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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M8851999-10-0808 October 1999 Informs of Staff Determination That Listed Calculations Should Be Withheld from Public Disclosure,Per 10CFR2.790, as Requested in 990909 Affidavit ML20211J7731999-08-31031 August 1999 Forwards Insp Rept 50-312/99-03 on 990802-06.No Violations Noted.Insp Included Decommissioning & Dismantlement Activities,Verification of Compliance with Selected TS & Review of Completed SEs ML20211H7481999-08-13013 August 1999 Forwards Amend 126 to License DPR-54 & Safety Evaluation. Amend Changes Permanently Defueled Technical Specification (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP Level Alarm Switches with Generic Ref 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments ML20195B8511999-05-27027 May 1999 Forwards Change 4 to Rancho Seco Emergency Plan, Incorporating Commitments Made to NRC as Outlined in NRC .Emergency Plan Includes Two Listed Supporting Documents ML20207E9181999-05-27027 May 1999 Informs That Effective 990328,NRR Underwent Reorganization. within Framework of Reorganization,Div of Licensing Project Mgt Created.Reorganization Chart Encl ML20206U7411999-05-18018 May 1999 Provides Summary of 990217-18 Visit to Rancho Seco Facility to Become Familar with Facility,Including Onsite ISFSI & Meeting with Representatives of Smud to Discuss Issues Re Revised Rancho Seco Ep,Submitted to NRC on 960429 ML20206M1611999-05-10010 May 1999 Forwards Listed Proprietary Calculations to Support Review of Rancho Seco ISFSI Sar.Proprietary Encls Withheld ML20206E8591999-04-12012 April 1999 Provides Info Re High Total Coliform Result in Plant Domestic Sewage Effluent Prior to Confluence with Combined Effluent.Cause of High Total Coliform Result Was Broken Flow Rate Instrument.Instrument Was Repaired on 990318 ML20204H6751999-03-19019 March 1999 Forwards Insp Rept 50-312/99-02 on 990309-11.No Violations Noted.Portions of Physical Security & Access Authorization Programs Were Inspected ML20204E4031999-03-16016 March 1999 Submits Rept of Status of Decommissioning Funding for Rancho Seco,As Required by 10CFR50.75(f)(1).Plant Is Currently in Safstor, with Operating License Scheduled to Expire in Oct 2008 ML20204E6661999-03-11011 March 1999 Forwards Rancho Seco Exposure Rept for Individuals That Received Greater than 100 Mrem During 1998,IAW TS D6.9.2.2 & NRC Regulatory Guide 1.16 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 ML20207L1711999-03-10010 March 1999 Informs of Staff Determination That Supporting Calculations & Drawings Contained in Rev 2 of Sar, Should Be Withheld from Public Disclosure,Per 10CFR2.790 NL-99-002, Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3)1999-03-10010 March 1999 Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20207D4431999-03-0101 March 1999 Forwards Annual Radioactive Effluent Release Rept, for Rancho Seco Nuclear Generating Station for 1998 ML20207H6181999-02-18018 February 1999 Provides Attached Metrix & Two Copies of Rancho Seco ISFSI Sar,Rev 2 on Compact Disc,As Requested in 990209 Meeting. First Rounds of RAIs Dealt Primarily with Use of Cask as Storage Cask.Without Compact Disc ML20203D0761999-02-10010 February 1999 Ltr Contract:Task Order 37 Entitled, Technical Assistance in Review of New Safety Analysis Rept for Rancho Seco Spent Fuel Storage Facility, Under Contract NRC-02-95-003 ML20155D4431998-10-27027 October 1998 Forwards Amend 3 to Rancho Seco Dsar,Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode.With Instructions & List of Effective Pages NL-98-032, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1998-09-30030 September 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20237A6031998-08-0707 August 1998 Forwards Insp Rept 50-312/98-03 on 980706-09.No Violations Noted ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements ML20236Q9461998-07-15015 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-02 ML20236J6331998-06-30030 June 1998 Forwards Response to Violations Noted in Insp Rept 50-312/98-02.Corrective Actions:Util Revised RSAP-1003 to Clarify District Security Staff Responsibilities Re Handling & Review of Criminal History Info ML20236E8211998-06-0303 June 1998 Forwards Insp Rept 50-312/98-02 on 980519-21 & NOV Re Failure to Review & Consider All Info Obtained During Background Investigation.Areas Examined During Insp Also Included Portions of Physical Security Program ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 IR 05000312/19980011998-03-25025 March 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-01 on 980205 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) ML20202C4641998-02-0505 February 1998 Forwards Insp Rept 50-312/98-01 on 980105-08 & Notice of Violation.Insp Included Decommissioning & Dismantlement Work Underway,Verification of Compliance W/Selected TS & Main & Surveillance Activities Associated W/Sfp ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks ML20198K5391997-10-21021 October 1997 Forwards Insp Rept 50-312/97-04 on 970922-25 & Notice of Violation.Response Required & Will Be Used to Determine If Further Action Will Be Necessary ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility ML20198G8141997-08-22022 August 1997 Forwards Amend 125 to License DPR-54 & Safety Evaluation. Amend Permits Smud to Change TS to Incorporate Revised 10CFR20.Amend Also Revises References from NRC Region V to NRC Region IV ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 ML20149E5031997-07-10010 July 1997 Second Partial Response to FOIA Request for Documents. Forwards Records Listed in App C Being Made Available in Pdr.Records in App D Already Available in PDR ML20148P5161997-06-30030 June 1997 Second Partial Response to FOIA Request for Documents.App B Records Being Made Available in PDR ML20141A1721997-06-17017 June 1997 Forwards Insp Rept 50-312/97-03 on 970603-05.