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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20216G3501999-09-29029 September 1999 Confirms Conversations Re NRC Staff Voluntary Response to Orange County Discovery Requests.Staff Will Voluntarily Answer Discovery Requests & Will Not Waive Any Objection or Privilege Under NRC Regulations.Related Correspondence ML20212M1081999-09-29029 September 1999 Confirms Intent to Meet with Utils on 991025 in Atlanta,Ga to Discuss Pilot Plants,Shearon Harris & Sequoyah Any Observations & Lessons Learned & Recommendations Re Implementation of Pilot Program ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements ML18016B0391999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML20212H7741999-06-23023 June 1999 Responds to Re Petition Filed by Orange County Board of Commissioners Re Proposed Expansion of Sf Storage Capacity at Shearon Harris Npp.Public Meeting Will Be Held at Later Date.With Certificate of Svc.Served on 990624 ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18016A9831999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9721999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re Cpl Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation ML18016A9631999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend ML20206R2511999-05-19019 May 1999 Responds to Addressed to Chairman Jackson Requesting That NRC Grant Standing to Orange County Board of Commissioners in Shearon Harris Proceeding Currently Before Board.With Certificate of Svc.Served on 990519 ML20206Q5281999-05-17017 May 1999 Responds to 990304 Request for Two Rail Routes to Be Used for Transport of Spent Fuel from Brunswick Steam Electric Plant,Southport,Nc & Hb Robinson Steam Electric Plant, Hartsville,Sc to Shearon Harris Npp,Near New Hill,Sc ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 ML18016A9601999-05-11011 May 1999 Forwards Resolution Adopted by Carrboro Board of Aldermen at 990504 Meeting.Resolution Expresses Town Concern Re Util Plans to Double high-level Nuclear Waste Storage at Shnpp ML18016A9481999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 ML18016A9451999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld ML18016A9211999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC ML18016A9221999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9161999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl IR 05000400/19982011999-04-12012 April 1999 Discusses Safeguards Insp Rept 50-400/98-201 (Operational Safeguards Response Evaluation) on 980908-11.No Violations Noted.Licensee Performance During Evaluation Indicated Excellent Overall Contingency Response Capability 1999-09-08
[Table view] Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217A9811999-10-30030 October 1999 Forwards Sept 1999 Performance Indicator Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Includes Data Through Aug 1999 (two-thirds of 3rd Quarter of 1999) for 13 Units at 9 Pilot Sites ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20196H8491999-06-28028 June 1999 Forwards June 1999 Performance Indicator (PI) Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Constitutes Second Monthly PI Data Submittal from Pilot Plant Licensees,Which Includes Data Through May 1999 ML20210F7021999-04-30030 April 1999 Requests Waiver of Fees for Thirteen Dockets That Compromise Plant Population for NRR Pilot Regulatory Oversight Program. Purposes of Pilot Program Described in Commission Papers SECY-99-007 & SECY-99-007A ML20207L1901999-03-16016 March 1999 Informs That NRC Staff Set Up Single Electronic Mail Address to Receive All Communications (Including Service of Filings) Re CP&L Proceeding.All Electronic Communications Should Be Sent to Counsel for NRC Staff at New Electronic Address ML20207G5621999-01-12012 January 1999 Requests That Nc Denr & Div of Radiation Protection Use Whatever State Sources Necessary to Do Thorough Independent Technical,Regulatory,Safety,Risk & Engineering Review of Proposed Amend.With Certificate of Svc.Served on 990309 ML20198F1471997-08-0707 August 1997 Discusses Dam Safety Audit at Plant Auxiliary Reservoir Dam. Draft Ltr for Use in Transmitting FERC Rept to Licensee, Action List of NRC Requested Licensee Actions,Info Re Natl Inventory of Dams & Insp Rept,Dtd 970630,encl ML20205M3331997-07-28028 July 1997 Provides Final Agenda for Region II Enforcement Meeting to Be Held on 970730.OI Attendance Requested for Issue Involving Termination of Turkey Point Radwaste Operator Who Failed to Follow Procedure ML20128G5751996-10-0303 October 1996 Forwards Ltr to Be Sent to Licensees of Six Pressurized Water Reactor Plants That Have Used Fuel Mfg by Siemens Power Corp Since 1986.Licensees Requested to Verify Compliance of 10CFR50.46 W/Regulations ML20134B7921996-06-24024 June 1996 Discusses Results of Audit Review of Changes to Siemens Large Break ECCS Evaluation Model ML20134J1821990-07-12012 July 1990 Informs That Full Investigation Re Counterfeit Electrical Components Shipped to Shearon Harris Nuclear Plant Will Be Initiated ML20134H3841990-06-26026 June 1990 Requests That OI Investigate Circumstances Surrounding Possible Wrongdoing by Stokely Enterprises of Norfolk,Va & Spectronics of Mobile Re Misrepresented Potter & Brumfield Relays to Shearon Harris Nuclear Power Plant ML20235S6271989-02-28028 February 1989 Notification of 890307 Meeting W/Bwr Owners Group in Rockville,Md to Discuss Items of Current Interest.Agenda Encl ML20195E6191988-06-13013 June 1988 Notifies of CRGR Meeting 138 on 880614 in Rockville,Md. Agenda Listed ML20154D8541987-12-30030 December 1987 Forwards Info on Auxiliary Feedwater Check Valves for Facilities Per IE Bulletin 85-001,in Response to 871229 Request ML20238A8041987-09-0303 September 1987 Notification of 870917 Meeting W/Util in Bethesda,Md to Discuss Tech Specs Improvement Program Per Generic Ltr 87-09 ML20238E0001987-09-0303 September 1987 Notification of Time Change for 870917 Meeting W/Util in Bethesda,Md to Discuss Generic Ltr 87-09 Re Tech Spec Improvement Program ML20195G3891987-08-21021 August 1987 Forwards Safety Evaluation Re Util 870526 Application for Amend to License NPF-63,increasing Max Allowed Enrichment of Reload Fuel to 4.2% Weight U-235.Changes Acceptable ML20195G2961987-07-14014 July 1987 Forwards Request for Addl Info Re Util 870526 Proposed Tech Spec Change Concerning Handling & Storage of Fuel W/Increased Enrichment to 4.2 Weight % U-235 NUREG-1079, Forwards Documents to Be Placed on Document Control Sys. Advance Copy Already Sent to PDR1987-05-13013 May 1987 Forwards Documents to Be Placed on Document Control Sys. Advance Copy Already Sent to PDR ML20209A9621987-04-28028 April 1987 Forwards Two Photographs of Separation Problem in Fuel Handling Bldg.Previous Pictures of licensee-identified Items Not Similar in Nature to Problem Identified by Ford ML20210L9561987-02-0505 February 1987 Forwards NRR Monthly