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MONTHYEARML20147H1371978-12-14014 December 1978 Approves Supplemental Info Re Section 3 of Fire Protection Ser,Including Installation of Thermal Insulation on Channel A,C & D Conduits,Mod of Lube Oil Pump Control Circuits Associated W/Hpis & Procedures for Diesel Generators Project stage: Other ML20127H4351985-05-16016 May 1985 Provides Info on Changes to 850515 Nuclear Svc Electric Bldg Fire Hazards Analysis Rept,Emergency Lighting Compliance to Section Iii.J of App R & Automatic Suppression of Fire Areas 81 & 82,per 850510 Meeting Project stage: Meeting ML20128N5611985-05-20020 May 1985 Summarizes 850206 Meeting W/Util Re Fire Protection.List of Attendees & Meeting Agenda Encl Project stage: Meeting ML20128Q5921985-05-24024 May 1985 Forwards Addl Requests for Exemptions from 10CFR50,App R for Auxiliary Bldg Roof Area (Fire Area 74),nuclear Svc Yard Area (Fire Area 69) & Nuclear Svc Cooling Water Surge Tank Level Switches.Encl Suppls 850228 & 0404 Submittals Project stage: Other ML20133H6371985-07-31031 July 1985 RO 85-09:on 850702,Cardox (CO2) Fire Suppression Sys Reported Inoperable for 14 Days.Sys Deenergized Due to Failure of Fire Doors to Withstand Sys Discharge Pressure W/O Opening.Latching Mechanism Changed Project stage: Other ML20198C2341985-11-0707 November 1985 Forwards Revised Requests for Exemptions from Requirements of 10CFR50,App R,Including Update of Previous Requests List of Required Mods & Respective Schedule for Installation & Addl Request Re Lack of Suppression in Control Room Project stage: Other ML20141M9551986-01-29029 January 1986 Notice of Environ Assessment & Finding of No Significant Impact Re 850228 & 1107 Requests for Exemption from 10CFR50 App R Extending Time to Reach Cold Shutdown Under Natural Circulation W/No Offsite Power to 72 H Project stage: Approval ML20141M9521986-01-29029 January 1986 Informs That Commission Requested Publication of Encl Fr Notice of Environ Assessment & Finding of No Significant Impact Re 850228 & 1107 Requests for Exemption from Subsection Iii.L of 10CFR50,App R Project stage: Approval ML20206F9071986-05-19019 May 1986 Safety Evaluation Supporting Util Request for Exemption from Requirements of 10CFR50,App R,Subsection Iii.L Re Capability to Achieve Cold Shutdown in 72 H Project stage: Approval ML20206F8801986-05-19019 May 1986 Exemption from Requirements of 10CFR50,App R,Subsection Iii.L Re Capability to Achieve Cold Shutdown in 72 H. Alternative Shutdown Capability Should Be Able to Achieve Cold Shutdown Conditions in 205 H Project stage: Approval ML20206F8651986-05-19019 May 1986 Forwards Exemption from Subsection Iii.L of 10CFR50,App R Re Capability to Achieve Cold Shutdown in 72 H & Safety Evaluation Supporting Util Request for Exemption from Subsection of 10CFR50,App R Project stage: Approval ML20215K5921987-06-17017 June 1987 Environ Assessment & Finding of No Significant Impact Supporting Requests for Exemptions from 10CFR50,App R Requirements Re Fire Protection Program Project stage: Other ML20215K5581987-06-17017 June 1987 Forwards Environ Assessment & Finding of No Significant Impact,In Response to Util Requests for Exemptions from 10CFR50,App R Requirements Project stage: Other 1985-05-24
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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
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$SMU= SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, P.O. Box 15830, Sacramento, CA 95813; (916) 452-3211 RJR-85-246 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA May 24 , 1985 Director of Nuclear Reactor Regulation Attention: Hugh L. Thompson Jr., Director Division of Licensing U.S. Nuclear Regulatory Commission Washington DC 20555 Docket 50-312 Rancho Seco Nuclear Generating Station, Unit No. 1 REO EST FOR EXEMPTION TO SOME REQUIREMENTS OF 10CFR50, APPENDIX R SUPPLEMENTAL Please find, enclosed, three additional requests for exemptions to 10CFR50, Appendix R which have been identified during the ongoing Appendix R reevaluation effort. This submittal supplements the Districts submittals of February 28,1985 (RJR 85-097) and April 4, 1985 (RJR 85-140).
