ML090370086
| ML090370086 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 07/23/2003 |
| From: | Bhagwat Jain NRC/ACNW, Advisory Committee on Reactor Safeguards |
| To: | Bonaca M, Ford F, Leitch G, Rosen S, Wallis G Advisory Committee on Reactor Safeguards |
| References | |
| Download: ML090370086 (9) | |
Text
UNITED STATES
- NUCLEAR REGULATORY COM SiaN ADVISORY COMMITIEE ON REACTOR SAFEGUARDS WASHINGTON, D.C. 20555-0001 July 23, 2003 MEMORANDUM TO: Graham Leitch, Subcommittee Chairman Mario Bonaca, Member F. Peter Ford, Member Stephen Rosen, Member Graham Wallis, Member
~
FROM:
B.P. Jain, Senior Staff Engineer ACRS/ACNW
~_-=-_-
SUBJECT:
UPCOMING LICENSE RENEWAL SUBCOMMITTEE MEETING ON H.B. ROBINSON, STEAM ELECTRIC PLANT, UNIT 2 The Subcommittee on Plant License Renewal will be meeting on September 30, 2003, to review the license renewal application for H.B. Robinson Steam Electric Plant, Unit 2 and the associated Safety Evaluation Report (SER) prepared by the NRC staff. The SER is still being prepared by the staff. Attached is the license renewal application (CD-ROM also included) for your review. A list of review assignment for individual members is also attached.
Those members who are not scheduled to attend the subcommittee meeting on September 30, 2003, should send their comments to the Subcommittee Chairman Mr. Graham Leitch with a copy to me by September 15, 2003.
Status report for the September 30, 2003, meeting along with the SER and additional supporting information will be provided to you by end of August 2003. If you have any questions, please call me (301-415-7270) or E-mail (bpj@nrc.gov).
Attachment:
As stated cc w/
Attachment:
ACRS Members J. Barton cc wo/
Attachment:
J. Larkins S. Bahadur S. Duraiswamy
Arr/tCHIv1ENT,'.EHB£,e.S REV/£w. SS/&NMEAlTS
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Robinson Nuclear Plant License Renewal AppliCation Administrative Information TABLE OF CONTENTS f>r~fCl~....*..****..***************.***.*******.*.*......*...**....*.**.****************.**....*.....***...**....i ADMINISTRATIVE INFORMATION
1.1-1 1.1 PURPOSE AND GENERAL INFORMATION.................*................................1.1-1
1.1.1 NAME OF APPLICANT..................*............................................................1.1-2
1.1.2 ADDRESS OF APPLICANT.......*.......................*........................................1.1-2
1.1.3 OCCUPATION OF APPLICANT
1.1-2 1.1.4 ORGANIZATION AND MANAGEMENT OF APPLICANT
1.1-2 1.1.5 CLASS AND PERIOD OF LICENSE SOUGHT
1.1-5 1.1.6 ALTERATION SCHEDULE
1.1-5 1.1.7 CHANGES TO THE STANDARD INDEMNITY AGREEMENT 1.1-5 1.1.8 RESTRICTED DATA AGREEMENT....................................*......................1.1-5
1.2 DESCRIPTION
OF ROBINSON NUCLEAR PLANT
1.2-1
)
1.3 TECHNICAL INFORMATION REQUIRED FOR AN APPLICATION 1.3-1 1.4 CURRENT LICENSING BASIS CHANGES DURING NRC REVIEW 1.4-1 2.0
SCOPING AND SCREENING METHODOLOGY FOR IDENTIFYING STRUCTURES AND COMPONENTS SUBJECT TO AGING MANAGEMENT REVIEW AND IMPLEMENTATION RESULTS 2.0-1 2.1 SCOPING AND S~ENING METHODOLOGY
2.1-1 2.1.1 SCOPING...........*....r~~~~~/
~~..I.rf.H., g~.$.Q.~
2.1-2
2.1.1.1 Safety RelCited Criteria PursuCint to 10 CFR 54.4(a)(1)
2.1-3 2.1.1.2 Non-Safety Related Criteria Pursuant to 10 CFR 54.4(a)(2) 2.1-5 2.1.1 ~3 Other Scoping Pursuant to 10 CFR 54.4(a)(3) lj 2.1-7 2.1.2 STRUCTURE AND COMPONENT SCREENING..S.K~p..r..~f.rs..2.1-11 2.1.2.1 MechaniCCII Systems
~~.............*..............2.1-12
2.1.2.2 Civil Structures
2.1-13 2.1.2.3 ElectriCCII and I&C Systems.................*......":e'
2.1-14
2.1.3 GENERIC SAFETY ISSUES
~.~r:r.~
2.1-16 2.
