Letter Sequence Meeting |
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Results
Other: ML20136J106, ML20137W989, ML20140D589, ML20153D518, ML20153D535, ML20154M151, ML20154N307, ML20203N882, ML20206F544, ML20214L542, ML20214L543, ML20214L552, ML20214L559
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MONTHYEARML20214L5421985-12-26026 December 1985 Confirmatory Action Ltr Re Facility Return to Power Operations.Understands Util Will Conduct Root Cause Analysis of 851226 Reactor Trip & Provide Briefing of Assessment & Justification to Resume Power Operations Project stage: Other ML20214L5591985-12-27027 December 1985 Forwards Proposed Plan for Facility Augmented Investigation Team.Comments Requested by 851227.Chronological Sequence of Events Re 851226 Event Also Encl Project stage: Other ML20136J1061986-01-0505 January 1986 PNO-IIT-86-001A:on 851226,loss of Integrated Control Sys Occurred.Caused by Simultaneous Deenergizing of All Redundant Dc Power Supplies.Licensee Preparing Action Plans for Systematic Troubleshooting.Sequence of Events Encl Project stage: Other ML20137J7271986-01-0606 January 1986 Notifies of 860108 Meeting W/B&W Regulatory Response Group in Bethesda,Md to Discuss 851226 Loss of Integrated Control Sys Power & Generic Implications for Other B&W Plants.Info Confirms NRC 851230 Request Project stage: Meeting ML20214L5551986-01-0707 January 1986 Forwards Addl Info for Use in Conjunction W/Meeting W/B&W Regulatory Response Group,Including List of Issues That Rancho Seco Incident Investigation Team Has Identified to Date Associated w/851226 Overcooling Event Project stage: Meeting ML20214L5521986-01-20020 January 1986 Package of Two Documents Entitled, Action List,851226 Transient Project stage: Other ML20140D5891986-01-24024 January 1986 Forwards Schedule for Return to Power Operations from 851226 Transient.Schedule Consists of Comprehensive Action List & Milestone Schedule.Commencement of Power Operation Scheduled for 860308 Project stage: Other ML20214L5511986-02-0707 February 1986 Notification of Significant Licensee Meeting on 860210 W/Util in Walnut Creek,Ca to Discuss Review of Plant Restart Actions for Facility Following 851226 Event Project stage: Meeting ML20153D5351986-02-19019 February 1986 Description & Resolution of Issues Re 851226 Reactor Trip Project stage: Other ML20153D5181986-02-19019 February 1986 Forwards Summary Rept, Description & Resolution of Issues Re 851226 Reactor Trip, Supporting Resumption of Power Operation as Scheduled on 860308.Previous Actions Summarized Project stage: Other ML20137W9891986-02-24024 February 1986 Forwards Addendum to 860219 Summary Rept Re Resolution of Issues from 851226 Reactor Trip,Replacing Page 41.Addendum Addresses Remote Isolation Capability for Main Steam Lines, Independent of ICS Power & Controls Project stage: Other ML20214E3401986-03-0505 March 1986 Requests Review of Encl Tentative Review Assignments for Action Plan for Restart of Plant by 860307.Requests for Addl Info Re Encl Proposed Resolution of Issues Concerning 851226 Event Requested by 860321.W/o Encls Project stage: Approval ML20154M1511986-03-0606 March 1986 Staff Requirements Memo Re 860225 Briefing in Washington,Dc Concerning Incident Investigation Team Rept on 851226 Loss of Power in Integrated Control Sys.Schedules for Followup Plan & Assessment Re Lack of Plant Mods Requested Project stage: Other ML20214L5431986-03-10010 March 1986 Viewgraphs Entitled, Smud Project stage: Other ML20154N3071986-03-12012 March 1986 Forwards Design Basis Rept for Mods to Facility Based on 851226 Transient Project stage: Other ML20199D7561986-03-17017 March 1986 Notification of 860324 & 25 Meetings & Plant Trip W/Util in Herald,Ca to Discuss Proposed Plans for Recovery from 851226 Incident.Agenda Encl Project stage: Meeting ML20203H2181986-04-14014 April 1986 Summary of 860205 Meeting W/B&W Owners Group in Bethesda,Md Re B&W Owners Group Ongoing Programs & Activities & 850609 & 1226 Transients at Davis Besse & Rancho Seco,Respectively. Attendance List & Handout Incl Project stage: Meeting ML20210R9391986-04-23023 April 1986 Summary of 860324-25 Meetings W/Util Re Plans to Recover from 851226 Overcooling Event.Preparation of Comprehensive Recovery Plan,Demonstrating Safe & Reliable Plant Operation, Needed for NRC Restart Approval.Viewgraphs Encl Project stage: Meeting ML20210R9331986-04-23023 April 