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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 T May 2,1986 g g] h Docket No. 50-312 DI_SIRIBUT4QI Tocke jt Fe> BGrimes UR JPartlow Mr. Ronald J. Rodriguez L PDR RIngram Assistant General Manager, Nuclear PBD#6 Rdg SMiner Sacramento Municipal Utility District 0 ELD GKalman 6201 S Street FMiraglia Gray File P. O. Box 15830 ACRS-10 HSmith Sacramento, California 95813 EJordan SScott
Dear Mr. Rodriguez:
The Comptroller General in a Report to the Congress dated September 19, 1984, stated "NRC needs better management controls to ensure implementation of generic issue solutions." To correct this situation, the Nuclear Regulatory Commission is working on a long-term program which will improve its documentation on the status of power reactor licensees' implementation of approved regulatory improvements.
To assist me in developing this information for Rancho Seco Nuclear Generating Station, please review the enclosed plant-specific list, add omitted significant actions to the list, and provide the date that all aspects of each identified requirement were completed / implemented or are expected to be completed. For each requirement that has been completed, enter " completed" under the Status column and the date the item was completed. For requirements that have not been completed / implemented, provide the projected date and enter
" projected" under the Status column. I do not expect or want a major effort made to obtain precise dates. Rather, I will accept readily-known or best-estimate dates for actions that have been completely implemented. For example, the year only would be acceptable for completions prior to 1984; the nonth as well as year is needed for requirements completed after that time. For projected completions / implementations in 1986, use month and year. Use year only for projections thereafter. Please provide a response in the fonn of a marked up listing by May 31, 1986.
In the future, NRR will need estimated dates prior to issuance of the safety evaluation so that the estimated schedule may be included in the evaluation.
This request is covered by OMB Clearance Number 3150-0011, which expires September 30, 1986.
t Sincerely, "GTdEULALdrM 5 W Sydney Miner, Project Manager PWR Project Directorate #6 Division of PWR Licensing-B
Enclosure:
As stated cc w/ enclosure: See next page A' a u rs
, PBD-6 PBD-6 PB -6 l SMiner- RWeller JS .l z 5/ /86 5// /86 5/ '6 g$cg $$ 2 P
_ . . - _ - ___. . - _ _ - -. _ _ . --- -~ _ _ _~ . . . . -_. _ _ _ . - _ - -
Mr. R. J. Rodriguez Rancho Seco Nuclear Generating Sacramento Municipal Utility District Station cc:
Mr. David S. Kaplan, Secretary Sacramento County and General Counsel Board of Supervisors Sacramento Municipal Utility 827 7th Street, Room 424 District Sacramento, California 95814 6201 S Street P. O. Box 15830 Ms. Helen Hubbard 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
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9P R-1208731-001 REGULAT0RY INF0RMATION TRACKINO SYSTEM PAGE NO. 411 FACILITY IMPLEMENTATION 03/31/86
' FACILITY: RANCHO SECO 1 i PLANT LOCATION: 25 MI SE OF SACRAMENTO, CA LICENSED P0HER: 2772 MHT PROJECT HANAGER: S. MINER
. DOCKET NUMBER: 050-00312 DESIGN P0HER: 0918 MNE BRANCH CHIEF: J. STOLZ
' ARCH / ENGINEER: BECH NSSS VENDOR: 88H LIC. ASSISTANT: R. INGRAM .
,IE INSPECTOR: JueSSRIWWID- !
