ML20002C642
| ML20002C642 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/23/1975 |
| From: | Goller K Office of Nuclear Reactor Regulation |
| To: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8101100641 | |
| Download: ML20002C642 (14) | |
Text
....
's Jun 231975 Docket bo. 50-155 o
Consuzers Power Company
'ATTh:
Pr. Ralpi E. Sewell t.uclear Licensing Administrator 212 West hichiran Avenue Jackson, Hichigan 49201 Centleren:
is a continuing objective of the Nuclear kegulatory Commission (NLC) to Itprovide cotplete, prompt reviews of all applications for construction permits, operating 1; censes and license amendments.
The length of time necessary to act upon such applications is, to a large extent, a function of the corpleteness of the information supplied by the licensee in support of it s application.
Coepleteness is particularly important for proposed license amendnents that relate to reactor refuelings since they of ten include a wide range of proposed technical specification changes that must be developed and approved before the facility can return to operation.
The hhc has developed preliminary Fuidance (Enclosure 1) f or use in preparint proposed license amendnents that relate to refuelings that may help to assure that ycur submit t als vill include all required inf ormation.
Arother related problem is that of lateness of licensee subrittels which reke it dif ficult and sometir;es impossibic for the staff to corplete its review in time to accommodate scheduled dates for resumpt ion of operat ion.
Thie problem becomes particularly dif ficult for license amendments that relete to refuelings that involve an extensive number of technical specification changes. Moreover, the growing number of operating f acilit ies request ing such license amendments is taxint the st af f's ability to acconrodete individual schedules, unless the requests are submitted with adequate tire for review.
Ir order to improve the ef ficacy anc scheduling of our reviews of proposed license en.endments that relate to ref ueliDFs we have prepared a list of the intoreation that we need to forecast the requirenents for such reviess, (ref ueline Informat ion Fequest, Enclosure 2).
Please submit this intorretion for your Dir Fock Foint Plant within 30 days of receipt of this letter and update this inf ormation annually thereaf ter, or more of ten if appropriate. We suggest that this inf ormat ion be made a regular part of your annual operst ic; report.
P00ROR.IG.f,INM 81011006.41 t
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l Form AEC.31s (Rev. 9 53) AEcM 0240 W u. s. eovsam.snt paintine orrecs: sers.ase-see
JUN 2 31975 Ce ssumers Power Company 2-with this information we can assess your plans f or It is'our hope that ref uelinr and schedule subesit tal dates which realist ically reflect our review requirements and your need f or timely licensing act'".
for generic infortnation was apprcved by GAO under a blanket 1
- 1977, clearance number B-180225 (R0072); this clearat.ce expires July 3,
This r.. quest Sincerely, Originnisigced by:
KarlR. Goller Karl R. Goller, Assist ant Director for Operating Reactors Division of Reactor Licensing d
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Enclosures:
i 1.
Guidance for Proposed License Amende:ent s Relatir-g to Ref ueling 2.
Refueling Inforestion Eequest ec: w/encls See next page DISTRIBLTION Docket VHoore JRCPDR TBAbernathy Local PDR DEisenhut i
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Consumers ' Power Coi, any' Jgg i' ; 1373, c
cc w/ enclosures:
Mr. Paul A. Perry, Secretary
. Consumers Power. Company' 212 West. Michigan Avenue Jackson, Michigan 49201 Peter W. ' Steketec, Esquire
' Freihofer, Cook, Hecht, Oosterhouse and be Boer Union Bank Building, Suite.950
- Grand Rapids, :lichigan 49502 e
George C. Freeman, J'r., Esquire llunton, Williams, Gay & Gibson 700 East Main Street Richmond, Virginia 23212 Charles F. Bayless.
Of Counsel Consumers. Power Company
-212 West Michigan Avenue Jackson.. Michigan 49201 Anthony Z. Roisman, Esquire.
Berlin, Roisman and Kessler
'1712 N Street, N. W.
Washington,- D. C.
20036 Charlevoix Public Library 107 Clinton Street Charlevoix, Michigan 49720 O
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h ENCLOSURE 1 GUIDANCE FOR PROPOSED LICENSE AMENDMENTS RELATING TO REFUELING A.
