ML033140291

Summary of Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station

ML033140291
Person / Time
Site:	Cooper
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)

Text

UNITED STATES

- iNUCLEAR REGULATORY COMMISSION

& REGION IV 611 RYAN PLAZA DRIVE, SUITE 400 44t SoARLINGTON, X TEXAS 76011-4005 November 7, 2003 Clay C. Warren, Chief Nuclear Officer Nebraska Public Power District P.O. Box 98 Brownville, NE 68321

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: "Yes El No Initials: W tVJ 0' Publicly Available El Non-Publicly Available Cl Sensitive ONon-Sensitive DMA f'KQIXtK144 A A'rAC% _D .M...-A I I--UO1V1O-LJ.-urc.wpu WCWalker;df KMKennedy _ ________

11/O6/03 11/ 1/03 _ _ I 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

[ NAME (PLEASE PRINT) ORGANIZATION Q 7C 1 n _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l l _

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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.

LOCATION Brownville Concert Hall, Brownville, Nebraska NAME (PLEASE PRINT) I ORGANIZATION 1R, >APe 0

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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.

LOCATION Brownville Concert Hall, Brownville, Nebraska NAME (PLEASE PRINT) I ORGANIZATION

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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.

LOCATION Brownville Concert Hall, Brownville, Nebraska NAME (PLEASE PRINT) ORGANIZATION b iFf(\ t bl~ {kl- )4i~r lth 4 k~~j iy/fL'Se/tVzI

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Page 4 Of 4

ENCLOSURE 2 NRC PRESENTATION SLIDES

U.S. Nuclear Regulatory Commission

• Hi _ NRC Personnel Art Howell Director, Division of Reactor Projects

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

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

a~ Meeting Guidelines 4 Meeting Agenda Inspection Summary Registration Table Confirmatory Action Letter Inspection Questions and Answers Identification and Resolution of Problems Inspection Handouts Nebraska Public Power District Response Feedback Forms Questions and Answers Sfld.5d 37 S6Jd.6d37 x a, Inspection Summary Inspection Summary (Cont)

• The confirmatory action letter inspection allows

• Progress is being made in each CAL area, but the NRC to assess the effectiveness of the Cooper either additional efforts or time Is needed Strategic Improvement Plan to address degraded especially in the area of human performance and performance. equipment reliability.

u The identification and resolution inspection allows

• Issues adequately identified, but problems persist the NRC to evaluate the effectiveness of the with the evaluation of issues and effectiveness of Cooper corrective action program to detect and corrective actions.

correct problems in a manner that limits risk to members of the public.

• 6 Potential Violations of low safety significance Sfid. 7 d37 M.*8 d Sid. 7 6137 Sfld.9 6137 37

' Confirmatory Action Letter iConfirmatory Action Letter nspection Scope

• Emergency Preparedness

• Six CAL Focus Areas

• Human Performance

• NRC and Cooper Performance Indicators

• Material Condition and Equipment Reliability

• NRC Baseline Inspections

• Plant Modifications and Configuration Control

• Issues Identified in the 2nd Quarterly CAL

• Corrective Action Program, Utilization of Industry Inspection, June 2003 Operating Experience, and Self-Assessments

• Cooper Audits and Self Assessments

• Implementation of Engineering Programs Sd. Sd 37 SMd.10 .M37 Confirmatory Action Letter 'l Quality of Improvement Plan Inspection Results Closure Packa!ge

• Team reviewed 52 improvement plan actions.

• Closure packages were complete with two

• 50 of 52 actions reviewed were completed as exceptions noted.

described in the Strategic Improvement Plan.

• Some minor discrepancies noted

• 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.

SlMd.1 I c37 Sfid. 12 d 37

Oa Emergency Preparedness Evaluation of Human Performance 1114aw-, -I,-

• Improvement Plan Actions addressed in CAL completed and previously inspected (June

• Five CAL related improvement plan actions 2003) reviewed and completed.

• Performance indicators

• Efforts to improve performance have been less than fully effective. However, some

• Baseline inspections Improvements noted.

