ML20069K580
| ML20069K580 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/10/1994 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20069K582 | List: |
| References | |
| NUDOCS 9406160182 | |
| Download: ML20069K580 (8) | |
Text
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l' UNITED STATES
~ s'*,2 NUCLEAR REGULATORY COMMISSION W A 5 m '. G T O N D C 2: L 007 COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET N0. 50-254 00AD CITIES NUCLEAR POWER STATION. UNIT 1 l
AMENDMENT 10 FACILITY OPERATING LICENSE Amendment No.146 License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated December 20, 1993, 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 rFR 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 paragraph 3.B. of Facility Operating License No. DPR-29 is hereby amended to read as follows:
9406160182 940610 PDR ADOCK 05000254 p
PDR.
. B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.146, 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 its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
^%LJo Q Robert A. Capra, Director Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 10,1994 1
i
I f.
ATTACHMENT TO LICENSE AMENDMENT NO.146 FACILITY OPERATING LICENSE NO. OPR-29 DOCKET N0. 50-254 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 INSERI 1.1/2 1-1 1.1/2.1-1
QUAD CITIES
~
DPR-29 1.1/2.1 FUEL CLADDING INTEGRITY SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING Applicability:
Applicability:
The safety limits established to The limiting safety system settings preserve the fuel cladding integrity apply to trip settings of the apply to those variables which instruments anJ devices which are monitor the fuel thermal behavior, provided to prevent the fuel cladding integrity safety limits from being exceeded.
Objective:
Objective:
The objective of the safety limits The objective of the limiting safety is to establish limits below which system settings is to define the the integrity of the fuel cladding level of the process variables at is preserved.
which automatic protective action is initiated to prevent the fuel cladding integrity safety limits from being exceeded.
SPECIFICATIONS A.
Reactor Pressure > 800 psig A.
Neutron Flux Trii Settings and Core Flow > 10% of Rated The limiting safety system The existence of a minimum trip settings shall be as critical power ratio (MCPR) specified below:
less than 1.07 shall constitute violation of the 1.
APRM Flux Scram Trip fuel cladding integrity safety Setting (Run Mode) limit When the reactor mode switch is in the Run position, the APRM flux scram setting shall be as shown in Figure 2.1-1 and shall be:
S 5 (.58Wo + 62) with a maximum setpoint of 120% for core flow 6
equal to 98 x 10 lb/hr and greater.
where S = setting in percent of rated power 1.1/2.1-1 AMENDMENT NO. 14
L UNITED STATES i
~
NUCLEAR REGULATORY COMMISSION usmcTo., e c : a
- e.e*
COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY i
DOCKET NO. 50-265 OVAD CITIES NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.142 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated December 20, 1993, 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 paragraph 3.8. of Facility Operating License No. DPR-30 is hereby amended to read as follows:
l
. B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.142, 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 its issuance.
It should be implemented after completion of Cycle 13 and prior to the startup from a refueling outage for Cycle 14.
FOR THE NUCLEAR REGULATORY COMMISSION Robert A. Capra, Director Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 10, 1994 1
)
]
I ATTACHMENT TO LICENSE AMENDMENT NO.142 FACILITY OPERATING LICENSE N0. DPR-30 DOCKET N0. 50-265 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 i
indicating the area of change.
REMOVE INSERT 1.1/2.1-1 1.1/2.1-1 i
i I
l l
QUAD CITIES DPR-30 1.1/2.1 FUEL CLADDING INTEGRITY SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING Applicability:
Applicability:
The safety limits established to The limiting safety system settings preserve the fuel cladding integrity apply to trip settings of the apply to those variables which instruments and devices which are monitor the fuel thermal behavior.
provided to prevent the fuel cladding integrity safety limits from being exceeded.
1 Objective:
Objective:
The objective of the safety limits The objective of the limiting safety is to establish limits below which system settings is to define the i
the integrity of the fuel cladding level of the process variables at 4
is preserved which automatic protective action is initiated to prevent the fuel cladding integrity safety limits from being exceeded SPECIFICATIONS A.
Reactor Pressure > 800 psig A.
Neutron Flux Trip Settings and Core Flow > 10% of Rated The limiting safety system The existence of a minimum trip settings shall be as critical power ratio (MCPR) specified below:
I less than 1.07 shall constitute violation of the 1.
APRM Flux Scram Trip fuel cladding integrity safety Setting (Run Mode) limit When the reactor mode B.
Core Thermal Power Limit switch is in the Run (Reactor Pressure s 800 psig) position the APRM flux scram setting shall be When the reactor pressure is <
as shown in Figure 2.1.1 800 psig or core flow is less-and shall be:
than 107s of rated the core thermal power shall not exceed S < (.58Wo + 62) 25% of rated thermal power.
~
with a maximum setooint C.
Power Transient of 120% for core flow 6
equal to 98 x 10 lb/hr 1.
The neutron flux shall and greater.
not exceed the scram setting established in where Specification 2.lA for longer than 1.5 seconds S - setting in percent as indicated by the of rated power process computer.
W = percent of drive 2.
When the process fiow required to produce computer is out of a rated core flow of 98 service this safety million lb/hr.
In the limit sball be assumed event of operation with to be exceeded if the a maximum fraction of neutron flux exceeds the limiting power density scram setting fractio)n of rated powergreater than th JMFLPD established by Specification 2.1.A and b(FRP)d,ified as follows:the setting shal a control rod scram does e mo not occuc FRP S s (.58W, + 62 [MFEPD]
1.1/2.1-1 AMENDMENT NO.142