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MONTHYEARML20055H7561990-07-24024 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 Project stage: Other 1990-07-24
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M8851999-10-0808 October 1999 Informs of Staff Determination That Listed Calculations Should Be Withheld from Public Disclosure,Per 10CFR2.790, as Requested in 990909 Affidavit ML20211J7731999-08-31031 August 1999 Forwards Insp Rept 50-312/99-03 on 990802-06.No Violations Noted.Insp Included Decommissioning & Dismantlement Activities,Verification of Compliance with Selected TS & Review of Completed SEs ML20211H7481999-08-13013 August 1999 Forwards Amend 126 to License DPR-54 & Safety Evaluation. Amend Changes Permanently Defueled Technical Specification (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP Level Alarm Switches with Generic Ref 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments 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 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 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 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) 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 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 IR 05000312/19980021998-07-15015 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 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation 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 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 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 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 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 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 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 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 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) 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 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 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 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 ML20029E4601994-05-12012 May 1994 Forwards Response to NRC Bulletin 94-001, Potential Fuel Pool Drain-Down Caused by Inadequate Maint Practices at Dresden Unit 1. Util Plans to Move Spent Fuel Into Proposed Rancho Seco ISFSI by 1998 ML20149E3971994-05-10010 May 1994 Forwards Re Updated Decommissioning Cost Estimate for Rancho Seco & Attached Rept by Tlg Engineering,Inc. W/Svc List NL-94-008, Forwards Endorsement 118 to Nelia Policy NF-0212 & Endorsement 106 to Maelu Policy MF-00751994-04-28028 April 1994 Forwards Endorsement 118 to Nelia Policy NF-0212 & Endorsement 106 to Maelu Policy MF-0075 ML20029D3531994-04-28028 April 1994 Forwards Documents S11-25-003, Update of 1991 Decommissioning for Rancho Seco Nuclear Generating Station 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 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 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 ML20055J0331990-07-25025 July 1990 Notifies of Change in Operator/Senior Operator Status. Operators Terminating Employment & No Longer Require License ML20055J0311990-07-25025 July 1990 Forwards fitness-for-duty Performance Data for Facility from 900103-0630 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 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 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 ML20043G9521990-06-12012 June 1990 Notifies of Organizational Changes.Svc List Should Be Revised as Listed ML20043G5701990-06-12012 June 1990 Forwards NSHC for long-term Defueled Condition of Plant for Security Plan,Per Util .As Discussed W/Nrc During Telcon,Determination Made That NSHC Needed to Be Processed in Support of Security Plan ML20043E8191990-06-0606 June 1990 Requests Withdrawal of 900510 Request for Exemption from GDC 17, Electric Power Sys. Util Understands That Formal Exemption Not Required,Based on