ML20141K731
| ML20141K731 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/19/1997 |
| From: | Lesser M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Kingsley O TENNESSEE VALLEY AUTHORITY |
| References | |
| NUDOCS 9705290351 | |
| Download: ML20141K731 (35) | |
Text
_.__ _
May 19, 1997 Tennessee Valley Authority ATTN: Mr. Oliver D. Kingsley, Jr.
President, TVA Nuclear and Chief Nuclear Officer 6A Lookout Place 1101 Market Street Chattanooga, TN 37402 2801
SUBJECT:
MEETING
SUMMARY
SEQUOYAH NUCLEAR PLANT, DOCKET NOS. 50-327 AND 50 328
Dear Mr. Kingsley:
On May 14, 1997, the NRC staff met at the NRC Region II Office, with Tennessee i
Valley Authority Management. The purpose of this meeting was to discuss the owrational performance of the Sequoyah Units, including performance during t1e Unit 1 Cycle 8 refueling outage. Enclosure 1 is a list of the individuals who attended the meeting, and Enclosure 2 contains a copy of the material supplied by the licensee at the meeting.
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10 Code of Federal Regulations, a coay of this letter and its enclosures will be placed in the NRC Public Document loom.
Should you have any questions concerning this letter, please contact us.
Sincerely, (Original signed by M.
S. Lesser) 1 Mark S. Lesser, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos. 50 327. 50 328 l
Enclosures:
- 1. List of Attendees
- 2. Handout Material cc w/encls:
(See page 2)
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TVA 2
cc w/encls:
Mr. 0. J. Zeringue Mr. J. T. Herron i
l Senior Vice President Plant Manager Nuclear Operations Sequoyah Nuclear Plant i
Tennessee Valley Authority Tennessee Valley Authority 6A Lookout Place P. O. Box 2000 1101 Market Street Soddy Daisy TN 37379 Chattanooga, TN 37402 2801 l
Mr. Michael H. Mobley, Director
(
Mr. J. A. Bailey Division of Radiological Health l
Vice President 3rd Floor, L and C Annex Engineering and Technical Services 401 Church Street 6A Lookout Place Nashville, TN 37243 1532 1101 Market Street i
Chattanooga, TN 37402 2801 County Executive Hamilton County Courthouse Mr. R. J. Adney Chattanooga, TN 37402-2801 Site Vice President Sequoyah Nuclear Plant Distribution w/encls:
(See page 3)
Tennessee Valley Authority P. O. Box 2000 Soddy Daisy TN 37379 General Counsel Tennessee Valley Authority ET 10H 400 West Summit Hill Drive 1
Knoxville TN 37902 Mr. R. R. Baron General Manager Nuclear Assurance & Licensing 1
4J Blue Ridge 1101 Market Street i
Chattanooga, TN 37402 2801 I
Mr. P. Salas, Manager Licensing and Industry Affairs Tennessee Valley Authority 4J Blue Ridge 1101 Market Street Chattanooga, TN 37402 2801 Mr. R. H. Shell, Manager Licensing and Industry Affairs Sequoyah Nuclear Plant Tennessee Valley Authority S$dy-sy N 37379 a
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TVA 3
Distribution w/encls:
J. R. Johnson, RII M. S. Lesser, RII S. E. Sparks, RII F. J. Hebdon, NRR R. W. Hernan. NRR W. C. Bearden RII C. F. Smith, RII D. H. Thompson, RII l
J. H. Moorman, RII E. D. Testa, RII PUBLIC NRC Resident Inspector U. S. Nuclear Regulatory Commission 2600 Igou Ferry Soddy Daisy, TN 37379 NRC Resident Inspector U. S. Nuclear Regulatory Commission 1260 Nuclear Plant Road Spring City. TN 37381 0FFICE 000/011 SIGNATURE NAME 25 park s:vyg l
DATE 05 / h / 97 05 /
/ 97 05 /
/ 97 05 /
/ 97 05 /
/ 97 05 /
/ 97 COPY?
YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL htCURD C0Fr DOCUMtNi NAMt; 6: \\6R6.5QdN0514. bum
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LIST OF ATTENDEES NRC l
L. A. Reyes, Regional Mministrator, Region II (RII)
J. R. Johnson, Dire: tor, Division of Reactor Projects (DRP). RII J. P. Jaudon, Director, Division of Reactor Safety (DRS), RII l
H. O. Christensen, Chief, Engineering Branch, DRS. RII M. S. Lesser, Chief Reactor Projects Branch 6 DRP, RII i
S. E. Sparks, Project Engineer, Reactor Projects Branch 6 DRP, RII l
J. E. Richmond, Project Engineer, Reactor Projects Branch 6, DRP, RII M. C. Shannon, Senior Resident Inspector, DRP, RII D. A. Seymour, Re::ident Inspector, DRP, RII F. J. Hebdon, Director, Project Directorate II 3, Office of Nuclear Reactor Regulation (NRR)
R. W. Hernan, Senior Licensing Project Manager, NRR l
Licensee Attendees:
l
- 0. J. Zeringue, Senior Vice President, Nuclear Operations R. Adney, Site Vice President, Sequoyah Nuclear Plant R. Baron, General Manager Nuclear Assurance & Licensing l
R. Shell, Manager, Licensing and Industry Affairs L
J. Herron, Plant Manager, Sequoyah Nuclear Plant l
H. Fecht, Nuclear Assessment and Licensing Manager T. Flippo, Site Services Manager L. Bryant. Outage Manager K. Whittenburg, Manager, Nuclear Communications l
C. Burton, Sequoyah Nuclear Plant i
i
i Tennessee Valley Authority Sequoyah Nuclear Plant TVA/NRC Meeting May.14,1997 i
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6 Sequoyah Nuclear Plant TVA/NRC Meeting Agenda May 14,1997 I.
Introduction R. J. Adney II.
Unit 1 Cycle 8 Outage L. S. Bryant III.
Material Condition Improvement T. A. Flippo 1
IV.
Plant Performance J. T. Herron V.
Quality Assurance Perspective M. J. Fecht VI.
Summary R. J. Adney m
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Sequoyah Nuclear Plant I
Introduction 1
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Unit 1 Cycle 8 Outage I
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Sequoyah Nuclear Plant
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Unit : Cycle 8 Outage UIC8 Material Condition Improvements Reliability
- Pressurizer safety valve modifications
- Two low-pressure rotor swaps
- No. 2 feedwater heater bypass (sparger only)
- EHC system electronics / diagnostics
- Duplex seal oil filter
- 500-kV yard bus pts
- Main transformer cooling fans /contactors
- Redundant generator backup relay
- Stator cooling water pump isolation valves 3
Sequoyah Nuclear Plant Unit 1 Cycle 8 Outage UIC8 Material Condition Improvements Man-machine Interface
- 46 of 46 control room deficiencies cleared l
- Plant process computer replacement
- Control room work stations 1
- Control room recorder improvements
- No. 7 heater drain tank flow indicator in main control room
- Pressurizer pressure controller upgrade Steam generator feedwat.er nozzles replaced
- 480V motor starters (Arrow Hart) 4
Sequoyah Nuclear Plant Unit 1 Cycle 8 Outage UIC8 Material Condition Improvements Equipment Performance
- Five new containment electrical penetrations
- Vital inverter / power board maintenance
- Steam dump drain system improvements
- Main condenser replacement Amertap system upgrades New debris filter
- Ice condenser floor modification (3 of 24 bays)
- 6.9kV breaker refurbishments (23 total)
- Rod control system diagnostics
- Temporary leak repairs cleared (31 of 31)
- Erosion / corrosion inspections / repairs '
5
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i Sequoyah Nuclear Plant i
Material Condition Improvement t
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Sequoyah Nuclear Plant Material Condition Improvement UICS Eight Red / Yellow Systems Will Go White Based On Outage Results
- Reactor Protection - Processor board replacement
- TSC Computer-ICS replaced P-250 computer
- Main Steam - Steam dump drain system improvements
- Condenser Cire Water - Condenser retube project
- Generator Cooling - Replacement of CUNO filter and addition of stator cooling water discharge isolation valve
- Main Bank Transformers and Switchyard - Switchyard modifications I
- Electrical Penetrations - Replacement of five penetrations
- CO Storage / Purging - Computer room CO damper modification 2
2 L
7
e Sequoyah Nuclear Plant Material Condition Improvement Nonoutage Focus Take Six Red / Yellow Systems to White During 1997
