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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M6631999-10-19019 October 1999 Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted ML20217K9241999-10-14014 October 1999 Forwards Amend 234 to License DPR-56 & Se.Amend Consists of Changes to TS in Response to Application & Suppls ,1001 & 06,which Will Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Mining Sys ML20217F7391999-10-14014 October 1999 Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests ML20217F6841999-10-13013 October 1999 Forwards Senior Reactor Operator Initial Exam Repts 50-277/99-302(OL) & 50-278/99-302(OL) Conducted on 990913- 16.All Applicants Passed All Portions of Exam ML20217F3021999-10-12012 October 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at PBAPS Have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying Licenses, ML20217E7451999-10-0808 October 1999 Forwards Response to NRC 990820 RAI Concerning Proposed Alternatives Associated with Third ten-yr Interval ISI Program for Pbaps,Units 2 & 3 ML20217B7701999-10-0606 October 1999 Submits Corrected Info to NRC 980528 RAI Re Util Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20217B9151999-10-0606 October 1999 Provides Clarifying Info to Enable NRC to Complete Review of License Change Request ECR 98-01802,re Changes Necessary to Support Installation of Digital Pr Neutron Monitoring & Incorporate long-term T/H Stability Solution Hardware ML20217C4141999-10-0606 October 1999 Forwards Response to NRC 981109 RAI Re Resolution of USI A-46 for Pbaps.Proprietary Excerpts from GIP-2,Ref 25 Results of BWR Trial Plant Review Section 8 Also Encl. Proprietary Excerpts Withheld ML20217B3181999-10-0505 October 1999 Advises That Info Submitted in 990712 Application,Which Contained Attachment Entitled, Addl Info Re Cycle Spec SLMCPR for Peach Bottom 3 Cycle 13,dtd 990609, with Affidavit,Will Be Withheld from Public Disclosure ML20217B4051999-10-0505 October 1999 Forwards Amend 233 to License DPR-56 & Safety Evaluation. Amend Changes Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Report 05000278/LER-1999-004, Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv)1999-10-0101 October 1999 Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv) ML20217B8891999-10-0101 October 1999 Forwards Response to RAI Re Request to Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term,thermal-hydraulic Stability Solution Hardware. Revised TS Table 3.3.2.1-1 Encl ML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20212J6851999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Peach Bottom Atomic Power Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl New Insps Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212J5751999-09-28028 September 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990913-16 at Licensee Facility.Without Encls ML20216J0191999-09-27027 September 1999 Forwards Request for Addl Info Re Util 990301 Request to Support Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware,For Plant ML20212H6171999-09-24024 September 1999 Forwards Rev 2 to COLR for Pbaps,Unit 2,Reload 12,Cycle 13, IAW TS Section 5.6.5.d.Rept Incorporates Revised Single Loop Operation MAPLHGR Flow Multiplier ML20216H6451999-09-24024 September 1999 Forwards Notice of Withdrawal of Util 990806 Application for Amends to Fols DPR-44 & DPR-56.Proposed Change Would Have Involved Temporary Change to Increase Limit for Average Water Temp of Normal Heat Sink ML20212H5431999-09-24024 September 1999 Informs of Decision to Inspect H-3 & H-4 Shroud Welds During Upcoming 3R12 Outage Scheduled to Begin Late Sept 1999 ML20216H6751999-09-24024 September 1999 Forwards Amends 229 & 232 to Licenses DPR-44 & DPR-56, Respectively & Ser.Amends Will Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by SR 3.9.1.1 ML20216F8811999-09-23023 September 1999 Withdraws 990806 Exigent License Change Application.Tech Spec Change to Allow Continued Power Operation with Elevated Cooling Water Temps During Potentially Extreme Weather Conditions No Longer Needed Due to Favorable Weather ML20212E8661999-09-22022 September 1999 Discusses GL 98-01 Y2K Readiness of Computer Sys at NPPs & Supplement 1 & PECO Response for PBAPS Dtd 990630. Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient During Y2K Transition ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212D1191999-09-17017 September 1999 Forwards SE Re Proposed Alternatives to ASME Section XI Requirements for Containment Inservice Insp Program at Plant,Units 2 & 3 ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment ML20211P2961999-09-0707 September 1999 Provides Authorization to Administer NRC Approved Initial Written Exams to Listed Applicants on 990913 at Peach Bottom Npp,Delta,Pennsylvania ML20211K7031999-08-30030 August 1999 Forwards Response to NRC 990826 RAI Re License Change Application ECR 99-01255,revising TSs 2.1.1.2 & 5.6.5 ML20211E6941999-08-26026 August 1999 Forwards Request for Addl Info Re Min Critical Power Ratio. Response Should Be Submitted within 30 Days of Ltr Receipt ML20211Q4491999-08-25025 August 1999 Responds to Re Changes to PBAPS Physical Security Plan,Safeguards Contingency Plan & Guard Training & Qualification Plan Identified as Revs 13,11 & 9, Respectively.No NRC Approval Is Required,Per 10CFR50.54(p) ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info ML20211D5421999-08-23023 August 1999 Forwards Amends 228 & 231 to Licenses DPR-44 & DPR-56, Respectively & Se.Amends Revise TSs to Correct Typographical & Editorial Errors Introduced in TSs by Previous Amends ML20211A9721999-08-20020 August 1999 Forwards Request for Addl Info Re Third 10-year Interval Inservice (ISI) Insp Program Plan for Plant,Units 2 & 3 ML20210T5451999-08-12012 August 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Licensee Request for Amends to Plant. Amends Consist of Changes to TS to Correct Typos & Editorial Errors Introduced in TS by Previous Amends ML20210P8321999-08-11011 August 1999 Responds to NRC 990715 Telcon Re Util 990217 Submittal of Proposed Alternatives to Requirements of 10CFR50.55a(g)(6)(ii)(B)(1) Re Containment Inservice Insp Program ML20210P8151999-08-11011 August 1999 Forwards Final Pages for Pbaps,Unit 2 & 3 OLs Re License Change Application ECR 99-01497,which Reflects Change in Corporate Structure at Pse&G ML20211B6521999-08-10010 August 1999 Informs That Dp Lewis,License SOP-11247,has Been Permanently Reassigned & No Longer Requires License,Per 10CFR50.74.Util Requests That Subject Individual Be Removed from List of License Holders ML20210P1561999-08-10010 August 1999 Submits Response to Requests for Addl Info Re GL 92-01,rev 1,Suppl 1, Rv Structural Integrity, for Pbap,Units 1 & 2. NRC Will Assume That Data Entered Into Rvid Are Acceptable for Plants,If Staff Does Not Receive Comments by 990901 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210N7831999-08-0909 August 1999 Forwards Copy of Notice of Consideration of Issuance of Amends to Fols,Proposed NSHC Determination & Opportunity for Hearing, Re 990806 Request for License Amends.Amends Incorporate Note Into PBAPS TS to Permit One Time Exemption ML20210P0801999-08-0404 August 1999 Forwards Initial Exam Repts 50-277/99-301 & 50-278/99-301 on 990702-14 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999 Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls ML20210J0161999-07-30030 July 1999 Forwards Copy of Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amends Re 990723 Application ML20210H5341999-07-27027 July 1999 Forwards Insp Repts 50-277/99-05 & 50-278/99-05 on 990518- 0628.NRC Determined That Two Severity Level IV Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20210F3731999-07-23023 July 1999 Submits Confirmation That,Iaw 10CFR50.80,PSE&G Is Requesting NRC Approval of Transfer of Ownership Interests in PBAPS, Units to New Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20210E5811999-07-21021 July 1999 Forwards Final Tech Specs Pages for License Change Application.Proposed Change Will Revise Tech Specs to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062F2241990-11-0909 November 1990 Forwards SSFI Repts 50-277/90-80 & 50-278/90-80 on 900917- 1003 Conducted by Corrective Action Review Team.Corrective Actions Generally Acceptable W/Some Weaknesses Noted IR 05000277/19900191990-11-0707 November 1990 Forwards Exam Repts 50-277/90-19OL & 50-278/90-19OL Administered During Wk of 900924 ML20062D5381990-11-0606 November 1990 Forwards List of Unimplemented Generic Safety Issues at Facilities,Per Generic Ltr 90-04 ML20058G1541990-10-31031 October 1990 Requests That Util Furnish Ref Matl Listed in Encl 1, Ref Matl Requirements, for Administration of Licensing Exams & Evaluation of Requalification Program Scheduled for Wk of 910304 ML20062C7451990-10-26026 October 1990 Forwards Safety Evaluation Accepting Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow ML20058D2371990-10-26026 October 1990 Informs of Impending fitness-for-duty Program Insp & Requests 10CFR26.20 Required Policies & Procedures ML20062B8211990-10-11011 October 1990 Forwards Final SALP Repts 50-277/89-99 & 50-278/89-99 for Jul 1989 to May 1990.Improvements Noted ML20062A0651990-10-0505 October 1990 Forwards Safety Insp Repts 50-277/90-17 & 50-278/90-17 on 900814-0924.One Violation Noted ML20059N5841990-10-0303 October 1990 Informs That Issuance of Senior Reactor Operator Licenses, for Fuel Handling Only,For More than One Facility Conditionally Acceptable ML20059M6561990-09-22022 September 1990 Ack Receipt of Util Re Corrective Actions Taken in Response to Insp Repts 50-277/90-13 & 50-278/90-13 ML20059J1971990-09-13013 September 1990 Ack Receipt of & Payment for Civil Penalty Proposed by NRC in in Amount of $75,000 ML20059H0701990-09-11011 September 1990 Requests Addl Info Re Audit Rept Distribution,Per 890711 & 900420 Application Request for Removal of Organization Charts from Tech Spec Per Guidance Provided in Generic Ltr 88-06 & Miscellaneous Administrative Changes ML20059K7211990-09-0606 September 1990 Forwards Safety Insp Repts 50-277/90-15 & 50-278/90-15 on 900723-27 & Notice of Violation ML20056B2691990-08-23023 August 1990 Forwards Request for Addl Info Re 880126 Application for Amends to Licenses,Revising Tech Specs to Provide More Restrictive Limits on Emergency Svc Water Sys.Response Should Be Provided within 60 Days of Ltr Receipt ML20059A6581990-08-16016 August 1990 Requests Discussion of Measures Considered &/Or Taken to Reduce Amount of Time Needed to Obtain Effluent Sample Analyses Results,Per 870121 Application for License Amends to Licenses DPR-44 & DPR-56 ML20058N0531990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Managers Forum ML20056A5011990-07-30030 July 1990 Forwards Safety Insp Repts 50-277/90-13 & 50-278/90-13 on 900516-0702 & Notice of Violation ML20055E1711990-07-0606 July 1990 Requests That Licensee Provide Data on Channel Box Bow