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MONTHYEARML20127H4351985-05-16016 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:NRC TO UTILITY
MONTHYEARML20059N3331990-10-0202 October 1990 Forwards Notice of Consideration of Issuance of Amend to OL & Proposed NSHC Re 900426 Application for Possession Only License ML20059M6871990-09-14014 September 1990 Forwards Notice of Consideration of Issuance of Amend & Proposed NSHC Re Plant Physical Security Plan for Long Term Defueled Condition ML20059G9421990-09-10010 September 1990 Forwards Amend 115 to License DPR-54 & Safety Evaluation. Amend Revises License Condition Re Fire Protection Plan,Adds Administrative Controls to Tech Specs in Support of Fire Protection Plan & Relocates Fire Protection Requirements ML20056B4621990-08-22022 August 1990 Forwards Environ Assessment & Finding of No Significant Impact Re 900724 Request for Exemption to 10CFR50.47 ML20058N6461990-07-31031 July 1990 Forwards Insp Rept 50-312/90-11 on 900527-0706.No Violations Indentified ML20055E5151990-07-0303 July 1990 Requests Listed Addl Info on Licensee 900606 Plans Re Diesel Generator Operation as Peaking Power Supplies to Assure That Generators Will Be Maintained in Nondegraded Status IR 05000312/19900101990-07-0303 July 1990 Forwards Security Insp Rept 50-312/90-10 on 900611-22.No Violations Noted.Major Areas Inspected:Physical Protection. Rept Withheld (Ref 10CFR2.790 & 73.21) ML20055D5441990-06-28028 June 1990 Forwards Request for Addl Info Re 891129,900221 & 0327 Ltrs Concerning Computerized Commitment Tracking Sys,Long Range Scope List & Effluents & Water Mgt Project Action Plan Items Needing Deferral ML20248D3411989-09-25025 September 1989 Forwards Amend 8 to Indemnity Agreement B-66,reflecting Changes to 10CFR140,effective 890701 ML20248G7031989-09-21021 September 1989 Forwards Enforcement Conference Rept 50-312/89-16 on 890915 ML20248G5731989-09-21021 September 1989 Forwards Insp Rept 50-312/89-12 on 890801-04,21-25 & 30.No Violations or Deviations Noted.Concerns Raised Re Contamination Control Practices,Instrumentation Control & Informal Use of Vendor Data for Liquid Effluent Release ML20248B4131989-09-19019 September 1989 Provides Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exam to Be Administered on 891004.Map of Area,List of Lodging in Immediate Area & Preliminary Instructions for Taking Exam Encl ML20248C8401989-09-11011 September 1989 Forwards Insp Rept 50-312/89-14 on 890828-0901.Concern Raised Re Apparent Decrease in Level of Emergency Preparedness.Enforcement Action Will Be Subj of Separate Correspondence ML20247C4931989-09-0606 September 1989 Informs That 890901 Insp Determined That Preparedness to Respond to Emergency Was Degraded.Violation Involved Failure to Assign Individuals Qualified Per EPIP to Critical Emergency Response Position ML20247B7561989-09-0606 September 1989 Advises That Response to Generic Ltr 88-17 Re Expeditious Actions for Loss of DHR Acceptable.Training Program Should State That Maint Personnel Included in Program & Daily Walkdowns of Tygon Tube Areas Should Be Performed ML20246K4581989-08-18018 August 1989 Forwards Insp Rept 50-312/89-10 on 890603-0721.No Violations Noted ML20247H5551989-07-21021 July 1989 Advises That Util 890511 Response to SALP Meeting Rept 50-312/88-39 Appropriate & No Changes to 890328 SALP Board Rept Deemed Necessary ML20247F0291989-07-20020 July 1989 Redistributed Forwarding Amend 112 to License DPR-54.Amend Revises Tech Specs Re Increasing Max Closure Time for Selected Containment Isolation Valves & Addition of 12 Valves to Table 3.6-1 ML20247B4031989-07-19019 July 1989 Forwards Errata to Amends 109,110 & 111 to License DPR-54, Correcting Omission of Language from Revised Pages ML20247B2961989-07-17017 July 1989 Forwards Amend 112 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Increase Max Closure Time for Selected Containment Isolation Valves & Add 12 Valves to Table 3.6-1 ML20247J0581989-07-12012 July 1989 Forwards Insp Rept 50-312/89-08 on 890422-0602.No Violations or Deviations Noted ML20246D5241989-07-0707 July 1989 Forwards Request for Addl Info Re 10-yr Internal Inservice Insp Program Plan.Response Requested within 45 Days of Ltr Receipt ML20247A0471989-07-0606 July 1989 Forwards Insp Rept 50-312/89-11 on 890629-30.No Items