ML20037B337

Guidance for Proposed License Amends Re Refueling, Draft. Refueling Info Request Encl

ML20037B337
Person / Time
Site:	Dresden
Issue date:	06/23/1975
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20037B336	List: ML20037B335 ML20037B337
References
NUDOCS 8009150607
Download: ML20037B337 (11)

Text

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l ENCLOSURE 1 j

G3 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 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 i

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tests or experiments not described in the SAR without prior Commission approval unless such changes involve a change in the technical speci-f fications or involve an unreviewed safety question. The request for h*RC authori:ation for any such change must include an appropriate safety l

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 l

l 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 separate document.

Significant changes in fuel i

esign or reactor control procedures may be addressed 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.

to be evaluated.

The " reference cycle" is the cycle to which the proposed

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reload is tc be compared. The appropriate reference cycle is i

therefore the cycle which has the most up-to-date, inclusive safety analysis report approved by the Commission.

In most cases, this will

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be the "present", currently operating cycle. However, an applicant l

nay use any cycle or analysis back to the FSAR cycle for reference, if this analysis bounds the parameters of the proposed reload and uses l

currently approved analytical nethods. The various safety analyses may be expedited by such reference if the reload cycle parameter values j

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 l

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.

REGUIATORY 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 l

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 startt:p date.

If significant different analytical methods or design concepts are to be incorporated into the reload core and have net 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 cf the submittal.

2.

Operating History l

Discuss any operating anomalies in the current cycle which may i

l affect the fuel characteristics in the reload cycle.

It is recognized that only information from the first part of the cycle will be available.

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l 3.

General Description Provide a core loading map for the planned reload cere, shqwing l

the position, by :one, of new and irradiated fuel.

Incluce the position l

I of any tert assemblies. Show the initial enrichment distribution of l

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the fresh fuel, the initial burnup distribution, and the burnable poison distribution and concentration (if any).

Deviations from this planned map at actual reload time are acceptable provided the finalized reload core's safety parameters are bounded by the safety analysis.

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Fuel Svru-Desiga 4.1 Fuel resign The rel:Ed fuel submittal should provide a table that presents the following iters 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 EOC, and clad collapse time.

For the new core loading in ?WRs, the limiting region or fuel assemblies based on fuel perfor:ance considerations should be identified.

4.2 Mechanical Desicn 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 asse=bly cenpenents should be presented in tables and drawings.

Particular I

attention shculd be given to the following items:

(1)

For P'r'Es, control rod assembly accommodation and associated operational functioris (for example, damping and travel limits).

(2)

Fuel cladding techanical interaction.

(3)

Fuel red towing as related to fuel rod axial position and spacer grid flexibility.

(4)

Steady-state fuel asse:bly hold-down and lift-off forces.

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Verification techniques for location and orientation of fuel assemelies in the core.

(6)

Specific dimensional or caterial changes from present approved assemblies.

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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 1

new fuel design satisfies such design limits as stress intensity, strain, deflection, collapse, fretting wear and fatigue for all conditions, steady-state, nor:al, and abnormal transients.

Any changes in design limits should be identified and justified.

i Demonstrate by calculation with approved methods or tests that i

I the new fuel design teets the requirements of Appendix K of 10 CFR 50.

43 Thereal Desirn Where fuel asse:blies are considered new in concept, fuel thermal performance calculations based on the above mechanical design and the vendor's approved fuel performance codel should be provided.

Fuel cladding integrity and collapse considerations should be included.

This may

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be accomplished by suitable reference.

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'e~here futi asse blics are censidered new in concept or. utilize component 1

materials tnat differ fro: the present design, chemical compatibility of all possit'e :ue'-cladding-ccolant-assembly interactions should be analyzed.

Tnis may be accc:;11shed by suitable reference.

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4.5 Oceracin-Exrerience

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' Previous operating experience as related to safety considerations t

with cc: parable fuel rod / assembly designs should be presented.

This may be accc:plished by suitable reference.

5.

NUCtEAF DESIG!;

lt l-5.1 Phvsics C.aracteristics Provide information regardir.g any changes from the reference cycle to j

the reload cycle for the following parameters used in the safety analysis:

1 Fer 500, EC:, and any extre=um during the cycle:

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(1) Mcderator Ccefficients (e.g., temperature, pressure, density, or void.

Give er reference the power distributions used in their develeprent.)

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(2) Doppler Coefficient (3) Maximun Radisl and Axial (or Total) Peaking Factors I

(t) Ejected Ecd Werth (for PWRs)

(5) Red Crep Paraceters (for SURs)

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(1) Delayed Neutren Fraction c

(2) Critical Boron Concentration (for PWRs) s t

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Boron Worr.h (for PhRs)

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Standby L; quid Control System Worth (for BhRs) 4 m

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Scram Function (for BWRs?