INTRODUCTION The refueling of a power reactor represents a change in the facility which may involve a change in the technical specifications or an unreviewed safety question. Title 10, CFR Part 50, Section 50.59(a) permits a licensee to make changes in the facility as described in the SAR, changes in the procedures as described in the SAR and conduct tests or experiments not described in the SAR without prior Comission approval unless such changes involve a change in the technical speci-fications or involve an unreviewed safety question. The request for NRC authorization for any such change must include an appropriate safety analysis report (SAR). The format and content of such a SAR is the subject of this guide.
B.
DISCUSSION The licensee must demonstrate that safe operation will continue Generally, a refueling will involve only changes in with the new core.
the core loading.
Any changes in facility design not associated with the refueling (reload) design and its effect on subsequent operation should be addressed by a separato document. Significant changes in fuel design or reactor control procedures may be addressed by reference to topical reports.
l Two operating cycles or " loads" are of interest in a reload l-The " reload cycle" is the upcoming cycle, whose safety is l
submittal.
to be evaluated. The " reference cycle" is the cycle to which the proposed
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s reload is to be compared. The appropriate reference cycle is therefore the cycle which has the most up-to-date, inclusive safety analysis report approved by the Commission.
In most cases, this will be the "present", currently operating cycle. However, an applicant may use any cycle or analysis back to the FSAR cycle for reference, if this analysis bounds the parameters of the proposed reload and uses
. currently approved analytical methods. The various safety analyses may be expedited by such reference if the reload cycle parameter values are bounded by the reference cycle values.
The amount of detailed analysis required in any submittal depends on the type of reload. For equilibrium cycle reloads, where mechanical design and enrichment do not change it is expected that accident parameters will remain within their previously analyzed ranges and a reanalysis may not be required.
Conversely, for non-equilibrium cycle reloads, the thermal and nuclear characteristics generally require new analysis and a full evaluation. When a reload involves different analytical methods or design concepts, a complete r.eview of these changes and their effects is necessary.
C.
REGULATORY POSITION Changes in design, analysis techniques, and other information relevant to a reload are often generic in nature. Generic information may be provided by reference to generic report rather than giving explicit. justification in a reload SAR for a specific plant.
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\\ A reload submittal should be submitted at least 90 days before the planned starttip date.
If significant different analytical methods or design concepts are to be incorporated into t?e reload core and have not been justified by generic review or if the cha nges otherwise entail a significant hazards consideration, a significantly greater time period may be required.
In cases where timing is a problem, there may be cases in which the submittal may be provided in sections so that the staff review can be expedited. The submitt: 1 should contain the following:
1.
Introduction and Sur. mary Give the purposes of the submittal and summarize the contents of the submittal.
2.
Operating 111 story Discuss any operating anomalies in the current cycle which may affect the fuel characteristics in the reload cycle.
It is recognized that only information from the first part of the cycle will be available.
3.
General Description Provide a core loading map for the planned reload core, shqwing the position, by zone, of new and irradiated fuel.
Include the position of any tett assemblies. Show the initial enrichment distribution of the fresh fue'., the initial burnup distribution, and the burnable Deviations from poison distribution and concentration (if any).
this planned map at actual reload time are acceptable provided the finnlized-reload core's safety parameters are bounded by the safety analysis.
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6 4-4.
Fuel System Desic.a 4.1 Fuel Design The reloed fuel submittal should provide a table that presents the following items for both the proposed and the reference cycle fuel:
fuel assembly type, planned number of reload and residual assemblies in the core, initial fuel enrichment, initial fuel density, initial fill gas pressure, region burnups at BOC, and clad collapse time.
For the new core loading in PWRs, the liniting region or fuel assemblies based on fuel performance considerations should be identified.
4.2 Mechanical Desinn Where fuel assemblies are considered new in concept, the following information should be provided, by reference or explicitly, for the reload fuel assemblies:
The vibration, flow and structural characteristics including seismic response should be presented. The dimensions and configuration of fuel assembly components should be presented in tables and drawings. Particular attention should be given to the following items:
(1) For PWRs, control rod assembly accommodation and associated operational functions (for example, damping and travel limits).
(2)
Fuel cladding mechanical interaction.
(3) Fuel rod bowing as related to fuel rod axial position and spacer grid flexibility.