• Baseline Inspections Sid. 13d 37 Slid.14 d 37 Evaluation of Human Performance (cont) 4valuation E~

of Human Performance (cont) 4 of 6 performance indicators reviewed by the team did not meet goals or were unsatisfactory.

• Self assessments

- Human Performance Event

- Human Performance Error Rate

- Qualification Matrix Adherence

• Additional actions are needed to

- Overtime (%hours) Year to Date improve and maintain performance.

• 2 of 6 performance indicators meeting goals

• Improvements are in the process of

- Configuration Control Events being implemented.

- OSHA Recordable Injury Rate SM. ISd 37 SlidM.

1S 37

~Maeril ondtin and Equipment ~aterial Condition and Equipment 4 Ribility

• 35 of 37 improvement plan actions were completed as scheduled.

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

• Actions Implemented have not resulted In satisfactory performance. - Numerous equipment improvements have recently been completed.

• Several examples of challenges to plant and equipment reliability - Additional time is needed to bring about improvement.

Sld. 170139 SM9d. 19 137 Plant Modifications and Configuration Corrective Action Program, Utilization Control oy lndustry Operating Experience and Self-Assessment

• 3 actions were completed as scheduled.

• 7 actions completed as scheduled.

• Baseline Inspections

• Issues adequately identified, but problems persist with the evaluation of Issues and effectiveness of corrective actions.

• Performance Indicators

• Baseline Inspections

• Engineering Inspection May 2003 did not

• Self Assessments were thorough and self-critical.

identify any significant issues.

• Industry operating experience

• Additional time is needed to bring about improvement.

• Performance indicators Sd.190d37 Slid. 20d 37

I Confirmatory Action Letter 14 1 Engineering Programs 4 Inspection Conclusions

• One action completed as scheduled.

Most improvement plan actions were completed

• Performance Indicators not meeting goals. on schedule.

• Baseline inspections Progress Is being made in each CAL area.

• Additional time is needed to bring about - Additional actions appear to be necessary In improvement. the human performance area.

- More time is necessary to demonstrate improved equipment reliability.

Slid.21 d 37 Soid.22 237 Identification and Resolution of 4 E Identification and Resolution of Problems_nspecton (Cont)

Evaluated Areas Introduction - Anthony Gody 1) Effectiveness of problem Identification

2) Effectiveness of prioritization and evaluation of issues

3) Effectiveness of corrective actions

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

f I

Effectiveness of Problem Effectiveness of Prioritization and

,valuation of Issues - Assessment ii4 Identification -Assessment

• Problems were adequately identified and entered

• Problems with prioritization and evaluation of into the corrective action program -some Issues.

exceptions noted.

- Operator work arounds

• Two -evaluations failed to Identify the apparent

- Aging Agastat relays -Potential Criterion XVI cause of the events.

Violation

- RCR 2003-0979

• Previous inspections also determined problems were adequately Identified. - RCR 2003-0428

• Plant personnel had low thresholds for entering problems into the corrective action program.

SMil.2Sd 37 Slid. 26 d 37 Effectiveness of Prioritization and Effectiveness of Prioritization and Evaluation of Issues - Assessment Evaluation of Issues - Assessment (Cont)

• Two examples of not performing operability

• The quality of root cause determinations were determinations when required - Potential T.S. 5.4.1 good.

Violation

• Significant improvement in the ownership and

• 17 examples of failure to follow preventive knowledge of the condition review group and maintenance procedures - Potential T.S. 5.4.1 the corrective action review board.

Violation Sid. 27 d 37 SMd.M8d 37

Effectiveness of Corrective Effectiveness of Corrective Actions -Assessment w~ctons Asessment_(Cqnt)

• Majority of conditions adverse to quality were effectively resolved. Some exceptions were noted.

• Continued problems with operability determinations - Potential Criterion XVI violation

- 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 .137 Slid. 30 d 37 Safety-Conscious Work Identification and Resolution of I Environment - Assessment Problems Conclusions S1. .- _.

• Employees were willing to identify safety

• All potential violations have either been issues through either the corrective action corrected or placed into the corrective action program or the employee concerns program. 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.31d137 Slid.*32 d 37

Public Power District i0 Other Finding

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

Response

Slid. 33dl 37 Slid.34 d D U.S. Nuclear Regulatory Commission Region IV Coi Com -.me .tns.

