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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20195C3041999-05-28028 May 1999 Annual Rept on ABB CE ECCS Performance Evaluation Models ML20204H1401999-03-23023 March 1999 Rev 1 to Engineering Rept C-NOME-ER-0120, Design Evaluation of Various Applications at Waterford Unit 3 ML20204H2451999-03-22022 March 1999 Rev 2 to C-NOME-SP-0067, Design Specification for Mechanical Nozzle Seal Assembly (Mnsa) Waterford Unit 3 ML20204H1231999-03-22022 March 1999 Rev 1 to Design Rept C-PENG-DR-006, Addendum to Cenc Rept 1444 Analytical Rept for Waterford Unit 3 Piping ML20198H3911998-07-14014 July 1998 Non-proprietary Rev 5 to HI-961586, Thermal-Hydraulic Analysis of Waterford-3 Spent Fuel Pool ML20248E7781998-06-0101 June 1998 Annual Rept on ABB CE ECCS Performance Evaluation Models ML20198H4681998-05-20020 May 1998 Non-proprietary Rev 1 to HI-981942, Independent Review of Waterford Unit 3 Spent Fuel Pool Cfd Model ML20247A3891998-05-0101 May 1998 SG Eddy Current Examination (8th Refueling Outage) ML20199F5831998-01-29029 January 1998 Errata Change Pages for Rept HI-971628,for Section 8.6.1.2 & Table 8.1.Change Pages Submitted to Assure Consistency Between LAR & Calculations Performed for SFP Structural Analysis ML20198H4641998-01-28028 January 1998 Non-proprietary Rev 1 to HI-91700, Dynarack Validation Manual ML20141G7081997-07-0505 July 1997 To Rept on Vortexing in Condensate Storage Pool ML20140F1491997-04-16016 April 1997 Rev 3 to 10CFR50.59 Safety Evaluation ML20137G2141997-03-27027 March 1997 Non-proprietary Version of Licensing Rept for Reracking of Waterford 3 Sfps ML20094H4141995-11-0303 November 1995 Thermo-Lag Installed to Tested Fire Barrier Evaluation (GL 86-10 Evaluation) ML20086T3561995-07-31031 July 1995 Individual Plant Exam for External Events ML20094H4001995-05-30030 May 1995 Pyrolysis Gas Chromatography Analysis of 3 Thermo-Lag Fire Barrier Samples ML20078F1001995-01-31031 January 1995 Summary of Waterford 3 Criticality Safety Analysis for Fuel Enrichments Above 4.1 W/O U-235 Taking Credit for Fixed Burnable Poisons ML20078Q2951994-11-0909 November 1994 3 Ses Tsc/Osc Tabletop 4,941109 ML20078Q3111994-11-0707 November 1994 3 Ses EOF Tabletop 4,941107 ML20078Q2851994-10-12012 October 1994 3 Ses Tsc/Osc Tabletop 3,941012 ML20078Q3051994-10-10010 October 1994 3 Ses EOF Tabletop 3,941010 ML20078Q2741994-09-20020 September 1994 3 Ses Tsc/Osc Tabletop 2,940920 ML20078Q3021994-08-15015 August 1994 3 Ses EOF Tabletop 2,940815 ML20078Q2731994-05-25025 May 1994 3 Ses Tsc/Osc Tabletop 1,940525 ML20078Q3001994-05-23023 May 1994 3 Ses EOF Tabletop 1,940523 ML20062M1441993-12-29029 December 1993 Section 6.0 of Development of RCS Pts...& Recommended Surveillance Withdrawal Schedule for Waterford Unit 3 ML20059D3971993-10-31031 October 1993 Rev 0 to Development of RCS Pressure Temp Limits for 20 EFPYs (Fluence = 2.29 X 10(19) n/cm(2)) & Recommended Surveillance Withdrawal Schedule for Waterford Unit 3, Final Rept ML20198H3711991-11-12012 November 1991 Non-proprietary HI-91700, Dynarack Validation Manual ML20086C4241991-09-0505 September 1991 Design Engineering Program Assessment Executive Summary ML20073K8451991-03-31031 March 1991 Entergy Nuclear Performance Rept,Mar 1991 ML20199F5531991-03-31031 March 1991 Chin Shan Analyses Show Advantages of Whole Pool Multi-Rack Approach, from Nuclear Engineering International,Mar 1991 ML20072R2261991-03-20020 March 1991 3 Plant Ref Simulator Certification Package ML20056A7301990-06-30030 June 1990 Basemat Monitoring Program Special Rept 3 ML20246P2561989-07-31031 July 1989 Compliance W/10CFR50.62 Reduction of Risk from ATWS Events ML20245J5071989-07-31031 July 1989 Unit 3 Control Element