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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M8851999-10-0808 October 1999 Informs of Staff Determination That Listed Calculations Should Be Withheld from Public Disclosure,Per 10CFR2.790, as Requested in 990909 Affidavit ML20211J7731999-08-31031 August 1999 Forwards Insp Rept 50-312/99-03 on 990802-06.No Violations Noted.Insp Included Decommissioning & Dismantlement Activities,Verification of Compliance with Selected TS & Review of Completed SEs ML20211H7481999-08-13013 August 1999 Forwards Amend 126 to License DPR-54 & Safety Evaluation. Amend Changes Permanently Defueled Technical Specification (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP Level Alarm Switches with Generic Ref 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments ML20195B8511999-05-27027 May 1999 Forwards Change 4 to Rancho Seco Emergency Plan, Incorporating Commitments Made to NRC as Outlined in NRC .Emergency Plan Includes Two Listed Supporting Documents ML20207E9181999-05-27027 May 1999 Informs That Effective 990328,NRR Underwent Reorganization. within Framework of Reorganization,Div of Licensing Project Mgt Created.Reorganization Chart Encl ML20206U7411999-05-18018 May 1999 Provides Summary of 990217-18 Visit to Rancho Seco Facility to Become Familar with Facility,Including Onsite ISFSI & Meeting with Representatives of Smud to Discuss Issues Re Revised Rancho Seco Ep,Submitted to NRC on 960429 ML20206M1611999-05-10010 May 1999 Forwards Listed Proprietary Calculations to Support Review of Rancho Seco ISFSI Sar.Proprietary Encls Withheld ML20206E8591999-04-12012 April 1999 Provides Info Re High Total Coliform Result in Plant Domestic Sewage Effluent Prior to Confluence with Combined Effluent.Cause of High Total Coliform Result Was Broken Flow Rate Instrument.Instrument Was Repaired on 990318 ML20204H6751999-03-19019 March 1999 Forwards Insp Rept 50-312/99-02 on 990309-11.No Violations Noted.Portions of Physical Security & Access Authorization Programs Were Inspected ML20204E4031999-03-16016 March 1999 Submits Rept of Status of Decommissioning Funding for Rancho Seco,As Required by 10CFR50.75(f)(1).Plant Is Currently in Safstor, with Operating License Scheduled to Expire in Oct 2008 ML20204E6661999-03-11011 March 1999 Forwards Rancho Seco Exposure Rept for Individuals That Received Greater than 100 Mrem During 1998,IAW TS D6.9.2.2 & NRC Regulatory Guide 1.16 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 ML20207L1711999-03-10010 March 1999 Informs of Staff Determination That Supporting Calculations & Drawings Contained in Rev 2 of Sar, Should Be Withheld from Public Disclosure,Per 10CFR2.790 NL-99-002, Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3)1999-03-10010 March 1999 Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20207D4431999-03-0101 March 1999 Forwards Annual Radioactive Effluent Release Rept, for Rancho Seco Nuclear Generating Station for 1998 ML20207H6181999-02-18018 February 1999 Provides Attached Metrix & Two Copies of Rancho Seco ISFSI Sar,Rev 2 on Compact Disc,As Requested in 990209 Meeting. First Rounds of RAIs Dealt Primarily with Use of Cask as Storage Cask.Without Compact Disc ML20203D0761999-02-10010 February 1999 Ltr Contract:Task Order 37 Entitled, Technical Assistance in Review of New Safety Analysis Rept for Rancho Seco Spent Fuel Storage Facility, Under Contract NRC-02-95-003 ML20155D4431998-10-27027 October 1998 Forwards Amend 3 to Rancho Seco Dsar,Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode.With Instructions & List of Effective Pages NL-98-032, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1998-09-30030 September 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20237A6031998-08-0707 August 1998 Forwards Insp Rept 50-312/98-03 on 980706-09.No Violations Noted ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements ML20236Q9461998-07-15015 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-02 ML20236J6331998-06-30030 June 1998 Forwards Response to Violations Noted in Insp Rept 50-312/98-02.Corrective Actions:Util Revised RSAP-1003 to Clarify District Security Staff Responsibilities Re Handling & Review of Criminal History Info ML20236E8211998-06-0303 June 1998 Forwards Insp Rept 50-312/98-02 on 980519-21 & NOV Re Failure to Review & Consider All Info Obtained During Background Investigation.Areas Examined During Insp Also Included Portions of Physical Security Program ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 IR 05000312/19980011998-03-25025 March 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-01 on 980205 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) ML20202C4641998-02-0505 February 1998 Forwards Insp Rept 50-312/98-01 on 980105-08 & Notice of Violation.Insp Included Decommissioning & Dismantlement Work Underway,Verification