staff.
Sincerely, f
ohn E. Ward Deputy General Manager, ear j Attachment cc: George Kalman, NRC - Bethesda A. D'Angelo, NRC - Rancho Seco I
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ATTACHMENT 1 REG. GUIDE 1.97 CHRONOLOGY i-The following provides a short history of ,the District's response to Regulatory Guide 1.97.
- July 13, 1984 - Letter transmitting SMUD's original Regulatory Guide.
- . 1.97 positions.
,
- September 14, 1984 - District transmittal of the revised Reg. Guide 1.97 paper incorporating the description of SPDS.
- July 9, 1985 - SMUD provided a listing of Reg. Guide items which had
! not been completed and the schedules.
- August 19, 1985 - NRC interim report on Reg. Guide 1.97 plus 11 requests for additional information.
- September 30, 1985 - The Dis.trict provided a detailed discussion of
, each item listed in the July 1985 letter.
- October 31, 1985 - SMUD.provided the responses to the questions from the NRC August 1985 letter.
.
- January 13, 1986 - SMUD provides additional information on the pressurizer level and heater current variables.
- November 12, 1986 - The District provides an updated status of the items not yet installed with accelerated implementation dates for all but 2 items. Dates were changed as a result of a meeting held with
] the staff on August 14, 1986.
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ATTACHMENT 2 , ,
MTE OF ORIGINAL VARIABLE VARIABLE COMMITNENT COMITMENT NEW NUISER* UPGRADE TO: LETTER DATE DATE ORIGINAL 14 Coolant Inventory (ICC) New 9/14/84 Cycle 8 Cycle 8 OPEN Variable (No Change)
ITEMi (Cat 1) +
4 Steam Generator Cat 1 9/14/84 Cycle.9 Restart 87 Level 5 Steam Generator Pressure Cat 1 9/14/84 , Cycle 9 Restart 87 1 RCS Hot Le'g Temperature Cat 1 9/14/84 Cycle 8 Restart 87 44 Pressurizer Level Cat 1 9/14/84 Cycle 9 Restart 87 Density Compensation N/A SPDS Upgrade Cat 1 9/14/84. Cycle 9 Restart 87 (Class 1 redundant indication)
NEW E Neutron Flux Cat 1 10/31/85 Cycle 9 Cycle 8 C0lGETMENTS MADE AFTER 35 RHR (Decay Heat) Heat Cat 2 10/31/85 Cycle 9 Cycle 8 4 NRC LETTER Exchanger Outlet (8/19/85) 47 Quench Tank (PRT) Temperature Low Range 10/31/85 Cycle 8 Cycle 8 (Remains (No Change)
Cat 3) 57 Containment Atmosphere Cat 2 10/31/85 Cycle 9 N/A Temperature (See Attachment 4). ,
l 62A Component cooling Water Cat 2 10/31/85 Cycle 9 Cycle 8 Temperature to ESF System (NSCW) 45 Pressurizer Heater Status Direct 1/13/86 Cycle.9 Cycle 8 Indication l (Remains Cat 3)
O As identified.in the District's October _31 1985 g and September 149 .198_4 - submittals.
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s t s.: v 6N Variable Jame: Coolant Inventory /Reect'or Vessel Level (14) g 4 4
- Category / Variable Type
- Category 1/ Type 3 Y w s, ..
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' Variable Purpose (R.G. 1.97):- Provide information to indicate whether plant \'
safety functions are being accomplished.- (Veriff. cation; accomplishment of ,Q'J' mitigation). [' ,
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. I c , y e,1 Justification until Cycle 8: The purpose of this variable.is the verification .. c 'g ,;
that cooling water is reacliing the core. This verification can be ok,tained~
via alternate means, direct as well as indirect, currently eva11able. The ,' ,
operator,.viaSPDS,hasavailableCategory1 variables (bot 1eptemperatpedl/W! '
hot leg level, core exit tseperature RCS pressure, pressMfgerilevel) which ')f will provide indication that adequate . cooling is being prov;de? in the cms.' r s ,
In additi6n, Category 2 subcooling margin curves are available'['.SP?S) asj W11 as Class 1 indication of Tsat and Psat in the control room. This}$.emperakure and pressure Indication anMthe flow monitoring (Category 2) of thh Lecay'f' Heat, high pressure and low iressure injection systems (SPDS) wil11 provide the W be-operator sufficient'ini%rmation to determine that, thCcore is being provide.4 t ' s adequate' cooling. Since the intended function is\ me via other variables; % /
operation during the interkperiod is cons *dered ach'tytable. ..