- Control Air (compressor replacement)
- High-Pressure Fire Protection
- Heat Tracing Sampling
- Waste Disposal (Radwaste)
- Auxiliary Boiler and Associated Fuel Oil Short-term
- Nonoutage corrective maintenance WOs greater than 1 year l
- AUO concerns i
- Control room disabled alarm indications and controls not requiring outage to repair
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- Temporary alterations l
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s Sequoyah Nuclear Plant Material Condition Improvement U2C8 Five Yellow Systems Will Go To White Based On Outage Results
- Reactor Protection - Replacement of processor boards
- Main Steam - Steam dump drain system improvements
- Heater Drains and Vents - No. 2 feedwater bypass to main condenser
- Diesel Generator - 2B-B governor actuator replacement j
- Reactor Coolant System - Replacement of flow meters for seal leakoff i
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Plant Performance 1
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Sequoyah Nuclear P. ant P ant Performance Efforts Taken to Evaluate Previous Corrective Action Effectiveness
- Previously reported to you on our effort to review closed documents
- Additional effort being taken to specifically look at corrective actions taken for significant events 4
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B Sequoyah Nuclear Plant Plant Performance Personnel Performance Continues to be a Priority
- Department manager / supervisor assessments (Man-Model)
- Department performance self assessments
- Personnel accountability is being enforced
- Selected personnel attended SRO certification training
- Rotational assignments being used to broaden knowledge and increase plant talent
- New experienced management recruits are being added
- Communication of expectations Performance appraisals Evaluation of site personnel 12
f Sequoyah Nuclear Plant Plant Performance SQN Key Processes / Additional Emphasis
- Status control
- PMT process
- Surveillance program
- Sensitive activities
- Procedural adherence Experienced Manager Owners Self-assessment Plans Formalized t
13
- m
b Sequoyah Nuclear Plant Plant Perfonnance 1
Status Control t
Owner - Bill Lagergren (Operations Manager)
Status Control Errors Have Been Cut in Half for Second Quarter FY '97
- Posted performance
- Briefings of status control errors within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of t
occurrence l
- Required use of PEER checks i
Additional Effort to Ensure Component Alignment Returning from UIC8 Refueling Outage SRO teams assembled to verify configuration control 14
Sequoyah Nuclear Plant Plant Perfonnance PMT Process 5
Owner - Joe Valente (Engineering and Materials Manager)
Results of Assessment of the PMT Process Revise procedures to recognize maintenance testing and return to L
operability
- Enhance PMT matrix Establish Operations position for return to operability PMT planning Revise applicable procedures to ensure Operations review if scope /PMT changes are made O
15
Sequoyah Nuclear Plant Plant Performance Surveillance Program Owner - Jeff Summy (Assistant Plant Manager)
Surveillance Instruction (SI) Improvements Evaluate the adequacy of the SI process for controlling SI performance t
Revise administrative process
- To ensure work performed does not invalidate previous work
- To require evaluation ofsurveillance requirements when deferring an outage activity to online
- Adequacy of SI/ procedure content GL 96-01 review completed Ten complex evolutions reviewed
- Industry generic SI content is being evaluated Increased Emphasis on Surveillance Deficiencies Through Senior Management Visibility
Sequoyah Nuclear Plant Plant Performance Sensitive Activities Owner - Walt Hunt (Operations Training Manager)
Assign Managers to Perform Interactive Roles in Prejob Briefs Additional Specialized Training Given to Assigned Managers Sensitive Activities and Special Evolutions Identified Including Selected Routine Activities t
Assignments Reviewed Daily in POD
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Sequoyah Nuclear Plant Plant Perfonnance Procedural Adherence Owner - Charles Kent (Chemistry and RadCon Manager)
Identified by Trending i
Site Wide Emphasis on Procedure Adherence Follow the procedure /stop and fix Site standdown Covered during POD Meet with Plant Manager to explain failure to follow procedure Line management and QA oversight in the field Posted performance Procedural Quality
