Overview of 08/23/11 Earthquake Response and Restart Readiness Demonstration Plan. North Anna Power Station Units 1 and 2
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1 Overview of 08/23/11 Earthquake Response and Restart Readiness Demonstration Plan North Anna Power Station Units 1 and 2
2 Introduction and Agenda Gene Grecheck Vice President, Nuclear Development
3 Agenda Overview of Event Station ISFSI Seismic Results Restart Readiness Demonstration Plan Results to Date Restart Schedule Summary Questions 3
4 Overview of Event Fred Mladen Director, Station Nuclear Safety and Licensing
5 Overview of Event Quake Epicenter (~Eleven miles southwest of North Anna Power Station) 5
6 Sequence of Events 08/23/11 Both units at 100% power; U1 Turbine Driven AFW pump removed from service for scheduled surveillance test 13:51:00 Magnitude 5.8 earthquake with epicenter near Mineral, Va. 13:51:11 Reactor Trip Breakers open on negative flux rate trip (Both Units Mode 3) 13:51:12 Transformers 1-EP-MT-1A, 2-EP-MT-1A,1B, 1C, all RSSTs, 1-EP-SST-1C and Switchyard Transformer #2 tripped due to sudden pressure relay actuations (Loss of offsite power) 13:51:20 All four EDGs auto start and energize their respective emergency buses 6
7 North Anna Electrical Distribution System 7
8 Sequence of Events 14:03 ALERT declared Tab HA6.1, Shift Manager judgment 14:19 1-FW-P-2 available (flowing to A S/G) 14:40 2H EDG manually tripped on coolant leak 2H Emergency Bus de-energized 14:55 ALERT declared Tab SA1.1 U2 AC capability reduced to a single source (2J EDG) 15:18 2H Emergency Bus re-energized by the Station Blackout (SBO) Diesel 8
9 Sequence of Events 17:23 Energized C RSST and F transfer bus 17:40 2J emergency bus transferred to C RSST 17:48 1H energized from F transfer bus, securing 1H EDG 20:03 B RSST energized 20:17 A RSST energized 22:58 Offsite power supplying Emergency Busses, 3 EDGs and SBO diesel in Auto and available 9
10 Sequence of Events 8/24/11 08:51 Commenced Unit 1 cooldown 11:16 Downgrade to NOUE under Tab HU1.1 13:15 NOUE terminated 13:34 Unit 1 in Mode 4, Hot Shutdown 21:26 Unit 1 in Mode 5, Cold Shutdown 10
11 Sequence of Events 8/25/11 01:08 NOUE declared under Tab HU1.1(aftershock) 11:37 Commenced Unit 2 cooldown 16:22 Unit 2 in Mode 4, Hot Shutdown 8/26/11 14:05 NRC notification EP criteria seismic activity >OBE met but not declared (EAL HA6.1 versus HA1.1) 16:23 NRC notification of potential unanalyzed condition (DBE above 5 Hz) 20:38 Unit 2 in Mode 5, Cold Shutdown 11
12 Sequence of Events 8/28/11 15:36 NOUE terminated 9/1/11 05:18 NOUE Declared, tab HU1.1 (aftershock) 12:23 NOUE terminated 12
13 U2 Turbine Building Powdex Demineralizer Tanks (Non-safety Related) 13
14 U2 Turbine Building Powdex Demineralizer Tanks Base Pedestal (Non-safety Related) 14
15 Unit 1 Containment Seal Table Room (Interior Wall) 15
16 Unit 1 Containment Seal Table Room Excavated Section 16
17 Dry Cask Storage Pad No.1 25 of 27 TN-32 casks shifted during earthquake Largest shift was 4.5 on TN No alarms were received, alarm panel test sat Radiological conditions were normal 6 pairs of casks <16 center to center Confirmed all cask heat loads <27.1 KW, therefore, minimum 16 spacing requirement not applicable Evaluating possible cask movement following aftershocks 17
18 Dry Cask Storage Pad No. 1 18
19 TN Cask Movement 19
20 Dry Cask Storage Pad No. 2 NUHOMS Horizontal Storage Module Gaps noted Limited concrete damage (non-structural) HSMs were intact and capable of performing their intended function Radiological conditions were normal 20
21 Dry Cask Storage Pad No. 2 21
22 NUHOMS HSM 22
23 NUHOMS HSM Roof Vents 23
