ML20212C096

Proposed ITS & Bases Changes Strikeout & Shadowed Text & Revision Bar Format,Increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revising Configuration for Storage of Fresh Fuel

ML20212C096
Person / Time
Site:	Crystal River
Issue date:	09/16/1999
From:	FLORIDA POWER CORP.
To:
Shared Package
ML20138D882	List: 3F0999-07, Application for Amend to License DPR-72,to Change ITS Proposed in LAR 239,rev 0,increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revise Configuration for Storage of Fresh Fuel.Proprietary Encl Withheld ML20212C096 ML20212C099 ML20212C112 ML20212C135 ML20212C150
References
NUDOCS 9909210132
Download: ML20212C096 (33)

Text

,

D FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 ATTACHMENT B LICENSE AMENDMENT REQUEST # 239, REVISION 0 Proposed Improved Technical Specifications and Bases Changes i

Strikeout and Shadowed Text i

Text Being Added Indicated by Shadowed Text Text Being Deleted Indicated by Strikeout Text 732'"18e23s83Mo2 e,..P

,PDR i

Spant Fuel Pool Boron Concentration 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Spent Fuel Pool Boron Concentration LCO 3.7.14 The spent fuel pool boron concentration shall be 21925 ppm.

t APPLICABILITY:

When fuel assemblies are stored in the spent fuel pool and a spent fuel _ pool verification has not been performed since the last movement of fuel assemblies in the spent fuel pool.

I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Spent fuel pool boron

---

NOTE------------

concentration not LCO 3.0.3 is not applicable.

Within limit.

A.1 Suspend movement of Immediately fuel assemblies in the spent fuel pool.

AND A.2.1 Initiate action to Immediately restore spent fuel pool boron concentration to within limit.

08 A.2.2 Verify by Immediately j

administrative means a Storage Pool A and

)

Storage Pool B, Regi e spent fuel pool verification has been performed since the last movement of i

fuel assemblies in the spent fuel pool.

Crystal River Unit 3.7-28 Amendment No. 149

Spent Fuel Assembly Storage 3.7.15 3.7 PLANT SYSTEMS 3.7.15 Spent Fuel Assembly Storage LCO 3.7.15 The combination of initial enrichment and burnup of each spent fuel assembly stored in Storage Pool A and Storage Pool B, shall be within the acceptable region of Figure 3.7.15-1 66 Figure.3.7.15-2. Figure 3.7.15-3, er stored in accordance with the ISAR.

4 APPLICABILITY:

Whenever any' fuel assembly is stored in Storage Pool A or Storage Pool B of the spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Requirements of the A.1

---

NOTE--------

LCO not met.

LCO 3.0.3 is not applicable.

Initiate action to Immediately move the noncomplying i

fuel assembly to an acceptable configuration.

Crystal River Unit 3 3.7-30 Amendment No. 151

i L

b Spent Fuel Assembly Storage 3.7.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify by administrative means the initial Prior to enrichment and burnup of the fuel assembly storing the is in accordance with Figure 3.7.15-1 on fuel assembly Figure 3.7.15-2. Figure 3.7.15-3,-cr in in Storage Pool accordar.cs with the ISAR.

A or Storage Pool B.

t Crystal River Unit 3 3.7-31 Amendment No. 1H

Spent Fuel Assembly Storage 3.7.15 MINIMUM BURNUP REQUIRED FOR "A"

POOL STORAGE Minimum Burnup vs Initial Enrichment NOTE: ~ 0ne-out-of-two' checkerboard loading with empty cells allowed for any combination of enrichment and burnup.

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3.8 3.5 4.0 4.5 5.9 Initial Enrichment; Weight Percent U235 Figure 3.7.15-1 fpage-1-of-3) l Burnup versus Enrichment Curve for Spent Fuel Storage Pool A Crystal River Unit 3 3.7-32 Amendment No.1H

)

Spe.nt Fuel Assembly Storage 3.7.15 MINIMUM BURNUP REQUIRED FOR REGION-1-OF "B" POOL STORAGE Minimum Burnup vs Initial Enrichment Burned-Fuel-itt-checkerboard Configurat-ica with 5.0 wt% Fresh-Fuel 35.0 30.0 e

o ACCENT-ABIErFOR4TORAGFrAIMACFNT TO FRECH FUEL WT4M-FNRIGHMFNT 25.0-3 m.Te WHEN ASOYE AN!)TO THE 7

LE!"r OF CURVE 20.0-EXISTING CURVE 15.0 REPLACED WITH

'N TWO DIFFERENT CURVES BASED ON 10 0 REVISED VALUES.

NEWNOTESADDED 5.0 TO FIGURE.