Status Rept,Including Info Available as of 870131.Rept Identifies Potential or Actual Licensing Delay for Shoreham,Comanche Peak Unit 1,Braidwood Unit 1 & Seabrook Unit 1 ML20212G3021987-01-20020 January 1987 Forwards Attachments to Be Incorporated in Transcript Re Facility ML20207M0361987-01-0606 January 1987 Provides Current Status of Facility Proceeding,Including Admitted Contentions Raising Listed Issues.Aslb Issued Three Initial Decisions & Concluding or Final ASLB Decision Favorable to Applicants ML20207K8061987-01-0606 January 1987 Forwards Ltr Presented to Asselstine on 870105 to Be Served on Parties to Proceeding.Served on 870106 ML20215E9231986-12-19019 December 1986 Summarizes Status of Shearon Harris Proceeding.Contentions Raised on Listed Issues.Aslb Issued Three Partial Initial Decisions & One Concluding Decision.Decisions Appealed & Three Affirmed by Appeal Board.One Decision Pending ML20207E2271986-12-19019 December 1986 Notifies of Commissioner Asselstine 870105 Site Visit. Representatives of Interested Parties Invited to Attend. Served on 861219 IA-86-843, Summarizes Status of Shearon Harris Proceeding.Contentions Raised on Listed Issues.Aslb Issued Three Partial Initial Decisions & One Concluding Decision.Decisions Appealed & Three Affirmed by Appeal Board.One Decision Pending1986-12-19019 December 1986 Summarizes Status of Shearon Harris Proceeding.Contentions Raised on Listed Issues.Aslb Issued Three Partial Initial Decisions & One Concluding Decision.Decisions Appealed & Three Affirmed by Appeal Board.One Decision Pending ML20212C6771986-12-15015 December 1986 Requests That Encl 861215 Minutes of 861210 Meeting W/ Coalition for Alternatives to Shearon Harris Be Placed in PDR ML20211L6521986-12-12012 December 1986 Advises That Time for Commission to Review ALAB-852 Expired. Commission Declined Review.Decision Became Final Agency Action on 861210.Served on 861212 ML20196B6441986-12-12012 December 1986 Forwards Ofc of Investigations Rept of Inquiry Re Alleged Falsification of Radiation Exposure Records & Alleged Discrimination (Q2-86-017).Partially Deleted Related Info Encl ML20215B1281986-12-10010 December 1986 Advises That Time for Commission to Review ALAB-843 Expired. Commission Declined Review.Decision Became Final Agency Action on 861031.Served on 861210 ML20206C0431986-12-0404 December 1986 Memo for Affirmation,Notifying That Commission Being Asked to Respond to Request from W Eddelman & Coalition for Alternatives to Facility for Hearing on Util Requested Exemption from Requirements for Emergency Exercise ML20215N6601986-11-0606 November 1986 Advises That Commissioner Bernthal Has Canceled Planned 861118 Visit to Facility.Served on 861106 ML20215N5681986-10-29029 October 1986 Forwards 860825-29 Rept Documenting IE Assessment of Three Technical Allegations Re Cable Tray Support Design at Facility.Allegation Re Load Carrying Adequacy of Connection Detail Used for Cable Tray Supports Included in Rept ML20215M4501986-10-28028 October 1986 Advises of Commissioner Bernthal 861118 Visit to Facility. All Representatives of Party to Proceeding Wishing to Attend Should Notify Author by C.O.B. on 861112.Served on 861029 ML20236F1641986-10-23023 October 1986 Advises That Based on Implementation of Insp Program,Const & Preoperational Testing of Plant Have Been Completed Per FSAR & Other Docketed Commitments.Recommends Issuance of Low Power License for Plant.List of Licensed Conditions Encl IA-87-279, Advises That Based on Implementation of Insp Program,Const & Preoperational Testing of Plant Have Been Completed Per FSAR & Other Docketed Commitments.Recommends Issuance of Low Power License for Plant.List of Licensed Conditions Encl1986-10-23023 October 1986 Advises That Based on Implementation of Insp Program,Const & Preoperational Testing of Plant Have Been Completed Per FSAR & Other Docketed Commitments.Recommends Issuance of Low Power License for Plant.List of Licensed Conditions Encl ML20215J4321986-10-21021 October 1986 Forwards Trip Rept of 860825-29 Visit to Facility to Conduct Assessment of Technical Allegation Re Cable Tray Support Design.One Allegation Re Connection Detail Used on Cable Tray Substantiated ML20212G0401986-09-30030 September 1986 Forwards Background Info on Facility Per 860924 Request. Proposed Agenda for Chairman Lw Zech 860914-15 & Commissioner KM Carr 861050-06 Site Visits Encl ML20209A9981986-09-30030 September 1986 Notification of 861009 Enforcement Conference W/Util in Region II Ofc to Discuss Potential Deficiency in Const QA Program.Util Nonconformance Rept,List of Attendees & Util Presentation Viewgraphs Encl ML20214R5231986-09-24024 September 1986 Informs Parties That Commissioner KM Carr Will Tour Facility on 861006.Notification Requested by 861002 of Any Parties to Proceeding Wishing Single Representative Attendance. Served on 860924 IA-86-793, Forwards Ofc of Investigations Rept of Inquiry Q2-85-021 Re Alleged Falsification of Preservice Piping Insp Records by Contractor.W/Nuclear Energy Svcs,Inc Calibr Data Sheets1986-09-22022 September 1986 Forwards Ofc of Investigations Rept of Inquiry Q2-85-021 Re Alleged Falsification of Preservice Piping Insp Records by Contractor.W/Nuclear Energy Svcs,Inc Calibr Data Sheets ML20237G4671986-09-22022 September 1986 Forwards Ofc of Investigations Rept of Inquiry Q2-85-021 Re Alleged Falsification of Preservice Piping Insp Records by Contractor.W/Nuclear Energy Svcs,Inc Calibr Data Sheets ML20207S2361986-09-17017 September 1986 Advises That Commission Disapproved SECY-86-252, Commission Review of Shearon Harris Appeal Board Decision on Environ Issues ML20210B5561986-09-16016 September 1986 Forwards Ps Miriello Affidavit to Be Serve Upon Appropriate Parties & Boards in Pending Proceedings. Served on 860917 ML20214N4421986-09-15015 September 1986 Notifies That Time Provided by NRC Regulations within Which Commission May Act to Review ALAB-837 Expired.Served on 860915 ML20236F1421986-09-12012 September 1986 Forwards Lists of Items to Be Completed Prior to Fuel Loading,Per Insp Procedure 94300B.Licensee Projected Fuel Load Date Is Sept 1986 ML20209F9741986-09-11011 September 1986 Requests That 860911 Memo Re Emergency Planning Exemption Request Be Served on Parties to Proceeding.Served on 860911 ML20209G0191986-09-11011 September 1986 Discusses B Cummings Telcon Concerning Ltr Expressing Opposition to Util Request for Exemption to Emergency Drill Requirements 1999-07-27
