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Category:EMERGENCY EXERCISE SCENARIO
MONTHYEARML20151C4121988-07-12012 July 1988 Rev 0 to Northern States Power Co Section V:Exercise Scenario,Part 1:Narrative Summary 1988-07-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G4461999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pingp.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20216E7151999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pingp,Units 1 & 2. with ML20211D3981999-08-24024 August 1999 Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively ML20211C2531999-08-0404 August 1999 Unit 1 ISI Summary Rept Interval 3,Period 2 Refueling Outage Dates 990425-990526 Cycle 19 971212-990526 ML20210Q4891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with ML20211B5971999-07-31031 July 1999 Cycle 20 Voltage-Based Repair Criteria 90-Day Rept ML20209J1131999-07-15015 July 1999 Safety Evaluation of Topical Rept NSPNAD-8102,rev 7 Reload Safety Evaluation Methods for Application to PI Units. Rept Acceptable for Referencing in Prairie Island Licensing Actions ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209F9811999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196F4081999-06-23023 June 1999 Revised Pages 71,72 & 298 to Rev 7 of NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units ML20195G5181999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With . Page 3 in Final Rept of Incoming Submittal Was Not Included ML20207B5931999-05-26026 May 1999 SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs ML20196L2501999-05-13013 May 1999 Rev 0 to PINGP Unit 1 COLR Cycle 20 ML20206L6191999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pingp,Units 1 & 2. with ML20205N1081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pingp,Units 1 & 2. with ML20205Q5101999-03-15015 March 1999 Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327-981229 ML20207J6951999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Prairie Island Nuclear Generating Plant ML20202J7711999-02-0404 February 1999 Simulator Certification Rept for Prairie Island Plant Simulation Facility,1998 Annual Rept ML20202G3761999-01-31031 January 1999 Non-proprietary Rev 7 to NSPNAD-8102-NP, Prairie Island Nuclear Power Plant Reload SE Methods for Application to PI Units ML20207L2811999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for Pingp,Units 1 & 2 ML20202J1731999-01-22022 January 1999 Safety Evaluation Concluding That NSP Proposed Alternative to Surface Exam Requirements of ASME BPV Code for CRD Mechanism Canopy Seal Welds Will Provide Acceptable Level of Quality & Safety ML20206P7861998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Prairie Island Nuclear Generating Plant.With ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20198J6441998-12-17017 December 1998 Rev 0 to PINGP COLR Unit 2-Cycle 19 ML20206N2731998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196D7341998-11-20020 November 1998 Third Quarter 1998 & Oct 1998 Data Rept for Prairie Island Isfsi ML20155K6301998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20154H4061998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Prairie Island Nuclear Generating Plant.With ML20202J7991998-09-30030 September 1998 Non-proprietary Version of Rev 3 to CEN-629-NP, Repair of W Series 44 & 51 SG Tubes Using Leaktight Sleeves,Final Rept ML20198P0571998-09-0303 September 1998 Rev 1 to 95T047, Back-up Compressed Air Supply for Cooling Water Strainer Backwash Valve Actuator ML20153B0761998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Prairie Island Nuclear Generating Plant.With ML20237A3961998-08-11011 August 1998 Safety Evaluation on Westinghouse Owners Group Proposed Insp Program for part-length CRDM Housing Issue.Insp Program for Type 309 Welds Inadequate from Statistical Point of View ML20237A8171998-08-0505 August 1998 SER Related to USI A-46 Program GL 87-02 Implementation for Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20236X8531998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Prairie Island Nuclear Generating Plant ML20236R6481998-07-15015 July 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at PINGP Unit 2 - Preliminary Summary Rept ML20236R0771998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Prairie Island Nuclear Generating Plant ML20249A5751998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Prairie Island Nuclear Generating Plant ML20247G7011998-05-31031 May 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at Prairie Island Nuclear Generating Plant,Unit 2 ML20248M0561998-05-31031 May 1998 Rev 5 to CEN-620-NP, Series 44 & 51 Design SG Tube Repair Using Tube Rerolling Technique ML20247E2671998-05-0505 May 1998 Rev 0 to Pingp,Units 1 & 2,Pressure & Temp Limits Rept (Effective Until 35 Efpy) ML20247G2921998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Prairie Island Nuclear Generating Plant ML20217M6901998-04-29029 April 1998 Safety Evaluation Accepting Methodology for Relocation of Reactor Coolant Sys P/T Limit Curves & LTOP Sys Limits Proposed by NSP for Pingp,Units 1 & 2 ML20216C6361998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Prairie Nuclear Generating Plant Units 1 & 2 ML20216H0341998-03-31031 March 1998 Cycle-19 Voltage Based TSP Alternate Repair Criteria 90-Day Rept ML20217D2041998-03-13013 March 1998 Rev 1 to 28723-A, Intake Canal Liquefaction Analysis Rept for Pingp,Welch,Mn ML20236P9801998-03-12012 March 1998 Rev 0 to 97FP02-DOC-01, Compliance Review of 10CFR50,App R, Section Iii.O RCP Lube Oil Collection Sys ML20248L3931998-03-10010 March 1998 ISI Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 971018-971212 Cycle 18,960303-971212 ML20216D0911998-03-0606 March 1998 Rev 0 to Prairie Island Generating Plant,Units 1 & 2, Pressure & Temp Limits Rept 1999-09-30
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT l 4
EMERGENCY PLAN EXERCISE Rev. 0 1988 l
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NORTHERN STATES POWER COMPANY j SECTION V: EXERCISE SCENARIO PART 1: NARRATIVE
SUMMARY
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O PITC/EPLAN Page 1 of 4 SECTION V Part 1 l 8807210350 880712 PDR ADOCK 05000282 Q PDC ]
. G PRAIRIE ISLAND NUCLEAR GENERATING PLANT .
