ML072770735
| ML072770735 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/01/2007 |
| From: | NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | |
| pickett , NRR/DORL, 415-1364 | |
| References | |
| TAC MD3295 | |
| Download: ML072770735 (15) | |
Text
(b)
Pursuant to the Act and 10 CFR Part 70, to possess and use four (4) mixed oxide fuel assemblies in accordance with the RG&E's application dated December 14, 1979 (transmitted by letter dated December 20, 1979) as supplemented February 20, 1980 and March 5, 1980; (3)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
(1)
Maximum Power Level Ginna LLC is authorized to operate the facility at steady-state power levels up to a maximum of 1775 megawatts (thermal).
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 103, are hereby incorporated in the renewed license.
,he licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Fire Protection (a)
The licensee shall implement and maintain in effect all fire protection features described in the licensee's submittals referenced in and as approved or modified by the NRC's Fire Protection Safety Evaluation (SE) dated February 14, 1979 and Amendment No. 103
SFP Storage 3.7.13 3.7 PLANT SYSTEMS Spent Fuel Pool (SFP) Storage 3.7.13 LCO 3.7.13 APPLICABILITY:
The combination of initial enrichment and burnup values, with appropriate decay times, of each fuel assembly stored in the spent fuel pool shall be within the acceptable burnup domain of the applicable Figures 3.7.13-1 through 3.7.13-11, based on region and cell type.
Whenever any fuel assembly is stored in the spent fuel pool.
ACTIONS CONDITION
[
REQUIRED ACTION COMPLETION TIME A.
Requirements of the LCO A.1 not met.
- NOTE -
LCO 3.0.3 is not applicable.
Initiate action to move the Immediately noncomplying fuel assembly to an acceptable storage location.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Verify by administrative means the initial enrichment, Prior to storing, or burnup, and decay time of the fuel assembly is in moving, the fuel accordance with the applicable Figures 3.7.13-1 assembly in the through 3.7.13-11.
spent fuel pool R.E. Ginna Nuclear Power Plant 3.7.13-1 Amendment 103
SFP Storage 3.7.13 A
Acceptable burnup domain for storage in any location within Region I B
Acceptable bumup domain for storage in cells with lead-in funnels only Figure 3.7.13-1 irn i s
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R.E. Ginna Nuclear Power Plant 3.7.13-2 Amendment 103
SFP Storage 3.7.13 70000 65000 60000 55000 60000
~45000 40000 35000 S30000 25000 20000 15000 10000 5000 0
I____ 1 I___
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4 4-Al z7 1 2
.2 3 0
0.5 1
1.5 2
2.5 3
3.5(
Assembly Nominal Initial Enrichment (Wt%).
4 4.5 5
5.5 Al Acceptable burnup domain for storage in any location within Region 2 Type I Cells A2 Acceptable bumup domain for storage face-adjacent to a Type Al or A2 assembly, or a water cell witin Region 2 Type I Cells B
Acceptable burnup domain for storage face-adjacent to a Type Al assembly, or a water cell witbin Region 2 Type 1 Cells C
Acceptable bamop domain for storage face-adjacent to a water cell only, within Region 2 Type 1 Cells Figure 3.7.13-2 Burnup Vs =*" "ch'et C