Discussions W/Nrc.Info on Plans Re Diesel Generator Operation Also Provided ML20043E1691990-05-25025 May 1990 Forwards Refinement List of Tech Specs Applicable in Defueled Condition,Per .Unless NRC Differs W/ Approach,Conduct of Activities in Defueled Condition Will Proceed Until Amend 182,Rev 1 Approved 05000312/LER-1990-001, Forwards Errata to LER 90-001-00,re Inoperable Radioactive Gaseous Effluent Monitoring Instrumentation Not Reported in Semiannual Radioactive Effluent Release Rept Due to Procedural Deficiencies,To Include Rept Date1990-05-0202 May 1990 Forwards Errata to LER 90-001-00,re Inoperable Radioactive Gaseous Effluent Monitoring Instrumentation Not Reported in Semiannual Radioactive Effluent Release Rept Due to Procedural Deficiencies,To Include Rept Date ML20042F3421990-04-26026 April 1990 Forwards Long Term Defueled Condition Security Plan.Plan Withheld (Ref 10CFR2.790) ML20042F6121990-04-26026 April 1990 Forwards Rancho Seco Emergency Plan Change 4 Long-Term Defueled Condition. New Plan Includes Provisions Necessary for Protection of Onsite Personnel & for Protection of Public Via Communication W/Offsite Agencies ML20034C4081990-04-24024 April 1990 Forwards Rev 5 to Sections 1 & 8 of Plant Emergency Plan,Per NRC Requesting Two Changes ML20042E0941990-04-10010 April 1990 Advises That Util Intends to Submit EIS Associated W/Plant Decommissioning After Submittal of Decommissioning Plan ML20033G5981990-03-30030 March 1990 Forwards Mods to Plant Operator Training Program Submitted on 891228,in Response to Requesting Addl Info ML20012E2211990-03-23023 March 1990 Forwards Amend 18 to Physical Security Plan.Encl Withheld (Ref 10CFR73.21) ML20012B8731990-03-0909 March 1990 Provides Status of Inservice Insp & Inservice Testing Programs.Util Does Not Intend to Continue Normal Test Schedule for Pumps & Valves in Sys Not Required by Tech Specs to Be Operable NL-90-030, Forwards Endorsements 94,95 & 96 to Nelia Policy NF-212, Endorsements 82,83 & 84 to Maelu Policy MF-75,Endorsements 10 & 11 to Nelia Certificate N-49 & Maelu Certificate M-49, Respectively & Endorsements 5,6,14 & 15 to Master Policy 11990-02-21021 February 1990 Forwards Endorsements 94,95 & 96 to Nelia Policy NF-212, Endorsements 82,83 & 84 to Maelu Policy MF-75,Endorsements 10 & 11 to Nelia Certificate N-49 & Maelu Certificate M-49, Respectively & Endorsements 5,6,14 & 15 to Master Policy 1 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 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 ML20033F1661990-02-14014 February 1990 Forwards Revised Pages to Sections 1-8 of Rev 4 to Emergency Plan,Per NRC 900206 Telcon Request.Summary of Changes Listed,Including Deletion of Ref to Accidents Not Exceeding Alert Classification ML20006F1451990-02-13013 February 1990 Revises 891212 Exemption Request Re Requirements for Simulation Facility Training & Testing.Requested Exemptions Commensurate W/Nuclear Safety Requirements W/Plant in Defueled Condition ML20033E3471990-02-12012 February 1990 Advises of Change in Operator/Senior Operator Status for H Coomes,Effective 900205 ML20006D6771990-02-0808 February 1990 Requests Limited Scope Exemption from Requirements of 10CFR26 Fitness for Duty Programs.Util Currently Implementing Program in Accordance W/Enforcement Discretion Granted in Commission NL-90-023, Forwards Endorsements 95 & 83 to Nelia Policy NF-212 & Maelu Policy MF-75,respectively,Endorsements 10 & 11 to Certificates N-49 & M-49 & Endorsements 5,6,14 & 15 to Maelu Policy 11990-02-0707 February 1990 Forwards Endorsements 95 & 83 to Nelia Policy NF-212 & Maelu Policy MF-75,respectively,Endorsements 10 & 11 to Certificates N-49 & M-49 & Endorsements 5,6,14 & 15 to Maelu Policy 1 ML20006D0201990-02-0202 February 1990 Requests Exemption from Simulator Training & Testing Requirements of 10CFR55.11 While Plant in Defueled Mode.In Present Defueled Condition,Use of Simulator to Ensure Skills & Abilities Re Plant Operations Irrelevant