24 NUHOMS HSM Roof Vent Screen 24
25 Seismic Results Eric Hendrixson Director, Nuclear Engineering
26 Plant Seismic Instrumentation The station has two separate recording systems, an active system (provided by Kinemetrics Inc.) and a primarily passive system (provided by Engdahl) Both systems provide input to the Main Control Room (MCR) via a common instrumentation panel MCR Seismic Instrumentation Panel 26
27 Plant Seismic Instrumentation Kinemetrics Triaxial Seismic Trigger Triaxial Seismic Switch Triaxial Time History Accelerograph Engdahl Triaxial Response Spectrum Recorder Triaxial Peak Accelerograph 27
28 Plant Seismic Instrumentation (Kinemetrics - Active) Sensor Type Location/Elevation Equipment Mounting Triaxial Time History Accelerograph Unit 1 Containment 216 U1 Containment Mat Triaxial Seismic Trigger Unit 1 Containment 216 U1 Containment Mat Triaxial Seismic Switch Unit 1 Containment 216 U1 Containment Mat Triaxial Time History Accelerograph Unit 1 Containment 291 U1 Containment Operating Deck 28
29 Plant Seismic Instrumentation (Engdahl - Passive) Sensor Type Location/Elevation Equipment Mounting Triaxial Response Spectrum Recorder Unit 1 Containment 216 Unit 1 Containment Mat Triaxial Response Spectrum Recorder Unit 1 Containment 231 Unit 1 Residual Heat Removal (RHR) pump and heat exchanger area Triaxial Response Spectrum Recorder Aux Building 244 In between Unit 1 and Unit 2 Component Cooling (CC) pumps Triaxial Response Spectrum Recorder Aux Building 274 Near Unit 1 A CC heat exchanger Triaxial Peak Accelerograph Unit 1 Containment 218 On Unit 1 C Safety Injection Accumulator discharge piping Triaxial Peak Accelerograph Unit 1 Containment 241 On Unit 1 B RHR heat exchanger Triaxial Peak Accelerograph Aux Building 279 On Unit 1 A CC heat exchanger, 29
30 Triaxial Response Spectrum Recorder Triaxial Response Spectrum Recorder Recorder Scratch Plates Styluses Recorder Scratch Plates 30
31 North Anna Design Basis Seismic Criteria (Station and ISFSI) Horizontal Peak Ground Acceleration (g) Rock Vertical Peak Ground Acceleration (g) Rock Horizontal Peak Ground Acceleration (g) Soil Vertical Peak Ground Acceleration (g) Soil OBE DBE
32 Comparison of Kinemetrics Data Horizontal Direction 32
33 Comparison of Kinemetrics Data Vertical Direction 33
34 Cumulative Absolute Velocity (CAV) Concept used by EPRI to address OBE Exceedance in 1988 (EPRI NP-5930) Indicator of damage based on analysis of 263 time-histories from 42 earthquakes OBE Exceedance criterion is CAV <0.16 g-sec (EPRI TR and RG 1.166) Criterion is conservative and has a minimum factor of three Revision 3 Rev. 2 34
35 Plant Seismic Response Results East-West (g-sec) North-South (g-sec) Vertical (g-sec) Kinemetrics SGH Bechtel Average (CAV limit = 0.16 g-sec, per NRC RG 1.166) 35
36 a 2 dt (g 2 -sec) Husid Function Plot Representation of Cumulative Energy Cumulative Energy for Records Labeled "CW026" Time (sec) CW026_CH1_L_corrected CW026_CH2_V_corrected CW026_CH3_T_corrected Cumulative Energy (HUSID Plot) for the Containment Basemat Records Effective Strong Motion Duration for Records Labeled CW026 Time History Effective Strong Motion Duration (sec) CW026_CH1_L_corrected 3.1 CW026_CH2_V_corrected 1.5 CW026_CH3_T_corrected
37 Seismic Margin As part of response to GL (IPEEE) and GL (USI-A46 ), the following actions were completed: Extensive inspections of 1800 safe shutdown components assuming an earthquake peak acceleration of 0.3g for IPEEE With few exceptions, components evaluated could withstand 0.3g or higher Worst case capacity of 0.16g, which exceeds 0.12g DBE Modifications provided additional seismic ruggedness Comprehensive peer review walkdown of 20% sample Consequently, safe shutdown components are capable of surviving seismic accelerations in excess of the DBE design criteria 37