Assembly Drop Time Tech Spec Change Justification ML20155E1311988-10-31031 October 1988 Compliance W/10CFR50.62,Reduction of Risk from ATWS Events ML20207L2881988-09-30030 September 1988 Basemat Monitoring Program,Special Rept 2, from Inception to Aug 1988 ML20155B7181988-09-0909 September 1988 Rev 1 to Louisiana Power & Light Co Response to US-NRC Bulletin 88-005 ML20154D0571988-09-0909 September 1988 Actions Completed by Louisiana Power & Light Co ML20151F1771988-06-30030 June 1988 1987 SALP Progress Rept Updated June 1988 ML20195G8941988-06-20020 June 1988 MSIV Guide Rail Failure Final Rept ML20151B7901988-03-31031 March 1988 1987 SALP Progress Rept W3P87-1746, Emergency Preparedness Exercise1987-10-14014 October 1987 Emergency Preparedness Exercise ML20234C1501987-07-31031 July 1987 Basemat Summary Rept ML20214M5571987-05-27027 May 1987 Draft Waterford 3 Nuclear Plant Island Structure Basemat Summary Rept. W/Two Oversize Figures ML20198H4061987-04-30030 April 1987 Non-proprietary HI-87113, Evaluation of Fluid Flow for In- Phase & Out-of-Phase Rack Motions ML20198H4421987-04-0707 April 1987 Non-proprietary HI-87112, Fluid Flow in Narrow Channels Surrounding Moving Rigid Bodies ML20198H4121987-04-0707 April 1987 Non-proprietary HI-87114, Estimated Effects of Vertical Flow Between Racks & Between Fuel Cell Assemblies ML20198H4371987-01-14014 January 1987 Non-proprietary HI-87102, Study of Non-Linear Coupling Effects ML20215N4601986-10-0101 October 1986 Program to Perform Confirmatory Analyses,Nuclear Plant Island Structure Basemat:Results of Analyses 1999-05-28
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F2891999-10-13013 October 1999 Drill 99-08 Emergency Preparedness Exercise on 991013 05000382/LER-1999-014, :on 990910,reactor Shutdown Due to Loss of Controlled bleed-off Flow,Occurred.Caused by Rotating Baffle failure.Two-piece Rotating Baffle of Original Design Was Located & Installed,In Order to Repair RCP 2B1999-10-12012 October 1999
- on 990910,reactor Shutdown Due to Loss of Controlled bleed-off Flow,Occurred.Caused by Rotating Baffle failure.Two-piece Rotating Baffle of Original Design Was Located & Installed,In Order to Repair RCP 2B
ML20217G7211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with 05000382/LER-1999-013, :on 990825,exceeding TS Limits for RCS Cooldown Rate Was Discovered.Caused by Inadequate Content & Inadequate Implementation of TS Requirements.Page 2 of 2 in Attachment 2 of Incoming Submittal Not Included1999-09-23023 September 1999
- on 990825,exceeding TS Limits for RCS Cooldown Rate Was Discovered.Caused by Inadequate Content & Inadequate Implementation of TS Requirements.Page 2 of 2 in Attachment 2 of Incoming Submittal Not Included
05000382/LER-1999-012-01, :on 990812,potential Operation with Both Control Room Normal Outside Air Intakes Valves Inoperable Occurred.Cause for Event Was Indeterminate.Seat Leakage Requirements Calculated.With1999-09-13013 September 1999
- on 990812,potential Operation with Both Control Room Normal Outside Air Intakes Valves Inoperable Occurred.Cause for Event Was Indeterminate.Seat Leakage Requirements Calculated.With
ML20211Q2141999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With 05000382/LER-1999-011-01, :on 990801,with Plant Operating 100% Power, Lowering RCP Seal Pressures,Along with Dropping Controlled bleed-off (Cbo) & Increasing Cbo Temp Discovered.Caused by fatigue-induced Failure of Rotating Baffle of RCP 2B1999-08-31031 August 1999
- on 990801,with Plant Operating 100% Power, Lowering RCP Seal Pressures,Along with Dropping Controlled bleed-off (Cbo) & Increasing Cbo Temp Discovered.Caused by fatigue-induced Failure of Rotating Baffle of RCP 2B