of Compliance W/Selected TS & Main & Surveillance Activities Associated W/Sfp ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks ML20198K5391997-10-21021 October 1997 Forwards Insp Rept 50-312/97-04 on 970922-25 & Notice of Violation.Response Required & Will Be Used to Determine If Further Action Will Be Necessary ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility ML20198G8141997-08-22022 August 1997 Forwards Amend 125 to License DPR-54 & Safety Evaluation. Amend Permits Smud to Change TS to Incorporate Revised 10CFR20.Amend Also Revises References from NRC Region V to NRC Region IV ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 ML20149E5031997-07-10010 July 1997 Second Partial Response to FOIA Request for Documents. Forwards Records Listed in App C Being Made Available in Pdr.Records in App D Already Available in PDR ML20148P5161997-06-30030 June 1997 Second Partial Response to FOIA Request for Documents.App B Records Being Made Available in PDR ML20141A1721997-06-17017 June 1997 Forwards Insp Rept 50-312/97-03 on 970603-05.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program 1999-08-31
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195B8511999-05-27027 May 1999 Forwards Change 4 to Rancho Seco Emergency Plan, Incorporating Commitments Made to NRC as Outlined in NRC .Emergency Plan Includes Two Listed Supporting Documents ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments ML20206M1611999-05-10010 May 1999 Forwards Listed Proprietary Calculations to Support Review of Rancho Seco ISFSI Sar.Proprietary Encls Withheld ML20206E8591999-04-12012 April 1999 Provides Info Re High Total Coliform Result in Plant Domestic Sewage Effluent Prior to Confluence with Combined Effluent.Cause of High Total Coliform Result Was Broken Flow Rate Instrument.Instrument Was Repaired on 990318 ML20204E4031999-03-16016 March 1999 Submits Rept of Status of Decommissioning Funding for Rancho Seco,As Required by 10CFR50.75(f)(1).Plant Is Currently in Safstor, with Operating License Scheduled to Expire in Oct 2008 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 ML20204E6661999-03-11011 March 1999 Forwards Rancho Seco Exposure Rept for Individuals That Received Greater than 100 Mrem During 1998,IAW TS D6.9.2.2 & NRC Regulatory Guide 1.16 NL-99-002, Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3)1999-03-10010 March 1999 Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20207D4431999-03-0101 March 1999 Forwards Annual Radioactive Effluent Release Rept, for Rancho Seco Nuclear Generating Station for 1998 ML20207H6181999-02-18018 February 1999 Provides Attached Metrix & Two Copies of Rancho Seco ISFSI Sar,Rev 2 on Compact Disc,As Requested in 990209 Meeting. First Rounds of RAIs Dealt Primarily with Use of Cask as Storage Cask.Without Compact Disc ML20155D4431998-10-27027 October 1998 Forwards Amend 3 to Rancho Seco Dsar,Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode.With Instructions & List of Effective Pages NL-98-032, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1998-09-30030 September 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements ML20236J6331998-06-30030 June 1998 Forwards Response to Violations Noted in Insp Rept 50-312/98-02.Corrective Actions:Util Revised RSAP-1003 to Clarify District Security Staff Responsibilities Re Handling & Review of Criminal History Info ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 NL-97-030, Forwards Endorsement 132 to Nelia Policy NF-0212 & Endorsement 118 to Maelu Policy MF-0075 for Smuds Rsngs1997-05-13013 May 1997 Forwards Endorsement 132 to Nelia Policy NF-0212 & Endorsement 118 to Maelu Policy MF-0075 for Smuds Rsngs ML20138F5321997-04-28028 April 1997 Forwards Response to RAI Re License Amend 192,updating Cask Drop Design Basis Analysis,Per NRC 960510 Request for Addl Info on 960318 Application NL-97-027, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility1997-04-17017 April 1997 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility ML20137W8091997-03-20020 March 1997 Forwards Biennial Update to Rancho Seco Post-Shutdown Decommissioning Activities Rept ML20137S3571997-03-19019 March 1997 Provides Notification of Use of Revised Quality Manual for Activities Re Rancho Seco ISFSI ML20137D0981997-03-18018 March 1997 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1996.Provided IAW TS D6.9.2.2 & Guidance Contained in NRC Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1996 ML20137D1221997-03-18018 March 1997 Submits,Iaw 10CFR20.2206 & TS D6.9.2.1,1996 NRC Form 5 Individual Monitoring Repts for Personnel Requiring Radiation Exposure Monitoring Per 10CFR20.1502 During 1996. W/O Encl NL-97-012, Submits Rept of Listed Current Levels of Property Insurance for Plant,Iaw 10CFR50.54(w)(3)1997-02-11011 February 1997 Submits Rept of Listed Current Levels of Property