J LIC ACT LICENSEE
- i TAC NO. MPA 0 TITLE COMPLETE ETATUS AAlg A
jM10816 A-01 10 CFR 50.55 A(G) - ISI 01/28/83C M08153 A-02 APPENDIX I - ALARA 02/22/84C M07017 A-03 SECURITY REVIENS-MODIFIED AMENDMENT PLANS 02/23/79C M11130 A-04 APPENDIX J - CONTAINMENT LEAK TYSTING 05/10/82C
,M07497 A-06 RESPIRATORY PROTECTION SYSTEM 04/09/79C l M10563 A-10 CONTINGENCY PLANNING 04/13/81C
- M105G9 A-11 GUARD TRAINING PLANS 04/13/81C jM10564 A-12 VITAL AREA ANALYSIS 03/27/80C Mt1288 A-14 10CFR 50.55 A(G) - INSERVICE TESTING 09/25/84C M12616 A-15 QUALITY ASSURANCE REQUEST REGARDING DIESEL GENARAT 01/31/84C M47565 A-16 QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 08/05/82C I M51126 A-17 INSTRUMENTATION TO FOLLON THE COURSE OF AN ACCIDEN 04/15/86 M55735 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43) 12/28/84C M59134 A-20 10 CFR 50.62 OPERATING REACTOR REVIENS N//S /
I to CFR 50.61, PRESSURIZED THERMAL SHOCK RULE M59976 A-21 12/31/86 M06165 B-02 FIRE PROTECTION 02/28/78C M08390 B-03 PHR MODERATOR DILUTION 03/01/79C iM06710 B-04 REACTOR VESSEL OVERPRESSURE PROTECTION 06/29/84C
- M11328 B-08 PHR HPSI-LPSI FLOH RESISTANCE 06/22/79C M10849 B-14 CEA GUIDE TUBE HEAR 07/24/81C i
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9M R-1208731-001 REGULAT0RY INF0RMATION. TRACKING SYSTEM PAGE NO. 412 FACILITY IMPLEMENTATION 03/31/86 RANCHO SECO 1 (CONTINUATION)
LIC ACT LICENSEE TAC N3. MPA 8 TITLE COMPLETE STATUS DAIE M12154 B-16 EMERGENCY PLANNING AND REVISIONS 04/01/81C M43206 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 12/24/85C M10321 B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 05/11/81C M10383 B-21 LOSS OF 125-V DC BUS VOLTAGE WITH LOSS OF ANNUNCIA 02/28/82C M08605 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 04/09/82C M10928 B-23 DEGRADED GRID VOL1 AGE 01/28/82C M10206 3-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL P0H 05/11/81C M42601 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL PON 10/25/83C M10258 B-26 INADVERTANT SAFETY INJECTION DURING COOLDOHN 09/14/79C M10534 B-35 ORIFICE ROD ASSEMBLY INTEGRITY - B8W 12/15/78C M11284 B-33 TENDON SURVEILLANCE - BECHTEL CONTAINMENTS 05/25/82C M08609 B-39 PHR PRESSURE - TEMPERATURE LIMIT TECH SPECS 11/13/80C l M11076 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 08/20/81C M43320 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 09/19/83C M11926 B-42 TMI FOLLOH UP - ALL PLANTS 11/23/79C M11927 B-42 TMI FOLLOH UP - ALL PLANTS 05/19/81C M11801 B-43 PHR FEEDHATER LINE CRACKS 12/19/80C M30612 B-44 LESSONS LEARNED IMPLEMENTATION 05/01/80C M30613 B-44 LESSONS LEARNED IMPLEMENTATION 05/01/80C
'M30214 B-44 LESSONS LEARNED IMPLEMENTATION 05/01/80C M30615 B-44 LESSONS LEARNED IMPLEMENTATION 05/01/80C i M30616 B-44 LESSONS LEARNED IMPLEMENTATION 05/01/80C M30617 B-44 LESSONS LEARNED IMPLEMENTATION 05/01/80C
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M R-1208731-001 REGULAT0RY INF0RMATION. TRACKINO SYSTEM PAGE NO 413 FACILITY IMPLEMENTATION 03/31/86 RANCHO SECO 1 (CONTINUATION)
LIC ACT LICENSEE TAC NO. MPA 8 TITLE COMPLETE STATUS DAlf M30618 B-44 LESSONS LEARNED IMPLEMENTATION 05/01/80C M30619 B-44 LESSONS LEARNED IMPLEMENTATION 05/01/80C M30620 B-44 LESSONS LEARNED IMPLEMENTATION 05/01/80C M30221 B-44 LESSONS LEARNED IMPLEMENTATION 05/01/80C s
