ML033140291

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Summary of Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station
ML033140291
Person / Time
Site: Cooper Entergy icon.png
Issue date: 11/07/2003
From: Kennedy K
NRC/RGN-IV/DRP/RPB-C
To: Warren C
Nebraska Public Power District (NPPD)
References
Download: ML033140291 (31)
v • d • e


Text

UNITED STATES iNUCLEAR REGULATORY COMMISSION REGION IV 611 RYAN PLAZA DRIVE, SUITE 400 44t X

SoARLINGTON, TEXAS 76011-4005 November 7, 2003 Clay C. Warren, Chief Nuclear Officer Nebraska Public Power District P.O. Box 98 Brownville, NE 68321

SUBJECT:

SUMMARY

OF MEETING WITH NEBRASKA PUBLIC POWER DISTRICT REGARDING COOPER NUCLEAR STATION

Dear Mr. Warren:

This refers to the meeting conducted at the Brownville Concert Hall, Brownville, Nebraska, on November 4, 2003. The purpose of this meeting was to present the results of the NRC's third quarterly inspection of Cooper Nuclear Station's actions associated with the Confirmatory Action Letter issued on January 30, 2003, and the Biennial Problem Identification and Resolution inspection conducted at the Cooper Nuclear Station. The attendance list and the NRC's and Nebraska Public Power District's presentation slides are enclosed.

In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely, Kriss M. Kennedy, Chief Project Branch C Division of Reactor Projects Docket: 50-298 License: DPR-46

Enclosures:

1. Attendance List
2. NRC Presentation Slides
3. NPPD Presentation Slides

Nebraska Public Power District Chief, Radiation and Asbestos Control-Section Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366 Daniel K. McGhee Bureau of Radiological Health Iowa Department of Public Health 401 SW 7th Street, Suite D Des Moines, IA 50309 William J. Fehrman, President and Chief Executive Officer Nebraska Public Power District 1414 15th Street Columbus, NE 68601

Nebraska Public Power District Electronic distribution by RIV:

Regional Administrator (BSM1)

DRP Director (ATH)

Acting DRS Director (DDC)

Senior Resident Inspector (SCS)

Branch Chief, DRP/C (KMK)

Senior Project Engineer, DRP/C (WCW)

Staff Chief, DRP/TSS (PHH)

RITS Coordinator (NBH)

Jim Isom, Pilot Plant Program (JAI)

RidsNrrDipmLipb Anne Boland, OEDO RIV Coordinator (ATB)

CNS Site Secretary (SLN)

AqIAMS:

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II OFFICIAL REC-(ORD COPY T=Telephone E=E-mail F=Fax

ENCLOSURE 1 ATTENDANCE LIST

NRC PUBLIC MEETING ATTENDANCE LICENSEE/FACILITY Nebraska Public Power District l_

Cooper Nuclear Station DATE/TIME November 4, 2003; 7:00 p.m.

LOCATION Brownville Concert Hall, Brownville, Nebraska

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NRC PUBLIC MEETING ATTENDANCE LICENSEE/FACILITY Nebraska Public Power District Cooper Nuclear Station DATE/TIME November 4, 2003; 7:00 p.m.

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NRC PUBLIC MEETING ATTENDANCE LICENSEE/FACILITY Nebraska Public Power District Cooper Nuclear Station DATE/TIME November 4, 2003; 7:00 p.m.

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NRC PUBLIC MEETING ATTENDANCE LICENSEE/FACILITY Nebraska Public Power District Cooper Nuclear Station DATE/TIME November 4, 2003; 7:00 p.m.

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ENCLOSURE 2 NRC PRESENTATION SLIDES

U.S. Nuclear Regulatory Commission

=2 Region IV I'm Cooper Nuclear Station Exit Meeting sW. I d 37 Hi _ NRC Personnel Art Howell Director, Division of Reactor Projects Kriss Kennedy Chief, Branch C, Division of Reactor Projects Anthony Gody Chief, Operations Branch, Division of Reactor Safety Greg Werner Senior Operations Engineer, Operations Branch, Division of Reactor Safety Wayne Walker Senior Project Engineer, Branch C, Division of Reactor Projects Scott Schwind Senior Resident Inspector, Cooper Nuclear Station Victor Dricks Public Affairs Officer, Region IV Srd*. 2 d 37 Nebraska Public Power District Cooper Nuclear Station Introduction Meeting Guidelines

41.