Insurance for Plant,Iaw 10CFR50.54(w)(3) ML20138L1091997-01-29029 January 1997 Informs of Schedule Change Re Decommissioning of Rancho Seco.Incremental Decommissioning Action Plan,Encl NL-97-005, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility1997-01-22022 January 1997 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility NL-96-056, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1996-12-16016 December 1996 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20134E0041996-10-23023 October 1996 Forwards Response to NRC GL 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks ML18102B6871996-08-0606 August 1996 Informs That Util Will Revise Loading & Unloading Procedures & Operator Training as Necessary ML20149E4491994-05-16016 May 1994 Forwards 1993 Annual Rept of Sacramento Municipal Utility District,For Info ML20149E3971994-05-10010 May 1994 Forwards Re Updated Decommissioning Cost Estimate for Rancho Seco & Attached Rept by Tlg Engineering,Inc. W/Svc List ML20059H6731994-01-20020 January 1994 Forwards Revised Rancho Seco Quality Manual, Reflecting Current Rancho Seco Pol Phase Nuclear Organization Changes ML20059E1221994-01-0303 January 1994 Forwards Amend 7 to Long Term Defueled Condition Physical Security Plan.Encl Withheld (Ref 10CFR73) ML20059C1681993-12-22022 December 1993 Forwards Suppl Info to Support Review & Approval of 930514 Proposed License Amend 186 Re Nuclear Organization Changes, Per NRC Request 1999-07-07
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L5431990-09-20020 September 1990 Requests Exemptions from Certain Requirements of 10CFR50.47(b) & 50,App E & Proposes New Emergency Plan That Specifically Applies to Long Term Defueled Condition ML20059J9161990-09-13013 September 1990 Notification of Change in Operator/Senior Operator Status for R Groehler,Effective 900907 ML20059J9221990-09-13013 September 1990 Responds to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2,Part 2, 'Vendor Interface for Safety-Related Components.' No Vendor Interface Exists for Spent Fuel Pool Liner NL-90-442, Forwards Endorsements 13 to Nelia Certificate N-49 & Maelu Certificate M-49,Endorsements 91 & 92 to Maelu Policy MF-75 & Endorsements 103 & 104 to Nelia Policy NF-2121990-09-12012 September 1990 Forwards Endorsements 13 to Nelia Certificate N-49 & Maelu Certificate M-49,Endorsements 91 & 92 to Maelu Policy MF-75 & Endorsements 103 & 104 to Nelia Policy NF-212 ML20059G0791990-09-0606 September 1990 Forwards Supplemental Fitness for Duty Performance Data, Omitted from 900725 Rept Re Random Drug Testing Results ML20059E0031990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept,Jan- June 1990, Corrected Repts & Revs to ODCM ML20059C2491990-08-27027 August 1990 Advises That M Foster & B Rausch Leaving Util Effective on 900810 & 17,respectively & Will No Longer Require Active Operator Licenses ML20056B2591990-08-20020 August 1990 Forwards Long-Term Defueled Condition Security Training & Qualification Plan. Encl Withheld (Ref 10CFR2.790) ML20056B2961990-08-10010 August 1990 Discusses 900731 Meeting Re Future of Util & Closure & Decommissioning of Facility.Request for Possession Only License Pending Before Commission ML20058Q2811990-08-0909 August 1990 Forwards Updated Listing of Commitments & long-range Scope List Items Deferred or Closed by Commitment Mgt Review Group Since Last Update ML20058N0911990-08-0707 August 1990 Notifies of Minor Change in List of Tech Specs Applicable in Plant Defueled Condition.Determined That Surveillance Requirements Table 4.1-1,Item 63 Not Required to Be Included in List of Tech Specs Applicable in Defueled Condition ML20056A1131990-07-30030 July 1990 Apprises of Status of Plans to Use 3 of 4 Emergency Diesel Generators as Peaking Power Supplies & Responds to Questions in .Util Obtained Authorization for Operation of Diesel Generators for No More than 90 Days Per Yr ML20056A2041990-07-30030 July 1990 Provides Response to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. Pressure & Differential Pressure Transmitters 1153 & 1154 Do Not Perform Any safety-related Function in Current Plant Mode ML20055J0311990-07-25025 July 1990 Forwards fitness-for-duty Performance Data for Facility from 900103-0630 ML20055J0331990-07-25025 July 1990 Notifies of Change in Operator/Senior Operator Status. Operators Terminating Employment & No Longer Require License ML20055H8081990-07-24024 July 1990 Forwards Decommissioning Financial Plan for Plant,Per 10CFR50.33(k)(2) & Requests Interim Exemption Re Requirement to Have Full Decommissioning Funding at Time of Termination of Operation,Per 10CFR50.12 ML20055H7561990-07-24024 July 1990 Requests Exemption from Performing Annual Exercise of Emergency Plan,Activation of Alert & Notification Sys & Distribution of Public Info Brochures,Per 10CFR50.12 Requirements ML20055F8421990-07-13013 