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program 1999-08-31
[Table view] Category:NRC TO UTILITY
MONTHYEARML20059N3331990-10-0202 October 1990 Forwards Notice of Consideration of Issuance of Amend to OL & Proposed NSHC Re 900426 Application for Possession Only License ML20059M6871990-09-14014 September 1990 Forwards Notice of Consideration of Issuance of Amend & Proposed NSHC Re Plant Physical Security Plan for Long Term Defueled Condition ML20059G9421990-09-10010 September 1990 Forwards Amend 115 to License DPR-54 & Safety Evaluation. Amend Revises License Condition Re Fire Protection Plan,Adds Administrative Controls to Tech Specs in Support of Fire Protection Plan & Relocates Fire Protection Requirements ML20056B4621990-08-22022 August 1990 Forwards Environ Assessment & Finding of No Significant Impact Re 900724 Request for Exemption to 10CFR50.47 ML20058N6461990-07-31031 July 1990 Forwards Insp Rept 50-312/90-11 on 900527-0706.No Violations Indentified ML20055E5151990-07-0303 July 1990 Requests Listed Addl Info on Licensee 900606 Plans Re Diesel Generator Operation as Peaking Power Supplies to Assure That Generators Will Be Maintained in Nondegraded Status IR 05000312/19900101990-07-0303 July 1990 Forwards Security Insp Rept 50-312/90-10 on 900611-22.No Violations Noted.Major Areas Inspected:Physical Protection. Rept Withheld (Ref 10CFR2.790 & 73.21) ML20055D5441990-06-28028 June 1990 Forwards Request for Addl Info Re 891129,900221 & 0327 Ltrs Concerning Computerized Commitment Tracking Sys,Long Range Scope List & Effluents & Water Mgt Project Action Plan Items Needing Deferral ML20248D3411989-09-25025 September 1989 Forwards Amend 8 to Indemnity Agreement B-66,reflecting Changes to 10CFR140,effective 890701 ML20248G7031989-09-21021 September 1989 Forwards Enforcement Conference Rept 50-312/89-16 on 890915 ML20248G5731989-09-21021 September 1989 Forwards Insp Rept 50-312/89-12 on 890801-04,21-25 & 30.No Violations or Deviations Noted.Concerns Raised Re Contamination Control Practices,Instrumentation Control & Informal Use of Vendor Data for Liquid Effluent Release ML20248B4131989-09-19019 September 1989 Provides Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exam to Be Administered on 891004.Map of Area,List of Lodging in Immediate Area & Preliminary Instructions for Taking Exam Encl ML20248C8401989-09-11011 September 1989 Forwards Insp Rept 50-312/89-14 on 890828-0901.Concern Raised Re Apparent Decrease in Level of Emergency Preparedness.Enforcement Action Will Be Subj of Separate Correspondence ML20247C4931989-09-0606 September 1989 Informs That 890901 Insp Determined That Preparedness to Respond to Emergency Was Degraded.Violation Involved Failure to Assign Individuals Qualified Per EPIP to Critical Emergency Response Position ML20247B7561989-09-0606 September 1989 Advises That Response to Generic Ltr 88-17 Re Expeditious Actions for Loss of DHR Acceptable.Training Program Should State That Maint Personnel Included in Program & Daily Walkdowns of Tygon Tube Areas Should Be Performed ML20246K4581989-08-18018 August 1989 Forwards Insp Rept 50-312/89-10 on 890603-0721.No Violations Noted ML20247H5551989-07-21021 July 1989 Advises That Util 890511 Response to SALP Meeting Rept 50-312/88-39 Appropriate & No Changes to 890328 SALP Board Rept Deemed Necessary ML20247F0291989-07-20020 July 1989 Redistributed Forwarding Amend 112 to License DPR-54.Amend Revises Tech Specs Re Increasing Max Closure Time for Selected Containment Isolation Valves & Addition of 12 Valves to Table 3.6-1 ML20247B4031989-07-19019 July 1989 Forwards Errata to Amends 109,110 & 111 to License DPR-54, Correcting Omission of Language from Revised Pages ML20247B2961989-07-17017 July 1989 Forwards Amend 112 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Increase Max Closure Time for Selected Containment Isolation Valves & Add 12 Valves to Table 3.6-1 ML20247J0581989-07-12012 July 1989 Forwards Insp Rept 50-312/89-08 on 890422-0602.No Violations or Deviations Noted ML20246D5241989-07-0707 July 1989 Forwards Request for Addl Info Re 10-yr Internal Inservice Insp Program Plan.Response Requested within 45 Days of Ltr Receipt ML20247A0471989-07-0606 July 1989 Forwards Insp Rept 50-312/89-11 on 890629-30.No Items of Noncompliance Noted IR 05000312/19890011989-06-30030 June 1989 Ack Receipt of Responding to Violations Noted in Insp Rept 50-312/89-01.Reasons for Denial of Violations a & B.2 Will Be Reviewed During Future Insp ML20246B0911989-06-28028 June 1989 Forwards Exemption from Requirements of 10CFR20,App a, Footnote d-2(c) to Allow Use of Radioiodine Protection Factor of 50 for MSA GMR-I Canisters at Plant,Per 881117 Request.Notice of Environ Assessment Also Encl ML20245J3301989-06-22022 June 1989 Provides Background Info on Regulatory Analysis Supplementing NRC Proposed Backfit,Per 890413 Request.Util Expected to Provide Schedule for Implementation of Required Improvements ML20245E0961989-06-20020 June 1989 Forwards Amend 111 to License DPR-54 & Safety Evaluation. Amend Revises Section 2.C.