of Noncompliance Noted IR 05000312/19890011989-06-30030 June 1989 Ack Receipt of Responding to Violations Noted in Insp Rept 50-312/89-01.Reasons for Denial of Violations a & B.2 Will Be Reviewed During Future Insp ML20246B0911989-06-28028 June 1989 Forwards Exemption from Requirements of 10CFR20,App a, Footnote d-2(c) to Allow Use of Radioiodine Protection Factor of 50 for MSA GMR-I Canisters at Plant,Per 881117 Request.Notice of Environ Assessment Also Encl ML20245J3301989-06-22022 June 1989 Provides Background Info on Regulatory Analysis Supplementing NRC Proposed Backfit,Per 890413 Request.Util Expected to Provide Schedule for Implementation of Required Improvements ML20245E0961989-06-20020 June 1989 Forwards Amend 111 to License DPR-54 & Safety Evaluation. Amend Revises Section 2.C.(4) of License Re Fire Doors & Dampers Based on Reevaluation of Fire Areas in Uitl 1985 Updated Fire Hazards Analysis ML20245F5731989-06-20020 June 1989 Advises That Senior Reactor Operator Licensing Writtem Exams & Operating Exams Scheduled for 890905 & 06-19,respectively. Encl Ref Matl Requested by 890710 in Order to Meet Schedule ML20245A1831989-06-0909 June 1989 Forwards Amend 110 to License DPR-54 & Safety Evaluation. Amend Removes Tabular Listing of Snubbers from Tech Specs as Suggested by Generic Ltr 84-13 NUREG-0460, Forwards Safety Evaluation & Inel Rept EGG-NTA 8341, Providing Details & Basis for Concluding That Existing Intervals for on-line Functional Testing at Plant Should Result in High Reactor Trip Sys Availability.W/O Inel Rept1989-06-0606 June 1989 Forwards Safety Evaluation & Inel Rept EGG-NTA 8341, Providing Details & Basis for Concluding That Existing Intervals for on-line Functional Testing at Plant Should Result in High Reactor Trip Sys Availability.W/O Inel Rept ML20248B9451989-06-0505 June 1989 Forwards Amend 109 to License DPR-54 & Safety Evaluation. Amend Revises Tech Spec 4.17, Steam Generators & Associated Bases & Tables 4.17-2A & 417-2B to Permit Repairs of Steam Generator Tubes by Means of Tube Sleeves ML20248B9191989-06-0505 June 1989 Forwards Amend 107 to License DPR-54 & Safety Evaluation. Amend Removes Requirements for Fire Suppression Sys in Fire Zones 75-80 from Tech Spec 3.14 ML20248B6091989-06-0505 June 1989 Forwards Amend 108 to License DPR-54 & Safety Evaluation. Amend Modifies Paragraph 2.C.(3) to Require Compliance W/ Amended Physical Security Plan ML20248B6611989-06-0202 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/89-04 ML20247P1571989-05-30030 May 1989 Forwards Safety Evaluation Accepting Util 831104 Response to Item 4.5.2 of Generic Ltr 83-28, Reactor Trip Sys Reliability ML20247J1831989-05-25025 May 1989 Forwards Notice of Withdrawal of 860613 Application for Amend to License DPR-54 to Modify Tech Specs Pertaining to Deletion of Nonradiological Items Contained within App B Tech Specs & LER Clarifications ML20247K7061989-05-23023 May 1989 Forwards Amend 105 to License DPR-54 & Safety Evaluation. Amend Clarifies Operational Mode of Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Train & Revises Frequency for Verifying Auxiliary Feedwater Sys Flow Path ML20247M9001989-05-23023 May 1989 Forwards Amend 106 to License DPR-54 & Safety Evaluation. Amend Revises Tech Spec 4.17, Steam Generators, to Provide for More Extensive Insp of Steam Generator Tubes by Defining Tube Areas to Complete 100% Insp Where Degradation Expected IR 05000312/19890051989-05-17017 May 1989 Forwards Insp Rept 50-312/89-05 on 890304-0421.Two Noncited Violations Noted ML20247K6621989-05-16016 May 1989 Forwards Amend 104 to License DPR-54 & Safety Evaluation. Amend Deletes Tech Specs Re Reactor Vessel Matl Surveillance.Approval to Use B&W Integrated Reactor Vessel Matl Surveillance Program,Per 851014 & s,Approved IR 05000312/19880021989-05-12012 May 1989 Discusses Insp Rept 50-312/88-02 on 880104-14,0210-12 & 0307-09.Violations Noted.Advises That Violations Demonstrated Lack of Mgt Control Over Certain Aspects of Procurement Program.Enforcement Action Not Necessary ML20247B1341989-05-12012 May 1989 Forwards State of CA 1987 Environ Radiological Measurements Rept,Per Cooperative Agreement NRC-32-83-684.No Outstanding Concerns Identified in Data Comparisions Between Util & State Measurements ML20246M6271989-05-11011 May 1989 Advises