1986 Forwards Summary of 860324-25 Onsite Meetings W/Util Re Plans for Recovery from 851226 Overcooling Event. Comprehensive Restart Rept,Demonstrating Correction of Plant Design Programmatic & Organizational Deficiencies,Expected Project stage: Meeting ML20203N8821986-04-24024 April 1986 Discusses NUREG-1195, Loss of Integrated Control Sys Power & Overcooling Transient at Rancho Seco on 851226. Minor Technical Corrections to & Comments on Misperceptions in Incident Investigation Team Rept Encl Project stage: Other ML20210N9891986-04-25025 April 1986 Responds to 860313 Memo Re Identification & Assignment of Responsibilities for Generic & plant-specific Actions Resulting from Investigation of 851226 Incident.Summary of Plans,Schedule,Status & Draft Action Plan Encl Project stage: Draft Other ML20198B8301986-05-12012 May 1986 Comments on Adequacy,Scope & Direction of 860418 Meeting W/ Util Re Plant Performance & Mgt Improvement Program Addressing Broad Range of Issues Affecting Restart & Safe & Reliable Operation in Response to 851226 Transient Project stage: Meeting ML20198B4341986-05-14014 May 1986 Summary of 860418 Meeting W/Util in Bethesda,Md Re Util Proposed Plant Performance & Mgt Improvement Program in Light of 851226 Transient.List of Attendees & Viewgraphs Encl Project stage: Meeting ML20206F5441986-05-29029 May 1986 Forwards List of Open Items,Including 851226 Overcooling Event Concerns,Requiring Util Action Per 860523 Telcon.Items Listed in Areas a & B Should Be Addressed in Restart Rept Project stage: Other ML20214L5481987-05-30030 May 1987 Agenda for 860210 Meeting W/Nrc to Discuss Facility 851226 Transient Project stage: Meeting 1986-03-12
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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 ML20057C4971993-09-0202 September 1993 Forwards Insp Rept 50-312/93-06 on 930819.No Violations or Deviations Noted ML20057A3251993-09-0202 September 1993 Forwards Environmental Assessment & Fonsi Re Exemption from Requirements of 10CFR50.120 at Plant 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) 1999-08-31
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] ) I'1 {3 0 lo Docket No. 50-312 NAY 121986 DISTRimlTION
@cket File) BGrimes Taylor axC rox JPartlow Martin, RV L PDR RIngram ED0 R/F Mr. Dewey K. Lowe PBD#6 Rdg PM General Manager FMiraglia Gray File Sacramento Municipal Utility District 0 ELD EBrach 6201 S Street ACRS-10 B0rnstein P.O. Box 15830 EJordan venton Sacramento, California 95813 Stello Roe
Dear Mr. Lowe:
Rehm On April 18, 1986, representatives of the Sacramento Municipal Utility District _(SMUD) met with members of the NRC staff to discuss SMUD's proposed plant performance and management improvement program for the Rancho Seco Nuclear Generating Station. This meeting was a follow-up to the meeting held between SMUD and senior NRC management on March 24-25, 1986 where SMUD was requested to develop a program to address a broad range of issues affecting the safe and reliable operation of the Rancho Seco plant and not just focused on_ responding to the December 26, 1985 transient. The purpose of this letter is to provide you with the NRC staff views regarding the adequacy, scope and direction of your. improvement program.
The staff notes that you have taken a structured approach to program improvement which includes the establishment of independent review and oversight panels reporting directly to you. With regard to management improvement, the creation of six departments with defined functional responsibilities (operations, quality, engineering, training, licensing, and projects) should enhance SMUD's ability
.to. deal with the programmatic deficie,cies apparent over the past several years.
Wo~also note that SMUD has been able to attract experienced personnel for several of the management positions in the new organization. The staff expects
'that the beneficial impact of the new organization will become apparent as you progress in your plant performance improvement program. However, the staff wishes to emphasize _the importance of filling the position of the Assistant General Manager Nuclear by an individual with a known track record to direct the upgrading effort needed for the safe and reliable operation of the Rancho Seco plant. This individual, with six department heads reporting to him, will be a key factor in meeting acceptable recovery goals.