AUXILIARY BUILDING ROOF AREA (FIRE AREA 74)
The first request (exemption 10) involves an exemption to Section III.G.3 requirements for fire detection and automatic suppression for the auxiliary building roof area. This exemption was referenced in the District's April 5, 1985 revised response to Generic Letter 81-12 (RJR 85-179). In this response, this exemption was described as an exemption to III.G.2, however, after further evaluation, the District has determined that the exemption is required to III.G.3.
The analysis provided in the District's ravised response to Generic Letter 81-12 described fire areas RTl and 2 as alternate j
snutdown areas since a fire in these areas could disable the I redundant control room HVAC units and result in evacuation of the '
control room. This alternate shutdown analysis is unchanged with the exception that a fire in fire area 74 (Auxiliary Building Roof) could also disabic the redundant control room HVAC units and result in evacuation of the Control Room.
NUCLEAR SERVICE YARD AREA (FIRE AREA 69)
The second request (exemption 11) involves an exemption to l Section III.G.2 for the redundant Nuclear Service Water Pumps located in fire area 69. This exemption request is a new request 1 which had not been previously identi 4
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RJR 85-246 AUXILIARY BUILDING ROOF AREA (FIRE AREA 74)
The. third request (exemption 12) involves an exemption to III.G.2~for the redundant Nuclear Service. Cooling Water Surge Tank Level Switches' loc.::Od in Fire Area 74. This exemption request is a new request which had not been previously identified.
CONTROL COMPUTER ROOM (FIRE AREA 1) AND CONTROL / COMPUTER ROOM CORRIDOR (FIRE AREA RT1)
The-District's revised response to Generic Letter 81-12 stated that exemption requests would be submitted for lack of detection and/or automatic suppression in fire area 1 (Control / Computer Room) and fire area RT1 (Control / Computer Room Corridors).
Further evaluation has determined that these exemptions are not required as follows:
- 1. Fire Area 1 - The staff's denial of a previously requested exemption (January 10, 1983) for this area stated that, "with the alternate shutdown capability installed, a suppression system is not required in the area."
2.- Fire-Area RT1 - The District is installing fire detection in the corridor area and a suppression system already exists. The detection system is currently being installed but will not be operable until July 31,
-1985. Commencing with startup from the current refueling outage and until the detection system is operable, appropriate compensatory measures in accordance with existing Technical Specifications will be maintained.
FIRE AREA RB1 AUXILIARY BUILDING The District's February 28, 1985 exemption request for-fire area RB1 (exemption request 7) stated that "...Two fire breaks are located in the corridor (045), of fire area RB1, a minimum of 20 feet apart...". The District had originally considered the installation of these fire breaks as an alternative method to separate the redundant circuits. Based on discussion with the staff on February 6, 1985, it was determined that adding additional sprinkler heads in the corridor provides greater protection. Based on this discussion, the details involving the two fire breaks were deleted from the exemption request area description and fire protection systems section. However, as a result of an oversight the discussion involving the *.wu fire breaks was not deleted-from the fire hazards analysis section.
Thus, the. District is modifying its exemption request to clarify this discussion.
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RJR 85-246 Since this' submittal is a supplement to the District's submittals
. - of February 28, 1985 and April 4, 1985 2n application fee is not required. If you have any questions concerning this submittal please 1" contact _ Larry Young at the. Rancho Seco Generating Station.
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R.J. Ro rigue AssistantGengalManager, Nuclear t
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EXEMPTION REQUEST 10 F.A. 74 AUXILIARY BUILDING ROOF FIRE DETECTION AND AUTOMATIC SUPPRESSION EXEMPTION REQUEST Per the provisions of 10CFR50.12, the District requests an exemption. from the specific requirements of 10CFR50, Appendix R, Section III.G.3 which requires fire detection and automatic suppression for the auxiliary building roof area.(fire area 74).
DESCRIPTION OF EXEMPTION 4
'Both trains of essential control room HVAC are located in the same fire area. Since both trains of essential control room HVAC share a common duct, separation as required by Appendix R,Section III.G.2 is impractical. If a fire on the auxiliary building roof damaged both trains of the control room HVAC, .the loss of HVAC could require the evacuation of the control room. Alternate shutdown is being provided for the control room area since a fire in the control room could also require evacuation of the control room. Thus, the auxiliary building roof area is considered an area requiring alternate shutdown and requires fire detection and automatic suppression per 10CFR50, Appendix R, Section III.G.3. Ne area fire detection or automatic suppression is previded in this area.
