ML030920499
| ML030920499 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/21/2003 |
| From: | Eric Duncan NRC/RGN-III/DRP/RPB6 |
| To: | |
| References | |
| Download: ML030920499 (21) | |
Text
Annual Assessment And Performance Meeting Nuclear Regulatory Commission
NRC REPRESENTATIVES
- Jim Dyer, Administrator, Region III
- Sam Collins, Director, Office of Nuclear Regulation
- Geoffrey Grant, Director, Division of Reactor Projects, RIII
- Anton Vegel, Former Chief, Reactor Projects Branch 6
- Eric Duncan, Chief, Reactor Projects Branch 6
- Brian Kemker, Senior Resident Inspector, DC Cook
- Ivy Netzel, Resident Inspector, DC Cook
NRC Performance Goals P Maintain safety and protect the environment P Enhance public confidence P Improve effectiveness, efficiency, and realism of processes and decision making P Reduce unnecessary regulatory burden
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response
Annual Licensee Assessment Meeting P A public forum for discussion of the licensees performance P NRC will address the licensee performance issues identified in the Annual Assessment Letter P Licensee will respond to the information in the letter and inform the NRC of new or existing programs to maintain or improve their performance
Key Aspects of the Assessment Program P Objective review of licensee performance P Action Matrix identifies agency response commensurate with safety significance P Increasing safety significance results in:
- Increased levels of inspection
- Involvement of higher levels of NRC and Licensee management
- Increased regulatory action P Plant specific assessment information on NRC public web site
Significance Threshold
- Performance Indicators
- Green: Only baseline Inspection
- White: May increase NRC oversight
- Yellow: Requires more NRC oversight
- Red: Requires more NRC oversight
Significance Threshold
- Inspection Findings
- Green: Very low safety issue
- White: Low to moderate safety issue
- Yellow: Substantial safety issue
- Red: High safety issue
An Action Matrix is used to assess overall plant safety performance and specify thresholds for NRC Enforcement Actions L ic e n s e e R e s p o n s e R e g u la to ry R e s p o n s e D e g ra d e d C o rn e rs to n e M u lt ip l e / R e p e titi ve U n a c c e p ta b le C o lu m n C o lu m n C olum n D e g ra d e d C o rn e rs to n e P e rfo rm a n c e C o lu m n C o lu m n R A ll A s s e ss m e n t In p u ts O n e o r T w o W h i te O n e D e g ra d e d R e p e tit iv e D e g ra d e d O ve ra ll U n a c c e p ta b l e E (P e rf o rm a n c e In p u ts (i n d iff e re n t C o rn e rs to n e (2 W h i te C o rn e rs to n e , M u l tip le P e rfo rm a n c e ; P l a n ts S In d ic a t o rs (P Is ) a n d c o rn e rs to n e s ) in a In p u ts o r 1 Y e ll o w D e g ra d e d N o t P e rm itte d to In s p e c tio n F i n d in g s ) S tra te g ic P e rfo rm a n c e In p u t) o r a n y 3 W h it e C o rn e rs to n e s , M u lti p l e O p e ra t e W ith i n t h is U
G re e n ; C o rn e rs to n e A re a ; C o rn e rs to n e In p u ts i n a S tra t e g ic Y e l lo w In p u ts , o r 1 R e d B a n d , U n a c c e p ta b le L O b je c t iv e s F u l ly M e t O b je c t iv e s F u l ly M e t P e rfo rm a n c e A re a ; In p u t; C o rn e rs to n e M a rg in to S a fe ty T C o rn e rs to n e O b je c t iv e s O b je c ti ve s M e t w ith S M e t w it h M in im a l L o n g s ta n d i n g Is s u e s o r R e d u c t io n in S a f e ty S ig n if ic a n t R e d u c t io n in M a rg i n S a fe ty M a rg i n R R e g u l a to ry N on e B ra n c h C h i e f (B C ) o r D D o r R e g io n a l R A (o r E D O ) M e e t w ith C o m m is s io n m e e t in g E P e rfo rm a n c e D iv is io n D ire c t o r (D D ) A d m in is tra to r (R A ) S e n io r L ic e n s e e w ith S e n i o r L ic e n s e e S M e e tin g M e e t w ith L ic e n s e e M e e t w ith L ic e n s e e M a na gem en t M a nag em en t P L ic e n s e e A c tio n L ic e n s e e C o rre c ti ve L ic e n s e e ro o t c a u s e L ic e n s e e S e lf L ic e n s e e P e rfo rm a n c e O A c tio n e v a l u a tio n a n d As s e s s m e n t w i th N R C Im p ro v e m e n t P l a n w ith N c o rre c ti ve a c tio n w i th O ve rs ig h t N R C O v e rs ig h t S N R C O ve rs ig h t E
N R C In s p e c t io n R is k- In fo rm e d B a s e lin e B a s e l in e a n d B a s e l in e a n d B a s e l in e a n d In s p e c tio n s u p p le m e n ta l s u p p le m e n ta l s u p p le m e n ta l P ro g ra m in s p e c tio n p ro c e d u re in s p e c tio n p ro c e d u re in s p e c tio n p ro c e d u re 95 00 1 95 002 95 003 R e g u l a to ry A c ti o n s N on e S up plem ent al S u p p le m e n ta l -1 0 C F R 2 .2 0 4 D F I O rd e r to M o d i fy ,
in s p e c tio n o n l y in s p e c tio n o n ly -1 0 C F R 5 0 .5 4 (f) L e tte r S us pen d, or R ev ok e