(4) of License Re Fire Doors & Dampers Based on Reevaluation of Fire Areas in Uitl 1985 Updated Fire Hazards Analysis ML20245F5731989-06-20020 June 1989 Advises That Senior Reactor Operator Licensing Writtem Exams & Operating Exams Scheduled for 890905 & 06-19,respectively. Encl Ref Matl Requested by 890710 in Order to Meet Schedule ML20245A1831989-06-0909 June 1989 Forwards Amend 110 to License DPR-54 & Safety Evaluation. Amend Removes Tabular Listing of Snubbers from Tech Specs as Suggested by Generic Ltr 84-13 NUREG-0460, Forwards Safety Evaluation & Inel Rept EGG-NTA 8341, Providing Details & Basis for Concluding That Existing Intervals for on-line Functional Testing at Plant Should Result in High Reactor Trip Sys Availability.W/O Inel Rept1989-06-0606 June 1989 Forwards Safety Evaluation & Inel Rept EGG-NTA 8341, Providing Details & Basis for Concluding That Existing Intervals for on-line Functional Testing at Plant Should Result in High Reactor Trip Sys Availability.W/O Inel Rept ML20248B9451989-06-0505 June 1989 Forwards Amend 109 to License DPR-54 & Safety Evaluation. Amend Revises Tech Spec 4.17, Steam Generators & Associated Bases & Tables 4.17-2A & 417-2B to Permit Repairs of Steam Generator Tubes by Means of Tube Sleeves ML20248B9191989-06-0505 June 1989 Forwards Amend 107 to License DPR-54 & Safety Evaluation. Amend Removes Requirements for Fire Suppression Sys in Fire Zones 75-80 from Tech Spec 3.14 ML20248B6091989-06-0505 June 1989 Forwards Amend 108 to License DPR-54 & Safety Evaluation. Amend Modifies Paragraph 2.C.(3) to Require Compliance W/ Amended Physical Security Plan ML20248B6611989-06-0202 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/89-04 ML20247P1571989-05-30030 May 1989 Forwards Safety Evaluation Accepting Util 831104 Response to Item 4.5.2 of Generic Ltr 83-28, Reactor Trip Sys Reliability ML20247J1831989-05-25025 May 1989 Forwards Notice of Withdrawal of 860613 Application for Amend to License DPR-54 to Modify Tech Specs Pertaining to Deletion of Nonradiological Items Contained within App B Tech Specs & LER Clarifications ML20247K7061989-05-23023 May 1989 Forwards Amend 105 to License DPR-54 & Safety Evaluation. Amend Clarifies Operational Mode of Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Train & Revises Frequency for Verifying Auxiliary Feedwater Sys Flow Path ML20247M9001989-05-23023 May 1989 Forwards Amend 106 to License DPR-54 & Safety Evaluation. Amend Revises Tech Spec 4.17, Steam Generators, to Provide for More Extensive Insp of Steam Generator Tubes by Defining Tube Areas to Complete 100% Insp Where Degradation Expected IR 05000312/19890051989-05-17017 May 1989 Forwards Insp Rept 50-312/89-05 on 890304-0421.Two Noncited Violations Noted ML20247K6621989-05-16016 May 1989 Forwards Amend 104 to License DPR-54 & Safety Evaluation. Amend Deletes Tech Specs Re Reactor Vessel Matl Surveillance.Approval to Use B&W Integrated Reactor Vessel Matl Surveillance Program,Per 851014 & s,Approved IR 05000312/19880021989-05-12012 May 1989 Discusses Insp Rept 50-312/88-02 on 880104-14,0210-12 & 0307-09.Violations Noted.Advises That Violations Demonstrated Lack of Mgt Control Over Certain Aspects of Procurement Program.Enforcement Action Not Necessary ML20247B1341989-05-12012 May 1989 Forwards State of CA 1987 Environ Radiological Measurements Rept,Per Cooperative Agreement NRC-32-83-684.No Outstanding Concerns Identified in Data Comparisions Between Util & State Measurements ML20246M6271989-05-11011 May 1989 Advises That plant-specific Reactor Coolant Pump Trip Setpoint Development,Per TMI Action Item II.K.3.5, Acceptable,Based on Methodology Contained in Generic Ltr 86-05 IR 05000312/19890061989-05-11011 May 1989 Forwards Safeguards Insp Rept 50-312/89-06 on 890424-28.No Violations Noted.Evaluation of Plant Security Sys Conducted Through Extended Augmented Sys Review Requested.Rept Withheld (Ref 10CFR2.790(d)) ML20246P4801989-05-10010 May 1989 Advises of Locations & Features That Geologists Need to Inspect for Completion of Review of Sept 1987 Response to NRC Questions on Geologic & Seismologic Conditions ML20246M1741989-05-0808 May 1989 Submits Addendum to Safety Evaluation Supporting Amend 92 to License DPR-54,per Util 881129 Request to Revise Safety Evaluation.Approval to Extend Refueling Interval as Applies to Reactor Vessel Vent Valve Granted ML20246F4631989-05-0404 May 1989 Forwards Safety Evaluation & Technical Evaluation Rept Supporting Util Inservice Testing Program for Pumps & Valves.Certain Relief Requests Denied Where Proposed Alternative Testing Unacceptable ML20246H9151989-04-28028 April 1989 Forwards Insp Rept 50-312/89-07 on 890417-21.No Violations Noted ML20245J9031989-04-25025 April 1989 Advises of Special Emergency Operating Procedure Insp Program.Initiative Includes Team Insp of B&W Plants Not Insp Under 1988 Initiative ML20245F8771989-04-18018 April 1989 Forwards Amend 103 to License DPR-54 & Safety Evaluation. Amend Revised Tech Specs by Changing Air Flow Rate Through Reactor Bldg Purge Valves,Adding Requirement to Test Reactor Bldg Purge Exhaust HEPA Filters 1990-09-14
