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 attachedcopy of meeting handout materials, will be sent to the Document ControlDesk 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 proprietarymaterials.
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) (ifavailable)
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 NRC FORM 658 (9-1999) PRINTED ON RECYCLED PAPER This form was designed using InForms
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 H. Miller Regional Administrator A. Blough W. Lanning Director Division of Reactor Projects Director Division of Reactor Safety Brian Holian R. CrIenjak Deputy Director Deputy Director I I I I Ginna Project Engineers Nine Mile Point Calvert Cliffs Resident Inspectors William Cook Resident Inspectors Resident Inspectors Chris Welch Paulette Torres
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
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"*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 S70 hrs/yr
"- Annual Fire Protection 5 hr s/y r S3
"* Trienniel Fire Protection -200 hrs every 3 yrs
"* Operator Response - 125 hrs/yr
"* Plant security -40 hrs/yr
"* Emergency preparedness -60 hrs/yr
"* Rad release controls -O0 hrs every 2 yrs
"* Worker radiation protection A125 hrs/yr
"* Corrective action program 10% every inspection
"* Corrective action program -200 hr every 2 yrs
Signifigance Threshold Green: Very Low safety significance White: Low to moderate safety significance Yellow: Substantial safety significance Red: High safety significance Green: Only baseline Inspection White: May increase NRC oversight Yellow: Requires more NRC oversight Red: Requires more NRC oversight
Action Matrix Concept Licensee Regulatory Degraded Multiple/Degraded Unacceptable Response Response Cornerstone Cornerstone Performance Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions
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 1834 SWhite 8 SYellow 0 SRed: 0 n Total Inspection Findings (April 2001 - December 2001)
Green 660 SWhite 23 SYellow 2 o Red 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
-- , 17=
- - _7 z---- 'i 1117 17ý1,- I I - , I - '17- _-, -:,ýT ý - ZMEEMMM Performance Indicators 4Q/2001 Performance Indicators
Ginna Inspection Finding Summary Most Significant Inspection Findings 4Q12001 3Q02001 CoSurAt3gn~ation 2Q12001 Ftininswitio~L color designation IQ12001 Mfisefflneous fiding's
Simplified Pressurized Water Reactor Containment THrottle Valve Main Electric Turbine 0 er dox
-J Reactor Feedwate Pump
Strategic Performance Areas I Safety Cornerstones Reactor Safety
- Emergency Preparedness 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 Eggs=
"* 18 Performance Indicators
"* Covers all cornerstones
"* Licensee submits data to NRC quarterly
"* Baseline Inspection program verifies accuracy
"* Available on Reactor Oversight Program Web site
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 er ity Emergency 01 Preparedness Physical PrPtection Performance Indicators Emergency AC Power System Unavailability Protected Area Equipment High Pressure Injection System Unplanned Unavailability Scrams Personnel Screening Heat Removal ProgramI System Scrams with Unavailability Loss of Normal Heat Removal Residual Heat FFDlPersonnel Removal System Reliability Unavailability Program Unplanned Power Change Safety System Functional Failure
Inspection Areas Safeguards Emergency Preparedness Physical Protection Inspection Procedures 0 Adverse Weather S rability Evaluation 0 Excercise Evaluation "* Sec Authorization 0 Evaluation of Changes S rator Workarounds 0 Alert and Notice Access S Equipment Alignment 0 ianent Mods-Online 0 ERO Augment "* Sec Search 0 Fire Protection 0 ianent Mods o EAL "* Sec Response S Flood Protection 0 Maintenance Test 0 EP Preparation "* Sec Plan change S Heat Sink 0 eling Outage 0 Drill Evaluation S In Service Inspection S I 0 RAD Access 0 Operator Requalification 0 eillance Testing
- ALARA Plan 0 Maintenance Rule Imp 0 porary Modifications 0 RAD monitoring 0 Maintenance Risk Assessment 0 R 0 RAD Effluents S Non-Routine Events S it Follow-up 0 RAD Transport S erification o RAD Environmental
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%
90.0% 92.1%
88.0%
86.0%
04.0%
82.0%
00.0%1 Thresholds: White < 94.0% Yellow < 90.0%