ML021020060
| ML021020060 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/09/2002 |
| From: | Meyer G Reactor Projects Branch 3 |
| To: | |
| References | |
| Download: ML021020060 (22) | |
Text
NRC FORM 658 U.S. NUCLEAR REGULATORY COMMISSION (9-1999)
TRANSMITTAL OF MEETING HANDOUT MATERIALS FOR IMMEDIATE PLACEMENT IN THE PUBLIC DOMAIN This form is to be filled out (typed or hand-printed) by the person who announced the meeting (i.e., the person who issued the meeting notice). The completed form, and the attached copy of meeting handout materials, will be sent to the Document Control Desk on the same day of the meeting; under no circumstances will this be done later than the working day after the meeting.
Do not include proprietary materials.
DATE OF MEETING The attached document(s), which was/were handed out in this meeting, is/are to be placed 04/09/2002 in the public domain as soon as possible. The minutes of the meeting will be issued in the near future. Following are administrative details regarding this meeting:
Docket Number(s) 05000333 Plant/Facility Name FitzPatrick Nuclear Plant TAC Number(s) (if available)
Reference Meeting Notice 02-023 Purpose of Meeting (copy from meeting notice)
NRC staff and Entergy Nuclear Northeast's mgt will discuss the results of the NRC's assessment of the safety performance at FitzPatrick for the period 4/1-12/31/01.
NAME OF PERSON WHO ISSUED MEETING NOTICE TITLE Glenn W. Meyer Chief, Projects Branch 3 OFFICE USNRC RI DIVISION Division of Reactor Projects BRANCH Projects Branch 3 Distribution of this form and attachments:
Docket File/Central File PUBLIC NRC FORM 658 (9-1999)
PRINTED ON RECYCLED PAPER This form was designed using InForms
Annual Assessment Meeting Reactor Oversight Program - Cycle 2 Nuclear Regulatory Commission -Region I King of Prussia, PA
Agenda
"* Introduction
"* Reactor Oversight Process
"* Plant Performance Results
"* Entergy Nuclear Northeast Remarks
"* NRC Closing Remarks NRC will be available to address questions from the public afterward
NRC Representatives
"* Glenn Meyer, Chief Reactor Projects Branch 3
- (610) 337-5211
"* Richard Rasmussen, Senior Resident Inspector -FitzPatrick
- (315) 342-4907
"* Douglas Dempsey, Resident Inspector - FitzPatrick
- (315) 349-6667
"* Michele Evans, Chief, Reactor Projects Branch 1 (Responsible for Nine Mile Point 1 & 2 / Ginna)
NRC Activities
"* Ensure nuclear power plants are designed, constructed, and operated safely
"* Issue licenses for the peaceful use of nuclear materials in the U.S.
"* Ensure nuclear facilities are prepared to respond to emergencies
NRC 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
NRC Oversight Activities
"* Provides assurance plants are operating safely and in accordance with the regulations
"* Risk informed process
"* Objective indicators of performance
"* Inspections focused on key safety areas
"* Defines expected NRC and licensee actions
NRC Response to 9/11
"* Highest Level of Security Maintained
"* Comprehensive Review of Security
"* Closely Coordinated Response With:
Licensees FBI Military, State, and Local Agencies Intelligence Communities
"* Security Advisories Increased Patrols Augmented Security Capabilities Added Barriers and Posts More Limited Access Enhanced Security Awareness
"* February 25th Order on Security
"* NRC Monitoring Enhanced Security
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones
~Baseline Inspection Rs rs-Pý S~Results Significance Threshold
-- I A
r Regulatory Response
Examples of Baseline Inspections
"* Equipment Alignment
"* Annual Fire Protection
"* Trienniel Fire Protection
"* Operator Response
"* Plant security
"* Rad release controls
"* Worker radiation protection
"* Corrective action program
"* Corrective action program S70 hrs/yr S35 hrs/yr 200 hrs every 3 yrs 125 hrs/yr 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />s/yr 60 hrs/yr 100 hrs every 2 years 125 hrs/year 10% every inspecton S200 hr every 2 yrs
Action Matrix Concept Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions Licensee Regulatory Degraded Multiple/Degraded Unacceptable
Response
Response Cornerstone Cornerstone Performance
National Summary of Plant Performance End of Calendar Year 2001 Licensee Regulatoi
Response
Response Degraded Cornerstone Multiple/Repetitive Degraded Cornerstone Unacceptable Total Plants 74 24 4
1 0
103
National Summary m Performance Indicator Results 4th Qtr Calendar Yr 2001 Green
, White SYellow
- Red:
1834 8
0 0
