ML18038B446
| ML18038B446 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/28/1995 |
| From: | Lesser M NRC Office of Inspection & Enforcement (IE Region II) |
| To: | Kingsley O Tennessee Valley Authority |
| References | |
| NUDOCS 9510100238 | |
| Download: ML18038B446 (88) | |
Text
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'ROWNS FERRY UNIT 3 MANAGEMENT MEETING
SUMMARY
Dear Hr. Kingsley:
On September 21, 1995, the NRC staff met at the Browns Ferry Nuclear Plant with representatives of the Tennessee Valley Authority (TVA) management staff to discuss the status and schedule for Unit 3 restart activities.
Enclosure 1 is a list. of the individuals who attended the meeting and Enclosure 2 is the handout material supplied by TVA.
In accordance with Section 2.790 of the NRC's "Rules of Practice,"
Part 2, Title 10 Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room.
Should you have any questions concerning this letter, please contact us.
Sincerely, (Original signed by H. Lesser)
Docket No. 50-296 License No.
Enclosures:
- 1. List of Attendees
,2. Presentation Notes cc w/encls:
(See page 2)
Hark S.
- Lesser, Acting Chief Reactor Project Branch 4
Division of Reactor.Projects
+5<><<>>gg q50928 pgp ADQCK 0 P
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TVA cc w/encls:
Hr. 0. J. Zeringue, Senior Vice Pres.
Nuclear Operations Tennessee Valley Authority 3B Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Dr. Mark O. Hedford, Vice Pres.
Engineering 8 Technical Services Tennessee Valley Authority 3B Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. D.
E.
Nunn, Vice Pres.
New Plant Completion Tennessee Valley Authority 3B Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Hr.
R.
D. Hachon, Site Vice Pres.
Browns Ferry Nuclear Plant Tennessee Valley Authori,ty P. 0.
Box 2000
- Decatur, AL 35602
.General Counsel Tennessee Valley Authority ET llH 400 West Summit Hill Drive Knoxville, TN 37902 Hr.
P.
P. Carier, Manager Corporate Licensing 4G Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Hr. T.
D. Shriver, Manager Nuclear Assurance L Licensing Browns Ferry Nuclear Plant Tennessee Valley Authority P. 0.
Box 2000
- Decatur, AL 35602 Hr. Pedro Salas Site Licensing Manager Browns Ferry Nuclear'lant Tennessee Valley Authority P. 0.
Box 2000
- Decatur, AL 35602 TVA Representative Tennessee Valley Authority 11921 Rockville Pike Suite 402 Rockvi.lie, MD 20852 Chairman Limestone County Commission 301 West Washington Street
- Athens, AL 35611'tate Health Officer Alabama Dept., of Public Health 434 Monroe Street Montgomery, AL 36130-1701 Distribution w/encls:
(See page 3)
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TVA Distribution w encls:
E.
W. Herschoff, RII J.
R. Johnson, RII C. A. Casto, RII H.. S. Lesser, RII F,. J.
- Hebdon, NRR J.
F. Williams, NRR S.
H. Shaeffer, RII K. P. Barr, RII Document Control Desk NRC Senior Resident Inspector U.S. Nuclear Regulatory Commission 10833 Shaw Road
- Athens, AL 35611 9
OPU I
CUM T ROO OFFICE
.'DRP 11 SIGNATURE NAM SSha errvyQ DATE'9 /21/ 95 09 /
/95 09 /
/95 09 /
/95 09 /
/95 09 /
/95 E@
NO YES NO YES NO YES NO COPY?
)
OFF!CIAL CORD COPY DOCUMENT NAME:
GriSEC4AiBF30921.SUM YES NO'ES NO
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LIST OF ATTENDEES NRC J.
R. Johnson, Deputy Director, Division of Reactor Projects (DRP),
Region II (RII)
H. S. Lesser, Acting Chief, Branch 4A, DRP, RII L.
DE Wert, Senior Resident Inspector, Branch 4A, DRP, RII T.