With regard to the plant performance improvement program, you have developed a program which appears to respond to a broader range of issues than just the problems and deficiencies related to the December 26, 1985 overcooling transient. This step is indicative of SMUD's efforts to look beyond the narrow focus of the transient. Of course it remains to be seen if your program translates into improved performance. Your near term performance goals are modest (greater than 60% plant availability, less than 10% forced outage rate and less than 3 reactor trips per year) but reflect the degree of improvement SMUD has to make.
8605220147 860512 PDR ADOCK 05000312 S PDR a
Mr. Dewey Lowe MAY 121986 The SMUD performance improvement program includes deterministic failure consequence analyses of a number of components and systems to determine which could (1) cause a reactor trip, (2) challenge a safety system or (3) impact the ability of the plant to stay within the desired " post-trip response
-window" (reactor coolant and steam outlet pressure and temperature).
Components and systems with identified deficiencies will be targeted for possible modifications to hardware and procedures and enhanced operator training and possible testing.
Additionally, we understand that the improvement program may include some other (as yet, unidentified) system testing. However, the staff's sense of your test program is that it is rather limitcd in scope. The staff has reservations about the adequacy of your test program and would urge that you assess the merits of conducting a broader scope test program. The ongoing program at Davis-Besse is an example of a broad scope test program. Members of my staff are available to discuss the detailed aspects of the Davis-Besse program, including the results obtained to date, to permit you to determine its applicability to your proposed test program at Rancho Seco. As you are aware from our meetings.of March 24-26, 1986, SMUD has the burden of demonstrating to NRC that Rancho Seco can be restarted and operated safely and reliably.
The staff corsiders the system testing to demonstrate safe and reliable operation under both normal and abnormal conditions to be an important element of your overall plant performance improvement program.
Regarding restart, at.the April 18 meeting SMUD staff was asked about the projected schedule of activities or milestones which are prerequisites to restart. The NRC staff was informed that the Rancho Seco startup report would be submitted for NRC review in early July. This report should clearly delineate your position as to which issues or actions are restart items (i.e.,
short term actions) and which can be completed after restart (i.e., long term items). The NRC staff is prepared to meet with SMUD staff for detailed technical discussion of the issues, if such meetings would be useful prior to the
- bmittal of your restart report. In this regard your staff agreed at the April 18, 1986 meeting to send the NRC staff an outline of the scope and content of your restart report well before your formal submittal. Please advise us of the projected schedule for the report submittal if the schedule changes from the anticipated date of early July.
I look forward to hearing from you.
Sincerely, G&J!nl@@.9 IPT Victor Stello, Jr.
Executive Director for Operations cc: See next page
- See previous white for concurrence. pg P -6 4 D-6 , D-6 g b B
~
E R:V Etb SMi , 'ak R Js Fly a 1ia JTay1or JMartin*
5/}/86 5/ /86 5/j/86 5/L /86 5/ /86 5/7/86 st la
, a Mr. Dewey Lowe The SMUD performance improvement program includes deterministic failure consequence analyses of a number of components and systems to determine which could (1) cause a reactor trip, (2) challenge a safety system or (3) impact the ability of the plant to stay within the desired " post-trip response window" (reactor coolant and steam outlet pressure and temperature).
Components and systems with identified deficiencies will be targeted for possible modifications to hardware and procedures and enhanced operator training and possible testing.
Additionally, we understand that the improvement program may include some other (as yet, unidentified) system testing. However, the staff's sense of your test program is that it is rather limited in scope. The staff has reservations about the adequacy of your test program and would urge that you assess the merits of conducting a broader scope test program. The ongoing program at Davis-Besse is an example of a broad scope test program. Members of my staff are available to discuss the detailed aspects of the Davis-Besse program, including the results obtained to date, to permit you to determine its applicability to your proposed test program at Rancho Seco. As you are aware from our meetings of March 24-26, 1986, SMUD has the burden of demonstrating to NRC that Rancho Seco can be restarted and operated without undue risk to the health and safety of the public. The staff considers the system testing to be an important element'of your overall plant performance inprovement program.