ML20011E1711990-01-30030 January 1990 Forwards Rev 0 to NDP-039, Sys Required to Support Defueled Mode, & Rev 1 to TSAP-4124, Sys Layup Program. Sys Categories at Facility Include,Operable,Available,Prudent to Operate & Layup ML19354E4441990-01-22022 January 1990 Advises That Actions Requested by NRC Bulletin 89-003 Not Applicable to Station Since Station Currently in Defueled Shutdown Condition.Util Took Action to Disallow Temporary Storage of Fuel Assemblies W/O Approval of Reactor Engineer ML20005G2571990-01-12012 January 1990 Responds to NRC Re Violations Noted in Insp Rept 50-312/89-18.Violation a Denied & Violation B Ack.Corrective Actions:Controls for Environ Pollution Reanalyzed I-131 in Water Sample Using Correct Efficiency Factor for Instrument ML20005F1791990-01-0808 January 1990 Responds to NRC Re Violations Noted in Insp Rept 50-312/89-15.Util Denies Alleged Violations on Basis That Removing Auxiliary Fuel Handling Bldg to Facilitate Testing Performed Considered Consistent W/Plant Work Practices ML20005F0351990-01-0303 January 1990 Certifies Implementation of fitness-for-duty Rule,Per 10CFR26 ML20005E4121989-12-27027 December 1989 Suppls NRC Summary of Util Plans to Close & Decommission Facility & Identifies Subjs Needing Further Discussion.Four Phases Listed,Including First Phase Re Relief from Existing Commitments ML20005D8751989-12-0707 December 1989 Forwards Util Cooling Tower Basin Sludge Sample.Activity Confined to Natural Isotopes & Cs-137 at Level of 2.058E-7 Uci/Gm,Based on Gamma Spectroscopy & Tritium Analysis ML20005F2561989-10-23023 October 1989 Forwards 1989 Annual Plant Exercise Scenario,Per IE Info Notice 85-055.Counties & State Will Not Be Officially Participating Since Biennial Participation Evaluted Last Yr 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 1990-09-06
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$8 MUD SA.;RAMENTo MUNICIPAL UTILITY DIS 1RICT D 0201 S Street. P.o. Box 15830. Sacramento CA 95852-1830.(916) 452 3211 AN ELECThlC SYSTEM SERVING THE HEART OF CALIFORNIA AGM/NUC 90-209 July 24, 1990 U. S Nuclear Pegulatory Commission Attn: Document %ntrol Desk Hashington, DC 21555 Docket No. 50-312 Rancho Seco Nuclear Ger.erating Station License No. OPR-54 EXEHPTION FROM PERFORMING AN ANNUAL EXERCISE OF THE EMERGENCY PLAN, ACTIVATION OF ALERT AND N0*f*1 CATION SYSTEM, AND DISTRIBUTION OF PUBLIC INFORMATION BROCHURES
References:
1.
D. Keuter (SMUD) to J. Larkins (NRC) letter AGM/NUC 90-130, dated April 30, 1990, Proposed Amendment No. 182, Revisicn 1 2.
D. Keuter (SMUD) to J. Larkins (NRC) letter AGM/NUC 90-120, dated April 26, 1990, Long Term Defueled Condition Emergency Plan 3.
NRC to D. Keuter (SMUD) letter dated May 16, 1990, Exemption Related To 10 CFR 55 - P.equirements For Simulation Facility And simulator Training (TAC No. 75520) 4.
NRC to D. Keuter (SMUD) letter dated January 2, 1990, NRC Inspection Attention:
John Larkins The purpose of this letter is to request an exemption pursuant to 10 CFR 50.12 from the following emergency preparedness requirements:
10 CFR 50.47(b)(14) and 10 CFR 50, and Appendix E, IV. Section F,
=
" Training," paragraphs 1 through 3(f) and NUREG-0654 " Criteria for Preparation and Evaluation of Radiological Ec'ergency Response Plans and Preparedness in Support of Nuclear Power Plants," Sections II.N.l.a. and II.N.l.b. requiring an annual exercise and mobil 12ation of emergency preparedness plans and organizations.
10 CFR 50.47(b)(5) as implemented by FEMA REP-10 " Guide for the Evaluation of Alert and Notification Systems for Nuclear Power Plants" requiring annual activation of the alert and notification lj l system.
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roc RANCHO SECO NUCLEAR GENERATING STATION O 1444o Twin C oes Road. Herald. C A 95638-9799;(209) 333 2935 "y
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AGM/NUC 90-209.
5 10 CFR 50.47(b)(7) and 10 CFR 50 Appendix E, IV. Section D,.