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M8851999-10-0808 October 1999 Informs of Staff Determination That Listed Calculations Should Be Withheld from Public Disclosure,Per 10CFR2.790, as Requested in 990909 Affidavit ML20211J7731999-08-31031 August 1999 Forwards Insp Rept 50-312/99-03 on 990802-06.No Violations Noted.Insp Included Decommissioning & Dismantlement Activities,Verification of Compliance with Selected TS & Review of Completed SEs ML20211H7481999-08-13013 August 1999 Forwards Amend 126 to License DPR-54 & Safety Evaluation. Amend Changes Permanently Defueled Technical Specification (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP Level Alarm Switches with Generic Ref ML20207E9181999-05-27027 May 1999 Informs That Effective 990328,NRR Underwent Reorganization. within Framework of Reorganization,Div of Licensing Project Mgt Created.Reorganization Chart Encl ML20206U7411999-05-18018 May 1999 Provides Summary of 990217-18 Visit to Rancho Seco Facility to Become Familar with Facility,Including Onsite ISFSI & Meeting with Representatives of Smud to Discuss Issues Re Revised Rancho Seco Ep,Submitted to NRC on 960429 ML20204H6751999-03-19019 March 1999 Forwards Insp Rept 50-312/99-02 on 990309-11.No Violations Noted.Portions of Physical Security & Access Authorization Programs Were Inspected ML20207L1711999-03-10010 March 1999 Informs of Staff Determination That Supporting Calculations & Drawings Contained in Rev 2 of Sar, Should Be Withheld from Public Disclosure,Per 10CFR2.790 ML20203D0761999-02-10010 February 1999 Ltr Contract:Task Order 37 Entitled, Technical Assistance in Review of New Safety Analysis Rept for Rancho Seco Spent Fuel Storage Facility, Under Contract NRC-02-95-003 ML20237A6031998-08-0707 August 1998 Forwards Insp Rept 50-312/98-03 on 980706-09.No Violations Noted ML20236Q9461998-07-15015 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-02 ML20236E8211998-06-0303 June 1998 Forwards Insp Rept 50-312/98-02 on 980519-21 & NOV Re Failure to Review & Consider All Info Obtained During Background Investigation.Areas Examined During Insp Also Included Portions of Physical Security Program IR 05000312/19980011998-03-25025 March 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-01 on 980205 ML20202C4641998-02-0505 February 1998 Forwards Insp Rept 50-312/98-01 on 980105-08 & Notice of Violation.Insp Included Decommissioning & Dismantlement Work Underway,Verification of Compliance W/Selected TS & Main & Surveillance Activities Associated W/Sfp ML20198K5391997-10-21021 October 1997 Forwards Insp Rept 50-312/97-04 on 970922-25 & Notice of Violation.Response Required & Will Be Used to Determine If Further Action Will Be Necessary ML20198G8141997-08-22022 August 1997 Forwards Amend 125 to License DPR-54 & Safety Evaluation. Amend Permits Smud to Change TS to Incorporate Revised 10CFR20.Amend Also Revises References from NRC Region V to NRC Region IV ML20149E5031997-07-10010 July 1997 Second Partial Response to FOIA Request for Documents. Forwards Records Listed in App C Being Made Available in Pdr.Records in App D Already Available in PDR ML20148P5161997-06-30030 June 1997 Second Partial Response to FOIA Request for Documents.App B Records Being Made Available in PDR ML20141A1721997-06-17017 June 1997 Forwards Insp Rept 50-312/97-03 on 970603-05.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program ML20140G6341997-05-0707 May 1997 Forwards ERDS Implementation Documents Including Data Point Library Updates for McGuire Number 224,WNP2 Number 225, Beaver Valley Number 226 & Calvert Cliffs Number 227. W/O Encl ML20140E6911997-04-25025 April 1997 Forwards Insp Rept 50-312/97-02 on 970331-0403.No Violations Noted ML20137C7211997-03-21021 March 1997 Forwards Insp Repts 50-312/97-01 & 72-0011/97-01 on 970224-27.No Violations Noted ML20129G7431996-09-27027 September 1996 Forwards Insp Repts 50-312/96-03 & 72-0011/96-01 on 960909-12.No Violations Observed ML20059J9771994-01-14014 January 1994 Informs That Document Rancho Seco ISFSI Sar,Vol Iv,Drawings & Calculations Submitted on 931027,w/Pacific Nuclear Fuel Services Group Affidavit of 931006 Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5),as Requested ML20058D6291993-11-19019 November 1993 Forwards Exemption from Requirements of 10CFR140.11(a)(4) to Extent That Primary Financial Protection in Stated Amount Shall Be Maintained ML20058C9721993-11-0202 November 1993 Ack Receipt of Transmitting Rev 6 of Section 5 to Plant Emergency Plan.Advises Revised Emergency Plan Continues to Meet Planning Stds in 10CFR50.47(b) & Requirements of 10CFR50 App E ML20057D1841993-09-27027 September 