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217A9811999-10-30030 October 1999 Forwards Sept 1999 Performance Indicator Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Includes Data Through Aug 1999 (two-thirds of 3rd Quarter of 1999) for 13 Units at 9 Pilot Sites ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20196H8491999-06-28028 June 1999 Forwards June 1999 Performance Indicator (PI) Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Constitutes Second Monthly PI Data Submittal from Pilot Plant Licensees,Which Includes Data Through May 1999 ML20210F7021999-04-30030 April 1999 Requests Waiver of Fees for Thirteen Dockets That Compromise Plant Population for NRR Pilot Regulatory Oversight Program. Purposes of Pilot Program Described in Commission Papers SECY-99-007 & SECY-99-007A ML20207L1901999-03-16016 March 1999 Informs That NRC Staff Set Up Single Electronic Mail Address to Receive All Communications (Including Service of Filings) Re CP&L Proceeding.All Electronic Communications Should Be Sent to Counsel for NRC Staff at New Electronic Address ML20207G5621999-01-12012 January 1999 Requests That Nc Denr & Div of Radiation Protection Use Whatever State Sources Necessary to Do Thorough Independent Technical,Regulatory,Safety,Risk & Engineering Review of Proposed Amend.With Certificate of Svc.Served on 990309 ML20198F1471997-08-0707 August 1997 Discusses Dam Safety Audit at Plant Auxiliary Reservoir Dam. Draft Ltr for Use in Transmitting FERC Rept to Licensee, Action List of NRC Requested Licensee Actions,Info Re Natl Inventory of Dams & Insp Rept,Dtd 970630,encl ML20205M3331997-07-28028 July 1997 Provides Final Agenda for Region II Enforcement Meeting to Be Held on 970730.OI Attendance Requested for Issue Involving Termination of Turkey Point Radwaste Operator Who Failed to Follow Procedure ML20128G5751996-10-0303 October 1996 Forwards Ltr to Be Sent to Licensees of Six Pressurized Water Reactor Plants That Have Used Fuel Mfg by Siemens Power Corp Since 1986.Licensees Requested to Verify Compliance of 10CFR50.46 W/Regulations ML20134B7921996-06-24024 June 1996 Discusses Results of Audit Review of Changes to Siemens Large Break ECCS Evaluation Model ML20134J1821990-07-12012 July 1990 Informs That Full Investigation Re Counterfeit Electrical Components Shipped to Shearon Harris Nuclear Plant Will Be Initiated ML20134H3841990-06-26026 June 1990 Requests That OI Investigate Circumstances Surrounding Possible Wrongdoing by Stokely Enterprises of Norfolk,Va & Spectronics of Mobile Re Misrepresented Potter & Brumfield Relays to Shearon Harris Nuclear Power Plant ML20235S6271989-02-28028 February 1989 Notification of 890307 Meeting W/Bwr Owners Group in Rockville,Md to Discuss Items of Current Interest.Agenda Encl ML20195E6191988-06-13013 June 1988 Notifies of CRGR Meeting 138 on 880614 in Rockville,Md. Agenda Listed ML20154D8541987-12-30030 December 1987 Forwards Info on Auxiliary Feedwater Check Valves for Facilities Per IE Bulletin 85-001,in Response to 871229 Request ML20238E0001987-09-0303 September 1987 Notification of Time Change for 870917 Meeting W/Util in Bethesda,Md to Discuss Generic Ltr 87-09 Re Tech Spec Improvement Program ML20238A8041987-09-0303 September 1987 Notification of 870917 Meeting W/Util in Bethesda,Md to Discuss Tech Specs Improvement Program Per Generic Ltr 87-09 ML20195G3891987-08-21021 August 1987 Forwards Safety Evaluation Re Util 870526 Application for Amend to License NPF-63,increasing Max Allowed Enrichment of Reload Fuel to 4.2% Weight U-235.Changes Acceptable ML20195G2961987-07-14014 July 1987 Forwards Request for Addl Info Re Util 870526 Proposed Tech Spec Change Concerning Handling & Storage of Fuel W/Increased Enrichment to 4.2 Weight % U-235 NUREG-1079, Forwards Documents to Be Placed on Document Control Sys. Advance Copy Already Sent to PDR1987-05-13013 May 1987 Forwards Documents to Be Placed on Document Control Sys. Advance Copy Already Sent to PDR ML20209A9621987-04-28028 April 1987 Forwards Two Photographs of Separation Problem in Fuel Handling Bldg.Previous Pictures of licensee-identified Items Not Similar in Nature to Problem Identified by Ford ML20210L9561987-02-0505 February 1987 Forwards NRR Monthly Status Rept,Including Info Available as of 870131.Rept Identifies Potential or Actual Licensing Delay for Shoreham,Comanche Peak Unit 1,Braidwood Unit 1 & Seabrook Unit 1 ML20212G3021987-01-20020 January 1987 Forwards Attachments to Be Incorporated in Transcript Re Facility ML20207Q2021987-01-16016 January 1987 Staff Requirements Memo Re 870108 Discussion/Possible Vote in Washington,Dc on Full Power OL for Plant.Commission Authorized Issuance of Full Power OL ML20207M0361987-01-0606 January 1987 Provides Current Status of Facility Proceeding,Including Admitted Contentions Raising Listed Issues.Aslb Issued Three Initial Decisions & Concluding or Final ASLB Decision Favorable to Applicants ML20207K8061987-01-0606 January 1987 Forwards Ltr Presented to Asselstine on 870105 to Be Served on Parties to Proceeding.Served on 870106 IA-86-843, Summarizes Status of Shearon Harris Proceeding.Contentions Raised on Listed Issues.Aslb Issued Three Partial Initial Decisions & One Concluding Decision.Decisions Appealed & Three Affirmed by Appeal Board.One Decision Pending1986-12-19019 December 1986 Summarizes Status of Shearon Harris Proceeding.Contentions Raised on Listed Issues.Aslb Issued Three Partial Initial Decisions & One Concluding Decision.Decisions Appealed & Three Affirmed by Appeal Board.One Decision Pending ML20215E9231986-12-19019 December 1986 Summarizes Status of Shearon Harris Proceeding.Contentions Raised on Listed Issues.Aslb Issued Three Partial Initial Decisions & One Concluding Decision.Decisions Appealed & Three Affirmed by Appeal Board.One Decision Pending ML20207E2271986-12-19019 December 1986 Notifies of Commissioner Asselstine 870105 Site Visit. Representatives of Interested Parties Invited to Attend. Served on 861219 ML20212C6771986-12-15015 December 1986 Requests That Encl 861215 Minutes of 861210 Meeting W/ Coalition for Alternatives to Shearon Harris Be Placed in PDR ML20211L6521986-12-12012 December 1986 Advises That Time for Commission to Review ALAB-852 Expired. Commission Declined Review.Decision Became Final Agency Action on 861210.Served on 861212 ML20196B6441986-12-12012 December 1986 Forwards Ofc of Investigations Rept of Inquiry Re Alleged Falsification of Radiation Exposure Records & Alleged Discrimination (Q2-86-017).Partially Deleted Related Info Encl ML20215E0721986-12-11011 December 1986 Staff Requirements Memo Re 861204 Affirmation/Discussion & Vote in Washington,Dc Re W Eddleman & Coalition for Alternatives to Shearon Harris Request for Hearing on Util Request for Exemption from Full Scale Exericse ML20215B1281986-12-10010 December 1986 Advises That Time for Commission to Review ALAB-843 Expired. Commission Declined Review.Decision Became Final Agency Action on 861031.Served on 861210 ML20206C0741986-12-0505 December 1986 Staff Requirements Memo Re Affirmation/Discussion & Vote on Request for Hearing Re Facility Exemption Request.Order Finds No Matl Issues of Fact That Warrant Hearing ML20206C0431986-12-0404 December 1986 Memo for Affirmation,Notifying That Commission Being Asked to Respond to Request from W Eddelman & Coalition for Alternatives to Facility for Hearing on Util