..a Purpose of Meeting - Inform Public of Inspection Findings Meeting with Licensee sWd.3.I37 M~. 4 d 37

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Meeting Guidelines Registration Table Questions and Answers Handouts Feedback Forms Sfld.5d 37 4

Meeting Agenda Inspection Summary Confirmatory Action Letter Inspection Identification and Resolution of Problems Inspection Nebraska Public Power District Response Questions and Answers S6Jd.6d 37 x a, Inspection Summary

  • The confirmatory action letter inspection allows the NRC to assess the effectiveness of the Cooper Strategic Improvement Plan to address degraded performance.

u The identification and resolution inspection allows the NRC to evaluate the effectiveness of the Cooper corrective action program to detect and correct problems in a manner that limits risk to members of the public.

Inspection Summary (Cont)

  • Progress is being made in each CAL area, but either additional efforts or time Is needed especially in the area of human performance and equipment reliability.
  • Issues adequately identified, but problems persist with the evaluation of issues and effectiveness of corrective actions.
  • 6 Potential Violations of low safety significance Sfid. 7 d37 M.*8 d 37 Sid. 7 6137 Sfld. 9 61 37

Confirmatory Action Letter

  • Human Performance
  • Material Condition and Equipment Reliability
  • Plant Modifications and Configuration Control
  • Corrective Action Program, Utilization of Industry Operating Experience, and Self-Assessments
  • Implementation of Engineering Programs Sd. S d 37 i Confirmatory Action Letter nspection Scope
  • Six CAL Focus Areas
  • NRC and Cooper Performance Indicators
  • NRC Baseline Inspections
  • Issues Identified in the 2nd Quarterly CAL Inspection, June 2003
  • Cooper Audits and Self Assessments SMd. 10.M 37 Confirmatory Action Letter Inspection Results Team reviewed 52 improvement plan actions.

50 of 52 actions reviewed were completed as described in the Strategic Improvement Plan.

A number of the important actions in the Action Plans covered by the CAL have been implemented.

Overall, 157 of 263 Strategic Improvement Plan actions reviewed.

'l Quality of Improvement Plan Closure Packa!ge

  • Closure packages were complete with two exceptions noted.
  • Some minor discrepancies noted SlMd. 1 I c37 Sfid. 12 d 37

Oa Emergency Preparedness 1114aw-, -I,-

  • Improvement Plan Actions addressed in CAL completed and previously inspected (June 2003)
  • Performance indicators
  • Baseline inspections Sid. 13 d 37 Evaluation of Human Performance
  • Five CAL related improvement plan actions reviewed and completed.
  • Efforts to improve performance have been less than fully effective. However, some Improvements noted.
  • Baseline Inspections Slid. 14 d 37 Evaluation of Human Performance (cont) 4 of 6 performance indicators reviewed by the team did not meet goals or were unsatisfactory.

- Human Performance Event

- Human Performance Error Rate

- Qualification Matrix Adherence

- Overtime (%hours) Year to Date

  • 2 of 6 performance indicators meeting goals

- Configuration Control Events

- OSHA Recordable Injury Rate SM. IS d 37 4valuation of Human Performance E~

(cont)

  • Self assessments
  • Additional actions are needed to improve and maintain performance.
  • Improvements are in the process of being implemented.

SlidM.

1S 37

~Maeril ondtin and Equipment 4

Ribility

  • 35 of 37 improvement plan actions were completed as scheduled.
  • Actions Implemented have not resulted In satisfactory performance.
  • Several examples of challenges to plant and equipment reliability Sld. 170139

~aterial Condition and Equipment

  • Actions completed to date have provided the necessary processes or actions for Improvement.

- Numerous equipment improvements have recently been completed.