38 Restart Readiness Demonstration Plan
39 Restart Readiness Demonstration Plan North Anna UFSAR Section Use of Data from Seismic Instrumentation - In accordance with paragraph V(a) of Appendix A to 10 CFR 100, an orderly and sequential shutdown of the North Anna units will be carried out according to detailed written station procedures if a seismic event with vibratory ground motion equal to or exceeding that of the operational-basis earthquake occurs. Prior to resuming operations, it will be demonstrated to the NRC that no functional damage has occurred to those features necessary for continued operation without undue risk to the health and safety of the public, or that the necessary repairs to those features have been completed. [emphasis added] 39
40 Restart Readiness Demonstration Plan Based on exceeding the station OBE and DBE seismic criteria and the CAV limit, the station restart readiness assessment actions were based on the guidance contained in the following documents: RG 1.166, Pre-earthquake Planning and Immediate Nuclear Power Plant Operator Post-earthquake Actions, dated March 1997 RG 1.167, Restart of a Nuclear Power Plant Shut Down by a Seismic Event, dated March 1997 EPRI NP-6695, Guidelines for Nuclear Plant response to an Earthquake, dated December
41 EPRI NP-6695 Figure 3-1 Figure 3-1. Flow Diagram of Short-Term Actions 41
42 EPRI NP-6695 Figure 3-2 Figure 3-2. Flow Diagram of Post-Shutdown Inspections and Tests 42
43 EPRI NP-6695 Figure 3-2 Figure 3-2. Flow Diagram of Post-Shutdown Inspections and Tests 43
44 EPRI NP-6695 Figure 3-2 Figure 3-2. Flow Diagram of Post-Shutdown Inspections and Tests 44
45 Restart Readiness Demonstration Plan Seismic Data Collection and Analysis Damage Assessment and Evaluation Restart Assessment Long-Term Actions 45
46 Restart Readiness Demonstration Plan Seismic Data Collection and Analysis Perform data collection/analysis of earthquake seismic data to quantitatively define earthquake magnitude - Complete Compare results with the station design basis OBE and DBE criteria to determine if they were exceeded - Complete Obtain 3 rd party peer reviews of analysis by industry experts 46
47 Restart Readiness Demonstration Plan Damage Assessment and Evaluation Perform post-earthquake walkdowns/inspections of plant structures, systems and components (SSCs) consistent with regulatory and industry guidance (includes North Anna Spillway dam and SG tube inspections) Perform comprehensive surveillance testing to validate SSC operability/performance Perform comprehensive inspections and evaluations of ISFSI pads and casks Perform evaluations of reactor vessel internals and fuel in the core, Spent Fuel Pool and New Fuel Storage Area Complete Root Cause Evaluation of reactor trip Document assessments/evaluations in appropriate engineering technical evaluations 47
48 Restart Assessment Restart Readiness Demonstration Plan Complete inspections, evaluations, testing and repair, if necessary, of SSCs to ensure they are capable of performing their intended design functions Finalize and obtain FSRC review and approval of Engineering technical documents demonstrating SSC restart readiness Review and disposition open Condition Reports, as necessary, to ensure that no outstanding issues exist that would preclude restart 48
49 Long-Term Actions Installation of free-field seismic instrumentation Permanently re-power Seismic Monitoring Panel in MCR from an Uninterruptible Power Supply Coordinate update of the station seismic design and licensing bases with ongoing GI-199 resolution effort 49