'8 Department Managers to Provide Assessment Every Six Months
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INPO INDEX SEQUOYAII UNIT 1 min max weight
' value index Product criteria Unit Capability Fa wr 40 90 0.16 78.55 77.100 12.3 78.550 Unplanned Capability loss Factor 15 0
0.12 6.56 56.267 6.8 6.560 Unplanned Automatic Scrams 5
1 0.08 1.447 88.815 7.1 1.447 High Pressure injection 0.03 0.01 0.1 0.005s 100.000 10.0 0.010 Auxiliary Feedwater 0.04 0.01 0.1 0.008 100.000 10.0 0.010 Emergency AC System Availability 0.05 0.01 0.1 0.012 95.000 9.5 0.012 Hermal Performance 98 100 0.06 99.821 91.038 5.5 99.821 Fuel Reliability 0.01 0.0005 0.08 0.000 100.000 8.0 0.001 Chemistry Index 2.00 1.10 0.07 1.112 98.687 6.9 1.112 Collective Radianon Exposure 400 100 0.08 217.329 60.891 4.9 217.329 Industrial Safety Accident Rate 2
0.3 0.05
~ 0.167 100.000 5.0 0.300 Weighted Index APRIL 1997 =
85.9 SEQUOYAll UNIT 2 min max weight value index Product criteria Unit Cdpability Factor 40 90 0.16 87.34 94.680 15.1 87.340 Unplanned Capability loss Factor 15 0
0.12 5.42 63.867 7.7 5.420
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Unplanned Automatic Scrams 5
1 0.08 0.892 100.000 8.0 1.000 liigh Pressure injection 0.03 0.01 0.1 0.007 100.000 10.0 0.010 Auxiliary Feedwater 0.04 0.01 0.1 0.028 39.667 4.0 0.028 Emergency AC System Availability 0.05 0.01 0.1 0.012 95.000 9.5 0.012 Thermal Performance 98 100 0.06 99.617 80.864 4.9 99.617 Fuel Reliability 0.01 0.0005 0.08
~ 0.000 100.000 8.0 0.001 Chemistry Index 2.00 1.10 0.07 1.133 96.367 6.7 1.133 Collective Radiation Exposure 400 100 0.08 217.329 60.891 4.9 217.329 Industrial Safety Accident Rate 2
0.3 0.05 0.167-100.000 5.0 0.300 Weighted Index APRIL 1997 =
83.7 6
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Sequoyah Nuclear Plant QA Perspective Unit 1 Cycle 8 Outage Oversight Plan
- Focused assessments Dedicated activity owners (assessors)
Key projects, critical evolutions, backshift activities
- Defined methodologies
- Separate outage report 20
Sequoyaa Nuclear Plant QA Perspective Unit 1 Cycle 8 Outage Oversight
- Broad range of oversight for each functional area
- Assessment / observation findings Impact reviews PER initiation Independent verification Event critiques Out-of-specification readings FSAR revisions Foreign material exclusion Fire watch duties Personnel safety / security /RadCon practices Abnonnal/ unanticipated responses 21
Sequoyah Nuclear Plant QA Perspective Unit 1 Cycle 8 Outage Oversight (cont.)
- Oversight Conclusions 1
Positive management improvement initiatives are being implemented which we see improving site performance
- Control room / full scope observations 1
- Complex and infrequently performed tests
- Plan of the Day
- Engineering support
- Management observations I
22 i
Sequoyah Nuc. ear Plant QA Perspective Unit 1 Cycle S Outage Oversight (cont.)
- Oversight Conclusions (cont.)
Differing work standards for nonsensitive work activities and human performance deficiencies sometimes compromise these initiatives
- Human performance deficiencies Procedure adherence Supervisors monitoring / enforcing / correcting Sensitivity to routine evolutions 23
Sequoyah Nuclear Plant QA Perspective QA Oversight i
- NA&L Manager Evaluation Corrective Action Program Audit /100% review M&TE Program Equipment failure trending assessment Maintenance Rule implementation assessment and audit Degraded condition assessment
- Operator workarounds assessment 7
Status control Procedure compliance adverse trend / personnel performance (trend program)
Freeze protection assessment t
Selfassessment I
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9 Sequoyah Nuclear Plant QA Perspective QA Oversight (cont.)
- Conclusion QA is intrusive in identifying issues Line management is listening to QA-identified issues and taking corrective action QA is monitoring the line's corrective actions QA escalation Improvement has been noted in line performance
- Sustained performance is required t
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Sequoyah Xuclear Plant QA Perspective QA Top Five Issues
- Human performance
- Self assessment
- Corrective action
- Trending
- Plant material condition t
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