R. Decker, Section Chief, Division of Radiation Safety and Safeguards, RII H.
B. Shymlock, Section Chief, Di,vision of Reactor Safety, RII F. J.
Hebdon, Director, Project Directorate II-3, Office of Nuclear Reactor Regulation (NRR)
P.
P. Narbut, Operations Inspector, Division, of Inspection and Support
- Programs, NRR G.
H. Tracy; Region II Coordinator, Office of Executive Director for Operations R. A. Husser, Resident Inspector, Branch 4A DRP, RII TVA
- 0. Kingsley, President, TVA Nuc'lear and Chief Nuclear Officer R. Hachon, Vice President, Browns Ferry G. Preston, Plant Hanager C. Crane,,Assistant Plant Hanager T. Shriver, Nuclear Assurance and Licensing Hanager R.'Greenman, Browns Ferry Unit 3 Readiness Hanager P. Salas, Licensing Hanager W. Peabody, TVA Consultant T. HcGrath,
- Chairman, Nuclear Safety Review Board Enclosure I
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~ aao mC Browns Ferry Nuclear Plant Unit 3 estart ctivities l
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STANDING AGENDA 1.0 Introductions and Old Business R. Machon 2.0 Schedules 2.1 Integrated Restart Schedule 2.2 Recovery Schedule 2.2.1
.Commodities 2.2.2 Milestones 2.3 Licensing Schedule 2.4 Power Ascension Test Schedule R. Machon C. Crane P. Salas C. Crane 3.0 Organization 3.1 Recovery 3.2 Multiple Operating Unit Site Organization R. Machon R. Machon 4.0 Unit 3 Operational Readiness Reviews 4.1 Self Assessments 4.1.1 Operational Readiness 4.1.2 System Windows 4.1.3 Test Deficiency Resolution 4.2 Independent Assessments 4.2.1 Corporate Audits 4.2.2 Operational Readiness Program 4.2.3 lNPO Periodic Evaluation 4.2A NSRB Review I Senior Management Review Team G. Preston / R. Machon G. Preston C. Crane M. Fecht W. Peabody B. Greenman T. McGrath NOTE: Not Covered This Month
li
STANDING AGENDA(CONT.)
6.0 Quality Assurance Activities 6.0 Licensing Project Plan 7.0 Lessons Learned 8.0 Emerging Issues 9.0 Fidelity Issues 10.0 Backlog Summaries 11.0 Summary IAction Items T. Shriver P. Salas C. Crane C. Crane C. Crane C. Crane R. Machon NOTE: Not Covered This Month
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1.0 INTRODUCTION
S AND OLD BUSINESS MEETING OBJECTIVES
~
Update NRG Region II Restart Review Board on the Progress Towards BFN Unit 3 Restart Activities Since the Last Monthly Meeting
~
Action Items from Previous Meetings Aetio Ite Brief NRC on Actions Being Taken to Strengthen the Foreign Material Exclusion (FME) Program Provide Completion Milestones for the Equipment Qualification Program Finalize Operational Readiness Assessment Team (ORAT) Inspection Dates Provide List of Outstanding QA I NSRB I ORRT Issues and Discuss Overall Issue of Open Item Lists Revise the Status of Commodities Table to Differentiate Between Pre-and Post-restart Requirements Status Status of Issue Discussed in the Emerging Issues Section During this Meeting Completion of Program Pending Closure of Remaining ECNs.
EQ Certification Letter Will Be Submitted Approximately One Week Prior to Restart (November 8, 1995).
Item Complete.
Site VisitScheduled For September 2? - 29. Inspection Scheduled for October 10-October 20. Exit Meeting WillBe October 27.
Outstanding Issues Discussed as Part of Each Topic During this Meeting Commodities Table Revised R. Machon
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1.0 INTRODUCTION
S AND OLD-BUSINESS MEETING OBJECTIVES (CONT.)