1993 Grants Exemption from Requirements in 10CFR50.120 to Establish,Implement,& Maintain Training Programs,Using Sys Approach to Training,For Categories of Personnel Listed in 10CFR50.120.Exemption Effective 931122 & Encl IR 05000312/19930031993-09-24024 September 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/93-03 ML20057A3251993-09-0202 September 1993 Forwards Environmental Assessment & Fonsi Re Exemption from Requirements of 10CFR50.120 at Plant ML20057C4971993-09-0202 September 1993 Forwards Insp Rept 50-312/93-06 on 930819.No Violations or Deviations Noted ML20056F0011993-08-11011 August 1993 Forwards Mgt Meeting Rept 50-312/93-04 on 930727 ML20056G0041993-06-25025 June 1993 Submits Info Re Implementation of Training Rule 10CFR50.120 for Licensees of Plant in Decommissioning Process ML20127D3451993-01-0808 January 1993 Advises That 921105 Rev 3 to Rancho Seco Security Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan ML20127D3351993-01-0606 January 1993 Ack Receipt of 921105 & 30 Ltrs,Transmitting Rev 6 & Suppl 1 to Physical Security Plan.Changes Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan ML20126E2751992-12-10010 December 1992 Forwards Insp Rept 50-312/92-07 on 921110-11.No Deviations or Violations Noted ML20062G9951990-11-15015 November 1990 Forwards Insp Rept 50-312/90-14 on 901003-04,09-11 & 1102. Violations Noted But Not Cited ML20062C1921990-10-24024 October 1990 Advises That Commissioner Jr Curtiss Will Visit Facility on 901105 to Tour Plant & Meet W/Util Mgt & Personnel to Review General Status of Activities.W/Certificate of Svc.Served on 901024 ML20058G4471990-10-18018 October 1990 Forwards Sept 1990 Rept to Commission on Implementation of TMI Action Plan Items,Per 900320 Commitment.W/O Encl.Review Concluded for All But Two Units ML20059N3331990-10-0202 October 1990 Forwards Notice of Consideration of Issuance of Amend to OL & Proposed NSHC Re 900426 Application for Possession Only License ML20059M6871990-09-14014 September 1990 Forwards Notice of Consideration of Issuance of Amend & Proposed NSHC Re Plant Physical Security Plan for Long Term Defueled Condition ML20059G9421990-09-10010 September 1990 Forwards Amend 115 to License DPR-54 & Safety Evaluation. Amend Revises License Condition Re Fire Protection Plan,Adds Administrative Controls to Tech Specs in Support of Fire Protection Plan & Relocates Fire Protection Requirements ML20056B4621990-08-22022 August 1990 Forwards Environ Assessment & Finding of No Significant Impact Re 900724 Request for Exemption to 10CFR50.47 ML20056A5991990-08-0303 August 1990 Responds to Re Interaction of NRC W/Util to Facilitate Expeditious Closure of Plant.Nrc Continuing to Work Expeditiously on Number of Other Requests from Util. Prioritization Schedule Developed for Pending Applications ML20058N6461990-07-31031 July 1990 Forwards Insp Rept 50-312/90-11 on 900527-0706.No Violations Indentified ML20055G9791990-07-20020 July 1990 Responds to Expressing Concern Re Issuance of Possession Only License Amend.Nrc Project Manager Will Notify by Telephone When Util Submits Application Matl for Possession Only License Amend ML20055E5151990-07-0303 July 1990 Requests Listed Addl Info on Licensee 900606 Plans Re Diesel Generator Operation as Peaking Power Supplies to Assure That Generators Will Be Maintained in Nondegraded Status IR 05000312/19900101990-07-0303 July 1990 Forwards Security Insp Rept 50-312/90-10 on 900611-22.No Violations Noted.Major Areas Inspected:Physical Protection. Rept Withheld (Ref 10CFR2.790 & 73.21) ML20055D5441990-06-28028 June 1990 Forwards Request for Addl Info Re 891129,900221 & 0327 Ltrs Concerning Computerized Commitment Tracking Sys,Long Range Scope List & Effluents & Water Mgt Project Action Plan Items Needing Deferral ML20058K5791990-05-22022 May 1990 Final Response to FOIA Request for Records.App G & H Records Available in Pdr.App H & Releasable Portions of App J Documents Encl.App I Records Withheld in Entirety & App J Record Partially Withheld (Ref FOIA Exemptions 5 & 7) ML20055D6511990-05-10010 May 1990 Partial Response to FOIA Request for Info.App D & Releasable Portions of App E Documents Encl.Portions of App E Documents & App F Documents Withheld (Ref FOIA Exemptions 5,6 & 7) ML20248D3411989-09-25025 September 1989 Forwards Amend 8 to Indemnity Agreement B-66,reflecting Changes to 10CFR140,effective 890701 1999-08-31
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20cket No.: 50-312 DEC 141979 e W Mr. J. J. Mattimoe S Assistant General Manager and d p Chief Engineer Sacramento Municipal Utility District ll- #gf [ y A T._
6201 S. Street 2" -
P. O. Box 15830' ghgD , gg 'S Sacramento, California 95813 g.y
Dear Mr. Mattimoe:
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SUBJECT:
RANCHO SECO EMERGENCY PROCEDURES FOR SMALL-BREAK LOCAs
Reference:
Letter, R. S. Davis to S&W 177 Owners' Group - Technical Subcommittee on TMI-2 Incident Related Tasks dated November 27, 1979 During a meeting with the NRC staff on November 8,1979, Mr. Rodriguez of your staff discussed the way he interpreted IE Sulletin 79-05C with regard to reactor coolant pump (RCP) trip for both LOCA and non-LCCA transients.