m Total Inspection Findings (April 2001 Green SWhite SYellow S Red
- December 2001) 660 23 2
0
FitzPatrick Inspection Activities a
4E~f
-MRA~m
_W
.r (Jan 1 - Dec 31, 2001)
"* Over 3,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of inspection-related activity
"* Two on-site inspectors performing resident inspections
"* Numerous inspections by regional inspectors
, Includes several major team inspections
"* Inspection Findings
, 11 findings of very low safety significance
FitzPatrick Annual Assessment Now-a is a
8 1
1
=I ws=I E
(April 1 - Dec 31, 2001)
- Operated safely
- Fully met all cornerstone objectives
- Licensee Response Band of Action Matrix (In the regulatory response band until 7/2001)
- All Performance Indicators require no additional NRC oversight (Green)
- NRC plans to conduct baseline inspections
FitzPatrick Performance Indicators 4Q/2001 WWW.nrc.gov/NRR/OVERSIGHT/FITZ/fitzchart.html Performance Indicators
Performance Indicator Unplanned Power Changes per 7000 Critical Hrs C
a I-I a
a r
N Thresholds: White > 6.0 C
a r
C a
N C
a 7
CY M
0 2
4 6
8 10 5
8.4 now WASEEMM"W 71A -1 M
Performance Indicator Safety System Functional Failures (BWR)
C a
r 0
2 4
6 8
10 C
ad 0
C a
Thresholds: White > 6.0 a
N r
Ct a
a EMMUEZZMA I - t ý man= ý, 1 -,
I
ý I
FitzPatrick Inspection Finding Summary Most Significant Inspection Findings 40W2001 ti 3012001
,olkoo, W
1 20f2001 10f2001 0 flnlnqý o TI~d~ngaFindingswithout I
,nIN11icl thi-,
ý3a fter thi quatlerColo r designation I y' t'
7Wsce~fneoau7 Additional Inspection & Assessment Information
- Assessment Reports/Inspection Plans:
4Q/2001 30/2001 20/2001 1 Q/2001
- 0 Cross Reference Of Assessment Reports
+
List of Inspection Reports
+
List of Assessment Letters/inspection Plans I
I-IIIII a
L
.1 OEM :
I-1L- -EM -
ZVEMM FT
Reference Sources
"* Reactor Oversight Process o http ://www.nrc.gov/NRR/OVERSIGHT/AS SES S/index.html
"* Public Electronic Reading Room Shttp ://www.nrc.gov/reading-rm/adams.html
"* Public Document Room o 1-800-397-4209 (Toll Free) w IF IMMMEMM - - MEMEMEMM ME ow I I
- ý ME WMEEFAMMM L
mammmummm
NRC Action Matrix Licensee Response Regulatory Response Degraded Cornerstone Multiple/ Repetitive Unacceptable Column Column Column Degraded Cornerstone Performance I -
- Column Column All Assessment Inputs One or Two White One Degraded Repetitive Degraded Overall Unacceptable (Performance Inputs (in different Cornerstone (2 White Cornerstone, Multiple Performance; Plants Indicators (Pis) and cornerstones) in a Inputs or I Yellow Degraded Not Permitted to Inspection Findings)
Strategic Performance Input) or any 3 White Cornerstones, Multiple Operate Within this 0
Green; Cornerstone Area; Cornerstone Inputs in a Strategic Yellow Inputs, or 1 Red Band, Unacceptable wL Objectives Fully Met Objectives Fully Met Performance Area; Input; Cornerstone Margin to Safety Cornerstone Objectives Objectives Met with Met with Minimal Longstanding Issues or Reduction in Safety Significant Reduction in
___...._Margin Safety Margin Regulatory None Branch Chief (BC) or DD or Regional RA (or EDO) Meet with Commission meeting Performance Meeting Division Director (DD)
Administrator (RA)
Senior Licensee with Senior Licensee Meet with Licensee Meet with Licensee Management Management Licensee Action Licensee Corrective Licensee Corrective Licensee Self Licensee Performance 0
Action Action with NRC Assessment with NRC Improvement Plan with
)z Oversight Oversight NRC Oversight 0
I NRC Inspection Risk-Informed Baseline Baseline and Baseline and Baseline and U0 Inspection supplemental supplemental supplemental I
Program inspection procedure inspection procedure inspection procedure 95001 95002 95003 Regulatory Actions None Supplemental Supplemental
-10 CFR 2.204 DFI Order to Modify, inspection only inspection only
-10 CFR 50.54(f) Letter Suspend, or Revoke I - CAL/Order Licensed Activities Assessment Reports BC or DD review/sign DD review/sign RA review/sign RA review/sign oassessment report (w/
assessment report assessment report assessment report Sinspection plan)
(w/ inspection plan)
(w/ inspection plan)
(w/ inspection plan)
____--__Commission Informed O
Annual Public Meeting SRI or BC Meet with BC or DD Meet with RA (or designee)
EDO (or Commission)
Commission Meeting U
Licensee Licensee Discuss Performance Discuss Performance with Senior Licensee with Licensee with Senior Licensee Management
,Manauement INb.RFA5AINr KAFFTW K1(NIFI>IANCF
Simplified Boiling Water Reactor Eli