~
Action Items from Previous Meetings (Cont.)
Aetio Item Provide List of Pre-and Post-restart CATDs Resolve Appendix R High Impedance Faults Issue Provide Support for NRC Review of Multi-unitPRA Status item Complete. List and Justification for Post-restart CATDs Submitted.
Status of Issue Discussed in the Licensing Project Plan Section During this Meeting Item Complete.
TVASupported One Day NRC Visits on September 7 and 12, 1995 and Ongoing NRC Inspection.
Provide Briefing on Results of INPO Assist Visit Briefing Included in the Independent Assessments Section During this Meetihg Discuss August 9, 1995 Letter to Congress TVAPolicy WillRequire Future Submittals That Discuss NRC Be Reviewed by Licensing Discuss Evaluation of Multi-unitOperational Attributes Discuss Control of Operational Issues Identified Issues Loaded Into the Tracking and Reporting During Independent Reviews of Open Items Database Which Feeds into the
.Site Master Punchlist WillBe Validated With Operational Readiness Assessment Team R. Machon
!III'rKQIRA'rKDD Sl)78 SCHKDo!u!I!.K 95 6/I/85 7/I/95 8/I/95 9/! ~ 95 la/I/95 II/I/95 l2/I/95 I/I/96 2/I/96 3/I/96 c/I/96 2/I/95 3/ I/95
</I/95 5/I/
5/I/96 6/I/96 I
UNIT 3 NRC RESIARI REVIEI(
BOARD (RRBI HEET ING 2nsna RRB I
RRB HEE'IING HEETINQ V2l/ts t/lt/%
STATION I
. BLACKOUT I
I SELF EVALUATIONS (NINDD((
NRC RRB CHAIRHAN RRB RR'I RRB RRB'E(C'ETING HEETING HEE TING HEETINSIEEIII(G HEETING COHHISSIDN HEET ING S/2S/&
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< LICENSING (PLAN
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'N-GOING INSPECTIONS a CLOSEOUT ORAT; ORAT LETTEII CLOSEOUT
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HATER I
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S a SYSTEHS(
TVA BULK ESSANTIALLY i CDHPLETE!
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I PHASE Il ORR A CORP 4(EIIT TORUSl F(LL 4 CATE REMOVAL FIELD( WORK COMPLETE INFO NSRB
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NSRB FUEL LOAD
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LYDRO CRITICALITY I
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I MAJOR FIELD WORK REMOVE FUEL COMP(.ETE
< POOL OAI(ES l
PO((ER 4SCENSION TESTING COHPLETE BCB 04YS
" U2 CLOSE BREAKER UNIT 2 RFO 8 DCN HATDR SCOPE HAINT 2/I/%
I HIT RECOHEIIATION I
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SCOPE LE APPROYEO I
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REV (B) SEOUL TRACTS SHENT SITE N(Y(K SCHED(LES!
OTG I READY'TG READY I SCHEO START U3 ~0 S 010 PREPS I
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2.0 SCHEDULES (CONT.)
2.2 RECOVERY SCHEDULE (CONT.)
~
Summary of Commodities Commodit DCN's Issued DCN's FWC DCN's RTO'd Drawings SPAEs Systems FWC SPOC I SPOC II Work Items FWC PMT I Restart Tests Sls MOVATs LLRTs
~Ccm late 638 (98%)
1 )088 (90%)
1,057 (86%)
26,395 (78%)
60 (100%)
94 (98%)
45 (96%)
33 (55%)
16,292 (92%)
870 (80%)
196 (43%)
44 (66%)
43 (57%)
Remaining tncludin Postdnitiai Criticalit 115 178
?,523 27 1,361 223 261 23 33 Post-initiaI C~tttlcallt 24 4,000 to 5,500 c
600'3 See Backlog Summary Data Through 9I17(95 C. Crane
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2.0 SCHEDULES (CONT.}
2.2 RECOVERY SCHEDULE (CONT.}
Summary of Commodities (Cont.)