M30622 B-44 LESSONS LEARNED IMPLEMENTATION 05/01/80C M30623 B-44 LESSONS LEARNED IMPLEMENTATION 05/01/80C
) M30624 B-44 LESSONS LEARNED IMPLEMENTATION C5/01/80C M30225 B-44 LESSONS LEARNED IMPLEMENTATION 05/01/80C M12452 B-44 LESSONS LEARNED IMPLEMENTATION 05/01/80C M12604 B-46 ANALYSIS OF TURBINE DISC CRACKS 08/19/81C M12746 B-48 ADEQUACY OF S1ATION ELECTRIC DISTRIBUTION VOLTAGE 08/30/83C M42120 B-57 DHR CAPABILITY 07/03/85C M42918 B-59 MASONRY HALL DESIGN 12/03/83C M43507 B-60 ENVIRONMENTAL QUALIFICATION 04/25/85C M42703 B-61 LOSS OF NON CLASS IE 18C P0HER 07/28/82C M42774 B-62 ESF RESET CONTROL DESIGN DEFICIENCY 06/12/81C M43938 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT 10/23/82C M43224 B-64 58C INDUCED FLUX ERRORS 04/21/82C M47170 B-66 NATURAL CIRCULATION C00LDOHN 03/31/86 i M46855 B-69 IEB 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 02/15/85C M46634 B-70 FATIGUE TRANSIENT LIMIT TS 05/25/82C B-72 NUREG 0737 TECN SPECS (GENERIC LETTER 82-16) 08/03/82C l M49752 M49616 B-73 PLANS FOR PREVENTING EXCEEDING PTS SCREENING CRITE 12/28/83C
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94m R-1208751-001 REGULAT0RY INF0RMATION. TRACKINO SYSTEM PAGE NO. 414 FACILITY IMPLEMENTATION 03/31/86 RANCHO SECO 1 (CONTINUATION)
LIC ACT LICENSEE j TAC NO. MPA 0 TIT'E COMPLETE STATUS DAlg i M52793 B-76 ITEM 1.1 - POST TRIP REVIEH; PROGRAM DESCRIPTION & 07/03/85C M53874 B -7 7 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 10/30/86 j M52955 B-78 ITEMS 3.1.1 8 3.1.2 -POST MAINTENANCE TEST PROCEDU 08/19/L3C M53036 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTIN'O - CHANGES TO 10/09/85C M53091 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 08/02/85C
- M53144 B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 05/28/86 j M53190 B-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 08/10/84C B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83- 02/28/86 l M54352 M53626 B-85 SALEM ATHS 1.2 DATA CAPABILITY 03/15/86 M53709 B-86 SALEM ATHS 2.2 S-R COMPONENTS 10/30/86
- M53792 B-87 SALEM ATHS 3.2.1 a 3.2.2 S-R COMPONENTS 08/19/85C M53875 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 10/09/85C M53931 B-89 SALEM ATHS 4.2.3 8 4.2.4 LIFE COMPONENTS 12/31/86
,i M55373 B-90 SALEM ATHS 4.3 H AND B&H T.S. 11/30/86 M53958 B-91 SALEM ATHS 4.4 58W TEST PROCEDURES 04/30/86 4
M54102 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 08/19/85C 1
- M54019 B-95 SALEM ATHS 4.5.2 8 4.5.3 TEST ALTERNATIVES 04/31/87 1 M08247 C-01 PHR SECONDARY HATER CHEMISTRY MONITORING REQUIREME 09/29/83C i
- M08612 C-04 FILTER TECH SPECS 09/13/82C l'M08589 C-06 PUMP SUPPORT-LAMELLAR TEARING 04/17/81C
~
M08614 C-07 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT 04/15/80C
! M08079 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 10/25/83C l M43663 C-14 AUXILIARY FEEDWATER SEISMIC QUALIFICATION 11/12/82C a:
4 1
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!R-1208731-001 REGULAT0RY INF0RMATION. TRACKING SYSTEM PAGE NO. 415 FACILITY IMPLEMENTATION 03/31/86 RANCHO SECO 1 (CONTINUATION)
LIC ACT LICENSEE
- TAC NO. MPA 8 TITLE CHdPLETE STATUS RAIE M52264 C-15 CONTROL OF HEAVY LOADS - PHASE II (FDLLOHUP OF MPA 06/28/85C M58082 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 01/22/86C M11285 D-04 PHR REACTOR VESSEL CAVITY SEAL RING MISSILE POTENT 09/29/80C M08602 D-10 ASYMMETRIC LOCA LOADS 01/16/84C
