ML030990064

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Annual Assessment Meeting - Hatch Nuclear Power Plant
ML030990064
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 04/09/2003
From:
Office of Nuclear Reactor Regulation
To:
References
Download: ML030990064 (20)


Text

Annual Assessment Meeting Hatch Nuclear Power Plant iAt ilk, Nuclear Regulatory Commission April 9, 2003

Annual -Licensee Assessment Meeting

  • A public forum for discussion of the licen see' s performance as outlined in the NRC's Annual Assess ment Letter
  • Provide licensee with an opportunity to respond to the information in the Assess ment Letter

N-RC Performance Goals

  • Maintain safety and protect the environment
  • Enhance public confidence
  • Improve effectiveness, efficiency, and realism of processes and decision making
  • Reduce unnecessary regulatory burden

Regulatory Framework - - - -

Cornerstones


a HUMAN ----------------- SAFETY CONSCIOUS WORK --------------------- PROBLEM -------------------

PERFORMANCE ENVIRONMENT IDENTIFICATION AND RESOLUTION Cross-Cutting Areas

Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Regulatory Respnse

Action Matrix I Licensee Il Regulatory I Degraded IMultiple.' Repetifive I Unsacceptable.

I Response Response Cornerstone Degraded Cornerstone Performance Column I Column Column Column Column All Assessment Inputs One orTwo white Inputs (in One Degraded Cornerstone Repetbve Degraded Dverall Unacceptable

( (Performance Indicators different cornerstones) in a (2White Inputs or I Yellow Cornerstone, Multiple Performance; Plants (Pis) and Inspection Strategic Performance Area; Input) or any 3 White Inputs Degraded Cornerstones, Not Permitted to J Findings) Green; Cornerstone Objectives Fully in a Strategic Performance Multiple Yellow Inputs, or Operate Within this Cornerstone Objectives Met Area; Cornerstone 1 Red Input; Cornerstone Band, Unacceptable Co Fully Met Objectives Metwith Moderate Objectives Met with Margin to Safety Degradation in Safety Longstanding Issues or Performance Significant Degradation in i Safety Performance None Branch Chief (BC) or RA (or EDO) Meet with Commission meeting gulatory Performance Division Director (DD) Meet DD or Regional Administrator Senior Licensee with Senior Licensee Meeting with Licensee (RA) Meetwith Licensee Management Management Z Licensee cumulative root Z Licensee root cause Licensee cumulative root causeevation with

a. Licensee Action Licensee Corrective Action evaluation and corrective cause evaluation with NRC Performance 02 action with NRC Oversight Oversight Improvement Plan with Lii i NRC Oversight Baseline and Risk-Informed Baseline Baseline and supplemental Baseline and supplemental supplemental inspection NRC Inspection Inspection Program inspection procedure 95001 inspection procedure 95002 procedure 95003

-10 CFR 2.204 DFI Order to Modify, Supplemental inspection only Supplemental inspection only -10 CFR 50.54(f) Letter Suspend, or Revoke Regulatory Actions' None - CAL/Order Licensed Activities Z BC or DO review/sign RA review/sign o Assessment Letters assessment report (w DD review/sign assessment RA review/sign assessment assessment report (w/

iIe I inspection plan) report w/ inspection plan) report (w/ inspection Plan) inspection plan) l I C)SRI or BC Meet with BC or DID Meet with Licensee RA (or DID) Discuss RA or EDO Discuss Annual Public Meeting A Licensee Performance with Licensee Performance with Senior Licensee Management l l Comrrission Meeting o Commission Invvement None None None Plant discussed at AARM with Senior Licensee F..)

l____InvolvmentNo l e Management INCREASING SAFETY SIGNIFICANCE -------4'l Note 1: The regulatory actions for plants in the Multiple/Repetitive Degraded Cornerstone column are not mandatory agency actions. However, the regional office should consider each of these regulatory actions when significant new information regarding licensee performance becomes available.

Key Aspects of the Assessment Program

  • Objective review of licensee performance
  • "Action Matrix" identifies agency response commensurate with safety significance
  • Increasing safety Significance results in:

- Increased levels of inspection

- Involvement of higher levels of NRC and Licensee management

- Increased regulatory action

  • Plant specific assessment information on NRC public web site:

actionmatrixsummary.html

NRC Inspection Activities in 2002

  • Routine Resident Baseline Inspections
  • Security Inspections
  • Safety System Design and Peformance Capability Inspection

Plant Performance Summary

  • Al I Performance Indicators and Inspection Findings were Green
  • All cornerston e objectives fully met
  • In Licensee Response Column for all four quarters
  • Preserved public health and safety
  • Baseline inspection program to be performed

Fourth Quarter 2002 Perfon'nance Summary Performance Indicators Hatch Unit 1 Licensee Response Column Performance Indicators

Year 2002 Perfornmance Summary Inspection Findings Hatch Unit 1: Licensee Response Column Most Significant Inspection Findings 4Q/2002 M

3Q)2002 2Q12002 IQ02002

Fourth Quarter 2002 Performance Summary Performance Indicators Hatch Unit 2: Licensee Response Column Performance Indicators

Year 2002 Performance Summary Inspection Findings Hatch Unit 2: Licensee Response Column Most Signiflcant Inspection Findings 4Q2002 3Q2002 2Q42ll21 142002

ROP Action Matrix Summary for 2002

  • Column 1 - Licensee Response
  • Column 2 - Regulatory Response
  • Column 3 - Degraded Cornerstone
  • Column 4 - Multiple/ Repetitive Degraded Cornerstone
  • Column 5 - Unacceptable Performance (Nationwide number does not contain Davis Besse)

Security & Safeguards Update

  • Creation of Office of Nuclear Security and Incident Response
  • Top-to-Bottom Review of Security Program Initiated E Issuance of Orders/ Interim Compensatory Measures (ICM)

. Verification of Licensee Actions on 1CM

Security & Safeguards Update

  • Proposed Revisions to Design Basis Threat
  • Pending Orders on Fatigue/Guard Training nitiation El1 of Pilot Force-on-Force Exercise Program

Contacts for additional information for:

Hatch Nuclear Power Plant

  • Regional Public Affairs Officer:

Name: KennethlM. Clark

  • Phone: 404-562-4416
  • E-mail: kmc2mnrc.gov
  • State Liaison Officer:

Name: Robert E. Trojanowski

  • Phone: 404-5624427
  • E-mail: ret(nrc.gov
  • Branch Chief:

Name: Brian R. Bonser

  • Phone: 404-5624540 E-mail: brbl¢nrc.gov
  • Senior Resident Inspector:

Name: Nonn Garrett (Acting)

  • Phone: 912-367-9881
  • E-mail: nxg~nrc.gov

Contacting the NRC

  • Report an emergency
  • (3 01) 816-5 100 (call collect)
  • Report a safety concern:

(800) 695-7403

  • Allegation~nrc.gov
  • General information or questions
  • www.nrc.gov
  • Select "What We Do" for Public Affairs

Regional Organization Regional Organization