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ATTACHMENT 3 (CONT.)
4 < 1.Va iable Name: ~ Neutron Flux (6)
Cetegory/ Variable Type: Category 1/ Type B J' ,!
Variable Purpose (R.G. 1.97): Provide information to include whether plant s'afety Junctions are being accomplished. (Function detection; accomplishment l
of mitigation).
Justification until Cycle 8: In determining the amount of reactivity. control available to the core several methods already exist. The plant currently has excore neutron flux instrumentation, control rod position indication and boron I concentration neasurement capability via the normal and Post Accident Sampling System which could provide indication of the reactivity levels in'the core.
i s During post-accident conditions additional means of reactivity indication is available by the use of the Borated Water Storage Tank level (Category 3),
containment sump level (Category 1) and safety injection flow indication (Category 2). Thus the operator will have adequate indication during the
'interim operation period to determine that adequate reactivity control is available to the core.
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Variable Name: RHR (Decay Heat) Heat Exchanger Outlet (35) >
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q t-Variable Purpose (R.G. 1.97): Provide'information to indicate the c'peration 3 of individual safety systems and other systems important to safety. -(To 1
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monitor operation and for analysis.) - '- '
4 Justification until Cycle 8: Proper operation of the Decay Heat Removal (DHR) .'
System can be obtained from information currently available to the operator. - c The combination of the Category 3 heat exchanger outlet temperature indication
, & Category 2 ficw indication will provide the operator indication of proper ,
DHR system operationn Alternate /means are also available'using the DHR suction temperature and Nuclear-Service Cooling water differential.
temperature. . Thus adequate information is available to the operator to verify proper DHR operation during the interim period of operation.
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Variable Name: Quench. Tank (PRT) Temperature (47)
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[ Category / Variable Type:- Category 3/ Type D Variable Pur' pose (R.G.'1.97): Provide information to indicate the operation of individual safety systems and other systems important to safety. (To
, monitor operation).
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- . Justificat3on until Cycle _8
- The PRT temperature indication currently
-installed on the auction of the PRT recirculation pump has been determined to be acceptable (NRC letter dated 8/19/85) for temperature indication for this variable. The modification required to provide full compliance is the lowering of the temperature range from 1000 to 500F. Since post-accident water / steam temperatures anticipated to be relieved to the PRT would be at
. temperatures greater than 1000F, interim operation without the extended range will not be affected.
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Variable Name: Component Cooling Water Temperature to ESF System (NSCW) (62A)
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Category / Variable Type: Category 2/ Type D Variable Purpose (R.G. 1.97): Provide information to indicate the operation of individual safety systems and other systems important to safety. (To monitor operation).
Justification until Cycle 8: Proper operation of the NSCW can be determined by the use of the Class 1 pump and valve status indication. With indication of proper system alignment and the pond providing an assured source of sufficiently low temperature coolant the operator will have adequate
'information of proper system function. In addition, Category 3 NSCW temperature indication is provided which gives direct indication that heat removal by the NSCW is occurring. Thus adequate indication is available to the operator to determine proper operation of the NSCW system.
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ATTACHMENT 3 (CONT.)
Variable Name: Pressurizer Heater Status (45)
Category / Variable Type: Category.2/ Type D Variable Purpose (R.G. 1.97): Provide information to indicate the operation of individual safety systems and other systems important to safety. (To determine operating status.)
l Justification until Cycle 8: The control.of the pressurizer heater bank is i either "on" or "off" and not by modulation of the current. Thus the existing I
heater status lights will provide the operator with the state of the heaters.