That plant-specific Reactor Coolant Pump Trip Setpoint Development,Per TMI Action Item II.K.3.5, Acceptable,Based on Methodology Contained in Generic Ltr 86-05 IR 05000312/19890061989-05-11011 May 1989 Forwards Safeguards Insp Rept 50-312/89-06 on 890424-28.No Violations Noted.Evaluation of Plant Security Sys Conducted Through Extended Augmented Sys Review Requested.Rept Withheld (Ref 10CFR2.790(d)) ML20246P4801989-05-10010 May 1989 Advises of Locations & Features That Geologists Need to Inspect for Completion of Review of Sept 1987 Response to NRC Questions on Geologic & Seismologic Conditions ML20246M1741989-05-0808 May 1989 Submits Addendum to Safety Evaluation Supporting Amend 92 to License DPR-54,per Util 881129 Request to Revise Safety Evaluation.Approval to Extend Refueling Interval as Applies to Reactor Vessel Vent Valve Granted ML20246F4631989-05-0404 May 1989 Forwards Safety Evaluation & Technical Evaluation Rept Supporting Util Inservice Testing Program for Pumps & Valves.Certain Relief Requests Denied Where Proposed Alternative Testing Unacceptable ML20246H9151989-04-28028 April 1989 Forwards Insp Rept 50-312/89-07 on 890417-21.No Violations Noted ML20245J9031989-04-25025 April 1989 Advises of Special Emergency Operating Procedure Insp Program.Initiative Includes Team Insp of B&W Plants Not Insp Under 1988 Initiative ML20245F8771989-04-18018 April 1989 Forwards Amend 103 to License DPR-54 & Safety Evaluation. Amend Revised Tech Specs by Changing Air Flow Rate Through Reactor Bldg Purge Valves,Adding Requirement to Test Reactor Bldg Purge Exhaust HEPA Filters 1990-09-14
[Table view] Category:OUTGOING CORRESPONDENCE
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 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 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 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 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 ML20237A6031998-08-0707 August 1998 Forwards Insp Rept 50-312/98-03 on 980706-09.No Violations Noted ML20236Q9461998-07-15015 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-02 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 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 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 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 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 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 ML20140G6341997-05-0707 May 1997 Forwards ERDS Implementation Documents Including Data Point Library Updates for McGuire Number 224,WNP2 Number 225, Beaver Valley Number 226 & Calvert Cliffs Number 227. W/O Encl ML20140E6911997-04-25025 April 1997 Forwards Insp Rept 50-312/97-02 on 970331-0403.No Violations Noted ML20137C7211997-03-21021 March 1997 Forwards Insp Repts 50-312/97-01 & 72-0011/97-01 on 970224-27.No Violations Noted ML20129G7431996-09-27027 September 1996 Forwards Insp Repts 50-312/96-03 & 72-0011/96-01 on 960909-12.No Violations Observed ML20059J9771994-01-14014 January 1994 Informs That Document Rancho Seco ISFSI Sar,Vol Iv,Drawings & Calculations Submitted on 931027,w/Pacific Nuclear Fuel Services Group Affidavit of 931006 Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5),as Requested ML20058D6291993-11-19019 November 1993 Forwards Exemption from Requirements of 10CFR140.11(a)(4) to Extent That Primary Financial Protection in Stated Amount Shall Be Maintained ML20058C9721993-11-0202 November 1993 Ack Receipt of Transmitting Rev 6 of Section 5 to Plant Emergency Plan.Advises Revised Emergency Plan Continues to Meet Planning Stds in 10CFR50.47(b) & Requirements of 10CFR50 App E ML20057D1841993-09-27027 September 1993 Grants Exemption from Requirements in 10CFR50.120 to Establish,Implement,& Maintain Training Programs,Using Sys Approach to Training,For Categories of Personnel Listed in 10CFR50.120.Exemption Effective 931122 & Encl IR 05000312/19930031993-09-24024 September 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/93-03 ML20057A3251993-09-0202 September 1993 Forwards Environmental Assessment & Fonsi Re Exemption from Requirements of 10CFR50.120 at Plant ML20057C4971993-09-0202 September 1993 Forwards Insp Rept 50-312/93-06 on 930819.No Violations or Deviations Noted ML20056F0011993-08-11011 August 1993 Forwards Mgt Meeting Rept 