July 1990 Forwards Application for Proposed Decommissioning of Plant. Util Needs Relief from Equipment Maint,Surveillance,Staffing & Other Requirements Not Necessary to Protect Public Health & Safety During Defueled Condition ML20055G9821990-07-12012 July 1990 Advises That Environ Exposure Controls Action Plan Will Be Provided by Sept 1990,per Insp Rept 50-312/90-02 ML20055E5111990-07-0606 July 1990 Notifies of Change in Operator/Senior Operator Status for D Rosenbaum & M Cooper,Effective 900622 & 29,respectively ML20055C3541990-02-14014 February 1990 Forwards Updated Response to Insp Rept 50-312/88-30. Calculations for Liquid Effluent Monitors Completed & in Use & Rev to Reg Guide 4.15 in Procedure RSAP-1702 Scheduled to Be Completed & Implemented by Apr 1990 ML20055C3511990-02-14014 February 1990 Forwards Addl Info Re 900306 Response to NRC Bulletin 88-003, Inadequate Latch Engagement in Hfa Type Latching Relays Mfg by Ge. Util Will Replace Only Relays Found Not to Meet Insp Criteria ML20248H2571989-10-0606 October 1989 Responds to NRC Re Addendum to Safety Evaluation Supporting Amend 92 to License DPR-54 Re Reactor Vessel Vent Valve Testing.No Testing of Reactor Vessel Vent Valves Will Be Performed ML20248H2391989-10-0606 October 1989 Requests Exemption from Requirements of 10CFR26 Re Fitness for Duty Programs Based on Present & Future Operational Configuration ML20248A8271989-09-25025 September 1989 Requests Permission to Submit Next Amend to Updated FSAR W/Decommissioning Plan Submittal.Extension Will Allow District to Incorporate Plant Closure Status in SAR Update to Reflect Plant Conditions Accurately ML20248D4611989-09-13013 September 1989 Responds to 890906 Request for Assessment of Util Compliance W/Ol & Associated Programs & Commitments,Per 10CFR50.54(f). Staffing Requirements for Emergency Preparedness Will Not Be Violated & Future Shortfalls Will Be Remedied ML20247G1991989-09-11011 September 1989 Requests Extension for Time Period Equivalent to That of Current Shutdown.Extension Would Result in Revised Final Expiration Date of Not Earlier than 900318.Plant Would Not Be Brought Above Cold Shutdown W/O NRC Prior Concurrence ML20247H3551989-09-0707 September 1989 Informs That Util Stands by Commitments of 890621 & 0829 Re Implementation of Closure Plan in Safe & Deliberate Manner in Compliance W/License & W/All Applicable Laws & Regulations ML20247H5541989-09-0101 September 1989 Responds to Violations Noted in Insp Rept 50-312/89-14. Corrective Actions:Stop Order on Fuel Movement Issued & Action Plan Generated on 890908 to Address Broader Issues 05000312/LER-1988-010, Forwards Rev 1 to LER 88-010,due to Change in Commitment Date for re-evaluating Fire Zones.Date Changed to 901001. Zones re-evaluated in Conjunction W/Mods to Fire Detection Annunciator Sys1989-08-23023 August 1989 Forwards Rev 1 to LER 88-010,due to Change in Commitment Date for re-evaluating Fire Zones.Date Changed to 901001. Zones re-evaluated in Conjunction W/Mods to Fire Detection Annunciator Sys ML20246A4011989-08-16016 August 1989 Forwards Rev 5 to Inservice Testing Program Plan. Changes Identified Consistent W/Guidance Provided by Generic Ltr 89-04 NL-89-593, Forwards Plant Closure Organizational Charts & Administrative Procedure RSAP-0101,per 890802 Request1989-08-15015 August 1989 Forwards Plant Closure Organizational Charts & Administrative Procedure RSAP-0101,per 890802 Request ML20245H4781989-08-10010 August 1989 Requests Exemption from Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs Because on 890607,util Board of Directors Ordered That Plant Cease Operation ML20245H1781989-08-0909 August 1989 Notifies of Change in Operator/Senior Operator Status. J Dailey & J Reynolds Terminated Employment on 890721 & 890802,respectively ML20245L1831989-08-0808 August 1989 Informs That Official Correspondence Must Be Directed to Listed Individuals Due to Reorganization of Util Following 890606 Election ML20247L9221989-07-26026 July 1989 Provides Revised Response to NRC Re Violations Noted in Insp Rept 50-312/88-33.Corrective Action:Portable Shield Walls Inspected Every 6 Months to Ensure All Safety Factors Met & Area Surveys Conducted on Weekly Basis ML20247M4121989-07-24024 July 1989 Requests Exemption from 10CFR50,App E,Section IV.F.2 to Allow Util Not to Perform Annual Emergency Plan Exercise for 1989.Request Results from Transitional Mode of Plant from Operating Plant to Plant Preparing for Decommissioning NL-89-541, Requests That Completion Date for Addl Training of Personnel Involved in Performing Work on Environ Qualified Equipment Be Extended from 890616 to 8912151989-07-14014 July 1989 Requests That Completion Date for Addl Training of Personnel Involved in Performing Work on Environ Qualified Equipment Be Extended from 890616 to 891215 ML20246P4011989-07-14014 July 1989 Informs That