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 
(NPF-049)
Issue date: 05/18/2005
From:
NRC Region 1
To:
Krohn P, RI/DRP/PB6/610-337-5120
Shared Package
ML051240334 List:
References
Download: ML051530478 (15)


Text

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

2 NRC Presentation

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

3 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

4 Special Inspection Team (SIT)

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

5 Special Inspection Team (SIT)

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

6 Event Chronology

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

7 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

8 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

9

10 Millimeters

11 NRC Special Inspection Team Results

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

12 NRC Special Inspection Team Results

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

13 NRC Special Inspection Team Results

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

14 Radiological Assessment

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

15 Conclusions

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