'M10108 D-11 FISSION GAS RELEASE 12/15/78C M07788 D-13 B8H SMALL BREAK ERROR 03/31/80C M08599 D-14 REACTOR VESSEL HELD - HIRE DEFICIENCY 10/29/80C
- M12326 D-15 HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEM FAIL 02/02/84C
.M43042 D-17 DEFINITION OF OPERABLE 03/04/85C
,M51732 D-18 NUREG 0630 CLADDING MODELS (B8H PLANTS) 08/03/83C
.M55896 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 09/30/86 MO8610 E-03 CCRE RELOADS REQUIRING PRIOR NRC APPROVAL 12/15/78C M12357 E-03 CORE RELOADS REQUIRING PRIOR NRC APPROVAL 03/31/80C M44052 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 01/12/82C M44123 F-02 I.A.1.3 SHIFT MANNING 06/30/83C M44194 F-03 I.A.2.1 UPGRADING OF R0 AND SRO TRAINING 10/20/82C
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.N44265 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/08/84C M44335 F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES (NUREG 01/?B/86
'M47248 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 12/10/81C
- M47320 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 12/10/&'C M51196 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEH PROGRA 10/29/84;'
M51276 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 10/10/84C
- M44402 F-10 II.B.1 RCS HIGH POINT VENTS 09/30/83C
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M R-1208731-001 REGULAT0RY INF0RMATION. TRACKING SYSTEM PAGE NO.s 416 FACILITY IMPLEMENTATION 03/31/86 RANCHO SECO 1 (CONTINUATION)
LIC ACT LICENSEE
, TAC NO. MPA 9 TITLE COMPLETE STATUS RAlg M47971 F-11 II.B.2 PLANT SHIELDING 08/25/83C M44473 F-12 II.B.3 POST ACCIDENT SAMPLING 09/02/83C M44544 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 10/20/82C M44615 F-14 II . D.1 RV AND SV TRAINING 04/30/86 M44673 F-15 II.E.1.1 AFH SYSTEM EVALUATION 10/05/83C
)
M44709 F-16 II.E.1.2.1 AFH SYSTEM INITIATION 09/07/82C
!M44755 F-17 II.E.1.2.2 AFH SYSTEM FLON INDICATION 09/07/82C M44812 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 06/20/83C
- M44883 F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 04/04/83C M44954 F-20 II.F.1.1 NOBLE GAS MONITOR 12/24/81C M45025 F-21 II . F .1. 2 IODINE / PARTICULATE SAMPLING 12/24/81C i
1M45096 F-22 II . F.1. 3 CONTAINMENT HIGN RANGE MONITOR 04/12/82C i
'M47632 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 07/28/82C
' M47703 F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMENT 07/28/82C M47774 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 07/28/82C M45166 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 01/31/87
,M42790 F-27 II.K.2.9 FMEA ON ICS 01/13/82C M45188 F-28 II.K.2.10 SAFETY GRADE ARTS 11/02/81C M45195 F-29 II.K.2.11 CONTINUED OPERATOR TRAINING AND DRILLIN 12/09/81C
'M45202 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06/05/84C M45209 F-31 II.K.2.14 LIFT FREQUENCY OF PORVS AND SVS 05/25/82C M45216 F-32 II.K.2.16 RCP SEAL DAMAGE 03/17/82C
- M45222 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 12/09/81C l