- C A L /O rd e r L ic e n s e d A c ti vi tie s C A s s e ss m e n t L e tte rs B C o r D D re vi e w /s ig n D D re v ie w /s i g n R A re v ie w /s i g n R A re v ie w /s i g n O a s s e s sm e n t re p o rt (w / a s s e s sm e n t re p o rt a s s e ss m e n t re p o rt a s s e ss m e n t re p o rt M in s p e c tio n p la n ) (w / i n s p e c ti o n p la n ) (w / in s p e c tio n p la n ) (w / in s p e c tio n p la n )
M C o m m iss io n In fo rm e d U
N I A n n u a l P u b l ic S R I o r B C M e e t w ith B C o r D D M e e t w it h R A (or d e s ig n e e ) E D O (o r C o m m iss io n ) C o m m is s io n M e e t in g C M e e tin g L ic e n s e e L ic e n s e e D is c u ss P e rf o rm a n c e D is c u ss P e rf o rm a n c e w ith S e n i o r L ic e n s e e A w ith L ic e n s e e w ith S e n io r L ic e n s e e M a nag em en t T M a na gem en t I
O N
IN C REASING SAFETY SIGN IFICA NC E ---------->
ROP Action Matrix Summary for 2002 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)
Column 1 Column 2 Column 3 Column 4 Column 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
PLANT INFORMATION P Name of Plant: D. C. COOK NUCLEAR POWER PLANT P Plant Operator: Indiana/Michigan Electric Co.
P Number of Units: 2 operating units P Reactor Type and Vendor: PWR, Westinghouse P Location: Bridgman, MI P Power Output (electrical): Unit 1 - 1066 MWe, Unit 2 - 1030 MWe
Plant Performance Summary P Operated safely P Fully met all Cornerstone Objectives P Unit 1 In Regulatory Response Column of Action Matrix P Unit 2 In Degraded Cornerstone Column of Action Matrix P Substantive cross-cutting issue in the area of Problem Identification and Resolution
Major Plant Activities in 2002 Unit 1
- April 25th - Power reduced to 8 percent to secure components of a 345 kilovolt (kV) line disconnect
- May 3 - June 9 - Scheduled refueling outage.
- June 12th - Loss of preferred offsite power due to 345 kV breaker explosion and switchyard fire (ALERT declared).
- June 14th - Unit was manually tripped due to a main feedwater pump trip, which was caused by zebra mussel clogging the feedwater pump condenser.
- November 10th - Power reduced to 30 percent to add oil to a reactor coolant pump motor.
- December 21st - Power reduced to 53 percent to add oil to the reactor coolant pump motor.
- December 24th - Power reduced to 55 percent to remove a main feedwater pump from service
Major Plant Activities in 2002 Unit 2
- Jan 19 - Feb 28 - Scheduled refueling outage.
- April 4 - Power reduced to 41% for inop battery; NOED granted
- May 12 - Reactor trip due to redundant power supply failures
- May 25 - Reactor shutdown to isolate a steam leak and replace one of the main turbine reheat stop valves
- July 22 - Reactor trip due to low condensor vacuum
- July 27 - Reactor shutdown to replace circ water discharge valve
Greater than GREEN PIs and Findings (Details)
- Two WHITE inspection findings in the Mitigating Systems Cornerstone.
Unit 2 turbine driven auxiliary feedwater pump start failures.
Degraded essential service water system performance on both Unit 1 and Unit 2. Supplemental inspection conducted.
- All other inspection findings and PIs for the most recent quarter for both units were GREEN.
Supplemental Inspection Results
Purpose:
Assure Root Causes For Individual And Collective Concerns Are Understood
- Independently Assess Extent Of Condition
- Assure Licensee Corrective Actions Are
- Appropriate To Prevent Recurrence
- Conducted Feb 18 - 28
- Inspection Report Will Be Available In Adams
Supplemental Inspection Results
- Unit Operated Safely
- Two Additional GREEN Findings Turbine Driven Aux Feed Pump Maintenance Procedure Inadequate Inadequate Corrective Actions For Known Aux Feed Pump Parts Deficiencies
- Significant Weakness For Incomplete Extent Of Condition Evaluation
- Two WHITE Findings Remain Open
- NRC To Reinspect Once Licensee Completes Extent Of Condition Review
Security & Safeguards Update P Creation of Office of Nuclear Security and Incident Response P Top-to-Bottom Review of Security Program Initiated P Issuance of Orders/ Interim Compensatory Measures (ICM)
P Verification of Licensee Actions on ICM
Security & Safeguards Update P Proposed Revisions to Design Basis Threat P Pending Orders on Fatigue/Guard Training P Initiation of Pilot Force-on-Force Excercise Program
Contacts for additional information for:
(Enter plant name here)
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: Anton Vegel
< Phone: 630-829-9620 P Senior Resident Inspector:
< Name: Brian Kemker
< Phone: 269-465-6775
Contacting the NRC P Report an emergency
< (301) 816-5100 (call collect)
P Report a safety concern:
< (800) 695-7403
< Allegation@nrc.gov P General information or questions
< www.nrc.gov
< Select What We Do for Public Affairs