ML021000037
| ML021000037 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/02/2002 |
| From: | Marilyn Evans Reactor Projects Branch 1 |
| To: | |
| References | |
| MN-02-012 | |
| Download: ML021000037 (32) | |
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 04/02/2002 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) 50-224 Plant/Facility Name R. E. Ginna Nuclear Power Plant TAC Number(s) (if available)
Reference Meeting Notice 02-012 Purpose of Meeting (copy from meeting notice)
The NRC staff and RG&E management will discuss the results of NRC's assessment of the safety performance of Ginna for the period of April - December 31, 2001.
NAME OF PERSON WHO ISSUED MEETING NOTICE TITLE Michele G. Evans Branch Chief OFFICE Region I DIVISION Division of Reactor Projects BRANCH Projects Branch 1 Distribution of this form and attachments:
Docket File/Central File PUBLIC This form was designed using InForms NRC FORM 658 (9-1999)
PRINTED ON RECYCLED PAPER
Annual Assessment Meeting Reactor Oversight Program - Cycle 2 50~
U.S. Nuclear Regulatory Commission - Region I King of Prussia, PA
Agenda
"* Introductions
"* The NRC - Who We Are & What We Do
"* The Reactor Oversight Process
"* Ginna's Plant Performance
"* Comments by RG&E
"* NRC Closing Remarks
"* The NRC staff will be available following the meeting to address questions from the public
Region I Organization I
Ginna Resident Inspectors Chris Welch I
I I
Project Engineers Nine Mile Point Calvert Cliffs William Cook Resident Inspectors Resident Inspectors Paulette Torres H. Miller Regional Administrator A. Blough Director Division of Reactor Projects Brian Holian Deputy Director W. Lanning Director Division of Reactor Safety R. CrIenjak Deputy Director
NRC Representatives
"* Michele Evans, Chief Reactor Projects Branch 1
- (mge@nrc.gov (610) 337-5224)
"* William Cook, Senior Project Engineer
- (wacl@nrc.gov (610) 337-5074)
"* Chris Welch, Acting Senior Resident Inspector
- (crw@nrc.gov (315) 524-6935)
Reference Sources MMK~xl=
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77-1 iillilill 1 1:
"* NRC Home Page o http://www.nrc.gov
- Reactor Oversight Process Shttp ://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 S 1-800-397-4209 (Toll Free)
NRC Mission Statement The mission of the Nuclear Regulatory Commission is to ensure adequate protection of public health and safety, promote the common defense and security, and protect the environment by regulating the Nation's civilian uses of nuclear fuels and materials. In undertaking this mission, we oversee nuclear power plants, non-power reactors, nuclear fuel cycle facilities, waste disposal, and the industrial and medical uses of nuclear materials.
NRC Performance Goals
- Maintain safety, protection of the environment, and the common defense and security
- Increase public confidence
- Make NRC activities and decisions more effective, efficient, and realistic
- Reduce unnecessary regulatory burden
NRC Activities
"- Issue licenses for the peaceful use of nuclear materials in the U.S.
"* Ensure nuclear plants are designed, constructed, and operated safely.
"* Ensure licensees are prepared to respond to radiological emergencies and safeguards events.
NRC Response to 9/11
"* Highest Level of Security Maintained
"* Comprehensive Review of Security
"* Closely Coordinated Response With:
Our Licensees FBI Military, State, and Local Agencies Intelligence Communities
"* Issued Security Advisories Increased Patrols Augmented Security Capabilities Added Barriers and Posts More Limited Access Enhanced Security Awareness
"* Issued Order on Security
"* NRC Monitoring Enhanced Security
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones SBaseline Inspection ut"'
Significance
-scnf Threshold rs Action Matrix 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 S3 5 h r s /y r
-200 hrs every 3 yrs
- 125 hrs/yr
-40 hrs/yr
-60 hrs/yr
-O0 hrs every 2 yrs A125 hrs/yr 10% every inspection
-200 hr every 2 yrs
Signifigance Threshold Green:
White:
Yellow:
Red:
Very Low safety significance Low to moderate safety significance Substantial safety significance High safety significance Green:
White:
Yellow:
Red:
Only baseline Inspection May increase NRC oversight Requires more NRC oversight Requires more NRC oversight
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 Response 74 Regulatory Response 24 Degraded Cornerstone 4
Multiple/Repetitive Degraded Cornerstone 1
Unacceptable 0
Total Plants 103
National Summary m Performance Indicator Results 4th Qtr Calendar Yr 2001 Green SWhite SYellow SRed:
1834 8
0 0
n Total Inspection Findings (April 2001 - December 2001)
Green SWhite SYellow o Red 660 23 2
0
Ginna Annual Assessment (April 1 - Dec 31, 2001)
"* Operated safely
"* Fully met all cornerstone objectives
"* Licensee Response Band of Action Matrix All Inspection Findings Green or No Color SAll Performance Indicators Green
"* NRC Plans to conduct baseline inspections
Ginna Inspection Activities (Jan 1 - Dec 31, 2001)
