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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified ML20211Q3091999-09-0909 September 1999 Forwards Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q4861999-09-0808 September 1999 Informs That Util Has Discovered Dose Calculation Utilized non-conservative Geometry Factor for Parameter.Calculation Error Being Evaluated in Accordance with Corrective Action Program ML20211Q0091999-09-0808 September 1999 Forwards Request for Addl Info Re Individual Plant Exam of External Events for Grand Gulf Nuclear Station,Unit 1. Response Requested by 000615 ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211P4171999-09-0707 September 1999 Ack Receipt of ,Which Transmitted Addendum to Rev 30 to Physical Security Plan for Ggns,Per 10CFR50.54(p).NRC Approval Is Not Required,Since Util Determined That Changes Do Not Decrease Effectiveness of Plan ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam ML20211K5641999-08-31031 August 1999 Forwards Rev 39 to Grand Gulf Nuclear Station Emergency Plan Non-Safety Related, IAW 10CFR50,App E,Section V. Changes Do Not Decrease Effectiveness of Plan & Continues to Meets Stds of 10CFR50.47(b) & Requirements of App E ML20211J2321999-08-26026 August 1999 Advises That Info Contained in to Support NRC Review of GE Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Will Be Withheld from Public Disclosure ML20211F4881999-08-25025 August 1999 Advises That Info Submitted by 990716 Application & Affidavit Containing Diskette & to Ineel Mareked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20211J3761999-08-25025 August 1999 Corrected Ltr Informing That Info Provided (on Computer Disk & in Ltr to Ineel ) Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended.Corrected 990827 ML20211F7751999-08-24024 August 1999 Forwards Insp Rept 50-416/99-10 on 990809-13.No Violations Noted.Insp Covered Licensed Operator Requalification Program & Observations of Requalification Activities ML20211C4381999-08-20020 August 1999 Forwards Rev 31 to Physical Security Plan for Protection of Grand Gulf Nuclear Station,Iaw 10CFR50.54(p).Util Has Determined That Rev Does Not Decrease Effectiveness of Plan. Encl Withheld,Per 10CFR73.21 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B3761999-08-16016 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001, ML20211A9481999-08-12012 August 1999 Informs of Completion of Analysis of Heat Transfer in Cooler During Fan Coast Down & Concludes That Potential Exists for Steam Foundation,Under Conditions Where Dcw Sys Flow Is Lost Prior to Full Isolation Valve Closure ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210P8411999-08-0909 August 1999 Forwards Insp Rept 50-416/99-09 on 990613-0724.No Violations Noted.Activities at Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20210N6401999-08-0303 August 1999 Informs That Eighteeen Identified Penetrations Will Be Restored to Conformance with Licensing Requirements Prior to Restart from RFO10,scheduled for Fall 1999,per GL 96-06. Example of Piping Analysis Being Performed,Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K1951999-07-30030 July 1999 Forwards Insp Rept 50-416/99-03 on 990405-08 & 0510-11.No Violations Identified ML20211K7491999-07-30030 July 1999 Forwards Ltr Rept Documenting Work Completed Under JCN-W6095,analyses Performed at Ineel to Calculate Minimum Time to Fuel Pin Failure in Boiling Water Reactors (BWR) ML20210K6661999-07-29029 July 1999 Forwards Fitness for Duty Program Performance six-month Rept for Period Covering Jan-June 1999,per 10CFR26.71 ML20210F3591999-07-26026 July 1999 Forwards Proprietary Version & Redacted Version of Wyle Test Rept M-J5.08-Q1-45161-0-8.0-1-0,re Pressure Locking & Thermal Binding Test Program.Proprietary Version Withheld ML20210E3251999-07-23023 July 1999 Forwards Insp Rept 50-416/99-07 on 990622-25.No Violations Noted.Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise Was Conducted ML20210D2401999-07-21021 July 1999 Informs of Resignation of Operator WE Griffith,License OP-20806-1,from Entergy Operations,Inc ML20209J0311999-07-16016 July 1999 Forwards Proprietary Info Supporting Review of Generic Alternate Source Term Request.Proprietary Info Withheld Per 10CFR2.790 ML20209G4791999-07-15015 July 1999 Forwards Proposed Emergency Plan Change as Addendum to Changes Previously Submitted Via GNRO-98/00028 & GNRO-99/00007,for NRC Review & Approval ML20210B1031999-07-15015 July 1999 Forwards Insp Rept 50-416/99-08 on 990502-0612.Determined That Three Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20210H3211999-07-14014 July 1999 Forwards Proprietary Info Supporting Review of 970506 Submittal of BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr. Proprietary Info Withheld Per 10CFR2.790 ML20209D7511999-07-0909 July 1999 Responds to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. as Result of NRC Review of Util Responses,Info Revised in Rvid & Rvid Version 2 Will Be Released ML20209D7671999-07-0101 July 1999 Submits Response to Violations Noted in Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Corrective Actions: Contractor Performance Has Been re-evaluated in Regards to UFSAR Reviews ML20196K4901999-07-0101 July 1999 Discusses Relief Requests PRR-E12-01,PRR-E21-01,PRR-E22-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01 Submitted by EOI on 971126 & 990218.SE Accepting Alternatives Proposed by Util Encl ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld ML20211Q4861999-09-0808 September 1999 Informs That Util Has Discovered Dose Calculation Utilized non-conservative Geometry Factor for Parameter.Calculation Error Being Evaluated in Accordance with Corrective Action Program ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211K5641999-08-31031 August 1999 Forwards Rev 39 to Grand Gulf Nuclear Station Emergency Plan Non-Safety