ML030920486
| ML030920486 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 04/16/2003 |
| From: | Ann Marie Stone NRC/RGN-III/DRP/RPB3 |
| To: | |
| References | |
| Download: ML030920486 (27) | |
Text
Annual Assessment Meeting Nuclear Regulatory Commission
NRC Performance Goals PMaintain safety and protect the environment PEnhance public confidence PImprove effectiveness, efficiency, and realism of processes and decision making PReduce unnecessary regulatory burden
Reactor Oversight Process Safety Cornerstones Inspection Results Significance Threshold Action Matrix Significance Threshold Performance Indicator Results Regulatory Response Strategic Performance Areas
Key Aspects of the Assessment Program PObjective review of licensee performance PAction Matrix identifies agency response commensurate with safety significance PIncreasing safety significance results in:
- Increased levels of inspection
- Involvement of higher levels of NRC and Licensee management
- Increased regulatory action PPlant specific assessment information on NRC public web site
Regional Organization Regional Specialists Roy Caniano, Deputy Director Division of Reactor Safety Cynthia Pederson, Director Braidwood Resident Inspector Office Steven Ray, Senior Resident Inspector Nirodh (Nick) Shah, Resident Inspector Thomas Tongue, Project Engineer Jack Rutkowski, Reactor Engineer Jamie Bond, Intern Reactor Projects Branch 3 Ann Marie Stone, Chief Steven Reynolds, Deputy Director Division of Reactor Projects Geoffrey E. Grant, Director James Caldwell, Deputy Regional Administrator Jan Strasma, Regional Public Affairs Officer Jim Dyer, Regional Administrator
Annual Licensee Assessment Meeting PA public forum for discussion of the licensees performance PNRC will address the licensee performance issues identified in the Annual Assessment Letter PLicensee will respond to the information in the letter and inform the NRC of new or existing programs to maintain or improve their performance
ROP Action Matrix Summary for 2002 Column 1 Column 2 Column 3 Column 4 Column 5 Nationwide 59 33 7
3 0
Region I 9
14 2
1 0
Region II 26 4
1 1
0 Region III 11 10 2
0 0
Region IV 13 5
2 1
0 P Column 1 - Licensee Response P Column 2 - Regulatory Response P Column 3 - Degraded Cornerstone P Column 4 - Multiple/ Repetitive Degraded Cornerstone P Column 5 - Unacceptable Performance (Nationwide number does not contain Davis Besse)
Security & Safeguards Update PCreation of Office of Nuclear Security and Incident Response PTop-to-Bottom Review of Security Program Initiated PIssuance of Orders/ Interim Compensatory Measures (ICM)
PVerification of Licensee Actions on ICM
Security & Safeguards Update PProposed Revisions to Design Basis Threat PPending Orders on Fatigue/Guard Training PInitiation of Pilot Force-on-Force Excercise Program
Plant Information P Name of Plant: Braidwood Station, Units 1 and 2 P Plant Operator: Exelon P Number of Units: 2 P Reactor Type and Vendor: PWR/W P Location: Braidwood, IL P Power Output (thermal): 3586.6 megawatts P Source of Circulating Water: Kankakee River
Major Plant Activities in 2002 Braidwood Station, Unit 1 P Unit operated at or near full power throughout the assessment period
Major Plant Activities in 2002 Braidwood Station, Unit 2 P Reactor shutdown for refueling outage (4/20/02)
P 75% power reduction for repairs to feedwater isolation valve (5/28/02)
P Reactor shutdown for rod control troubleshooting and repairs (8/27/02)
P 12% power reduction to address problem with feedwater heaters (11/01/02)
Major Plant Activities in 2002 Braidwood Station, Unit 2 (continued)
P 72% power reduction for testing of feedwater isolation valves (11/02/02)
P 76% power reduction and electric generator taken off electrical grid for balancing (12/26/02)
Plant Performance Summary Braidwood Station, Unit 2 P11 GREEN Findings
Maintenance errors
Failure to maintain proper operational configuration
Failure to follow procedures
Inadequate procedures
Failure to adequately evaluate conditions PAll Performance Indicators Within GREEN Band
Plant Performance Summary Braidwood Station, Unit 2 POperated Safely PFully met all Cornerstone Objectives PLicensee Response Band of NRC Action Matrix
Plant Performance Summary Braidwood Station, Unit 1 P6 GREEN Findings
Failure to follow procedures
Failure to maintain proper operational configuration
Inadequate procedures PAll Performance Indicators Presently Within GREEN Band
Greater than GREEN Findings and PIs Braidwood Station, Unit 1 P1 WHITE Finding (2/22/2002)
Inoperable Pressurizer Power Operated Relief Air Accumulator Check Valves
Failure to identify cause and prevent recurrence
Migitation System Cornerstone P1 Performance Indicator within WHITE band
Auxiliary Feedwater System Unavailability
1st and 2nd Quarters 2002
Migitation System Cornerstone
Greater Than Green Results and Requirements Braidwood Station, Unit 1 PDegraded Cornerstone Band (1st and 2nd quarters, 2002)
PRequired Actions
