ML17325B032
| ML17325B032 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/14/1988 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17325B033 | List: |
| References | |
| NUDOCS 8811170316 | |
| Download: ML17325B032 (7) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 INDIANA MICHIGAN POMER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No 118 License No.
DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated August 10,
- 1988, 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.
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-2" 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraphs
- 2. C.(2) and 2. C.(5) of Facility Operating License No.
DPR-58 are hereby amended to read as follows:
2.C.(2)
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. II8
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
2.C.(5)
S ent Fuel Pool Stora e
The licensee is authorized to store D.
C.
Cook, Unit 1 and Unit 2 fuel assemblies, new or irradiated, in any combination up to a total of 2050 fuel assemblies in the shared spent fuel pool at the Donald C.
Cook Nuclear Plant subject to the following conditions:
Fuel stored in the spent fuel pool shall not have an enrichment greater than 4.23K Uranium-235 or a fissile fuel density greater than 50.5 grams of Uranium-235 per axial centimeter of fuel assembly or the reactivity equivalent thereof.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Theodore quay, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V 8 Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 14, 1988
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UNITED STATES CLEAR REGULATORY COMMISSIO WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.>O4 License No.
DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated August 19,
- 1988, 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraphs 2.C.(2) and 2.C.(3)(s) of Facility Operating License No.
DPR-74 are hereby amended to read as follows:
2.C.(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
1O4
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
2.C.(3)(s)
S ent Fuel Pool Stora e
The licensee is authorized to store D.
C.
Cook, Unit 1 and Unit 2 fuel assemblies, new or irradiated, in any combination up to a total of 2050 fuel assemblies in the shared spent fuel pool at the Donald C.
Cook Nuclear Plant subject to the following conditions:
Fuel stored in the spent fuel pool shall not have an enrichment greater than 4.23K Uranium-235 or a fissile fuel density greater than 50.5 grams of Uranium-235 per axial centimeter of fuel assembly or the reactivity equivalent thereof.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Theodore quay, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, Y 8 Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 14,'988
a.
In accordance with the code requirements specified in Section 4.1$
of the PSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
Por a temperature of 650 P, except for the pressurizer which is 680 F.
0 0
VOLUME 5.4.2 5.5 The total contained volume of the reactor coolant system is 12,612 +
o 100 cubic feet. at a nominal T of 70 F.
avg EMERGENCY CORE COOLZNG SYSTEMS 5.5.1 The emergency core cooling systems are designed and shall be maintained in accordance with the original design provisions contained in Section 6.2 of the PSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.6 FUEL STORAGE CRITICALITY SPENT FUEL 5.6.1.1:
The spent fuel storage racks are designed and shall be maintained with:
a.
A k equivalent to less than 0.95 when flooded with unborated eff
- water, p
b.
A nominal 10.5 inch center-to-center distance betwen fuel assembli.es placed in the storage racks.
5.6.1.2:
Fuel stored in the spent fuel storage racks shall have a nominal fuel assembly enrichment as followss Fuel T~e Descri tion Maximum Nominal Fuel Assembly Enrichment Wt.
4 U-235 I
XI ZZZ ZV V
Westinghouse 15 x 15 Exxon 15x 15 Westinghouse 17 x 17 Exxon 17 x 17 Westinghouse OFA 15 x 15 3.50 3.50 3.50 +
p 4.23 4.00 CRITICALITY-NEW FUEL 5.6.2 The new fuel pit storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between new fuel assemblies such that k will not exceed 0.98 when Fuel Types Xi II, ZZZ, ZV a V (as deFfned in Section 5.6.1.2) are placed in the pit and aqueous foam moderation is assumed.
D. C. Cook - Unit 1 5-5 Amendment No.
5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy -4.
Each fuel rod shall have a nominal active fuel length of 144 inches.
The initial core loading shall have a maximum enrichment of 3.3 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4-23 weight percent U-235.
C 0
5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies.
The full length control rod assemblies shall
. contain a nominal 142"inches of absorber materi'al:
The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5
percent cadmium.
All.control rods shall be clad with stainless steel tubing.
5.4.1 The reactor coolant system is designed and shall be maintained:
a ~
In accordance with the code requirements specified in Section 4.1.6 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
b.
For a pressure of 2485 psig, and C ~
For a temperature of 650 F, except for the pressurizer which is 680 F.
D. C.
COOK - UNIT 2 5-4 Amendment No.
VOLUME 5.4.2 5.5 The total vater and steam volume of the reactor coolant system is 12,612 + 100 cubic feet as a nominal T of 70 F.
avg
/
METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological
=over shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY -
SPENT FUEL 5.6.1.1 The spent fuel storage racks are designed and shall be maintained wt,th:
a.
A K fQ equivalent to less than 0.95 when flooded vith unborate'd water,
.b.
A nominal 10.5 inch center-to-center distance betveen fuel assemblies, placed in the storage racks.
5.6.1.2 Fuel stored in the spent fuel storage racks shall have a nominal fuel assembly enrichment as follows:
~Fuel T; e
IV Westinghouse 15 x 15 Exxon 15 x 15 Westinghouse 17 x 17 Exxon 17 x 17 Westinghouse 15 x 15 OFA Maximum Nominal Fuel Assembly Enric~~pt Wt.
0 U
3.50 3.50 3,50 4.23 4.00 CRITICALITY -
NEW FUEL 5.6.2 The nev fuel pit storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between nev fuel assemblies such that K <<vill not exceed 0.98 vhen Fuel Types I, II, III, IV & V (as Sefined in Section 5.6.1.2) are placed in the pit. and aqueous foam moderation is assumed.
D. C.
COOK - UNIT 2 5-5 Amendment No.