Related, IAW 10CFR50,App E,Section V. Changes Do Not Decrease Effectiveness of Plan & Continues to Meets Stds of 10CFR50.47(b) & Requirements of App E ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam ML20211C4381999-08-20020 August 1999 Forwards Rev 31 to Physical Security Plan for Protection of Grand Gulf Nuclear Station,Iaw 10CFR50.54(p).Util Has Determined That Rev Does Not Decrease Effectiveness of Plan. Encl Withheld,Per 10CFR73.21 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B3761999-08-16016 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001, ML20211A9481999-08-12012 August 1999 Informs of Completion of Analysis of Heat Transfer in Cooler During Fan Coast Down & Concludes That Potential Exists for Steam Foundation,Under Conditions Where Dcw Sys Flow Is Lost Prior to Full Isolation Valve Closure ML20210N6401999-08-0303 August 1999 Informs That Eighteeen Identified Penetrations Will Be Restored to Conformance with Licensing Requirements Prior to Restart from RFO10,scheduled for Fall 1999,per GL 96-06. Example of Piping Analysis Being Performed,Encl ML20211K7491999-07-30030 July 1999 Forwards Ltr Rept Documenting Work Completed Under JCN-W6095,analyses Performed at Ineel to Calculate Minimum Time to Fuel Pin Failure in Boiling Water Reactors (BWR) ML20210K6661999-07-29029 July 1999 Forwards Fitness for Duty Program Performance six-month Rept for Period Covering Jan-June 1999,per 10CFR26.71 ML20210F3591999-07-26026 July 1999 Forwards Proprietary Version & Redacted Version of Wyle Test Rept M-J5.08-Q1-45161-0-8.0-1-0,re Pressure Locking & Thermal Binding Test Program.Proprietary Version Withheld ML20210D2401999-07-21021 July 1999 Informs of Resignation of Operator WE Griffith,License OP-20806-1,from Entergy Operations,Inc ML20209J0311999-07-16016 July 1999 Forwards Proprietary Info Supporting Review of Generic Alternate Source Term Request.Proprietary Info Withheld Per 10CFR2.790 ML20209G4791999-07-15015 July 1999 Forwards Proposed Emergency Plan Change as Addendum to Changes Previously Submitted Via GNRO-98/00028 & GNRO-99/00007,for NRC Review & Approval ML20210H3211999-07-14014 July 1999 Forwards Proprietary Info Supporting Review of 970506 Submittal of BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr. Proprietary Info Withheld Per 10CFR2.790 ML20209D7671999-07-0101 July 1999 Submits Response to Violations Noted in Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Corrective Actions: Contractor Performance Has Been re-evaluated in Regards to UFSAR Reviews ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20195J6351999-06-16016 June 1999 Forwards Addendum to Rev 30 of GGNS Physical Security Plan IAW 10CFR50.54(p).Addendum Is Submitted to Announce Relocation/Reconfiguration of Plant Central & Secondary Alarm Station Facilities.Rev Withheld,Per 10CFR73.21 ML20195G0281999-06-0909 June 1999 Submits Summary on Resolution of GL 96-06 Re Eighteen Penetrations Previously Identified as Being Potentially Susceptible to Overpressurization ML20207F5041999-06-0202 June 1999 Forwards Updated Medical Rept IAW License Condition 3 for DA Killingsworth License OP-20942-1.Without Encls ML20206P2981999-05-13013 May 1999 Forwards Responses to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Cancelling 990402 Submittal ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 ML20206J0941999-05-0404 May 1999 Forwards Proprietary & Redacted ME-98-001-00,both Entitled, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators. Rept ME-98-002-00 Re Flexible Wedge Gate Valves,Encl.Proprietary Rept Withheld ML20206D8171999-04-29029 April 1999 Informs NRC of Results of Plant Improvement Considerations Identified in GGNS Ipe,As Requested in NRC . Licensee Found Efforts Have Minimized Extent of Radiological Release in Unlikely Event That Severe Accident Occurred ML20206E7811999-04-29029 April 1999 Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested ML20206D7281999-04-28028 April 1999 Forwards South Mississippi Electric Power Association 1998 Annual Rept, Per 10CFR50.71(b).Licensee Will Submit 1998 Annual Repts for System Energy Resources,Inc,Entergy Mississippi,Inc & EOI as Part of Entergy Corp Annual Rept ML20206C9551999-04-22022 April 1999 Forwards 1999 Biennial Emergency Preparedness Exercise Scenario. Without Encl ML20205M1311999-04-0202 April 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. Info Was Discussed During Conference Call with NRC on 990126.Wyle Position Paper Encl.Subj Paper Withheld ML20205H5861999-04-0101 April 1999 Requests Relief from ASME B&PV Code,Section XI for Period of Time That Temporary non-code Repair Was in Effect,Per 10CFR50.55a(g)(5)(iii) ML20205F1781999-03-31031 March 1999 Forwards Consolidated Entergy Submittal to Document Primary & Excess Property Damage Insurance Coverage for Nuclear Sites of Entergy Operations,Inc,Per 10CFR50.54(w)(3) ML20196K7101999-03-26026 March 1999 Submits Reporting & Recordkeeping for Decommissioning Planning,Per 10CFR50.75(f)(1) ML20205A6511999-03-25025 March 1999 Responds to NRC Re Violations Noted in Insp Rept 50-416/99-01 on 990201-05.Corrective Actions:Program Will Be Implemented to Ensure Accessible Areas with Radiation Levels Greater than 1000 Mrem/H ML20204E7391999-03-15015 March 1999 Forwards Objectives for June 1999 Emergency Preparedness Exercise for Plant.Without Encl ML20207H9291999-03-0404 March 1999 Submits Update to Original Certification of Grand Gulf Nuclear Station Simulation Facility IAW Requirements of 10CFR55.45(b)(5) ML20207E3081999-03-0303 March 1999 Informs That GGNS Severe Accident Mgt Implementation Was Completed on 981223.Effort Was Worthwhile & Station Ability to Respond & Mitigate Events That May Lead to Core Melt Has Been Enhanced ML20207E3221999-03-0303 March 1999 Notifies of Change in Status of Mj Ellis,License SOP-43846. Conditional License Requested to Accommodate