SAFE SHUTDOWN REQUIREMENTS Ato least one train of the essential control room- HVAC is required to ensure habitability of the control ~ room. Since alternate shutdown is being provided for the control room area, loss of the essential control room HVAC will only require that the alternate shutdown capability for a fire in the' control room be utilized for a~ fire on the auxiliary building roof. Thus the loss of both trains of essential control room- HVAC could require use of control room alternate shutdown capability.
FIRE AREA DESCRIPTION Fire area 74 consists of an unenclosed outside area on the auxiliary building roof with a floor area of 14,467 square feet (See Attached figure 1). The roof construction is 6 1/2" and 12" concrete with a light weight concrete cover of variable thickness. The roof slab is covered by two layers of 1-5/8" rigid insulation topped off with a fiberglass roll roofing. Wooden nailing strips which form part of the roofing system below the fiber glass roll roofing are fire retardant pressure treated. The roof covering and method of
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EXEMPTION REQUEST 10 F.A. 74 AUXILIARY BUILDING ROOF
, FIRE DETECTION'AND AUTOMATIC SUPPRESSION '
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' EXEMPTION REQUEST Per the provisions of 10CFR50.12', the District requests an exemption- -from the specific requirements of 10CFR50, Appendix. R, Section III.G.3 which requires fire detection.
'and -automatic suppression for the_ auxiliary. building roof area-(fire area 74).
DESCRIPTION OF EXEMPTION Both trains-of essential control room HVAC are' located in the same fire area. Since both trains of essential control room HVAC share a common duct, separation as required by Appendix R,Section III.G.2'is impractical. If-a fire on the. auxiliary _ building roof damaged both trains of the ,
control room EVAC, the loss of HVAC could- require the evacuation of the control room. Alternate shutdown is being
.provided -for the control room area since a fire in the
. control room could also require evacuation of the. control-room. Thus, the auxiliary building roof area is considered an_-area requiring alternate shutdown and . requires fire ~- ;
detection and automatic suppression per 10CFR50, speandix R, ~
Section III.G.3. No area fire- detection or automatic suppression is provided in this area.
SAFE SHUTDOWN REQUIREMENTS At -least one train of the' essential control room EVAC is required to ensure habitability'oflthe control room. Since alternate shutdown is being provided for the control room area, -loss of the essential control room EVAC will only require that the alternate shutdown capability'forla fire in the control room be utilized-for a fire on the auxiliary bui] ding roof. Thus the loss of both trains of essential control room HVAC could require use. of control- room alternate shutdown capability.-
FIRE AREA DESCRIPTION Fire area 74 consists of an unenclosed outside area on the auxiliary building roof with a floor area of 14,467 square feet (See. Attached figure 1). The roof construction is 6 ;
1/2" and'12"' concrete with a light weight concrete cover of variable thickness. The roof slab is covered by two layers of 1-5/8" rigid insulation topped off with a fiberglass roll roofing. Wooden nailing strips which form part of the roofing system below the fiber glass roll roofing are fire retardant pressure treated. The roof covering and method of~
y installation results' in - a class "A" roof covering which will notusupport combustion.
Access to the-roof area is through the Number 2 stairwell exit enclosure with a l~1/2 hour rated door provided with a security 11ock and door position switch. There are numerous HVAC. duct-Lpenetrations through the roof with no fire dampers.
The combustible inventory on the roof area consists - of 15 gallons- of lubricating oil in the compressor casings of the refrigeration condensing units (7.5 gallons / compressor) 'and 2024 pounds; of charcoal in the filtration units (1012 lbs/ unit). Since_the charcoal is totally-enclosed in filter canisters which are contained within the steel filter unit housings, the derated equivalent is only 101.5 pounds per filter units. This results in a fire loading of 330 BTU / square foot. corresponding to a_1 minute fire. Since the roof.is not an enclosed room, the maximum-fire severity would occur as.a transient condition. The peak temperature will be localized at the location of the combustible
. material since. the heat dissipates into the atmosphere immediately in-the absence of an enclosed space.
FIRE-PROTECTION SYSTEMS There are no area detection or suppression systems in the-
. fire area. Local heat detectors are provided in the charcoal.
filter housing. Portable CO2 extinguishers and a fire hose station are' located in the turbine level corridor (FA RTl).
FIRE HAZARDS ANALYSIS.