'urives for Region 2 Type C
s (No U-R.E. Ginna Nuclear Power Plant 3.7.13-3 Amendment 103
SFP Storage 3.7.13 70000 85000D_______
600 Al.
55000 5OOO0 A
45000 30000
,A20000 15000 10000 0
e 0
0.5 1
1.5 2
2.5 3
3.5 4
4.5 5
5.5 Assembly Nominal Initial Enrichment (WtI Al Acceptable burnup domain for storage in any location within Region 2 Type 1 Cells AZ Acceptable bumup domain for storage face-adjacent to a Type Al or A2 assembly, or a water cell within-Region 2 Type I Cells B
Acceptable burnup domain for storage face-adjacent to a Type Al assembly, or a water cell within Region 2 Type I Cells C
Acceptable bumup domain for storage face-adjacent to a water cell only, within Region 2 Type 1 Cells Figure 3.7.13-3 Burnup Vs Enrichment Curves for Region 2 Type I Cells (5-Year Pu-241 Decay)
R.E. Ginna Nuclear Power Plant 3.7.13-4 Amendment 103
SFP Storage 3.7.13 70000 65000 60000 65000 50000 45000 40000 395000 E
30000 26000 20000 15000 10000 A
6000 0
0 0.6 1
1.5 2
2.5 3
3.5 4
4.5 5
5.5 Assembly Nominal Initial Enrichment (Wt%)
Al Acceptable burnup domain for storage in any location within Region 2 Type I Cells A2 Acceptable bumup domain for storage face-adjacent to a Type Al or A2 assenbly, or a water cell within Region 2 Type I Cells B
Acceptable bumuap domain for storage face-adjacmt to a Type Al assembly, or a water ceii wiamin Region 2 Type i Cells C
Acceptable burnup domain for storage face-adjacent to a water cell only, within Region 2 Type I Cells Figure 3.7.13-4 ou.up IV's Enrichment Curves for Region 2 Type i Cells (1u-Year Pu-24i Decay)
R.E. Ginna Nuclear Power Plant 3.7.13-5 Amendment 103
SFP Storage 3.7.13 70000 05000 60000 56000 A
50000 25000 260000 15000 10000 25000 2000 0
0.5 1
1.5 2
2.5 3
3.5 4
4.5 5
5.5 Assembly Nominal Initial Enrichment (Wt%)
Al Acceptable bumup domain for storage in any location within Region 2 Type I Cells A2 Acceptable bumup domain for storage face-adjacent to a Type Al or A2 assembly, or a water cell within Region 2 Type I Cells B
Acceptable bumup domain for storage face-adjacentio a Type Al assembly, or a water ceii within Region 2 Type I Cells C
Acceptable burnup domain for storage face-adjacent to a water cell only, within Region 2 Type I Cells Figure 3.7.13-5 Burnup' Vs,,.,.,,.
n* Curves for Region 2 Type I Cells (15-Year Pu-241 Decay)
R.E. Ginna Nuclear Power Plant 3.7.13-6 Amendment 103
SFP Storage 3.7.13 70000 65000
]
60000 55000 Al 50000 0.2 456000 4000 30000 E
,a 25000
[
7z 15000 10000 5000 0
A 0
0.5 1
1.5 2
2.5 3
3.5 4
4.5 5
5.6 Assembly Nominal Initial Enrichment (Wt"P)
Al Acceptable burnup domain for storage in any location within Region 2 Type 1 Cells A2 Acceptable bumnup domain for storage face-adjacent to a Type Al or A2 assembly, or a water cell within Region 2 Type I Cells B
Acceptable.bunrnu domainr fw stnrgfa3ce-tdj oe.t a 'T-o
. Al asS,.ly,"
or a water cell within Region 2 Type I Cells C
Acceptable burnup domain for storage face-adjacent to a water cell only, within Region 2 Type 1 Cells Figure 3.7.13-6 s
,' Curves for Region 2 Type 1 Cells (20-Year Pu-241 Decay)
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R.E. Ginna Nuclear Power Plant 3.7.13-7 Amendment 103
SFP Storage 3.7.13 45000
-. 30000 25000 E~.20000 1.5 2
2.5 3
3.5 4
Asembly Nominal Initial Enrichment (Wt%)
4.5 5
5.5 Al A2 B
C Acceptable burnup domain for storage in any location within Region 2 Type 2 Cells Acceptable burnup domain for storage face-adjacent to a Type Al or A2 assembly, or a water cell within Region 2 Type 2 Cells Acceptable burnup domain for storage face-adjacent to a Type AI assembly, or a water cell within Region 2 Type 2 Cells Acceptable burnup domain for storage face-adjacent to a water cell only, within Region 2 Type 2 Cells Figure 3.7.13-7 Burnup Vs Enrichment Curves for Region 2 Type 2 Ceils (No Pu-241 Decay)