- Additional time is needed to bring about improvement.

SM9d.

19 137 Plant Modifications and Configuration Control

  • 3 actions were completed as scheduled.
  • Baseline Inspections
  • Performance Indicators
  • Engineering Inspection May 2003 did not identify any significant issues.
  • Additional time is needed to bring about improvement.

Sd. 190 d37 Corrective Action Program, Utilization oy lndustry Operating Experience and Self-Assessment

  • 7 actions completed as scheduled.
  • Issues adequately identified, but problems persist with the evaluation of Issues and effectiveness of corrective actions.
  • Baseline Inspections
  • Self Assessments were thorough and self-critical.
  • Industry operating experience
  • Performance indicators Slid. 20d 37

I 14 1 Engineering Programs

  • One action completed as scheduled.
  • Performance Indicators not meeting goals.
  • Baseline inspections
  • Additional time is needed to bring about improvement.

Slid. 21 d 37 Confirmatory Action Letter 4

Inspection Conclusions Most improvement plan actions were completed on schedule.

Progress Is being made in each CAL area.

- Additional actions appear to be necessary In the human performance area.

- More time is necessary to demonstrate improved equipment reliability.

Soid.

22 237 Identification and Resolution of Introduction - Anthony Gody 4

E Identification and Resolution of Problems _nspecton (Cont)

Evaluated Areas

1) Effectiveness of problem Identification
2)

Effectiveness of prioritization and evaluation of issues

3)

Effectiveness of corrective actions

4)

Assessment of safety-conscious work environment Sid. 24 d 37 Sid. 230137

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Effectiveness of Problem ii 4 Identification -Assessment

  • Problems were adequately identified and entered into the corrective action program -some exceptions noted.

- Operator work arounds

- Aging Agastat relays -Potential Criterion XVI Violation

  • Previous inspections also determined problems were adequately Identified.
  • Plant personnel had low thresholds for entering problems into the corrective action program.

SMil. 2S d 37 Effectiveness of Prioritization and

,valuation of Issues - Assessment

  • Problems with prioritization and evaluation of Issues.
  • Two -evaluations failed to Identify the apparent cause of the events.

- RCR 2003-0979

- RCR 2003-0428 Slid. 26 d 37 Effectiveness of Prioritization and Evaluation of Issues - Assessment (Cont)

  • 17 examples of failure to follow preventive maintenance procedures - Potential T.S. 5.4.1 Violation Effectiveness of Prioritization and Evaluation of Issues - Assessment
  • The quality of root cause determinations were good.
  • Significant improvement in the ownership and knowledge of the condition review group and the corrective action review board.

Sid. 27 d 37 SMd. M8 d 37

Effectiveness of Corrective Actions -Assessment

- Fire protection modifications not actively pursued

- Service air compressor preventive maintenance not performed

- Aging Agastat relay replaced with a relay of the same age -Potential Criterion XVI violation Sd. 29.1 37 Effectiveness of Corrective w~ctons Asessment_(Cqnt)

  • Continued problems with operability determinations - Potential Criterion XVI violation Slid. 30 d 37 Safety-Conscious Work I Environment - Assessment S1..-
  • Employees were willing to identify safety issues through either the corrective action program or the employee concerns program.

Identification and Resolution of Problems Conclusions

  • All potential violations have either been corrected or placed into the corrective action program.
  • All potential violations are of low safety significance.
  • Issues adequately identified, but problems persist with the evaluation of issues and effectiveness of corrective actions.

Slod.31 d137 Slid.* 32 d 37

i0 Other Finding

  • Potential Appendix B, Criterion III, design control violation for an unauthorized modification to the Zurn strainer controllers.