Vs Exposure Associated W/Methods Used to Account for Effects of Channel Box Bow During Second Bundle Lifetime Channel Boxes, Per 900425 Response to Bulletin 90-002,within 30 Days ML20055E9611990-07-0505 July 1990 Requests Addl Info Re Util 891228 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance ML20055D0721990-06-27027 June 1990 Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wks of 900924 & 1001.Ref Matls,Listed on Encl,Should Be Provided by 900724 ML20055C8761990-06-15015 June 1990 Forwards Safety Insp Repts 50-277/90-10 & 50-278/90-10 on 900403-0515.No Violations Noted.Increased Mgt Attention Warranted to Ensure That Instances of Failure to Complete Surveillance Testing Identified & Corrected ML20059M8671990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248H8041989-10-0505 October 1989 Grants Termination of Requirements Set Forth in Section VA of Order to Permit Operation of Both Units at Full Power ML20248H1361989-10-0303 October 1989 Forwards Unexecuted Amend 22 to Indemnity Agreement B-28, Reflecting Changes to 10CFR140 Re Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20248G2291989-09-29029 September 1989 Forwards Safety Insp Repts 50-277/89-21 & 50-278/89-21 on 890901.No Violations Noted.Insp Concluded That Improvements in Radiological Controls Program Have Been Slow.Addl Mgt Attention to Program Warranted ML20248E2351989-09-27027 September 1989 Forwards Summary of Issues Re Verification of Quality of Certain Types of Activities Performed for Mods at Facility. Mods Cover Automatic Depressurization Sys/Msiv Instrument Nitrogen Accumulator & Svc Water Pipe Replacement ML20248A4111989-09-25025 September 1989 Forwards Restart Team Safety Insp Repts 50-277/89-20 & 50-278/89-20 on 890730-0902.No Violations Noted ML20248E5581989-09-21021 September 1989 Forwards SER Supporting Use of Frosstey Fuel Performance Code Described in Topical Rept PECo-FMS-003, Steady-State Fuel Performance Methods Rept. Addl Applications of Subj Code Require NRC Review & Approval ML20247L9331989-09-13013 September 1989 Advises That Written Reactor Operator Licensing Exams Scheduled on 891211 & Operating Exams on 891212-15.Ref Matl Listed on Encl Should Be Provided by 891001.Simulator Exam Scenario Should Be Retained Until Exam Process Completed ML20247E8491989-09-0707 September 1989 Forwards SALP Board Repts 50-277/88-99 & 50-278/88-99 for Aug 1988 - June 1989 ML20247B8711989-09-0101 September 1989 Forwards Restart Safety Insp Repts 50-277/89-19 & 50-278/89-19 on 890618-0729.No Violations Noted ML20246E0241989-08-21021 August 1989 Forwards Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 2.1 (Parts 1 & 2) Re Components Required to Trip Reactor & Interface W/Nmss Vendors or Vendors of Each Component,Respectively ML20246J4571989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purpose of Setting Occupational Exposure Limits,Per Info Notice 81-26.Util Should Ensure That Procedures Incorporate Applicable Dose Limits in 10CFR20 ML20248D0261989-08-0101 August 1989 Confirms 890714 Telcon & Requests Assistance & Cooperation in Review of Allegation Involving Plant.Util Should Fully Review Allegation & Take Action in Accordance W/Encl Instructions.Encl Withheld (Ref 10CFR2.790) ML20248C0421989-07-28028 July 1989 Responds to Util in Response to NRC Re Potential Violation of 10CFR50.7.Review of Record Indicates That Violation May Have Occurred.No Further Action Warranted as Case Settled Prior to Investigation ML20247E3191989-07-21021 July 1989 Relaxes Requirements of Section V.A of 870331 Order to Permit Operation of Unit 2 to Full Power ML20246F6121989-07-0606 July 1989 Forwards NRR to Ecology Ctr of Southern California Re Petition to Fix or Close All Nuclear Power Reactors Designed by Ge.Petition Being Treated Under 10CFR2.206 ML20246C3681989-06-30030 June 1989 Forwards Safety Evaluation Supporting 871019 Response to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability, On-Line Testing of Reactor Trip Sys. Existing Test Intervals Consistent W/High Reactor Trip Sys Availability ML20246B9561989-06-28028 June 1989 Forwards Annual Emergency Preparedness Exercise Safety Insp Repts 50-277/89-17 & 50-278/89-17 on 890614.No Violations Noted ML20246B9161989-06-28028 June 1989 Advises That Requirements of 870331 Order Relaxed to Permit Unit 2 Operation Not to Exceed 70% Full Power,In Accordance W/Section Ve of Order ML20246A0001989-06-26026 June 1989 Forwards Restart Safety Insp Repts 50-277/89-16 & 50-278/89-16 on 890507-0617 & Notice of Violation ML20245C9671989-06-16016 June 1989 Requests Addl Info on Response to Generic Ltr 88-01 on IGSCC in Matls.Response Should Be Provided within 60 Days of Receipt of Ltr ML20247M7731989-05-26026 May 1989 Forwards Director'S Decision Re Ohio Citizens for Responsible Energy 10CFR2.206 Petition Re 880309 Power Oscillation Event at Lasalle,Unit 2 ML20247N8481989-05-25025 May 1989 Forwards Safety Insp Repts 50-277/89-12 & 50-278/89-12 on 890410-13.No Violations Noted ML20247L6481989-05-24024 May 1989 Forwards Restart Safety Insp Repts 50-277/89-15 & 50-278/89-15 on 890402-0506.No Violations Noted.Two Issues Remain Unresolved,Including HPCI Sys Wiring Error That Occurred During Plant Mod Installed in Mar & Apr 1989 ML20247K9191989-05-18018 May 1989 Forwards Electrical Insp Repts 50-277/89-13 & 50-278/89-13 on 890405-07 & 13.Issues to Be Resolved Before Unit 3 Restart Listed.No Violations Noted ML20246N3401989-05-10010 May 1989 Advises That Written Senior Reactor Operator Licensing Exams Scheduled for 890814 & Operating Exams Scheduled for Wk of 890918.Ref Matls Listed on Encl Should Be Provided by 890601 ML20246Q3711989-05-0303 May 1989 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Agenda & Info Re Lodging Arrangements Encl IR 05000277/19870301989-04-26026 April 1989 Ack Receipt of Re Steps Taken to Correct Violations Noted in Insp Repts 50-277/87-30 & 50-278/87-30 ML20245F3181989-04-26026 April 1989 Requests Encl Addl Info Re Util 890310 Application for Amends to Licenses DPR-44 & DPR-56 Re Intermediate Detector Not in Startup Position for Calibr 1990-09-06