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" Notification Procedures," paragraph.2 and NUREG-0654, Sections II.G.1 and II.G.2 requiring distribution.of public information (brochures).
In lieu of the annual exercise, the District will perform communications c
drills.
The scope of the drills will include the annual communication drill necessary to ensure that State and local authorities are notified in a timely 1
manner and provided updated information, as appropriate. Given the limited postulated accidents as described in Reference 3, the District believes that a
.these drills are sufficient to meet the emergency preparedness-requirements
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for a facility permanently shutdown and in the defueled condition.
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The District requests an exemption from the requirements for full F
participation of State and local agencies during the annual exercise.
Full participation-would' require the mobilization of large numbers of individuals L
from offsite agencies using the alert and notification system, as well as the distribution of public information brochures.
' Attachment 1 provides the bases for.the District's request for an exemption r
from the emergency preparedness requirements listed above.
5 Members of your staff requiring additional information may contact Jerry Delezenskt at (209) 333-2935, extension 4914.
r Attachment
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' State of California SS County of: Sacramento
? Dan R. Keuter, being first duly sworn, deposes and says:
that he is Assistant.
General Manager, Nuclear of Sacramento Municipal Utility District (SHUD), the li:censee herein; that he has executed the foregoing document; that the statemeTits'rade in this document are true and correct to the best of his
. knowledge,-informat!on, and belief, and that he'is authorized to execute this document on behalf of said licensee.
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j Dan R. Keuter
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Asshtant General Manager Nuclear Subicribed and affirmed to before me on this b day,of b k/4
, 1990.
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D M RB W NER Debbie Brenner l2 b Y O Notary Public e
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ATTACHMENT 1 i*
EXEMPTION REQUEST-10.CFR 50.47(b)(14)'.and 10 CFR 50, and Appendix E. IV. Section F,
" Training," paragraphs 1 through 3(f) and NUREG-0654 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and PreparednessLin' Support of Nuclear Power Plants," Sections II.N.1.a and-II.N.1.b.
10 CFR 50.47(b)(5) as implemented by FEMA REP-10." Guide for the-
. Evaluation of Alert and Notification Systems for Nuclear Power-Plants" t
10 CFR 50.47(b)(7) and 10 CFR 50 Appendix E IV..Section D, " Notification Procedures," paragraph 2 and )l0 REG-0654, Sections II.G.1 and II.G.2 liG& tory Reauirerrents 10 CFR 50.47(b)(14) and 10 CFR 50, Appendix E, Section F " Training,"
paragraphs 1 through 3(f) and NUREG-0654, Sections II.N.1.a. and II.N.l.b.
provide the requirements for exercise participation by the Emergency Response Organizations-(ERO) of the licensee and appropriate State and local agencies to the extent as is reasonably achievable.
These regulations:also provide the requirements for the level of participation in each offsite exercise.
'10 CFR 50.47(b)(5) as implemented by Planning Standard E in NUREG-0654/ FEMA-REP-10' establish the requirements for notification by the licensee of State and local ER0s and the notification of emergency personnel
.by:a11' response organizations as a means to provide early notification and' clear instruction to the populace within the plume exposure pathway.
10 CFR 50.47(b)(7) and 10 CFR 50 Appendix E Section D " Notification Procedures," paragraph 2 and NUREG-0654, Sections II.G.1 and TI.G.2 establish
.the requirements for periodic' dissemination to the public within the plume exposure pathway Emergency Planning Zone (EPZ) of. basic emergency planning informatica that would be helpful in the event of a radiological accident at o
Rancho Seco.
y The NRC promulgated the regulations contained in Part 50 on the potential radiological hazards to the public associated with the operation of facilities licensed under 10 CFR'Part 50. Appendix E establishes the minimum requirements for emergency plans for use in attaining an acceptable state of
' emergency preparedness and thereby provides adequate assurance to protect the U:
- public health and safety.
m Additionr.lly, on September 23, 1988, the Commission published Statements Of K
Consideration from!S3 FR 36955 amending its regulations to establish more clearly what emergency planning and preparedness requirements are needed for fuel loading and low-power testing of nuclear power plants, which applies as well to a defueled reactor.