05000382/LER-1999-010-01, :on 990726,discovered Inadequate Pumping Capacity in Dry Cooling Tower Area.Caused by Inadequate Design Control.Portable Pumps Were Installed in Each Dry Cooling Tower Areas to Ensure Sufficient Pumping Capacity1999-08-26026 August 1999
- on 990726,discovered Inadequate Pumping Capacity in Dry Cooling Tower Area.Caused by Inadequate Design Control.Portable Pumps Were Installed in Each Dry Cooling Tower Areas to Ensure Sufficient Pumping Capacity
05000382/LER-1999-009-01, :on 990727,discovered App R Noncompliance Condition Involving Inadequate Separation of Safe Shutdown Cables.Caused Design Analysis Deficiency.Compensatory Measures Were Established1999-08-26026 August 1999
- on 990727,discovered App R Noncompliance Condition Involving Inadequate Separation of Safe Shutdown Cables.Caused Design Analysis Deficiency.Compensatory Measures Were Established
ML20210Q6361999-07-31031 July 1999 Corrected Monthly Operating Rept for July 1999 for Waterford 3 ML20210S0581999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Waterford 3.With 05000382/LER-1999-008-01, :on 990629,failure to Perform Testing of ESF Filtration Units Per TS Was Noted.Cause for Testing Charcoal Samples Contrary to TS Could Not Be Determined.All Future Analysis Will Be Performed IAW ASTM D3803-1989,per GL 99-021999-07-29029 July 1999
- on 990629,failure to Perform Testing of ESF Filtration Units Per TS Was Noted.Cause for Testing Charcoal Samples Contrary to TS Could Not Be Determined.All Future Analysis Will Be Performed IAW ASTM D3803-1989,per GL 99-02
05000382/LER-1999-007-01, :on 990625,operation Outside Tornado Missile Protection Licensing Basis for turbine-driven EFW Pump & Steam Supply Piping,Was Discovered.Caused Indeterminent. Entergy Will Submit 10CFR50.90 to NRC Staff1999-07-23023 July 1999
- on 990625,operation Outside Tornado Missile Protection Licensing Basis for turbine-driven EFW Pump & Steam Supply Piping,Was Discovered.Caused Indeterminent. Entergy Will Submit 10CFR50.90 to NRC Staff
ML20210D8951999-07-23023 July 1999 Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020 05000382/LER-1999-006-01, :on 990614,plant Experienced Automatic Reactor Trip Following Loss of 7kV Bus.Caused by Spurious Actuation of Relay on Either RCP 1A or 2A.Personnel Performed Final Switchgear Walkdown with Indications Normal.With1999-07-14014 July 1999
- on 990614,plant Experienced Automatic Reactor Trip Following Loss of 7kV Bus.Caused by Spurious Actuation of Relay on Either RCP 1A or 2A.Personnel Performed Final Switchgear Walkdown with Indications Normal.With
ML20209H3781999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Waterford 3 Ses. with 05000382/LER-1999-005-01, :on 980702,determined That Four Contacts in Control Circuits of EFW Control Valves Were Untested.Caused by Personnel Error.Untested Contacts Have Been Tested1999-06-24024 June 1999
- on 980702,determined That Four Contacts in Control Circuits of EFW Control Valves Were Untested.Caused by Personnel Error.Untested Contacts Have Been Tested
ML20195J8951999-06-17017 June 1999 Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii) ML20195J9741999-06-16016 June 1999 Safety Evaluation Supporting Amend 152 to License NPF-38 ML20207E8631999-06-0303 June 1999 Safety Evaluation Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressure Safety Valves at Plant,Unit 3 ML20195D5491999-06-0303 June 1999 Safety Evaluation Supporting Amend 151 to License NPF-38 ML20195K3391999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Waterford 3 Ses.With ML20195C3041999-05-28028 May 1999 Annual Rept on ABB CE ECCS Performance Evaluation Models 05000382/LER-1999-004-02, :on 990415,discovered That Complete Response Time for ESFAS Containment Cooling Function Had Not Been Performed.Caused by Response Time Testing Deficiency. Procedures Will Be Revised to Include Subject Testing1999-05-14014 May 1999