Requested Exemption from Requirements for Emergency Exercise ML20215N6601986-11-0606 November 1986 Advises That Commissioner Bernthal Has Canceled Planned 861118 Visit to Facility.Served on 861106 ML20215N5681986-10-29029 October 1986 Forwards 860825-29 Rept Documenting IE Assessment of Three Technical Allegations Re Cable Tray Support Design at Facility.Allegation Re Load Carrying Adequacy of Connection Detail Used for Cable Tray Supports Included in Rept ML20215M4501986-10-28028 October 1986 Advises of Commissioner Bernthal 861118 Visit to Facility. All Representatives of Party to Proceeding Wishing to Attend Should Notify Author by C.O.B. on 861112.Served on 861029 ML20236F1641986-10-23023 October 1986 Advises That Based on Implementation of Insp Program,Const & Preoperational Testing of Plant Have Been Completed Per FSAR & Other Docketed Commitments.Recommends Issuance of Low Power License for Plant.List of Licensed Conditions Encl IA-87-279, Advises That Based on Implementation of Insp Program,Const & Preoperational Testing of Plant Have Been Completed Per FSAR & Other Docketed Commitments.Recommends Issuance of Low Power License for Plant.List of Licensed Conditions Encl1986-10-23023 October 1986 Advises That Based on Implementation of Insp Program,Const & Preoperational Testing of Plant Have Been Completed Per FSAR & Other Docketed Commitments.Recommends Issuance of Low Power License for Plant.List of Licensed Conditions Encl ML20215J4321986-10-21021 October 1986 Forwards Trip Rept of 860825-29 Visit to Facility to Conduct Assessment of Technical Allegation Re Cable Tray Support Design.One Allegation Re Connection Detail Used on Cable Tray Substantiated ML20212G0401986-09-30030 September 1986 Forwards Background Info on Facility Per 860924 Request. Proposed Agenda for Chairman Lw Zech 860914-15 & Commissioner KM Carr 861050-06 Site Visits Encl ML20209A9981986-09-30030 September 1986 Notification of 861009 Enforcement Conference W/Util in Region II Ofc to Discuss Potential Deficiency in Const QA Program.Util Nonconformance Rept,List of Attendees & Util Presentation Viewgraphs Encl ML20214R5231986-09-24024 September 1986 Informs Parties That Commissioner KM Carr Will Tour Facility on 861006.Notification Requested by 861002 of Any Parties to Proceeding Wishing Single Representative Attendance. Served on 860924 IA-86-793, Forwards Ofc of Investigations Rept of Inquiry Q2-85-021 Re Alleged Falsification of Preservice Piping Insp Records by Contractor.W/Nuclear Energy Svcs,Inc Calibr Data Sheets1986-09-22022 September 1986 Forwards Ofc of Investigations Rept of Inquiry Q2-85-021 Re Alleged Falsification of Preservice Piping Insp Records by Contractor.W/Nuclear Energy Svcs,Inc Calibr Data Sheets ML20237G4671986-09-22022 September 1986 Forwards Ofc of Investigations Rept of Inquiry Q2-85-021 Re Alleged Falsification of Preservice Piping Insp Records by Contractor.W/Nuclear Energy Svcs,Inc Calibr Data Sheets ML20203N3441986-09-19019 September 1986 Staff Requirements Memo on 860911 Affirmation/Discussion & Vote in Washington,Dc Re SECY-86-254,SECY-86-257 & SECY-86-258 ML20207S2361986-09-17017 September 1986 Advises That Commission Disapproved SECY-86-252, Commission Review of Shearon Harris Appeal Board Decision on Environ Issues ML20210B5561986-09-16016 September 1986 Forwards Ps Miriello Affidavit to Be Serve Upon Appropriate Parties & Boards in Pending Proceedings. Served on 860917 1999-07-27
[Table view] Category:NRC TO ASLP
MONTHYEARML20205A6041986-08-0707 August 1986 Expresses Appreciation for 851119 & s Re Adequacy of Emergency Alerting Siren Sys at Nuclear Power Reactors. Commission Will Request Views on Generic Issue & Decide If Rules & Guidance Documents Need Rev.Served on 860807 ML20138A2551986-03-10010 March 1986 Forwards V Stello 860224 Memo to Commissioners,Clarifying Info Contained in FEMA Re Nighttime Notification. Memo Being Served on All Parties in Proceeding.Related Correspondence ML20137X0901986-02-26026 February 1986 Forwards Addl Handwritten Notes Transmitted by FEMA from Anl for in Camera Insp in Response to Request for Aid in Resolution of Dispute Between Eddleman & Fema.W/O Encl. Related Correspondence ML20205J6761986-02-21021 February 1986 Forwards Testimony of Kd Kryter Re Memorandum & Order Concerning Limited Reopening of Record in Eddleman Contention 57-C-3 Which FEMA Will Present at 860304 Hearing. Related Correspondence ML20153D5091986-02-20020 February 1986 Forwards Addl Handwritten Notes from Anl Per FEMA Request for in Camera Insp Re Resolution of Discovery Dispute Between Eddleman & Fema.W/O Encl.Related Correspondence ML20137S0501986-02-0707 February 1986 Informs That FEMA Will Present Testimony of Kryter,Per Item 2 of 860116 Order.Kryter Will Answer Questions Re Items 3 & 5.Testimony on Item 6 Will Not Be Provided Due to Lack of Resources to Conduct Analysis ML20137P0931986-01-31031 January 1986 Forwards Handwritten Notes Provided by Fema,As Requested for in Camera Insp to Aid in Resolution of Pending Discovery Dispute Between FEMA & Eddleman.Remaining Notes Will Be Forwarded When Located.W/O Encl.Related Correspondence ML20136J4401986-01-0303 January 1986 Provides Lee Prefiled Testimony Re Data Underlying Generation of Map.Related Correspondence ML20138R0851985-12-23023 December 1985 Forwards Signed Page 57 of NRC 851220 Proposed Findings of Fact & Conclusions of Law on Conservation Council of North Carolina Contention WB-3 (Drug Abuse During Const) ML20138P4941985-12-23023 December 1985 Forwards Wj Dircks 851211 Memo & FEMA Re Emergency Nighttime Notification Sent in Response to Encl ASLB .Encls Will Be Served on Parties to Proceeding.Related Correspondence ML20138E8381985-12-12012 December 1985 Responds to 851204 Request for Map Underlying Lee Testimony. Copies Being Reproduced for Board,Applicant & Eddleman by FEMA & Unavailable Until After Christmas ML20137S6521985-12-0303 December 1985 Forwards English Translation of Bassiouni Final Rept, Studies of Effects of Waking Signals on Sleepers W/ Different Depths of Sleep & Dispositions. Translation Served on All Parties.Related Correspondence ML20137D6601985-11-15015 November 1985 Forwards MR Bassiouni Forwarding ATI Review & German Study of Prefiled Testimony Re Eddleman Contention 57-C-3 Concerning Alert & Notification Sys,Per Request. Related Correspondence ML20138D1871985-10-18018 October 1985 Forwards FEMA Testimony & Supplemental Response to General Interrogatories Re Eddleman Contention 57-C-3.No Other Documents Intended for Introduction as Exhibits in Proceeding.Related Correspondence ML20137W4001985-09-23023 September 1985 Forwards Revised Testimony of LL Bush on Contention WB-3 Re Util Drug Prevention & Detection Program,Replacing 850920 Transmittal.Related Correspondence ML20135H8601985-09-20020 September 1985 Forwards Testimony of Fj Long,Wj Tobin,Rl Prevatte & LL Bush Re Conservation Council of North Carolina Contention