Evaluation of Contracts & Agreements Identified No Restrictions on Employee Ability to Provide Info About Potential Safety Issues to NRC NL-89-547, Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 1061989-07-0606 July 1989 Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 106 ML20246A9751989-06-30030 June 1989 Advises That Concerns Addressed in Generic Ltr 89-08 Inapplicable,Since Util Intends to Defuel Reactor.Generic Ltr Will Be Reviewed Prior to Placing Facility in heatup-cooldown Operational Mode for Return to Power ML20246A5171989-06-30030 June 1989 Forwards Rancho Seco Closure Plan, Per 890621 Request for Addl Info Re Plan CEO-89-289, Notifies of Change in Operator/Senior Operator Status.Listed Operator/Senior Operator Terminated Employment on Listed Effective Date1989-06-27027 June 1989 Notifies of Change in Operator/Senior Operator Status.Listed Operator/Senior Operator Terminated Employment on Listed Effective Date NL-89-526, Lists Discrepancies Noted in Amend 109 to License DPR-54,per 890615 Discussion W/S Reynolds.Tech Specs Encl1989-06-22022 June 1989 Lists Discrepancies Noted in Amend 109 to License DPR-54,per 890615 Discussion W/S Reynolds.Tech Specs Encl ML20245H4181989-06-21021 June 1989 Discusses Util Plans Re Overall Closure of Plant,Per 890615 Meeting W/Nrc.Util Will Request Appropriate Changes to Tech Specs to Reflect Defueled Mode & Will Evaluate & Request Changes to Emergency Plan ML20245D9281989-06-21021 June 1989 Discusses Activities Underway Re Plan for Closure of Plant Discussed During 890615 Meeting W/Region V.Util Intends to Continue Use of Essential Programs,Such as Preventive Maint Program,For Sys within Scope of Closure Process ML20245A0981989-06-16016 June 1989 Responds to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. No Westinghouse Plugs Used at Plant ML20248B5751989-06-0202 June 1989 Advises That Util Anticipates That Final Analysis of Thermal Striping Will Conservatively Support Surge Line Lifetime Significantly Longer than June 1994 Date,Per NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification NL-89-468, Submits Justification for Absence of Functional Testing Requirement in Proposed Tech Spec 4.14(f) Re Snubber Svc Life Monitoring,Per 890517 Request1989-05-30030 May 1989 Submits Justification for Absence of Functional Testing Requirement in Proposed Tech Spec 4.14(f) Re Snubber Svc Life Monitoring,Per 890517 Request ML20247N2601989-05-25025 May 1989 Requests Guidance Re Whether NRC Concurs W/Arbitrator Order Concerning Employee Access to Plant 1990-09-06
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'$SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT D P. O. Box 15830, Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CAUFORNIA JEW 86-923 December 1, 1986 J B MARTIN REGIONAL ADMINISTRATOR REGION V OFFICE OF INSPECTION AND ENFORCEMENT U S NUCLEAR REGULATORY COMMISSION 1450 MARIA LANE SUITE 210 WALNUT CREEK CA 94596 DOCKET NO. 50-312 LICENSE NO. DPR-54 NRC INSPECTION REPORT 86-14 Gentlemen:
By letter dated October 28, 1986, the Sacramento Municipal Utility District was transmitted a Notice of Violation concerning the Rancho Seco Nuclear Generating Station's emergency preparedness program.
In accordance with 10 CFR 2.201, the District provides the enclosed response to the Notice of Violation.
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J WARD DEPUTY GENERAL MANAGER NUCLEAR Attachment w
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,9 v1 8701130284 861224 PDR ADOCK 05000312 G PDR RANCHO SECO NUCLEAR GENERATING STATION E 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935
-s ENCLOSURE District Response to NRC Inspection Report No. (50-312/86-14)
Notice of Violation NRC Violation A Rancho Seco Technical ' Specification 6.8.1.e requires, in part, that written procedures covering the emergency plan shall be implemented. Section 5.4.2 of Procedure AP-580, " Training,"
required training be conducted annually and whenever necessitated by significant revisions to the emergency plan implementing procedures or equipment.
contrary to the above, eight of the control room staff, i
including four shift supervisors, and twenty-four members of the licensee'Is emergency response organization, had not received their annual emergency preparedness retraining during the year 1985. The retraining interval for these individuals varied between 15.7 and 20 months. In addition, personnel identified in AP 506.01 as the primary and alternate individuals assigned to the dose assessment responsibility had not received any training on dose assessment during 1985 even though there were modifications to two of the dose assessment computer codes during the year (1985).
This is a severity Level IV Violation (Supplement VIII).
i District Response to Violation A
- 1) Admission or denial of the alleged violation.