I R.E. Ginna Nuclear Power Plant 3.7.1-3-8 Amendment 103
SFP Storage 3.7.13 45000 40000 35600 30000 25000 E
CO 20000 16000 10000 5000 0
I 1
1.5 2
2.5 3
3.5 4
4.5 5
5.5 Assembly Nominal Inial Enrichment (WN.)
Al Acceptable burnup domain for storage in any location within Region 2 Type 2 Cells A2 Acceptable burnup domain for storage face-adjacent to a Type Al or A2 assembly, or a water cell within Region 2 Type 2 Cells B Accptable bu,,,up uumai ir stoiage face-adjacent to a Type AI assembly, or a water cell within Region 2 Type 2 Cells C
Acceptable bumup domain for storage face-adjacent to a water cell only, within Region 2 Type 2 Cells Figure 3.7.13-8 Burnup Vs Enrichment Curves
.for Region 2 Type 2 Cells (5-Year Pu-241 Decay) i R.E. Ginna Nuclear Power Plant 3.7.13-9 Amendment 103
SFP Storage 3.7.13 45000 3M00 25000 E
2 20000 15000 1
1.5 2
2.5 3
3.5 4
Assembly Nominal Initial Enrichment (Wt%)
4.5 5
5.5 Al A2 B
C Acceptable burnup domain for storage in any location within Region 2 Type 2 Cells Acceptable burnup domain for storage face-adjacent to a Type AI or A2 assembly, or a water cell within Region 2 Type 2 Cells Acceptable burnup domain for storage face-adjacent to a Type A l assembly, or a water cell within Region 2 Type 2 Cells Acceptable burnup domain for storage face-adjacent to a water cell only, within Region 2-Type 2 Cells Figure 3.7.13-9 Burnup IV's Enrichment Curves for Region 2 Type 2 Cells
"(1-Year Pu-241 De(ay)
LJ L_
1 11 t
,ý Iu-1% 1 Pu-241k 1Ucay) i R.E. Ginna Nuclear Power Plant 3.7.13-10 Amendment 103
SFP Storage 3.7.13 Al A2 B
C Acceptable burnup domain for storage in any location within Region 2 Type 2 Cells Acceptabie bmynup domain for storage face-adjacent to a Type Al or A2 assembly, or a wate cell within Region 2 Type 2 Cells or a water cell within Region 2 Type 2 Cells Acceptable bumnup domain for storage face-adj acent to a water cell only, wilhin Region 2 Type 2 Cells Figure 3.7.13-10 Burnup V'.... r. chin. C.ur-es fi'* Dow n; R
o1l 2
s 'k 1 V..
D,,
ýA I e....A R.E. Ginna Nuclear Power Plant 3.7.13-11 Amendment 103
SFP Storage 3.7.13 45000 40000 350OO 30000
> 20000 15000 10000 5000 0
1.5 2
215 3
3.5 4
4.5 5
5.5 Assembly Nominal Initial Enrichment (Wl/.)
Al A2 B
C Acceptable burnup domain for storage in any location within Region 2 Type 2 Cells Acceptable burnup domain for storage face-adjacent to a Type Al or A2 assembly, or a water celi within Region 2 Type 2 Cells A*cyvpabui buraup duou,,a fur.tolage face-adjacent to a Type Ai assembly, or a water cell within Region 2 Type 2 Cells Acceptable burnup domain for storage face-adjacent to a water cell only, within Region 2 Type 2 Cells Figure 3.7.13-11 Burnu... Vs Enri-hmnnt Cu.,rves for'- RPegion 9 T.no 2 C'e)lsonAvcr
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II R.E. Ginna Nuclear Power Plant 3.7.13-12 Amendment 103
Fuel Storage 4.3 4.0 DESIGN FEATURES 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
- a.
Fuel assemblies having a maximum nominal U-235 enrichment of 5.0 weight percent;
- b.
keff < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;
- c.
keff < 0.95 if fully flooded with water borated to > 975 ppm, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; and
- d.
Consolidated rod storage canisters may be stored in the spent fuel storage racks provided that the fuel assemblies from which the rods were removed meet all the requirements of LCO 3.7.13 for the region in which the canister is to be stored. The average decay heat of the fuel assembly from which the rods were removed for all consolidated fuel assemblies must also be _ 2150 BTU/hr.
4.3.1.2 The new fuel storage dry racks are designed and shall be maintained with:
- a.
Fuel assemblies having a maximum nominal U-235 enrichment of 5.0 weight percent;
- b.
keff 5 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; and
- c.
keff < 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR.
R.E. Ginna Nuclear Power Plant 4.3-1 Amendment 103
Fuel Storage 4.3 4.3.2 Drainage The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 257'0" (mean sea level).
4.3.3 Capacity The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 1321 fuel assemblies.
R.E. Ginna Nuclear Power Plant 4.3-2 Amendment 103