(4) Steady-state fuel assembly hold-down and lift-off forces.
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(5) Verification techniques for location and orientation of fuel assembljes ia the core.
(6) Specific dimensional or material changes from present approved assemblies.
(7) Design of spacer grids as related to local flow effects, DNB considerations, and mechanical strength and integrity of the assembly.
Demonstrate by calculation with approved methods or tests that the new fuel design satisfies such design limits as stress intensity, strain, deflection, collapse, fretting wear and fatigue for all conditions, steady-state, normal, and abnormal transients.
Any changes in design limits should be identified and justified.
Demonstrate by calculation with approved methods or tests that the new fuel design meets the requirements of Appendix K of 10 CFR 50.
4.3 Thermal Desinn Where fuel assemblies are considered new in concept, fuel thermal performance calculations based on the above mechanical design and the vendor's approved fuel performance model should be provided.
Fuel cladding integrity and collapse considerations should be included. Tnis may be accomplished by suitable reference.
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t 4.4 Chemical _ Design Where fuel assesblies are considered new in concept or utilize component materials that differ from the present design, chemical compatibility of all possible f uel-cladding-coolant-assembly interactions should be analyzed.
This may be accomplished by suitable reference.
4.5 Operatinn Experience Previous operating experience as related to safety considerations with comparable fuel rod / assembly designs should be presented. This may be accomplished by suitable reference.
5 NUCLEAR DESIGN 5.1 Physics Characteristics Provide information regarding any changes from the reference cycle to the reload cycle for the following parameters used in the safety analysis:
For BOC, EOC, and any extremum during the cycle:
(1) Moderator Coefficients (e.g., temperature, pressure, density, or void. Give or reference the power distributions used in their development.)
(2) Doppler Coefficient (3) Maximum Radial and Axial (or Total) Peaking Factors (4)
Ejected Rod Worth (for PWRs)
(5)
Rod Drop Parameters (for BWRs)
For BOC and EOC:
(1) Delayed Neutron Fraction (2) Critical Boron Concentration (for PWRs) 4 y
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(4) Standby Liquid Control System h' orth (for BKRs)
For PWRs, provide, in tabular form, a detailed calculation of the shutdown margin for the BOC and EOC and any mid-cycle minimum of the This table should also indicate the required reference and reload cycles.
margin.
For BNRs, provide the shutdown margin curve.
For PWRs, specify the control rod patterns to be used during the reload cycle, including any rod interchanges and any differences from the reference cycle.
5.2 Analytical Input _
Describe briefly the information gathered on the burnup history of the exposed fuel, at? how it was used in the reload analysis only if required to support reload design changes. This may be done by reference.
Indicate how the incore measurement calculation constants (or matrices) to be used in calculating bundle powers were prepared for the reload cycle. This,
may be done by reference.
5.3 Changes in Nuclear Design Describe any changes in core design features, calculational methods, data or information rele. ant to detenmining important nuclear design parameters which depart f, rom prior practice for this reactor, and lisc This should be done by reference where possible.
the affected parameters.
Discuss in detail or give a reference describing any significant changes in operational procedure from the reference cycle with regard to axial power shape control, radial power shape control, xenon control, and tilt control.
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-8 In cases khere different analytical methods are used, detailed information on the new analytical methods for evaluating core neutronic behavior should be supplied, and any interfacing between the new andiold methods should be t
This should be done by reference where possible.b dtscribed.
6.
Thernal Hveraulic Desinn In the event there are changes in the fuel geometry, such as spacer grid design, s;acer grid axial separation, fuel pin spacing, or of the fuel pin or control rod guide tube; or if there are changes in the radial or axial design pcwer distributions of the core, evaluate the effects of these changes on:
(a) The einimum DNBR/CHFR/CPR values for normal operation and anticipated transients.
(b) The hydraulic stability of the primary coolant system for all conditions of steady-state operation, for all operational transients including load following maneuvers, and for partial i
loop operation.
This may be done by appropriate reference.
'n cases where different calculational procedures for tLermal hydraulic design are used, these procedures and appropriate calculatio,ns should be described or referenced.
7 Accident and Transient Analysis The potential effect of any changes in the reload fuel design on each incident listed in the Accident and Transient Analysis s,ection of the reference cycle analysis sherid be considered.