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,'y For PWRs, provide, in tabuitr foEm, a detfiled calculation of the

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shutdown margin for the BOC and EOC and any mid-cycle mini:ium of the '

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reference and reload cycles'. Thii table should also indicat,e the required '7,

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N-margin.

ForBhRs,providetheshLtd$amargincurve.,

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,,e For PWRs, specify the control ro'd patterns to be used during the

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reload cycle, including any rod interchanges and;cny' differ'tices from. he;

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a reference cycle.

A 5.2 Analytical Input V-

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l Describe briefly the information gathered on the burnup history of theI

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exposed fuel, and how it was used-in the reload analysis only if' required,

to support reload design changes. This_ pay be'done by reference.

Indiccte how the incore measurement calculation constants (or matrices) to be used, in calculating bundle powers were' prep'ared for.'the reload cycle. This 7 r

may be done by reference.

5.3 Changes in Nuclear Design Describe any changes in core design features, calculational method's.'

data or information relevant to detemining important nuclear design parameters which depart from prior practice for this reactor, and list.

This should be done by reference where possible.

the affected parameters.

Discuss in detail or give a reference describing any significant chatZes in operational procedure from the reference cycle with regard to axial _ -

power shape control, radial power shape control, xenon contio1,'and tilt' o

control.

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on the' new aga}f tici;l methods for evaluating core neutronic behavior should be

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l supplied,' and Eny",ir':,erfacing between the new andi old methods should be

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uescribed. -TM s should be done by reference where possible.

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6. 'Therr d? jraulie Desinn

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A, In the,, event there are changes in the fuel geometry, such as spacer qf,

er grid desi'hrf$'hpacer g~ rid axial separation, fuel pin spacing, or of the fuel i

pin or control rod;5ulde tube; or if there are changes in the radial or

,o axial design pcuer dstributions of the core, evaluate the effects of these

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changes,en:

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(s)i. The vinhum-;DNBR/CHFR/CPR values for normal operation and j

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l anticipated transients.

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3 (b) Thd fiydraulic stability of the primary coolant system for all l

conditions of steady-state operation, for all operational

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trar sients including load following maneuvers, and for partial i

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loop operation.

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In c?.ses where different calculational procedures for ther=al hydraulic i

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desiC'iaheused,theseproceduresandappropriatecalculationsshouldbe r

descrioed or. referenced.

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Accident a*1d Transient Analysis The potential effect of any changes in the reload fuel design on

.each incident listed in the Accident and Transient Analysis section of

< the reference cycle analysis shot id be considered.

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Irovice a -table of the input parancters applicable v3 all accicents and traraients.

This table o' "connon" parancters should list two colunns f6r each p: raneter:

the lin'i;in'; values for the r'eference cycle and the liciting vtlues for the reIcod cycle.

A second table should be provided which lists each accident with its 9

accident-specific input parameters.

The table should also list limiting values for the reference cycle and the reload cycle.

In case an accident input parametcr falls outside of bounds previously analyzed, provide or reference a re-analysis of the accident.

Justify any changes frca the reference cycle in accident analysis If this i:

techniques, calculational methods, correlations, and codes.

not donc by reference to a topical report, an appropriately longer time periodwillberequiredforapprovalofthereloadsubmittal.

8.

Paer; sed Modifications te Technical Srecifications Present the proposed nodifications to the Technical Specifications. ~

Justify the changes.

9 Etartun Freera, List and briefly describe the planned startup tests asscciated uith core performance.

Recorrended tests include:

For PWFs:

(1)

Cc6 trol Rod Drive Tests and Drop Time (Hot)

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(2)

Critical Boron Concentration

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1 (3) Cor. trol Rod Group Worth (4)

Ejected Rod Worth

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Dropped Rod Worth (6) Moderator Temperature Coefficient i

(7)

Power Doppler Coefficient (8) Startup Power Maps For B'a'Rs:

l (1) Control Rod Drive Tests and Scram Time (Cold and Hot) l (2) Shutdown Margin With Most Reactive Rod Withdrawn (3)

Patterns for Criticality I

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ENCLOSURE 2 REFUELING INFORMATION REQUEST 1.

Name of facility Schedulcd date for next refueling shutdown

-2.

Scheduled date for restart following: refueling 3.

h'ill 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?

l If answer is no, has the reload fuel design and core t

configuration been reviewed by your Plant Safety Review Committee to deternine whether any unreviewed safety I

questions are associated with the core reload (Ref.

10 CFR Section 50.59)?

l If no such review has taken place, when is it scheduled?

Scheduled date(s) for submitting proposed licensing action and 5.

l supporting information licensing considerations associated with refueling, e.g.,

Important 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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