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F R-1208731-001 REGULAT0RY INF0RMATION. TRACKINO SYSTEM PAGE NO.* 411 FACILITY IMPLEMENTATION 04/14/86 FACILITY: RANCHO SECO 1 PLANT LOCATION: 25 MI SE OF SACRAMENTO, CA LICENSED POWER: 2772 MHT PROJECT MANAGER: S. MINER DOCKET NUMBER: 050-00312 DESIGN PONER: 0918 MNE BRANCH CHIEF: J. STOLZ ARCH / ENGINEER: BECH NSSS VENDDRs B&W LIC. ASSISTANT: R. INGRAM
'IE INSPECTOR: 35MCIROIRIP TAC NO. MPA 0 TITLE M08247 C-01 RANCHO SECO - PHR SECONDARY CHEMISTRY MONITORING REQUIREMENTS - GENERIC
- M49680 G-01 RANCHO SECO - REACTOR COOLANT PUMP TRIP M44052 F-01 RANCHO SECO - NUREG-0737 I.A.1.1 STA LONG TERM REQUIREMENTS
- M10816 A-01 RANCHO SECO - 10 CFR 50.55A(G) - INSERVICE INSPECTION - GENERIC M08153 A-02 RANCHO SECO - APPENDIX I TECH SPEC IMPLEMENTATION REVIEH
'M44123 F-02 RANCHO SECO - NUREG-0737 I.A.1.3.1, SHIFT MANNING OVERTIME LIMITS M06165 B-02 RANCHO SECO FIRE PROTECTION M07017 A-05 RANCHO SECO 10 CFR 73.55 IMPLEMENTAT!ON
'M44194 F-03 RANCHO SECO - NUREG-0737 I.A.2.1.4, U?SRADING OF R0 AND SRO TRAINING M08396 B-03 RANCHO SECO - PHR MODERATOR DILUTION
.M08610 E-03 RANCHO SECO - CYCLE 3 RELOAD REVIEH M12357 E-03 RANCHO SECO - CYCLE 4 RELOAD M08612 C-04 RANCHO SECO - FILTER TECH SPECS M11130 A-04 RANCHO SECO - APPENDIX J - CONTAINMENT LEAK TESTING M11285 D-04 RANCHO SECO REACTOR VESSEL CAVITY SEAL N06710 B-04 RANCHO SECO - REACTOR COOLANT SYSTEM OVERPRESSURIZATION' PROTECTION
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M44265 F-04 RANCHO SECO - NUREG-0737 I.C.1.2.A, INADEQUATE CORE COOLING GUIDELINES M44335 F-05 RANCHO SECO 1 - PROCEDURES GENERATION PACKAGE REVIEH (NUREG 0737 SUPP/1)
M07497 A-06 RANCHO SECO RESPIRATORY PROTECTION RELIEF M08589 C-06 RANCHO SECO - PHR PUMP & S/G SUPPORTS - LAMELLAR TEARING & FRACTURE TOUGHNESS
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! 9 R-1208731-001 REGULAT0RY INF0RMATION. TRACKING SYSTEM PAGE NO. 412 FACILIT'( IMPLEMENTATION 04/14/86
' RANCHO SECO 1 (CONTINUATION)
TAC NO. MPA 9 TITLE M47248 F-06 RANCHO SECD FEEDBACK OF OPE) TING EXPERIENCE (API.C.5)
M08314 C-07 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT - RANCHO SECO 1 M47320 F-07 RANCHO SECO - CORRECT PERFORMANCE OF OPERATING ACTIVITIES CAPI.C.6)
M51196 F-08 RANCHO SECD - I.D.1.1 - DETAILED CON' TROL ROOM DESIGN REVIEW PROGRAM PLAN F-08 M11328 B-08 RANCHO SECO HPSI - LPSI FLOH RESISTANCE M51276 F-09 RANCHO SECO 1 - I.D.2. SAFETY PARAMETER DISPLAY SYSTEM M08079 C-10 RANCHO SECO 1-CONTROL OF HEAVY LDADS DVER SPENT FUEL POOL (NUREG 0612)
M08002 D-10 RANCHO SECO - REVIEW OF ASYMMETRIC LOCA LOADS SUBMITTAL M44402 F-10 RANCHO SECO - NUREG-0737 II.B.1, RCS HIGH POINT VENTS M10563 A-10 RANCHO SECO - CONTINGENCY PLAN REVIEH M10569 A-11 RANCHO SECO - GUARD TRAINING PLAN REVIEW M47971 F-11 RANCHD SECO - PLANT SHIELDING MODIFICATIONS (II.B.2.2)
M10108 D-11 RANCHO SECO - ENHANCED FISSION PRODUCT RELEASE FOR HIGH BURNUP LHR FUEL M10564 A-12 RANCHO SECO - VITAL AREA ANALYSIS M44473 F-12 RANCHO SECO - NUREG-0737 II.B.3.2, POST ACCIDENT SAMPLING MODIFICATIONS M07788 D-13 RANCHO SECO HPI MODIFICATIONS M44544 F-13 RANCHO SECO - NUREG-0737 II.B.4.1, TRAINING FOR MITIGATING CORE M08599 D-14 RANCHO SECO - REACTOR VESSEL ATYPICAL HELD MATERIAL M10849 B-14 RANCHO SECO - CONTROL ROD GUIDE TUBE HEAR
'M33663 C-14 RANCHO SECO - SEISMIC QUALIFICATION OF THE AUXILIARY FEEDWATER SYSTEM M44615 F-14 RANCHO SECO 1 - RV AND SV TESTING M11288 A-14 RANCHO SECO - INSERVICE TESTING (REGION V)