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. Provice a table of the input parameters applicable to all accidents and transients. This table of " common" parameters should list two colunna for cach pt rameter:
the limiting values for the reference cycle and the limiting vtlues for the reload cycle.
A second table should be provided which lists each accident with its accident-specific' input parameters. The table should also list limiting values for the reference cycle and the reload cycle.
In case an accident input parameter falls outside of bounds previously
. analyzed, provide or reference a re-analysis of th.e accident.
Justify any changes from the reference cycle in accident analysis If this is to'chniques, calculational methods, correlations, and codes.
not done by reference to a topical report, an appropriately longer tino P
period will be required for approval of the reload submittal.
8.
Proposed flodifications to Technical Scecifications Present the proposed modifications to the Technical Specifications.
Justify the changes.
9 f,tartun Pronram List and briefly describe the planned startup tests associated uith core performance.
Recommended tests include:
For PWRs:
(1) Control Rod Drive Tests and Drop Time (Hot)
(2) Critical Boron Concentration J
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(3) Control Rod Group Worth (4) Ejected Rod Worth (5) Dropped Rod Worth (6) Moderator Temperature coefficient (7)
Powe' loppler Coefficient (8) Startup Power Maps Ihr BWRs:
(1) Coiidrol Rod Drive Tests and Scram Time (Cold and Hot)
(2) Shutdown Margin With Most Reactive Rod Withdrawn (3) Patterns for Criticality e
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q ENCLOSURE 2 REFUELING INFORMATION REQUEST 1.
Name of facility Scheduled date for next refueling shutdown 2.
Scheduled date for restart following refueling 3.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
4.
If answer is yes, what, in general, will these be?
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref.
10 CFR Section 50.59)?
If no such review has taken place, when is it scheduled?
Scheduled date(s) for submitting proposed licensing action and 5.
supporting information Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or 6.
performance analysis methods, significant changes in fuel design, new operating procedures.
9
^
t ENCLOSURE 1 GUIDANCE FOR PROPOSED LICENSE AMENDMENTS RELATING TO REFUELING
.A.
IhTRODUCTION The refueling of a power reactor represents a change in the facility which may involve a change in the technical specifications or an unreviewed safety question. Title 10, CFR Part S0, Section 50.S9(a) permits a licensee to make changes in the facility as described in the SAR, changes in the procedures as described in the SAR and conduct tests or experiments not described in the SAR without prior Commission approval unless such changes involve a charge in the technical speci-fications or involve an unreviewed safety question. The request for NRC authorization for any such change must include an appropriate safety analysis report (SAR). The format and content of such a SAR is the subject of this guide.
B.
DISCUSSION The licensee must demonstrate that safe operation will continue Generally, a refueling will involve or.ly changes in with the new core.
the core loading. Any changes in facility design not associated with the refueling (reload) design and its effect on subsequent operation should be addressed by a separate document. Significant changes in fuel design or reactor control procedures may be ad ressed by reference to topical reports.
Two operating cycles or " loads" are of interest in a reload The " reload cycle" is the upcoming cycle, whose safety is submittal.
The " reference cycle" is the cycle to which the proposed to be evaluated.
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reload is te be compared. The appropriate reference cycle is therefore the cycle which has the most up-to-date, inclusive safety analysis report approved by the Commission.
In most cases, this will be the "present", currently operating cycle. However, an applicant may use any cycle or analysis back to the FSAR cycle for reference, if this analysis bounds the parameters of the proposed reload and uses currently approved analytical methods. The various safety analyses may be expedited by such reference if the reload cycle parameter values are bounded by the reference cycle values.
The amount of detailed analysis required in any submittal depends on the type of reload. For equilibrium cycle reloads, where mechanical design and enrichment do not change it is expected that accident parameters will remain within their previously analyzed ranges and a reanalysis may not be equired.
Conversely, for non-equilibrium cycle reloads, the thermal ar.d nuclear characteristics generally require new analysis and a full evaluation. When a reload involves different analytical metheds or design concepts, a complete r.eview of these changes and their effects is necessary.
C.
REGULATORY POSITION Changes in design, analysis techniques, and other information relevant to a reload are often generic in nature. Generic information may be provided by reference to generic report rather than giving explicit justification in a reload SAR for a specific plant.