- The effectiveness of the heaters can be determined by the use of the Category 1 RCS pressure and pressurizer level indications available via SPDS.
Consequently the operator has available indications which will provide a .
status of the operation of the heaters during the interim period.
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.- ATTACHMENT 4 l l
CONTAINMENT ATMOSPHERE TEMPERATURE The District has reviewed its position on variable no. 57 in light of the recent acceptance of Category 3 indication for this variable by the staff on the South Texas Project (Docket l's 50-498 & 499, SSER-2). A review of-the position taken by HL&P reveals that the indication available to the operator at Rancho Seco is comparable.
The key variables for controlling the containment building environment are radiation, hydrogen concentration and containment pressure. All of these variables have been-provided by the District as Category 1 variables. -As stated in the original District position on Regulatory Guide 1.97 (July 13, 1984) the primary variable required to show accident mitigation and.
containment integrity is containment pressure. The temperature indication is only a backup to containment pressure. This is based on the post-accident containment atmosphere pressure and temperature being coupled due to the -
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saturated conditions which would exist af ter containment spray initiation.
Therefore the post-accident containment temperature could be obtained based on the saturated containment pressure. This will provide a better indication of the general containment temperature rather than a localized temperature that
).
would be provided by' individual temperature elements.
j i To assure containment cooling is being provided, the operator has several
, indicators available. As an indicator of cooling provided by the containment spray systet instrumentation is provided for pump status (Category 2), Class 1 valve position, spray flow, spray water temperature, and containment sump
] water level (Category 1) all of which are available to the operator..
Containment cooling provided by the Reactor Building Emergency Cooling System is indicated by Class 1 fan status as well as pump and valve status for the Nuclear Service Cooling Water System.
Based on this information and the indication available to the operator, l
^
containment temperature is considered a back-up to containment pressure. As a l result of the staff's review on South Texas and the information provided here the District feels justified in providing containment temperature as a l Category 3 variable as originally presented to the staff in the District's July 13,1984 submittal.
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4 ATTACHMENT 5 REVISION TO REGULATORY GUIDE 1.97 POSITION PAPER 1
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Var. Variable Per SED SRD Compiter MC sin n). R.G. 1.97 Rev. 3 Tag Nr>a. Cat. Display hoge hnge Commenta l
HPE B VEN'.TTS corit!d.
16 ICS Pressure IT-21050 1 SIDS 0-3000 pelg Comply Same as Varlable 2 (category 1) IT-21051 IDADS i
17 Containment IE-26112 C,D 2 SIDS Top to Botton Comply See Variable 3 Sine Eter Tavel IDADS Plant See M>te I (Category 2) New 12-20509 A,B 1 Slecific 17 (category 1) Wide IE-20510 A,B i
18 -Containment IT-53621 1 SIUS 0-design Comply
, Pressure IT-53622 IDADS Pressure (Category 1) (59 poig) 19 Cont. Tao. Valve See 1 Sms Closed / Open/
Iba (excl. Table IDADS Not Closed Closed Check valves) 5.2-2 See n>te (Category 1) in IISAR 19 20 Containment IT-53621 1 SmS -5 peig Couply Same as Wriable 18 Pressure IT-53622 IDADS to dealgn (Category 11 preamire (59 pelg)