The total fire loading in fire area 74 consists of 15 gallons- of lubricating oilland 2024 pounds of charcoal
- (derated to 203 lbs). This results in an average fire loading' of 330 BTU / square feet which corresponds to a one minute ~ fire. Electrical cables'are routed ~in conduit and do not contribute to the combustible. ' inventory. The combustible ~ inventory is enclosed in a seismic category 1 structure. This area is not used for routine traffic- or
. storage of combustible -materials and hence transient combustibles.are not of concern.
Since the combustible inventory is enclosed within seismic-
. category. 1 structures and is not exposed to an external ignition -source, the _probatility of a fire occurring is extremely remote. _ Based on-the nature of the combustibles and the. outdoor' unenclosed area, if a fire occurred it would be of' short duration with heat and combustion products rapidly dissipating- to the atmosphere. Since the area is outside and subject to rain,~no damage is expected to result from normal' fire-suppression activities.
CONCLUSION The District concludes that although not in strict compliance with Appendix R,Section III.G.3 the control room HVAC units are adequately protected from a fire that could disable both trains.- Modification by the installation of
~
fire detection and automatic suppression would not significantly enhance the fire protection features provided by the~ existing configuration. Thus, the District requests an exemption.to 10CFR50, Appendix R, Section III.G.3 for the existing configuration.
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EXEMPTION REQUEST 11 FA 69 NUCLEAR SERVICE WATER PUMPS FIRE DETECTION AND AUTOMATIC SUPPRESSION EXEMPTION REQUEST. '
.Per. the provisions of 10CFR50.12, the District requests an exemption for Rancho Seco from the specific requirements of
' Appendix R, Section III.G.2, requiring one of the following forms of protection for the redundant Nuclear Service water pumps.-
- 1. . Separation by a 3-hour rated fire barrier.
- 2. Separation by at least 20 feet of horizontal distance without intervening combustibles with fire detection and automatic suppression.
- 3. Enclosure of cables and equipment and associated non-safety circuits of one-redundant train in a 1-hour rated fire barrier with fire detection and automatic suppression.
DESCRIPTION OF EXEMPTION The redundant Nuclear Service Water Pumps are located in the same fire area. The pumps are separated by approximately 55 feet with no intervening combustibles. Power circuits to the ~ pumps are routed underground, in separate conduits, duct banks, and manholes except in 'he immediate vicinity of the pumps. Although the redundan . trains are separated by approximately 55 feet without intervening combustibles, no fire detection or automatic suppression is provided.
SAFE SHUTDOWN REQUIREMENT At least one train of Nuclear Service Water is required to be operable in order to achieve and maintain hot and cold shutdown conditions.
FIRE AREA DESCRIPTION Fire area 69 is an outside, fenced-in area which contains the Nuclear Service yard equipment. This 20,500 square foot area is surrounded on three sides by an unrated, 8-foot high, cinder block wall supporting a chain link fence. The remaining portion of the perimeter consists of the adjoining reactor and auxiliary building walls.
Located in the eastern portion of this area are the Nuclear Service Water Pumps. The pumps are separated by approximately 55 feet without intervening combustibles.
Additionally, the 40 foot diameter Borated Water storage tank (T-250) is located between the pumps. (See Figure 2, attached)
' FIRE PROTECTION SYSTEMS Manual fire fighting equipment-is located within the fire area.
FIRE HAZARDS ANALYSIS The total fire loading in Fire Area 69 consists- of approximately 20 gallons'of oil and approximately 467 pounds Eof Lcable insulation. .This results in. an average fire loading of-2930-BTU / square foot, which if totally consumed wotid_ correspond to a fire severity of 2 minutes on the ASTM E-119 standard time-temperature curve.
The cables for each pump are routed underground in separate conduits, duct banks and manholes. Additionally, the pumps are--separated by tha Borated Water Storage Tank which would act as a' radiant: heat shield.
Based on the lack of combustibles in the immediate area of the .pwnps _ as well as a lack- of ignition source, the probability of a fire occurring is extremely' remote. _Since the pumps are separated by approximately 55 feet and the Borated Water _ Storage Tank ~, a single fire involving one pump would not damage the redundant pump. Since the area is outside and unenclosed, any products of combustion and heat ~
produced by a- fire would' immediately . dissipate to the atmosphere. Since__the area is located outside and subject to 1 rain, no damage'is: expected to result from normal fire 4 suppression activities.
CONCLUSION ,
The District concludes that,' .although not in strict compliance with Appendix R, Section:III.G.2, .the Nuclear Service Water Pumps are adequately protected against a fire
' disabling both trains. Modification. of the system by-
-relocation, installation of a rated barrier or addition of detection 'and suppression would-not significantly enhance
.the fire protection. features provided by the existing configuration. Thus the District requests an exemption to-10CFR50, Appendix R, 'Section III.G.2 for the existing configuration.