50-312/93-04 on 930727 ML20056G0041993-06-25025 June 1993 Submits Info Re Implementation of Training Rule 10CFR50.120 for Licensees of Plant in Decommissioning Process ML20127D3451993-01-0808 January 1993 Advises That 921105 Rev 3 to Rancho Seco Security Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan ML20127D3351993-01-0606 January 1993 Ack Receipt of 921105 & 30 Ltrs,Transmitting Rev 6 & Suppl 1 to Physical Security Plan.Changes Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan ML20126E2751992-12-10010 December 1992 Forwards Insp Rept 50-312/92-07 on 921110-11.No Deviations or Violations Noted ML20062G9951990-11-15015 November 1990 Forwards Insp Rept 50-312/90-14 on 901003-04,09-11 & 1102. Violations Noted But Not Cited ML20062C1921990-10-24024 October 1990 Advises That Commissioner Jr Curtiss Will Visit Facility on 901105 to Tour Plant & Meet W/Util Mgt & Personnel to Review General Status of Activities.W/Certificate of Svc.Served on 901024 ML20058G4471990-10-18018 October 1990 Forwards Sept 1990 Rept to Commission on Implementation of TMI Action Plan Items,Per 900320 Commitment.W/O Encl.Review Concluded for All But Two Units ML20059N3331990-10-0202 October 1990 Forwards Notice of Consideration of Issuance of Amend to OL & Proposed NSHC Re 900426 Application for Possession Only License ML20059M6871990-09-14014 September 1990 Forwards Notice of Consideration of Issuance of Amend & Proposed NSHC Re Plant Physical Security Plan for Long Term Defueled Condition ML20059G9421990-09-10010 September 1990 Forwards Amend 115 to License DPR-54 & Safety Evaluation. Amend Revises License Condition Re Fire Protection Plan,Adds Administrative Controls to Tech Specs in Support of Fire Protection Plan & Relocates Fire Protection Requirements ML20056B4621990-08-22022 August 1990 Forwards Environ Assessment & Finding of No Significant Impact Re 900724 Request for Exemption to 10CFR50.47 ML20056A5991990-08-0303 August 1990 Responds to Re Interaction of NRC W/Util to Facilitate Expeditious Closure of Plant.Nrc Continuing to Work Expeditiously on Number of Other Requests from Util. Prioritization Schedule Developed for Pending Applications ML20058N6461990-07-31031 July 1990 Forwards Insp Rept 50-312/90-11 on 900527-0706.No Violations Indentified ML20055G9791990-07-20020 July 1990 Responds to Expressing Concern Re Issuance of Possession Only License Amend.Nrc Project Manager Will Notify by Telephone When Util Submits Application Matl for Possession Only License Amend ML20055E5151990-07-0303 July 1990 Requests Listed Addl Info on Licensee 900606 Plans Re Diesel Generator Operation as Peaking Power Supplies to Assure That Generators Will Be Maintained in Nondegraded Status IR 05000312/19900101990-07-0303 July 1990 Forwards Security Insp Rept 50-312/90-10 on 900611-22.No Violations Noted.Major Areas Inspected:Physical Protection. Rept Withheld (Ref 10CFR2.790 & 73.21) ML20055D5441990-06-28028 June 1990 Forwards Request for Addl Info Re 891129,900221 & 0327 Ltrs Concerning Computerized Commitment Tracking Sys,Long Range Scope List & Effluents & Water Mgt Project Action Plan Items Needing Deferral ML20058K5791990-05-22022 May 1990 Final Response to FOIA Request for Records.App G & H Records Available in Pdr.App H & Releasable Portions of App J Documents Encl.App I Records Withheld in Entirety & App J Record Partially Withheld (Ref FOIA Exemptions 5 & 7) ML20055D6511990-05-10010 May 1990 Partial Response to FOIA Request for Info.App D & Releasable Portions of App E Documents Encl.Portions of App E Documents & App F Documents Withheld (Ref FOIA Exemptions 5,6 & 7) ML20248D3411989-09-25025 September 1989 Forwards Amend 8 to Indemnity Agreement B-66,reflecting Changes to 10CFR140,effective 890701 1999-08-31
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.,' NAY 2 01985 Docket No. 50-312 Mr. Ronald J. Rodriguez Assistant General Manager, Nuclear Sacramento Municipal Utility District 6201 S Street P. O. Box 15830 Sacramento, California 95813
Dear Mr. Rodriguez:
SUBJECT:
SUMMARY
OF MEETING HELD ON FEBRUARY 6,1985 WITH SACRAMENTO MUNICIPAL UTILITY DISTRI P i0 DISCUSS FIRE PROTECTION Sacramento Municipal Utility District (SMUD, the licensee) had initiated a complete re-evaluation of Rancho Seco's conformance.with the requirements of 10~CFR Part 50 Appendix R.