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M6631999-10-19019 October 1999 Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted ML20217K9241999-10-14014 October 1999 Forwards Amend 234 to License DPR-56 & Se.Amend Consists of Changes to TS in Response to Application & Suppls ,1001 & 06,which Will Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Mining Sys ML20217F7391999-10-14014 October 1999 Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests ML20217F6841999-10-13013 October 1999 Forwards Senior Reactor Operator Initial Exam Repts 50-277/99-302(OL) & 50-278/99-302(OL) Conducted on 990913- 16.All Applicants Passed All Portions of Exam ML20217B4051999-10-0505 October 1999 Forwards Amend 233 to License DPR-56 & Safety Evaluation. Amend Changes Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Report ML20217B3181999-10-0505 October 1999 Advises That Info Submitted in 990712 Application,Which Contained Attachment Entitled, Addl Info Re Cycle Spec SLMCPR for Peach Bottom 3 Cycle 13,dtd 990609, with Affidavit,Will Be Withheld from Public Disclosure ML20212J6851999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Peach Bottom Atomic Power Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl New Insps Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20212J5751999-09-28028 September 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990913-16 at Licensee Facility.Without Encls ML20216J0191999-09-27027 September 1999 Forwards Request for Addl Info Re Util 990301 Request to Support Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware,For Plant ML20216H6751999-09-24024 September 1999 Forwards Amends 229 & 232 to Licenses DPR-44 & DPR-56, Respectively & Ser.Amends Will Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by SR 3.9.1.1 ML20216H6451999-09-24024 September 1999 Forwards Notice of Withdrawal of Util 990806 Application for Amends to Fols DPR-44 & DPR-56.Proposed Change Would Have Involved Temporary Change to Increase Limit for Average Water Temp of Normal Heat Sink ML20212E8661999-09-22022 September 1999 Discusses GL 98-01 Y2K Readiness of Computer Sys at NPPs & Supplement 1 & PECO Response for PBAPS Dtd 990630. Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient During Y2K Transition ML20212D1191999-09-17017 September 1999 Forwards SE Re Proposed Alternatives to ASME Section XI Requirements for Containment Inservice Insp Program at Plant,Units 2 & 3 ML20211P2961999-09-0707 September 1999 Provides Authorization to Administer NRC Approved Initial Written Exams to Listed Applicants on 990913 at Peach Bottom Npp,Delta,Pennsylvania ML20211E6941999-08-26026 August 1999 Forwards Request for Addl Info Re Min Critical Power Ratio. Response Should Be Submitted within 30 Days of Ltr Receipt ML20211Q4491999-08-25025 August 1999 Responds to Re Changes to PBAPS Physical Security Plan,Safeguards Contingency Plan & Guard Training & Qualification Plan Identified as Revs 13,11 & 9, Respectively.No NRC Approval Is Required,Per 10CFR50.54(p) ML20211D5421999-08-23023 August 1999 Forwards Amends 228 & 231 to Licenses DPR-44 & DPR-56, Respectively & Se.Amends Revise TSs to Correct Typographical & Editorial Errors Introduced in TSs by Previous Amends ML20211A9721999-08-20020 August 1999 Forwards Request for Addl Info Re Third 10-year Interval Inservice (ISI) Insp Program Plan for Plant,Units 2 & 3 ML20210T5451999-08-12012 August 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Licensee Request for Amends to Plant. Amends Consist of Changes to TS to Correct Typos & Editorial Errors Introduced in TS by Previous Amends ML20210P1561999-08-10010 August 1999 Submits Response to Requests for Addl Info Re GL 92-01,rev 1,Suppl 1, Rv Structural Integrity, for Pbap,Units 1 & 2. NRC Will Assume That Data Entered Into Rvid Are Acceptable for Plants,If Staff Does Not Receive Comments by 990901 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210N7831999-08-0909 August 1999 Forwards Copy of Notice of Consideration of Issuance of Amends to Fols,Proposed NSHC Determination & Opportunity for Hearing, Re 990806 Request for License Amends.Amends Incorporate Note Into PBAPS TS to Permit One Time Exemption ML20210P0801999-08-0404 August 1999 Forwards Initial Exam Repts 50-277/99-301 & 50-278/99-301 on 990702-14 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999 Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls ML20210J0161999-07-30030 July 1999 Forwards Copy of Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amends Re 990723 Application ML20210H5341999-07-27027 July 1999 Forwards Insp Repts 50-277/99-05 & 50-278/99-05 on 990518- 0628.NRC Determined That Two Severity Level IV Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209F2461999-07-15015 July 1999 Request Addl Info Re Relief Request CRR-01 Through CRR-11 for Plant,Units 2 & 3.RAI Undtd ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195K2251999-06-11011 June 1999 Forwards Insp Repts 50-277/99-04 & 50-278/99-04 on 990405- 0517.One Severity Level IV Violation of NRC Requirements Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20207G2051999-06-0707 June 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Reorganization Chart Encl ML20207B8381999-05-24024 May 1999 Forwards FEMA Final Exercise Rept for Peach Bottom Atomic Power Station Plume Exposure Pathway Exercise Conducted on 981117.One Deficiency & 27 Areas Requiring Corrective Actions Identified ML20207A0541999-05-17017 May 1999 Acks 990512 & 14 Telcons with Licensee Re Util Request That Rev 8 of NUREG-1021, OL Exam Stds for Power Reactors Be Followed Rather than Interim Rev 8 for Exams in Sept 1999. Request Acceptable ML20206K2231999-05-0606 May 1999 Informs That Author Authorized to Exercise Discretion & Not Issue NOV or Civil Penalty Re Violation Util Identified Involving Unit 2 Rod Block Monitoring Sys Being Inoperable for 29 of 185 Control Rods ML20206K1921999-05-0606 May 1999 Discusses 990503 Telcon Between J Williams & B Bierly Re Arrangements Made for Administration of Licensing Exam at Peach Bottom Facility During Week of 990913 ML20206A1511999-04-20020 April 1999 Forwards Request for Addl Info Re Util 980514 Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-operated Valves. Response Requested within 90 Days of Ltr Receipt ML20206A2801999-04-20020 April 1999 Discusses Proposed Changes Submitted by PECO on 980416, 981116,990122 & 990211 to Plant Emergency Action Levels (Eals).Eals Incorporate Guidance in NUMARC/NESP-007,Rev 2. SE Supporting Proposed EALs Encl ML20205N1961999-04-0909 April 1999 Informs of NRC Planned Insp Effort Resulting from Peach Bottom Atomic Power Station Plant Performance Review Conducted for Period April 1998 to 990115.Historical Listing of Plant Issues & Insp Plans Through Jan 2000 Encl ML20205K7321999-04-0707 April 1999 Forwards Amends 227 & 230 to FOLs DPR-44 & DPR-56, Respectively.Amends Consist of Changes to TS SRs Re Secondary Containment Doors,In Response to 980204 Application,As Revised by ML20205J0531999-04-0101 April 1999 Ack Receipt of 990326 Notice of Enforcement Discretion Request & Documents Resolution.Notes That E3 EDG Returned to Operable Status on 990327,within 14 Day Completion Time Required by Ts.No Enforcement Discretion Necessary ML20205B9891999-03-25025 March 1999 Forwards Insp Repts 50-277/99-01 & 50-278/99-01 on 990105-0215.Violation Noted & Being Treated as non-cited Violation.Nrc Concluded That Staff Maintained Effective Influents Controls & Effective Security Program ML20203H8101999-02-12012 February 1999 Discusses Completion of Licensing Action for Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in BWR, ML20203H7751999-02-12012 February 1999 Discusses Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, for Peach Bottom Atomic Power Station ML20202J5251999-02-0101 February 1999 Forwards Insp Repts 50-277/98-11 & 50-278/98-11 on 981110- 990104 & Notice of Violation Re Failure to Complete Facility Licensed Operator Requalification Program ML20202J8081999-02-0101 February 1999 Forwards Insp Repts 50-277/98-09 & 50-278/98-09 & Notice of Violation.Insp Focused on Reactor Core Isolation Cooling & 4kV Electrical Distribution Sys Operation Under Normal & Emergency Operation Conditions ML20203A6111999-01-22022 January 1999 Confirms 990115 Conversation Between Mj Williams & P Orphanos Re Arrangements Made for Administration of Licensing Exam at Limerrick Generating Station & Peach Bottom Atomic Power Station During Week of 990705 ML20198P1761998-12-30030 December 1998 Forwards from R Calvan Transmitting FEMA Rept for Spring 1998 Peach Bottom Atomic Power Station Ingestion Exposure Pathway Exercise.No Deficiencies Identified During Exercise Conducted on 980407-09,980506 & 980519-21 ML20198K5911998-12-24024 December 1998 Forwards Emergency Response Data Sys Implementation Documents Which Include Data Point Library Updates for Fermi (Number 268),Peach Bottom (Number 269) & Beaver Valley (Number 270).Without Encls IR 05000277/19980081998-12-21021 December 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-277/98-08 & 50-278/98-08 Issued on 981028 ML20198D4071998-12-16016 December 1998 Forwards Emergency Preparedness Insp Repts 50-277/98-12 & 50-278/98-12 on 981116-19.No Exercise Weaknesses,Safety Concerns or Violations of NRC Requirements Identified 1999-09-07
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JUL 01 % .
Docket Nos. 50-277 50-278 Philadelphia Electric Company ATTN: - Mr. 5. L. Daltroff Vice President Electric Production 2301 Market Street Philadelphia, Pennsylvania 19101 Gentlemen:
This letter transmits the exercise evaluation report from the Federal Emergency Management Agency, Region III, dated May 6, 1985, for the Peach Bottom remedial exercise of April 10, 1985. The remedial exercise was conducted to correct two Category A deficiencies cited at the October 17, 1984 Peach Bottom exercise.
FEMA found that the April 10, 1985 remedial exercise demonstrated that the Category A deficiencies cited during the October 17, 1984 exercise had been corrected and, based on these results, offsite radiological emergency preparedness is adequate to protect the health and safety of the public in the event of an accident at the Peach Bottom Power Station.
If you have any questions concerning this matter please contact me at (215) 337-5208.