Slid. 33 dl 37 Public Power District

Response

Slid. 34 d D U.S. Nuclear Regulatory Commission Region IV Coi Com -.me n

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Closing Comments Slid. 35 d 37

U.S. Nuclear Regulatory Commission Region IV Conclusion of the Cooper Nuclear Station Exit Meeting Skib 37 d 37

ENCLOSURE 3 NPPD PRESENTATION SLIDES

Agenda PI & R / 3rd Quarter TIP Inspection NRC Public Meeting Cooper Nuclear Station November 4, 2003

  • Opening Remarks
  • Inspection Results &

Overall Performance

  • Human Performance
  • Corrective Action Program
  • Equipment Reliability &

Program Improvements

. Closing Remarks Stu Minahan Stu Minahan Stu Minahan John Christensen Gary Kline Stu Minahan Inspection Results &

Overall Performance Stu Minahan Acting Site Vice President I'I 3

Inspection Results

  • CNS generally agrees with the results
  • CNS concurs with the potential NCVs
  • CNS recognizes importance of cross-cutting focus areas
  • Actions have been taken, or in progress, to address these issues I

Overall Performance

  • Plant Performance

- Recent forced outage

- Planned power reductions to correct equipment issues

  • Working toward changing attitudes concerning plant and personnel performance 5

Pillar PI Trend 70%

60%

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-006 CO.g.40..00" 20%

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Human Performance

  • Accelerating improvement efforts
  • Implementing changes and tools
  • Realizing changing trends in the positive direction
  • 0 Human Performance Event Free Days 100 80.

70 60 50 30 20 10

OSHA Recordable Injury Rate 1.4

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1 1.0 106 0.4 02 00 Operator Distractions 250 200 A

150 I100 50 04O ow

>+s~~//e4 Control Room Deficiencies 540 40 II 2 5 10 5

0-On-line Maintenance Backlog 300

[50

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5 '

4

Engineering Inventory 3750 3125 2500 I t87s L 1250 Q1 Human Performance Going Forward

  • Increased focus on management observations and coaching
  • Increase in dedicated resources
  • Implementation of integrated Human Performance Trainer

- Multi-faceted - Safety, chemistry, radiation protection, human performance traps, procedure usage,..

  • Long term evolution of Trainer 0 -

I - - __ -

11.1

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  • 7 Conclusion
  • Will continue to be one of the critical management focus areas
  • Maturing Human Performance Trainer
  • Focus on upcoming refuel outage
  • Future assessments 19 Corrective Action Program John Christensen Plant Manager I~

1 la~="70 5

CAP Open Items 2800 2600 2400-2200

{C 2000 i 1800 '

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  • 600 -

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1400 1&DO CAP Backlog 350 300-S.50

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'0 0 0 CAP Performance Index 35s 3sA 2 5 2D 1.5 001 Equipment Reliability &

Program Improvements Gary Kline General Manager, Engineering 6

Building the Foundation

  • Equipment Reliability Process
  • Plant Health Committee
  • System Engineering Roles and Responsibilities
  • Trending / Monitoring Focus
  • Top 10 Alignment
  • Training

~2 6

Equipment Reliability Process

'I I

27 Building the Foundation ao.,

  • Plant Health Committee

- Management Alignment

- Interfacing with System Engineers

- Key Focus Areas 7

Building the Foundation

  • System Engineering Roles and Responsibilities

- Realignment of Priorities

- INPO Assist Visit 29 Building the Foundation (cont)

  • Trending / Monitoring Focus

- Proactive Engineering

- Improvements 30 New SW System Equipment Related CM Orders El f

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Unplanned RB HVAC System LCO's V1 1

A 13 Building the Foundation (..,

  • Training

- Upgrade to improve Engineering Performance

- Emphasis on Plant reliability 351 Successes

  • Overall System Health
  • Mitigation of Missouri River Level Changes
  • Scram Solenoid Pilot Valves
  • Diesel Generator Connecting Rod 9

System Health Successes (cont.)

10 S ~m

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  • Mitigation of Missouri River Level Changes
  • Scram Solenoid Pilot Valves
  • Diesel Generator Connecting Rod 38 Challenges
  • Material Condition Balance of Plant
  • Change Management
  • Workload Management 39 Program Improvements
  • Performance Indicator
  • EQ Program Closure Assessment 1-10

Program Health woCo 7S5' Closing Remarks Stu Minahan Acting Site Vice President 11

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