N12616 A-15 QUALITY ASSURANCE REQUIREMENTS REGARDING DIESEL GENERATOR FUEL DIL
R-1208751-001 REGULAT0RY INF0RMATION. TRACKINO SYSTEM PAGE No.: 413 FACILITY IMPLEMENTATION 04/14,/86 RANCHO SECO 1 (CONTINUATION)
TAC NO. MPA 9 TITLE M12326 D-15 RANCHO SECO - HELB AND CONSEQUENTIAL SYSTEM FAILURE RANCHO SECO M44G73 F-15 RANCHO SECO - NUREG-0737 II.E.1.1, AFH SYSTEM EVALUATION M52264 C-15 RANCHO SECO - CONTROL OF HEAVY LOADS - PHASE II (FOLLDHUP OF MPASC-10)
M47565 A-16 RANCHO SECO - QUALIFICATIONS: INSP, EXAM, TEST, M12154 B-16 RANCHO SECO - UPGRADED EMERGENCY PLAN M44709 F-16 RANCHO SECO - NUREG-0737 II.E.1.2.1, AFH SAFETY GRADE AUTO INITIATION M58082 C-16 RANCHO SECO I - STEAM GENERATOR GENERIC REVIEN RECOMMENDATIONS CONCERNING STEAM GENERATORS (GL 85-02)
M44755 F-17 RANCHO SECO - NUREG-0737 II.E.1.2.2, AFH SAFETY GRADE FLON INDICATION M51126 A-17 RANCHO SECO 1 - INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDENT (RG 1.97)
M43042 D-17 RANCHO SECD - TECHNICAL SPECIFICATIONS DEFINING OPERABILITY FOR SAFETY SYSTEMS M43606 B-17 RANCHO SECO - SNUBBER INSERVICE SURVEILLANCE TECHNICAL SPECIFICATIONS (REGION V)
M44812 F-18 RANCHO SECO - NUREG-0737 II.E.4.1.2, DEDICATED HYDROGEN PENETRATIONS M51732 D-18 RANCHO SECO - NUREG-0630 CLADDING MODELS FOR LOCA ANALYSIS M55735 A-18 RANCHO SECO - TECH. SPECS. AFFECTED BY 50.72 AND 50.73 (GL 83-43)
M55896 D-19 RANCHO SECO - DIESEL GENERATOR RELIABILITY TECH. SPECS. (GL 84-15)
M44883 F-19 RANCHO SECO - NUREG-0737 II.E.4.2, CONTAINMENT ISOLATION DEPENDABILITY M59134 A-20 RANCHO SECO -10 CFR 50.62 OPERATING REACTOR REVIENS (ATHS)
M44954 F-20 RANCHO SECO - NUREG-0737 II.F.1.1, NOBLE GAS MONITOR M10321 B-20 RANCHO SECO - CONTAINMENT LEAKAGE DUE TO SEAT DETERIORATION
'M10383 B-21 RANCHO SECO - LOSS OF 125-V DC BUS VOLTAGE HITH LOSS OF ANNUNCIATOR SYSTEM M45025 F-21 RANCHO SECO - NUREG-0737 II.F.1.2, IODINE / PARTICULATE SAMPLING M59976 A-21 RANCHO SECO - 10CFR50.61 PRESSURIZED THERMAL SHOCK RULE REQUIREMENTS, PHASE 1 M45096 F-22 RANCHO SECO - NUREG-0737 II.F.1.3, CONTAINMENT HIGH RANGE MONITOR S
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.208731-001 REGULAT0RY INF0RMATION. TRACKING SYSTEM PAGE NO. 414 FACILITY IMPLEMENTATION 04/14/86 RANCHO SECO 1 (CONTINUATION)
TAC NO. MPA 9 TITLE M08605 B-22 RANCHO SECO - MECHANICAL SNUBBER SURVEILLANCE M10968 B-23 RANCHO SECO - DEGRADED GRID VOL TAGE M47032 F-23 RANCHO SECO - NUREG 0737 ITEM II F1.4 CONTAINMENT PRESSURE INSTRUMENT M47703 F-24 RANCHO SECG - NUREG 0737 ITEM II F1.5 CONTAINMENT HATER LEVEL MONITOR
,M42601 B-24 RANCHO SECO - LONG TERM REVIEN CONTAINMENT PURGE AND VENT (B-24)
M10206 B-24 RANCHO SECO - CONTAINMENT PURGE M47774 F-25 RANCHO SECO - NUREG 0737 ITEM II F1.6 CONTAINMENT HYDROGEN MONITOR M45106 F-26 RANCHO SECO - NUREG-0737 II.F.2.3, INADEQUATE CORE COOLING INSTRUMENTATION M10258 B-26 RANCHO SECO - INADVERTENT SAFETY INJECTION DURING C00LDOHN (PHR'S)
M42790 F-27 RANCHO SECO - CONFIRMATORY ORDER - ICS RELIABILITY ANALYSIS M45188 F-28 RANCHO SECO - NUREG-0737 II.K.2.10, SAFETY GRADE ARTS M45195 F-29 RANCHO SECO - NUREG-0737 II.K 2.11, OPERATOR TRAINING AND DRILLING M45202 F-30 RANCHO SECO - HUREG-0737 II.K.2.13, THERMAL-MECHANICAL REPORT M45209 F-31 RANCHO SECO - NUREG-0737 II.K.2.14, LIFT FREQUENCY OF PORV'S AND SV'S M45216 F-32 RANCHO SECO - NUREG-0737 II.K.2.16, RCP SEAL DAMAGE M45222 F-33 RANCHO SECO - NUREG-0737 II.K.2.17, POTENTIAL FOR VOIDING IN RCS M45228 F-35 RANCHO SECO - NUREG-0737 II.K.2.20, SYSTEM RESPONSE TO SB LOCA M10534 B-35 RANCHO SECO-ORIFICE ROD ASSEMBLY INTERITY,-B&H M45273 F-36 RANCHO SECO - NUREG-0737 II.K.3.1, AUTO PORV ISOLATION