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0.0 l

2.0 2.5 3.0 3.5 4.0 4.5 5.0 WtW Errichment, wt% U235 Figure 3.7.15-2 (page 2 of -3)

Burnup versus Enrichment Curve for Spent Fuel Storage. Pool BT-Region-1 Crystal River Unit 3 3.7-33 Amendment M1

Spent Fuel Assembly Storage 3.7.15 1

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Figure 3.7.15-2 Burnup versus Enrichment Curve for Spent Fuel Storage Pool B Crystal River Unit 3 3.7-33 Amendment 151

Spent Fuel Assembly Storage 3.7.15 MINIMUM-BURNUP-REQUIRED-FOR REGION-2-Of "B M 006 Hinimum-Burnup-vs-Initi & Enrichment FIGURE DELETED 45

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Burnup-versus-Entithment-Ctrvt d r Spent fuel Storage roci 0,- Region-2 FIGURE DELETED Crystal River Unit 3 3.7-33A Amendment 151

Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent; l

b.

k s 0.95 if fully flooded wit' unborated water, I

wN'ich includes an allowance Ior uncertainties as described in Section 9.6 of the FSAR; l

c.

A nominal E-6 9.11 inch center to center distance between fuel assemblies placed in Region 1 of the B pool; tb A nominal ^.17 inch center to center-di-stance-between fttel-assembHes placed in Region 2 of the O poci; and

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d.7 e-A nominal 10.5 inch center to center distance between fuel assemblies placed in the A pool.

4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent; l

b.

k s 0.95 is fully flooded with unborat' d water, e

wN'i ch includes an allowance for uncertainties as described in Section 9.6 of the FSAR; k,,,ludes an allowance for uncertainties as described s 0.98 if moderated by aqueous foam, which c.

inc in Section 9.6 of the FSAR; and d.

A nominal 21.125 inch center to center distance between fuel assemblies placed in the storage racks.

(continued) j Crystal River Unit 3 4.0-2 Amendment No. El

Dmsign Features 4.0 4.0 DESIGN FEATURES (continued) 4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 138 feet 4 inches.

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1357 1474 fuel assemblies and six failed fuel containers.

Crystal River Unit 3 4.0-3 Amendment No. 149

Spent Fual Pool Boron Concentration B 3.7.14 8 3.7 PLANT SYSTEMS B 3.7.14 Spent Fuel Pool Boron Concentration BASTES BACKGROUND As described in the Bases for LCO 3.7.15, " Spent Fuel Assembly Storage," fuel assemblies are stored in the high-density region of the spent fuel pool storage racks in accordance with criteria based on initial weight-percent enrichment-and discharge burnup. Although the water in the spent fuel pool is normally borated to 2 2000 ppm, the criteria that limit the storage of a fuel assembly to specific rack locations (criticality analysis) are conservatively developed without taking credit for the boron in the pool water.

APPLICABLE The acceptance criteria for the fuel storage pool SAFETY ANALYSIS criticality analyses is that a k,,,of < s 0.95 must be l

maintained for all postulated events. The storage racks are capable of maintaining this k 'fiighest reactivity (assuming with unborated pool water at a temperature yielding the*

the storage restrictions of LCO 3.7.15 are met). Most abnormal storage locations will not result in an increase in the k,, of the racks. However, it is possible to postulate event,s, such as the mis-loading of an assembly with a burnup and enrichment combination outside the acceptable area in Figure 3.7.15-1 and 3.7.15-2, or dropping an assembly between the pool wall and the fuel racks, which could lead to an increase in reactivity. For such events, credit is taken for the presence of boron in the pool water since the NRC does not require the assumption of two unlikely, independent, concurrent events to ensure protection against a criticality accident (double contingency principle). The reduction in k caused by the boron more than offsets the reactivity addition caused by credible accidents (Ref-3).

l The concentration of dissolved boron in the fuel storage pool satisfies Criterion 2 of the NRC Policy Statement.

LCO The required concentration of dissolved boron in the fuel storage pool of 2 1925 ppm,p~ reserves the assumption used in the analyses of the potentia accident scenarios described above. This concentration of dissolved boron is the minimum required concentration for fuel assembly storage and movement within the fuel storage pool.

(continued)

Crystal River Unit 3 B 3.7-69 Amendment No. 149

Tl-Spent Fuel Pool Boron Concentration B 3.7.14 BASES SURVEILLANCE SR 3.7.14.1 (continued) l REQUIREMENTS Operating experience has shown significant differences between boron measured near the top of the pool and that measured elsewhere. As long as this SR is met, the analyzed events are fully bounded. The 7 day Frequency is acceptable because no major replenishment of pool water is expected to l

vake place over this period of time.

