ML20126H922
| ML20126H922 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/30/1992 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9301050357 | |
| Download: ML20126H922 (40) | |
Text
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Decembec 30, 1992-Docket No. 50-346 i
' LICENSEE: TOLED0 EDIS0N COMPANY FACILITY: DAVIS-BESSE NUCLEAR POWER STATION, UNIT I
SUBJECT:
SUMMARY
OF MEETING HELD ON DECEMBER 2, 1992 TO DISCUSS UPCOMING REFUELING OUTAGE PLANS AND-RECENT PLANT PERFORMANCE On December 2, 1992, NRC staff members met at Rockville, Maryland, with employees of Toledo Edison Company-(TE) to discuss the upcoming refueling outage plans and recent plant performance for the Davis-Besse Nuclear Power Station, Ur.it I. A list of attendees is included as enclosure I. The handout used at the meeting is included as enclosure 2.
As shown in enclosure 2, Davis-Besse items discussed at the meeting were organizational changes, cycle 8 performance, major 1992 activities, the upcoming eighth refueling outage, and long term issues. During the discussion, TE commented that the motor-operated valve test program was beginning to impact the outage path. At the conclusion of the meeting, there-were no outstanding questions from either TE or the NRC staff.
ORIGINAL SIGNED BY Jon B. Hopkins, Sr. Project Manager Project. Directorate III-3 Division of-Reactor Projects III/IV/V Office of Nuclear Reactor Regulation DISTRIBUTION
Enclosures:
? Docket File- OGC A stated NRC & Local PDRs EJordan PD3-3 Reading SStasek cc w/ enclosure: TMurley/FMiraglia RLanksbury
'See next page JPartlow. ACRS(10)
._JRoe GGrant, ED0 IKing Region III, DRP JHannon PKreutzer JHopkins
-0FFICE PDIII-3:LA:DRPW PDIII-3:PM:DRPW PDIII-3:PD:DRPW NAME- PKreutzer D JBHopkins/jbh/baj ~JHannon T r-
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DATE /k /3D /92 lh /3D/92 0FFICIAL RECORD DOCUMENT NAME: g:\davisbes\ dbl 202.mts- _.
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.') Davis-Besse Nuclear Power Station Toledo Edison Company Unit No. I cc:
Mary E. O'Reilly Centerior Energy Corporation Radiological Health Program 300 Madison Avenue Ohio Department of Health Toledo, Ohio 43652 Post Office Box 118 Columbus, Ohio 43266-0149 Mr. Robert W. Schrauder Attorney General Manager, Nuclear Licensing Department of Attorney Toledo Edison Company General 300 Madison Avenue 30 East Broad Street Toledo, Ohio 43652 Columbus, Ohio 43215 Mr. James W. Harris, Director Gerald Charnoff, Esq. Division of Power Generation Shaw, Pittman, Potts Ohio Department of Industrial Regulations and Trowbridge P. O. Box 825 2300 N Street, N.W. Columbus, Ohio 43216 Washington, D.C. 20037 Regional Administrator, Region Ill Ohio Environmental Protection Agency U.S. Nuclear Regulatory Commission DERR--Compliance Unit 799 Roosevelt Road ATTN: Zack A. Clayton Glen Ellyn, Illinois 60137 P. O. Box 1049 Columbus, Ohio 43266-0149 Mr. Robert B. Borsum Babcock & Wilcox President, Board of Ottawa Nuclear Power Generation Division County Commissioners 1700 Rockville Pike, Suite 525 Port Clinton, Ohio 43452 Rockville, MD 20852 Resident inspector State of Ohio U. S. Nuclear Regulatory Commission Public Utilities Commission 5503 N. State Route 2 180 East Broad Street Oak Harbor, Ohio 43449 Columbus, Ohio 43266-0573 Mr. Murray R. Edelman Mr. James R. Williams Executive Vice President - State Liaison to the NRC Power Generation Adjutant General's Department Centerior Service Company Office of Emergency Management Agency 6200 Oak Tree Boulevard 2825 West Granville Road Independence, Ohio 44101 Columbus, Ohio 43235-2712 Mr. Donald C. Shelton, Vice President Nuclear - Davis-Besse Centerior Service Company c/o Toledo Edison Company 300 Madison Avenue Toledo, Ohio 43652 l
ATTENDEES December 2, 1992 tiEL ORGANIZAT10))
J. Roe NRC T. King NRC S. Stasek NRC J. Hopkins NRC R. Lanksbury NRC J. Hannon NRC -
D. Shelton TE (Centerior)
L. Storz TE S. Jain TE R. Schrauder TE J. Rogers TE N. Bonner TE T. Chambers TE M. Leisure 1E
TOLEDO EDISOX/XRC SENIOR MAXAGEMENT MEETING Nuclear Regulatory Commission Headquarters Rockville, Maryland
'T December 2,1992 i
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- e J AGENDA TOLEDO EDISON /NRC SENIOR MANAGEMENT MEETING NRC Headquarters Rockville, MD
- Organizational Changes
- Cy'le 8 Performance
- Major 1992 Activities Motor Operated Valve Programs Plant Modification Backlog Reduction Water Chemistry Containment Neutron Surveys Casualty Control Drill Continuous Improvement Initiatives
- Eighth Refueling Outage Oven'iew Outage Goals Shutdown Risk Management -
RCS Leakage
-- Steam Generator Activities
- Commitment Status NRC Actions
- Long Term Issues Spent Fuel Storage New Standard Technical Specifications Generic License Renewal Application
-- Individual Plant Examination l
7 , .