Sincerely, 0FliiEa1 signea By:
Terry L. Harpster, Chief Emergency Preparedness Section Division of Radiation Safety and Safeguards Attachments: As Stated cc w/ encl:
R. S. Fleischmanr. Station Superintendent John S. Kemper, Vice President, Engineering and Research A. J. Pietrofitta, General Manager, Power Production Engineering, Atlantic Electric Troy B. Conner, Jr. , Esquire Eugene J. Bradley, Esquire, Assistant General Counsel Raymond L. Hovis, Esquire Thomas Magette, Power Plant Siting, Nuclear Evaluations Public Document Room (PDR)
Local Public Document Room (LPDR) 8507170572 850701 Nuclear Safety Information Center (NSIC) pDR ADOCM 05000277 /
NRC Resident Inspector PDR; b Commonwealth of Pennsylvania i
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0FFICIAL RECORD COPY
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- Philadelphia Electric Company 2 bec w/ encl:
RegionI-DocketRoom(withconcurrences)
.DRP Section Chief D. Vito, RI J..Hawxhurst, RI-FEMA Region III k
~Harpster' 6/)]/85-0FFICIAL RECORD COPY' l
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FEDERAL EMERGENCY MANAGEMENT AGENCY REGION III EXERCISE EVALUATION REPORT FACILITY: Peach Bott e At mic Power Station OPERATOR: Philadelphia Electric Capany LOCATION: Peach Bott a Township, York County, Pennsylvania REPORT DATE: May 6, 1985 EXERCISE DATE: April 10,1985 PARTICIPATING JURISDICTIONS: Lancaster and York Counties Drumore Township, Little Britain Township Fawn Grove Township and Fawn Grove Borough
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TABLE OF CONTENTS Page(s)
EXERCISE
SUMMARY
................................................ 1 OB S E R V ER AS S I G NMEN TS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i i
, EVALUATION CRITERIA.............................................. iii EXERCISE OBJECTIVES.............................................. iv i
SCENARIO / TIME LINE............................................... v DEFIC IENCIES NOTED IN PAST EXERCISES. . . . . . . . . . . . . . . . . . . . . . . . . . . . . vi-viii EXERCISE REP 0RTS................................................ 1-5 Drumore Township E0C......................................... 1-2 Litt l e Bri t ai n Townshi p E0C. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Fawn Grove Borough / Fawn Grove Township E0C................... 4-5
SUMMARY
LIST OF CATEGORY "A" DEFICIENCIES AND RECOMMENDATIONS... 6 r
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EXERCISE StNWARY The remedial exercise held on April 10, 1985 involved the participation of two Lancaster County municipalities and two York County municipalities. The two Lancaster County municipalities, Drumore and Little Britain Townships, did not allow Federal observation of their operations during the October 17, 1984 Peach Bottom Exercise, and thus were considered non-participating. Tne two York County municipalities, Fawn Grove Borough and Fawn Grove Township, which have a joint radiological emergency response plan and operate a joint E0C, demonstrated a number of deficiencies which cummulatively led to the conclusion that emergency preparedness was not adequate to provide a reasonable assurance that appropriate protective measures can be taken to protect the health and safety of the public living in the vicinity of the Peach Bottom Atomic Power Station in the event of a radiological emergency.
Drumore and Little Britain Townships implemented their REP plans quite satisfactorily. Fawn Grove Borough / Fawn Grove Township also implemented their joint REP plan satisfactorily, thus eliminating most of the deficiencies brough to light in the October 1984 exercise.
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OBSERVER ASSIGW9ENTS DRAFT Lancaster County E0C r Drumore Township Janet Lamb i
Lancaster County E0C 4
Little Britain Township James Asher i
York County E0C l Fawn Grove-Township / Fawn Grove Borough and Stewartstown Decontamination Center Joseph Gavin i
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EVALUATION CRITERIA USED The local government's response capabilities during this remedial exercise were evaluated in relationship to the draf t Radiological Emergency Response Plans for each municipality. These plans were developed in accordance with NUREG 0654/ FEMA-REP-1, Rev. 1. " Criteria for Preparedness and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plans," November 1980.
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8 OBJECTIVES OF THE EXERCISE
- 1. To demonstrate the capability of municipal governments to implement emergency response plans to protect the health and safety of people located within the Emergency Planning Zone (EPZ).
- 2. To demonstrate the adequacy of communications systems.
- 3. To demonstrate the operational knowledge and support from elected or appointed public officials.
4 To demonstrate the capability to alert and mobilize people and resources in a timely manner.
- 5. To demonstrate adequacy of facilities to provide sufficient space and accessibility for response team staff and communications equipment.
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e scE 10 DRAFT Unit 1 at the Peach Bottom Atomic Power Station is operating at 100% power.
Two operators were contaminated this morning at 0800. While working in the refueling area of the reactor building, one of the operators fell into the spent fuel pool. The second operator, who was helping the first, slipped, fell, and cut his neck. An unusual event was declared - radioactivity was not released.
At 1300 a fire was reported in the control room at the Peach Bottom Atomic Power Station. The fire was fueled by leaking fuel oil. The CO2 fire extinguishing system malfunctioned requiring offsite assistance due to the severity of the fire. An unusual event continues - radioactivity was not released.
At 1500 a discharge pipe on a condensate pump ruptured and water from the rupture sprayed on the other condensate pumps, tripping the pumps. The loss of the condensate pumps resulted in a reactor scram, an unplanned shutdown resulted - unususi event continues.
Security forces are investigating the possibility of sabotage. Facility engineers, NRC, and BRP are attempting to manually open relief valves to depressurize the reactor vessel. PEMA is monitoring the situation and will keep all agencies abreast of any changes in systems which could jeopardize the public health and safety.
At 1700 an alert was declared at Unit I due to release of radioactive gases within the reactor building. There has not been a radioactive release from the plant but the reactor building had to be evacuated.
CHRONOLOGY OF EVENTS Alert 1700 Site Area Emergency 1800 General Emergency 1900 Evacuation Ordered 1940 Termination of Exercise 2000 (Approx.)
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l DEFICIENCIES NOTED IN PAST EXERCISE This remadial exercise was necessitated by the following Category "A" l deficiencies reported in the October 17, 1984 exercise report.
Drumore Township and Little Britain Township (Lancaster County)
Deficiency
- 1. Because no federal observation was permitted, FEMA is unable to find that emergency preparedness was adequate to provide reasonable assurance that appropriate protective measures can be taken to protect the health and safety of residents in the event of a radiological emergency at Peach Bottom Atomic Power Station.
Disposition l
In this exercise Drumore and Little Britain Townships demonstrated a level of preparedness sufficient to provide reasonable assurance that appropriate
- protective measures can be taken to protect the health and safety of l
residents in the event of a radiological emergency at Peach Bottom Atomic I
Power Station.
l Fawn Grove Borough / Fawn Grove Township Deficiency
- 2. Fawn Grove Borough / Fawn Grove Township did not demonstrate an overall level of emergency preparedness sufficient to provide reasonable assurance that appropriate protective measures can be taken to protect the health and safety of borough and township residents in the event of a radiological emergency at Peach Bottom.
Disposition In this exercise the borough / township demonstrated a sufficient level of emergency preparedness. The following Category "B" deficiencies were reported for Fawn Grove Borough / Fawn Grove Township in the October 1984 exercise and, taken together, resulted in the Category "A" deficiency noted l above.