REFERENCES 1.

Criticality Safety Analysis of the Crystal River Unit-3 Pcci A Spent ruel Storage Raek, S. C. Tttraer. Southern Science, 55-162.

CriticalitplSafity~ EYalUstioriT6f?theIP6ollTA"Spenf Fuel Storage (Racks:in CrystaliRivereUnit-3LWith Fuel of 5 0%

Enrichment; < S.

E.1.aTu ner,.,Holteci,Reporti HI-931111; December;19932 2.

Technical Specification Change Request 175, dated Detober 31, 1989-CH t'icalit9(Safety'Analps W ofTthe West'ingholisel Spent Fuel StorageLRacks-.in' PoolLBiof Crystal: River Unit?3,-

S6E.1 Turner,0Holtec;ReportLHI-992128,,May;1999.;

3.

NRC Safety Cvaittation Report foHmendment 134 to CR-3 Operating License, dated April 15, 1991.

l l

Crystal' River Unit 3 B 3.7-71 Amendment No. -149 l

Spent Fuel Assembly Storaga B 3.7.15 B 3.7 PLANT SYSTEMS B 3.7.15 Spent Fuel Assembly Storage BASES BACKGROUND This document describes the Bases for the Spent Fuel Assembly Storage which imposes storage requirements upon irradiated and unirradiated fuel assemblies stored in the fuel storage pools containing high. density racks. The storage areas, which are part of the Spent Fuel System, governed by this Specification are:

a.

Fuel storage pool "A" and b.

Fuel storage pool "B".

In general, the function of the storage racks is to support and protect new and spent fuel from the time it is placed in the storage area until it is shipped offsite.

Spent fuel is stored underwater in either fuel storage pool A or B. Only fuel pool A has the capability to store failed fuel in containers. Spent fuel pool A features high density poison storage racks with a 10 1/2 inch center-to-center distance capable of storing 542 assemblies. Fuel pool A is capable of storing fuel with enrichments up to 5.0 weight percent U-235 (Ref. 1) without exceeding the criticality criteria of Reference 3 providing the fuel has sufficient burnup.

NessfueDwilli be"~pl ated ui nto rpool 2 A? only ?

l Spent fuel pool B also contains high density racks separated into 2 regicas. The racks in Regica 1 have a 10.00 inch center-tc-center spacing capable cf stcring 174 assc;blies.

The high density racks in Regica 2 have 9.17 havinciai9211 inch center-to-center distance capable of storing 641 932 assemblies. Fuel pool B is capable of storing fuel with enrichments up to 5.0 weight percent U-235 (Ref. 2) without exceeding the _ criticality criteria of Reference 3, i

providing the fuel has sufficient burnup and required storage configuration. NetEfueliuM11Tnotibe?placedjint6 j

boolLB?

It should be noted that the maximum enrichment limits are actually nominal values. The tolerance of fuel supplied by DOE is t 0.013 weight percent. Thus, it is possible to have fuel with an initial enrichment slightly in excess of the stated limit. This is accounted for in the criticality analysis and is therefore acceptable.

(continued)

Crystal River Unit 3 B 3.7-72 Amendment Revision No. 11

=

Spent Fuel Assembly Storage B 3.7.15 BASES BACKGROUND Both of the spent fuel pools are constructed of reinforced (continued) concrete and lined with stainless steel plate. They are located in the fuel handling area of the auxiliary building l (Ref. 2).

New fuel storage requirements are addressed in Section 4.0,

" Design Features".

APPLICABLE The function of the spent fuel storage racks are to support SAFETY ANALYSES and protect spent fuel assemblies from the time they are placed in the pool until they are shipped offsite. The spent fuel assembly storage LCO was derived from the need to establish limiting conditions on fuel storage to assure sufficient safety margin exists to prevent inadvertent criticality. The spent fuel assemblies are stored entirely underwater in a configuration that has been shown to result in a reactivity of less than or equal to 0.95 under worse case l conditions (Ref. 1 and 2). The spent fuel assembly enrichment requirements in this LCO are required to ensure inadvertent criticality does not occur in the spent fuel pool.

Inadvertent criticality within the fuel storage area could result in offsite radiation doses exceeding 10 CFR 100 limits.

The spent fuel assembly storage satisfies Criterion 2 of the NRC Policy Statement.

LCO Limits on the new and irradiated fuel assembly storage in high l

density racks were established to ensure the assumptions of the criticality safety analysis of the spent fuel pools is maintained.

Limits on initial fuel enrichment and burnup for both new and~for spent fuel stored in pool A have been established.

Two limits are defined:

1.

