ML20211K624

Proposed Tech Specs,Changing ISFSI License Conditions 6,7 & 8 & TS 3/4.1 by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks

ML20211K624
Person / Time
Site:	Prairie Island
Issue date:	08/31/1999
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20211K598	List: ML20211K593 ML20211K610 ML20211K624
References
NUDOCS 9909080032
Download: ML20211K624 (9)

Text

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3/4.1 PUEL TO BE STORED'AT ISFSI LI(ITINC CONDITION EUR OPERATION 1

3.1.l' The spent nuclear fuel to be received and stored in the TN-40 cask at the Prairie Island ISFSI shall meet the following requirements:

(1) Only fuel irradiated at the Prairie Island Nuclear Generating Plant Unit Nos. 1,and 2 may be used.

(2) Maximum initial enrichment shall not exceed 3.85 weight percent U-235.

(3) Maximum Assembly average burnup shall not exceed 45,000 megawatt-days per metric ton uranium.

(4) Fuel shall have cooled a minimum of 10 years after reactor discharge, before storage in the ISFSI.

(5) Fuel shall be intact unconsolidated fuel. Partial fuel asceablies, that is, fuel assemblies from which fuel pins are missing must not be loaded unless dummy fuel pins are used to displace an amount of water equal to that displaced by the original pins.

(6) Fuel assemblies known or suspected to have structural defects or gross cladding failures (other than pinhole leaks) sufficiently severe to adversely affect fuel handling and transfer capability shall not be loaded into the cask for storage.

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APPLICABILITY: This specification is applicable to all spent fuel to be )

loaded and stored in the TN-40 cask at the Prairie Island I

! ISFSI. l l  !

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I l ,. ACTION: If the requirements of the above specification are not met,

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do not load the fuel assembly into the TN-40 cask.

SURVEILIANCE REQUIREMENTS:

i 4.1.1 Each fuel assembly iuid[fue1[5sseinbly[idisrt3(BPRA[orlTPD)) to be loaded

.shall have the above specifications independently verified and documented.

l 4.1.2 Before inserting a spent fuel assembly into a cask and again before closing the cask, the identity of each fuel assembly siind5tM)yps[gefach[ fuel

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d@y[lis@g3hT65T9Df shall be independently verified and documented.

BASIS: The design criteria and subsequent safety analyses of the Prairie Island ISFSI and' storage casks assumed certain characteristics and limitations for the fuel that is to be stored. Specification 3/4.1 ensures that the integrity of-the fuel is protected by defining characteristics such as the ,

source of the spent fuel, maximum initial enrichment, irradiation history, and '

minimum post-irradiation cooling time, ,

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l 'conciesMaminologybThia}burnup;of a7fual irisertids((d5fAnedIto}bh[th thetfueltinsert; This specification was derived to ensure that the peak fuel rod temperatures, cask surface contact dose rates, reactivity, and fuel nass are below the design values. ]

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, Table 3/4-1 TN-40 CASK OPERATING LIMITS 1

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l Operating Limit Maximum Lifting Height with a Non-Redundant Lifting Device 18 inches (45 cm)

Maximum Cask Surface Temperature 250 F (121 C) i l Maximum Surface Dose Rate (or equivalent at 2 meters) 200 mrem /hr l

Maximum Removable Surface Contamination Beta and Gamma 1000 dpm/100 cm*

Alpha 20 dpm/100 cm 2 i

i I

Maximum Helium Leak Rate 10-5 atm-cc/s I I l l l

Initial Helium Pressure (Cask Cavity) 20 i 1 psia (1.d hee I rm,..-

l (1l.4;bar

• 70 mbar)

Pressure During Cask Drying Test (held for 30 min.) s 10 mbar j Boron Concentration in Pool and Cask 2 1800 ppm l

l Storage Capacity s 40 assemblies l

Fuel Assembly Characteristics l

Initial Enrichment, U-235 s 3.85 wt. %

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Average Burnup 5 45,000 MND/MTU j i

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Time after Irradiation h 10 years BPitkhiel$1MN(CliGO6iiiliiEid n.,,.,,_,,r.,.,,,m,_, , _ , . . , - . . - . -

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- JAverage3t=- ;,7 K30i000ileID/MTG )

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1 3/4-10 l.

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l Pursuant to the Atenio Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 j (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter I, Part 72, and in j i

reliance on statements and representations heretofore made by the Licensee, a License is hereby l issued authorizing the Licensee'to receive, acquire, and possess the power reactor spent fuel '

and other' radioactive materials associated with spent fuel storage designated below; to use such enterials for the purposes and at the place designated below; and to deliver or transfer such materials to persons authorized to receive these materials in accordance with the regulations of the applicable Parts of 10 CFR Chapter I. This License shall be h to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereaf ter in effect and to any conditions specified herein.

