ML20078C300
| ML20078C300 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 01/20/1995 |
| From: | Dick G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078C304 | List: |
| References | |
| NPF-37-A-068, NPF-66-A-068, NPF-72-A-058, NPF-77-A-058 NUDOCS 9501260256 | |
| Download: ML20078C300 (17) | |
Text
-
UNITED STATES 9
j
'j NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 30806 4001
%,...../
COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 PYRON STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 68 License No. NPF-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the
~
licensee) dated November 7,1994, as supplemented December 16, 1994, 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 sssurance ;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.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby l
amended to read as follows:
5 l
9501260256 950120 PDR 4MCK 05000454 P
. (2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 68 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Fnsit onmental Protection Plan.
3.
This license aa ndment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Wk George F. Dick, 'Jr., Pr ect Mana Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January.
1995
f* ** %
g.s UNITED STATES NUCLEAR REEULATORY COMMISSION If WASHINGTON, D.C. 30865-0001
%...../
COMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 68 License No. NPF-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 7, 1994, as supplemented December 16, 1994, 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 1; 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.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-66 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A (NUREG-Ill3),
as revised through Amendment No. 68 and revised by Attachment 2 to NPF-66, and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated into this license. Attachment 2 contains a revision to Appendix A which is hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
George F. Dick, Jr., Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications t
Date of Issuance: January 20, 1995
ATTACHMENT TO LICENSE AMENDMENT NOS. 68 AND 68 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET N05. STN 50-454 AND STN 50-455 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Remove Paaes Insert Paaes 5-5 5-5 5-Sa 5-Sa 5-5b i
i l
i
't
i DESIGN FEATURES I
5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with a k 'u' des a conservative allowance for uncertainties as described in less than or equal to 0.95 when flooded with unborated water, which incl of the UFSAR. This is ensured by controlling fuel assembly placement in each region as follows:
a.
REGION 1 1.
A nominal 10.32 inch north-south and 10.42 inch east-west, center-to-center distance is maintained between fuel assemblies placed in the spent fuel storage racks.
2.
Fuel assemblies may be stored in this region with a) a maximum nominal initial U-235 enrichment of less than or equal to 4.2 weight percent, or b) a maximum nominal initial U-235 enrichment of 5.0 weight percent with sufficient Integral Fuel Burnable Absorbers present in each fuel assembly such that the maximum reference fuel assembly km is less than or equal to 1.470 at 68'F.
b.
REGION 2 1.
A nominal 9.03 inch center-to-center distance is maintained between fuel assemblies placed in the spent fuel storage racks.
2.
a)
Fuel assemblies may be stored in this region with a maximum nominal initial U-235 enrichment of 1.6 weight percent with no burnup and up to 5.0 weight percent U-235 with a minimum discharge burnup as specified in Figure 5.6-1, or b)
Fuel assemblies with a maximum nominal initial U-235 enrichment of greater than 1.6 and less than or equal to 4.2 weight percent that do not meet the M nimun burnup specified in Figure 5.6-1, shall be loaded in a checkerboard pattern for stor:ge in this region.
5.6.1.2 The k,,, for new fuel for the first core loading stored dry in the spent fuel storage racks shall not sxceed 0.98 when aqueous foam moderation is assumed.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 423 feet 2 inches.
[APACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 2870 fuel assemblies.
BYRON - UNITS 1 & 2 5-5 Amendment No. 68
a ',
1 DESIGN FEATURES 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
B r
i i
i e
i i
BYRON - UNITS 1 & 2 5-Sa Amendment No. 68 i
I s
w
.o,
- - - - ~.. - -
e 50,000 2
45,000 Enrichment Burnup
/
(w/c)
(MWD /NTU)
/
[
1.60 0 i f
1.00 4.635
/
2.00 8,565
/
40,000 2.20 11,845
/
2.40 14,729 Acceptable I
/
2.60 17,397 Region N
/
2.80 20,085 35,000 3.00 22,742 f
sg 3.20 25,132
/
f, 3.40 27,810
/
~
3.60 30,179
/
r2,30,000 -- 3.80 32.651
/
b 4.00 35,047
/
4.20 37,389 4.40 39,655 f
l 4.60 42,024
/
C 25,000 --
4.80 44,290
/
g e
5.00 46,442
/
/
0 20,000 Q
'/
Unacceptable Region y
f
/l
, 15,000
,j N
//
/
10,000 f
/ i i
/
/
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5.000 lf I I i
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~
I i
.I' O
s,,
i
,, i 1.60 2.00 2.40 2.80 3.20 3.60 4.00 4.40 4.80 5.20 Fuel Assembly Initial U-235 Enrichment (w/o)
Notes:
The use of linear interpolation between the minimum burnups reported above is acceptable.