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- q. A reload submittal should be submitted at least 90 days before the planned startup date.
If significant different analytical methods or design concepts are to be incorporated into the reload core and have not been justified by generic review or if the changes otherwise entail a significant hazards consideration, a significantly greater time period may be required.
In cases where timing is a problem, there may be cases in which the submittal may be provided in sections so that the staff review can be expedited. The submittal should contain the following:
1.
Introduction and Summary Give the purposes of the submittal and summarize the contents of the submittal.
J 2.
Operating History Discuss any operating anomalies in the current cycle which may affect the fuel characteristics in the reload cycle.
It is recognized that only information from the first part of the cycle will be available.
3.
General Description Provide a ccre loading map for the planned reload core, shqwing the position, by zone, of new-and irradiated fuel.
Include the position of any tett assemblies. Show the initial enrichment distribution of the fresh fuel, the initial burnup distribution, and the burnable Deviations from poison distritution and concentration (if any).
this planned map at actual reload time are acceptable provided the finalized reload core's safety parameters are bounded by the safety analysis.
l
l 4
4.
Fuel System Desir;n 4.1 Fuel Design The reload fuel submittal should provide a table that preseats the following items for both the proposed and the reference cycle fuel:
fuel assembly type, planned number of reload and residual assemblies in the core, initial fuel enrichment, initial fuel density, initial fill gas pressure, region burnups at BOC, and clad collapse time.
For the new core loading in PWRs, the limiting region or fuel assemblies based on fuel performance considerations should be identified.
4.2 Mechanical Dosinn Where fuel assemblies are considered new in concept, the following information should be provided, by re carence or explicitly, for the reload fuel assemblies:
The vibration, flow and structural characteristics including seismic response should be presented. The dimensions and configuration of fuel assembly components should be presented in tables and drawings. Particular attention should be given to the following items:
(1) For PWRs, control rod assembly accommodation and associated operational functions (for example, damping and travel limits).
(2)
Fuel cladding mechanical interaction.
(3) Fuel rod bowing as related to fuel rod axial position and spacer grid flexibility.
(4) Steady-state fuel assenbly hold-down and lift-off forces,.
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. (5) Verification techniques for location and orientation of fuel assemblies in the core.
(6) Specific dimensional or material changes from present approved assemblies.'
(7) Design of spacer grids as related to local flow effects, DNB considerations, and mechanical strength and integrity of the assembly.
Demonstrate by calculation with approved methods or tests that the new fuel design satisfies such design limits as stress intensity, strain, deflection, collapse, fretting wear and fatigue for all conditions, steady-state, normal, and abnormal transients.
Any changes in design
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limits should be identified and justified.
Demonstrate by calculation with approved methods or tests that the new fuel design meets the requireaents of Appendix K of 10 CFR 50.
4.3 Thermal Desinn Where fuel assemblies are considered new in concept, fuel thermal performance calculations based on the above mechanical design and the vendor's approved fuel performance model should be provided.
Fuel cladding integrity and collapse c37siderations should be included. This may be accomplished by suitable reference.
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- 4.4 Chemical Desian Where fuel assesblics are considered new in concept or utilize component materials that differ from the present design, chemical compatibility of all possible fuel-cladding-coolant-assembly interactions should be analyzed.
This may be accomplished by suitable reference.
4.5 Operating Experience Previous operating experier.ce as related to safety considerations with comparable fuel rod / assembly designs should be presented. This may be accomplished by suitable reference.
5.
NUCLEAR DESIGN 5.1 Physics Characteristics Provide information regardin6 any ' changes from the reference cycle to the reload cycle for the following parameters used in the safety analysis:
For BOC, EOC, and any extremum during the cycle:
(1) Moderator Coefficients (e.g., temperature, pressure, density, or void. Give or reference the power distributions used in their l-development.)