Initial fuel enrichment must be less than or equal to 5.0 weight percent U-235, and (continued)

Crystal River Unit 3 8 3.7-73 Amendment Revis ion No. H

Spent Fuel Assembly Storage B 3.7.15 BASES LCO (continued) 2.

For ne'wCowlirradiationZand spent fuel with initial l

enrichment less than or equal to 5.0 weight percent and greater than or equal to 3.5 weight percent, fuel burnup must be within the limits specifi_ed in Figure 3.7.15-1.

(Figure 3.7.15-1 presents twofar.easLof required fuel assembly burnup as a function of initial enrichment.}

Forifuel with! enrichment-burnup:combinationslin"the area above the curve,Jthere are nonrestrictionsion where therfuel can-beistored. -For fuelLwith enrichment-bur.nup: combinations!below the.curv'e, the fuel must beistored in>a one-out-of-two checkerboard configuration withLwater cells'thaticontainsnoifuel.:

The acceptabilityLof storing this fueLin:the checkerboard;configurationils;documentedmin; Reference 6.

Fuel enrichment limits are based on avoiding inadvertent criticality in the spent fuel pool. The CR-3 spent fuel storage system was initially designed to a maximum enrichment of 3.5 weight percent. Enrichments of up to 5.0 weight percent are permissible for storage in spent fuel pool A as long as the fuel burnup is sufficient to limit the worst case reactivity in the storage pool to less than orf equalito 0.95. l Fuel burnup reduces the reactivity of the fuel due to the accumulation of fission product poisons.

Reference 1

documents that the required burnup varies linearly as a function of enrichment with 10500 megawatt days per metric ton uranium (Mwd /mtV) required for fuel with 5.0 weight percent enrichment and 0 burnup required for 3.5 weight percent enriched fuel.

Similar types of restrictions have been established for Pool B.

1.

Initial fuel enrichment must be s 5.0 weight percent U-235, and h

For Region 1, fuel with initial enrichment s 5.0 weight percent and 2 F 08 2.0Tweight percent, fuel burnup must be within the limits specified in Figure 3.7.15-2 and-arranged in a required checkerboard configuration witn new fuel or burned fuel of 6 5.0 weight percent, and h

for spent-fuel wi th an initial enrichi, ant of s+0 weight percent and-21.03 weight percent in Region 2, fuel burnup must be within the limits specified in figure 3.7.15-3. (rigure 3.7.15-3 presents required fuel asscmbly uurnup, 23 & function-of initial enrichment.)

(continued)

Crystal River Unit 3 B 3.7-74 Amendment Revision No. 11

Spent Fuel Assembly Storage B 3.7.15 BASES (cont-inued)

'LCO' Fuel with burnup-en"richment combinations in.the area'above the (continued) upper curve has no-restrictions on where it can be stored.

Fuel with burnup-enrichment combinations in the area between the lower and upper curves must be stored in the peripheral cells of the pool. The peripheral cells are _those that are adjacent to the walls of the spent fuel pool.

Fuel with burnup-enrichment combinations in the area below the' lower:

curve cannot be stored in Pool B, but.must beLstored in Pool A.

The LCO allows compensatory loading techniques, specified in the FSAR and applicable fuel handling procedures, as an alternative to storing fuel assemblies in accordance with Figures 3.7.15-1 and 3.7.15-2 and Figure 3.7.15-3. This is l

acceptable since these loading patterns assure the same degree of subcriticality within the pool.

APPLICABILITY In general, limiting fuel enrichment of stored fuel prevents inadvertent criticality in the storage pools. Inadvertent criticality is dependent on whether fuel is stored in the pools and is completely independent of plant MODE.

Therefore, this LCO is applicable whenever any fuel assembly is stored in high density fuel storage locations.

ACTIONS A.1 1

Required Action A.1 is modified by a Note indicating LCO 3.0.3 does not apply. Since the design basis accident of concern in this Specification is an inadvertent criticality, and since the possibility or consequences of this event are independent i

of plant MODE, there is no reason to shutdown the plant if the LCO or Required Actions cannot be met.

When the configuration of fuel assemblies stored in the spent fuel pool is not in accordance with Figure 3.7.15-1 or Figure 3.7.15-2, Figure 3.7.15-3, or the ISAR, immediate action (continued)

Crystal River Unit 3 B 3.7-75 Amendment Revision No. H

Spent Fuel Assembly Storage B 3.7.15 BASES ACTIONS 611 (continued) must be taken to make the necessary fuel assembly movement (s) to bring the configuracion into compliance. The Immediate Completion Time underscores the necessity of restoring spent fuel pool irradiated fuel loading to within the initial assumptions of the criticality analysis.