Medical Condition.Revised NRC Form 396 with Supporting Medical Evidence Attached.Without Encls ML20207A8161999-02-24024 February 1999 Forwards 1998 Annual Operating Rept for Ggns,Unit 1. Listed Attachments Are Encl ML20207A9901999-02-24024 February 1999 Informs That Util Has No Candidates from GGNS to Nominate for Participation in Planned Gfes,Scheduled for 990407 ML20203A1551999-02-0101 February 1999 Forwards Grand Gulf Nuclear Station Fitness for Duty Program Performance six-month Rept for Reporting Period 980701-981231 ML20202G0791999-01-26026 January 1999 Informs That He Mcknight Has Been Permanently Reassigned from Position Requiring License to Perform Assigned Duties. License Is No Longer Needed,Effective 981231 ML20199K4151999-01-20020 January 1999 Forwards Proposed Addendum to Emergency Plan Changes Previously Submitted Via GNRO-98/00028 for NRC Review & Approval as Required by 10CFR50.54(q) & 50.4 ML20199K6771999-01-14014 January 1999 Provides Notification of Planned ERDS Software Change Scheduled to Take Place on 990215 ML20199D8811999-01-11011 January 1999 Submits Response to SE JOG Program on Periodic Verification of motor-operated Valves,In Response to GL 96-05 ML20199D9521999-01-0808 January 1999 Informs That CE Cresap,License SOP-4220-4,has Been Permanently Reassigned from Position Requiring License & No Longer Has Need for License,Per 10CFR50.74 ML20199A6081999-01-0606 January 1999 Submits List of Plant Info Brochures Disseminated Annually to Public & List of Updated State &/Or Local Emergency Plan Info,Per NRC Administrative Ltr 94-07, Distribution of Site-Specific & State Emergency Planning Info ML20202B7531998-12-21021 December 1998 Submits Ltr Confirming Discussion with J Tapia,Documenting Extension for Response to NOV 50-416/98-13.Util Response Will Be Submitted by 990212 1999-09-08
[Table view] Category:RESEARCH INSTITUTION/LABORATORY TO NRC
MONTHYEARML17261A8541989-01-13013 January 1989 Discusses 890110-11 Meetings Re Nozzle Sizing Study.Most Accurate Sizing Obtained by Collecting Data of Edge Diffracted Waves from Geometric Extremities of Flaw ML20043B2801988-12-12012 December 1988 Forwards Draft Ltr Rept ORNL/NRC/LTR-88/8, Grand Gulf Stability Measurements During Cycle 2 ML19324A1111988-05-19019 May 1988 Forwards Memo Describing Results of Testing of Plant Bolting Matls Under FIN A-3866,Task Assignment 12 ML19324B2701988-03-0202 March 1988 Forwards Rept on Metallurgical Evaluation of Five Bolts Obtained from Farley Plant.Bolts Found Acceptable ML20234F0891987-12-28028 December 1987 Forwards Final Rept of M Stein for Plant 871117 Annual Exercise.Minor Changes Made to Draft.Rept Covered Control Room & TSC ML20235J2211987-09-0404 September 1987 Forwards Rev 0 to PRA-Based Sys Insp Plan, Technical Rept. Items Requiring Addl Discussion Listed,Including Recommendation of Trending for Wear of CRDs as Result of Maint for Use as Monitoring Tool ML20207R7571987-03-10010 March 1987 Forwards Technical Evaluation Rept Input for South Texas Initial Plant Test Program Through FSAR Amend 56,Feb 1987 Sser & & Beaver Valley Unit 2 Initial Plant Test Program Through FSAR Amend 15 & Nov 1986 Sser ML20207S5001987-03-0606 March 1987 Forwards Technical Evaluation Repts for Domestic Mark III Plants (Grand Gulf,Clinton,River Bend & Perry) & Gessar Ii. Inserts to Be Included in Section 6.2.1.8 of Draft Sser 2 for Clinton,River Bend & Perry Plants Also Encl ML20195F8651986-10-31031 October 1986 Forwards Request for Addl Info Re MSIV Operability at Facility,Based on Initial Review of Util Rept Entitled, Final Rept 10CFR50.55(e) MSIV Actuators, Forwarded by Util ML20206H3211986-09-10010 September 1986 Forwards Summary Repts from 860811-14 Visit to Kewaunee Nuclear Station & 851002-03 Visit to Cooper Nuclear Station Re Generic Issue 83 on Control Room Habitability ML20206J6001986-08-0808 August 1986 Advises That NUREG-0956 Support Calculations Using ORNL Trends Code to Evaluate Influence of Containment Chemistry or Retention of Hi Can Also Provide Useful Info for General NUREG-1150 Issue Paper,Per Telcon Discussion ML20206H1131986-06-23023 June 1986 Submits DHEAT2 Parametric Calculations for Plant,Per 860620 Discussions.Calculations Run Assuming Any Steam Spike Would Develop Too Slowly to Contribute to DCH Peak Pressure ML20214E1721986-02-25025 February 1986 Ack Receipt of 860210 & 21 Ltrs Accepting Task Orders 3 & 4 Under FIN A-3552 & Task Order 5,respectively.Orders Include Work at Palisades & LaSalle Stations & Mod Review at Davis-Besse.Modified Task Order 4 Under FIN A-3550 Encl ML20206J2521986-01-24024 January 1986 Forwards Early Draft of Executive Summary from Analysis of Station Blackout Accidents for Bellefonte PWR, Per Request. Initial Draft of Rept Scheduled to Be Completed by 860315 ML20206J3681986-01-15015 January 1986 Discusses Latest Calculations of Molecular Iodine (I2) & Organic Iodide (CH3I) Scrubbing During TC1 Sequence from Draft Plant Rept ML20136F4771985-12-31031 December 1985 Forwards PNL-5718, Review of Tdi Diesel Generator Owners Group Engine Requalification Program,Final Rept, Technical Evaluation Rept ML20206J4031985-12-13013 December 1985 Summarizes Preliminary Scoping Calculations for Molecular Iodine (I2) Scrubbing in BWR Pressure Suppression Pools. Calculations Made for Most Recent TC1 Sequence in Draft Plant Rept ML20133A3141985-09-27027 September 1985 Forwards Review of Section 4.7 of Technical Evaluation Rept PNL-5600, Review of Resolution of Known Problems in Engine Components for Tdi Emergency Diesel Generators, Reflecting Views Re Crankshafts for 16-cylinder Engines ML20128H7371985-06-27027 June 1985 Forwards Rev 1 to Review of Engine Base & Bearing Caps for Tdi DSRV-12,DSRV-16 & DSRV-20 Diesel Engines, Technical Evaluation Rept ML20141N2981985-05-29029 May 1985 Requests Listed Addl Info Re S&W 1982 Rept, Ultimate Pressure Capacity of