ML20148S049
| ML20148S049 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/01/1997 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20148S054 | List: |
| References | |
| NUDOCS 9707080096 | |
| Download: ML20148S049 (10) | |
Text
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p UNITED STATES g
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20066 4001 o%...../
TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-327 SE0V0YAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 225 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated March 13, 1997, as supplemented on June 26, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment-can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9707080096 970701 PDR ADOCK 05000327 P
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment.
Paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:'
L l-(2) Technical Soecifications l
l The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 225, are hereby incorporated in the l
license. The licensee 1shall operate the facility in accordance with the Technical Specifications.
l 3.
This license' amendment is effective as of its date of issuance, to be L
implemented no later than 45 days-of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/7
' R h tL Y V.sfrederick J. Hebdon, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
- 1. Changes to the Technical Specifications Date of Issuance: July 1,1997 l
l
p ATTACHMENT TO LICENSE AMENDMENT NO. 225 4
FACILITY OPERATING LICENSE NO. DPR-77 DQ[KET NO. 50-327 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines j.
indicating the area of change.
l REMOVE INSERT f
5-Sa 5-Sa 5-5f i
1 i
I t
I-l i
4 f
i i
i t
DESIGN FEATURES l
1 5.6 FUEL STORAGE each other and from the inner Region 3 cells by at least one (1)
Region 2 spenn fuel assembly (i.e.,
fuel of 50 MWD /KgU burnup or equivalent).
2.
Region 1 fuel assemblies located along the wide water-gaps ** between l
storage modules must be isolated from each other and from the inner Region 3 cells by at least one (1) Region 2 spent fuel assembly (i.e., fuel of 50 MWD /KgU assembly average burnup or equivalent).
3.
Region 1 fuel assemblies located along the narrow water-gaps **
between storage modules must be isolated from each other by at least two (2) Region 2 spent fuel assemblies and from the inner Region 3 cells by at least one (1) Region 2 spent fuel assembly (i.e., fuel of 50 MWD /KgU assembly average burnup or equivalent).
4.
A checkerboard pattern of fresh fuel and empty cells may be used throughout any storage module, or internal to any storage module in lieu of Region 3 fuel as shown in Figure 5.6-2.
Figure 5.6-1 shows a typical arrangement of regions.
Figure 5.6-2 illustrates internal module checkerboarding of fresh fuel with empty cells in a portion of the fuel pool. Figure 5.6-3 illustrates the two burnup-enrichment equations (5.6.1.1.c.2 and 5.6.1.1.c.3) in graphical form, e.
Only spent fuel meeting the Region 3 burnup requirements chall be stored in any module in the cask loading area of the cask pit.
CRITICALITY - NEW FUEL 5.6.1.2 The new fuel pit storage racks are designed for fuel enriched to 5.0 weight percent U-235 and shall be maintained with the arrangement of 146 storage locations shown in Figure 5.6-4.
The cells shown as empty cells in Figure 5.6-4 shall have physical barriers installed to ensure that inadvertant loading of fuel assemblies into these locations does'not occur.
The remaining storage cells must remain empty (contain no fuel assemblies). This configuration ensures k, will remain less than or equal to 0.95 when flooded with unborated water and less than or equal to 0.98 under optimum moderation conditions.
DRAINAGE 5.6.2 The spent fuel pit is designed and shall be unintained to prevent inadvertent draining of the pool below elevation 722 ft.
- The nominal gap (2-1/8 inches) running in the E-W direction between the l
adjacent modules is referred to as the " wide gap. "
The N-S direction gap (1.5 inch) is referred to as the " narrow gap."
SEQUOYAH - UNIT 1 5-5a Amendment No. 13, 60, 114, 144, 167, 225
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l L.
Basic Cell 21 inch X 21 inch Empty Cell
=
9 4 X 5 Cell Racks 146 /180 Loading Pattern 1
i Figure 5.6-4 New Fuel Pit Storage Rack Loading Pattern i
SEQUOYAH - UNIT 1 5-5f Amendment No. 225
- "t ro o
UNITED STATES f
j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20066 4001 TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-328 FE000YAH NVCLEAR PLANT. UNIT 2 1
AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.216 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that-A.
