ML030920499

Summary of Public Meeting with American Electric Power Co., to Discuss D.C. Cook End of Cycle Plant Performance Assessment. NRC Presentation Slides

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 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

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

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

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

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

E S

U L

T S

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

N S

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

M U

N I

C A

T I

O N

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

ROP Action Matrix Summary for 2002 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 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)

PLANT INFORMATION PName of Plant: D. C. COOK NUCLEAR POWER PLANT PPlant Operator: Indiana/Michigan Electric Co.

PNumber of Units: 2 operating units PReactor Type and Vendor: PWR, Westinghouse PLocation: Bridgman, MI PPower Output (electrical): Unit 1 - 1066 MWe, Unit 2 - 1030 MWe PSource of Circulating Water: Lake Michigan

Plant Performance Summary POperated safely PFully met all Cornerstone Objectives PUnit 1 In Regulatory Response Column of Action Matrix PUnit 2 In Degraded Cornerstone Column of Action Matrix PSubstantive 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

• June 12 - NOED to allow opertion while restoring AFW

• July 22 - Reactor trip due to low condensor vacuum

• July 27 - Reactor shutdown to replace circ water discharge valve

• Nov 4 - NOED granted to allow operation while restoring EDG

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 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

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 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

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