ML20024G642

Forwards Guidance for Proposed License Amend Re Refueling & Refueling Info Request for Use in Preparing Proposed License Amends So That Submittals Include All Required Info

ML20024G642
Person / Time
Site:	Monticello
Issue date:	06/23/1975
From:	Goller K Office of Nuclear Reactor Regulation
To:	Mayer L NORTHERN STATES POWER CO.
References
NUDOCS 9102130571
Download: ML20024G642 (14)

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Itvel I t rec l er i. t iuclear support Service >

4U. 1,icollet ball Finneapolis, Minnesot a $5401 J

Gent leraen ifRC) to is a cent inuing obicet ive of the Nuclear Regulatory Cornission reviews of all applicat ions f or const ruction pertrit t It trovide co*plete, t ro :.pt

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Corst le t enen ir sart icularly important for proposod licanso e, + enir ( t, - t r.1 t,

t., r e.- r f o r retoelines sicce they of t er. include r siue ranse et crer or e t et nical e peci f iest ion chanres t hat must te develoFe-

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relet, to retoelinrs thz.t ir.vo lve an extensivo nurr.ber of technical specification cheeres.

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1r orJer tc t - ! : es. Ine e t 1 s c u. " :st. c Fcheduling of our reviews of prt eed licerce arend r.e"t ! t hrt relate to ref uelitigts we have prepared a list of the intorr at ion t i. a. t we neeo to forecast the requi renent s for such reviervs, (t.t:

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I n f o re r.t i on i.e qu e s t. T.nelosure 7).

Please subnit t t. is infort et iv-10 voor f oot ic s lo :ccle.r Generettop Plant withtr. 30 days at receipt et annonlly i t.ei e t f t e r. er re o f t e:

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• t hat ref u,*1is r end schedule submit t al dates which realistically reflect out review requirements and your neod for timely licensing action..

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inf orration was approved by CAO unier a blankot for peneric This reJucst clearanco number b-100225 (R0072); this clearance espires July 31, 1977.

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t 1:arl R. Coller, Assi'st ant Director f

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Division of koactor Licensinr 4

Enclosurce:

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Guidance for Prorored License Arendraent e i t i t, t i n, t o f e t ue 1 i nc t w 1i-1r t, e r : t ic-i, ::on t

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a hc :ct t, ce DISTRIBUITON Docket Vlioore ARC PDR TBAbernat.hy Local PDR DEisenhut ORB #2 Reading KRGoller TJCarter DLZiemann BCBuckley I'JiDiggs /cj OELD 01&E (3)

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o Nott.hera States Power Company JUN " r,1975 cc w/o, closures:

Arthur Renquist, Esquire The Environmental Conservation Vice President - Law Library Northern States Power Corpany Minneapolis Public Library 414 Nicollet !!all 300 Nicollet Mall Minneapolis, Minnesota 55401 Minneapolis,l11nnesoin 55401 Gerald Charnoff Shaw, Pittnan, Potts, Trowbridge and Madden 910 - 17t h St reet, N.

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h'ashington, D. C.

20036

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j llouard J. Yorc1, Esquire i

1,cgal Counsel j

2750 Dean l'arl.way l

Minneapolis, Minnesota 55416 f

j Steve Cadler, P. E.

2120 Carter Avu.9e j

St. 1.iul, Mhanc M a 55105

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1)..niel 1.

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As r.i st a nt City Attorney 6*W City JLil 4

i St. Paul, Minno a

55102 1

!!r. I.ennet h P:ut:an l.nvironmental Planning j

Consultant i

St. Paul City Planning i

4 21 lia ba r :." di r e c t I

St. Paul, !linnesota A SI O.:

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Sandra S. Gardebring Special Assistant Attorney General i

Counsel for Minnesota Pollution l

Control Agency l

1935 t'. County I;oad I;?

Ronevill e, "innesot:

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I Anthony ". Roisman, Esquire 1:erlin, 1:oisman and Kessler 1712 N Street, S. ii.

lia t hington, D. C.

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i ENCIhSURE 1 GUIDANCE TOR PROPOSED LICENSE AMENDMENTS RELATING TO REFUELING j

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A.

INTR _0 DUCTION The refueling of a power reactor represents a change in the facility which may involve a change in the technical specifications or i

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Title 10, CFR Part 50, Section 50.59(a)

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j an unreviewed safety question.

permits a licensee to make changes in the facility as described in the j

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i SAR, changes in the procedures as described in the SAR and conduct t

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tests or experiments not described in the SAR without prior Commission i

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approval unless such chsnges involve a change in the technical speci i

The request for fications or involve an unreviewed safety question.

f.