(2) Doppler Coefficient (3) Maximum Radial and Axial (or Total) Peaking Factors I
(4) Ejected Rod Wotth (for PWRs)
(5) Rod Drop Paramettes (for BWRs)
For BOC and EOC:
(1) Delayed Neutron Fraction (2) Critical Boron Concentration (for PWRs) g r
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. (3)
(4) Standby Liquid Control System h' orth (for BWRs)
(5) Scram Function (for BNRs)
.For PWRs, provide, in tabulsr form, a detailed calculation of the shutdown margin for the BOC and EOC and any mid-cycle minimum of the This table should also indicate the required reference and reload cycles.
margin. For B4'Rs, provide the shutdown margin curve.
For PWRs, specify the control rod patterns to be used during the reload cycle, including any rod interchanges and any differences from the reference cycle.
5.2 Analytical Input Describe'briefly the information gathered on the burnup histery of the exposed fuel, and how it was used in the reload analysis only if required to support reload design changes. This may be done by reference. Indicate how the incore measurement calculation constants (or matrices) to be us f n calculating bundle powers were prepared for the reload cycle. This,
may be done by reference.
5.3 Changes in Nuclear Design Describe any changes in core design features, calculational methods,
' data or information relevant to determining important nuclear design parameters which depart from prior practice for this reactor, and list This should be done by reference where possible.
the a tfected parameters.
Discuss in detail or give a reference describing any significaat changes in operational procedure from the reference cycle with regard to axial power shape control, radial power shape control, xenon control, and tilt control.
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< In cases there different analytical methods are used, detailed information on the new analytical methods for evaluating core neutronic behavior should be supplied, and any interfacing between the new andiold methods should be b
described. Th$s should be done by reference where possible.I' 6.
Thermal Hydraulic Desirm In the event there are changes in the fuel geometry, such as spacer grid design, spacer grid axial separation, fuel pin spacing, or of the fuel pin or control rod guide tube; or if there are changes in the radial or axial design pcwer distributions of the core, evaluate the effects of these changes on:
(a) The minimum DNBR/CHFR/CPR values fn.c normal operation and anticipated transients.
(b) The hyder alic stability of the primary coolant system for all cond'. ions of steady-state operation, for all operational transients including load following maneuvers, and for partial loop operation.
This may be done by appropriate reference.
In cases where different calculational procedures for thermal hydraulic design are used, these procedures and appropriate calculatio.ns should be described or referenced.
7.
Accident and Transient Analysis The potential effect of any changes in the reload fuel design on each incident listed in 'he Accident and Transient Analysis section of the reference cycle antaysis should be considered.
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9-Provice a table of the input parameters applicable to all accidents and transients.
This table of " common" parameters should list two colunna for each ptrameter:
the limiting values for the reference cycle and the limiting vtlues for the reloa.1 cycle.
A second table should be provided which lists nach accident with its accident-specific. input parameters. The table should also list limiting values for the reference cycle and the reload cycle.
In case an accident input parameter rails outside of bounds previously analyzed, provide or reference a re. analysis of th.e accident.
Justify any changes from the reference cycle in accident analysis If this is te'chniques, calculational methods, correlations, and codes.
not done by reference to a topical ceport, an appropriately longer timo period will b required for approval of the reload submittal.
8.
Proposed Modifications to Technical Specifi ations Present the proposed modifications to the Technical Specifications.
Justify the changes.
9 Startun Procram List and briefly describe the planned startup tests associated uith core perf5rmance.
Reevmmended tcsts include:
For PWRs:
(1) Control Rod Drive, Tests and Drop Time (Hot)
(2) Critical. Boron Concentration 9
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. i (3) Control Rod Group Worth (4) Ejected Rod Worth (5) Dropped Rod Worth (6) Moderator Temperature Coefficient (7)- Power Doppler Coefficient (8) Startup. Power Maps For BWRs:
(1) Control Rod Drive Test.s and Scram Time (Cold and Hot)
(2) Shutdown Margin With M st Reactive Rod Withdrawn (3)
Patterns for Criticalit o
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l ENCLOSURE 2 REFUELING INFORMATION REQUEST _
1.
Name of facility Scheduled date for next refueling shutdown 2.
. Scheduled date for restart following refueling 3.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
I 4.
If answer is yes, what, in general, will these be?
If answer is no, has'the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref.
10 CFR Section 50.59)?
If no such review has taken place, when is it scheduled?
Scheduled date(s) for submitting proposed licensing action and 5.
supporting information Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or 6.
performance analysis methods, significant changes in fuel design, new operating procedures.
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