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C Exemotion Reauested.
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?The District requests an exemption frc~ the following emergency preparedness l'
- requirements:
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110 CFR 50.47(b)(14) and 10 CFR 50, and Appendix E. IV. Section F.
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" Training" paragraphs 1 through 3(f) and NUREG-0654 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans
=and Preparedness in Support of Nuclear Power Plants," Sections 1
II.N.1.a. and II.N.1.b:: requiring State.and local participation in
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the annual exercise.
e' 110 CFR 50.47(b)(5) as implemented by FEMA REP-10 "C"
'or the-Evaluation of Alert and Notification Systems for Nt Power
' t Plants" requiring annual activation of the alert ant
...fication system.
~10 CFR 50.47(b)(7) and'10 CFR'50 Appendir E, IV..Section D,
" Notification Procedures" paragraph 2 and NUREG-0654, Sections
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II.G.1 and II.G.2 requiring distribution of information brochures to
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the public within.'
plume exposure pathway.EPZ.
Rancho Seco is permanently shutdown and completely defueled; therefore, the L
potential for postulated accidents are much less than those considered when
-the NRC promulgated the emergency preparedness regulations.
.j The Statements Of' Consideration regarding " Emergency Planning and
- Preparedness Requirements for Nuclear Power Plant Fuel Loading and Low-Power L
Testing" more clearly define-the= application of requirements for a defueled E
facility, and state that the primary goal of emergency pianning and p
preoaredness is for dealing with accidents that could affect persons onsite.
The District agrees with the Commission's statement that the licensee provide L
onsite personne1~for mitigating and containing accidents and keeping offsite agencies informed of-plant events. Therefore, the District will perform l
- communications drills'to ensure that information is provided to the offsite
. emergency organizations but without the activation of the offsite agencies for par ticipation in lan annual exercise.
Information communicated to offsite e
agencies would typically not' require the activation of the alert ud notification system or distribution of information. However, these drills will include the communications necessary to ensure State. and local authorities are notified in a timely manner and updated as appropriate.
+
The District successfully passed the 1989 annual exercise, and, as cited by Reference 4,
... demonstrated the'llcensee's ability to adequately respond to aa emergency at the facility and to protect the public's health and safety.
No deficiencies, violations of NRC requirements, or exercise weaknesses-were identified."
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The District contends that the results of this exercise provide assurance of emergency preparedness of both the onsite and offsite organizations based on an operating plant's emergency program. - Activation of the-alert and notification system or distribution of information for full State.and local i
participation is not required for a shutdown. defueled facility.
Since-the last exercise, the District has prepared and submitted the Long Term Defueled-Condition Emergency Plan (Reference 3) and the Long Term Defueled s
Technical Specifications, Proposed Amendment No.18', Revision 1 (Reference 1).
These submittals, as well as the supporting dose calculations, describe the defueled status of Rancho Seco.
Reference 3 acknowledges that there are no postulated design basis accidents with~all fuel removed from the reactor and placed in long term storage. These-submittals,' supported by District calculations, conclude that plume exposure
-Protective Action Guidelines (PAGs) will not be exceeded for any postulated
+
event at Rancho Seco in'the defueled condition.
State and local agencies have reviewed this dumentation and have found them to be acceptable.
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Exemotion Criteria 10 CFR 50.12 " Specific Exemptions" describes the criteria for exemptions from-
- the requirements of 10 CFR 50.
The~NRC may grant exemptions from Part 50 i
regulations if special circumstances ars present and an undue risk will not be presented to thc public health and safety.
In the discussion below the Distrir.t will address the following exemption criteria of 10 CFR 50.12(a)(2):
(ii)
Application of:the regulation in the particular circumstances L
would not serve the underlying purpose of the rule or is not I
necessary to achieve the underlying purpose of the rule; (iii)
Compliance would result in undue hardship or other costs that are significantly in excess of those contemplated when the rule was' adopted...;
i.