Shoreham Primary Containment ML20126E8721985-05-24024 May 1985 Forwards PNL-5200-3, Review of Emergency Diesel Generator Engine & Auxiliary Module Wiring & Terminations, Dtd May 1985 ML20133N7721985-03-27027 March 1985 Forwards Info Telecopied on 850325 Re Locational Distribution of Three Fission Product Species for Surry V Sequence & Time Dependent Release for Fission Product Groups for Peach Bottom ML20214F5101985-03-13013 March 1985 Forwards List of Questions Re Plant Pra,Per 850512 Telcon. Statement of Work, Review of PRA for Seabrook Nuclear Power Plant, Encl ML20134A1011985-02-20020 February 1985 Submits Results of Noble Gas Release Sequences Using March Code for Facilities ML20133N3461985-02-20020 February 1985 Discusses Review of March Results for Surry & Peach Bottom Sequences,In Order to Quantify Expected Noble Gas Releases. March Model Appropriate for Behavior of Noble Gases ML20128P3401984-12-0505 December 1984 Submits Rept for Task 1 Per M Silberberg 841116 Memo Re Concerns Re Lanthanum Releases in BMI-2104.Discusses Discrepancies in Corcon Calculations,Presents Revised Tables 6.14 & 7.16 & Recommends Reanalyses ML20138N6971984-09-18018 September 1984 Forwards Repts Re Irradiation,Decontamination & DBA Testing, Per Request of Y Korobov of Carboline Co ML20134E1591984-08-0202 August 1984 Forwards Brief Summary Rept on Leakage Characteristics of Nuclear Containment Hatches During Severe Accident. Draft of Complete Rept Will Be Mailed Later in Aug ML20127B9221984-07-20020 July 1984 Forwards PNL-5201, Review & Evaluation of Tdi Diesel Engine Reliability & Operability - Grand Gulf Nuclear Station, Unit 1 ML20127B8881984-05-21021 May 1984 Comments on May 1984 Draft Tdi Diesel Generator Owners Group Program Plan.Full Insp of One Engine to Owners Group Spec Recommended ML20093G4821984-05-0202 May 1984 Provides Summary of Battelle Subcontract W/Tdi to Evaluate Special Silicon carbide-impregnated Cylinder Liners & Piston Rings.Task Does Not Involve Dependability Tests of Tdi Engines.No Apparent Conflict Found ML20084F3881984-04-17017 April 1984 Responds to Request for Clarification of Several Issues Addressed in Re Standby Diesel Generators. Complete Disassembly & Insp Should Be Performed on Engine Operating Most Hours ML20246C8941984-04-13013 April 1984 Forwards Wv Thomas,Rj Traub,F Vosbury & G Wehmann Finalized Rept Re Grand Gulf Emergency Preparedness Exercise.Areas Covered Listed ML20113A0201984-04-0404 April 1984 Forwards Requests for Addl Info Developed During Review of FSAR Chapter 14 Re Initial Plant Test Program.Review Conducted Through Amend 4.Listing of Items Requiring Resolution Encl ML20117C9421984-04-0303 April 1984 Forwards Proposed Radiological Source Term Input for Facility.Encl Amended to Reflect NRC Suggested Changes ML20084F3811984-03-30030 March 1984 Provides Comments on Engine Start & Operability from Review of Standby Diesel Generators & Reliability Rept Submitted on 840220 ML20093C5281984-03-30030 March 1984 Forwards Audit of Susquehanna Unit 2 Tech Specs, Technical Evaluation Rept ML17320A9711984-03-0606 March 1984 Forwards First Round Questions Following Evaluation of Exxon Rept, Steam Tube Rupture Incident at Prairie Island Unit 1, PTSPWR2 Vs Data,Preliminary Benchmark Analysis. ML17320A9741984-03-0505 March 1984 Forwards First Round Questions on Exxon Methodology Rept for PTSPWR2.Rept Lacks Specific Details Re Biases in Initial Conditions & Boundary Conditions ML20128N6571984-02-22022 February 1984 Comments on Draft Vols IV-VI of BMI-2104,presented at Peer Review 840126 & 27 Meetings.Comments Concern Completed Calculations for Sequoyah Ice Condenser Plant,Recalculated Surry Results & Completed Calculations for Zion Plant ML19306A0151984-02-10010 February 1984 Summarizes 840206-07 Visit to Nevada Test Site Hydrogen Burn Facility to Inspect Condition of Equipment & Cable/Splice Samples After Series of Hydrogen Burn Tests Conducted by Epri.No Indication of External Damage to Equipment Noted ML20128D4701984-01-25025 January 1984 Forwards Proposed Research Program on Fission Product Transport Program - Limerick Plant Analyses Task. Proposal Expands Existing Contract to Cover Analyses of Fission Product Release to Environ ML17320A9731983-11-22022 November 1983 Forwards First Round Questions on Mods to Exxon Draft Repts, PTSPWR2 Mods for St Lucie Unit 1 & Description of Exxon Plant Transient Simulation Model for Pwrs. ML17320A9721983-09-30030 September 1983 Forwards First Round Questions on Exxon Plant Transient Code,Based on Review of Proprietary Rept, Description of Exxon Nuclear Plant Transient Simulation Model for Pwrs. ML20087N8741983-08-15015 August 1983 Forwards Comments on Draft Order for Intergranular Stress Corrosion Cracking Insps ML20080B5631983-08-12012 August 1983 Forwards Draft Preliminary Review of Limerick Generating Station Severe Accident Risk Assessment,Vol I:Core Melt Frequency. Rept Satisfies Milestone for Task 1 of Project 3 Under FIN A-3393 ML20211D5971983-04-11011 April 1983 Forwards Summary of Independent Development of Finite Element Models & Determination of Natural Frequencies for Piping Problems in Containment Spray Discharge Line & Accumulator Loop 4 ML20132B4961983-02-11011 February 1983 Forwards Evaluation of Generic Key Indicators for Project Engineering/Design Activities at Facilities ML20209B8601983-01-13013 January 1983 Requests Addl Info,Including full-size Isometric Drawings 437985 & 446484 ML20072L7101982-12-20020 December 1982 Forwards BNL 821213 Memeo Re Degraded Core Accidents at Facilities,Per Task III.3 Defined in Design Basis for Hydrogen Control Sys in CP & OL Applications. No-cost Extension to Contract Requested 1989-01-13
[Table view] |
Text
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+w April 13, 1984-Paciic Northwest Laboratories P.O.2o:999 Rahlano Washington U.5A 99.152 Wr. Ronald Marston.