Licensee i

1. Northern States Power Company i

3. License Number: SNM-2506

3. Address:

Amendment 23 dated ich:=: ; 1,' 1005 414 Nicollet Mall 4. Expiration Date: i Minneapolis, Minnesota 55401 October 31, 2013

5. Docket Number: 72-10

6. Byproduct, source, and/ 7. Chemical and/or 8. Maximum amount that or special nuclear physical form. that licensee may material possess at any one time under this license 1

A. Spent fuel assemblies A. As UO2 clad with A. 715.28 TeU of l from P'fairie Island Nuclear zirconium or spent fuel l Station Units 1 and 2 zirconium alloys assemblies reactor, using natural water

'for cooling and enriched not greater than 3.85 percent U-235, and associated radio-active materials related to receipt, storage, and transfer of the fuel assemblies B'.' isMdihEd[fiis1?Eieiibly Bi ' ~ T30FitUssotaare,7 88 t B7 OneYBPRAI6e i

' nserts$fesasErais1ehIsliUid i isconeh718hsprings TPDiperaspent Nealear$8tunsAan?Ura$tsE195nd?2 Endi boirated pyres fueltassemblMi~

$ reactor AniinseirtfaidyYbe/A ~ glash' tmrnabla%jpelsesi9n6diassembly

[(SPRARbr;Mthimb1EM1uggiig Mevice](TPD)$

9. Authorized Use: For use in accordance with statements, representations, and the conditions of the Technical Specifications and Safety Analysis Report dated August 31, 1990, and supplements dated October 29, 1990; April 2, June 5, October 9 and 31, November 15, December 11, 20, and 23, 1991; January 17, February 6, 10, and 12, March 2 and 5, April 3, 22, and 23, July 10, August 12,13, and 14,1992; and 0.:tober 2,1995.

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. EXHIBIT C l PRAIRIE ISLAND INDEPENDENT SPENT FUEL STORAGE INSTALLATION .

l i l License Amendment Request dated August 31,1999 l

l Revised Pages Appendix A, Technical Specifications 3/4-1 3/4-2 l 3/4-10 Special Nuclear Material License 1

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, .3/4.1. FUEL TO'BE STORED AT ISFSI

LIMITING CONDITION FOR OPERATION .

! ' 3. l '.1 The spent nuclear fuel to be received and stored in the TN-40 cask at the Prairie. Island ISFSI shall meet the following requirements:

-(1) Only fuel irradiated at the Prairie Island Nuclear

! . Generating Plant Unit Nos. 1 and 2 may be used.

'(2) Maximum initial enrichment shall not exceed 3.85

~

weight percent U-235.

.(3) Maximum Assembly average burnup shall not exceed 45,000 megawatt-days per metric ton uranium.

(4) Fuel shall have cooled a minimum of 10 years after l reactor. discharge, before storage in the ISFSI. l (5) Fuel shall be intact unconsolidated fuel. Partial fuel assemblies, that is, fuel assemblies from which '

i- fuel pins are missing must not be loaded unless dummy fuel pins are used to displace an amount of water equal'to that displaced by the original pins.

i (6) Fuel assemblies known or suspected to have structural defects or gross cladding failures (other than pinhole leaks) sufficiently severe to adversely affect fuel handling and transfer capability shall not be loaded  ;

into the cask for storage.

(7) The burnup of burnable poison rod assemblies (BPRA) inserted inside spent fuel assemblies shall not exceed a cask average of 30,000 MWD /MTU.

(8) Any BPRA inserted inside any spent fuel assembly shall have cooled for a minimum of 18 years.

~(9) The burnup of thimble plugging devices (TPD) inserted inside spent fuel assemblies shall not exceed a cask average of 125,000 MND/MTU.

(10) Any TPD inserted inside any spent fuel assembly shall have cooled for a minimum of 9 years.

APPLICABILITY: This specification is applicable to all spent fuel to be loaded and stored in the TN-40 cask at the Prairie Island ISFSI.

3/4-1 a-

E .; e

,. ACTION: If the requirements of the above specification are not met, l

do not lead the fuel assembly into the TN-40 cask.