Commodit PIT Procedures Sl Procedures Tl Procedures Operating Procedures (E.GAOl's, Ol's, SSI's, and ARP's)
C~om lete 237 (97%)
720 (93%)
51 (70%)
150 (100%)
Remaining
!ncludin Postdnitial Criticalit 57 22 Postdnitial C~tMee lit I
0 Data Through 9/17/95 C. Crane
0 ik
2.0 SCHEDULES (CONT.)
2.2 RECOVERY SCHEDULE (CONT.)
e Major Gimpleted or Upcoming Milestones I
Torus Fill/Fuel Pool Gate Removal/System Field Work Completed (May 4, 1995 A)
Completed Installation of CRDs (June 21, 1996 A)
Completed Refueling Bridge Upgrade and Testing (July 16, 1996 A) sl I
Pull Condenser Vacuum (September 13; 1996 A)
Fuel Load (October 16, 1995)
Initial Criticality (No Earlier than November 16 1995)
C. Crane
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2.0 SCHEDULES {CONT.)
2.3 LICENSING SCHEDULE g ~
Closure of Remaining Restart Commitments Integrated With Project Schedule P. Salas
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2.0 SCHEDULES (CONT.)
2.4 POWER ASCENSION TEST SCHEDULE e
Power Ascension Test Program Scope and Intent of Program Well Defined Remaining Supporting Procedure Scheduled to Be Completed October )6, 1996 Schedule Established Sufficient Time Provided For Management Assessments
~
Confirmation That Prerequisites Completed Plant Material Condition Acceptable
~
Personnel Ready to Proceed C. Crane
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4.0 UNIT 3 OPERATIONAL READINESS REVIEWS 4.1 SELF ASSESSMENTS
~
Operational Readiness Windows Colors Used to Convey Rating Green Signifies Significant Strength IltSlhM Signifies Satisfactory Performance Yr'.I tour Signifies Improvement Needed
~ ~
o Red Signifies Significant Weakness Blue Signifies insufficient Data G. Preston
ii
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PROCESSES BROWNS FERRY UNlT3 OP ERATlONALREADlNESS August 1996
- Recovery Organization and Administration OVERALL MANPOWER SCHEDULING KNOWLEDGE 8 PERFORMANCE CONDUCT OF RECOVERY CONTRACTOR CONTROL WORK CONTROL QUAUTY PROGRAMS Engineering PROCEDURES AND DOCUMENTATION CONFIGURATION MANAGEMENT DCNs'SSUED ELECTRICAL ISSUES
~ APPENDIX R SPAE EQ PROGRAM SEISMIC MATERIAL INVENTORY STAFFING Construction PROCEDURES AND DOCUMENTATION DCNs.
IMPLEMENTED HOUSEKEEPING CONDUCT OF CONSTRUCTION MATERIAL MANAGEMENT STAFFING Maintenance PROCEDURES AND DOCUMENTATION PLANT MATERIEL CONDITION
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HOUSEKEEPING
~
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- = MANAGEMENT PREVENTIVE MAINTENANCE STAFFING MA'INTENANCE BACKLOG Page 3 of2
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4.0 UNIT 3 OPERATIONAL READINESS REVIEWS (CONT.)
4.1 SELF ASSESSMENTS (CONT.)
~
Foreign Material Exclusion (FME) Issue Recently Identified Foreign Material In Unit 3 Core Spray Pump Bowl Log Issue (LightString)
Immediate Incident Investigation in Progress
)
Interim Corrective Actions 0
Underwater Inspections of Unit 3 Torus and Ringheader o
Access Points Locked to Establish Positive Control on Critical Plant Systems 0
Central Point of Contact Established for Plant FME Program FME Program Enhancements Being Developed Ongoing Assessments by NA&L Closely Monitoring Developments at Limerick G. Preston 13
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4.0 UNIT 3 OPERATIONAL READINESS. REVIEWS (CONT.j 4.1 SELF ASSESSMENTS (CONT.)