The ACTIONS do not specify a time limit for completing movement of the affected fuel assemblies to their correct location. This is not meant to allow an unnecessary delay in resolution, but is a reflection of the fact that the complexity of the corrective actions is unknown.

SURVEILLANCE SR 3.7.15.1 REQUIREMENTS Verification by administrative means that initial enrichment and burnup of fuel assemblies in accordance with Figure 3.7.15-1 and Figure 3.7.15-2 and-Figure 3.7.15-3 is required l

prior to storage of spent fuel in storage pool A or pool B (as applicable). This surveillance ensures that fuel enrichment limits, as specified in the criticality safety analysies (Ref.

1:and 2), are not exceeded. The surveillance Frequency (prior to storage in high density region of the fuel storage pool) is appropriate since the initial fuel enrichment and burnup cannot change after removal from the core.

REFERENCES 1.

Criticality Safety Evaluation of the Pool A Spent Fuel Storage Racks in Crystal River Unit 3 with Fuel of 5.0% Enrichment, S.

E.

Turner, Holtec Report HI 931111, December 1993.

C-ristal River-Unit 3 Sgent fuel Storage Pcci 0 2:

C r' '

ticality Analysis,

. A. Wttkopf,

u. A. llassler-B&W FuelComr5any,CAJ-2209P, October 1993.

Critical ty Safety Analysis of the Westinghouse Spent

~ E. Turner,ge Racks.in Pool B of Crystal River Unit 3, S.

Fuel Stora Holtec Report HI-992128, May 1999._

3.

NUREG 0800, Standard Review Plan, Section 9.1.1 and 9.1.2, Rev. 2, July 1981.

4.

10 CFR 100.

5.

CR-3 FSAR, Section 9.6.

6.-

Criticality Safety Analysis of the Crystal River Unit 3 Pool A for Storage of 5% Enriched Mark B-11 Fuel in Checkerboard Arrangement With Water Holes, S.

E..

Turner, Holtec Report HI-992285, August 1999.-

Crystal River Unit 3 B 3.7-76 Amendment Revision No.11 7

l

FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 ATTACHMENT C LICENSE AMENDMENT REQUEST # 239, REVISION O Proposed Improved Technical Specifications and Bases Changes Revision Bar Format

Spent Fusl Pool Boron Concentration 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Spent Fuel pool Boron Concentration LCO. 3.7.14 The spent fuel pool boron concentration shall be 21925 ppm.

4 APPLICABILITY:

When fuel assemblies are stored in the spent fuel pool and a spent fuel pool verification has not been performed since the last movement of fuel assemblies in the spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Spent fuel pool boron

---

NOTE------------

concent~ ration not LCO 3.0.3 is not applicable.

With'n limit.

A.1 Suspend movement of Immediately fuel assemblies in the spent fuel pool.

AND A.2.1 Initiate action to Immediately restore spent fuel pool boron concentration to within limit.

QB A.2.2 Verify by Immediately administrative means a Storage Pool A and Storage Pool B spent fuel pool verification has been performed since the last movement of fuel assemblies in the spent fuel pool.

Crystal River Unit 3 3.7-28 Amendment No,

Spent Fuel Assembly Storage 3.7.15 3.7 PLANT SYSTEMS 3.7.15 Spent Fuel Assembly Storage LCO 3.7.15 The combination of initial enrichment and burnup of each spent fuel _ assembly stored in Storage Pool A and Storage Pool B, shall be within the acceptable region of _ Figure 3.7.15-1 or Figure 3.7.15-2.

APPLICABILITY:

Whenever any' fuel assembly is stored in Storage Pool A or Storage Pool B of the spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Requirements of the A.1

---

NOTE--------

LCO not met.

LCO 3.0.3 is not applicable.

Initiate action to Immediately move the noncomplying fuel assembly to an acceptable configuration.

Crystal River Unit 3 3.7-30 Amendment No.

c Spant Fuel Assembly Storage 3.7.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify by administrative means the initial Prior to enrichment and burnup 6 the fuel assemb'ly storing the is in accordance with Figure 3.7.15-1 or fuel assembly Figure 3.7.15-2.

in Storage Pool A or Storage Pool B.

4 l

l

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Crystal River Unit 3 3.7-31 Amendment No.

a

Spent Fuel Assembly Storage 3.7.15 MINIMUM BURNUP REQUIRED FOR A" POOL STORAGE NOTE: One-out-of-two checkerboant loading with empty cells allowed for any combination of enrichment and burnup.