WB-3 Concerning Drug Use During Const.Related Correspondence ML20137J3071985-08-27027 August 1985 Advises That NRC Has Insufficient Facts to Take Position on Applicant 850712 Motion for Summary Disposition of Intervenor Contention WB-3 Re Drug Abuse During Const.No Response Will Be Filed,Pending Receipt of Addl Info ML20134H3731985-08-23023 August 1985 Returns ASLB Documents Used in Preparing Response to ASLB 850805 Memorandum.Related Correspondence.W/O Encl ML20129H2511985-06-0505 June 1985 Forwards Page 120 of 850122 Proposed Finding of Fact & Conclusions of Law on Safety Issues,Inadvertently Omitted from ASLB Copies.Page Also Served Upon All Parties to Proceeding ML20129H0781985-06-0505 June 1985 Requests 3-wk Hearing Extension in Order to Consult W/Ofc of General Counsel & Commission Re Ofc of Investigation Testimony at Contested Licensing Hearings.Served on 850605 IA-85-173, Requests 3-wk Extension in Order to Consult W/Ofc of General Counsel & Commission Re Ofc of Investigation Testimony at Contested Licensing Hearings1985-06-0404 June 1985 Requests 3-wk Extension in Order to Consult W/Ofc of General Counsel & Commission Re Ofc of Investigation Testimony at Contested Licensing Hearings ML20154B5681985-06-0404 June 1985 Requests 3-wk Extension in Order to Consult W/Ofc of General Counsel & Commission Re Ofc of Investigation Testimony at Contested Licensing Hearings ML20127M5401985-05-20020 May 1985 Forwards Sanitized Ofc of Investigation Investigation Rept, Alleged Harassment/Intimidation & Falsification of Documentation Commitments. Served on 850521 ML20154B4351985-04-19019 April 1985 Advises of Status of Ofc of Investigation Response to 850313 Memo (82-472-03 Ol).Guild Will Represent Confidential Alleger & Coordinate Affidavit.Interview Scheduled for 850430 or 0505 ML20062F2991978-12-0101 December 1978 Forwards NRC Staff Proposed Evidence for Remanded Proc in Subj Matter ML20062D7341978-11-0303 November 1978 Forwards Memos Repting Incident Relevant to Subj Facil Proc. Memo Allegations Are Still Unsubstantiated,But Are Presently Being Investigated 1986-08-07
[Table view] |
Text
,.- - .
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M# o,,
n UNITED STATES NUCLEAR REGULATORY COMMISSION NM
r, .. j wAssincrow, o. c. 20sss A.,*****j December 23, 1985 Cydf James L. Kelley, Chairman Mr. Glenn 0. Bright
~
Administrative Judge Administrative Judge Atomic Safety and Licensing Board Atomic Safety and Lj'6Ensi ~~ Boardi U.S. Nuclear Regulatory Comission U.S. Nuclear Regulatorf ~issio$".
Washington, DC 20555 Washington, DC 20555 Dr. James H Carpenter
' Administrative Judge
~
Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, DC 20555 In the Matter of Carolina Power and Light Company and North Carolina Eastern Municipal Power Agency (Shearon Harris Nuclear Power Plant, Units 1 and 2)
Docket Nos. 50-400 and 50-401 -CC
Dear Administrative Judges:
Enclosed for your information is a Memorandum for Chairman Palladino froni William Dircks, E.D.0. with attachment from FEMA prepared at the request of the Chairman. This Memorandum related to the letter sent by the Board to the Commission concerning nighttime notification. Copies of the enclosed document are also being served on the parties to this proceeding.
Sincerely,
~
8512260137 851223 PDR ADOCK 05000400 Janice E. Moore O PDR ,
Counsel for NRC Staff
Enclosure:
Palladino Memorandum cc w/ encl.: Service List
}S0
e s
[ g UNITED STATES
[]
( 'e NUCLEAR REGULATORY COMMISSION RfASHINGTON. D. C. 308E5
..... DEC 11985 MEMORANDUM FOR: Chairman Palladino Commissioner Roberts Commissioner Asselstine Commissioner Bernthal Commissioner Zech
^
FROM: William J. Dircks Executive Director for Operations
SUBJECT:
NIGHTTIME EMERGENCY NOTIFICATION Thismemor'SdumrespondstotheChairman'sNovember22,sNovember 1985, request that the staff respond to the Atomic Safety and Licensing Board 19, 1985, letter notifying the Commission of a possible noneric safety issue involving nighttime emergency notification of residents 'n the plume ex
. planning zones surrounding nuclear power plants (Enclosure 1)posure . Atemergency the staff's
. request the Federal Emergency Management Agency (FEMA) has reviewed the Licensing Board's letter and their response is provided in Enclosure 2. The applicable regulations and guidance relating to public alert and notification systems are summarized in Enclosure 3. 1/ .
4 The Federal Emergency Management Agency has evaluated the information presented in the Licensing Board's letter and has concluded that it does not indicate that there are generic safety problems involving nighttime emergency notification.
Further, FEMA states that the results of their study conducted for the Shearon i Harriscaseconfirmstheirjudgmentthatsirensystemsdesignedandevaluatedin accordance with NUREG-0654/ FEMA-REP-1, Rev. 1, and FEMA-43 meet the NRC require-ments for both daytime and nighttime alerting. .
1/By letter of December 2, 1985, the applicants (Carolina Power and Light Company andNorthCarolinaEasternMunicipalPowerApency)alsoprovidedtheirviewsto the Commission regarding the Licensing Board s November 19 letter. FEMA and the NRC staff have briefly reviewed the submission and find that it generally reflects the record of the Shearon Harris proceeding to date.
CONTACT: D. B. Matthews, IE '
492-9647
o l
,' The Commissioners Based on FEMA's conclusion in response to the Licensing Board's letter and the staff's understanding of the regulations in 10 CFR Part 50.47(b)(5), Appendix E SIV of 10 C.F.R. Part 50, the guidance in NUREG-0654/ FEMA-REP-1 Rev. 1, and the FEMA-43 review process, the staff does not believe that any generic action need be taken by the Commission in this matter.
ggegWilliam].DW William J. Dircks Executive Director for Operations
Enclosures:
,. 1. Licensing Board 1tr. dtd.
11/19/85
- 2. FEMA Evaluation
- 3. Summary of Requirements
.. cc: OGC OPE --- ...
SECY Shearon Harris Service List
,e , . v, . ENCLOSURE 1 UNITE 3 STATES f NUCLEAR REGULATORY COMMISSION
(*****).
, 5 ATOMIC SAFETY AND LICENSING eOARD PANEL wasemorow.ocasses November 19, 1985 i
l Chairman Nunzio J. Palladino " ,
Consissioner Thomas M. Roberts l Commissioner James K. Asselstine Commissioner Frederick M. Betathal Commissioner Lando W. Zeck
Dear Mr. Chairman and Commissioners:
We are writing this letter to bring to your attention evidence of possible generic safety problems involving nighttime emergency notification of residents in the plume emergency planning zones _ ,
surrourfding nuclear power plants. It apmars that under the acceptance criteria,being generally applied by the federal Emergency Management _
Agency 'to nuclear plant siren systems -- criteria wh' ch are based on daytime conditions -- substnntial numbers of EPZ residents would not be,
.. aroused from sleep should an emergency siren notification be necessary between, say, midnight and 6:00 a.m.. particularly if bedroom windows
. were closed.