. As a result of the re-evaluation, the licensee found a number of additional areas where they concluded exemptions were required. The purpose of the meeting was to provide the licensee the opportunity of discussing with the staff the exemptions and obtaining staff comments prior to submitting their exemption request. The attendees list (enclosure 1), and copies of some of the hand out from the meeting (enclosure
- 2) are attached.
The licensee stated that they had 3 areas of concern where they were not sure an exemption is required and 9 exemptions to discuss. During the discussion the licensee used video tape to illustrate problem areas. The licensee stated that the exem'ption request will be submitted within a few weeks. In addition, the licensee stated that their requested target date for a decision on the exemptions was start up from the refueling outage scheduled to stv t
- in March, 1985. The expected ts' art up date was early in June,1985. The staff comments are as follows:
- 1. We indicated that since there will be no automatic suppression or fire detection for the NSEB roof area an exemption will be required. We further noted that since the area below the roof is a non safety area, the effect of a fire in this area on the redundant safety systems on the roof should be addressed.
- 2. We agreed with the licensee an exemption is not required for the contsinment hatch and purge valves.
- 3. We stated that since they do not propose to provide detection and entomatic sprinklers in the nuclear service raw water pump area an a.temption will be required.
4 With regard to an exemption from the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> requirement to achieve cold shut down, we indicated that their approach for justifying the exemption appears reasonable, hF
.? ..
Rancho Seco Meeting Summary 5. With regard to the RCP Oil Collection proposed exemption we suggested that the licensee describe where material in the normal sump flows to when the oil collection system overflows.
- 6. We stated that a sprinkler system and detection system will probably be needed for the Auxiliary Feedwater Pumps for fires adjacent to the pumps.
- 7. With regard.to the auxiliary feed water valves we indicated that they probably would have to install a cable tray fire break.
- 8. With regard to the Auxiliary Building Penetration Area a sprinkler will be required in the hallway opening.
Sincerely, 0:feind **cd W Sydney Miner, Project Manager Operating Reactors Branch #4 Division of Licensing Encl'osure: As Stated-cc w/ enclosure:
See next-page ORB #4:DQ, C :ENG SMinepe/F' RF#guson
-5/t0/85 5/2p/85
ENCLOSURE 1 LIST OF ATTENDEES FIRE PROTECTION FEBRUARY 6, 1985 NAME ORGANIZATION Sydney Miner NRC/DL Bob Dieterich SMUD Elizabeth A. Kleinsorg IMPELL Robert L. Ferguson NRR/DE David Abbott SMUD Larry D. Young UESC/SMUD Bob Daniels SMUD Ken Scown IMPELL Bob Sherman IMPELL Douglas B. Wood BECHTEL Tarlochan Singh SMUD Ray Green BABCOCK & WILC0X John J. Vella BECHTEL POWER CORP.