~
sammer ummannsos==orm je V. P. NUCLEAR Don Shelton M
3 DIRECTOR- DIRIX.* TOR - DIRECTOR- DIRECTOR-PLANTMANAGER D-B ENGINEERING TEGINICAL PIANNING &
QUAIITY SUPPORT ASSURANCE SERVICES
~
Lou Storz Greg Gibbs SushilJain Ted Myers EricSalowitz MANAGER-ISE
- Nudrar Ucendng
- Maheenance11anedng
- Plant Operations
- QuaRty Verificason
- Nudeur L-@-.L g andOuenge Managenent
- L.me.,y Pnpere&se , Vince Sodd
- Plant Maintenance
- Qualty Contrtd
- Systems C@_ .Lg ,
- Design L r,LaLg
- Environsnental
- Radiation Protrdien
- Macedab Managernent Canpliance
- Security
- Performance Engineering
- Nudrar Safety and
- P!antServlas
- Lgh.Lg Assurane Hygiene and Servkrs
- NudrerTrakung l
l l
I
____m.
I cawrsg I -
Organizational Changes
- Promotions
- Superintendent -I&C Maintenance to Manager - DB Maintenance
- Rotational Development Program
- Manager -Independent Safety Engineering to SRO Class
- Superintendent - Maintenance Services to Manager -
Independent Safety Engineering
- Manager - Maintenance Planning and Outage Management to Superintendent - Maintenance Services
- SRO Candidate (previous Superintendent - Electrical Maintenance) to Manager- Maintenance Planning and Outage Managanent
- Superintendent-ElectricalMaintenance to Superintendent -I&C Maintenance 2
. CE Organizational Changes
- Rotational Development Program (cont.) !
- Superintendent - Shift Operations to Superintendent - >
Electrical Maintenance
- SRO Class Graduate (previous Facility Modifications Section Manager) to Superintendent - Shift Operations
- Supervisor-Independent Safety to New Standard Technical Specifications Program Manager
- SRO Class Graduate (previous Supervisor - Mechanical Design) to Windows Program Manager
- General Supervisor - Radiological Support to SRO Class
- Manager-Materials Management to Manager-Integrated Planning
- Manager - Quality Systems to Manager - Materials Management 3
DAVIS-BESSE NUCLEAR POWER STATION .
1992 MAJOR ACTIVITIES d ANS Names D-B Most l Improved Plant for 1992 g Blackout IInitial RO & SRO Diesel 1 Operator Exams - Generator Year-to-Date 1992 Available For Use CAP. Factor 99.2% d NRC EDSFI InTection Predictive AVAIL. Factor 99.4% - Maintenance Prograns Award NRC Audit of DBNPS .
c as Chrrent Licensing Basis _
hRCinp9 Emergency Preparedness Exercise { Utility Only) NRC Operator l
/NRC Inspection . TE/ Region III
- Meeting to Discuss - Requal:Tication Engineering Issues Examinations NRC/TE Meeting to Discuss FP Issues e-FEB' MAR APR MAY JUN JUL AUG SEP OCT NOV DEC JAN Reactor Trip ha etion - NRC Inspection TE/NRC MOV Program
~~
Casualf Contro Senior a Ra ation -
Protection Drill Q"g- 8 TE/NRC
- Presentation on IPE NRC/ Licensee Counterpart Meeting N t
- Sc7ior sident NRC Inspector -
Desig_n Stan Stasek and MOD TE/ Region III Inspection l , Meeting to T: County Industry i
Award Announced PUCO A ves Rate Stain ation NRC Training
- Prograrn
_ & Simulator Site Visit
~
^ ^
-DAVIS-BESSE NUCLEAR POWER STATION 1993 MAJOR. ACTIVITIES Re los III .