. SURVEILLANCE REQUIREMIDITS:

l 4.1.1 Each fuel assembly and fuel assembly insert (BPRA or TPD) to be loaded l l shall have~the above specifications independently verified and documented.

l l 4.1.2 Before inserting a spent fuel assembly into a cask and again before closing.the cask, the identity of each fuel assembly and the type of each fuel assembly insert (BPRA or TPD) shall be independently verified and documented.

BASIS: The design criteria and subsequent safety analyses of the Prairie Island ISFSI and storage' casks assumed certain characteristics and limitations l for the fuel that is to be stored. Specification 3/4.1 ensures that the

~

j' integrity of the fuel .is protected by defining characteristics such as the source of the spent fuel, maximum initial enrichment, irradiation history, and minimum post-irradiation cooling time.

A measure of the irradiation history of a fuel insert is referred to as the "burnup" of the fuel insert. Application of this term to an item without any uranium content is not technically precise but provides for a consistent and concise terminology. The burnup of a fuel insert is defined to be the i cumulative.burnup accumulated by each fuel assembly during the residency of I

the fuel. insert. l

[ l l _

This specification was derived to ensure that the peak fuel rod l- temperatures, cask surface contact dose rates, reactivity, and fuel mass are l below the design values.

l 3/4-2

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l c Table 3/4-1 TN-40 CASK OPERATING LIMITS f L

Operating Limit 1

Maximum Lifting Height with a Non-Redundant I Lifting Device 18 inches (45 cm)

Maximum Cask Surface Temperature 250 F (121 C) ,

l Maximum Surface Dose Rate (or equivalent at 2 meters) 200 mrem /hr l l

Maximum Removable Surface Contamination 1

Beta and Gamma 1000 dpm/100 cm2 j l

Alpha 20 dpm/100 cm2 Maximum Helium Leak Rate 10'5 atm-cc/s Initial Helium Pressure (Cask Cavity). 20 i i psia l (1.4 bar i 70 mbar) )

l Pressure During Cask Drying Test (held for 30 min.) s 10 mbar I 1

l Boron Concentration in Pool and Cask 2 1800 ppm  !

Storage Capacity 5 40 assemblies Fuel Assembly Characteristics Initial Enrichment, U-235 s 3.85 wt. %

Average Burnup s 45,000 MWD /MTU Time after Irradiation 2 10 years l

BPRA Fuel Insert Characteristics Average Burnup s 30,000 MWD /MTU Time after Irradiation 2 18 years TPD Fuel Insert Characteristics Average Burnup s 125,000 MWD /MTU Time after Irradiation 2 9 years 3/4-10

Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 l (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter I, Part 72, and in j reliance on statements and representations heretofore made by the Licensee, a License is hereby ismaed authorizing the Licensee to receive, acquire, and possess the power reactor spent fuel and other* radioactive materials associated with spent fuel storage designated below; to use such materials for the purposes and at the place designated below; and to deliver or transfer such materials to persons authorized to receive these materials in accordance with the regulations of the applicable Parts of 10 CFR Chapter I. This License shall be deemed to contain the conditions specified in Section 183 of the Atcenic Energy Act of 1954, as --ded, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter {

in effect and to any conditions specified herein.

l Licensee t

1. Northern States Power Company

3. License Number: SNM-2506

3. Address:

Amendment 3 dated l 414 Nicollet Mall 4. Expiration Date:

Minneapolis, Minnescta 55401 October 31, 2013

5. Docket Number: 72 .0

6. Byproduct, source, and/ 7. Chemical and/or 8. Maximum amount that or special nuclear physical form that licensee may ,

material possess at any one '

time under this license A. Spent fuel assemblies A. As UO2 clad with A. 715.28 TeU of from Prairie Island Nuclear zirconium or spent fuel Station Units 1 and 2 zirconium alloys assemblies reactor, using natural wates.

for cooling and enriched not greater than 3.85 percent U-235, and associated radio-active materials related to receipt, storage, and transfer of the fuel assemblies B. Irradiated fuel assembly B. SS 304 structure, B. One BPRA or inserts from Prairie Island Inconel 718 spring TPD per spent Nuclear Station Units 1 and 2 and borated pyren fuel assembly.

reactor. An insert may be a glass.

burnable poison rod assembly (BPRA) or a thimble plugging device (TPD).

9. Authorized Use: For use in accordance with statements, representations, and the conditiona of the Tuchnical Specifications and Safety Analysis Report dated August 31, 1S90, and supplements dated October 29, 1990; April 2, June 5, Octobar 9 ;usd 31, November 15, December 11, 20, and 23, 1991; January 17, February o, 10, and 12, March 2 and 5, April 3, 22, and 23, July 10, August 12, 13, and 14, 1992; and October 2, 1995.

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