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M45319 F-37 RANCHO SECO - NUREG-0737 II.K.3.2, REPORT ON PORV FAILURES M11284 B-38 RANCHO SECO - TENDON SURVEILLANCE M45376 F-38 RANCHO SECO - NUREG-0737 II.K.3.3, REPORT ON RV/SV FAILURES M08609 B-39 RANCHO SECO - PHR PRESSURE-TEMPERATURE TECH SPECS
- P R-1208731-001 REGULAT0RY INF0RMATION. TRACKING SYSTEM PAGE NO.s 415 FACILITY IMPLEMENTATION 04/14/86 RANCHO SECO 1 (CONTINUATION)
' TAC NO. MPA 0 TITLE M45440 F-39 RANCHO SECO - NUREG-0737 II.K.3.5, AUTO TRIP OF RCPS
'M11076 B-41 RANCHO SECO - FIRE PROTECTION SER SUPPLEMENT M43320 B-41 RANCHO SECO - FIRE PROTECTION - APPENDIX R M11926 B-42 RANCHO SECO-TMI FOLLOH-UP HORK M11927 B-42 RANCHO SECD - PUBLIC HEARINGS ON COMMISSION ORDER OF MAY 7, 1979 M11801 B-43 RANCHO SECO - FEEDWATER LINE CRACKS M12452 B-44 RANCHO SECO - LESSONS LEARNED IMPLEMENTATION
'M30612 B-44 RANCHO SECO-2.1.7.B CONTROL GRADE AUX FEED FLON INDICATION M30613 B-44 RANCHO SECO-2.1.5 A,C DEDICATED H2 CONTROL PENETRATIONS & RECOMBINER PROCEDURE M30614 B-44 RANCHO SECD-2.1.1. EMER. POWER SUPPLY PORV/ BLOCK VALVE, PER HEATER & LEVEL M30615 B-44 RANCHO SECO-2.2.2 A,B,C CONTROL ROOM ACCESS, TSC, OPERATIONAL SUPPORT CENTER M30316 B-44 RANCHO SECO-2.2.1 A,B,C SHIFT SUPER. RESP., STA, TURNOVER PROCEDURES M30617 B-44 RANCHO SECO-2.1.8.C IMPROVED IDDINE INST.
M30618 B-44 RANCHO SECO-2.1.8.B HIGH RANGE RADIATION MONITORS M30619 B-44 RANCHO SECO-2.1.8.A POST ACCIDENT SAMPLING M30620 B-44 RANCHO SECO-2.1.6.B SHIELDING REVIEW M30621 B-44 RANCHO SECO-2.1.6.A SYSTEMS INTEGRITY FOR HIGH RADI0 ACTIVITY M30622 B-44 RANCHO SECO-2.1.4 DIVERSE CONTAINMENT ISOLATION M30623 B-44 RANCHO SECO-2.1.3.8 INST. FOR CORE COOLING M30624 B-44 RANCHO SECO-2.1.3.A DIRECT INDICATION OF VALVE POSITION M30625 B-44 RANCHO SECO-2.1.2 RELIEF & SAFETY VALVE TESTING M12604 5-46 RANCHO SECO - ANALYSIS OF TURBINE DISC CRACKS M45302 F-47 RANCHO SECO - NUREG-0737 II.K.3.17, ECC SYSTEM OUTAGES S
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R-1208731-001 REGULAT0RY INF0RMATION. TRACKING SYSTEM PAGE NO.: 416 FACILITY IMPLEMENTATION 04/14/86 RANCHO SECO 1 (CONTINUATION)
TAC NO. MPA 9 TITLE M12746 B-48 RANCHO SECO - ADEQUACY OF STATION ELECTRIC DISTRIBUTION SYSTEMS VOLTAGES M42120 B-57 RANCHO SECO - DECAY HEAT REMOVAL CAPABILITY TECH SPECS M45859 F-57 RANCHO SECO - NUREG-0737 II.K.3.30, SB LOCA OUTLINE M48198 F-58 RANCHO SECO -NUREG 0737 II.K.3.31 COMPLIANCE HITH 1G CFR 50.46
.M42918 B-59 RANCHO SECO - MASONRY HALL DESIGN. RESPONSE TO IE BULLETIN 80-11 M42507 B-60 RANCHO SECO - ENVIRONMENTAL QUALIFICATI0H OF SAFETY RELATED ELECTRICAL EQUIPMENT (80-CLI-21)
'M42703 B-61 RAFCHO SECO - IE BULLETIN 79-27, LOSS OF NON CLASS IE INST & CONTR. POWER. REV. & EVAL. RESPONSES M42774 B-62 RANCHO SECD - ESF RESET CONTROL DESIGN DEFICIENCY - ISE BULLETIN 80-06 M45978 F-63 RANCHO SECO - NUREG-0737 III.A.1.2, TECHNICAL SUPPORT CENTER