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Initial Enrichment, Weight Percent U235 Figure 3.7.15-1 l

Burnup versus Enrichment Curve for Spent Fuel Storage Pool A Crystal River Unit 3 3.7-32 Amendment No.

t

Spent Fuel Assembly Storage 3.7.15 MINIMUM BURNUP REQUIRED FOR "S" POOL STORAGE Minimum Burnup vs. Initial Enrichment 45 -

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initial Enrichment, Weight Percent U235 Figure 3.7.15-2 Burnup versus Enrichment Curve for Spent Fuel Storage Pool 8 Crystal River Unit 3 3.7-33 Amendment No.

Dasign Features 4.0 4.0.

DESIGN. FEATURES.

l 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent;

b..

k s 0.95 if fully flooded with unborated water, wN,ich includes an allowance for uncertainties as described in Section 9.6 of the FSAR; c.

A nominal 9.11 inch center to center distance between fuel assemblies placed in the B pool; d.

A nominal'10.5 inch center to center distance between fuel assemblies placed in the A pool.

4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent; b.

k s 0.95 is fully flooded with unborated water, i

wTich includes an allowance for uncertainties as described in Section 9.6 of the FSAR; k,,,ludes an allowance for uncertainties as described s 0.98 if moderated by aqueous foam, which c.

inc in Section 9.6 of the FSAR; and d.

A nominal 21.125 inch center to center distance 1

between fuel assemblies placed in the storage racks.

(continued)

Crystal River Unit 3 4.0-2 Amendment No.

i

Design Features 4.0 4.0 DESIGN FEATURES l

4.3.2 Drainaae The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 138 feet 4 inches.

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a. storage capacity limited to no more than 1474 fuel l

assemblies and six failed fuel containers.

Crystal River Unit 3 4.0-3 Amendment No.

Spant Fuel Pool Boron Concentration B 3.7.14 8 3.7 PLANT SYSTEMS B 3.7.14 Spent Fuel Pool Boron Concentration BASES BACKGROUND As described in the Bases for LCO 3.7.15, " Spent Fuel Assembly Storage," fuel assemblies are stored in the high-density region of the spent fuel pool storage racks in accordance with criteria based on initial weight-percent enrichment and discharge burnup. Although the water in the spent fuel pool is normally borated to 2 2000 ppm, the criteria that limit the storage of a fuel assembly to specific rack locations (criticality analysis) are conservatively developed without taking credit for the boron in the pool water.

APPLICABLE The acceptance criteria for the fuel storage pool SAFETY ANALYSIS criticality analyses is that a k,,, of s 0.95 must be l

maintained for all postulated events. The storage racks are capable of maintaining this k,, with unborated pool water at a temperature yielding the bighest reactivity (assuming the storage restrictions of LCO 3.7.15 are met). Most I

abnormal storage locations will not result in an increase in the k,,, of the racks. However, it is possible to postulate events, such as the mis-loading of an assembly with a burnup and enrichment combination outside the acceptable area in Figure 3.7.15-1 and 3.7.15-2, or dropping an assembly between the pool wall and the fuel racks, which could lead to an increase in reactivity. For such events, credit is taken for the presence of boron in the pool water since the NRC does not require the assumption of two unlikely, independent, concurrent events to ensure protection against a criticality accident (double contingency principle). The reduction in k caused by the boron more than offsets the reactivityaddY',ioncausedbycredibleaccidents.

l t

The concentration of dissolved boron in the fuel storage pool satisfies Criterion 2 of the NRC Policy Statement.

LCO The required concentration of dissolved boron in the fuel storage pool of 2 1925 ppm preserves the assumption used in the analyses of the potential accident scenarios described above. This concentration of dissolved boron is the minimum required concentration for fuel assembly storage and movement within the fuel storage pool.

(continued)

Crystal River Unit 3 8 3.7-69 Amendment No, i

Spent Fuel Pool Boron Concentration B 3.7.14 i

{

BASES SURVEILLANCE SR 3.7.14.1 (continued)

REQUIREMENTS Operating experience has shown significant differences between boron measured near the top of the pool and that measured elsewhere. As long as this SR is met, the analyzed events are fully bounded. The 7 day Frequency is acceptable because no major replenishment of pool water is expected to take place over this period of time.

REFERENCES 1.

Criticality Safety Evaluation of the Pool A Spent Fuel Storage Racks in Crystal River Unit 3 With Fuel of 5.0%

Enri chment, S.

E.

Turner, Holtec Report HI-931111 December 1993.

2.

Criticality Safety Analysis of the Westinghouse Spent Fuel Storage Racks in Pool B of Crystal River Unit 3, S. E. Turner, Holtec Report HI-992128, May 1999.