- 4860 hours0.0563 days <br />1.35 hours <br />0.00804 weeks <br />0.00185 months <br /> of inspection related activity
- Two resident inspectors performing resident inspections
- 12 inspections by regional inspectors
,* Includes 3 team inspections
- Inspection Findings 4 findings of very low safety significance 4 findings with no color
Ginna Performance Indicators 4Q/2001 Performance Indicators
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Ginna Inspection Finding Summary Most Significant Inspection Findings 4Q12001 CoSurAt3gn~ation 3Q02001 2Q12001 IQ12001 Ftininswitio~L color designation Mfisefflneous fiding's
Simplified Pressurized Water Reactor Containment THrottle Valve Main Turbine Electric 0 er dox
-J Feedwate Pump Reactor
Strategic Performance Areas I Safety Cornerstones
"* Reactor Safety
"* Radiation Safety
- Occupational Radiation Safety
"* Safeguards
NRC Resident and Regional Inspectors Conduct Safety Inspections Baseline Inspections at all reactor sites to monitor plant safety performance in each of the Strategic Performance Areas V-_
Event Follow-up and Supplemental
_4 Inspections when required
Key Aspects of Baseline Inspection Program
"* Conducted at all plants
"* Objective evidence of safety in all cornerstones
"* A Risk Informed Process that emphasizes safety significant systems, components, activities, and events
"* Monitors licensee effectiveness in finding and fixing safety issues
"* Standardized inspection report format to describe significant findings and non-compliance
"* Inspection reports are publicly accessible
Event Follow-up & Supplemental Inspection n Review events for risk significance m Follow-up risk significant inspection findings
- Determine the causes behind performance declines
- Provides for graduated response
Performance Indicators
"* 18 Performance Indicators
"* Covers all cornerstones
"* Licensee submits data to NRC quarterly
"* Baseline Inspection program verifies accuracy
"* Available on Reactor Oversight Program Web site Eggs=
Key Aspects of Assessment Program
"* Objective assessment of performance
"* "Action Matrix" to determine agency response
- Inspection level increases
- Management involvement increases
- Regulatory action increases
"* Plant specific assessment letters
"* Information on NRC public web site
Substantive Cross Cutting Issue
"- Multiple inspection findings with a common cause in:
o Human performance
~ Problem Identification and Resolution Safety conscious work environment
"* Common cause of inspection findings
"* Common cause documented in an assessment letter
Performance Indicators Safeguards Physical PrPtection er Emergency 01 ity Preparedness Performance Indicators Emergency AC Power System Unavailability High Pressure Injection System Unplanned Unavailability Scrams Heat Removal System Scrams with Unavailability Loss of Normal Heat Removal Residual Heat Removal System Unavailability Unplanned Power Change Safety System Functional Failure Protected Area Equipment Personnel Screening ProgramI FFDlPersonnel Reliability Program
Inspection Areas Emergency Preparedness Safeguards Physical Protection Adverse Weather Evaluation of Changes Equipment Alignment Fire Protection Flood Protection Heat Sink In Service Inspection Operator Requalification Maintenance Rule Imp Maintenance Risk Assessment Non-Routine Events S
S 0
0 0
0 S
0 0
0 S
S Inspection Procedures rability Evaluation 0 Excercise Evaluation rator Workarounds 0 Alert and Notice ianent Mods-Online 0 ERO Augment ianent Mods o EAL Maintenance Test 0 EP Preparation eling Outage 0 Drill Evaluation I
0 RAD Access eillance Testing
- ALARA Plan porary Modifications 0 RAD monitoring R
0 RAD Effluents it Follow-up 0 RAD Transport erification o RAD Environmental
"* Sec Authorization Access
"* Sec Search
"* Sec Response
"* Sec Plan change 0
0 S
0 S
S S
0 0
0 S
NRC Action Matrix Licensee Response Regulatory Response Degraded Cornerstone Multiple/ Repetitive Unacceptable Column Column Column Degraded Cornerstone Performance S......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 Green; Cornerstone Area; Cornerstone Inputs in a Strategic Yellow Inputs, or I Red Band, Unacceptable w
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 UJ Action Action with NRC Assessment with NRC Improvement Plan with z
Oversight Oversight NRC Oversight 0 a.
NRC Inspection Risk-Informed Baseline Baseline and Baseline and Baseline and CO Inspection supplemental supplemental supplemental WIProgram 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
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 inspection 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 0u Licensee Licensee Discuss Performance Discuss Performance with Senior Licensee with Licensee with Senior Licensee Management Management
.j INONRFA'qN(
RAFPTV 5IGNIFICANOI
Performance Indicator Alert & Notification System 100.0%
98.0%
96.0%
.4%
94.0%
92.0%
92.1%
90.0%
88.0%
86.0%
04.0%
82.0%
00.0%1 Thresholds: White < 94.0% Yellow < 90.0%