John Stang NRR/DE Victor Benaroya NRR/DE/CMEB Leon Whitney IE/00ASIP/ORPB/ SECT 1 Jerry Wilson NRR - ASB Joe Holonich NRR - ASB
ENCLOSURE 2
~:DEX CONCERNS
- 1. NSEB ROOF
- 2. RB HATCH AND PURGE VALVE
- 3. NSRW PUMPS EXEMPTIONS
- 1. ACHIEVE COLD SHUTDOWN CONDIT0NS WITHIN 72 HOURS WITH LOSS OF 0FFSITE POWER
' 2. F.A. 68 - REACT 0R COOLANT PUMP OIL COLLECTION SYSTEM CAPACITY'0F COLLECTION TANKS
- 3. F.A. 69 - AUXILIARY FEEDWATER PUMPS - LACK OF SEPARATION
) 4. F.A. 69 - AUXILIARY FEEDWATER VALVES -
INTERVENING COMBUSTIBLES
- 5. F.A. 68 - CABLES INSIDE CONTAINMENT, ELECTRICAL
-PENETRATION AREA - INTERVENING COMBUSTIBLES
- 6. F.A. RGI - AUXILIARY BUILDING ELECTRICAL PENETRATION AREA - ONE-HOUR RATING OF CABLE -
FIRE BARRIER
. 7. FIRE AREA RB1 - AUXILIARY BUILDING (-)20'-0"
- l- LACK OF AUTOMATIC SUPPRESSION i
- 8. CONDUIT PENETRATIONS THROUGH FIRE BARRIERS -
INTERNAL SEALS-J l 9. HVAC DUCTS BETWEEN FIRE AREAS - NO FIRE DAMPERS 1
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7 I.
, FIRE AREAe 91-2 DESCRIPTION: NSEB ROOF EXEWTION FROM APPENDIX "R", SECTION III.G.2 SEPARATION: HORIZONTAL SEPARATION OF APPROXIMATELY 44 FEET SUPPRESSION: NONE DETECTION: NONE i
, REDUFOANT CDWONENTS: HVAC UNITS FOR NSEB (U-S03A AND B)
WHIOi PROVIDE SUPPORT FOR CONTROL ROOM HVAC POWER SUPPLIES.
2 FIRE LOAD: INSIGNIFICANT BTU /FT INSIGNIFICANT MINUTES f -g JUSTIFICATION FOR EXEMPTION:
OUTDOOR AREA WHERE LACK OF HEAT BUILD-UP AND LACK OF INTERVENING COEUSTIBLES PREQ.UDES THE NE SSITY OF AN AUTOMATIC SUPPRESSION SYSTEM OR FIRE RATED ENCLOSURE.
0 I
FIRE AREA: 68 DESCRIPTION: CONTAINENT PERSONNEL HATOi AND PUFEE VALVES EXEWTION FROM APPENDIX "R", SECTION III.G.2 SEPARATION: 3UBSTANTIAL ETAL BOUf0 ARIES TO AUXILIARY BUILDING.
1 SUPPRESSION: MANUAL EQUIPMENT INSIDE CONTAINENT
-. DETECTION: IONIZATION SMOKE DETECTORS REDUPOANT CDWONENTS: VARIOUS 2
FIRE LOAD: N/A BTU /FT N/A MINUTES JUSTIFICATION FOR EXEMPTION:
THE DISTRICT 00NQ.UDES 11tE QJRRENT DESIGN IS A SUBSTANTIAL FIRE BARRIER.
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FIRE AREA: 110 (NORTH YARD AREA)
DESCRIPTION: NSW RJMPS EXEWTION FROM APPENDIX "R", SECTION III.G.2 SEPARATION: HORIZONTAL SEPARATION OF APPROXIMATELY 400 FEET WITH NO INTERVENING COEUSTIBLES SUPPRESSION: NONE OETECTION: NONE REDUf0 ANT COMM)NENTS: NSW PUMPS (P-472A AND B) 2 FIRE LOAD: INSIGNIFICANT BTU /FT INSIGNIFICANT MINUTES JUSTIFICATION FOR EXEWTION:
(. '
i OUTDOOR LOCATION, LACK OF INTERVENING COEUSTIBLES AND LARGE HORIZONTAL SEPAPATION PREQ.tK)ES THE NECESSITY OF AN AUTOMATIC SUPPRESSION SYSTEM, DETECTION, OR FIRE RATED ENCLOSURE.
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FIRE AREA: N/A DESCRIPTION: 72 liOUR COLD SHUTDOWN EXE WTION FROM APPENDIX "R", SECTION III.L SEPARATI0tl N/A SUPPRESSIOV: N/A DETECTION: N/A
- 1 REDUf0 ANT 0)WONENTS: N/A 2
FIRE LOAD: N/A BTU /FT N/A MINUTES 4
JUSTIFICATION FOR EXEWTION:
B&W REACTORS, UPON LOSS OF OFFSITE POWER, ARE NOT CAPABLE 0F AQiIE/ING COLD SHUTDOWN WITHIN 72 HOURS.
