ML20058H382
| ML20058H382 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/06/1990 |
| From: | Barrett R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058H384 | List: |
| References | |
| NUDOCS 9011150232 | |
| Download: ML20058H382 (4) | |
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UNITED STATES.
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g-NUCLEAR REGULATORY COMMISSION-
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COMMONWEALTH EDISON-COMPANY AND-i IOWA-ILLINOIS GAS AND ELECTRIC COMPANY i
DOCKET NO. 50-254
-QUAD CITIES' NUCLEAR' POWER STATION, UNIT 1 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.'127
' License No.1DPR-29 1.
The Nuclear Regulatory Commission (the Comission) has ;found that:.
A.
The application for amendment by Commonwealth Edison Company l
(thelicensee)datedAugust 31, 1990, 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.
Thereisreasonableassurance(i)'thattheactivitiesauthorized by this amendment can be conducted without endangering the-health l
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 ".he-health and safety.of the i
public; and I
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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.B.-of Facility Operating License No.TOPR-29-is t
hereby amended to read as follows:
i 9011150232 901106 PDR ADOCK 05000254 P
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B.
Technical Specifications The Technical Specifications contained'in Appendices.A'and B,'as.
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revised through Amendment No.127,Jare hereby incorporated in the.
license. The licensee shall operate the facilityL in accordance with the Technical. Specifications.
F 3.
This license amendment.is effective as of the date of:its issuance, l
.t FOR THE NUCLEAR dEGULATORY COMMISSION h-J' Richa j.:Barrett,-Director-1 Project )irectorate III-2 Division of Reactor Projects - III,
-i IV, Y and Special Projects.
Office of Nuclear' Reactor Regulation
Attachment:
1 Changes to the Technical Specifications Date of Issuance:
November 6, 1990 3
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ATTACHMENT TO LICENSE' AMENDMENT NO.127 J
FACILITY OPERATING LICENSE NO. DPR-29 1
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DOCKET NO. 50-254 1
Revise the Appendix A Technica1' 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'11nes indicating the area of change, REMOVE INSERT t
1.1/2.1-1
'1.1/2.1-1
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QUAD CITIES DPR-29 1.1/2.1 FUEL CLADDING INTEGRITY'
-1 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING I
l Applicability:
. Applicability:
The safety limits established to preserve The limiting safety system settings apply the fuel-cladding integrity apply to to trip settings of the i struments and n
those variables which monitor the fuel devices which are provided to prevent the thermal behavior, fuel cladding integrity safety limits from' being exceeded.
Objective:
Objective:
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The objective of the safety limits is to The objective of the limiting safety sys-i establish limits below which the integ-tem settings is:to define the level of "a
rity of the fuel cladding is preserved, the process variables at which' automatic protective action is initiated to pre.
i vent the fuel. cladding integrity safety limits from being exceeded.
SPECIFICATIONS i
A.
Reactor Pressure > 800 psig and Core A.
Neutron Flux Trip Settings Flow > 10% of Rated i
The existence of a minimum critical The limiting safety system trip. set-power ratio (MCPR) less than 1.06 l
tings shall be as specified below:
shall constitute violation of the fuel cladding integrity safety limit.
1.
'APRM Flux Scram Trip Setting-
.(Run Mode)
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:
l S 1 (.58WD + 62) with a maximum setp'oint of 120%
.for core flow equal to'98 x 108 lb/hr and greater.
where S = setting in percent of rated power l
1.1/2.1-1 Amendment No.127
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