50 Results to Date Mark Walker Manager, Nuclear Site Engineering
51 Results to Date Although evaluations are continuing, to date, SSCs inspections have only identified superficial damage and Surveillance Tests have not identified any safety-related SSC operability issues related to the seismic event Inspector Training and Inspection Process Inspection results indicate North Anna in the 0 category of the EPRI Damage Intensity Scale As of 9/7/11 82% of 134 system inspections completed 97% of 141 structure inspections completed 28% of 448 Surveillance Tests completed (Unit 1) 20% of 50 High Confidence Low Probability of Failure (HCLPF) component SQUG inspections completed 51
52 Restart Schedule N. Larry Lane Site Vice President North Anna Power Station
53 NAPS U1 Restart Timeline 09/07 Facility Safety Review Committee (FSRC) approval of Safe Shutdown System Operability Determination 09/16 Engineering Final Technical Evaluation review by FSRC 09/18-20 Comprehensive ESF functional testing complete Comprehensive post-event testing and inspections complete Start-up Assessment by FSRC 09/22 Containment close-out complete and unit ready to enter Mode 4 53
54 NAPS U2 Planned Refueling Restart Timeline 09/07 FSRC approval of the Safe Shutdown System OD 09/12 FSRC approval of the Mode 6 System OD 09/12-15 Reactor Disassembly- Inspections 09/15-17 Reactor Core Off-load to the SFP 09/16 Secondary activities complete Engineering Final Technical Evaluation review by FSRC 09/17-30 Defueled Primary Maintenance 10/01-02 Reactor Core Reload 10/02-06 Reactor Reassembly 10/06-13 Comprehensive ESF functional testing complete Comprehensive post-event testing and inspections complete Containment close-out complete Start-up Assessment by FSRC 10/13 Ready for Mode 4 54
55 Summary Gene Grecheck Vice President, Nuclear Development
56 Summary OBE and DBE criteria were exceeded; however, CAV calculations indicate that significant damage would not be expected Extensive actions are underway to inspect, evaluate, test and repair, if necessary, SSCs to ensure they are capable of performing their required design basis functions - Results are confirming the CAV expectations To date, no safety related SSCs have been identified that require repair IPEEE and USI-A46 results demonstrate that safe shutdown SSCs are capable of withstanding peak accelerations in excess of DBE Unit will be ready for restart when we establish confidence that SSCs will perform as designed Long-term actions are planned to improve plant seismic monitoring capability and to re-evaluate plant OBE and DBE criteria in conjunction with resolution of GI
57 Questions?
58 List of Acronyms AC AFW DBE EAL EDG EP EPRI ESF FSRC FW GI HSM IPEEE KW MT NRC NOUE NUHOMS OBE OD Alternating Current Auxiliary Feedwater Design Basis Earthquake Emergency Action Level Emergency Diesel Generator Electric Power or Emergency Plan Electric Power Research Institute Engineered Safety Features Facility Safety Review Committee Feedwater Generic Issue Horizontal Storage Module Individual Plant Examination External Events Kilowatts Main Transformer Nuclear Regulatory Commission Notification of Unusual Event Nuclear Horizontal Modular Storage System Operating Basis Earthquake Operability Determination P Pump RSST Reserve Station Service Transformer SBO Station Blackout SGH Simpson Gumpertz & Heger SFP Spent Fuel Pool SSC Systems, Structures and Components SST Station Service Transformer TN Transnuclear U1 Unit 1 U2 Unit 2 USI Unresolved Safety Issue 58
59 2003 Dominion 59
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