ML021000052
| ML021000052 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 04/05/2002 |
| From: | Marilyn Evans Reactor Projects Branch 1 |
| To: | |
| References | |
| MN-02-013 | |
| Download: ML021000052 (37) | |
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 04/05/2002 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) 50-317; 50-318 Plant/Facility Name Calvert Cliffs Nuclear Power Plant, Units 1 and 2 TAC Number(s) (if available)
Reference Meeting Notice 02-013 Purpose of Meeting (copy from meeting notice)
The NRC staff and CCNPPI management will discuss the results of NRC's assessment of the safety performance of Calvert Cliffs for the period 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 1 *L R0c 4
4**Q Nuclear Regulatory Commission King of Prussia, PA
-Region I
Agenda
"- Introduction
"* The NRC - Who We Are & What We Do
"* The Reactor Oversight Process
"* Calvert Cliff's Plant Performance
"* Comments by Constellation Nuclear
"* NRC Closing Remarks
"* The NRC staff will be available following the meeting to address questions from the public
NRC Response to 9/11 1 ' -. --
I.................
"* 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
Region I Organization n SI gional Speiai'stsl I
Michele Evans Branch Chief Calvert Cliffs Resident Inspectors David Beaulieu Leonard Cline I
I I
Project Engineers Ginna Nine Mile Point William Cook Resident Inspectors Resident Inspectors Paulette Torres H. Miller Regional Administrator J. Wiggins Deputy Regional Administrator A. Blough Director Division of Reactor Projects Brian Holian Deputy Director W. Lanning Director Division of Reactor Safety R. Crlenjak Deputy Director I
I
NRC Representatives
"* Hubert Miller, Regional Administrator
"* A. Randolph Blough, Director, Division of Reactor Projects
"* Michele Evans, Chief Reactor Projects Branch 1
- (mge@nrc.gov (610) 337-5224)
"* Donna Skay, Project Manager, NRR
- (dms6@nrc.gov (301) 415-1322)
"* David Beaulieu, Senior Resident Inspector
- (dpb@nrc.gov (410) 586-2626)
"* Leonard Cline, Resident Inspector
- (lmcl@nrc.gov (410) 586-2626)
"* Public Affairs Office Region 1
- (OPA1@nrc.gov (610) 337-5330)
Reference Sources
"* NRC Home Page Shttp://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 S1-800-397-4209 (Toll Free) t " -7T,
- I --
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 use nuclear materials and operate plants safely, and 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
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones
~Baseline Inspection R.
I1 Results Significance Threshold Action Matrix I Regulatory Response I
Strategic Performance Areas I Safety Cornerstones
"* Reactor Safety
"* Radiation Safety
- Occupational Radiation Safety
"* Safeguards
Examples of Baseline Inspections
"* Equipment Alignment
"* Annual Fire Protection
"* Trienniel Fire Protection
"* Operator Response
"* Plant Security
"* Radiation 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 hrs/yr
-60 hrs/yr
-O0 hrs every 2 yrs A125 hrs/yr
-10% every inspection
-200 hrs every 2 yrs
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
Significance Threshold Inspections Findings Green:
Very Low safety significance White:
Low to moderate safety significance Yellow:
Substantial safety significance Red:
High safety significance Performance Indicators Green:
Only baseline Inspection White:
May increase NRC oversight Yellow:
Requires more NRC oversight Red:
Requires more NRC oversight
Calvert Cliffs Inspection Activities (January 1 - December 31, 2001)
- 4990 hours0.0578 days <br />1.386 hours <br />0.00825 weeks <br />0.0019 months <br /> of inspection related activity
- Two resident inspectors performing resident inspections
- 13 inspections by regional inspectors
, Included: two team inspections, one special inspection, and one supplemental inspection
- Inspection Findings
, 17 findings of very low safety significance One finding of substantial safety significance
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 Regulatory 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 SWhite SYellow SRed:
1834 8
0 0
n Total Inspection Findings (April 2001 - December 2001)
Green SWhite SYellow SRed 660 23 2
0
Calvert Cliffs Annual Assessment (April 1 - December 31, 2001)
"* Both units operated safely.
"* Met all cornerstone objectives with moderate degradation in safety performance.
"* Overall plant performance was within the Degraded Cornerstone Column of Action Matrix based on a Unit 1 inspection finding of substantial safety significance (Yellow) in Mitigating Systems cornerstone.
"* The "Scrams with Loss of Normal Heat Removal" performance indicator (PI) for Unit 1 has been WHITE since the first quarter of 2000.
Calvert Cliffs Annual Assessment (April 1 - December 31, 2001)
- Unit 2 was within the Licensee Response Column of the Action Matrix for the entire assessment cycle, based on all inspections findings and performance indicators being GREEN.