I l Deficiency Disposition
- 25. Future exercises should This deficiency is corrected.
demonstrate staffing of the Staffing of the E0C was adequate E0C to include active involve- during the exercise. There was ment by elected officials during active involvement on the part of critical periods of activity and elected officials and sufficient greater control and direction of direction and control was demon-emergency response activities strated by the EMC.
demonstrated by the EMC.
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- 26. Twenty-four hour staffing of all This deficiency has been corrected.
E0C positions should be estab- Twenty-four hour staffing was de-lished, and the RERP updated monstrated by double staffing for accordingly, this exercise.
- 27. Additional training should be The provisions of the RERP regard-provided to response personnel ing the use of KI were not demon-with regard to the provisions of strated during this exercise. No the RERP, especially concerning direction concerning its use was evacuation and relocation of E0C received from the York County E0C.
activities and use of KI. Arrangements have been made for the relocation of the E0C out of the 10-mile EPZ.
- 28. The communications systems used This deficiency has been corrected, at the E0C should be critically Communications between the County reviewed and reorganized. The EOC and the Fawn Grove Borough /
revised system should enable Fawn Grove Township regarding plant timely notification to the EMC status and protective action and E0C staff regarding changes recommendations were timely. RACES in plant status and protective operationc were efficient.
action recommendations.
Specifically, RACES network operations, and training with re-gard to the recently provided scanner should be provided.
- 29. The borough and township's plan This deficiency has been satis-for the utilization of route factorily addressed pending the alerting is unclear; route next Pennsylvania-Maryland Peach alerting was conducted at in- Bottom exercise. The RERP has been appropriate times. Clarification clarified to the effect that the is needed with regard to the joint EOC is not responsible for timing of the dispatching of route alerting in Maryland, route alerting teams. Initiating route alerting with the sounding of Maryland's sirens is not in-dicated in the RERP, and could cause coordination difficulties with Pennsylvania EBS announcements.
Responsibility for completing route alerting in Maryland (as alluded to by the Fire personnel) should be clarified and incorporated in the RERP, if appropriate.
30 Route alerting took an excessive At least one route alerting team amount of time. Route alert completed its route well within 45 sectors should be reviewed and minutes 'as called for by the exist-restructured as necessary in order ing RERP. Additional restructuring to provide for a more timely com- of sectors is underway and can be pletion of routes. expected to result in timely completion of routes, vii
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- 31. Lists of mobility-impaired in- Lists of mobility-impaired in-dividuals should be developed dividuals are in the process of and maintained at the E0C. development . The borough and town-ship expect to have up-to-date lists during 1985
- 32. The RERP should be revised to RERP revisions are underway to reference all mutual support reference mutual support agreements. agreements.
- 33. The borough / township EMC should The borough / township EMC has ob-confer with the County in order tained approval for removal of the to establish an appropriate E0C to Stewartstown as necessary.
location outside of the 10-mile A decontamination center has been EPZ for the monitoring and de- established outside the 10-mile EPZ contamination of Delta Borough in Stewartstown and its operation evacuated emergency workers, was successfully demonstrated in this exercise.
34 The EMC should investigate the The use of KI was not addressed
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cause for the apparent lack of in this exercise. There was no notification to administer KI, notice from the County E0C of and ensure the completion of possible plume exposure in the corrective actions as necessary. Fawn Grove area.
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DRAFT Drumore Township EOC .
The Emergency Management Coordinator received a call at her home from I
, Lancaster County EOC at 1806 informing her of a Site Area Emergency at the Peach Bottom Power Station. The call was verified at 1820 when the EMC
! arrived at the Drumore Township EOC. She had notified two of her staff :
! members before leaving home and they arrived at the EOC shortly after she i did. She instructed them to notify the rest of the staff. The EOC was !
} completely manned at 1855. The following staff members were present in the
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i i Emergency Management Coordinator i
- Connunications Officer 4
Transportation Officer
- Public Works Officer Fire and Rescue ;
-Radiological Officer '
- Route Alert Team Members I The deputies were called and placed on standby, several deputies came into j the E0C and watched the procedures. Round-the-clock staffing capabilities j were adequately demonstrated by double staffing.
The Drumore Township ~ Emergency Management Coordinator demonstrated a good i
knowledge of the township emergency response plan and was effectively in ,
j control of the emergency operations in the E0C. However, other' staff :
{ members should be more actively involved in briefings and the decision i naking process. Copies of the township plan and written procedures were
! available and used throughout the exercise. The EMC kept a message log and i messages were distributed appropriately. The EMC should appoint another l staff member to keep the log so that she is free for the many other i responsibilities associated with her position. Access to the EOC was j controlled.
i The E0C was notified of Site Area Emergency at 1806, General Emergency at 1905 and at 1935 were instructed that the siren system would be activatet at 1945 with EBS announcements and evacuation to follow ~immediately. Township supervisors were present in the EOC and actively involved.
The Drumore Township EOC is more than adequate for emergency response functions with adequate space, furniture and lighting. There were two 1 telephones available in the EOC, one was wall-mounted and the other was a
. desk instrument. The township should rearrange the layout of the EOC to
, allow the accessibility to the telephone' instruments from the desk area.
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Status boards were available and posted.- Again, these boards should be moved so that they are closer to the communications room and the staff responsible l for posting ~them.
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DRAFT All appropriate maps, evacuation routes and relocation centers were available in the township plan. They were not posted. It is suggested that all these items be posted on the walls so that they are readily available to all staff members.
The township E0C demonstrated adequate communications with the County E0C.
As stated, two telephones were avialable and the county radio net was available. Both systems were used extensively. The County E0C dispatched a RACES operator to the township; however, he never arrived at the Township E0C.
At 1935 the Township E0C was informed that sirens would sound at 1945 and route alerting, if necessary, should begin in conjunction with siren activation. The township sent out 4 route alert teams at 1945 with instructions to the public to tune to their EBS stations for further information. The routes took approximately 4'. minutes to complete.
