ML12163A050

OL - TVA Letter to NRC_06-05-12 Fuel Storage TS Submittal

ML12163A050
Person / Time
Site:	Watts Bar
Issue date:	06/06/2012
From:	- No Known Affiliation
To:	Division of Operating Reactor Licensing
References
Download: ML12163A050 (11)

Text

WBN2Public Resource From: Boyd, Desiree L [dlboyd@tva.gov]

Sent: Wednesday, June 06, 2012 8:31 AM To: Epperson, Dan; Poole, Justin; Raghavan, Rags; Milano, Patrick; Campbell, Stephen Cc: Arent, Gordon; Hamill, Carol L; Boyd, Desiree L

Subject:

TVA letter to NRC_06-05-12 Fuel Storage TS Submittal Attachments: 06-05-12 Fuel Storage TS Submittal_Final.pdf Please see attached TVA letter that was sent to the NRC today.

Thank You,

~*~*~*~*~*~*~*~*~*~*~

Désireé L. Boyd WBN Unit 2 Licensing dlboyd@tva.gov 423-365-8764 1

Hearing Identifier: Watts_Bar_2_Operating_LA_Public Email Number: 699 Mail Envelope Properties (7AB41F650F76BD44B5BCAB7C0CCABFAF2DA4C378)

Subject:

TVA letter to NRC_06-05-12 Fuel Storage TS Submittal Sent Date: 6/6/2012 8:31:24 AM Received Date: 6/6/2012 8:31:28 AM From: Boyd, Desiree L Created By: dlboyd@tva.gov Recipients:

"Arent, Gordon" <garent@tva.gov>

Tracking Status: None "Hamill, Carol L" <clhamill@tva.gov>

Tracking Status: None "Boyd, Desiree L" <dlboyd@tva.gov>

Tracking Status: None "Epperson, Dan" <Dan.Epperson@nrc.gov>

Tracking Status: None "Poole, Justin" <Justin.Poole@nrc.gov>

Tracking Status: None "Raghavan, Rags" <Rags.Raghavan@nrc.gov>

Tracking Status: None "Milano, Patrick" <Patrick.Milano@nrc.gov>

Tracking Status: None "Campbell, Stephen" <Stephen.Campbell@nrc.gov>

Tracking Status: None Post Office: TVANUCXVS2.main.tva.gov Files Size Date & Time MESSAGE 274 6/6/2012 8:31:28 AM 06-05-12 Fuel Storage TS Submittal_Final.pdf 311205 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

U.S. Nuclear Regulatory Commission Page 2 June 5, 2012

Enclosures:

1. WBN Unit 2 TS Section 4.3 Mark-up

2. WBN Unit 2 TS Section 4.3 Clean Version of Changed Pages cc (Enclosures):

U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381

U.S. Nuclear Regulatory Commission Page 3 June 5, 2012 bcc (Enclosures):

Stephen Campbell U.S. Nuclear Regulatory Commission MS 08H4A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Fred Brown, Deputy Regional Administrator for Construction U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257

Enclosure 1 WBN Unit 2 TS Section 4.3 Mark-up

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks (shown in Figure 4.3-1) are designed and shall be maintained with:

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

b. keff < 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Sections 4.3.2.7 and 9.1 of the FSAR;

c. Distances between fuel assemblies are a nominal 10.375 inch center-to-center spacing in the twenty-four flux trap rack modules.

d. Fuel assemblies with enrichments less than or equal to 3.80 weight percent U-235 are allowed unrestricted storage.

d. Fuel assemblies with initial enrichments greater than 3.80 weight percent and less than a maximum of 5 percent enrichment (nominally 4.95 r 0.05 percent) may be stored in the spent fuel racks in one of four arrangements with specific limits as identified below:

1. New and spent fuel assemblies may be stored in the racks in an all cell arrangement provided the burnup of each assembly is in the acceptable domain identified in Figure 4.3-3, depending upon the specified initial enrichment.

2. New and spent fuel assemblies may be stored in a checkerboard arrangement of 2 new and 2 spent assemblies, provided that each spent fuel assembly has accumulated a minimum burnup in the acceptable domain identified in Figure 4.3-4.

3. New fuel assemblies may be stored in 4-cell arrays with 1 of the 4 cells remaining empty of fuel (i.e.

containing only water or water with up to 75 percent by volume of non-fuel bearing material.

Watts Bar - Unit 2 4.0-2 (developmental) G

Design Features 4.0 ACCEPTABLE BURNUP DOMAIN Burnup, MWD/kgU UNACCEPTABLE BURNUP DOMAIN Initial Enrichment wt% U-235 FIGURE 4.3-3 MINIMUM REQUIRED BURNUP FOR UNRESTRICTED STORAGE OF NEW AND SPENT FUEL OF VARIOUS INITIAL ENRICHMENTS Watts Bar - Unit 2 4.0-8 (developmental) G

ENCLOSURE 2 WBN Unit 2 TS Section 4.3 Clean Version of Changed Pages

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks (shown in Figure 4.3-1) are designed and shall be maintained with:

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

b. keff < 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Sections 4.3.2.7 and 9.1 of the FSAR;

c. Distances between fuel assemblies are a nominal 10.375 inch center-to-center spacing in the twenty-four flux trap rack modules.

d. Fuel assemblies with initial enrichments less than a maximum of 5 percent enrichment (nominally 4.95 r 0.05 percent) may be stored in the spent fuel racks in one of four arrangements with specific limits as identified below:

1. New and spent fuel assemblies may be stored in the racks in an all cell arrangement provided the burnup of each assembly is in the acceptable domain identified in Figure 4.3-3, depending upon the specified initial enrichment.

2. New and spent fuel assemblies may be stored in a checkerboard arrangement of 2 new and 2 spent assemblies, provided that each spent fuel assembly has accumulated a minimum burnup in the acceptable domain identified in Figure 4.3-4.

3. New fuel assemblies may be stored in 4-cell arrays with 1 of the 4 cells remaining empty of fuel (i.e.

containing only water or water with up to 75 percent by volume of non-fuel bearing material.

Watts Bar - Unit 2 4.0-2 (developmental) G

Design Features 4.0 ACCEPTABLE BURNUP DOMAIN Burnup, MWD/kgU UNACCEPTABLE BURNUP DOMAIN Initial Enrichment wt% U-235 FIGURE 4.3-3 MINIMUM REQUIRED BURNUP FOR UNRESTRICTED STORAGE OF NEW AND SPENT FUEL OF VARIOUS INITIAL ENRICHMENTS Watts Bar - Unit 2 4.0-8 (developmental) G