- rability -
rkshop M M-SALP 10 Annual INPO
- Plant Evaluation
' Implement Initial RO A SRO NRC Operator.
New Part 20 - -
Licensing - - Requal:Tecation Requirements . Examinations Examinations iiiiihii:i:ii :;nunnn:
ii!:.iiiiiiiii::
- idd6i
- )l) Mili3lidi 4
1 i 1%11 Scale Check Valve ""
., RisAy Exercise and IST - W laspection 4.
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Cycle 8 Performance 6
a l ! DAVIS-BESSE NUCLEAR POWER STATION l Cyc e Availability and Caaacity Factors l ! OCAPACITY E AVAILABILITY i 100 e
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! CYCLE *Through 11/30/92-2 i
- 1. 4 ~s sk Ca g
( ). MAJOR 1992 ACTIVITIES 8
Q,& ' c a . Motor Operated Valve Program Industry Activities
- EPRI Stem Lubricant Testing Program
- MOV User's Group
- Liberty Valve Operator Test Evaluation System (VOTES)-
User's Group
- Region III Manager's Forum on MOVs
- B&W Valve Working Group
- NUMARC Technical Exchange 9
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Motor Operated Valve Program Generic Letter 89-10
- NRC Inspection July,1992
- No Violations One Deviation
- Meeting with Region III Staff August,1992
- Results of Testing to Date Six Tests Completed Met Previous Acceptance Criteria Identified Deficiencies Related to Revised Acceptance Criteria No Safety Significant Concerns Voluntary Report 10
c , Plant Modification Backlog Reduction
- Reduce Backlog of Plant Changes in Various Stages of Implementation
- Process Partially implemented Changes
- Void Unwanted Changes I
Closcout Changes which are Field Complete
- Projectis 87% Complete Target Completion Date is April,1993
- All Backlog Plant Changes Reviewed No Changes Found Which May Adversely Impact Safe Operation of Plant or Personnel Safety 11
. F 3 MfffWg
- c ,
Water Chemistry All Volatile Treatment
- Startup to May,1989 -- Ammonia /Hydrazine
- May,1989 to Present -- Morpholine /Hydrazine
- Iron Transport Reduced One Third to One Half
- Erosion Rates Reduced by Factor of Four 12 i
j
w , - Water Chemistry Alternate Amines
- Pilot Program with EPRI
- Maintain / Extend Useful Life of Steam Generators Reduce Iron Transport to Steam Generators Delay Chemical Cleaning the Steam Generators Decrease Erosion / Corrosion in Low Pressure Piping Reduce Cation Conductivity in Feedwater e Baseline StudyInitiated August,1992
- Three Amines to be Tested-
- Ethanolamine (ETA)(testing complete) 2-Amino-2-Methylpropanol (AMP) (testing in progress) 3-Methoxypropylamine (MPA) (testing to be conducted later in cycle if time permits) 4 13 G'
G NTE c , Containment Neutron Surveys
- Containment Entries More Frequent
- Neutron Dose Presently Overestimated by 2 to 5 Times
- Neutron Energy Spectrum Survey Conducted at 100% Power e Results used for
- More Accurate Future Neutron Dose Assignments and Estimates Reassessment of 1992 Data 3
- Results Expected by End of Year 1992 14
& .- l L J Casualty Control Drill
- Conducted October 7,1992
- Der anstrate Plant Emergency Repair Activities, Minimizing Simulation
- Dispatch Operations Support CenterTeams Assemble Personnelin Protected Area
- Utilize Offsite Firefighting Assistance .
- Evaluated with Assistance of Eight INPO Observers
- All Objectives Satisfactorily Met ;
15
E Continuous Improvement Initiatives Self Assessment Activities
- Industry Event Reviews
- Transient Assessment Team
- Windows Program
- 7RFO Outage Critique
- Maintenance Self-Assessment
- Training Self-Assessment
- Industrial Safety Self-Assessment
- Security Involvement in Investigating Plant Events
- Safety System Functional Review (Once Through Steam Generators)-
-
- Contaminated Leakage Pathway Control Review
- CNRB Review of Reliability and Trip Vulnerability
- Team 91 Focus Teams 16 l
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kam l Continuous Improvement l Initiatives ! Industry Group Involvement ,
- Midwest Nuclear Engineering Manager's Forum
- NRC/ Licensee Counterparts Meeting (Region III)
- Nuclear Emergency Plan Advisory Council (with Beaver Valley, Perry, State, and County) *
- Region III Industrial Safety Organization I
- Region III Working Group on 10CFR20 Implementation ;
- Midwest NuclearTraining Association
- Midwest Nuclear Plant Manager's Association .