1.4 CONCLUSION
S
~
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2.1-17 2.
1.5 REFERENCES
.....*.......................................*............................*...........*...2.1-18
Table of Contents
Page vi
)
Robinson Nuclear Plant License Renewal Application Administrative Information Apos;t>LA~,S~ ~$£tojJ RA~SoM 2.2 PLANT LEVEL SCOPING RESULTS
2.2-1 2.3 SCOPING AND SCREENING RESULTS - MECHANICAL SYSTEMS 2.3-1 2.3.1 REACTOR VESSEL, INTERNALS, AND REA
SYST M2.3-2 2.3.1.1 Reactor Coolant System Piping S A.~ POwER5.. 2.3-3 2.3.1.2 Reactor. Coolant Pumps
sr'E.8E~
2.3-4 2.3.1.3 Pressunzer
BlWl:1'riiT.'-..... 2.3-5 2.3.1.4 Reactor Pressure VesseL..............................
2.3-5
2.3.1.5 Reactor Vessel Internals
2.3-6 2.3.1.6 Steam Generators
~..2.3-7 2.3.1.7 Reactor Vessel Level Instrumentation........*...................
2.3-8
2.3.1.8 Summary
2.3-8 2.3.2 ENGINEERED SAFETY FEATURES SYSTEMS
2.3-18 2.3.2.1 Residual Heat Removal System
2.3-18 2.3.2.2 Safety Injection System
2.3-20 2.3.2.3 Containment Spray System
2.3-22 2.3.2.4 Containment Air Recirculation Cooling System
2.3-23 2.3.2.5 Containment Isolation System
2.3-25 2.3.3 AUXILIARY SYSTEMS
2.3-29 2.3.3.1 Sampling Systems...........................................
2.3-30
2.3.3.2 Service Water System
2.3-32 2.3.3.3 Component Cooling Water System
2.3-33 2.3.3.4 Chemical And Volume Control System
2.3-36 2.3.3.5 Instrument Air System
2.3-38 2.3.3.6 Nitrogen SupplylBlanketing System
2.3-40 2.3.3.7 Radioactive Equipment Drains
2.3-41 2.3.3.8 Primary And Demineralized Water System
2.3-41 2.3.3.9 Spent Fuel Pool Cooling System
2.3-42 2.3.3.10 Containment Purge System...............................................
2.3-43
2.3.3.11 Rod Drive Cooling System
2.3-44 2.3.3.12 HVAC Auxiliary Building
2.3-45 2.3.3.13 HVAC Control Room Area
2.3-46 2.3.3.14 HVAC Fuel Handling Building.................................
2.3-48
2.3.3.15 Fire Protection System
2.3-49 2.3.3.16 Diesel Generator System
2.3-51 2.3.3.17 Dedicated Shutdown Diesel Generator 2.3-54 2.3.3'.18 EOFrrSC Security Diesel Generator 2.3-57 2.3.3.19 Fuel Oil System........*.................................*.....................
2.3-58
2.3.4 STEAM AND POWER CONVERSION SySTEMS
2.3-60 2.3.4.1 Turbine System
2.3-60 2.3.4.2 Electro-Hydraulic Control System
2.3-61 2.3.4.3 Turbine Generator Lube Oil System
2.3-61 2.3.4.4 Extraction Steam System
2.3-62 2.3.4.5 Main Steam System 2.3-62
( {"n IJ.)
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Table of Contents
Page vii
\\,
Robinson Nuclear Plant Ucense Renewal Appfication Administrative Information
£bt1 oj 2.3.4.6 Steam Generator Blowdown System..............**.*.*........*..................2.3-64
2.3.4.7 Steam Cycle Sampling.................*........*.............
2.3-65
2.3.4.8 Feedwater System
. ~a 2.3-66
~..wt'"
2.3.4.9 Auxiliary Feedwater System
2.3-68 2.3.4.10 Condensate System
~ I%:et 2.3-69 2.3.4.11 Steam Generator Chemical Addition
Stl£;~.r."
2.3-71 2.3.4.12 Circulating Water System..........*..*.....*.............