- on 990415,discovered That Complete Response Time for ESFAS Containment Cooling Function Had Not Been Performed.Caused by Response Time Testing Deficiency. Procedures Will Be Revised to Include Subject Testing
ML20206S7401999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Waterford 3.With ML20205T2621999-04-22022 April 1999 LER 99-S02-00:on 990216,contract Employee Inappropriately Granted Unescorted Access to Plant Protected Area.Caused by Personnel Error.Security Personnel Performed Review of Work & Work Area That Individual Was Involved with ML20206A9641999-04-21021 April 1999 Safety Evaluation Supporting Amend 150 to License NPF-38 05000382/LER-1999-003-02, :on 990311,determined That Four Containment Vacuum Relief valves,CVR-101,CVR-201,CVR-102 & CVR-202,were Not Tested.Caused by Contractor Supply of Misinformation. Details of Event Discussed with Contractor.With1999-04-0909 April 1999
- on 990311,determined That Four Containment Vacuum Relief valves,CVR-101,CVR-201,CVR-102 & CVR-202,were Not Tested.Caused by Contractor Supply of Misinformation. Details of Event Discussed with Contractor.With
ML20205N9671999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Waterford 3 Ses.With ML20205E8531999-03-30030 March 1999 Corrected Pages COLR 3/4 1-4 & COLR 3/4 2-6 to Rev 1, Cycle 10, Colr ML20205A6331999-03-25025 March 1999 SER Accepting Request to Use Mechanical Nozzle Seal Assemblies as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Applications at Plant,Unit 3 05000382/LER-1999-002-03, :on 990225,discovered RCS Pressure Boundary Leakage on Two Inconel 600 Instrument Nozzles.Caused by Axial Cracks Near HAZ of Nozzle Partial Penetration Welds Resulting from Pwscc.Leaking Nozzles Have Been Repaired1999-03-25025 March 1999
- on 990225,discovered RCS Pressure Boundary Leakage on Two Inconel 600 Instrument Nozzles.Caused by Axial Cracks Near HAZ of Nozzle Partial Penetration Welds Resulting from Pwscc.Leaking Nozzles Have Been Repaired
ML20204H1401999-03-23023 March 1999 Rev 1 to Engineering Rept C-NOME-ER-0120, Design Evaluation of Various Applications at Waterford Unit 3 ML20204H1231999-03-22022 March 1999 Rev 1 to Design Rept C-PENG-DR-006, Addendum to Cenc Rept 1444 Analytical Rept for Waterford Unit 3 Piping ML20204H2451999-03-22022 March 1999 Rev 2 to C-NOME-SP-0067, Design Specification for Mechanical Nozzle Seal Assembly (Mnsa) Waterford Unit 3 ML20204F0791999-03-17017 March 1999 Rev 1 to Waterford 3 COLR for Cycle 10 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207F3491999-03-0505 March 1999 LER 99-S01-00:on 990203,contraband Was Discovered in Plant Protected Area.Bottle Was Determined to Have Been There Since Original Plant Construction.Bottle Was Removed & Security Personnel Performed Search of Area.With ML20204B5141999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Waterford 3.With ML20203H8151999-02-17017 February 1999 Safety Evaluation Supporting Amend 149 to License NPF-38 ML20203H8591999-02-17017 February 1999 Safety Evaluation Accepting Licensee Second Ten Year ISI Program & Associated Relief Requests for Plant,Unit 3 05000382/LER-1999-001, :on 990105,TS 3.0.3 Was Entered.Caused by Less than Adequate Chiller Thermostat Control.Placed Tamper Seal on Chiller Thermostat.With1999-02-0404 February 1999
- on 990105,TS 3.0.3 Was Entered.Caused by Less than Adequate Chiller Thermostat Control.Placed Tamper Seal on Chiller Thermostat.With