BFN Readiftess Plan forDual Unit Operation c% Future Excellence Analysh 4 Esslassion Rcstscl 4 Ecccihnoc Flan hlsnsgmcnl Pasonnsl Facililica R qWpcecal qosschy of SUlh Tools hfahsish Fncilhica Okhl Capissl Molu ~ Unil Tash Based Bhaaviossl R. Machon
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4.0 UNIT 3 OPERATIONAL READINESS REVIEWS {CONT.}
4.1 SELF ASSESSMENTS {CONT.}
~
Dual Unit Sensitivity Objective Extends Beyond Unit 3 Recovery and Targets Overall Excellence as a Dual-unit Operating Site Program Areas 0
Personnel Processes and Programs 0
Management o
Facilities and Equipment Financial Resources Structure Overall Site Program Nlanagement Briefing by Department 0
Departmental Staff Briefings 0
Overall Site Briefing Paper R. Machon
t5
4.0 UNIT 3 OPERATIONAL READINESS REVIEWS (CONT.}
4.1 SELF ASSESSMENTS (CONT.)
~
Dual Unit Sensitivity (Cont.)
Site Sensitivity to Dual-unit Operations Included in Readiness for Restart Determination Specific Examples of Dual-unit Sensitivity Enhancements o
Training
~
Multi-unitTransients
~
Multi-unitPRA Lessons
~
System Differences
~
System Interactions SOS Mentor Selection Included Multi-UnitExperience 0
Lessons Learned from Dual Unit Incidents Reviewed During Plan ofthe Day Meetings R. Machon 16
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4.0 UNIT 3 OPERATIONAL READINESS REVIEWS (CONT.)
4.1 SELF ASSESSMENTS (CONT.)
~
Test Deficiency Resolution Process Overview Types of Deficiencies Identified Corrective Actions implemented C. Crane
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4.0 UNIT 3 OPERATIONAL READINESS REVIEWS (CONT.)
4.2 INDEPENDENT ASSESSMENTS
~
Operational Readiness Review Team (ORRT)
Assessment Status Sub-teams (Operations/Maintenance/Engineering and Technical Support/Oversight and NA&L)Have Completed InitialVisitAssessments Operations Sub-team Second Round of Assessments 4is Week System Readiness Assessments Continuing Identified Weaknesses o
Cognizant Personnel Knowledge of Unit Differences and System Interactions 0
Lack of Complete and Comprehensive Multi-unitTraining Program Lack of Documented Transition Plans (I.E., Staffing Versus Workload) for Near and Long Term Multi-unitConditions 0
Power Ascension Program Elements and Schedule W. Peabody 19
~0 il
4.0 UNIT 3 OPERATIONAL READINESS REVIEWS (CONT.)
4.2 INDEPENDENT ASSESSMENTS (CONT.)
o Operational Readiness Review Team (Cont.)
issues Being Monitored o
FME Enhancements Commitment/Work item Closure o
Non-CSSC Condition/Practices o
Advance Work Planning/Material Staging Observed Strengths o
NA&LFocus and.Reporting o
Senior Plant Management involvement o
Support Organization Readiness o
Radcon/Chemistry Readiness W. Peabody 20
0
4.0 UNIT 3 OPERATIONAL READINESS REVIEWS (CONT.)
4.2 INDEPENDENT ASSESSMENTS (CONT.)
~
Highlights of INPO Assist Visit Engineering Support Maintenance Outage Management Operations B. Greenman
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4.0 UNIT 3 OPERATIONAL READINESS REVIEWS (CGNT.)