" N U.S. Nuclear Regulatory Commission Region II 101 Marietta St., Suite'3100 Atlanta, GA 30303
Dear Ron:
CnAhD GULF EXERCISE Enclosed is the finalized report of W. V. Thomas, R. J. Traub, F. Vosbury, and G. Wehmann, who were Pacific Northwest Labortory participants during the Grand Gulf Emergency Preparedness Exercise, April 11. Only minor changes were made from the rough draft given to you prior to leaving.
Areas covered by PNL are as follows:
W. V.. Thomas" OSC, In-Plant Health Physics, and Fire Drill R. J. Traub OSC and Offsite Monitoring F. Vosbury Control Room and TSC Operations G. Wehmann TSC, all operations w
If you have any questions regarding.this report, please contact W. V. Thomas on(FTS)509-375-2088.
a Sincerely yours,
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'J./B.4 Martin W. V.' Thomas 4
h'LTechnicalLeader Senior-Research Scientist 2mergency Preparedness Group Health Physics Technology Section Health Physics Technology Section RADIOLOGICAL SCIENCE; DEPARTMENT tv RADIOLOGICAL SCIENCES DEPARTMENT j
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Q OPERATIONS SUPPORT CENTER (0SC)
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A.
Name: Walter V. Thomas B.
Assignment: Operations Support Center, In-Plant Health Physics, and Fire Drill C.
Site Personnel Contacted:
W. Lewis, Bechtel Industrial Safety; F.
Barron, Mississippi Power and Light (MPL) Industrial Safety; L. Hughes, Health Physics Technician (HPT); M. Owent, HPT; T. Hildebrandt, IP Coordinator; P.
Sudnak, OSC Controller, Fire Drill Controller; B. Gulley, OSC Controller; W.
Boots, OSC Maintenance Supervisor; F. Walsh, OSC Director; M. Sember, Fire Drill Observer; D. Hileman, Fire Drill Observer D.
Positive Findings: The activation of the OSC was accomplished in a prompt and orderly manner.
The OSC was fully functional by 0825 hr. OSC operations were supervised by the licensee officials predesignated in the emergency plan, consisting of the OSC Director HP Coordinator, and Maintenance Supervisor. All OSC Supervisors were knowledgeable of their duties and responsibilities and performed them in a conscientious manner.
Voice communication was established and maintained throughout the drill and the Control Room, the TSC, and the E0F.
The OSC was frequently monitored with radiation survey instrumentation and air samples were taken to confirm the habitability of the area. Personnel protective equipment for Iodine protection was available. The OSC emergency stores contained charcoal canisters, KI and spare bottles for Diopacks and Scott SCBA's.
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A large. status board was maintained in the OSC containing plant parameters and
' conditions, repair / recovery team members, locations of teams,- and names of individuals available for team assignments by craft / specialty. Radiation monitoring results within the OSC and in-plant were also displayed. Adequate numbers of health physics technicians, electrical maintenance technicians, and instrument and control technicians were available for repair / corrective action teams.
Radiochemistry and chemistry technicians were also available to take and analyze samples. Controllers did not prompt, coach or otherwise interfere with the exercise of the OSC.
Congestion and noise levels were kept to a minimum. All communications l
systems in use functioned properly.
Personnel to perform tasks requested by the control room or the TSC were assigned in a timely manner. Dose assignments for all tasks were determined by HP personnel in the TSC from the -
accumulated dose computer printout sheets. All teams were briefed prior to departure from the OSC and upon return.
Good health physics procedures were practiced and good contamination control procedures were used by all teams i
observed.
Fire Drill
.The fire drill was very realistic.
Two fires were actually set to enable the fire brigade members and the offsite backup support fire department to respond to and extinguish an actual fire. This was done to increase interest and to test the actual use of the fire brigade equipment.
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' Negative Findings E.
Communications protocol deteriorated as the-drill progressed.
Initially all personnel declared "This is a drill" when using radios onsite.
By
- 1300 hr personnel were using given names'and not stating "This is a
. drill." All personnel participants in drills must use proper radio protocol to prevent confusion and reduce rumor. Participating personnel should be referred to by drill title and not by name.
Additional training in this area is indicated.
The MP&L fire brigade. team arrived at the firesite after the fire had extinguished itself.
The fire burned for over 35 minutes after it was ignited, and for most of the time produced a very dense, heavy cloud of black smoke, which should have been visible a considerable distance.
The Claiborne County Fire Department arrived at the fire scene about two l
' minutes after the MPSL team and extinguished the fire assigned to them in a prompt manner. Upon arrival at the fire scene the fire brigade members l
l were not dressed in fire turnout gear and did not appear to be familiar with the fire fighting equipment.
It took an additional 10 minutes to get the foam deluge cannon operational.
It was apparent that additional training on the proper use of the fire brigade equipment was in order.
The reason for the fire brigade delay was complicated due to strict adherence to security procedures by the guard force, lack of turn out gear stored on the fire truck, and lack of designated OSC personnel being assigned to the fire brigade beforehand. Procedures should be I
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e implemented to assure'that emergency ingress and egress from the plant is
- not complicated by security considerations. Sufficient turn-out gear for the minimum number of personne1 required to operate the fire truck and-l-
Lequipment should be stored either in or on the vehicle or at least in a l
readily assessible location to the fire truck.
Fire brigade members should be assigned upon, initial assembly in the.0SC and should be restricted from others duties unless it is clear they will not be needed for fire fighting activity.
i i
F.
Chronology 1
Time' Observation 0800-Arrived at OSC.
0806 Alert announced on PA.
OSC activation began.
0825 OSC fully activated.
0913 CRD A pump reported burned out (bearings).
- 0933 Attended briefing of reconnaissance team by maintenance supervisor and OSC director.
0940 Accompanied team to 166 ft level'of turbine deck to monitor and take air sample.
0954 Steam leak on turbine deck.
Team evacuates to HP lab on 93 ft level without air sample.
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' Time Observation j
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0958;-
l Portal monitor. in HP area ~' alarmed, _ frisker' offscale. -
i 1000
. Set up new stepoff pad ~ area procure new frisker.
1015' Watched decontamination of team members.
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-i 1110
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1120 Returned to OSC.
Went out with steam tunnel team.
l 11200 Arrived at fire scene.
1210_
Fire ignited and burning well.
Security guard instructed to call in fire report.
.1250-
,First fire extinguishes itself._
1255.
Second fire still burning.