....BPlk...... 2.3-71
2.3.5 REFERENCES...................................................
2.3-73
2.4
SCOPING AND SCREENING RESULTS - STRUCTURES 2.4-1 2.4.1 CONTAINMENT.........**...*........*....**...*..*.*.*..........**.......*............................2.4-2
2.4.1.1 Containment Structure
2.4-2 2.4.1.2 Containment Internal Structural Components
2.4-6 2.4.1.3 Containment External Structural Components
2.4-10 2.4.1.4 Conclusion...........................................................................
2.4-11
2.4.2 OTHER STRUCTURES 2.4-22 2.4.2.1 Reactor Auxiliary Building....................................................
2.4-22
2.4.2.2 Fuel Handling Building
2.4-31 2.4.2.3 Turbine Building......*....*..........*......................*................................2.4-37
2.4.2.4 Dedicated Shutdown Diesel Generator Building...................
2.4-42
2.4.2.5 Radwaste Building................................................................
2.4-44
2.4.2.6 Intake Structure
2.4-45 2.4.2.7 North Service Water Header Enclosure
2.4-49
)
2.4.2.8 EOFrrSC Security Diesel Generator Building
2.4-53 2.4.2.9 Discharge Structures
2.4-54 2.4.2.10 Lake Robinson Dam..................*.*............................~............
2.4-55
2.4.2.11 Pipe Restraint Tower
2.4-57 2.4.2.12 Yard Structures and Foundations
2.4-61 2.4.2.13 Refueling System...............*.............................*...*..........................2.4-66
2.4.3 REFERENCES.....**..................*....................................*..........................2.4-67
2.5
SCOPING AND SCREENING RESULTS - ELECTRICAL AND
INSTRUMENTATION AND CONTROLS (I&C) SySTEMS.......*....*..............2.5-1
2.5.1 ELECTRICAUI&C COMPONENT COMMODITY GROUPS 2.5-2 2.5.2 APPLICATION OF SCREENING CRITERION 10 CFR 54.21 (A)( (I) TO
ELECTRICAUI&C COMPONENT COMMODITY GROUPS 2.5-3
2.5.3 APPLICATION OF SCREENING CRITERION 10 CFR 54.21 (A)( )(11) TO
ELECTRICAUI&C COMPONENT COMMODITY GROUPS..*...................2.5-4
2.5.3.1 Bus Duct
2.5-4 2.5.3.2 Insulated Cables And Connections.....*.....*.**...............*....................2.5-4
2.5.3.3 Electricalll&C Penetration Assemblies
2.5-5 2.5.4 ELECTRICAUI&C COMPONENTS REQUIRING AN AGING MA AGEMENT
REVIEW 2.5-6
2.5.5 REFERENCES....*...........*...............*...........*.....**.**...................................2.5-7
Table of Contents
Page viii
)
Robinson Nuclear Plant License Renewal Appncation Administrative Information 3.0 AGING MANAGEMENT REVIEW RESULTS..................*.............................3.0-1
3.1
AGING MANAGEMENT OF REACTOR VESSEL, INTERNALS AND REACTOR COOLANT SYSTEM.......*...........F.:e?&.C>.
SH~.J..R.8115ti~ Nt£.T/lN3.1-1 3.1.1 AGING MANAGEMENT REVIEW 3.1-1 3.1.-1.1 Methodology 3.1-1 3.1.1.2 Operating Experience.....*..................................................................3.1-2
3.1.2 AGI NG MANAGEMENT PROGRAMS.........*..............
3.1-3
3.1.2.1 Aging Management Programs Evaluated in the ALL Report that Are Relied on for License RenewaL..........*............................................3.1-3 3.1.2.2 Further Evaluation of Aging Management as Re mmended by the GALL Report 3.1-3 3.1.2.3 Aging Management Evaluations that Are Oiffere t from or Not Addressed in the GALL Report 3.
1.3 CONCLUSION
S 3.
1.4 REFERENCES
3.1-3 3.1-4 3.1-5 3.2 AGING MANAGEMENT OF ENGINEERED SAF~TY FEAT~ES 3.2-1 3.2.1 AGING MANAGEMENT REVIEW
~~...,.W~.~~t.,.81.£..tDr.t.3.2-1 3.2.1.1 Methodology 3.2-1 3.2.1.2 Operating Experience.......................................................
3.2-2
3.2.2 AGING MANAGEMENT PROGRAMS 3.2-3 3.2.2.1 Aging Management Programs Evaluated in the GALL Re ort that Are Relied on for License RenewaL........................................