I i

Crystal River Unit 3 8 3.7-71 Amendment No.

j

n Spent Fuel Assembly Storage B 3.7.15 B 3.7 PLANT SYSTEMS B 3.7.15 Spent Fuel Assembly-Storage BASES BACKGROUND This document describes the Bases for the Spent Fuel Assembly Storage which imposes storage requirements upon irradiated and unirradiated fuel assemblies stored in the fuel storage pools containing high density racks. The storage areas, which are part of the Spent Fuel System, governed by this Specification are:

a.

Fuel storage pool."A" and b.

Fuel storage pool "B".

In general, the function of the storage racks is to support and protect new and spent fuel from the time.it is placed in the storage area until it is shipped offsite.

Spent fuel is stored underwater in either fuel storage pool A or B. Only fuel pool A has the capability to store failed fuel in containers. Spent fuel pool A features high density poison storage racks with a 10 1/2 inch center-to-center distance capable of storing 542 assemblies. Fuel pool A is capable of storing fuel with enrichments up to 5.0 weight percent U-235 (Ref. 1) without exceeding the criticality criteria of Reference 3 providing the fuel has sufficient burnup. New fuel will be placed into pool A only.

l Spent fuel pool B also contains high density racks having a 9.11 inch center-to-center distance capable of storing 932 assemblies. Fuel pool B is capable of storing fuel with enrichments up to 5.0 weight percent U-235 (Ref. 2) without exceeding the criticality criteria of Reference 3, providing the fuel has sufficient burnup and required storage configuration. New fuel will not be placed into pool B.

It should be noted that the maximum enrichment limits are actually nominal values. The tolerance of fuel supplied by DOE is 0.013 weight percent. Thus, it is possible to have fuel with an initial enrichment slightly in excess of the stated limit. This is accounted for in the criticality analysis and is therefore acceptable.

(continued)

Crystal River Unit 3 B 3.7-72 Amendment No.

Spant Fuel Assembly Storage B 3.7.15 BASES BACKGROUND Both of the spent fuel pools are constructed of reinforced (continued) concrete and lined with stainless steel plate. They are located in the fuel handling area of the auxiliary building.

l New fuel storage requirements are addressed in Section 4.0,

" Design Features".

APPLICABLE The function of the spent fuel storage racks are to support SAFETY ANALYSES and protect spent fuel assemblies from the time they are placed in the pool until they are shipped offsite. The spent fuel assembly storage LCO was derived from the need to establish limiting conditions on fuel storage to assure sufficient safety margin exists to prevent inadvertent criticality. The spent fuel assemblies are stored entirely underwater in a configurat. ion that has been shown to result in a reactivity of less than or equal to 0.95 under worse case l

conditions (Ref. 1 and 2). The spent fuel assembly enrichment requirements in this LCO are required to ensure inadvertent criticality does not occur in the spent fuel pool.

Inadvertent criticality within the fuel storage area could result in offsite radiation doses exceeding 10 CFR 100 limits.

The spent fuel assembly storage satisfies Criterion 2 of the NRC Policy Statement.

LC0 Limits on the new and irradiated fuel assembly storage in high l

density racks were established to ensure the assumptions of the criticality safety analysis of the spent fuel pools is maintained.

Limits on initial fuel enrichment and burnup for both new and for spent fuel stored in pool A have been established.

Two limits are defined:

1.

Initial fuel enrichment must be less than or equal to 5.0 weight percent U-235, and (continued)

Crystal River Unit 3 B 3.7-73 Amendment No.

i I

Spent Fuel Assembly Storage B 3.7.15 BASES LCO 2.

For new, low irradiation, and spent fuel with initial l

(continued) enrichment less than or equal to 5.0 weight percent and greater than or equal to 3.5 weight percent, fuel burnup must be within the limits specified in Figure 3.7.15-1.

Figure 3.7.15-1 presents two areas of required fuel assembly burnup as a function of initial enrichment.

l For fuel with enrichment-burnup combinations in the area above the curve, there are no restrictions on where the fuel can be stored.

For fuel with enrichment-burnup combinations below the curve, the fuel must be stored in a one-out-of-two checkerboard configuration with water cells that contain no fuel.

The acceptability of storing this fuel in the checkerboard configuration is documented in Reference 6.

Fuel enrichment limits are based on avoiding inadvertent criticality in the spent fuel pool.

The CR-3 spent fuel storage system was initially designed to a maximum enrichment of 3.5 weight percent. Enrichments of up to 5.0 weight percent are permissible for storage in spent fuel pool A as long as the fuel burnup is sufficient to limit the worst case reactivity in the storage pool to less than or equal to 0.95. l Fuel burnup reduces the reactivity of the fuel due to the accumslation of fission product poisons.