. We are members of the Atomic Safety and Licensing Board presiding over the application of Carolina Power and Light Co. et al. for an operating license for the Shearon Harris facility. We ncently conducted an
- evidentiary hearing in that case on an Intervenor's contention that the l Applicants' sirens would not awaken sleeping residents in the EPZ
! between midnight and 6:00 a.m. particularly those who have closed their windows and turned on their air conditioners. Both the Applicants and -
l the Federal Emergency Management Agency presented extensive testimony and responded to cross-examination on the contention, as reflected in -
the Shearon Harris transcript. Tr. 9356-9976. The parties will be submitting proposed findings of fact on the siren and another contention ,
during December, and the Board expects to decide those contentions in early 1986. In these circumstances, we as a Licensing Board have not drawn any conclusions about the particular siren contention before us in the Shearon Harris case. In any event, we would have no occasion to write to you about Shearon Harris at this time -- in advance of the normal review process -- because Harris is not, of course, an operating facility. Furthermore, should any deficiencies in nighttime notification emerge from the Shearon Harris record, we could fashion l effective measures to deal with them on a site-specific basis. Rather, this letter is prompted by the possible generic implications of certain of the evidence in the Shearon Harris record, and our belief that such evidence should be called to your attention now. Most significantly, you should be aware of the following matters:
l 8
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yy . . . . .
.,, ...,. , .e.. , ,
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2-
)
- 1. The FEMA design critaria provide for siren sound covera 10d8(a)aboveambientnoiselevelsoraminimumof60d8(c)geof .
- 2. The " FEMA 43" reviews of siren system designs for operating nuclear facilities are based on sunner daytime conditions. Such reviews give no
! consideration to factors only applicable at night -- i.e. almost everyone is indoors and asleep, many with the windows closed. These
. factors are not offset by greater sound propagation at night.
- 3. The testimon air conditioning)y andisan that, for asiren outdoor house with sound theofwindows.
level 60 dB. theclosed (central is essentially zero. With the windows o.
probability of arousal is open, the probability from sleep (Tr. 9650).
7-85.
- 4. The sound levels necessary for high probability of arousal are substantially above the. FEMA minimum guidance. For example, a 505 probabfiity of arousal of an individual in a house with the windows closed requires outdoor sound levels of 90-99 decibels (Tr. 9927). The wide range in this estimate reflects the imperfect knowledge of stren i arousal capability, since direct tests have not been conducted, at least in the United States.
- 5. For the Harris assumed summer scenario -- including 36% of the houses in the EPZ with no air conditioning (windows open) -- arousal is estimated as approximately 705. Assuming the accuracy and acceptability of that estimate lower probable arousal rates in other climatic areas of the United States nevertheless suggest possible generic safety concerns -- particularly in the winter season, when more of the population may sleep with the windows closed.
- 6. We further note that overall arousal percentages for an EPZ can ..
mask the fact that. in areas of moderate housing density but with a fair number of houses more than one mile from a siren, a substantial ,
~
percentage of the houses would have an arousal probability of less than l
505. For example, at siren 70 in the Harris EPZ. about 100 houses of
- about 160 in that area, or 635, are in the 70-80 dB area. The l probability of arousing an individual in those houses with the windows closed is approximately 305, and is 555 for household arousal with two residents. If these houses correspond to U.S. averages 185 would have one resident. 305 would have two residents, and the average probability of arousing the household would be 435. Thus, although the risk of not being aroused, averaged over the EPZ. may be roughly 305. in some areas approximately 50% of the houses may have a risk of non-arousal of roughly 575.
NRC regulations require "early notification" to EPZ residents (10 C.F.R.
50.47(b)(5)) and this has been further defined to mean that the design objective of "the prompt public notification system shall be to have the capability to essentially complete the initial notification of the I l
. ~ ~1. ._ i .i l - ~ ~
/. 9 ?.
-3 public within the plume exposure pathway EPZ within about 15 minutes."
10 C.F.R. Part 50. Appendix E. IV D.3. The evidence we have cited indicates that in EPZs which rely primarily on siren notification it is our impression that that is the case for most comercial reactors)(, such notification would not be " essentially complete" urter some. typical nighttime conditions within 15 minutes. To be sure, emergency notification typically includes "back-up" notification by police, fire and other emergency vehicles driving prearranged routes with sirens sounding. However, as was testified to in the Shearon Harris case this back-up notification probably would not be accomplished in the 15-minute period. Testimony of Alvin H. Joyner at 42 ff. Tr. 9374. It seems doubtful that such back-up notification could be completed expeditiously
~
if emergency workers had to first be reached and activated between midnight and 6:00 a.m.
We also are aware that persons who are aroused from sleep might not only arouse.their household, but that they would also tend to contact some -
neighbors, friends and relatives in the EPZ. This process of " informal _
notific'ation" was testified to at some length in the Shearon Harris hearing, and the Board does not doubt that such informal notification would occur to some degree. However, the phenomenon cannot be controlled like a stren level or a police car route, and its likely
- effects are difficult to quantify. Therefore, we question whether informal notification should be viewed as a substitute for planned
. notification.
According to testimony in the Shearon Harris case, the siren systems around operating nuclear plants have not been field-tested to determine what percentage of EPZ residents would actually be aroused by their -
activation between midnight and six a.m. Tr. 9935-40. We believe that sirne such testing would be prudent and merits Comission consideration. ,
Respectfully submitted.
l ,
0e di
(
l JysL.Kelley l
LMM DpJamesH. Carp $hter
./
% d, NM Glenn D. Eright 47 I
- cc: H. Plaine. General Counsel
- 5. Chilk. Secretary i
Shearon Harris Service List
_..__ _ ___ _.___ _ ,__ _ ~ _ _ _ _ _ _
,. ENCLOSURE 2
.- t- Federal Emergency Management Agency Washington, D.C. 20472 DEC 6 GB5
~~
MSGANDEM FGts Dave Natthews Osief Baergency Preparedness Branch U.s tory canaission FEM: rt ruon ~ ,
Osief Technological Hazards Division f StBJECT: Nighttime Energency Notification 5
1his memorandsa transnits (see attachnent) FEMA's response to the Atomic Safety and Licensing Board's (ASIS) November 19, 1985 memoran&su notifying the n==fssion of possible generic safety probleas irwolving nighttime energency notification.
7 e
PURPOSE:
The numbers of the Asta presiding over the application of Carolina Power and Light Co. Jo al. for an operating license for the Shearon Harris facility infonned the Ennissioners, in a letter dated November 19, 1985, of " evidence of possible generic safety problene irwolving nighttine emergency notification of residents in the plume energency planning nones surrounding nuclear power plants." This disaassion presents the Federal Snorgency Managerient Agency's (FEMA's) evaluation of the evidence presented in this letter and its conclusions concerning the existence of a possible generic safety problem.