Mr. Rodriguez stated that upon seeing the symptoms of a LOCA, the operator would take certain immediate actions to regain control of reactor coolant system (RCS) pressure and pressurizer level. These actions may include the manual initiation of high pressure injection (HPI). By aanually initiating HPI, prior to aute:natic initiation at 1600 psig, the operator would not be required to trio the RCPs even if RCS pressure dropped below the autcmatic actuation setpoint. Mr. Rodriguez correctly stated that IE Bulletin 79-05C reads, "Upon reactor trip and initiation of HPI caused by low reactor coolant system pressure, iricediately trip all operating RCPs." He interpreted the words " ... initiation of HPI caused by low reactor coolant system pressure" as meaning automatic initiation. He based his accaptability of this approach on an analysis performed by Scbcock & Wilcox (3&W) :hich shows that for the range of breaks requiring RC? trip, the reactor coolant system prassure decreases at such a rate that the ocerator would not have time to take manual action prior to reaching the automatic setpoint.
Following manual initiation of HPI, the cperator would -onitor primary system parameters including the 1.? cunt of subcooling in the hot leg. If 200F of subcooling could not be maintained, the operators were instructed to trip the RCPs. Thus, it was believed that this overall approach would preclude tripping of the PCPs for non-LOCA transients even if the low pressure HPI actuation setpcint clas reached. However, RCP trip for LOCA transients would be assured by the predicted pressure decay rate and the hot leg subcooling cri aria.
c)0'02327 4 800114 o (gy
05 .
Mr. J. J. Mattimoe DEC 1
- 1979 At the m.ceting, the staff stated that although we agreed in principle with this approach, it did not moet the intant of the bulletin. We requested that 57.90 submit to the staff, for evaluation, additional information regarding this matter.
'Sile we hava not received a formal submittal from you, we ha.ve received the reference letter ,vhich was transmitted to us by B&W at your request. Fecm our review of this letter, we cannot at this time conclude the acceptability of the Rancho !cco interpretation of Sulletin 79-05C for RCP trip critaria.
This was di:.cussad with ifr. Rodriguez on Caccmber 6,1979. In additien, the reference letter identifies a concern with regard to manually initiating -
"P bec ,use frequent actuation will add appreciability to approaching Je dasign thanaal cycles on the HPI nozzles.
In order to fully evaluate the acceptability of your approach, we would need the additional information described in the enclosure. Therefore, until we have received this information and have provided our approval, we require that your procedures comply fully with the staff requirements for B&W plants; namely that when primary pressure reaches the HPI actuation setpoint, the operators are to manually trip the reactor coolant pumps.
Sincerely, Q 67 D. FI oss, Jr. , Director Bulletins and Orders Task Force Office of Nuclear Reactor Regulation
Enclosure:
.is stated -
cc: R. Rodriguez ',3 MUD)
R. Gill, (B&W Owners' Group)
J. Taylor (B&W) e t
90023275
RELATED CORRESPONDENCE 3 ' i s t!'i : .
Christopher Eilisen, Esq.
g i l% / 'b Dian Grueuf ch, Esc.
David S Xapian, Secretary California Energy' Commission General Counsel r. y A 1111 Howe Avenue 52::1 S Street O. cx 15S30
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- Sacramento, California 95825 Sa:ramen o, California g5 551 3 g S cra. ento County
~ 9@@*h4@g/ 6 Ms. Eleanor Schwart:
California State Office 600 Fennsyl vania Aver.ae , S. E. , Rm. 201 3:ard of'Su;ervisors Washington, D.C. 20003 s
527 7th Street, Room 424 %
Scramer.to, California 9581 68I Docketing and Service Section
~
- Mrbert H. Grown, Esq. Office of the Secret?.ry U vence Coe :4anpher, Esq.
U. S. Nuclear Reculatory Commission .
'!ashincten, D.C. 20555 Mill, C*iristcpher and Phillips, P.C. .