ML20202H9161999-02-0202 February 1999 Safety Evaluation Supporting Amend 148 to License NPF-38 ML20199H6261999-01-21021 January 1999 Safety Evaluation Accepting Classification of Instrument Air Tubing & Components for Safety Related Valve Top Works.Staff Recommends That EOI Revise Licensing Basis to Permit Incorporation of Change 05000382/LER-1998-020, :on 981204,determined That Certain Core Power Distribution SRs Had Been Incorrectly Scheduled.Caused by TS Change Implementation Error.Will Perform Final Review of TS SRs with 4.0.4 Exemption.With1998-12-31031 December 1998
- on 981204,determined That Certain Core Power Distribution SRs Had Been Incorrectly Scheduled.Caused by TS Change Implementation Error.Will Perform Final Review of TS SRs with 4.0.4 Exemption.With
ML20199C9101998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Waterford 3.With ML20198F4691998-12-21021 December 1998 Safety Evaluation Supporting Amend 147 to License NPF-38 ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20206N4131998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Waterford 3.With ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program 1999-09-30
[Table view] |
Text
p 4
WATERFORD-3 STEAM ELECTRIC STATION EOF TABLETOP #4 NOVEMBER 7,1994 Approval:
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Emergency Planning Managei Approval:
N/A General Manager Plant Operations Approval:
N/A Vice President Operations 9412220063 941216
$DR ADOCK 0500 2
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WATERFORD 3 SES EOF TABLETOP M
^
NOVEMBER 7,1994 W3 SES EMERGENCY PREPAREDNESS DRILL CUE CARD DRILL TYPE /NO.
EOF TABLETOP M CUE CARD NO.
2 TO:
All Participants TIME:
N/A FROM:
Lead Controller T=
N/A
--____--_= -___--
THIS IS A DRILL l
DO NOT initiate actions affecting normal plant operationa ANNUAL EXERCISE LESSONS LEARNED:
NRC WEAKNESSES: (Refer to Weakness Response Letter W3F1-93-0374)
- 1. The issuance of Protective Action Recommendations (PARS), the failure to follow applicable procedures for completing notification messages containing PARS, and the failure to receive i
the Emergency Coordinator's approval to modify previously approved PARS were identified as an exercise weakness.
j
- 2. The inability to timely assess the source of the release and implement mitigation strategies I
was identified as a weakness.
EOF IMPROVEMENT ITEMS: (Refer to W3 exercise report and NRC report.)
- 1. Although plant page announcements were frequently made to update plant personnel on 1
the status of the emergency, plant personnel were not informed of the identity of the person making the announcement, their emergency position or their emergency facility. This is also a good practice during "round table" status briefings, especially if personnel from the NRC or other agencies are present.
4
- 2. Transfer of responsibilities from the TSC to the EOF could have been performed more efficiently, especially transfer of communications.
- 3. The TSC did not always keep the EOF ir6med of their activities in a timely manner. For example, the EOF asked at least three times Mr the status of Containment isolation. The EOF personnel could have been more aggressive in pursuing information and the EOF Director did not ensure that the EOF staff was p arsuing completion of high priority assessment and mitigation activities.
- 4. Status boards were not maintained after the docluation of General Emergency. The NRC noted the PARS were not kept current on the dose assessment status boards.
S. EOF access was not maintained during the exercise.
- 6. Several EOF personnel did not follow posted instructions for frisking (turning up the frisker volume, etc.).
- 7. Discuss the importance of the EOF Director contacting the duty Emergency Planner. (Refer to Event Report 94-01.)
- 8. There was some confusion relating to computerized dose assessment results from montioring teams outside of the plume.
