ML051530478

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NRC Slides for Public Meeting with Nuclear Energy Advisory Council (Neac) Ref: Special Inspection Team Results of April 17, 2005 Event
ML051530478
Person / Time
Site: Millstone Dominion icon.png
Issue date: 05/18/2005
From:
NRC Region 1
To:
Krohn P, RI/DRP/PB6/610-337-5120
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Download: ML051530478 (15)


Text

NEAC Meeting May 18, 2005 Millstone Unit 3 Special Inspection April 17, 2005, Reactor Trip and Safety Injection Nuclear Regulatory Commission-Region I King of Prussia, PA

NRC Presentation

  • NRC Introductions
  • Special Inspection Team and Charter
  • Event Chronology
  • Event Overview and Analysis
  • Special Inspection Results
  • Discussion 2

NRC Representatives

  • Brian E. Holian, Acting Director, Division of Reactor Projects
  • Marvin D. Sykes, Chief, Engineering Branch 1, Team Manager
  • G. Scott Barber, Senior Project Engineer, Team Leader
  • Ronald Nimitz, Senior Health Physicist
  • Thomas Sicola, Reactor Inspector
  • S. Max Schneider, Senior Resident Inspector
  • Nicole Sieller, Reactor Engineer

Special Inspection Team (SIT)

  • Team Staffing 3/4 Four full time members 3/4 Four part time members 3/4 Multidisciplined group with diverse backgrounds 4

Special Inspection Team (SIT)

  • Charter / Objectives 3/4 Chronology of event 3/4 Apparent cause(s) 3/4 System response(s) 3/4 Equipment deficiencies including maintenance and surveillance history 3/4 Evaluation of licensee follow-up actions 3/4 Radiological Assessment 5

Event Chronology

  • Primary power operated relief valve cycling
  • Alert declared
  • Operator actions to stabilize plant conditions
  • Plant shutdown and cooldown 6

Event Overview

  • Initial response prompt
  • Emergency response organizations activated -

Dominion and NRC

  • Some operational / equipment challenges occurred while stabilizing plant conditions
  • Licensee successful in achieving cold shutdown
  • No consequences to public health and safety 7

Event Analysis

  • Dominion Actions 3/4Event Review Team activities initiated 3/4Apparent cause promptly identified by I&C -

Tin Whisker 3/4Timely assessment of radiological conditions 3/4Multiple corrective actions implemented (cause / equipment related) 3/4Additional evaluations initiated 8

9 Millimeters 10

NRC Special Inspection Team Results

  • Preliminary Findings 3/4 Turbine Driven Auxiliary Feedwater Pump 3/4 Emergency Operating Procedure Implementation Issues 3/4 Assessment of Plant Conditions 3/4 Simulator Fidelity 3/4 Indicator Design Issues 3/4 Boric Acid Control Program 3/4 Emergency Response Data System Activation 3/4 Thoroughness of Event Review Effort 11

NRC Special Inspection Team Results

  • Unresolved items 3/4 Pressurizer snubber - potential inoperability 3/4 Charging system issues 3/4 Simulator issues 3/4 Root Cause Evaluations 12

NRC Special Inspection Team Results

  • Observations 3/4 Thoroughness of Event Review Effort 3/4 Emergency Operating Procedure Documentation and Usage 3/4 Extent of Condition Review for Non-Solid State Protection System Cards 13

Radiological Assessment

  • Radiological release - well below Regulatory Limits
  • No consequence to health or safety of public
  • Worker doses were appropriately controlled 14

Conclusions

  • Event 3/4 Unit was safely shutdown by operators and placed in a stable condition 3/4 Radiological release well below regulatory limits 3/4 No consequences to public health and safety 15