EMERGENCY PLAN EXERCISE Roy. 0 .
1988 TIME EVENT 0700 INITIAL CONDITIONS
- 1. Units 1 & 2 have been operating at 100% power for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
- 2. 0.1 gpm leak on 1. . ?ince June 18.
- 3. Anticipate shutdown in about four hours.
- 4. VCT is at 85% for degas operations.
- 5. Unit 1 is at Middle of core life.
- 6. 12 Charging pump is 00S for cracked pump casing.
- 7. 13 Heater Drain Pump is 00S for PM.
- 8. 11 Safety Injection Pump is DOS due to leaking discharge flange. i l
- 9. Wind is from East Southeast (105') at 0.5 mph.
Temperature is 66'F.
0730 An element of the Reactor Coolant System (RCS) breaks loose causing a Digital Metal Impact Monitoring System (DMIMS) alarm and fuel damage. Some fuel damage occurs with channel blockage and localized overheating.
Auxiliary Building Operator reports the DMIMS alarm to the control room. 1 0745 The damaged fuel causes a rise in RCS activity which in turn causes the letdown radiation monitor R9 to alarm
(> 1R/Hr.).
The primary to secondary leak increases to approximately 75 gpm.
0800 An Alert is declared due to F3-2 Condition 2 and the plant begins an orderly shutdown.
0815 States and counties have been notified of Alert.
A steam generator tube rupture occurs. This initiates SI. 12 SI pump trips, 11 charging pump fails to minimum speed, 13 charging pump trips.
0830 Declare a Site Area Emergency due to F3-2 Condition 2.
Initiate a plant evacuation.
O PITC/EPLAN Page 2 of 4 SECTION V Part 1
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(IE. ISLAND NLCLEAR- GENERATING PLANT
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i* - EMERGENCY PLAN EXERCISE Rov 0 1988-TIME CONDITION 0900 TSC is fully operational.
1000 EOF is fully functional.
A steam line break occurs upstream of the MSlV.. PORV _
piping breaks on 4th floor. R22 and R50 alarm. A significant radioactive release to the environment is occurring.
1015 A General Emergency is declared based on Condition 6 Case 5.
1130 Plant is cooling towards shutdown.
1200 Exercise stops for 24-hour Time Step.
All EOCs review new conditions, emergency status, and odate status boards.
New Conditions: 1230 June 23, 1988
- 1. No significant radioactive release from site is occurring.
- 2. Affected unit is in cold shutdown condition.
O 3. Reactor is on RHR cooling and stable.
- 4. Broken steam line has been temporarily sealed.
- 5. Offsite ambient dose rates are t.ormal background.
The radioactive plume has dispersed.
- 6. The event classification was de-escalated to a Site Area Emergency at 0400 this morning, i 7. Offsite Protective Actions remain in effect.
1230 Restart of Exercise.
Coctrol Room and OSC personnel may terminate exercise involvement.
TSC and EOF discuss new conditions and Recovery efforts.
O PITC/EPLAN Page 3 of 4 SECTION V Part 1
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT . .-
EMERGENCY PLAN EXERCISE Rev. 0
1330 Full analysis of offsite radiological data complete.
NSP and States agree return / reentry of public is perm'is-sible. Protective Actions are cancelled. !
. . . . try news briefings conducted at MN JPIC.
1430 All EOCs close out. Exercise is terminated.
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1 PITC/EPLAN Page 4 of 4 SECTION V Part 1 )