The District admits that the violation occurred as stated.
- 2) Reasons for violation.
The violation was the result of an inadequate tracking system for emergency preparedness related training and retraining.
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- 3) Corrective actions which have been taken and results achieved.
The Emergency Preparedness Department, in coordination with the Nuclear Training Department, has recently initiated a new tracking system based on an IBM AT Computer. Emergency Preparedness has taken steps to increase the effectiveness of the interface with the training department.
- 4) Corrective actions which will be taken.
Long term plans include Training Department retention of all training records.
- 5) Date when full compliance will be achieved:
The current cycle of training will be completed mid December, 1986. Full compliance will be achieved at the completion of this cycle. The next cycle of training is scheduled to commence in May, 1987.
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t NRC Violation B.1-Rancho Seco Technical Specification 6.;B.l.e requires, in part, that written procedures covering the emergency plan shall be maintained.-
Procedures AP 509, 511 and 512, , " Dose Calculations for the Control Room," " Technical Support Center," and " Emergency Operations Facility" respectively, provided a means for hand calculating offsite doses. In addition, Procedure AP-501,
" Recognition and Classification of Emergencies," provided
, instruction on classifying emergencies based on affluent monitor (R15001 and R15002) readings. Each of these procedures relies on a knowledge and understanding of the effluent release rate.
Contrary to the above, at the time of the inspection, these 1
procedures were not maintained in that:
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- a. Procedures AP 501, 509 and 511 did not provide for using data from the expanded range affluent monitors R15044 and R15045.
- b. Procedures AP 509 and 511 did not provide a means to utilize data from the Reactor Building effluent monitor
- R15001 to calculate release rate / dose projection.
This is a Severity Level IV Violation (Supplement VIII).
District Response to Violation B.1.a i
- 1) Admission or denial of the alleged violation.
The District admits that this violation occurred as stated.
- 2) Reasons for the violation.
The procedure inadequacies in AP-501, AP-509 and AP-511 s)\ were due__tulack the maintenance andofrevision continuity _irtataffresponsible_
of these_ procedures. A fog Mbuting factor was the lack of administratTve controls to assure that emergency preparedness staff were dhawareofplantcoHYigurationchanges.
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- 3) Corrective actions which have been taken and the results achieved.
AP-509 and AP-511 were initially revised to properly include R150044 and R150045 monitor points on August 13, l
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1986. Subsequent improvements were included in the following procedure changes, dated September 18, 1986.
- AP 509, Revision 4
- AP 501, Revision 6
- AP 511, Revision 5 An Emergency Preparedness (EP) representative is now
$m required to attend the daily operations meetings which will assure that the EP organization is aware of plant configuration changes.
- 4) Corrective actions which will be taken.
Planned corrective actions have been completed as described in item 3 above.
- 5) Date when full compliance will be achieved.
Full compliance was achieved on September 18, 1986.
District Response to Violation B.l.b
- 1) Admission or denial of the alleged violation.
The District admits that this violation occurred as stated.
- 2) Reasons for the violation.
i Same as violation B.1.a.
- 3) Corrective actions which have been taken and the results
, achieved.
( Procedures AP-509, AP-511 and AP-512 are being revised to l provide appropriate means to calculate release rate / dose
- projections.
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- 4) Corrective actions which will be taken.
Re' visions to AP-509, AP-511 and AP-512 will be implemented prior to restart. Dose assessment codes currently used by
[ the District will be revised, updated and reflected in AP-l 509, AP-511 and AP-512 prior to restart.
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- 5) Date when full compliance will be achieved.
f Prior to restart, May 1, 1987.
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1 NRC Violation B.2 Rancho Seco Technical Specification 6.8.1.s requires, in part, that written procedures covering the emergency plan shall be maintained.
AP-511, " Technical Support Center Dose Calculations," described the licensee's methods for determining offsite dose assessment.
AP-511 states, "These calculations may be performed using Apple II Code 'RACODE'."
Contrary to the above, at the time of the inspection, the 4
procedure was not maintained in that the procedure provided no instructions for computer based dose calculations. In addition, there was insufficient documentation, i.e., users guides on the dose assessment codes to assist those persons who perform the calculations. ;
This is a Security Level IV Violation (Supplement VII).
District Response to Violation B.2
- 1) Admission or denial of the alleged violation.
The District admits that the violation occurred as stated.
- 2) Reasons for the violation.
- Same as violation B.1.a.
- 3) Corrective actions which have been taken and results achieved.
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Same as violation B.l.b. An interim procedure for utilizing the Apple II Code "RACODE" has been posted at the computer until all procedure revisions have been completed.
i 4) Corrective actions which will be taken.
! Same as violation B.l.b. In addition, user guide
- information will be provided to assist those persons who perform dose assessment calculations.
- 5) Date when full compliance will be achieved.
- Prior to restart, May 1, 1987.