1305 Fire Brigade arrived.
1307 Claiborne County Fire Department arrived.
1310 Port Gibson Fire Department arrived.
1311 Claiborne County fire extinguished.
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Time-Observation-
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Fire brigade ~attac'ked fire..
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i 1400 Returned to OSC.-
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' 1420-Departed OSC with onsite survey team..
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- 1450.~
Returned to OSC.
i 1500-
' Drill secured.
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OPERATIONS SUPPORT CENTER (OSC), AND OFFSITE MONITORING l
A. -Name:
R. J. Traub l
B._ Assignment: Operations Support Center and Offsite Monitoring g
C.
Site Personnel Contacted: OSC - Russ Comerford, Controller; Sam Merry, Maintenance Supervisor; Jack Hurst; Victor King, Charles Anding; Paul Sudnak, Controller. Offsite Monitoring - Bill McKelvy, Controller; Sid Flatt,
-Observer; John Cotton, Team !eader; Jeff Kireham D.
Positive Findings:
OSC The workers in the OSC appeared to be familiar with their assignments.
Individuals such as HP tech dressed in anti-C clothing upon announcement of an Alert. The names of individuals available for emergency repair, etc. were posted.
Potential emergency response team members were tagged with the dose they could receive for the quarter.
This information had been taken from a computer printout dated 10, April,1984. Based on meteorological data, sectors which would be affected were drawn on a map.
The emergency response team which was observed appeared to be well trained.
They were in constant radiocontact with the OSC.
The HP technician frequently requested the controller for meter readings. The HP technician also frequently called for checks of pocket dosimeters. When notified that the turbine building was filling with steam there was no hesitation by the team L
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leader in calling.'for evacuation. During the evacuation, the team leader
- checked the window in the door at every. level..
Offsite Monitoring The. team observed appeared to be familiar with the local roads and sites visited. 'The-individual at the SAP who provided instructions to the team.
appeared familiar with the local area and and roads.
The instructions were understood by team.
The. team members appeared familiar with the use of the instruments used. The team members were observed to check the batteries of their instruments. Also-the team members were observed to don gloves prior to handling filter samples and they were observed to check their hands after handling the filter, even those having background readings. Open and closed window readings were taken with the R0-2A.
The team members were observed to make periodic radio checks to ensure contact with the SAP / EOF. Radio reports were observed to be prefaced by caller ID.
E.
Negative Findings:
OSC
. The emergency response team observed (sent to check turbine building for j.
damage) did not wear hard hats, only skull caps.
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Offsite Monitoring The positive reading and.its background reading were made in the apparent plume.
The reading should have been retaken some distance from point of collection.
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Iodine readings were taken with an unshielded pancake probe which allowed high' background. A shielded probe should have been used.
I The van used by the team would not have been very useful on some unpaved i
roads observed in the area. A FWD would be useful here.
Radiotransmission was not good at 10-12 miles.
There appeared to be confusion on the part of the Controller re:
iodine l
count data radioed in at 11:06.
l l-Offsite team I received no information concerning changes in field conditions, plant conditions, etc.
F.
Chronologg Time Observation OSC 8:04 Announcement "this is a drill, this is a drill." Alert announced.
8:13 HP technicians began preparing pencil dosimeters.
. _ _ - - _ _ -. - - - - _ - _. _ _ - _ _ - _ _ _ - _ - = - _ _
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Time Observation 8:30 Emergency response teams dressing in anti-C's.
l 9:03 Emergency. response team members tagged with dose which could be received for the calendar quarter.
Based on computer listing date-10 April 84.
1 1
9:24-Teams organized to enter turbine building and to view turbine -
building roof.
l 9:30 Emergency response team I instructed to go to turbine building roof and observe damage and repair if possible.
Instructions recommended 1
to go to 166 ft level and observe from there.
l 9:31 Emergency Response Team I (ECT) received HP briefing 95% power and normal readings, no expected contamination or radiation.
Check l
j dosimeters every 10-15 min.
l ll 9:32 Tested radios, third radio tested was used.
9:41 ERT-I stopped at HP lab to ask if HP team in turbine building.
l 9:44 In turbine building - R0-2A readings normal.
9:49 Report rain was coming in on exciter and on HP instruments.
Team checked pocket dosimeters.
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9:53-Area was noticed to be filling with steam.
Team leader ordered an immediate evacuation. Team. leader looked through door window at i
l every level during evacuation.-
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9:56
- Team at entry to HP lab (the exit from plant), team members found to
- i be contaminated, outer clothing was removed and preparations for showers were made.
Observer exited to observe offsite monitoring teams.
Offsite Monitoring l
10:25 Offsite team appraised that centerline thought to be at Bechtel gate.
10:33 Offsite team dressing in whites.
10:34 Two-way radio antenna placed on van.
10:39 SAP activated.
10:40 Team instructed to take dose rate and air sampler at approximate position of the small br,idge.
10:49 Saw slight deflection on R0-2A. Max reading - 0.5 mrem, about 100 yd east of Bechtel gate.
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. Time Observation 10:50 Team instructed to take 10 ft3,j p. 3,,p),,
l 10:51 Took beta reading - found no measurable beta.
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10:53 Air sample taken. - 1.5 cfm for 7 minutes. estimated 1 mile from
. plant, used 55 gal drum as base for air sampler.
10:56 Referred to procedure for offsite monitoring.
10:57 Checked dosimeters.
11:02 Air sample read with pancake probe. Background - 1300 cpm; iodine filter 1780 cpm; ammended by controller to 4080 counts / min - net..
3
. 11:06 Reported 4080 counts / min for 10.5 ft sample. Logged in date on data sheet HP 1016.
Instructed to proceed to Sector B-12.
11:32 At Presbyterian Church at Yokena reported position.
Instructed to stay and wait 30 minutes for plume.
12:00 Monitoring team turned over to EOF.
1:12 Radioed to SAP, instructed to return to SAP as all readings were background.
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Time-Observation 1:39 Offsite Team 1 arrived t.t SAP, frisked themselves and gave sample to be sent to chemistry for analysis.
1:50 Offsite Team 1.sent to switchyard boundary. to take readings on 60*N sector.
2:04 Drove to impassible location on boundary. Team. leader took frisker and R0-2A on foot to take readings.
2:19.
