ML030990060

Annual Assessment Meeting Farley Nuclear Power Plant

ML030990060
Person / Time
Site:	Farley
Issue date:	03/27/2003
From:	NRC/RGN-II
To:
References
Download: ML030990060 (20)

Text

Annual Assessment Meeting Farley Nuclear Power Plant Nuclear Regulatory Commission March 27, 2003

Annual Licensee Assessment Meeting

• A public forum for discussion of the Ijcensee's performance as outlined in the NRC' s Annual Assessment Letter

• Provide licensee with an opportunity to respond to the information Assessment Letter in the

NRC Performance Goals

• Maintain safety and protect th environment e

• Enhance public confidence I improve effectiveness efficiency, and realism of processes and decision making

• Reduce unnecessary regulatory burden

Regulatory Framework Strategic Performance Areas Cornerstones

---

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

PERFORMANCE ENVIRONMENT IDENTIFICATION AND RESOLUTION Cross-Cutting Areas

Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Ruinspection Respons Results:

0

okRegulatory

Response :I

Action Matrix i

Licensee l

Regulatory Degraded l

Multiple/ Repetitive Unacceptable I

Response

Response Cornerstone Degraded Cornerstone l

Performance

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Column Column Column Column Column All Assessment Inputs One or Two Wnite inputs (In One Degraded Cornerstone Repebtive Degraded 11veralUnacceptable (Performance Indicators different cornerstones) in a (2 White Inputs or 1 Yellow Cornerstone, Multiple Performance; Plants W

(Pis) and Inspection Strategic Performance Area; Input) or any 3 White Inputs Degraded Cornerstones, Not Permitted to 1

Findings) Green; Cornerstone Objectives Fully in a Strategic Performance Multiple Yellow Inputs, or Operate Within this D

Cornerstone Objectives Met Area; Cornerstone 1 Red Input; Comerstone Band, Unacceptable

)

Fully Met Objectives Metwith Moderate Objectives Met with Margin to Safety Degradation in Safety Longstanding Issues or Performance Significant Degradation in L

__Safety Performance None Branch Chief (BC) or RA (or EDO) Meet with Commission meeting Regulatory Performance Division Director (DD) Meet DD or Regional Administrator Senior Licensee with Senior Licensee Meeting with Licensee (RA) Meet with Licensee Management Licensee cumulative root Z

cause evaluation with o

Licensee root cause Licensee cumulative root a.° Licensee Action Licensee Corrective Action evaluation and corrective cause evaluation with NRC Performance action with NRC Oversight Oversight Improvement Plan with NRC Oversight Baseline and Risk-lnftrmed 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 Actions1 None

- CAL/Order Licensed Activities Z

BC or DD review/sign RA review/sign o

Assessment Letters assessment report (w/

DD review/sign assessment RA review/sign assessment assessment report (w/

F I

inspection plan) report (w/ inspection plan) report (w/ inspection plan) inspection plan) 0 SRI or BC Meet with BC or DD Meet with Licensee RA (or DD) Discuss RA or EDO Discuss Z

Annual Public Meeting Licensee Performance with Licensee Performance with Senior E_

I Licensee Management Commission Meeting o

Commission Involvement None None None Plant discussed at AARM with Senior Licensee U

Management INCREASING SAFETY SIGNIFICANCE -------

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:

• http://www.nrc.gov/NRR/ OVERSIGHT/ASS actionmatrixsummary.html ESS/

NRC Inspection Activities in 2002

• Routine Resident Baseline InspectionS

• Security Inspections

• Reactor Vess el Head Inspection (Unit 2)

• Fire Protection Inspection

• Safety System Design and Performance Capability Inspection

• Emergency Exercise Inspection

Plant Performance Summary r w II ~ ~

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s, _ S Ad irnIr d;-a4r

• All Performance Indicators and Inspection Findings were Green

• All cornerston e objectives fully met E In Licensee Response Column for all four quarters

• Preserved public health and safety

• Baseline inspection program to be-performed

Fourth Quarter 2002 Performance Summary Performance Indicators Farley Unit 1: Licensee Response Column Performance Indicators

Year 2002 Performance Summary Inspection Findings Farley Unit 1a Licensee Response Column Most Significant Inspection Findings 4Q12002 30/2002 2Q/2002 10/2002

Fourth Quarter 2002 Performance Summary Performance Indicators

..... -.--.II-----

.1 Farley Unit 2: Licensee Response Column ISafeguars

~egrity Preparedne~

RadiationRakp)Pyil Safety I safety Poeto Performance Indicators

Year 2002 Performance Summary Inspection Findings

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iu_.iis 1_---i FarleyUnit 2 Licensee Response Column Most Significant Inspection Findings 4Q2002 3QA2002 2Qi200 IQQOO2

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

• Issuance Measures of Orders/ Interim Compensatory (ICM)

• Verification of Licensee Actions on 1CM

Security & Safeguards Update

• Proposed Revisions to Design Basis Threat

• Pending Orders on Fatigue/Guard Training

• Initiation of Pilot Force-on-Force Exercise Program

Contacts for additional information for:

Farley Nuclear Power Plant

• Regional Public Affairs Officer:

• Name: Kenneth M. Clark

• Phone: 404-562-4416

• E-mail: kmc2@nrc.gov

• State Liaison Officer:

• Name: Robert E. Trojanowski

• Phone: 404-562-4427

• E-mail: ret~nrc.gov

• Branch Chief:

• Name: Brian R. Bonser

• Phone: 404-562-4540

• E-mail: brb 1 nrc.gov

• Senior Resident Inspector:

• Name: Tom P. Johnson

• Phone: 334-899-3386

• E-mail: tpj 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