FIGURE 5.6 - 1 MINIMUM BURNUP VERSUS INITIAL ENRICHMENT FOR REGION 2 STOR4GE BYRON - UNITS 1 & 2 5-5b Amendment No. 68
.g ym pw g
UNITED STATES fi S
NUCLEAR REGULATORY COMMISSION b
f WASHINGTON, D.C. 3068H001
\\...../
COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 License No. NPF-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 7, 1994, as supplemented December 16, 1994, 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; P
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 by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-72 is hereby amended to read as follows:
. (2)
Technical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 58 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, t
FOR THE NUCLEAR REGUL/. TORY COMMISSION
/YY
/
Ramin R. Assa, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 20, 1995 i
- %,t d
j UNITED STATES
.g e NUCLEAR REGULATORY COMMISSION b
. WASHINGTON D.C. 30666-0001
\\.....
COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 License No. NPF-77 L
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The applicatinn for amendment by Commonwealth Edison Company (the licensee) dated November 7,1994, as supplemented December 16, 1994, 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; S.
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 (1) 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.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-77 is hereby amended to read as follows:
I
. (2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 58 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-77, dated July 2, 1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date if its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~
Ramin R.
sa, rojectMakager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 20, 1995
n ATTACtMENT TO LICENSE AMENDMENT NOS. 58 - AND 58 FACILITY OPERATING LICENSE N05. NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50-457
- Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Paaes Insert Paaes 5-5 5-5 5-5a 5-5a 5-5b f
b
DESIGN FEATURES
'* 5.6 FUEL STORAGE CRITICALITY i
5.6.1.1 The spent fuel storage racks are designed and shall be maintained with ak less than or equal to 0.95 when flooded with unborated water, which
-inclNdesaconservativeallowanceforuncertaintiesasdescribedinSection9.1 of.the UFSAR.
This is ensured by controlling fuel assembly placement in each i
region as follows:
i a.
REGION 1 1.
A nominal 10.32 inch north-south and 10.42 inch east-west, center-to-center distance is maintained between fuel assemblies i
placed in the spent fuel storage racks.
2.
Fuel assemblies may be stored in this region with t
a) a maximum nominal initial U-235 enrichment of less than or l
equal to 4.2 weight percent, or i
b) a maximum nominal initial U-235 enrichment of 5.0 weight percent with sufficient Integral Fuel Burnable Absorbers present in each fuel assembly such that the maximum l
reference fuel assembly km is less than or equal to 1.470 at 68*F.
l b.
REGION 2 1.
A nominal 9.03 inch center-to-center distance is maintained between fuel assemblies placed in the spent fuel storage racks.
i 2.
a)
Fuel assemblies may be stored in this region with a maximum nominal initial U-235 enrichment of 1.6 weight percent with no burnup and up to 5.0 weight percent U-235 with a minimum i
discharge burnup as specified in Figure 5.6-1, or b)
Fuel assemblies with a maximum nominal initial U-235 enrichment of greater than 1.6 and less than or equal to
{
4.2 weight percent that do not meet the minimum burnup specified in Figure 5.6-1, shall be loaded in a checkerboard pattern for storage in this region.
5.6.1.2 The k for'new fuel for the first core loading stored dry in the spent fuel sto,r,a,ge racks shall not exceed 0.98 when aqueous foam moderation is
]
assumed.
DRAINAGE l
5.6.2 The spent fuel storage pool is designed and shall be maintained to i
prevent inadvertent draining of the pool below elevation 423 feet 2 inches.
j CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 2870 fuel assemblies.
BRAIDWOOD - UNITS 1 & 2 5-5 Amendment No. 58 l
DESIGN FEATURES 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
i t
4
.~
BRAIDWOOD - UNITS I & 2 5-Sa Amendment No. 58
e 50,000 s
45,000 Enrichment Burnup
/
(w/o)
(MWD /wrU)
(( 1.60 0i f
1.80 4,635
/
40,000 2.00 8,565
/
2.20 11,845
/
2.40 14,729 Acceptable
/
a 2.60 17,397 Region
'/,
2.80 20,085 35,000 3.00 22,742
/
s 3.20 25,132
/
g 3.40 27,810
/
3 3.60 30,179
/
3.80 32,651
/
g30,000 -- 4.00 35,047 j
4.20 37,389 f
k
~~
4.40 39,655
/
4.60 42,024
/
e 25,000 4.80 44,290
/
g k
5.00 46,442
/
- 8
/
/
~4 20,000 A
/
Unacceptable g
[
Region
/
/
, 15,000 j
h
,I
/
10,000 j
/
____p-I 5,000
,j l/
~
,l 0
1.60 2.00 2.40 2.80 3.20 3.60 4.00 4.40 4.80 5.20 Fuel Assembly Initial U-235 Enrichment (w/o)
Notes:
The use of linear interpolation between the minimum burnups reported above is acceptable.
i FIGURE 5.6 - 1 MINIMUM BURNUP VERSUS INITIAL ENRICHMENT FOR REGION 2 STORAGE 1
l BRAIDWOOD - UNITS 1 & 2 5-5b Amendment No. 58 1
-