ML20045E713

Proposed Tech Specs 3.9.13 Re Storage of New & Spent Fuel Assemblies W/Initial Nominal Enrichment of U-235 No Greater than 5.0 Weight Percent

ML20045E713
Person / Time
Site:	Davis Besse
Issue date:	06/23/1993
From:	CENTERIOR ENERGY
To:
Shared Package
ML20045E709	List: ML20045E708 ML20045E711 ML20045E713
References
NUDOCS 9307020347
Download: ML20045E713 (7)

Text

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Docket Number 50-346

' License Number NPF-3 Serial Number 2149 Attachment 1 Page 12

' REFUELING OPEPATIONS

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,1 SPENT FUEL POOL FUEL ASSEMBLY STORAGE

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!l LIMITING CONDITION FOR OPERATION 3.9.13 Fuel assemolies s in the spent fuel pool shall be placed in the -

i i spent fuel storage rac  ::::75 4 b the criteria shown in Figure 3.9-1. )

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in. acc.ord nce. with Appt.ICABILITY: Whenever fuel assemolies are in the spent fuel pool.

ACTION:

With the requirements of the above specification not satisfied. suspend all other fuel movement within tne spent fuel pool and move the non-complying-fuel assemolies to allowable locations in tne spent fuel pool in accordance-with Figure 3.9-1. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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SURVEILLANCE REQUIREMENT 1r bpool shall bee burnus of each fuel assembly to be stored-in the speprior to ined througn analysis of its burnus storage in the spent 1. A completa r ch analysis snail be maintained as long as that s retained 2onstta.

4.9.13.2 After sa ssembly move in the s pool, the position of the fuel y that was moved shall be checked and ently (t ve o be in accordance with the criteria in Figure 3.9-1.

s 4.9. 83. x Pe lo c to sf ocin3 1% Zve I ss.sen bl y in. % spen +

Nuc.l fool > veris lay a d m ini s4 ca 4 lve, menns-lh=$~%e EnEbiaI en c'e c.h m snt a- b ue n vy o f ~t h e. Sue.\ e s. sea bly s is'n a ce.ce d a o, c e.

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l DAVIS-BESSE. UNIT 1 3/4 9-13 /aenoment No.130 9307020347 930623 PDR ADOCK 05000346 P PDR

' Docket Number 50-346 .l bicense fiumber NPF-3 j Serial Number 2149 Attachment 1 ,

Page 13 l

Figure 3.9-1 Burnup vs. .

Enrichment Curve for ,

Davis-Sesse Spent Fuel Storage Racks l 3

b Fuel Assemoly urnum (B). HWD/NTU l

40.000 r -.

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(3. B. 35930.8) 3

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, (3.3.30 4.31 30.000h ,8 = -26640 (225a4 x El-(1810 x 1

g

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{ 20.000 -

Not  !

l [ g D e ttted g

10.000 -

(1.3. 0 .01 ' ' ' ' '

0 0 0 i 1.5 Initial Fuel Enrtenment -(E).

2- 2.5 k w 3.5 U-235 4 4.5 i

Category " A" Fuel - May be located anywhere within th's storage rocks Category 'B' Fuel - Shall only be located adjacent t Category 'A* Fuel or water noles within the storage racks  ;

Category 'C' Fuel - Shall not.be locaten adjacent to Category "B" Fuel n

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l R 9 *u I All m 563 vre 5.9- I (A tta< k ed )

DAVIS-BESSE UNIT 1 3/4 9-14 Amenament No. 130 T n _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _

Docket'fiumber 50-346 License 11 umber fiPF-3 .

Serial fJumber 2149 Figure 0.9-1 Attac'hment 1 Page 14 Burnup vs. Enn.chment Curves For Davis-Besse Spent Fuel Storage Racks 60 50 -

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"B"  ;

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0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 1.0 Initial Enrichment (wt% U-235)

Category "A" May be placed in any rack location Category "B": Must not be placed directly adjacent to Category "C" assemblies Category "C". May only be placed directly adjacent to Category "A" assemblies or non-fuel locations

Docket Number 50-346 License Number NPF-3 Serial Number 2149 lA B l FORINfDRMATION DNLY SA5E5 i

3/a.9.12 STORAGE POOL VENTILATION l The reouirements on the emergency ventilation system servicing the

storage pool area to be operating or OPERABLE ensure tnat all radioactive j ; material released from an irradiated fuel assemoly will be filtered through

!I the HEPA filters and charcoal adsorcer prior to distnarge to the atmosphere.

l! The OPERABILITY of this system and the resulting iodine removal capacity are ll, consistent with the assumptions of the safety analyses.

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,3/a.9.13 SPENT FUEL POOL FUEL ASSEMBLY STORAGE lI The restrictions on the placement of fuel assemblies within the spent

!l,i fuel pool, as dictated by Figure 3.9-1, ensure that the k-effective of the spent fuel pool will always renain less than 0.95 assuming the pool to be flocoed with non-borated water. The restrictions delineated in Figure 3.9-1 and the action Statement are consistent with the criticality safety analysis I performed for the spent fuel pocl.