Closing Comments Slid. 35d 37

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

ENCLOSURE 3 NPPD PRESENTATION SLIDES

Agenda PI & R / 3rd Quarter TIP Inspection NRC Public Meeting

• Opening Remarks Stu Minahan

• Inspection Results & Stu Minahan Cooper Nuclear Station Overall Performance November 4, 2003

• Human Performance Stu Minahan

• Corrective Action John Christensen Program

• Equipment Reliability & Gary Kline Program Improvements

. Closing Remarks Stu Minahan Inspection Results Inspection Results &

Overall Performance

• CNS generally agrees with the results

• CNS concurs with the potential NCVs Stu Minahan

• CNS recognizes importance of cross-Acting Site Vice President cutting focus areas

• Actions have been taken, or in progress, to address these issues I'I 3

I

Overall Performance Pillar PI Trend

• Plant Performance 70%

- Recent forced outage 60%

- Planned power reductions to correct 50%.- -006 equipment issues CO.g.40..00"

• Working toward changing attitudes concerning plant and personnel 20% . -

performance 0%-

5 ERO Performance i _ C

~

S j000 ~

0 f ~ ~ ~

ff 0 0 00 ,fff0000

.5? .5 2

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 Operator Distractions 1.4 ~ ~ 250 200 1 1.0 A

106 150 I100 0.4 02 00 -.-.

50 04O ow >+s~~//e4 Control Room Deficiencies On-line Maintenance Backlog 300 540 40 [50 .2 c1 25 10 II log 5

so 50 0-1016 i ". ' 5 '

4

Engineering Inventory Human Performance Going Forward 3750 3125 Q1

• Increased focus on management observations and coaching 2500

• Increase in dedicated resources I t87s L

• Implementation of integrated Human 1250 Performance Trainer

- Multi-faceted - Safety, chemistry, radiation 0 - I - - __ -

protection, human performance traps, 11.1 Ile .111.1 1P1 .111.11 "P/ 1.1O11.1 41 .1 .1 11 procedure usage, ..

• Long term evolution of Trainer

• 7 Conclusion

• Will continue to be one of the critical Corrective Action Program management focus areas

• Maturing Human Performance Trainer John Christensen

• Focus on upcoming refuel outage Plant Manager

• Future assessments

__ I

~ "' 1 la~="70 19 5

CAP Open Items CAP Backlog 2800 2600 350 2400- - - -- - - 300- ,

2200

{C 2000 S.50 . /

i1800 ' .200

• 600 -

1 /

1400 ..

1&DO 50 a _ -_ . _ .- . .. _ _ . _ _

• ISA'

.' _'0 '0 0 0 0 ~ '0 0 0 CAP Performance Index Equipment Reliability &

35s Program Improvements 3sA 25 Gary Kline 2D General Manager, 1.5 Engineering 001 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 Building the Foundation ao.,

• Plant Health Committee

'I I - Management Alignment

- Interfacing with System Engineers

- Key Focus Areas 27 7

Building the Foundation Building the Foundation (cont)

• System Engineering Roles and

• Trending / Monitoring Focus Responsibilities - Proactive Engineering

- Realignment of Priorities - Improvements

- INPO Assist Visit 29 30 New SW System Equipment Related CM Orders El 3:

8

- -I-------- I------

Unplanned RB HVAC System LCO's AV1 13 1

Building the Foundation ( .., Successes

• Training

• Overall System Health

- Upgrade to improve Engineering

• Mitigation of Missouri River Level Performance Changes

- Emphasis on Plant reliability

• Scram Solenoid Pilot Valves

• Diesel Generator Connecting Rod 351 9

System Health Successes (cont.)

10

• Mitigation of Missouri River Level Changes

• Scram Solenoid Pilot Valves

• Diesel Generator Connecting Rod S ~m  :" ;~- ;

J7 38 Challenges Program Improvements

• Material Condition Balance of Plant

• Performance Indicator

• Change Management

• EQ Program Closure Assessment

• Workload Management 39 1-10

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