NRC authorization for any such change must include an appropriate safet l

l The format and content of such a SAR is the l

analysis report (SAR).

l subject of this guide.

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B.

DISCUSSION The licensee must demonstrave that safe operation will continue l

Generally, a refueling will involve only changes in with the new core.

Any changes in facility design not' associated with the core loading.

8 the refueling (reload) design and its effect on subsequent operation i

)

Significant changes in fuel should be addressed by a separato document.

a design or reactor control procedures say be addressed by reference i

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to topical reports.

l Two operating cycles or " loads" are of interest in a reload The " reload cycle" is the upcoming cycle, whose safety is submittal.

The " reference cyclo" is.the cycle to which the proposed to be evaluated.

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reload is tc be compared. The appropriate reference cycle is therefore ti.e 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, llowever, 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.

Tne 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.

PJ!GULATOW POSITION Changes in design, analysis techniques, ai.d other information relevant to a reload are'often generic in nature.

Generic information l

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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3 least 90 days before the A reload submittal should be submitted at i

If significant different analytical methods or planned staritp date.

design conc (pis 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 In cases where timing is a problem, there may be f

may be required.

the cases in which the submittal may be provided in sections so that The submittal should contain the following:

staff review can be expedited.

1 Int r o '.uc t.on ar.d Suman

c. f id summarize the content:

Give it.o par}.osc s c.i the submitir the submittal.

2.

Ogeratin? History Discuss any operating anomalies in the current cycle which may It is recognized affect the fuel characteristics in the reload cycle.

I only information from the first part of the cycle will be available.

that 3.

General Description Provide a core loading map for the planned reload core, shqwing Include the position the position, by zone, of new and irradiated fuel.

Show the initial enrichment distribution of of any tett assemblies.

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

actual reload time are acceptabic provided the this plar.ne! map at safety parameters are bounded by the safety finali:ed relaad core':

analysis.

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4.

Fuel Syst e m Derir.n 4.1 f_qe1 De eign The relor d fuel submittal should provide a table that presents i

the following items for both the proposed and the reference cycle fuelt 1

l planned number of relcad and residual assemblies fuel assembly type, I

in the core, initial fuel enrichment, initial fuel density, initial fill For the gas pressure, region burnups at 1400, and clad collapse time.

j loading in TWRs, the liniting region or fuel assemblies based 1

new cort l

on fuci performance consideratier:s should be identified.

I 4.2 Mechanical Desir.n Where fuel assemblies are considered new in concept, the following infornatier. should be providco, by reference or explicitly, for the reload i

1 fuel assemblies:

Tne vibration, flow and structural characteristics including seismic response should be presented. The dimensions and configuration of fuel l

Particular assembly components should be presented in tables and drawings.

attention shoL1d be given to the following itens (1) For Ph'Rs, control rod assembly accommodation and associated operational functions (for example, damping and travel limits).

(2)

Fuel cir4ddirq; reehanical interaction.

(3)

Fuel rod bowing as related to fuel rod axial position and spacer grid ficxibility.

(4)

Steady-state fuel assembly hold-down and lift-off forces.

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. Verification techniques for location and orientation of fuel (5) assemblies in the core.

(6) Specific dimensional or material changes from present approved assemb31es.

(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 satistics such design limits as stress intensity, strain, deflection, collapse, frctting 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, 43 Therra) De r i r.r>

Where fuel assemblies are considered new in concept, fuel thermal performance calculations based on the above mechanical design and the Puel cladding vondor's approved fuel performance model should be provided.

This may integrity and collapse considerations should be included.

be accomplished by suitable reference, i

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. 4.4 Chemice L Dcf;JEn Where fut1 asso.iblics are considered new in concept or utilire component rsterials that diffea from the present design, chemical compatibility of all possible fuel-cladding-coolai.t-assembly interactions should be analyzed.

This may be accomplished by suitable reference.

I 4.5 Operatine Etrerience Previous operating experienec ma related to safety considerations This with compartbic fuel rod /assenbly decicns should be presented.

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I may be accomplished by suitabic reference.