4.2 INDEPENDENT ASSESSMENTS (CONT.)
~
Nuclear Safety Review Board Review (NSRB) I Senior Management Assessment of Restart Team (SMART) (Cont.)
Background
'MART Review is an NRC Commitment to Implement an Assessment Similar to That Performed on Unit 2 NSRB Membership is Consistent With Unit 2 SMART Composition Purpose is to Ensure High Standards of Excellence for Restart Readiness This Objective Accomplished By o
Independent Assessments 0
Oversight of Other Assessments T. McGrath 23
ii i
4.0 UNIT 3 OPERATIONAL READINESS REVIEWS (CONT.)
4.2 INDEPENDENT ASSESSMENTS (CONT.)
~
Nuclear Safety Review Board Review (NSRB) I Senior Management Assessment of Restart Team (SMART)
Membership TVANuclear T. J. McGrath, Chairman O. J. Zeringue M. O. Medford D. E. Nunn J. A. Scalice R. J. Adney R. D. Machon J. P. Maciejewski R. R. Baron
'. J. Green E. Preston Outside W. F. Conway H. E. Stone T. L. Gerber T. McGrath 24
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4.0 UNIT 3 OPERATIONAL READINESS REVIEWS {CONT.)
4.2 INDEPENDENT ASSESSMENTS {CONT.)
I e
Nuclear Safety Review Board Review (NSRB) I Senior Management Assessment of Restart Team (SMART) (Cont.)
Responsibilities NSRB l SMART Oversees the Overall Adequacy and Quality of Preparedness for Restart of Unit 3 and Dual Unit Operations Charter Defines Areas of NSRB I SMART Responsibilities General Approach o
Oversight of Other Independent Review Activities Through Presentations and Selected Subcommittee'Reviews o
Evaluation of Listed Areas Against Acceptance Bases by Subcommittee.
Review of Nuclear Assurance and Line Assessments and the Actions Taken to Resolve Identified Issues 0
Collegial Review, Subcommittee Reports and Full Board Presentations to Ensure Acceptance Bases Are Met SMARTI NSRB Provides Independent Restart Readiness Recommendation to the President - TVANuclear T. McGrath
i)
4.0 UNIT 3 OPERATIONAL READINESS REVIEWS (CONT.)
4.2 INDEPENDENT ASSESSMENTS (CONT.)
~
Nuclear Safety Review Board Review (NSRB) / Senior Management Assessment of Restart Team (SMART) (Cont.)
Review Examples System Readiness
~
Corporate NA Review Adequacy of Site NAAssessment Plans Site NA Review of SPOC Process, Including System Walkdowns
~
ORR Review of Process Implementation and Three Systems NSRB Subcommittee Review of Process and Item Deferrals for Two Systems Phase II Site NA Review and Corporate NA Follow-up I
~
Review of System Windows and ORR/NA Results With NSRB/SMART Prior to Restart 0
Operations Readiness for Differences in Dual Unit Operation
~
Corporate NA Review of Operator Training on Unit Differences and Interactions NSRB Subcommittee Evaluation of Simulator Training and Control Room Operations
~
ORR Evaluation of Operator Training (Reported to NSRB/SMART)
NSRB Subcommittee Assessment of Actions in Response to NAand ORR Findings
~
ORR and NA Follow-up Reviews and Report to NSRB/SMART T. McGrath 26
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4.0 UNIT 3 OPERATIONAL READINESS REVIEWS (CONT.)
4.2 INDEPENDENT ASSESSMENTS (CONT.)
~
Nuclear Safety Review Board Review (NSRB) I Senior Management Assessment of RestarI); Team (SMART) (Cont.)