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l Var. Variable Per SBlUD Sti1D Contuter URC SMUD l 110 R.G. 1.97 Rev. 3 Tag ibs. Cat. Display Range Ramje Cor.nia:nts
'ivpg c trARTARLF9 21 Core Exit See Variable 1 SPDS 200 to Conply Living Schedule ~
Teg erature 13 TDADS 23000P Sanc as Variable 13 (Category 1) l ~22 Radioactivity Hone M/A 1/2 Tech N/A See Variable 23 l Concentration See Spec to 100 (Category 1) Note x Toch spec 22 ,
l 23 Analynis of Pass 3 10-6 to 10-6 to l Prinary Coolant 10 Ci/ml 3.75Ci/ml (Category 31 See Note 23 1
24 RCS Pressure (Category 1)
PT-21050 IT-21051 1 SPDS IDADS 0-3000 psig Conply' Sane as Variable 2 d 25 _Containnent IT-53621 1 SPDS. -5 psig'to Conply Sane as Var f able 18 Pressure PT-53622 IDADS 3 x design (Category 1) (177 tsig)
Containnr:nt LE-26112 C,n 26 Sune Ititer Level 2 SmS
- IDADS
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. Bottom conply See Ibte Sann as variable 17 g (Category 2) Urs LC-20'iO9 A,B -1 Plant 17-(Category 1) Wiele LE-20510 A,B Specific 19 Rev.' 4 '
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I I Var. Variable Per 9tD StD Compiter PRC stb No. R.G. 1.97 Rev. 3 Tag the. Cat. Display Range Range Conse:nts l; - _
TYl%.Il_YMIflRfFS Cor1L'd, -
f 39 Flow in IIPI ET-23805 2 SIDS 0-1104 Comply i System ET-23806 IDADS design flow
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(Category 2) ET-23807 (300 gpn) i EP-23808
, l 40 Plow in IPI FT-26003 2 SEDS 0-1106 Comply r
System ET-26004 IDADS dealgn flow
- (category 2) (3000 gpn) g i
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' livDS 41 Refueling E ter !!P-25001 3 ibp to Comply i Storage tank Imvel LI-25008 See Dottosa
! (Category 2) tbte (0-50')
- 41 i
42 Reactor Coolant Panels 3 Motor Comply l Fung Status If2PS, 32, Ostrent- (Motor (category 3) 33, 34, 35 Ostrent) 43 Prim. Sys. Safety XE-21520 2 IDADS Closed / Open/mt f.1ving Sciudsle
.Re1fef VaIve Pos. XE-21521 Wt Closed Ot en See (Category 2) XE-21522 Note 43 XE-21523 i XE-21524 .
XE-21525 44 Pressurizer T.7-21503A 1 - Sins Top to 0-320" f.iving Scludsle Icvel I.T-215038 IDADS Bottosa See >bte (Category 1) !?P-21503C .
(0-503") 44 1
22 Rev. 4
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I f Var. Variable Per fMD SMID Compiter M4C SMID 2
M1 R.G. 1.97 Rev. 3 Tag tes. Cat. Display hnge Enge Comments -
TYPE E VARTABIFS
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68 Containment R-15049 1 SHIS 1 to 107 Comply Same as Variable 27 I
Area bdiation R-15050 IDADS R/hr
- (Category 1) Diets i
69 Radiation R-15025 3 10-1 to Comply Estouure Rate R-15030 104 R/hr (category 3) thru' 38 Ibrtable Analyzers 70 Containment or WA WA 10-6 to WA ' Same as Variable 32 lbrge Effluent See 105u C1/cc (Category 2) mte 0-110% vent 32 design flow 71 Reactor Shield WA WA 10-6 to WA mt in Rancio Bldg. Annulus N)t In 104u C1/cc Seco Design (If in Design) Deal
te 0-110% vent
- 72 design flow 73 Condenser Air WA WA 10-6 to WA See Variables Rem. Sys. Exhaust (Category 2)
See mte 105 u Ci/cc 0-110% vent 28 and 72 k 73 design flow 9
27 Rev. 6 e
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I Var. Variable Per Ste p fMD Coopster DEC SBED Pb. R.G.1.97 Ih:v. 3 Tag tha. Cat. Display Range Hange cw ta 3YPE E VARIABfIN C6, 74 Common Plant WA WA 10-6 to WA See variables vent See 10h Ci/cc 32 asul 72
' Category 2) R>te 0-110% went 74 design flow 75 Vent from Steam R-15047 WA IDADS 10-1 to Comply
- Cen., Safety R-15048 See I*stS 103u C1/cc Rel. Valves M>te seconds 75 masa (Category 21 76 All Other~ WA WA 10-6 to WA See Variables
- in Release Ibinta See 102u Ci/cc 34, 35, 74, 77, 79 (Category 2) M>te 0-1104 vent 76 design flow 77 All ID Plant R-15001 A,B,E 3 IDADS 10-3 to See Ibtes See varJables l Release Points R-15002 A,B IWptS 102u C1/cc 32 and 75 28, 32, 33, 72 , 75 d l (Category 3) R-15004 0-110% went l R-15017 A,B design flow