- Great Lakes QA Manager's Association -
Region III 17
t J Continuous Improvement Initiatives Peer Review Activities
- INPO Technical Exchange Visit (Outage Experience / Safety Practices)- Doel (Belgium)
- Joint Utility Management Audit
- INPO Plant Peer Evaluations Kewaunce - Palisades Three Mile Island -
Salem Turkey Point - St. Lucie Crystal River
- Emergency Planning Peer Evaluations Ft. Calhoun Casualty Control Drill
- Perry Dry Run and Exercise
- Licensing Peer Evaluations Palisades Big Rock
- Training Accreditation Team Peer Evaluations Cooper Seabrook
- Procurement Peer Review - Region III Plants
- Joint Utility Technical Specialist Exchange for Auditors 18
[
'Q ..
c , Eighth Refueling Outage (8 RFO? l t 19-h s'M i 'us'it
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L J Eighth Refueling Outage Overview
- Start 3/1/93
- Full Core Offload
- 62 Day Planned Duration
- Work Scope 30 Modifications
- 610 Preventive MWOs 447 Corrective MWOs 165 MOV Activities
- Cost (Millions)
$21.51ncremental O&M
$13.8 Modifications
- Resource Sharing Program
- Integrated Outage Contract - Babcock and Wilcox 20
EIGHTH REFUELING OUTAGE MANAGEMENT TEAD OUTAGE DIRECTOR Rogers Wood Bonner
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SAFETY l ENVIRONMENTA1. SHUTDOWN RISK og Aoygson Aovison
. ADVISOR Moyers Delman stephenson DonneRon Isley Blay Beier McC M ey sodd S
OUTAGE OUTAGE OUTAGE MAINTENANCE OUTAGE OPERATIONS ENGINEERING SUPERINTENDENT MANAGEW SUPERINTENDENT MANAGER Crouch Haberland Bezilla Timms Dilich Evnng Roci Caba Byme - Michaelis Hawley Holden 1 if B&W-TASK B&W OUTAGE l -- COORDINATOR - --- MANAGER scribner stannes wason Janis , Geisen
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- 1 ,
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khc.mm[ c , Eighth Refueling Outage Outage Coals
- 1. LostTime Accidents $1
- 2. OSHA Recordables < 13
- 3. Loss of Core Cooling Events 0
- 4. ESF Actuations 0
- 5. Outage Duration s 62 days
- 6. Scheduled MWOs Completed 2 95'7e
- 7. Scheduled MODS Completed 100 %
- 8. Emergent Work Man hour increase < 20%
- 9. Rework Items <2%
- 10. Cumulative Dose <
- person rem
- 11. Solid Radwaste Generation <
- cuble feet
- 12. Personnel Contaminations <'
- 13. Increase in Total Area Contaminated 0
- 14. One liour Reportable Security Violations s2
- 15. Incremental O&M Budget s $21.5 million
- 16. Consecutive Days On Line Without Trip Caused by inaccurate Execution or Deferred Outage Work 2 90 days
- Actual numbers will be supplied when detailed job planning has been finallred and reviewed 22 4
&. l c ,
i Eighth Refueling Outage Shutdown Risk Management
- Nuclear Group Procedure -- Outage Nuclear Safety Control
- Establishes Specific Requirements for Shutdown Nuclear Safety Relating to the Scheduling of Outage Activities and the Availability of Plant Systems, Stmetures, and Components Necessary to Ensure:
- Electrical Power
- Decay Heat Removal
- ReactorCoolantInventory
- Reactivity
- Integrity of Fission Product Containment Barriers
- Developed Using NUM ARC,INPO, EPRI, and NUREG Guidance I
23
k-L% c , Eighth Refueling Outage Shutdown Risk Management (cont.)