BhCRGROLMD:
The Federal Bnergency Managenent Agency (FSUL), as the lead Federal agency in a Menorandun of Urx!erstanding 000) with the Nuclear Regulatory Cannission
, (NRC), is responsible for evaluating and approving pragt alert and notifi-cation systems that are installed arotmd consercial nuclear poter plants throughout the United States. These systens have been, or are being, installed within the terMaile Dnergency Planning Ione (EPI) of each nuclear power plant'by cogerative agreenents between NRC licensees and State and local goverrnents to provide a mechanien for rapidly alerting the p@lic in the event of an energency at the rmaclear power plant. IRC liconeses were mandated by the Imc to have alert and notification systens installed
, for all gerating nuclear power plants by February 1,1982, (originally July 1, 1981), or face enforcement actions. All nuclear poter plants scheduled to go on line after February 1,1982, sust have an alert and notification systen in place prior to operation.
10 CFR $ 50.47(b)(5) and 44 CFR Part 350 require that "means to provide early notification and clear instruction to the pcpulace within the p1true exp>sure patNay Dnergency Planning zone have been established." 10 CFR Part 50 Appendix E 5 D.3 requires in addition that "The design objective of the pragt p@lic notification systen shall be to have the capability to essentially caglete the initial notification of the p@lic within the :
plume exposure pathway EPZ within about 15 minutes. 1he.use of this
{ notification capability will range fran innodiate notification of the .
! p@lic (within 15 miraates of the time that State and local officials are
- notified that a situation exists requiring urgent action) to the more i likely events @ere there is s@stantial time available for the State and ,
local governnental officials to make a judpent whether or not to activate the p@lic notification systen."
In 1980, NRC and FEMA pelished final pidance in NLREG-0654AIMA-REP-1 Rev.1, " Criteria for Preparation and Evaluation of Radiological Bnemency Response Plans and Preparedness in Support of Nuclear Pcwor Plants" which defined in technical terms, how the regulatory requirenants in 10 CFR 50 i
where to be not.
In 1983, FEMA p@lished interim widance in FEMA-43 " Standard (kalde for the Evaluation of Alert and Notificatic Systems for Nuclear Power Plants" l which organized the acceptance criteria of NtREG-0654 NEMA-REP-1, Rev.1 into a format that could be used by the utilities to doctment their alert
to and notification systene installations for review and appewal under FEMA's 44 CFR 350 process. FEMA-43 did not change the design criteria established in ERm-0654/FBUHLEP-1, Rev.1.
To date, over 60 plants have stbmitted their prapt alert and notification syste design plans, as prescribed in FEMA-43, for review by FBlA.
FBlA expects to ocuplete its twiew of these sites, including findings to the IstC under the MXJ, by the end of calendar 1986.
IS8Wl8:
the Asta ==hars, in their letter, cited the ibliowing evidence as the basis
!. of their concern:
"1) The FDIA design criteria provide fbr siren sound coverage of 10dB(a) above ambient noise levels or a minimum of 60dB(c).
l ,,
- 2) The ' FEMA-43' rwiews of siren systen designs fbr cperating
- l. nuclear facilities are based on sunner daytine conditions.
~
Such rwiews give no consideration to factors only applicable at night-i.e., almost everyone is indoors and asleep, many with the windows ciceed. 1hese factors are not offset by l greater sound propagation at ni$ t.
i
- 3) The testimony is that, for a house with the windows ciceed (central air conditioning) and an outdoor siren sound level of 60dB, the probability of arousal fran sleep is essentially ,
zero. With the windows open, the probability is 7-84.
l (Tr. 9650).
i l 4) The sound levels necessary for high gobability of arousal -
l are substantially above the FDIA mininun guidance. Pbr exangle, a 50% probability of arousal d an individual ,
in a house with the windows closed requires outdoor sound -
levels of 90-99 decibels (Tr. 9927). The wide range in this
- estimate reflect.s the inperfect knowledge of siren arousal I capability, since direct tests have not been conducted, at i
least in the United States.
- 5) Pbr the Harris asstmed stener scenario--including 364 of the houses in the EP2 with no air conditioning (windows open)-
arousal is estimated as approximately 700. Asstning the l
- accuracy and acceptability of that estimate, lower probable l arousal rates in other climatic areas of the United States i
nevertheless suggest possible generic safety concerne--per-ticularly in the winter season, then nors of the population may sleep with the windows closed.
i i
i.' , ,
3_
- 6) Me further note that overall arcusal percentages for an EPE can mask the fact that, in areas of moderate housing density but with a fair nsaber of houses sore than one mile fra a siren, a stbetantial percentage of the houses would have an arousal probability of less than 50%. Ibr example, at siren 70 in the Harris EP2, about 100 houset of about 160 in that area, or 634, are in the 70-80dB area. 1he grobability of arousing an individual in those houses with the windows closed is approminately 304, and is 55% for household arousal with two residents. If these houses correspond to U.S. coverages,18% would have one resident, 30% would have two reridents, and the average probability of arousing the household would be 434. 1hus,
, although the risk of not being aroused, averaged over the ,
EP2, may be roughly 304, in same areas appecuinately 50% of I the houses may have a risk of non-arousal of roughly 574.
- 7) Walso are aware that persons who are aroused from sleep might not only arouse their household, but that they would also tend to contact some neighbors, friends and relatives in the EP2. His process of " informal notificatiorf was testified to at same length in the thearon Harris hearing, and the Board does not doubt that such informal rx,tification would occur to see degree. However, the phencuenon cannot
! . be controlled like a siren level or a police car route, and its likely effects are difficult to quantify. Therefore, we question whether infonnel notification should be viewed as a substitute for planned notification."
! FE m EVALUATION Issue 01. For acceptance of the licensee's or applicant's siren systen, -
FDE-43 requires that the design report demonstrate that either "(a) tt.2 expected siren sound level generally exceeds 70dBC where the population .
density exceeds 2,000 persons per square mile and 60dBC in other inhabited .-
areas or (b) the expected siren mund level generally exceeds the overage measured daytine anblent sound levels by 108." It should be noted that these are minimun requirements and, in fact, cost effective siren systen design,
- ich locates sirens within population centers, results in many households being exposed siren sound levels that significantly exceed these l mininans. For exsiple, the Sheaton Harris siren systen, which is not atypical, provides sound levels in excess of 80dBC to ainost 60% of the residence in the EP2, under typical stamer nighttine conditions.
l Issue 92. The FEMA-43 reviews are based upon simmer daytime conditions only to the extent that sumer daytine conditions are used to model sound propa-l gation. This approad is taken because siren sound propagation is least l effective ducirg these conditions. Therefore an analysis that davonstrates i
l l
i
. that the FMA-43 and NL5tBG-0654/MMA4tEP-1, Rev. I requirements are set under average suuner daytime conditions provides reasonable assurance that they will be met in the event of an actual energency at any time of year. The attenuation of structures, eether windows are open or closed and the need to provide a signal loud enough to alert people was considered in establishing the ministan acceptable sound pressze levels. In particular, as NLELE-0654/
FEMMEP-1, Dev. I states: ,,
! "The los differential above daytime anbient is intended to i
.. provide a distinguishable signal ins of average residential construction mder storage conditions ...research has shown
, that a person is capable of being alerted by such a difforen-tial above or below the background anbient in the case.cf a
- predominantly narrow band 300 to 800 Hz emitted by large f
sirens."