1900 M St.eet, N W .
Thoma5 A'. Baxter, Esq.
hshington D C 20036 - Shaw, Pittman, Potts *, Troworidge
.irector, T. ec hnical Assessrent 1800 M Street N W Washinoton, D. C. 20036 Division Dr. Richard F. Cole Cf f1[,D')ce y Radiation Programs Atomic Safety and Licensing Board S. -nvirencental Protection Agency
.e . Panel
-U. S. Nuclear Regulatory Comission yrystal I.all e2 Washington, D.C. 20555
. cling:cn, v,irginia ,0460 4
Ul S. Envi r:nmental Protection Agency Mr. Frederick J. Shen Atomic Safet"v and Licensing Board yagion y 0,iice 4TTfh :.IS COORDINATOR ?anel
-- U. S. Nuclear Reculatory Co=ission
- jan. a;.-rem:ntStreet r anci sco , Ca ii r.ornia 94111 Washington, D.C. ~ 20555 Mr. Richard D. Castro D'. ROLart 3. 3ersum 2231 K Street
?ac::ck & Wilcox Sacramento, California 0551a Lclear ~?cwer Generation ivision Suita 420, 7735 Old Georce:o-n Read -
! l Cathesda, Maryland 20054 James S. Reed, Esq.
Atomic Safety & Lic'ensing' Board Panel Michael H. Remy, Esq.
U. S. % clear Regulatory Ccanission Reed, Samuel & Remy Washington D C 20555 717 K Street, Suite a05 Sacramento, California 95314 At:mic Safety & Licensing Appaal Board Panel U. S. ':uclear 0.egulatory Ccmission Mr. Gary Hursh, E'sq.
,ashin; ton, D. C. 205cc 520 Capitol Mail - Suite 700 5acramento, California 95314 5:iza:stn S. Iowers, Esq. , Chairman California Depart: ent cf Health
.:mic Safe:y L Licensing Scarc Fanel ATTil: Chief, Envir nnantal Radiaticn V, 5. '.; clear Reculat:ry C:=ission Control Unit
.:shir n:n, D. C! 20555
" Eadiciocical Health Secti:n 714 ? Sireet, Room a98
'r. 'i :h ael R. Eat:n Sacramento, California 95514 5 ar;y Issues Coor:inator Sierra Cl.b '_egislative Cffice l'07 i:h 5:rcct Eccm 1C20
- u n. e :0, : m eni3 g5 m 90023276
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HPI upon reactor trip is necessary, then a recre complete explanatien of <hy it is necessary should be provided. 'oreover, you should submit your plan for ongoing stress analysis of the HPI nozzles to assure they have been designed to withstand the plant transients to which they have been exposed.
- 5. .The staff believes that pump trip based on loss of hot leg subccoling should rely on direct measurement of hot leg subcocling, and not by ,
indirect means, such as comparison by the operators of measured to saturation temperatures at the' system pressure frorr steam tables.
Ofscuss the instruments to be used by the operator to determine subcooling.
Discuss how their uncertainty, the uncertainty of the coolant temperature measurement, and the measurement time constant both are accounted for in the procedures as well as how they affect availaole operator L n.n I time. !
1 l
l 90023277
. . . ~ ,. . ., ..' ,. , l 7
istri:-
Christopher Ellisen, Esq.
Dav id S. Y.aplan, Secretary and Dian Grueuich, Esq.
California Energy Cor..a.ssion Sensral Counsel lill Howe Avenue c2 I,01o,5ge (jrati'5830 Sacramento, California 9582:.
Sacramen o, California 95813 Ms. Eleanor 5:,nwartz 1 S cramento County California State Office r- ' 3) 600 Pennsyl vania .. venue, S- ,. , .m 3:a:d of'5upervisors Washington, D.C. eu003 S27 7th Street, Room 424 .
Sacramento, California 95814 -
Docketing anc. Service Section Herbert H. Brown, Esq. Office of the Secretary , ,
Lawrence Coe Manpher, Esq. U. 5. Nuclear Regulatory Commission '
Washingt:n, D.C. 20555 Hill, Christopher and Phillips, P.C.
1900 M Street, N W Thomas. .A.. . Baxter, Esq.
'lashington 0 C 20036 Shaw, Pittman, Potts & Trowbridge
- f re'ctor, Technical Assessment 1800 N Street N W Washington, D. C. 20036 .
Divisien Office of Radiation Programs Dr. Richard F. Cole
~
(AW-459) Atomic Safety and Licensing 5 card U. S. Environmental Protection Agency Panel -
Crystal Mall #2 U. S. Nuclear Regulatory Corm.ission Arling :n, Virginia 20460 Washington, D.C. 20555 Ul S. Environmental Protection Agency Mr. Frederick J. Shen Atomic Safety and Licensing Board gigion p Office iiN: -IS COORDINATOR Panel U. S. Nuclear Reculatory Commissien
.jl:r.
remon:. Street ~
.an reancisco, Callrornia..
94111 Washing:en, D.C. 2C555 Mr. Ecbert 3. 5crsum Mr. Richard D. Castro 5ab::ck & Wilcox 2231 K Street Sacramento, California 95314
%cisar' Power Generation Division Ivi ta a20, 7735 Cid Georgetown Road -
Eethesda, Maryland 20014 James S. Reed, Esq.
Atomic Safety & Lic'ensincj Board Panel Michael H. Remy, Esq.
V. S. *:uclear Regulatory Commission Reed, Samuei & Remy Washington 0 C 20555 717 K Street, Suite 105 :
Sacramento, California 95814 At:mic Safety & Licensing Appeal Scard Panel U. S. I;uclear Regulatory C0mmission Mr. Gary Mursh, Esq.
