ML12160A063
| ML12160A063 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 06/05/2012 |
| From: | Hruby R Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML12160A063 (8) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 June 5, 2012 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 10 CFR 50.36 NRC Docket No. 50-391
Subject:
Watts Bar Nuclear Plant (WBN) Unit 2 - Submittal of Revised Section 4.3, "Fuel Storage," Developmental Revision G of the Unit 2 Technical Specification (TS)
Reference:
TVA Letter to NRC dated February 12, 2012, "Watts Bar Nuclear Plant (WBN) Unit 2 - Submittal of Developmental Revision G of the Unit 2 Technical Specification (TS) and Technical Specification Bases" This letter provides a correction to TS Section 4.3 on Fuel Storage previously submitted by the referenced letter. Also provided is a change to the title of Figure 4.3.3. This change was not made previously and is being made to clarify that the figure also applies to new fuel stored in fuel pool. provides a mark-up of the two changed pages. Enclosure 2 provides a final version with the changes incorporated.
There are no new regulatory commitments associated with this letter.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 5 th day of June, 2012.
Respectfull Raymond A. Hruby, Jr.
General Manager, Technical Services Watts Bar Unit 2
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
Enclosure I 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 initial enrichments grator than 3.80 weight peFGent and less than a maximum of 5 percent enrichment (nominally 4.95 +/- 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 7.0 6.5 6.0 5.5 5.0 4.5 4.0 3.5 3.0 2.5 2.0 1.5 1.0 0.5 0.0 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 (developmental) 4.0-8 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 +/- 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 7.0 6.5 6.0 5.5 5.0 4.5 4.0 3.5 3.0 2.5 2.0 1.5 1.0 0.5 0.0 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 (developmental) 4.0-8 G