Licensee self-assessment with NRC oversight
NRC perform supplemental inspection
NRC discuss Licensee performance with Licensee PRegulatory Response Band (3rd and 4th quarters, 2002)
Supplemental Inspection Braidwood Station, Unit 1 PPurpose
Assure Root Cause for individual and collective concerns are understood
Independently assess extent of condition
Assure Licensee corrective actions are appropriate to prevent recurrence PConducted November 4 - December 4, 2002
Supplemental Inspection Results Braidwood Station, Unit 1 PReport Conclusions
Unit Operated Safety
No additional findings or violations
Liscensee investigation was in-depth
Extent of condition addressed Generic Concerns
Planned corrective actions appear adequate to prevent recurrence PNRC Problem Identification and Resolution Inspection Scheduled for 2003
Plant Performance Summary Braidwood Station, Unit 1 POperated Safely PMet Cornerstone Objectives PRegulatory Response Band of NRC Action Matrix
Contacts for additional information for:
Braidwood Station, Units 1 and 2 P Regional Public Affairs Officer:
Name: Jan Strasma
Phone: 630-829-9663 P State Liaison Officer:
Name: Roland Lickus
Phone: 630-829-9660 P Branch Chief:
Name: Ann Marie Stone
Phone: 630-829-9729 P Senior Resident Inspector:
Name: Steve Ray
Phone: 815-458-2852
Contacting the NRC PReport an emergency
(301) 816-5100 (call collect)
PReport a safety concern:
(800) 695-7403
Allegation@nrc.gov PGeneral information or questions
www.nrc.gov
Select What We Do for Public Affairs
Lic ens e e R es p ons e R egu la tory R es po ns e D e grad ed C orne rs tone M ultiple/ R epe titive U nac c ep tab le C olum n C o lum n C olum n D egra ded C orn ers ton e P e rform anc e C olum n C olum n R
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U L
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A ll A s s ess m ent Inp uts (P erform anc e In dic ators (P Is ) an d Ins p ec tio n Find ings )
G reen ; C orn ers ton e O bjec t iv es Fully M et O ne or Tw o W hite In puts (in d ifferen t c orne rs tones ) in a S tra teg ic P erfo rm anc e A rea ; C orn ers ton e O bjec tiv es Fully M et O ne D e grad ed C orne rs tone (2 W hite Inp uts o r 1 Y e llow Inp ut) or a ny 3 W hite Inp uts in a S trat egic P erfo rm anc e A re a; C orne rs tone O bjec tiv es M e t w ith M in im al R educ tion in S afety M a rgin R epe tit iv e D eg rad ed C orne rs tone, M ultip le D egra de d C orne rs tones, M u ltiple Y ellow Inpu ts, or 1 R ed Inp ut; C orne rs tone O bjec tives M e t w ith Lo ngs ta nding Is s ues or S ig nific ant R educ tion in S afe ty M a rgin O vera ll Un ac c epta ble P erfo rm anc e; P lan ts No t P e rm itted to O perate W ithin this B and, U nac c ep tab le M a rgin to S afe ty R
E S
P O
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E R eg ulato ry P e rform anc e M ee tin g N on e B ranc h C hief (B C ) o r D iv is io n D irec tor (D D )
M eet w ith Lic e ns ee D D or R eg io nal A dm in is trato r (R A )
M e et w ith Lic ens e e R A (or E D O ) M eet w ith S en ior Lic ens e e M a na gem en t C om m is s ion m eet ing w ith S enior L ic ens e e M a nag em en t L ic ens ee A c tio n Lic e ns ee C orrec tive A c tio n Lic e ns ee roo t c aus e ev alua tio n a nd c orrec tive ac tio n w ith N R C O vers ig ht Lic e ns ee S elf As s es s m ent w ith N R C O vers ig ht Lic e ns ee P erfo rm anc e Im prov em en t P lan w ith NR C O v ers igh t N R C Ins pec tion R is k-Info rm ed B as e lin e Ins p ec tio n P rog ram B as elin e a nd s upp lem e nta l ins p ec tio n p roc ed ure 95 00 1 B as eline an d s upp lem en tal ins p ec tio n p roc edu re 95 002 B as eline an d s upp lem en tal ins p ec tio n p roc edu re 95 003 R eg ulato ry A c tions N on e S up plem ental ins p ec tio n o nly S up plem e nta l ins p ec tio n o nly
-10 C FR 2.2 04 D FI
-10 C FR 50.54 (f) Le tte r
- C A L/O rde r Ord er to M odify,
S us pen d, or R ev ok e Lic ens e d A c tivities C
O M
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A s s ess m ent Le tters B C or DD re view /s ig n as s es sm en t rep ort (w /
ins p ec tio n p la n)
D D rev iew /s ign as s es sm en t rep ort (w / ins pec tion pla n)
R A rev iew /s ign as s ess m ent rep ort (w / ins p ec tio n p la n)
R A rev iew /s ign as s ess m ent rep ort (w / ins p ec tio n p la n)
C om m iss io n In form ed A n nua l P u blic M ee tin g S R I o r B C M e et w ith Lic e ns ee B C or DD M ee t w ith Lic e ns ee R A (or d es ig nee )
D is c uss P erf orm anc e w ith Lic e ns ee E D O (o r C om m iss io n)
D is c uss P erform anc e w ith S en ior Lic ens e e M a na gem en t C om m is s ion M eet ing w ith S enior L ic ens e e M a nag em en t INCREASING SAFETY SIGNIFICANCE ---------->
An Action Matrix is used to assess overall plant safety performance and specify thresholds for NRC Enforcement Actions
Significance Threshold Inspection Findings Green:
Very low safety issue White: Low to moderate safety issue Yellow: Substantial safety issue Red:
High safety issue