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. l FIRE AREA: 68 DESCRIPTION: CONTAINENT, RCP OIL COLLECTION SYSTEM l I
EXE WTION FROM APPENDIX "R", SECTION III.0
{
SEPARATION: N/A SUPPRESSION: N/A DETECTION: INFRARED FLAE DETECTORS CLOSED CIRCUIT TELEVISION INSIDE CONTAINENT REDUNDANT CDWONENTS: N/A 2
FIRE LOAD: 54,000 BTU /FT 40.5 MINUTES 2
51,400 BTU /FT 38.55 MINUTES
(:'t JUSTIFICATION FOR EXEMPTION:
IN THE UNLIKELY EVENT THAT BOTH RCP OIL SYSTEMS SHOULD BE DRAINED INTO THEIR RESPECTIVE OIL COLLECTION TANKS, THE OVERFLOW WOULD NOT COME INTO CDNTACT WITH ANY IGNITION SOUR S ON THE WAY TO THE CDNTAINENT NORMAL SUMPS.
w - , - - - - - - --- -- - - - - - _ - - - - - - -
FIRE AREA: 69 DESCRIPTION: AFW PUMPS EXEWTION FROM APPENDIX "R", SECTION III.G.2 SEPARATION: HORIZONTAL SEPARATION OF LESS THAN TWO FEET WITH A RADIANT ENERGY SHIELD SUPPRESSION: FIRE HYDRANT AND HOSE HOUSE FOR MANUAL SUPPRESSION 1
DETECTION: FLAE DETECTION REDUEANT (X)WONENTS: AFW PUMPS 2
FIRE LOAD: 2,930 BTU /FT 2.4 MINijTES JUSTIFICATION FOR EXEWTION:
OUTDOOR LOCATION, RADIANT ENEEY SHIELD AND LACK OF SIGNIFICANT QUANTITIES OF COEUSTIBLE MATERIllS PREQ.UDES THE NEESSITY OF AN AUTOMATIC SUPPRESSION SYSTEM OR FIRE RATED ENCLOSURE.
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FIRE AREA: 69 DESCRIPTION: AFW VALVES EXEWTION FROM APPENDIX "R", SECTION III.G.2 SEPARATION: HORIZONTAL SEPARATION OF 5? FEET SUPPRESSION: FIRE HYDRANT AND HOSE HOUSE FOR MANUAL SUPPRESSION f
s DETECTION: NONE REDUNDANT COW'ONP'4TS: A TRAIN AFW VALVES: FV20528 AND SFV20578 B TRAIN AFW VALVES: FV20527 AND SFV20577 2
FIRE LOAD: 2,930 BTU /FT 2.4 MINUTES
.. \
JUSTIFICATION FOR EXEMPTION:
OUTDOOR LOCATION AND THE AMOUNT OF SEPARATION FROM INTERVENING COM3USTIBLES PREQ.UDES THE NECESSITY OF AN AUTOMATIC SUPPRESSION SYSTEM, DETECTION, OR FIRE RATED ENCLOSURE.
FIRE AREA: 68 DESCRIPTION: CONTAINENT ELECTRICAL PENETRATION AREA EXEWTION FROM APPENDIX "R", SECTION III.G.2 SEPARATION: HORIZONTAL SEPARATION OF GREATER THAN 20 FEET WITH INTERVENING COE USTIBLES IN CABLE TRAYS HAVING FIRE BREAKS INSTALLED.
SUPPRESSION: TEN POUES CO FIRE EXTINGUISHER 2
DETECTION: IONIZATION SMOKE DETECTORS REDU W ANT CO WONENTS: SEVERAL 2
FIRE LOAD: 12,020 BTU /FT 9.0 MINUTES
-j
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JUSTIFICATION FOR EXEWTION:
OPEN SPACE ABOYE PEUETRATION AREA, FIRE BREAKS IN INTERVENING CABLE TRAYS AND SEPARATION PRECLUDE THE NECESSITY FOR ADDITIONAL MODIFICATIONS. '
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FIRE AREA: RG1 DESCRIMION: AUXILIARY BUILDING ELECTRICAL PENETRATION AREA EXEFTION FROM APPENDIX "R", SECTION III.G.2 SEPARATION: HORIZONTAL SEPARATION OF 42 FEET SUPPRESSION: FIVE FIRE HOSE STATIONS, FIVE TEN-POUPO 00 2
PORTABLE. EXTINGUISHERS, WET PIPE SPRINKLER FULL FIRE AREA SYSTEM DETECTION: IONIZATION SMOKE DETECTORS REDUPOANT COWONENTS: RCS HOT LEG NARROW RANGE TEWERATURE j
APO SOURCE RANGE POCLEAR INSTRUENTATION.