'ashington, D. C. 20555 520 Capitol Mall - Suite 700 Sacramento, California 95314 Eli:a:eth S. 5cuers, Esq., Chairman California Department of Mealth A :mic Safety & Licensine Board Panel ATTH: Chief, Environmental Radia-icn U. S. *.uclear Recula:Ory"Crmission C:ntrol Unit
- ashin .:n, D. C! 20553
- Radiolecical Heal .h Secti n 71a P Street, Room 293
- 'r. .'i:nael R. 5aton Sacramen c, California 95514 Ener;y Issues C::rcinator -
Sierra 12 Legislative Office 1107 9 n Street Re:m 1C20 -
5acra.an0, California 95514 90023(l0
.f.
istri:-
Christopher Eilisen, Esq.
David S. Kaplan, Secretary and Ofan Grueufch, Esc. .
California Energy Cor..ission General Counsel lill Howe Avenue 95825 5201 S S:reet Sacramento, Califcrnia
. O. Sex 15330 Sacramen o, California 95813 Ms. Eleanor 5:hwartz 5 cramento County California State Office 600 Pennsyl vania Avenue , S.E. , Em. D1 B:ard of'Eupervisors Washington, D.C. 20003 827 7th Street, Room 424 ,
Sacramento, California 95814 Docketing and ' Service Section Harbert H. Brown, Esq. Office of the Secretary Lawrence Coe Manpher, Esq.
U. S. Nuclear Regulatory Commission -
Washington, D.C. 20555 Hill, Christopher and Phillips, P.C. '
1900 M Street, N W Thomas'A. Saxter, Esq.
Washington 0 C 20036 Shaw, Pittman, Potts & Trewbridge *
.i re'cto'r, T'echnical Assessment 1800 M Street N W Washington, O. C. 20036 ,
Civisien Office of Radiation Programs Dr. Richard F. Cole Atomic Safety and Licensing Board
,J.S.i9}
(AW cnvironmental Protection Agency Panel U. S. Nuclear Reculatory Commissior.
grystalMalle2 Washington , D. C.' 20555
,.rlingten, Virginia 20460 Ul S. Environmental Protection Agency Mr. Frederick J. Shon Region IX Office Atomic Safety and Licensing Board ATTN: EIS COORDINATOR Panel .
. 215 Frem:nt Street- U. S. Nuclear Regulatory Commissica San Francisco, California 94111 Washington, D.C. 20555 Mr. Robert S. Borsum Mr. Richard O. Castro 2231 K Street
?abc:ck & Wilcox Sacramento, California 95514
%claar ' Power Generation Division Icit2 420, 7735 Old Georgetown Road -
Othesda, Maryland 20014 James S. Reed, Esq.
Atomic Safety & Lic'ensingi Board Panel Michael H. Remy, Esq.
V. S. Muclear Regulatory Commission Reed, Samuel & Remy Washington 0 C 20555 717 K Street, Suite 405 Sacramento, California 95814 Atemic Safety & Licensing Appeal Board Panel i U. S. Nuclear Regulatory Commission Mr. Gary Mursh, Esq.
, asnin;:en, D. C. 20555 520 Capitol Mall - Suite 700 Sacramento, California 95814 E'iza':e:h S. Ecwers, Em ., Chairman California Department of Health A::mic Safety & Licv. sing Board Panel ATTN: Chief, Environrental Radia:i:n
'J. 5. '.; clear Regu n:Ory Commission C:n:rol Unit
.:ashin;;:n, D. C. 20555 Radi:1ccical Health Section 714 p street, Room a93
'jr. icjael R. Eaton Sacramen:c, California 95514
- .nargy .ssues Coordina:or Sierra :1.b Legislative Cffice 1107 i:n Street Room 1020 '
- ur ran:0, alifornia g55" 90023279 l
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C.. closure
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Mditicnal Infomation Needs on Rancho, Seco Pumo Trip Procedures 1
- 1. Submit a copy of your proposed procedures which would allow pump operation beyond ESFAS actQating on low pressure and only require manual trip on loss of subcooling margin.
- 2. You have stated that for small breaks in which analyses indicate pump trip is necessary, the pressure decay to the HPI lcw pressure actuation setpoint will occur before opeator action could be taken to manuaily initiate HPI.
Provide more detailed information on why th.e operators do not have ancugh time to take this action.
Present analyse's indicate a maximum of 2 minutes to be available to the operator to trip the pumps if excessive cladding temperature are to be avoided for all small breaks. If the operators manually initiate HPI and therefore base pump trip on hot leg subcooling, hcw much time is available to trip the pu.wr Pee the subcooled condition no longer exists?
- 3. The approved B&W gu " ines stata that when HPI is actuated because of low pressure conditions, spen .fic criteria must be met (e.g., 50*F subccoling) before HPI can be terminated. If the HPI is manually initiated for a small break, per your procedures, are the termination critaria still to be folicwed?
If not, explain why?
- 4. In the reference to the transmittal letter, B&W ex;ressed c:ncern regarding the capability of the HPI nozzles to accormodate a high nurter cf cycles of HPI injection associated with HPI being manually 60tuated upon react:r trip.
D,e staff is not of the opinion that manual actuation of hPI up;n react:r trio is a prudent course of action to take since the system was not specifically designed to cparate in this rede. If you ccnclude that mar.ual ir.itiatien of 90023280