Regarding restart, at the April 18 meeting SMUD staff was asked about the projected schedule of activities or milestones which are prerequisites to restart. The NRC staff was informed that the Rancho Seco startup report wnuld
'be submitted for NRC review in early July. This report should clearly delineate your position as to which issues or actions are restart items (i.e.,
short term actions) and which can be completed after restart (i.e., long term items). The NRC staff is prepared to meet with SMUD staff for detailed technical ,
discussion of the issues, if such meetings would be useful prior to the submittal of your restart report. In this regard your. staff agreed at the April 18, 1986 meeting to send'the NRC staff an outline of the scope and content of your restart report well before your formal submittal. Please advise us of the projected schedule for the report submittal if the schedule changes from the anticipated date of early July.
I look forward to hearing from you.
l Sincerely, Frank J. Miraglia, Director Division of PWR Licensing-B
! cc: See next page g.
PBD-6 PBD-6 PBD-6 D:PWR-B IE R:V $'g SMiner;jak RWeller Jstolz FMiraglia JTaylor JMartin 5/ /86 5/ /86 5/ /86 5/ /86 5/ /86 5/ 7 /86
Mr. Dewey Lowe The SVVD performance improvement program includes deterministic failure consequence analyses of a number of components and systems to determine which could (1) cause a reactor trip, (2) challenge a safety system or (3) impact the ability of the plant to stay within the desired " post-trip response window" (reactor coolant and steam outlet pressure and temperature).
Components and systems with identified deficiencies will be targeted for possible modifications to hardware and procedures and enhanced operator training and possible testing. Additionally, tne improvement program may include some other (as yet, unidentified) system testing; however, the staff's sense of your test program is that it is rather limited in scope. The staff has reservations about the adequacy of your test program and would urge that you assess the nerits of the current ongoing program at Davis-Besse for its application of appropriate aspects of it at Rancho Seco. Members of my statf are available to discuss the detailed aspects of the Davis-Besse program, including the results obtained to date, to permit you to make a more informed judgement on your proposed test program. As you are aware from our meetings of March 24-26, 1986, SMUD has the burden of demonstrating to NRC management that Rancho Seco can be restarted and operated without undue risk to the health and safety of the public and the staff considers the system testing to be an important element of your overall plant performance improvement program.
Regarding restart, SMUD staff was questioned at the April 18 meeting about the projected schedule of activities or milestones which are prerequisites to restart. The NRC staff was informed that the Rancho Seco startup report would be submitted for NRC review in early July. This report should clearly delineate which issues or actions are restart items (i.e., short term actions) and which can be completed after restart (i.e., long term items).
The NRC staff is prepared to meet with SMUD staff for detailed technical discussion of the issues if you think such meetings would be useful prior to the submittal of your restart report. In this regard your staff agreed at the April 18, 1986 meeting to send the NRC staff an outline of the scope and content of your restart report well before your formal submittal. In order that we may gear our resources for the forthcoming review of your restart report, please advise us of the projbcted schedule for the report submittal if the schedule changes from that anticipated (i.e., early July).
I look forward to hearing from you.
Sincerely, Frank Miraglia, Director Division of PWR Licensing-B cc: See next page A9u PBD-6 PBD-6 PB D:PWR-B DD:NRR SMi k RWeller Jf >%
1 A FMiraglia DEisenhut 5/ 6 5/7 /86 5/p86 5/ /86 5/ /86
Mr. R. J. Rodriguez Rancho Seco Nuclear Generating Sacramento Municipal Utility District Station cc:
Mr. David 5. Kaplan, Secretary Sacramento County and General Counsel Board of Supervisors Sacramento Municipal Utility 827 7th Street, Room 424 i District Sacramento, California 95814 '
6201 S Street P. O. Box 15830 Ms. Helen Hubbard i Sacramento, California 95813 P. O. Box 63 Sunol, California 94586 Thomas Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge 1800 M Street, N.W.
Washington, D.C. 20036 Mr. Robert B Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident Inspector / Rancho Seco c/o U. S. N. R. C.
14410 Twin Cities Road Herald, California 95638 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Director Energy Facilities Siting Division Energy Resources Conservation &
Development Commission 1516 .9th Street Sacramento, California 95814 Mr. Joseph 0. Ward, Chief Radiological Health Branch State Department of Health Services 714 P Street, Office Building #8 Sacramento, California 95814