The application for amendment by Tennessee Valley Authority (the licensee) dated March 13, 1997, as supplemented on June 26, 1997, complies "ith the standards and requirements of the Atomic Energy Act of 1934, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering $in health and safety of the public, and (ii) that such activities e: 1 be 1
conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
..-..~ -.
2.
Accordingly, the license is amended b) changes to the Technical Specification 2 as indicated in the attachment to this license amendment.
1 Paragraph 2.C.(2) of Facility Operating 1.icense No. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as
!~
revised through Amendment No. 216, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented no later than 45 days of its issuance.
t i
FOR THE NUCLEAR REGULATORY COMMISSION t
$^
'Y%
I rederick J. Hebdon, Director 1 _
Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Roactor Regulation
Attachment:
- 1. Chanc ' 'o the Technical
.:ifications 5
Date of Issuance: July 1,1997 i
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ATTACHMENT T0 LICENSE AMENDMENT N0. 216 FACILITY OPERATING LICENSE NO. OPR-72 DOCKET N0. 50-328 i
Revise the Appendix A Technica! Specifications by removing the pages identified below tad inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 5-Sa 5-Sa 5-5f i
i t
DESIGN FEATURES 5.6 FUEL STORAGE each other and from the innter Region 3 cell by at least one (1) Region 2 spent fuel assembly (i.e.,
fuel of 50 MWD /KgU burnup or equivalent).
2.
Region 1 fuel assemblies located tlong the wide water-gaps **
between storage modules must be isolated from each other and 1
from the inner Region 3 cells by at least one (1) Region 2 spent fuel assembly (i.e., fuel of 50 MWD /KgU assembly average j
burnup or equivalent).
3.
Region 1 fuel assemblies located along the narrow water-gaps **
between storage modules must be isolated from each other by at least two (2) Region 2 spent fuel assemblies and from the inner Region 3 cells by at least one (1) Region 2 spent fuel i
assembly (i.e., fuel of 50 MWD /KgU assembly average burnup or equivalent).
4.
A checkerboard pattern of fresh fuel and empty cells may be used throughout any storage module, or internal to any storage module in lieu of Regior. 3 fuel as shown in Figure 5.6-2.
Figure 5.6-1 shows a typical arrangement of regions.
Figure 5.6-2 illustrates internal module checkerboarding of fresh fuel with empty j
cells in a portion of the fuel pool.
Figure 5.6-3 illustrates the two burnup-enrichment equations (5.6.1.1.c.2 and 5.6.1.1.c.3) in graphical form.
e.
Only spent fuel meeting the Region 3 burnup requirements shall be stored in any module in the cask loading area of the cask pit.
CRITICALITY - NEW FUEL 5.6.1.2 The new fuel pit storage racks are designed for fuel enriched to 5.0 weight percent U-235 and shall be maintained with the arrangement of 146 storage locations shown in Figure 5.6-4.
The cells shown as empty cells in Figure 5.6-4 shall have physical barriers installed to ensure that inadvertant loading of fuel assemblies 3.nto these locations does not occur. The remaining storage cells must remain empty (contain no fuel assemblies). This configuration ensures k,, will remain less than or equal to 0.95 when flooded with unborated water and less than or equal to 0.98 under optimum moderation conditions.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 722 ft.
- The nominal gap (2-1/8 inches) running in the E-W direction between the adjacent modules is referred to as the " wide gap."
The N-S direction gap (1.5 inch) is referred to as the " narrow gap."
SEQUOYAH - UNIT 2 5-Sa Amendment Nos.
4, 52, 125, 157,216
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1 i
i l
1_
=
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I_
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Basic Cell 21 inch X 21 inch i
Empty Cell 9 - 4 X 5 Cell Racks i
146 /180 Loading Pattern Figure 5.6-4 New Fuel Pit Storage Rack Loading Pattern SEQUOYAH - UNIT 2 5-5f Amendment No. 216
.