! R-15044 k-15045 l
R-150046A k-15047 l
R-15048 re-15050 PP-54206 t1t-95108 tT-54612 FI-24211 78 Alttw>rne Portable 3 -
10-9 to Comply Radiohalogens & Analyzers
- 10-3u C1/cc Particulates j (category 3)
- 28 new. 4
.. - . . . . . = - .- . -
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47mriable Exe11 nation
. 72 These Radiation Monitors were installed to meet'the requirements of NUREG 073 7, Clarification -II.F.1, ~ Attachment 1, and as such, the Reg. Guide 1.97 Category classification is not applicable (accepted by the NRC in the letter dated 5/1/80, Reid to Mattimoe).
73 The condenser air jet ejector discharge is vented through1the Auxiliary Building common stack (variable 72). Therefore, this variable is not applicable as a post accident monitored i variable. In addition, the condenser air removal system is monitored by a Category 3 Type E system (see variable 281 jpg i
j 74 The. Common Plant Vent is the Auxilliary Building vent !
4 (variable 72) and, therefore, this variable is not
} applicable. The containment purge discharges through :
- dedicated vents. However, the Reactor Building purge fans are tripped off on a high radiation signal of approximately 10-8 micro Ci/cc for the particulate monitor or 10-4 micro Ci/cc for the gas monitor (variable 32, Containment Effluent
- Radiation).
4 2
75 Externally mounted radiation monitors were installed to provide combined noble gas effluent monitoring for the Steam Generator Safety-Relief Valves and Atmospheric Dump Valves (ADV) meeting the requirements of NUREG 0737, Clarification
- Item II.F.1, Attachment 1 and, as such, the Reg. Guide 1.97 category classification is not applicable (accepted by the l NRC in the letter dated 5/1/80, Reid to Mattimoe) .
- These radiation monitors, along with the Steam Generator j Safety valve and Aqv position indications (acoustic leak i detection system), and the plant computer which monitors the i number and duration of valves actuated, provide the necessary input for calculation of release rates per unit time as j '
i . required by NUREG 0737, Clarification II.F.1, Attachment 1.
1 (This is consistent with the B&WOG Reg. Guide 1.97 task .
force's generic position.) '
4 other variables which may be used to refine the calculation 3_ are steam Generator Pressure (Category 1, variables 2,12, i 16, 24, and 29)
I 76 Effluents are discharged through other monitored plant vents
, (see variables 3 2, 33, 72, 75, and 77) . Therefore, this variable is not applicable.
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,a Variable . Explanation:
55 All RB spray piping is Rancho'Seco-QA Class 1 and seismic-category 1. All piping inside the.RB is designed to ANSI B31.1.
All remaining piping and connections to the spray system are in accordance with ANSI B31.7. The controls for the pumps and all valves which are not~1ocked open are Class 1 with indication in the main control room. The District has performed single failure analysis on all active components of the RB spray system to show that the failure of any single active component will not prevent the fulfilling of the design function following a LOCA. Each train of the RB spray system also includes a non-qualified flow transmitter which provides indication in the Control Room.
The primary indication of the adequacy of the containment cooling systems are building pressure and temperature. At Rancho Seco RB pressure is Category 1 and RB temperat'ure Category 3. The Class 1 pump and valve control monitors indicate RB spray system actuation. In conclusion, the District maintains that indication of RB spray flow is a backup variable and therfore should be Category 3.
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