3.2-3 3.2.2.2 Further Evaluation of Aging Management as Recommen ed by the GALL Report......
,3.2-3 3.2.2.3 Aging Management Evaluations that Are Different from 0 Not Addressed in the GALL Report..........................
3.2-3 3.2.3 CONCLUSIONS 3.2-4 3.2.4 REFERENCES 3.2-5 3.3
AGING MANAGEMENT OF AUXILIARY SySTEMS 3.3-1 3.3.1 AGING MANAGEMENT REVIEW 3.3-1 3.3.1.1 Methodology........................................*.............................................3.3-1
3.3.1.2 Operating Experience 3.3-1 3.3.2 AGING MANAGEMENT PROGRAMS 3.3-3 3.3.2.1 Aging Management Programs Evaluated in the GALL R ort that Are Relied on for License RenewaL........................................
3.3-3 3.3.2.2 Further Evaluation of Aging Management as Recommen ed by the GALL Report..........*.......
3.3-3 3.3.2.3 Aging Management Evaluations that Are Different from Not Addressed in the GALL Report.........
3.3-3 3.3.3 CONCLUSION..........*...............................................................
3.3-4
3.3.4 REFERENCES......................................*....................................................3.3-5
Table of Contents
Page ix
( con1iJ)
Robinson Nuclear Plant Ucense Renewal Application Administrative Information 3.4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEMS
........................................Kg~ W!.tl::l.:J.$,...B T./l.N.
3.4-1
3.4.1 AGING MANAGEMENT REVIEW
3.4-1 3.4.1.1 Methodology.......*........*...........*.....*..........
- .......***.*.**..*....*.......3.4-1
3.4.1.2 Operating Experience
.........*~
3.4-1
3.4.2 AGING MANAGEMENT PROGRAMS
..*...........................*3.4-3
3.4.2.1 Aging Management Programs Evaluated in the ALL Report that Are Relied on for License Renewal..............................*...*.*....................3.4-3 3.4.2.2 Further Evaluation of Aging Management as R ommended by the GALL Report......*.......*....*.*.....*........*.................**..**.*..............*.....*..*..*.......3.4-3 3.4.2.3 Aging Management Evaluations that Are Differe t from or Not Addressed in the GALL Report......................*.........................*...........................3.4-3 3.
4.3 CONCLUSION
..........*.................3.4-4
3.
4.4 REFERENCES
3.4-5
3.5
~g~;o~~~~~~R~~.~.~~~~.I~~~~:~~~~g~~i~~~~
3.5-1 3.5.1 AGING MANAGEMENT REVIEW
3.5-1 3.5.1.1
Methodology................................................*....................................3.5-1
3.5.1.2 Operating Experience...........................................
3.5-2
3.5.2 AGING MANAGEMENT PROGRAMS
3.5-3 3.5.2.1 Aging Management Programs Evaluated in the LL Report that Are Relied on for License RenewaL 3.5-3 3.5.2.2 Further Evaluation of Aging Management as Rec mmended by the GALL Report 3.5-3 3.5.2.3 Aging Management Evaluations that Are Differen from or Not Addressed in the GALL Report................................................
3.5-3 3.
5.3 CONCLUSION
~.........................................................
3.5-4
3.
5.4 REFERENCES
.
3.5-5
3.6
~g~~~~~~~.~~~~8$¥-JE~~~~~~~~W~~}~~.~~.~~~.3.6.1 3.6.1 AGING MANAGEMENT REVIEW
.
3.6-1 3.6.1.1
Methodology
...*..............................3.6-1
3.6.1.2 Operating Experience......................................*...............*................3.6-2
3.6.2 AGING MANAGEMENT PROGRAMS
.
3.6-3 3.6.2:1 Aging Management Programs Evaluated in th GALL Report that Are Relied on for License Renewal..........................*..............................3.6-3 3.6.2.2 Further Evaluation of Aging Management as ecommended by the GALL Report..............................................................
3.6-3 3.6.2.3 Aging Management Evaluations that Are Diffe nt from or Not Addressed in the GALL Report....................................*........*.*......*.....................3.6-3 3.
6.3 CONCLUSION
.............*..............*............*...*....*........................................3.6-4
3.
6.4 REFERENCES
..........................................................