2
) FIRE LOAD: 18,220 BTU /FT 13.8 MINUTES JUSTIFICATION FOR EXEWTION:
ONE-HOUR CONDUIT WRAP UP TO THE CABLE PENETRATION HOUSING WITH AUTOMATIC SUPPRESSION AND DETECTION PREauDES THE
- ~
NE SSITY TO ENaOSE THE PEN'TRATION HOUSING WITH A l ONE-HOUR RATED FIRE BARRIER.
4
, --v.~, - - - - - - - - - - - -
ee ,. e - - - - - m--- - - - -, -- - --v -- - - --- --------- -
FIRE AREA: RB1 DESCRIPTION: AUXILIARY BUILDING E0iANICAL PENETRATION AREA l l
EXEWTION FROM APPENDIX "R", SECTION III.G.2 i
SEPARATION: HALL OPENING TO F.A. RB2 WITH PARTIAL AREA SUPPRESSION, CABLE TRAY FIRE BREAKS (20 FEET APART) APO A HORIZONTAL SEPARATION OF APPROXIMATELY 40 FEET SUPPRESSION: TWO FIRE HOSE STATIONS WITH PARTIAL AREA SPRINKLER SYSTEM DETECTION: IONIZATION SMOKE DETECTORS REDUlOANT 00WONENTS: HPI RJMPS 2
FIRE LOAD: 6,440 BTU /FT 4.8 MINUTES JUSTIFICATION FOR EXEWTION:
PARTIAL AREA SUPPRESSION, FIRE BREAKS, DETECTION, AND LACK 0F COEUSTIBLE LOADING PRECLUDES THE NEED FOR A FIRE
~
RATED BARRIER.
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FIRE AREA: VARIOUS DESCRIPTION: CONDUIT PENETP'.: IONS THROUGH FIRE BARRIERS EXEWTION FROM KPENDIX "R", SECTION III.G.2 I SEPARATION: SMOKE AND GAS SEAL AT OPENINGS OR FIRST AVAILABLE FITTING FROM FIRE BARRIER SUPPRESSION: N/A DETECTION: N/A REDUPOANT COWONENTS: N/A 2
FIRE LOAD: N/A BTU /FT N/A MINUTES
,_ JUSTIFICATION FOR EXEMPTION:
._ y
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LACK OF EARLY SPECIFIC REQUIREENTS LED TO RANCHO SECO'S PROGRAM TO VERIFY AND SEAL CONDUIT PENETRATIONS AS DESCRIBED IN COEUIT FIRE STOP DETAILS. THE DISTRICT CONCLUDES THAT THIS EETS THE REQUIREENT OF 10 CFR S0.48, APPENDIX R.
e
FIRE AREA: RB2, RG1, AND RM1 DESCRIPTION: HVAC PENETRATIONS EXE WTION FROM APPENDIX m", SECTION III.G.2 SEPARATION: UNRATED HVAC DUCT PENETRATIONS THROUGH VARIOUS FIRE BARRIERS SUPPRESSION: RB2 - PARTIAL AREA SPRINKLERS MD MANUAL HOSE STATIONS
RG1 - FULL AREA SUPPRESSION MD MANUAL HOSE STATION RM1 - FULL AREA WETPIPE OR AUTOMATIC CD2 WITH MANUAL HOSE STATIONS DETECTION: RB2 - IONIZATION SMOKE DETECTORS RG1 - IONIZATION SMOKE DETECTORS RM1 - IONIZATION SMOKE DETECTORS REDUEANT (DWONENTS: AFW CIRQJITS MD HPI/ MAKEUP CIRQJITS 2
FIRE LOAD: RB2 - 7,750 BTU /FT RB2 - 6 MINUTEE RG1 - 18,220 BTU /FT2 RG1 - 13.8 MINUTES RM1 - 72,450 BTU /FT2 RM1 - SS MINUTE
, JUSTIFICATION FOR EXEWTION:
SUPPRESSION, DETECTION, AND SUBSTANTIAL ETAL BARRIER WILL ENSURE ADEQUATE SEPARATION.
- s-MEETING
SUMMARY
DISTRIBUTION Licensee: Rancho Seco
'* Copies also sent to those people on service (cc) list for subject plant (s).
Docket File NRC PDR L PDR ORBf4~Rdg-Project Manager - S.. Miner JStolz BGrimes (Emerg. Preparedness only)
. , OELD EJordan, IE ACRS PMorriette NRC Meeting
Participants:
'R. Ferguson J. Stang V. Benaroya J. Wilson
.J. Holonich 6 -
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