The traffic control points in Drumore Township are manned by State Police.
The Emergency Management Coordinator verified through Lancaster County E0C that the traffic control points were manned.
There are three mobility-impaired individuals in the township. Each person was contacted to verify the need for ambulances and the transportation officer informed the county of ambulance requirements. The ambulances arrived at the township at 1943.
Mid-range dosimeters have been predistributed to Drumore Township. High and low-range dosimetry is not available but will be maintained in the Township E0C when it is available. Appropriate instructions were issued along with dosimetry. All staff members have received training in radiological exposure control. They were aware of maximum doses allowed without authorization and where to go for monitoring and decontamination.
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l Little Britain Township E0C Members of Little Britain Township assembled at the EOC at 1830, after the Emergency Management Coordinator had received a call at home from the Lancaster County E0C declaring a Site Emergency.
The E0C was staffed and operating by 1830. Dosimetry was distributed to all occupants in the E0C.
The RACES operator arrived and established a communication contact by RACES radio. There were three telephones available.
The Emergency Coordinator discussed all messages with his staff and all important events were listed on the status board. The staff frequently referred to its plans and all decisions were instantly conveyed to the staff for action.
The RADEF Officer supplied the people in the E0C with dosimetry and explained its use, then periodically reminded each one to read the inst rument ,
t The General Emergency message was received at 1900, at which time sirens and EBS messages were activated.
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Fawn Grove Borough / Fawn Grove Township E0C The Emergency Management Coordinator (EMC) for the borough and township received a call at home from the York County Emergency Operations Center (E0C) at approximately 1700, notifying him of an alert declaration at Peach Bottom. The EMC notified the deputy coordinator and proceeded to the Joint Borough / Township E0C in the Citizens' Fire Hall in Fawn Grove where he arrived at 1720. The EMC and deputy notified the remainirig E0C staff, all of whom reported by 1830. Each position was double staffed for training purposes. The following positions were filled:
Medical / Ambulance Public Works Transportation Fire / Rescue / Radiology Communications Police / Security Elected officials from both the borough and the townhip were present for the exercise. A RACES team dispatched by the County EOC established radio communications by 1829.
Sufficient furniture, space, lighting and telephones were p esent. Some awkwardness was evident in the use of telephones with the et ordinator and other EOC staff having to move across the room to receive various phone calls on one or another of the three phones available.
Status boards were clearly visible and kept up-to-date on sig11ficant events. Evacuation routes, relocation centers, etc. were ava"lable but not posted.
Communications with the County E0C were demonstrated satisfactcrily via phone and radio. Additionally, the County police / fire radio network was monitored in the E0C. The local EBS station was also monitored.
The coordinator was effectively in charge of operations. Messager were satisfactorily handled. Plans, checklists and SOPS were available and utilized and a message log kept. Access to the E0C was satisfactorily 1 controlled.
The E0C was notified of Site Emergency status at 1832 and of General l Emergency at 1914 Route alerting teams were dispatched, at county request, !
at 1900 in conjunction with a simulated siren sounding and EBS activation. I The message conveyed by the route alerting teams was that residents shouold monitor their EBS stations.
The route alerting team covering Sector One completed its route in approximately 30 minutes. Return of the other two teams to the E0C was not i observed by the FEMA observer, although they may have returned within 45 or l 50 minutes of their dispatch. It is understood that a revision of the ,
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sector configuration is underway and that an increase in the number of !
sectors is anticipated. In light of the large size of Sectors Two and Three, such a revision would seem warranted, Word of the Governor's declaration of Disaster Emergency was received at 1856. The evacuation order was received at 1945. Appropriate messages were conveyed to and from the decontamination center established in Stewartstown.
E0C staff were aware of the location of most mobility-impaired residents and spent time during the exercise compiling a list of same. The staff expects to obtain a complete list through a utility mailing that is scheduled for later this year and will recuest that mobility-impaired residents complete a form that will be forwarded to the borough / township ~ indicating the particular needs of such residents.
An adequate supply of mid-range dosimetry is permanently stored at the E0C and was distributed during the exercise. Dosimeters were charged and appropriate record forms distributed.
Arrangements have been made to relocate the joint E0C to the Stewartstown Borough office, should it become necessary. A letter from the president of the Stewartstown Borough Council on file in the Fawn Grove E0C assures the availability of the alternate location.
A decontamination center was activated at the Eureka Fire Company in Stewartstown. The facility was set up to handle anyone in need of monitoring and decontamination. The capacity of the center was estimated by the fire company chief to be several hundred persons.
Procedures for monitoring and decontamination of persons was demonstrated.
A CDV-700 dosimeter was used correctly. Proper procedures were demonstrated for handling contaminated clothing, etc.
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SUMARY LIST OF CATEGORY "B" DEFICIENCIES AND RECOMENDATIONS Deficiencies Drumore Township
- 1. The RACES operator never arrived at the E0C. The township, in conjunction with the Lancaster County Emergency Management Coordinator, should determine the source of this problem and tak-steps to avoid its reoccurrence.
Recommendations Drumore Township
- 1. The EOC staff should be used more by the Coordinator and should be involved more in the decision making process. Appointment of a specific individual as message runner and logger would free the EMC for supervision of all aspects of the response.
- 2. Reorganization of the EOC layout shuold be considered to ensure convenient access to message logs, status boards, etc. and to provide easier access to the telephone by the Coordinator. Various maps and other graphics would be more useful if mounted on the walls.
Fawn Grove Borough / Fawn Grove Borough
- 3. Consideration should be given to the repositioning of telephones within the E0C. The layout of tables and telephones in this exercise necessitated the Coordinator getting up and walking across the roon to answer phone calls.
4 Restructuring of route alerting sectors should be continued in order to ensure completion of routes within acceptable times.
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