At perimeter of switchyard on north side of unit 2 coolant tower (location described' by team leader) all readings background.
Returned for truck.
2:31 Reported in readings, instructed to obtain a 5 min air sample.
2:46 Field monitoring team began 5 r;in air sample on hill overlooking unit 2 cooling tower excavation.
2:55 Returned to van, removed filters, counted particulate and iodine filters, background readings were obtained.
3:02 Team reported air filter readings and were informed that the drill was terminated.
_ _ _ - _ = -. - - - - _ - -
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CONTROL ROOM AND TSC OPERATIONS A.
Name:
Fred Vosbury 8.
Assignment: Control Room and TSC Operations C.
Site Personnel Contacted: Control Room Shift Personnel, Shift Superinten--
dent, Shift Supervisor, Reactor Operator,- Shift Operations Supervisor, Control Room Controller, Emergency Director (ED), Plant Manager (PM)
D.
Positive Findings:
The control room operators rapidly classified the unusual event and alert.
Initial accident assessment by control room personnel indicated s station
- would escalate to an. Alert.
Recommended to man the TSC and OSC, was given early thereby allowing the TSC and OSC to be activated within 5 minutes of declaration of the Alert.
. The control personnel are proficient in the use of procedures.
I The control personnel kept the plant informed during the Unusual Event.
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Negative Findings:
l
. TSC was slow or did not provide information on plant status to plant per-sonnel, e.g., steam line break in turbine building was not announced for 20 minutes. No other information was announced inplant.
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It took the TSC 36 minutes to declare a site emergency. Site emergency.-
was required to be declared on a steamline break outside containment with-out isolation.
No habitability surveys were taken in the control room until 2:37.
The function / layout of the TSC should be reviewed.
Insufficient room exists for the TSC and the status boards are inadequate should be separated into different rooms if possible to reduce crowding and noise level.
The Emergency Director spent too much time talking with control room per-sonnel. He should minimize his conversations and allow them to perform their functions.
F.
Chronology Time Observation 6:00 Exercise began.
6:03 Unusual event declared based on issued hurricane warning - Shift Superintendent declared himself the Emergency Director (ED).
Consnenced procedure on severe weather.
6:07 Unusual event announced on plant PA system.
6:08 Consnenced offsite notifications.
6:10 Started the diesel generators.
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Time-Observation 6:15 Loaded diesels. All local agencies had been notified except the NRC. ED wanted to shutdown plant.
i l-6:23 ED recommended to Duty Plant Manager to activate.the TSC and OSC.
l ED directed Shift Supervisor to place all emergency equipment on emergency power supplies and place RCIC on recire.
I ED recognized that a scram would occur if they tried to shutdown.
i ED infonned Load Dispatcher that he wanted to drop to 50% power, and will drop power regardless of Load Dispatcher recommendations.
1 ED's intention was to minimize th'e scram transient by reducing
- power.
l 6:28 Plant notified NRC HQ.
6:30 ED had meeting in control room to discuss plant status and his intentions to shutdown.
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6:35 ED told Load Dispatcher he would drop the load in 5 minutes.
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6:36 Controller had ED keep plant on line for drill scenario.
6:40 Followup notifications completed.
I 6:55 Plant Manager arrived and ED briefed him.
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Time'
-Observation-7:04' PM directed manning of TSC and OSC.
7:05-Shift turnover started, y
17:49 Load reduced 25%.
' 7:53 Wind speed increased to 75 mph. Alert declared.
= 7:55 Plant Manager assumed role of ED.
8:02 TSC activ.1ted.
8:07
- Alert announced on plant PA system.
8:30-Time compression began.
9:00 9:13 Turbine building (TB) panels blown 'off.
Control room requested HP to sample turbine building atmosphere.
9:18 Control room requested OSC sample turbine building atmosphere.
p 9:21-MCC tripped.
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9:30 Shift Supt. discussed LCO's due to loss of MCC.
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. Time Observation 9:41 Scram / loss.of offsite power / main steam line break.
9:49 Determined MSIV A not closed. Turbine building ARM's at 400 mR/hr.
9:57 Shift Supt.: recommended plant depressurized.
10:01 Turbine buf1 ding evacuation ordered.
10:06 Control room rec. mmended declaration of " site area emergency."
10:08 Reactor depressurized.
10:17 Site area emergency declared.
10:30 Control room encountered a problem getting an operator to OSC.
. 10:40 Control room issued 0-5 R dosimeters.
11:15 Main steam ifne break isolated.
No air sample taken in CR, ordered by.
ED at 11:02.
- 11i45 No plant status announcements have been made.
11:58 Site evacuation ordered.
__m_.m.m__. _ _. - - - - -
Time Observation 12:30 Fire announced at pistol range.
12:35 CR and TSC discussed whether or not to fight fire with onsite team.
12:39 Fire brigade leader left for OSC.
12:42 TSC to request offsite assistance to fight fire. Note:
Is fire truck going to pass through plum?
12:51 Discovered fire is real.
1:05 Fire truck left protected area.
1:30 TSC directed HP to measure iodine levels in CR.
1:43 HP sampled control room.
2:27 ED discussed recovery priorities: plug holes in turbine building, regain offsite power, cleanup turbine building, sample turbine i
building sump, control access to turbine building, recharge air bottles, order fuel for diesels.
2:37 CR air sample < MDA (first air sample taken).
3:00 Exercise terminated.
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'A.
Name: George Wehmann B.
Assignment: TSC - all functions C.-
Site Personnel Contacted: Robert Snyder, Controller; Rodney Brown, Controller; Exercise Director.
D.
Positive Findings:.All TSC personnel appeared to understand their assignments and to perform them in an efficient manner. The TSC Emergency
' Director maintained positive control over all operations.
E.
Negative Findiregs:
'The TSC Emergency Director did not recognize the need to elevate the exercise from an Alert to a Site Emergency. He had to receive a " prompt" from the TSC Controller.
Recommended protective actions were not provided offsite organizations until I hr and 45 min after the Site Emergency had been declared. This i
notification is required within 15 minutes.
Radiological release data was not provided to offsite personnel via the q
follow-up notification proceoure until 1144 CST - nearly 2 hr after the release began.
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.TSC-did not dispatch field teams until I hr after release was first recognized.
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.. The site evacuation alarm was not initiated until more than 2 hr and 15 min after the release began.