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NRC Violation B.3 Rancho Seco Technical Specification 6.8.1.e requires, in part, that written procedures covering the emergency plan shall be maintained.
Procedure AP-509, " Control Room Dose Calculations," described a '
hand calculation method for " predicting offsite dose rates and i
integrated doses" for releases from the Auxiliary Building vent. In addition, the Unified Dose Assessment center, located in the Emergency Operations Facility, used the computer code titled JADE to make the offsite dose calculations.
Contrary to the above, at the time of the inspection, Procedure AP-509 was not maintained in that a method was not provided to calculate dose rates and integrated doses for unmonitored
! release paths, e.g., primary to secondary leakage (steam generator) with subsequent release to the atmosphere or leakage from the containment building. Also, at the time of the inspection, the Unified Dose Assessment Center dose calculation capability was not maintained in that the JADE code was not
' capable of calculating release rates and dose projections for a primary to secondary leak with subsequent release to the atmosphere. The SPECTER code, which can be used in the
! Technical Support Center, did provide for making this type of i dose projection.
. This is a Severity Level IV Violation (Supplement VIII).
- District Response to Violation B.3
- 1) Admission or denial of the alleged violation.
l The District admits that this violation occurred as i
stated. ;
- 2) Reasons for violation.
i Same as violation B.l.a. In addition, there was no
- means of identifying that Turbine Bypass Valves (TBV) or Atmospheric Dump Valves (ADV) were opened and the duration of that opening to determine a source term.
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- 3) Corrective steps which have been taken and results achieved.
AP-509, Rev. 3 da*ed August 13, 1986, addressed t:ais capability by requiring the assumption that all TBVs and ADVs are open unless otherwise indicated.
- 4) Corrective actions which will be taken:
AP-509 will be revised again when secondary release points have had monitoring equipment installed.
- 5) Date when full compliance will be achieved:
The District considers the August 13, 1986, revision of AP-509 to be in compliance.
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NRC Violation B.4 Rancho Seco Technical Specification 6.8.1.e requires, in part, that written procedures covering the emergency plan shall be 4
maintained.
Procedure AP-528, " Protective Action Guidance," required that protactive actions to be recommended to appropriate local and State authorities shall be based on plant conditions or trends as well as projected doses.
Contrary to the above, at the time of the inspection, Procedure AP-528 was not maintained in that guidance for relating plant conditions and trends to the various protective action recommendations had not been provided.
This is a Severity Level IV Violation (supplement VIII).
District Response to Violation B.4
- 1) Admission or denial of alleged violation, i
The District admits that this violation occurred as stated.
- 2) Reasons for violation.
\\ The lack of continuity of staff within the emergency
/ preparedness organization responsible for proceduro revisions and the inadequate turnover of work in progress Z to new emergency preparedness staff members directly contributed to this violation.
[ 3) Corrective steps which have been taken and results achieved:
AP-528, Revision 2 was implemented on September 18, 1986 to provide guidance for relating plant conditions and trends to protective action recommendations as adressed in
- IE Information Notice 83-28.
- 4) Corrective actions which will be taken:
! A turnover briefing of work in progress will be performed l when a new staff member is assigned procedure maintenance j responsibilities.
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- 5) Date when full compliance will be achieved:
Training of operations staff on AP-528 is scheduled to be completed on December 15, 1986. This will achieve full compliance with this item.
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NRC Violation B.5 Rancho Seco Technical Specification 6.8.1.e requires, in part, that written procedures covering the emergency plan shall be maintained.
Several procedures, i.e., AP-516, AP-552 and AP-305-9D, made reference to emergency kits, that include decontamination equipment and supplies, being located at the Herald Fire Department and the Ione Fire Academy.
Contrary to the above, at the time of the inspection, these procedures were not maintained in that the emergency kits had been removed in July 1985 and appropriate changes to the procedures had not been made. In addition, replacement guidance regarding what equipment and supplies, formerly in these two emergency kits, required to be taken from the reactor site when the offsite assembly area (s) are activated had not been provided.
This is a Severity Level V Violation (Supplement VIII).
District Response to Violation B.5
- 1) Admission or denial of alleged violation.
The District admits the violation occurred as stated.
- 2) Reasons for the violation:
j Same as Violation B.4.
l 3) Corrective steps which have been taken and results achieved:
l AP-305-9D dated September 25, 1986, has removed the j reference to the decontamination equipment and supplies.
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- 4) Corrective actions which will be taken:
AP-516 and AP-552 will be revised to be consistent with AP-305-9D and the current use and location of emergency kits and decontamination equipment and supplies.
- 5) Date when full compliance will be achieved:
Full compliance will be achieved by issuance of revised procedures prior to restart May 1, 1987.
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NRC Violation C.1 ,
10 CFR 50.54(q) requires a licensee to follow and maintain in effect emergency plans which meet the standards in 50.47(b) and the requirements in Appendix E of Part 50.