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EXEMPTION ~ REQUEST 12 ;
FA 74- l NUCLEAR SERVICE COOLING WATERJSURGE TANKS
~ FIRE' DETECTION AND AUTOMATIC SUPPRESSION EXEMPTION ~ REQUEST Per- the provision of 10CFR50.12,- the District requests an exemption for Rancho Seco from the specific requirements of-
- ' Appendix R, section III.G.2 which requires one of .the
.following forms of protection-for the redundant Nuclear Service-Water Surge Tank Level. Switches and circuits located on the auxiliary building roof.
- 1. Separation by a 3-hour rated barrier.
- 2. Separation by at least 20 feet of horizontal distance without intervening combustibles with detection and automatic suppression.
3.. Separation by a 1-hour rated barrier with detection and automatic suppression.
DESCRIPTION OF EXEMPTION The'-Nuclear Service Water Surge Tanks are located on the auxiliary building roof. The associated level switches and circuits are separated by approximately 40 feet of horizon-tal' separation with no intervening combustibles. Although
-separated by: greater than 20 feet.without intervening com-bustibles, no area fire detection or automatic suppression is provided.
SAFE SHUTDOWN' REQUIREMENT At least one train of the Nuclear Service Cooling Water is required ~to remain functional to achieve.and-maintain hot and cold shutdown conditions. A~ fire' induced short in-the
-surge tank- level switch curcuit could trip the associated pump. Thus at least 'one train. of Nuclear Service Water : Surge-Tank level instrumentation is required.
Fire Area Description Fire area 74 consists of an unenclosed outside area on the
. auxiliary . building roof with a floor area of 14,467 square feet- -(See attached Figure 1). The roof construction is' 6 1/2" and 12"~ concrete with a light weight concrete cover of variable thickness.
The roof . slab is covered by two layers of 1-5/8" rigid i insulation topped off with a fiberglass roll roofing.-
Wooden " nailing- strips which form a part of the roofing system' below the fiberglass roll roofing are fire retardant pressure ' treated. The: roof covering- and method- of
l a
l installation result in a class "A" roof covering which will ,
not support combustion. '
Access to the roof area is through the Number 2 stairwell exit enclosure with a-1 1/2 hour rated door provided with a security lock and door position switch. There are numerous HVAC duct penetrations through the roof with no fire dampers.
The tanks are located on the south central portion of the open roof area of the auxiliary building (FA-74). They are separated on the east, south, and west sides by a metal louvered screen wall. Access from the north is prevented by a combination of- louvered screen walls and the essential control room HVAC. The resulting enclosure is approximately 70 x'30 feet with the only access through a short section of the west screen.
FIRE PROTECTION SYSTEMS There are no area detection or suppression systems in the fire area. Local heat detectors are provided in the charcoal filter housings. Portable CO2 extinguishers and a fire hose station are located in the turbine level corridor (FA RTl).
FIRE HAZARDS ANALYSIS The total._ fire loading in fire area 74 consists of 15 gallons of lubricating oil and 2024 pounds of charcoal (derated- to 203 lbs). This results in an average fire loading .of 330' BTU / square feet which corresponds to a one minute fire. Electrical cables are routed in conduit and do not contribute to the combustible inventory. The combustible inventory is enclosed in a seismic category. 1 structure. This area is not.used for routine traffic or storage of combustible materials and hence transient combustibles are not of concern.
Since the combustible inventory is enclosed within seismic category 1 structures and.is not exposed to an external.
ignition source, the probability of a fire occurring is extremely remote. Based on the nature of the combustibles and the outdoor unenclosed area, if a fire occurred it would be of short duration with heat and combustion products rapidly dissipating to the atmosphere. Since the area is outside and subject to rain, no damage is expected to result from normal fire suppression activities.
CONCLUSION The District concludes that, although not in strict compliance with Appendix R,Section III.G.2, modification by relocation, protection by a three hour rated barrier, or addition of detectors and automatic suppression will not
F.
significantly enhance the level of fire protection provided by: - the existing configuration.. Therefore, the District
-requests an exemption to 10CFR50, ' Appendix R, Section
'III.G.2 ~.to the extent it requires detection and autoristic suppression protection the redundant Nuclear Service Cocling
-Water Surge Tank level for switches and citcuits.
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