L The Emergency Director had to be furnished with an offsite dose L
assessment " prompt" message by the. Controller. This message contained information relative to protection action guides.
False dose assessment indications resulted from preliminary " default" method calculations. As a consequence a number of decisions Were delayed or incorrect. The fact that the default values might not be correct was not recognized until 11:02 CST.
The relative concentrations (Chi /Q) at 0.433 miles for a "G" stability index and 4 mph wind speed is 1711 x 10-6 m/sec per plant procedures.
This is a factor of 4.8 times greater than the value of 359 x 10-6 m/sec reported.in the scenario for the very same distance, stability index and wind.
It appears that only two dose assessment calculations were made by TSC using field data prior to assumption of this responsibility by E0F.
The observer was unable to verify the dose calculations made by TSC nor to make an comparative analysis with dose projection data provided in the scenario.
l 1
0 4
- e-Based on this exercise, it appears that the present TSC has certain defici?ncies. An average of 18 players occupied the TSC with no provisions to reduce noise. Telephone and power-cords were laid on top of the rug and several people tripped on them. The loud speakers could not be muted when the evacuation sirens was alarmed.
F.
Chronology Time Observation 1
7:05 Control room Shift Superintendent requested TSC staff to assemble.
7:58 TSC activated - all principal staff present.
8:00 Alert declared.
8:06 Alert announced over PA.
8:44 Dose assessment attempting to make default calculations - trouble getting offgas flowrate.
9:10 Offgas flowrate still a problem - three values reported; 39,100 or 120 scfm.
9:20 Damage to turbine building reported. Emergency Director requested team dispatched from OSC to investigate damage.
9:41.
Report to offsite alarms given to Emergency Director.
Initially treated as a rumor.
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L Time Observation 9:48 Use of.offsite sirens is confirmed.
9:50 Emergency Director receives report of steam line break.
Turbine I
building ARM value is 400 mR/hr.
- 10:02 Evacuation of tui bine building ordered by Emergency Director.
10:12 Upgrade to General-(Site) Emergency decided by Emergency Director.
~
Default dose assessment calculation indicate very low doses.
10:18 Announcement'of Site Emergency made over PA.
10:24-Default dose assessment calculations still indicate very low dose.
10:25 Dose assessment requests source data.
10:40 Offsite monitoring teams dispatched.
10:52 First field data at site boundary received.
10:58 Emergency Director considering protective action recommendations.
11:10 Offsite dose data " prompt" provided the Emergency Director by Controller.
. A.
' Time
' Observation
.11: 11 ~
Offsite. teams having trouble getting into location.
Emergency Director considering' assistance from helicopter, weather permitting.
11:18
.First dose projections using field data become available.
11:20 RPM.and NRC agree that sheltering out to 10 miles should be considered.
11:40 EOF assumes responsibilities of dose assessment.
11:43' Emergency Director makes decision to evacuate site with certain staff personnel to remain behind.
' 12 :01
Site evacuation alarm is activated.
12:15 TSC dose assessment efforts continuing although responsibility has been assumed by EOF.
12:32 TSC receives report of black smoke near site.
12:42 Emergency Director briefed on fires by Controller, Director concerned if fire brigade would have to go through plume.
12:44
' Director orders fire brigade to respond and requests offsite support.
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Time Observation 12:55 Director learns that it is a real fire.and not simulated.
1:10 Emergency Director continues to try to analyze source'of radioactive release.
2:03 Emergency' Director'is considering downgrading of exercise'and commencement of recovery operations.'-
. 3:00 Exercise terminated by Controller.
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. Mississippi Offsito Sequence of Eventy s
i Grand Gulf Nuclear Station Emergency Preparedness Exercise April 10-12, 1984 I
Time Event
]
0530 LIERCISE SECINS.
Distribute initial conditions to key players.
Duty officer makes appropriate notifications based on vaather conditions.
0600 National Weather Service issues severe weather statement.
0615 UNUSUAL ETEKI DECLARED.
Declaration is based on severe weather conditions.
Appropriate notifications are nede based on conditions at GCNS.
l 0645 Reports of flash flooding in claiborne County.
0700 National Weather Service issues severe weather statement.
0730 Reports of tornado sightings in Claiborne County.
0800 ALERI DECLAED.
Declaration is based on severe weather conditions.
Appropriate notifications are made based on conditions at GCNS.
0800 National Weather Service issues severe weather, statement.
0815 Scace communications officer unable to get to Jackson.
0830 TIE COMPESSION.
0840 Loss of power at Claiborne ECC.
0855 Power restored at Claiborne EOC.
i S
0900 National Weather service issues severe weather statement.
091'0 Reports of vind damage in Claiborne County.
0910 Loss of power at State EOC.
0915 RESUME REAL TIE.
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0925 Power restored at S tate EOC.
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'0945 State Communications Officer arrive's at State EOC.
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4 1000 SITE AREA EMERGENCT DECLARED.
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unctatralled, utmonitorsd relocse.
The ralcosa inventory is 4.
high in iodines. -Projected thyroid. dose should result in a recommendation for sheltering out to two miles in sector 8, which will af fect protective action area 1.
1015 Activation of sirens, tone alert receivers, and EBS.
1050 Report that portions of Highway 13 are washed out.
i 1100 Reperc of a fire in Port Gibson.
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1105 Reports of debris blocking roads.
1115 Reports of fallen power lines.
l 112,5 Inquiry about protecting dairy cattle.
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1135 Report of a fire in the county.
- 1 1140 Possible problems with water system contamination.
1145 warren County shelters request that arrangements be made for 1-substitute clothing.
1150 Claiborne County Bospital needs portable generators due 'to j
power failure and problems with existing generators.
1155 Requests for transportation assistance.
1200 Evaluate copiah County shelters.
1200 Reports of spontaneous evacuation.
t 1205 Fire in Port Gibson reported out.
1205 Local industry requests information on how to shut down during sheltering.
1210 Health Department requests Wildlife Conservation to arrange for boats and personnel to support sampling activities.
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1220 Inquiry'about the availability of stored feed.
I 1230 Reports that gasoline supplies are low.
3 1240 GGNS Bet-Line communications lost.
1240 Fire in county reported out.
1245 claiborne County Rospital requests that ambulances be arranged for evacuating patients if neccesary.
1250 inquiry about protecting unharvested crop.
8
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