3.6-5
Table of Contents
Page x
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Robinson Nuclear Plant Ucense Renewal Application Administrative Information 4.0 TIME-LIMITED AGING ANALYSES
4.0-1 4.1
IDENTIFICATION OF TIME-LIMITED AGING ANALYSES 4.1-1
. 4.1.1 TIME-LIMITED AGING ANALYSES IDENTIFICATION PROCESS
.4.1-1 4.1.2 IDENTIFICATION OF EXEMPTIONS 4.1-2 4.1.3. REFERENCES
4.1-2 4.2
REACTOR VESSEL NEUTRON EMBRITTLEMENT 4.2-1 4.2.1 PRESSURIZED THERMAL SHOCK 4.2-3 4.2.2 UPPER SHELF ENERGY 4.2-4 4.2.3 OTHER ANALySES...........................................................................
4.2-5
4.2.4 REFERENCES.....
4.2-6 4.3
METAL FATIGUE '"
~.t\\:~.~.I fQ.1~J?.,
&A:~~QM 4.3-1 4.3.1 EXPLICIT FATIGUE A S A) 4.3-2 4.3.1.1
Pressurizer Surge Line Thermal Stratification 4.3-3 4.3.1.2 Pressurizer Insurge/Outsurge 4.3-4 4.3.1.3 Reactor Internals Holddown Spring And Alignment Pins
.4.3-5 4.3.1.4 Auxiliary Feedwater Line Fatigue Analysis 4.3-5 4.3.2 IMPLICIT FATIGUE DESIGN (ASME SECTION III. CLASS C. B31. )
4.3-7 4.3.3 ENVIRONMENTALLY ASSISTED FATIGUE EVALUATION 4.3-9 4.3.4 REACTOR VESSEL UNDERCLAD CRACKING 4.3-11 4.3.5 CONTAINMENT PENETRATION BELLOWS FATIGUE 4.3-12 4.3.6 CRANE CYCLIC LOAD LIMITS 4.3-13 4.3.7 REFERENCES...........................................................................
4.3-15
4.4
ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT 4.4-1 4.4.1 ELECTRICAL AND I&C COMPONENT ENVIRONMENTAL QUALIFICATION
ANALYSES Ae(l.:$.:r:Q.~~J~.I E.a~~~~..P.-:At.f$;QM,..ijAl~.4.4-3 4.4.1.1 ASCO NP8316 and NP8321 Series Solenoid Valves
.4.4-4 4.4.1.2 ASCO Solenoid Valves - AQR Report 4.4-5 4.4.1.3 Limitorque 5MB Motor Operated Valve (MOV) Actuators - Outside Containment 4.4-6 4.4.1.4 Limitorque Model SB-3 and 5MB-OO Motor-Operated Valve (MOV)
Actuators - Inside Containment 4.4-7 4.4.1.5 Rockbestos Cable - Firewall 111 4.4-8 4.4..1.6 Rockbestos RSS-6-104/LE Series Coaxial Cable
.4.4-9 4.4'.1.7 Rockbestos Cable - Firezone R 4.4-10 4.4.1.8 GEMS Liquid Level Transmitters - Model XM-54853 and XM-54854
.......................................................................................................4.4-11 4.4.1.9 B&W Valve Monitoring System 4.4-12 4.4.1.10 Westinghouse Reactor Containment Fan Cooler (RCFC) Motors 4.4-13 4.4.1.11 Westinghouse Motors - Frame 506UPZ. 509US. and SBOP - RHR. SI Pumps. HVA 6A. 6B, 8A. & 88 4.4-14 Table of Contents Page xi ( lQ.,tJJ
Robinson Nudear Plant License Renewal Application Administrative Information 4.4.2 g~~~N~~;~.~~:~~.~~~~:'~~~~~~.~.:~:.~~~:~
4.4-521-4.
4.3 REFERENCES
4.4-53
4.5 C~NTAINMENTTENDON LOSS OF PRESTRESS..I?.tM;~~lJ<**
4.6 OTHER PLANT-SPECIFIC TIME-LIMITED AGING AN
....*...............4.6-1
4.6.1 THERMAL AGING EMBRITILEMENT 4.6-1 4.6.2 FOUNDATION PILE CORROSION 4.6-3 4.6.3 ELIMINATION OF CONTAINMENT PENETRATION COOLERS.............*.4.6-4
4.6.4 AGI NG OF BORAFLEX..*.*.....*...................................................................4.6-5
4.
6.5 REFERENCES
4.6-6
(
Page xiii
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