I Schedule NSRB Meeting Subcommittee Reviews NSRB/SMART Meeting Subcommittee Reviews June 1, 1995 August/September 1996 September 12, 1996 October 1995 NSRB/SMART Restart Meeting Early November 1995 T. McGrath 27
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5.0 QUALITYASSURANCE ACTIVITIES e
Results/Status of Quality Assurance Activities Evaluation of Watts Bar Construction Deficiencies Three Completed Since Last Restart Review Board Meeting
~
Inappropriate Use of QDCNs
~
improper Control of Coatings
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Lack of Design Output for Diesel Generator Speed Switch Setting 40 Total Evaluations Completed Unit 3 Specific Assessments o
Four Completed Since Last Restart Review Board Meeting
~
Vertical Slice (RVLIS)
~
Procedure Upgrade
~.
SWSOPI Follow-up
~
GL 89-10 Follow-up o
16 Total Assessments Completed T. Shriver 28
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5.0 QUALITYASSURANCE ACTIVITIES(CONT.)..
~
Results/Status of Quality Assurance Activities (Cont.)
Plant Assessments Two Completed Since Last Restart Review Board Meeting Maintenance Rule Training
~
Pre-job Briefings Nine Total Assessments Completed Summary of Findings Eight Problem Evaluation Reports (PERs) Issued from QA Assessments Since Last Meeting o
?6 Total PERs Written 0 Level A
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13 Level 8
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39 Level C 24 Level D
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Corrective Actions Being Implemented T. Shriver 29
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5.0 QUALITYASSURANCE ACTIVITIES(CONT.)
REMAININGAUDITS, INSPECTIONS AND ASSESSMENTS September 1995 Restart Test Follow-up (In Process)
Procurement / Material Control (In Process)
Drawing Discrepancies (In Process)
Transfer of Recovery Responsibility (In Process)
Lessons Learned (In Process)
Dual Unit Operations / Operational Readiness / Power Ascension (Phase I) (In Process)
SPOC / SPAE (Phase II)
Design Baseline Corrective Action Audit QC / ISI / NDE Audit Appendix R Follow-up Backlog October 1995 Fuel Load Unit 3 Open Items Closure T. Shriver 30
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5.0 QUALITYASSURANCE ACTIVITIES(CONT.)
REMAININGAUDITS, INSPECTIONS AND ASSESSMENTS {CONT.)
November 1995 Restart Operations Audit Engineering I Modifications Audit Fitness for Duty Audit December 1995 Power Ascension (Phase ll)
January 1996 Multi-unitOperations (Phase ll)
T. Shriver 31
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6.0 LICENSING PROJECT PLAN
~
Restart Technical Specifications Remaining Topic Appendix R License Amendment (TS 337)
RHR Service Water Requirements forStandby Coolant (TS 361)
HPCiI RClc instrument Checks (TS 368')
SUBMITTAL DATE 9/30/93 6/02/95 9/13I95 NEED DATE 10/28I95 10/28/95 11I13/95 PROJECTED
~SSUE OATS 10/N/95 10/28/95 TBD
'Advantageous But Not Essential For Unit 3 Restart
~
Safety Evaluations RequIred Seismic Analysis of Flexible Conduit TVAProcessing Submittal of Requested Supplemental Information (September 29, 1995)
Appendix R 0
TVAINRCTeleconferences Held 0
TVAProcessing Submittal Describing Programmatic Enhancements (September 29, 1995)
P. Salas 32
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'.0 LICENSING PROJECT PLAN {CONT.}
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Summary of Unit 3 Post-restart issues TOPIC Generic Letter 88-20, Supplement 4, Individual Plant Examination of External Events (IPEEE)
Generic Letter 8946 - Safety Parameter Display System (SPDS)
Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance Generic Letter 9241 - Reactor Vessel Structural Integrity, Revision 1, Supplement 1
Generic Letter 92<8 -Thermokag 330-1 Fire Barriers COMMITMENT TVAWillComplete the Internal Fires IPEEE and Provide a Summary Report to NRC TVAWillInstall and Make Operational an SPDS TVAWillComplete Generic Letter 89 ~
Safety-related Motor-operated Valve Testing and Surveillance During the Power Ascension Test Program Revision 1, Supplement 1, Requested Licensees Verifythe Completeness of the Information Previously Submitted by November 15, 1995 TVAWillInstall Isolation Fuses In the 4kV Shutdown Board AC Power Circuit 2.