'M43938 B-63 RANCHO SECO - STATION BLACKOUT PROCEDURES & TRAINING M46049 F-64 RANCHO SECO - NUREG-0737 III.A.1.2, OPERATIONAL SUPPORT CENTER M43264 B-64 RANCHO SECO - B&W ACCIDENT INDUCED NEUTRON FLUX ERRORS (MULTI-PLANT ITEM B-64)
M46121 F-65 RANCHO SECO - NUREG-0737 III.A.1.2, EMERGENCY OPERATIONS FACILITY M47173 B-66 RANCHO SECO 1 NATURAL CIRCULATION C00LD0HN (GENERIC LTR 81-21)
M46193 F-66 RANCHO SECO 1 - III.A.2 NUCLEAR DATA LINK DATA
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M46265 F-67 RANCHO SECO 1 - III. A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE M46337 F -68 RANCHO SECO - NUREG-0737 III.A.2.2, METEOROLOGICAL DATA UPGRADE M46855 B-69 RANCHO SECO - PhR MSLB HITH CONT'D FEEDHATER ADDITION M46408 F-69 RANCHO SECO - NUREG-0737 III.D.3.3, INPLANT RADIATION MONITORING M46477 F-70 RANCHO SECO - NUREG-0737 III.D.3.4, CONTROL ROOM HABITABILITY M46634 B-70 RANCHO SECO - MONITORING OF FATIGUE TRANSIENT LIMITS FOR THE REACTOR COOLANT SYSTEM M5G158 F-71 RANCHO SECD - I.D.1.2 DETAILED CONTROL ROOM DESIGN REVIEH
SUMMARY
REPORT - F-71 M49752 B-72 RANCHO SECO "NUREG 0737 TECH SPECS (GENERIC LETTER 82-16 82-16 OR 83-02)"
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R-1208731-001 REGULAT0RY INF0RMATION. TRACKING SYSTEM PAGE NO. 417 FACILITY IMPLEMENTATION 04/14/86 RANCHO SECO 1 (CONTINUATION)
TAC NO. MPA 9 TITLE M49616 B-73 RANCHO SECO - PLANS FOR PREVENTING EXCEEDING PTS SCREENING CRITERION M52793 B-76 RANCHO SECO - ITEM 1.1 - POST TRIP REVIEN PROGRAM DESCRIPTION AND PROCEDURES M52874 B-77 RANCHO SECD - ITEM 2.1 - EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE - RTS COMPONENTS M52955 B-78 RANCHO SECO - ITEMS 3.1.1/3.1.2 - POST MAINTENANCE TESTING PROCEDURES / VENDOR RECOMMENDATIONS-RTS COMPONENTS (REGION
.M53036 M-79 RANCHO SECO-ITEM 3.1.3 -POST-MAINTENANCE TESTING-CHANGES TO TECH SPECS-RTS COMPONENTS M53091 B-80 RANCHO SECO - REACTOR TRIP SYSTEM RELIABILITY - VENDOR RELATED MODIFICATIONS (REGION V)
M53144 B-81 RANCHO SECO - ITEMS 4.2.1 & 4.2.2 - PREVENTATIVE MAINT PROGRAM FOR REACTOR TRIP BREAKERS - MAINTENANCE & TREND M53190 B-82 RANCHO SECO - ITEM 4.3 - AUTDANTIC ACTUATION OF SHUNT TRIP ATTACHMENT FOR H AND B & H PLANTS M54352 B-83 RANCHO SECO-NUREG 0737 TECH SPEC - GL83-37 ( AMMEND #100)
MS3626 B-85 RANCHO SECO - ITEM 1.2 - POST TRIP REVIEH-DATA AND INFORMATION C..PABILITY M53709 B-86 RANCHO SECO - ITEM 2.2 - EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE - ALL SR COMPONENTS M53792 B-87 RANCHO SECO - ITEMS 3.2.1 & 3.2.2 - POST-MAINT TESTING PROCEDURES & VENDOR RECOMMENDATIONS - ALL SR COMP (REG M53875 B-88 RANCHO SECO - ITEM 3.2.3 - POST-MAINTENANCE TESTING -CHANGES TO TECH. SPEC. - ALL SR COMPONENTS M53931 B-89 RANCHO SECO - ITEMS 4.2.3 & 4.2.4-PREVENTATIVE MAINTENANCE PROGRAM FOR RX TRIP BREAKERS - LIFE TESTING & REPLACEME M55372 B-90 RANCHO SECO - ITEM 4.3)TS) - AUTOMATIC ACTUATION OF SHUNT TRIP FOR H AND B&H PLANTS - TECH SPECS (8114)
M53958 B-91 RANCHO SECO - ITEM 4.4 - IMPROVEMENTS IN MAINTENANCE AND TEST PROCEDURES FOR B & H PLANTS M54102 B-92 RANCHO SECO - ITEM 4.5.1-REACTOR SYSTEM FUNCTIONAL TESTING - DIVERSE TRIP FEATURES (REGION V)
M54019 B-93 RANCHO SECO - ITEMS 4.5.2 & 4.5.3 - REACTOR TRIP SYSTEM FUNCTIONAL TESTING - ALTEkNATIVES & TEST INTERVALS D
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