- Outage Schedule Provides Defense in Depth and Implements Requirements for Key Safety Function Availability
- Outage Safety Review Conducted by Multi Disciplined Group
- Outage Activities Controlled and Implemented According to Approved Schedule
- Schedule Changes Subject to Same Philosophy and Basis as Initial Schedule ISE Overview
- Heightened Plant Status Visibility Plan of Day Meetings
- Plant Status Boards Shift Turnover Briefings
- Post-Outage Critique to be Conducted 24
r 3 - c , Eighth Refueling Outage RCS Leakage j u 1
- Unidentified RCS Leakage 0.35 to 0.45 gpm
- Tech Spec Limit 1 gpm 1
- Fonnal RCS Leakage Plan Implemented
- Containment Walkdowns During Cycle to Locate Source of Leakage and Plan Corrective Action
- SeveralInspections Outside D-Ring
- March 1992 Inspection Inside D-Ring After Power Reduction to 6%
- Suspected Prime Contributors
- Flange Leakage From OTSG Manways and Handholes
- Casket Leakage From Eight RCS Hot / Cold leg Temperature instrument Penetrations Leakage from CRDM Flanges
- Comprehensive Inspection of RCS Planned For-8RFO 25
'Qg..[
c , Eighth Refueling Outage Steam Generator Activities
- Current Status of Steam Generators SC 1-1 Loop 1 (B) 20 of 15457 tubes plugged SG 12 Loop 2 (A) 54 of 15457 tubes plugged
- Integrated Steam Generator Plan Eddy Current Testing (Each Outage,100% for 8RPO)
Preventive Sleeving (420 sleeves planned for 8RTO) Main Feedwater Nozzle Spray Plates (8RFO) Water Slap (future outages,1f needed)
- Chemical Cleaning (future outages,if needed)
,% =""u n Eighth Refueling Outage Commitment Summary
- 44 Conunitments to be Completed
- 1 Commitment Redefined
- Feed and Bleed Upgrades e 4 Commitments Reassessed as Unwarranted
- SPIP (2) ,
- HED
- Hose Station Upgrade 27
'Q.-l .
c , Eighth Refueling Outage Safety Performance Improvement Program
- Program Complete After 8RFO
- Recommendation Summary
- Total Recommendations 222 ,
- TotalImplemented to Date 176
- To Be Implemented in 8RFO 2
- Not Applicable to D-B 38
- Rejected 6 28
% ..,,, [
Eighth Refueling Outage Detailed Control Room Design Review 1
- HED Disposition Complete
- Summary
- Total HEDs Identified 378
- Safety Significant* 29
- Closed as of 7RFO 377
- Closed During Cycle 8 ' 1
- All Safety Significant HEDs Completed as ofend of 6RFO 29
i
, 1 r%="" tan L J j 1
i Eighth Refueling Outage i NRC Actions
- Technical Specification Changes Revise Fuel Assembly Description (Submitted October 29,1992)
Allow Operation With Inoperable Relative Position Indication (submitted April 30,1992) Allow Dilution of RCS High Boron Concentration During Refueling (Submitted May 1,1992) Eliminate Requirement for Safety Features Actuation System During Refueling (Submitted July 28,1992) Increase Allowable Maximum Steam Generator Water Level (Submitted September 3,1992)
- Other Approvals
- B&W Topical Report (BAW-10180) for NEMO Core Design Computer Code (NRC Appravalisimminent)
B&W Topical Report (BAW 2149) on Licensing Improvements for Fuel
.. Reconstitution (NRC Approval Expected 1st Quarter,1993)
T 30' i l
,% =~tn Long Term Issues 31
c > I Spent Fuel Storage e Original Design of Davis-Besse (1969)
- Ship Fuel Offsite for Reprocessing
- Spent Fuel Pool Re-Racked in 1978
- Capacity Increased to 735 Fuel Assemblies
- Complete Core Offload Capability Until 10RFO
- Decision Made to Proceed with Certified Dry Cask Storage System o Initial Use of Casks mid-1995, Prior to 10RFO 32
, - . - .~ . - . - . . -,--.
c , New Standard Technical Specifications
- PHASE 1 Validation / License Amendment Request Preparation
- Plant Specific Review of NUREG 1430.
Identification of Affected Plant Procedures
- PHASE 2 License Amendment Request Review and Submittal Submittal to NRC August,1994 NRC Approval August,1995
- PHASE 3 Procedure Modification
- PHASE 4 Training Program Revision and Personnel Training
- PHASE 5 Station Implementation (April,1996) 33
- r
. c ,
Generic License : Renewal Application
- B&W Owners Group (BWOG) '1 aking Proactive Role BWOG Executive Committee Cave One Year Approval EPRI and DOE Approached to Provide Funding BWOG Project Team in Place Detailed Project Plan Under Preparation NRC Management Briefings Completed
- NRC Staff Briefings Started Technical Work Proceeding
- Davis-Besse Providing Full-Time Project Coordinator in Lynchburg 4
l l~ $4 ^ Tf + - * - - w T+ - --#* p-3-- Nw-'- r8----- -- -- *
'Q c , .
1 Individual Plant Exarnination (IPE) !
- Quantification Essentially Completc
- Preliminary Evaluation Shows No Significant Vulnerabilities Identified
- Duke EngineeringIndependent Audit Completed
- High Marks Received
- Report Being Finalized
- Initial Submittal Scheduled February,1993 35
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