.,L' WATERFORD 3 SES EOF TABLETOP M NOVEMBER 7,1994 W3 SES EMERGENCY PREPAREDNESS DRILL CUE CARD DRILL TYPE /NO.
EOF TABLETOP #4 CUE CARD NO.
2 TO: All Participants TIME:
N/A FROM:
Lead Controller T=
N/A THIS IS A DRILL DO NOT initiate actions affecting normal plant operations
= _ = __--- _--__-- _--_ _
1 ANTICIPATED RESPONSE COMMENTS Participants should be encouraged to ask questions or comment on the issues discussed.
INSTRUCTIONS
- 1. The Lead Controller will use the Response to the NRC to discuss the NRC Weaknesses in detail.
- 2. The Lead Controller will use the W3 exercise report and the NRC report to discuss the improvement items in detail.
- 3. The Lead Controller will use Event Report 94-01 to discuss the problem in contacting the duty Emergency Planner.
- 4. The Lead Controller should also discuss the changes being made to EP-001-001 as a result of the recent NRC inspection. Additional indicators are being added to the three barrier General Emergency EALs to clarify how to determine if the cladding i
barrier has been breached.
- 5. The Lead Controller may discuss additional improvement items at his discretion.
,' ~
WATERFORD 3 SES EOF TABLETOP #4
- ~
NOVEMBER 7,1994 W3 SES EMERGENCY PREPAREDNESS DRILL CUE CARD DRILL TYPE /NO.. EOF TABLETOP #4 CUE CARD NO.
3 TO:
All Participants TIME:
N/A FROM:
Lead Controller T=
N/A
= _. - ____ _- ___ - _ -
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations i
i The following three practice scenarios will be provided to the participants to discuss Protective Action Recommendations:
i
- 1. Scenario #1 You have just declared a General Emergency due to a LOCA with cladding damage and Containment pressure of 36 psi and increasing. The wind is from 202 degrees at 3 miles per hour.
- 2. Scenario #2 A General Emergency was declared due to a dose projection calculation as follows:
TDE CDE EAB 7334 MR 8692 MR 2 miles 611 MR 724 MR 5 miles 105 MR 105 MR 10 miles 56 MR 87MR Wind direction is from 18 degrees at 2 miles per hour.
- 3. Scenario #3 A General Emergency had been declared 45 minutes ago and the minimum PARS provided to the offsite agencies. New dose projection information is received as follows:
TDE CDE EAB 14,325 MR 170,402 MR 2 miles 3,539 MR 42,099 MR 5 miles 1,112 MR 13,231 MR 10 miles 471 MR 5613 MR Wind direction is from 180 degrees at 6.3 miles per hour.
WATERFORD 3 SES EOF TABLETOP #4 NOVEMBER 7,1994 W3 SES EMERGENCY PREPAREDNESS DRILL CUE CARD DRILL TYPE /NO.
EOF TABLETOP #4 CUE CARD NO.
3 TO:
All Participants TIME:
N/A FROM:
Lead Controller T=
N/A
= = =____________-_____-____ _____________ _____________ ___________________
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = = = _ _ _
ANTICIPATED RESPONSE
- 1. Scenario #1 Participants should recommend: Evacuation for A1, B1, C1, D1, A2 & B2 and; Shelter for the rest of the sectors (A3, A4, B3, B4, C2, C3, C4, D2, D3, & D4)
- 2. Scenario #2 Participants should recommend: Evacuation for A1, B1, C1, D1, C2, & D2 and; Shelter for the rest of the sectors (A2, A3, A4, B2, B3, B4, C3, C4, D3 & D4)
- 3. Scenario #3 Participants should recommend: Evacuation for A1, B1, C1, D1, A2, C2, A3 & A4 and; Shelter for the rest of the sectors (B2, 83, B4, C3, C4, D2, D3, & D4)
COMMENTS The scenarios are not related to each other. They are individual sets of conditions.
INSTRUCTIONS
- 1. Provide the conditions for each scenario and instruct the participants to determine the correct PARS.
l
- 2. Encourage the participants to use EP-002-052 for these practice scenarios.
I
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NUCLEAR OPERATIONS TRANNG DEPARTMENT ATTENDANCE RECORD CLASS TITLE:
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