ML17331A262
| ML17331A262 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/08/1993 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17331A263 | List: |
| References | |
| NUDOCS 9304140328 | |
| Download: ML17331A262 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COIVlMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 MENDMENT TO FACILITY OPERATING LICENSE Amendment No.
172 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 May 1,
- 1992, 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.
9304l40328 930408 PDR AOGCK 05000315 P
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-58 is hereby amended to read as follows:
Technical S ec'fications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 172
, 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 the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
capri]
Q
)993 Ledyard B. Marsh, Director Project Directorate III-I Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
TTACHMENT TO LICENSE AMENDMENT NO.
172 TO FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the page identified below and inserting the attached page.
The revised page is identified by amendment number and contains vertical lines indicating the area of change.
REMOVE 3/4 3-53a INSERT 3/4 3-53a
TABLE 3.3-10 (Continued)
Unit a d Co e
etecti S ste s
ete tor S stem Locatio Total Number of Detector
~ea
/~am
~mo g (x/y)*
(x/y)*
(x/y)*
Ul Cable Tunnels a)
Quad 1 Cable Tunnel b) Quad 2 Cable Tunnel c) Quad 3N d) Quad 3S e)
Quad 3M f) Quad 4 0/3 0/4 0/3 0/3 0/3 0/5 0/4 0/7 0/4 0/3 0/4 0/6 Ul Charcoal Filter Ventilation Units a) 2-HV-AES-1 b) 2-HV-AES-2 c) 2-HV-ACRF d) 2-HV-CIPX e) 2-HV-CPR f) 12-HV-AFX 0/1~
0/1~
0/l~
0/].~~
0/].&~
0/1~C Ul Containment~~
a)
RCP 1
b)
RCP 2
c)
RCP 3
d)
RCP 4 e) Cable Trays 1/0 1/0 1/0 1/0 58/0*+~~
C
- (x/y)
System protects area common to both Units 1 and 2
x is number of Function A (early warning fire detection and notification only) instruments.
y is number of Function B (actuation of fire suppression systems and early warning and notification) instruments.
Originally installed to automatically deluge charcoal filters.
- However, manual actions are now necessary.
The fire detection instruments located within the Containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate tests.
Thermistors are located within all cable trays which contain combustible cables, in both upper and lower containment throughout quadrants 1-4.
COOK NUCLEAR PLANT - UNIT 1 3/4 3-53a AMENDMENT NO. 4344 172
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-74 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No.
155
, 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 the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
ppri] Q
]993 Ledyard
. Harsh, Director Project Directorate III-I Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
155 License No.
DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
E.
The application for amendment by Indiana Michigan Power Company (the licensee) dated May 1,
- 1992, 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;
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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.
TTACHMENT TO LICENSE AMENDMENT NO.
155 FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the page identified below and inserting the attached page.
The revised page is identified by amendment number and contains vertical lines indicating the area of change.
REMOVE 3/4 3-52a INSERT 3/4 4-52a
TABLE 3.3-11 (Continued)
U it and Commo e
e e e t o s
ems etection S stem cat Total Number etecto s
peat (x/y)*
~lame
+roke (x/y)*
(x/y)*
U2 Cable Tunnels a)
Quad 1 Cable Tunnel b) Quad 2 Cable Tunnel c) Quad 3N d) Quad 3S e)
Quad 3M f) Quad 4 U2 Charcoal Filter Ventilation Units a) 2-HV-AES-1 b) 2-HV-AES-2 c) 2-HV-ACRF d) 2-HV-CIPX e) 2-HV-CPR f)12-HV-AFX 0/]~
0/1+0+4+
0/l~
0/]~
0/].4++++
0/1~C 0/3 0/4 0/3 0/3 0/3 0/5 0/4 0/7 0/3 0/4 0/4 0/6 U2 Containment~~~
a)
RCP 1
b)
RCP 2
c)
RCP 3
d)
RCP 4 e) Cable Trays 1/0 1/0 1/0 1/0 64/Q~hk.~+
C System protects area common to both Units 1 and 2
- (x/y) x is number of Function A (early warning fire detection and notification only) instruments.
y is number of Function B (actuation of fire suppression systems and early warning and notification) instruments.
- ~ Originally installed to automatically deluge charcoal filters.
- However, manual actions are now necessary.
- ~* The fire detection instruments located within the Containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate tests.
- Thermistors are located within all cable trays which contain combustible
- cables, in both both upper and lower containment throughout quadrants 1-4.
COOK NUCLEAR PLANT - UNIT 2 3/4 3-52a AMENDMENT NO. 4k&'55