Basis for Exemotion cBecause of a public vote on lune 6, 1989, the District shutdown the Rancho Seco Nuclear Generating Station and completed defueling operations on December 8. 1989. As cited in Reference 1 and discussed in the granting of v
L partial exemption from 10 CFR 55 (Reference 3), there are no longer any l
credible design basis accidents except loss of offsite power and a fuel handling accident.
The permanently defueled condition, combined with administrative control, result in the minimum movement of fuel and thereby L
.further reduce the possibility of an accident.
Moreover, the NRC has issued a L
confirmatory order modifying the Rancho Seco license to prohibit the movement of fuel from the Spent Fuel Pool into the Reactor Building without prior Commission approval.
-The requirements for 10 CFR 50.47 and Appendix E were predicated upon the need l
-to ensure that the spectrum of postulated accidents from power operations
.would not endanger public health and safety by exceeding the requirements of
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10lCFR 100,.Because. Rancho Seco is no longer capable'of an accident i
comparable to;10 CFR-100-requirements, literal compliance with 10 CFR 50,
. Appendix E. Section F, " Training," paragraphs 1 through 3(f) and NUREG-06b.
Sections II.N l.a. ~and II.N.1.b. would not serve the underlying purpose of the
. rule.when the rule.was promulgated.
s Additionally. comp 11ance with. Planning Standard E in NUREG-0654/ FEMA-REP-10 for notification by the licensee,10 CFR 50 Appendix E Section D, e " Notification Procedures," paragraph 2, and.NUREG-0654, Sections II.G.1 and II'.G 2., would not serve the underlying purpose of the rule when the rule was promulgated because Rancho Seco is no longer capable of accidents comparable to 10 CFR 100 requirements (10 CFR 50.12(a)(2)(ii)).
The' requirements for alert and notification were predicated upon the need to ensure that.the spectrum of postulated accidents from power operations would not-endanger public health and safety by exceeding the requirements of 10 CFR:
- 100; therefore, literal compliance with the requirements for activation of the alert cnd notification system and distribution of information (brochures) would result in undue hardship and costs that are significantly in excess of those contemplated when the rule was adopted (10 'ti 50.12(a)(2)(iii)) for a plant in a permanently defueled condition.
Because of the preparatory work and pre-notificat1R. iequired for activation of the alert and notification system, the District believes that the amount of activity required to notify personnel, distribute emergency notification
'information, including broadcasting costs, are significant for a facility permanently shutdown, defueled, and not capable of exceeding 10 CFR Part 100
. requirements.
10 CFR-50.47(a)(1) states in part, "... reasonable assurance that adequate protective measures can and will be taken in the event of a radiological' emergency" clearly-indicate the protection measures necessary are directly dependant on the nature of the radiological emergencies credible at a given t
facility. : As described by "Part 50 - Statements of Consideration," it is perspicuous that the Commission did not intend the same level of emergency preparedness to be applied to a reactor undergoing fuel loading and low-power testing as for a reactor licensed for full power operation.
Likewise, it is prudent to assume that the Commission, in contemplating the regulations, did i
I' not intend to apply the full requirements for offsite participation in
' exercises when the capability for accidents resulting in potential offsite radiological hazards have been obviated.- The full spectrum of analyzed
? accidents and consequences of those accidents have been evaluated in References.1'and 3; therefore, the NRC should grant the District an exemption h
from the-above requested emergency preparedness requirements and allow the H
District ~to exclude State and local agency participation in an annual exercise.
f
. Additionally, State and local agencies, as well as FEMA, have recognized that, l
-given-the defueled condition of Rancho Seco, full activation of the ERO l(requirtN the mobilization of a large number of individuais from offsite agenc46, and activation of the alert and notifica:lon system to support an
. arn t J.xercise is not appropriate for the spectrum of postulated accidents anciatu' with a defueled plant.
The District believes that these conditions L.
. ave ob-lated the need to perform the annual exercise and to initiate f
utW son of the alert and notification system.
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