Issue 93. 1he cited tastimony is not in agreenent with FEMA expert witness testimony which indicates that the probability of arousing an individual from ,
sleep under the ciramstances cited with windows closed, is approstimately 204 ~
and with wi'ndous open is appecstinately 304. Using the mix of one and two -
.l resident households cited as representative of the U.S. by the board asmbers, this corresponds to an amrage household probability of direct (i.e., by siren) i' ,
arcuy.
open ofIt336 for houses should with be noted # indows thac these direct closedarcusal and 47% for housesare probabilities withfor windows ;
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- households at the minimian acceptable sound levels and, mder actuni ciraam-i stances, would be supplanented by informal notification by other alerted residents [see evaluation of issue 97].
Issue 94. Again the cited testinony is not in agewenent with FEMA expert witness testimony that indicates that about 85dB wculd provide a 50%
probability of direct arousal of a sleeping individual. Using the mix of one and two resident Museholds cited as representative by the board mosers, this 85d8 sound level would be expected to arouse about 70% of all houseM1ds. As noted in the discussion of issue 3, this direct arousal would be supplemented by infonnal notification by other alerted residents.
Issue 95. The arousal estimated cited is fbr direct arousal only. Both FEMA- l and applicant expert witnesses testified that the inclusion of informal arousal nochaniens (see response to issue 07] would increase the percentage at the population aroused to approstimately 904.
Issue 96. FEMA agrees with the otmervation that, if the overall direct arousal percentage for an EPZ is 70% then there will be households for which j
the direct arousal rate is less than 50%. However, it should be noted that the letter's treatment of multi-resident hcuseholds is improper since it l A Daytime anbient is used because it is higher than nighttime anbient.
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ignores the 52% of the households nationwh with three or more reshnts.
If those are treated (conservatively] as two resident households, the correct average probability of arousing the household would be 50.54. 1hus, although FEMA agrees with the general observation that there will be households with direct arousal probabilities lower than 50%, we note that the cited figures ,
do not provide a s@ porting esseple. i
. Issue 97 In disregarding infonnal alerting nedanians, the board surnbers 1 are failing to conske a phenmenon which is known to occtr and for which quantitative date have been obtained on analogcus occasions. . The Mtc makes predictive findings, often on the basis of engineering judgerent, for other phonamena that are known to happen but are not strictly controllable (e.g.,
accidents). It in FEMA's judgment that conshration of informal alerting mo&anians, based upon quantification of actual experience by disaster
- . sociologists, is appropriat.e so long as such conshration incorporates
. suitable conservatism. In addition, FEMA notes that infonnal notification sachanisms have been recognised by NRC boards in other hearings. See go. .
' Juk D P r (Catawba Itaclear Station, Units 1 and 2), IBP-84-37, 20 N.R.C.
933, 984) (Finding 10); Southern California Edison Conpany (San Onofre ~
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j Nuclear Generating Station, Units 2 and 3), IAP-82-46,15 N.R.C.1531, 1534-35 (1982).
l, CONCLUBIQ4:
Evaluation of the evidence presented in the Novesaber 19, 1985, letter to the Corsaissioners frcen the marbers of the ASIA presiding over the application of
! Carolina Power and Light Co. et al. for an gerating license for the Shearon Harris facility does not indi Ete that there are possible generic safety l problens involving nighttime emergency notification of residents in the plusas ;
i emergency planning mones surrounding nuclear power plants. The evaluation 1 criteria in NLREG-0654/ FEMA 4tEP-1, Rev. I and the acceptance criteria in
! FEMA-43 are intended to answe that alert and notification systems that are designed and evaluated in accordance with these criteria meet letC's 10 CFR 50 Appendix E design objective "to have the capability to essentially caplete
- the initial notification of the p&lic within the plume exposure pathway .
within about 15 minutes.* The siren system for the Shearon Harris Nuclear ,
Power Plant, thich is not atypical of the siren systems at other nuclear power plants, tes designed, evaluated, and found to be acceptable under these criteria. The conclusion reached in FEMA's study, in response to the hearing contention, that this siren systen can be expected to arouse and alert approximately 90% of the EPE residents during a nighttime energency serves to confirm FEMA's judgement that siren systems designed and evaluated in accordance with NLREG-0654/ FEMA-REP-1, Rev. I and FEMA-43 meet the Mtc requirements for both daytine and nighttime alerting.
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ENCLOSURE 3 RE0VIREMENTS AND GUIDANCE RELATING TO PUELIC ALERT AND NOTIFICATION SY5TEMS
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The requirement for a public alert and notification system is set forth in 10 C.F.R. 550.47(b)(5) of the Commission's regulations. This regulation
! requires that: " . . . means to provide early notification and clear instruc-tiontothepopulacewithintheplumeexposurepathwayEmergencV*PlanningZone l
have been estaolished." Appendix E to 10 C.F.R. Part 50 establishes the mini-mun requirements for emergency plans in order to attain an acceptable state of emergency preparedness. 10 C.F.R. Part 50, Appendix E SIV. In addition, the Commission has established a design objective for the prompt public notification
! system; this design objective is that the system ". . . shall.have the capa-
! bility to essentially complete the initial notification of the public within the plume exposure pathway EPZ within about 15 minutes." 10 C.F.R. Part 50, Appendix E SIV.D.3.
The responsibility for determining the adequacy of offsite emergency plans, including the adequacy of the prompt Federal Emefgency Management AFEMA). ency (public notification See, Memorandum system, rests~~with the of Understanding between NRC and FEMA, 50 Fed. . 15485 (AprT F18, 1985). FEMA makes its l determination of the adequacy o offsite emergency plans by evaluating their compliance with the standards and criteria of NUREG-0654/ FEMA-REP-1, Rev. 1 "CriteriaforPreparationandEvaluationofRadiologicalEmergencyResponsePlans j
and Preparedness in Support of Nuclear Power Plants (November 1980). NUREG-0654 l contains acceptance criteria for a prompt public notification system. NUREG-0654 Appendix 3, 58. The minimum acceptable design objectives for coverage by a j prompt public notification system are:
(a) Capability for providing both an alert signal and an informational or instructional message i to the population on an area wide basis throughout the 10-mile EPZ, within 15 minutes.
(b) The initial notification system will assure ,
direct coverage of essentially 100% of the .
population within 5 miles c. the site.
(c) Special arrangements will be made to assure 100% coverage within 45 minutes of the popu-lation who may not have received the initial notification within the entire plume exposure EPZ.
NUREG-0654, Appendix 3 at 3-3 1/ The acceptance criteria of NUREG-0654 have been further clarified by FEMA-43 ".Standard Guide for the Evaluation of Alert and NotificationSystemsforNuclearPowerPlants."
,l/ Appendix 3alsocontainsspecificacceptancecriteriarelatingtosirens and siren systems. These criteria are discussed further in the enclosed FEMA response.
WREG-0654 notes, however, that it is a design objective to meet the criteria of
$8 of Appendix 3, and that this does not mean that there is a ". . . guarantee that early notification can be provided for everyone with 1005 assurance or that the system when tested under actual field conditions will meet the design objec-tive in all cases." WREG-0654 at 3-1. This statement is consistent with the Commission's view of the effect of the actual operation of such a system. As the Commission stated, "The Commission recognizes that not every,. individual would necessarily be reached by the actual operation of such a system under all conditions of system use." 45 F,e,d. e R,eg.
e 55402 (August 19,1980).
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