Reference 1

documents that the required burnup varies linearly as a function of enrichment with 10500 megawatt days per metric ton uranium (Mwd /mtU) required for fuel with 5.0 weight percent enrichment and 0 burnup required for 3.5 weight percent enriched fuel.

Similar types of restrictions have been established for Pool B.

1.

Initial fuel enrichment must be s 5.0 weight percent U-235, and 2.

For fuel with initial enrichment s 5.0 weight percent and 2 2.0 weight percent, fuel burnup must be within the limits specified in Figure 3.7.15-2.

(continued)

Crystal River Unit 3 B 3.7-74 Amendment No.

Spent Fuel Assembly Storage B 3.7.15 BASES l

LCO (continued)

Fuel with burnup-enrichment combinations in the area above the upper curve has no restrictions on where it can be stored.

Fuel with burnup-enrichment combinations in the area between the lower and upper curves must be stored in the peripheral cells of the pool.

The peripheral cells are those that are adjacent to the walls of the spent fuel pool.

Fuel with burnup-enrichment combinations in the area below the lower curve cannot be stored in Pool B, but must be stored in Pool A.

The LCO allows compensatory loading techniques, specified in the FSAR and applicable fuel handling procedures, as an alternative to storing fuel assemblies in accordance with Figures 3.7.15-1 and 3.7.15-2.

This is acceptable since l these loading patterns assure the same degree of subcriticality within the pool.

i 1

APPLICABILITY In general, limiting fuel enrichment of stored fuel prevents inadvertent critica'lity in the storage pools. Inadvertent criticality is dependent on whether fuel is stored in the pools and is completely independent of plant MODE.

i Therefore, this LCO is applicable whenever any fuel assembly is stored in high density fuel storage locations.

ACTIONS A_d Required Action A.1 is modified by a Note indicating LC0 3.0.3 does not apply. Since the design basis accident of concern in this Specification is an inadvertent criticality,, and since i

the possibility or consequences of this event are independent of p'lant MODE, there is no reason to shutdown the plant if the LCO or Required Actions cannot be met.

When the configuration of fuel assemblies stored in the spent fuel pool is not in accordance with Figure 3.7.15-1 or Figure 3.7.15-2, immediate action must be taken to make the necessary fuel assembly movement (s) to bring the configuration into comoliance. The Immediate Completion Time underscores the necessity of restoring spent fuel pool irradiated fuel loadine to within the initial assumptions of the criticality ar.alysis.

3 (continued) r Crystal River Unit 3 8 3.7-75 Amendment No.

Spsnt Fuel Assembly Storage B 3.7.15 BASES l

ACTIONS L1 (continued)

The ACTIONS do not specify a time limit for completing movement of the affected fuel assemblies to their correct location. This is not meant to allow an unnecessary delay in resolution, but is a reflection of the fact that the complexity of the corrective actions is unknown.

SURVEILLANCE SP 3.7.15.1 REQUIREMENTS Verification by administrative means that initial enrichment and burnup of fuel assemblies in accordance with Figure 3.7.15-1 and Figure 3.7.15-2 is required prior to storage of l

spent fuel in storage pool A or pool B (as applicable). This surveillance ensures that fuel enrichment limits, as specified in the criticality safety analyses (Ref.1 and 2),

l are not exceeded. The surveillance Frequency (prior to-storage in high density region of the fuel storage pool) is appropriate since the initial fuel enrichment and burnup cannot change after removal from the core.

REFERENCES 1.

Criticality Safety Evaluation of the Pool A Spent Fuel Storage Racks in Crystal River Unit 3 with Fuel of 5.0%

Enrichtnent, S.

E.

Turner, Holtec Report HI 931111, December 1993.

2.

Criticality Safety Analysis of the Westinghouse Spent Fuel Storage Racks in ool B of Crystal River Unit 3, S.

r E. Turner, Holtec Re pet HI-992128, May 1999.

3.

NUREG 0800, Standard Review Plan, Section 9.1.1 and 9.1.2, Rev. 2, July 1981.

4.

10 CFR 100.

5.

CR-3 FSAR, Section 9.6.

6.

Criticality Safety Analysis of the Crystal River Unit 3 Pool A for Storage of 5% Enriched Mark B-11 Fuel in Checkerboard Arrangement With Water Holes, S. E.

Turner, Holtec Report HI-992285, August 1999.

Crystal River Unit 3 8 3.7-76 Amendment No.

4 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 ATTACHMENT E CRITICALITY SAFETY ANALYSIS OF THE CRYSTAL RIVER UNIT 3 POOL A FOR STORAGE OF 5% ENRICHED MARK B-11 FUEL IN CHEC.KERBOARD ARRANGEMENT WITH WATER HOLES LICENSE AMENDMENT REQUEST # 239, REVISION 0

,.