TVACommitted to Replace the Thermo-lag Material Installed in the Intake Pumping Station SCHEDU E The Summary Report WillBe Issued Within One Hundred Twenty Days after the Restart of Unit 3 from its First Refueling Outage Following Restart TVAWillCertify its Compliance with the Requirements of NUREG4?37, Supplement 1, Within Two Months after the SPDS Is Declared Fully Operational TVAWillComplete the Required Testing Within 30 days Following the Completion of the Power Ascension Test Program TVA's Response Is Scheduled for November 15, 1995 1.
TVAintended to Implement this Modification Prior to Unit 2 Cycle 8 Operation 2.
TVAIntends to Complete this Modification Prior to Hydrostatic Testing P. Salas 33
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6.0 LiCENSiNG PROJECT PLAN (CONT.)
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Summary of Unit 3 Pqst-.restart Issues (Cont.)
TOPIC Generic Letter 9442-Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in BoilingWater Reactors NUREG4737 (TMIAction Plan)
Action Item II.B.3 - Post-Accident Sampling System (PASS)
Seismic Class II Over I I Spacial Systems Interactions and Water Spray Unresolved Safety Issue A46-Seismic Quail('.cation of Equipment ln Operating Plants COMMITMENT TVAWillimplement the BWROG Option Ill Methodology forthe Stability Long-term Solution TVAWillInstall a PASS TVAWillEvaluate Potential Seismic-induced, Spatial Interaction Effects of Class II Systems on Class I Systems TVAWillComplete the Seismic Portion of the USI A46 Program SCHEDULE TVAWillInstall the PRNM Upgrade During the next Unit 3 Refueling Outage Testing ofthe Containment Atmosphere by the PASS WillBe Accomplished as Soon as Practical This Evaluation WillBe Incorporated as Part of the Resolution of Unresolved Safety Issue A46 This Program WillBe Completed Prior to March 19, 1996 P. Salas 34
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7.0 LESSONS LEARNED
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Lessons Learned From Unit 2 Recovery From Sequoyah From Other Facilities
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Engineering Lessons Learned Focused on Design Processes and Programs
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Lessons Learned from the Restart Test, Power Ascension Programs and Operations lricluded Personnel, Programmatic, Component, and System Enhancements Overall Lessons Learned Have Been Effectively Addressed C. Crane 35
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9.0 FIDELITYISSUES
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Differences in Plant Design Controlled by Site Stanaard Practice S.i, Piant ModiTications and Design Control Differences Require Approval by Engineering and Materials Manager, Responsible System Engineer, Technical Support Manager, and Operations Superintendent
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Major Differences Between the Units Appendix R Safe Shutdown Instructions Condensate Demineralizer Upgiade RWCU Rapid Isolation
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Control Rooms and Simulator VirtuallyIdentical C. Crane 36
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10.0 BACKLOGSUMMARIES MAINTENANCE UNIT 3 SPOC'D SYSTEM OPEN VfO'S/WR'S Sll 2ll TIINIS 7 II/IS MISS MNS NIIIIS NIIS NNIS N0/IS NIINS NIN 7/09/95
'7/16/95 7/23/95 7/30/95 8/06/95 8/13/95 8/20/95 8/27/95 9/03/95 9/10/95 Corrective Maintenance Bacido 40 36 46 43 65 77 69 66 74
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127 24 42 132 18 37 139 22 34 142 23 30 161 35 35 216 38 48 226 92 93 203 95 97 219 103 99 260 112
'05 Totals
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260 14 250 17
-7 272 16 284.
16 306 14 25 417 29 21 539 49 25 549 52 12 25 576 47 12 26 636 C. Crane 37
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