5 NUCLEAR DTSIGN j

5.1 Phyr.ies (hrrpqU?rf titt Providc-inforr,ation regardir.C ar.y changes from the reference cycle to the reload cycle for the following parameters used in the safety analysist J

for B00 EOC, and any extremum during the cycle:

i Moderator Coefficients (e.6., temperature, pressure, density, or (1)

Give or reference the power distributions used in their void.

i development.)

l (2)

Doppler Coefficient (3) Maximum Radial and Axial (or Total) Peaking Factors (4)

Ejected Rod Worth (for PWRs)

(5)

Rod Drep Parameterr (for PVEs)

For D30 and EOC:

(1)

Delayed Neutron Fraction (2) Critical Boron Concentration (for PWEc)

l

. (3)

Boron Wor.h (fo) PWRs)

Standby L quid (ontrol System Worth (for BWRs)

(4)

(5) Scram Tun: tion (for BWRs)

For PWRs, provido, in tabula r 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 BVRs, 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.

S.J An:ilyt i c al inpat tiescribe briefly the information gathered on the burnup history 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 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 relevant to determining important nuclear design paramet ers which depart f, rom prior practice for this reactor, and list This should be done by reference where possibic.

the affected parameters.

Discuss in detail or give a reference describing any significant changes in operational procedure from the reference cycle with regard to axini power shape control, radial power shape control, xenon control, and tilt control.

8 In cases there different ana;ytical cethods are used, detailed information on the new analytical methods for evaluating core neutronic behavior should be supplied, and a ny interfacing between the new and. old methods should be I

described. Th!a should be done b:' reference where possible.

6.

Therral HvcatiLqJesirq In the eve nt there are changes in the fuel geometry, such as spacer l

grid design, sincer 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 chances on:

(a) The rinimum Mbh/Ciif h/CPh values for nomal operation and anticipat es t ran:le nts.

(b) Tne hydraulic stability of the prinary coolant system for ali conditions of steady. state operation, for all operational l

transients including load following maneuvers, and for partiel l

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cr e ra t ic t..

Thir ray be done by appropriate reference.

In cases where different calculational procedures for thermal hydraulic cesi6n are used, these procedures and apprvpriate calculations should bc described or referenced.

7.

Accident cnd Trensient I.nniv ed e The potential effect of any changes in the reload fuel design on listed in the Accident and Transient Analysis section of each incident the reference :ycle a nalysis shot 1d be considered.

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Provic e a totic of the input parnmeters applicabic to all accidents i

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l Thic table or "co. mon" parar.cters should list two colunno 5

and transitnts.

l the limit.ing valuco for the reference cycle and the for each p:rteeter t

i for the rtioni cycle.

limiting nlu(:;

f A second tabic should be provided which lists each accident with its l

The table should also list limiting valuco 5,

accident-specific input parameters.

J, for the referonec cycic and the reload cycle.

In caso an accident input parameter falls outside of bounds previously j

analyzed, provide or reference a re-analysis of the accident.

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Justify any changes from the reference cycle in accident analysis l

If this ic

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techni;urs, caleelttier,a1 n.c thods, correlationc, and codes.

1 an appropriately longer ti.e ref erenec t o a topical report, 4

not d e r.e perjod will t,e required for approval of the reload submittal.

1 Prom'112ii fic;U_( r* t e Teebnical frecifleat ions 1

C.

l the proposed modifications to the Technical Specifications.

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J List and tiriefly deteribe the planned startup tests associated uith 4

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i care perf 3manec.

Feco:~ ended tests include:

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For Nr t.

l Control Rod Drive Teste and Drop Time (Hot)

(1)

(2) Critical Boron Concentration 4

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. (3) control Rod Group Worth (4)

Ejected Rod Worth t

(5) Dropped Rod Worth (6) Moderator Temperature Coefficient (7)

Power Doppler Coefficient I

(B) Startup Power Haps For BWPsi (1) Control Rod Drive Teste and Scram Time (Cold and Hot)

(2)

Shutcown Margin With Host Reactive Rod Withdrawn (3) Patterns for Criticality G

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O ENCLOSURE 2 REFUELING INFORMATION REQUEST _

1.

Name of facility Scheduled date for next refueling shutdown 2.

Schedultd date for restart following refueling f

3.

Will refueling or resumption of operation thereafter req 4.

in general, will these be?

If answer is yes, what, If answtr is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any u.7 reviewed safety questions are associat ed with the core reload (Ref.

10 CFk Section 50.59)?

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

Schiedoled 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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