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B 3/4 9-3 Amendment No. I?J,135 g DAVIS-BESSE, UNIT 1 i

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Docket Number 50-346  :

License Number NPF-3 l Serial' Number 2149 Attachment 1 Page 16 l

CESIGN FEATURES VOLUME

'5.4.2 The total water and steam volume of the reactor coolant system is j 12.110 t 200 cubic feet at a nominal T avg f 525'F.

i 5.5 METEOROLOGICAL TOWER LOCATION I

! 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

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FWFUEL STORgf C . Fue l a s seat <c s .s+ occ a w. m. sr. n t f F v e I pool in- accordece wAL CRITICALITY p 4,- p,g,

, 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. AK equivalent to less than or equal to 0.95 when flooded wit $fbnborated water, which includes a conservative allowance:

of 1% delta k/k for calculation uncertainty.

b. A rectangular array of stainless steel cells spaced 12 31/32.

( inches on centers in one direction and 13 3/16 inches on centers-in the other direction. Fuel assenblies stored in the spent-fuel

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pool shall be placed in a stainless steel cell of 0.125 inches' yaminal thickness or in a failed fuel container.

' M new' fue sTgned aridMEintained~M with:

a. A Keff equivalent to less than or equal to 0.95 when flooded 2 with unborated water, which includes a conservative allowance-of 1% delta k/k for uncertainties as described in Section 9.1 of the USAR.

b. A Keff equivalent to less than or equal to 0.98 when imersedrin a hydrogenous " mist" of such a density that provides optimum moderation (i.e. highest value of Keff), which includes a conservative allowance of 1% delta k/k for uncertainties as described in Section 9.1 of the USAR.

c. A nominal 21 inch center-to-center distance between fuel assamtdies:

torage racks. _

- DRAINAG

, 5.6.2 The spent fuel storage pool .is designed and shall be maintained-to l i prevent inadvertent draining of the' pool below 9 feet above the top of the  !

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\' j j d. Fue l a s s e, > 66cs % ~ ~ ev> > Mt d encick->=,,t of S.o weef t p erced veduum -2 35 DAVIS-BESSE. UNIT 1 5-5 Amenoment No.19,130

. Docket Number 50-346 License Number NPF-3 Serial Number 2149 Attachment 2  ;

Page 1 ENVIRONMENTAL ASSESSMENT LICENSE AMENDMENT REQUEST (LAR) 90-0042 Identification of Proposed Action This proposed action involves the Davis-Besse. Nuclear Power. Station (DBNPS), Unit Number 1, Operating License Number.NPF-3, Appendix A, Technical Specifications (TS). A license amendment is proposed to revise TS 3.9.13, Refueling Operations - Spent Fuel Pool Fuel Assembly Storage, associated TS Figure 3.9-1, Burnup versus Enrichment curve for '

Davis-Besse Spent Fuel Storage Racks, and TS 5.6, Design Features -

Fuel Storage. The proposed amendment would revise the provisions in the TS to allow storage of new and spent fuel assemblies with an.

Initial nominal enrichment of uranium-235 no greater than 5.0 veight percent (vt%). The existing TS Figure 3.9-1 limits the initial enrichment of fuel that can be stored in the spent fuel pool to 3.8 vt%. The existing TS do not directly restrict the initial enrichment-of new fuel that can be stored in the new fuel storage racks.

The use of higher enrichment fuel in the reactor is not part of this proposed action.

The Need for the Proposed Action The proposed changes to the TS are required.in order to provide the capability to store fuel with a higher initial enrichment of-uranium-235 for future use in the reactor, and to store the spent fuel

• when it is discharged from the reactor. This capability will allow a reduction in the number of new fuel' assemblies that are loaded into the reactor during each reload. Corresponding to this reduction in reload-batch size is an increase in the fuel assembly average discharge burnup.

i Environmental Impacts of the Proposed Action The environmental impacts of the uranium fuel cycle associated with higher enrichments and extended fuel burnups have been generically assessed by the NRC, as published in the Federal Register, 53 FR 6040' dated February 29,1988, " Extended Burnup Fuel Use-in Commercial LVRs;

• Environmental Assessment and Finding of No Significant-Impact," and 53 FR 30355 dated August 11, 1988, "NRC Assessment of the Environmental-Effects of Transportation Resulting from Extended Fuel Enrichment and Irradiation". In summary, the NRC Staff concluded that the environmental impacts summarized in Table S-3 of 10 CFR 51.51 and in ,

Table S-4 of 10 CFR 51.52 for a burnup level of 33 GVD/MTU are  ;

conservative and bound the' corresponding impacts for burnup levels up to 60 GVD/MTU and uranium-235 enrichments up to 5 percent by weight, and that the transportation impacts of extended irradiation and increased fuel enrichment are bounded by the impacts reported in Table S-4 of 10 CFR 51.

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Docket Number 50-346 License Number NPF-3 Serial Number 2149 Attachment-2 Page 2 Vith regard to potential non-radiological impacts, the proposed-amendment involves no. increase in the amounts or change in types of any non-radiological effluents that may be released offsite, and has no other environmental impact.

Alternatives to the Proposed Action Since it has been concluded that the environmental effects of the i proposed action are not significant, any alternatives vill have only similar or greater environmental impacts.

The principle alternative vould be not to amend the TS. This vould not reduce the environmental impacts of plant operation and would result'in reduced operational flexibility.

t Alternative Use of Resour'ces This action does not involve the use of resources not previously considered in the " Final Environmental Statement Related to the

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Operation of the Davis-Besse Nuclear Power Station, Unit Number 1" (NUREG 75/097), dated October 1975.

Finding of No Significant Impact Based upon the foregoing environmental assessment, Toledo Edison concludes that there are no significant adverse radiological or non-radiological impacts associated with the proposed Technical Specification changes.

Accordingly, Toledo Edison finds that the proposed license amendment, if approved by the NRC, will have no significant impact on the environment, and that no Environmental Impact Statement.is required.

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