Calvert Cliffs 1 Performance Indicators 4Q/2001 Performance Indicators S crams With Loss of Normal Heat Removal Mf
Calvert Cliffs 1 Inspection Finding Summary Most Significant Inspection Findings IEY 1)L M/scelfaneous I
f/nd/ngs 40/2001 3Q02001 2Qf2001 IQ02001 Ttlý
Calvert Cliffs 2 Performance Indicators 4Q/2001 Performance Indicators
Calvert Cliffs 2 Inspection Finding Summary Most Significant Inspection Findings 4Q12001 3Q12OO1 2Qt2001 1Q02001 miscefllneou.5 ffnincgf,q I 1111 a Kim FM M.-.
n S Ahis quarter"
. W.,
Mitigating Systems Cornerstone
"* Yellow inspection finding associated with the No. 11 auxiliary feedwater pump failure (reference Inspection Report 50-317/01-09, dated August 24, 2001).
"* Maintenance instructions were not adhered to during reassembly of the No. 11 AFW pump's bearing housing. As a result, excessive sealant was applied which contaminated the oil and most likely, entered the bearing, resulting in a loss of lubrication and bearing failure.
Mitigating Systems Cornerstone
"* Supplemental inspection conducted in December 2001 (reference Inspection Report 50-317/01-13, dated January 14, 2002), identified that the causal evaluation and corrective actions were acceptable.
"* Substantive cross-cutting issue identified in the area of Problem Identification and Resolution, in part, due to seven findings in this cornerstone involving inconsistent and less than thorough assessments of degraded and non-conforming structures, systems, and components.
"* NRC Plans to conduct PI&R inspections annually over the next two years because PI&R issues contributed to the YELLOW inspection finding.
Simplified Pressurized Water Reactor Containm.nt Valve Main EleCtric Turbine Geerator J
Feeedwater Pump RCP System
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 Event Follow-up and Supplemental 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
"* Review events for significance
"* Follow-up significant inspection findings
"* Determine causes of performance declines
- Provides for graduated response
Key Aspects of Assessment Program
- Objective assessment of performance
- "Action Matrix" to determine agency response to performance
- 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:
SHuman performance SProblem Identification and Resolution Safety conscious work environment
"* Common cause of inspection findings
"* Common cause documented in an assessment letter
Performance Indicators Safeguards]
Physical Protection Emergency C
erf Preparedness Performance Indicators Unplanned Scrams Scrams with Loss of Normal Heat Removal Unplanned Power Change Emergency AC Power System Unavailability High Pressure Injection System Unavailability Protected Area Equipment Personnel Screening Program FFD/Personnel Reliability Program Safety System Functional Failure 77777,777,777
Inspection Areas Safeguards]
Physical Protection Emergency Preparedness 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 Inspection Procedures
"* Operability Evaluation 0 Excercise Evaluation
"* Operator Workarounds 0 Alert and Notice
"* Permanent Mods-Online 0 ERO Augment
"* Permanent Mods 0 EAL
"* Post Maintenance Test 0 EP Preparation
"* Refueling Outage 0 Drill Evaluation
"* SSDI
- RAD Access
"* Surveillance Testing 0 ALARA Plan
"* Temporary Modifications 0 RAD monitoring
"* PI&R 0 RAD Effluents
"* Event Follow-up
- RAD Transport
"* PI Verification 0 RAD Environmental
"* Sec Authorization Access
"* Sec Search
"* Sec Response
"* Sec Plan change S
0 0
S 0
0 0
0 S
S 0
NRC Action Matrix Licensee Response Regulatory Response Degraded Cornerstone Multiple/ Repetitive Unacceptable Column Column Column Degraded Cornerstone Performance 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 1 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 ILI Objectives Fully Met Objectives Fully Met Performance Area; Input; Cornerstone Margin to Safety IX 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 I.
Action Action with NRC Assessment with NRC Improvement Plan with z
__Oversight Oversight NRC Oversight 0
[.
NRC Inspection Risk-Informed Baseline Baseline and Baseline and Baseline and U)
Inspection supplemental supplemental supplemental ILI 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 inspection plan)
(w/ inspection plan)
(w/ inspection plan)
(w/ inspection plan)
Commission Informed i
Annual Public Meeting SRI or BC Meet with BC or DD Meet with RA (or designee)
EDO (or Commission)
Commission Meeting 0
Licensee Licensee Discuss Performance Discuss Performance with Senior Licensee with Licensee with Senior Licensee Management
_Manaaement INC.RFARING SAFFTY Si;NIFICANCQ1
Performance Indicator Scrams with Loss of Normal Heat Removal r
N Ct, uCf U
3 3N Thresholds: White > 2.0 Yellow > 10.0 Red > 20.0 C
a r
C a
N
- 0.
4,-
8 12 16 20