Section IV.E of Appendix E requires that the emergency facilities and equipment be described in the emergency plan.
Contrary to the above, at the time of the inspection, the emergency plan did not describe the current emergency facilities in use as follows:
a) Section 7.1.5 of the emergency plan described the first aid room as being adjacent to the Auxiliary Building and next to the Safety Office. In addition, Figure 7.8 showed this location as being in the building housing the tool room. The first aid room, which was moved in the Fall of 1984, was located next to the cafeteria in the TER building.
b) Figures 7.2 and 7.3 showed the Technical Support Center (TSC) in a room located adjacent to the control room. The present TSC was located in a reconstructed room down the hallway from the former location. This change was made prior to September 10, 1985.
i c) Section 7.2.2 had not been changed to show that emergency lockers, removed in July 1985, were no longer located at the i
California State Forestry Fire Fighting Academy (Ione) and the Herald Fire Department.
I j This is a Severity Level V Violation (Supplement VIII).
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District Response to Violation C.l.a,b,c
- 1) Admission or denial of the alleged violation.
The District admits that this violation occurred as stated.
- 2) Reasons for the violation.
Same as violation B.4.
- 3) Corrective actions which have been taken and the results achieved:
The District has initiated a review of the Emergency Plan and implementing procedures.
- 4) Corrective actions which will be taken.
Emergency plan revisions necessary to resolve the specific discrepancies noted in the violation and those identified during the District's review will be submitted to the plant review committee prior to March 15, 1987.
- 5) Date when full compliance will be achieved:
Full compliance will be achieved with Management Safety Review Committee approval prior to restart, May 1, 1987.
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. s NRC Violation C.2 10 CFR 50.54(q) requires a licensee to follow and maintain in effect emergency plans which meet the standards in 50.4'7(b) and the requirements in Appendix E of Part 50.
Section IV.B of Appendix E requires that emergency action levels used to classify emergency events be reviewed with the State and local governmental authorities on an annual bcsis.
Contrary to the above, in 1985 the State of California and the counties of Amador, Sacramento and San Joaquin were not provided with an opportunity to review the emergency action levels.
This is a Severity Level V Violation (Supplement VIII).
District Response to Violation C.2
- 1) Admission or denial of alleged violation:
The District admits that this violation occurred as stated.
- 2) Reasons for violation:
Minutes for the meeting with the counties and state which should have reflected this review were not retrievable because of inadequate records system. Additional contributory factors were that the District staff relied upon meeting minutes and informal agenda items to cover this commitment.
- 3) Corrective actions which have been taken and results achiev.'d:
The courc les and state were provided with an opportunity for Emergency Action Level (EAL) review by formal letter issued by Licensing, letter number NL 86-195. Discussions with the State, Amador County, and Sacramento County were held on November 5, 1986 and San Joaquin County on November 17, 1986 to further review EAL's.
- 4) Corrective actions which will be taken:
Annual reviews will be documented by formal correspondence.
- 5) Date when full compliar ce will be achieved:
Full compliance will be achieved on December 1, 1986.
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. 8 NRC Violation C.3 Section IV.F of appendix E requires initial training and retraining of emergency personnel. Section 6.2.7 of the emergency plan required that health physics personnel and the emergency team will be provided Advanced First Aid and Multi-Media every three years.
_ Contrary to the above, at the time of the inspection, retraining in the Standard Multi-Media had been discontinued more than three years ago and retraining in Advanced First Aid was discontinued more than five years ago.
This is a Severity Level V Violation (Supplement VIII).
Dietrict Response-to Violation C.3
- 1) Admission or denial of alleged violation.
The District admits that this violation occurred as stated.
- 2) Reasons for violation:
The violation was due to the Emergency Plan not being revised to reflect that First Aid Training for emergency team members could be provided at an instructional level equivalent to Advanced First Aid. An additional contributor was the utilization of emergency medical technicians as First Aid instructors who were not able to issue Red Cross Certification Cards.
- 3) Corrective actions taken and results achieved.
Review of 1985 and 1986 First Aid training documentation indicated that Emergency First Aid training was provided to licensed operators as a requalification training program topic. This review also indicated that the i
training was provided to a level equivalent to Advanced First Aid including Multi-Media. Two instructors, who are qualified to issue Red Cross Certification, have been l hired to provide Advanced First Aid training.
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- 4) Corrective Actions which will be taken; Section 6.2.7.d of the Emergency Plan will be revised to reflect the acceptance of both Advanced First Aid or the equivalent. Emergency Team members will be enrolled in appropriate training and retraining programs. At least one member of the Emergency Team will have Advanced First Aid Training or the equivalent. Nine Radiation Protection personnel will be trained on Standard Multimedia by December 31, 1986.
- 5) Date when full compliance will be achieved.
. The District considers that full compliance will be achieved with the revision of the Emergency Plan prior to restart May 1, 1987.
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