ML20111B196
| ML20111B196 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/25/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co, Iowa Illinois Gas & Electric Company |
| Shared Package | |
| ML20111B199 | List: |
| References | |
| DPR-30-A-085 NUDOCS 8503130026 | |
| Download: ML20111B196 (4) | |
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION 7,.
j WASHINGTON, D. C. 20555
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COMMON 14EALTH EDISON COMPANY AND IOWA-ILLINOIS GAS ARU ELECTRIC COMPANY DOCKET NO. 50-265 00AD CITIES NUCLEAR POWER STATION, UNIT 2 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No. DPR-30 l
1.
The Nuclear Regulatory Comission (the Comission) has found that:
i A. _,,The application for amendment by Comonwealth Edison Company l
(the licensee) dated December 4, 1984, complies with the standards I
and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 rtfles and regulations of the Comission; C.
Thereisreasonableassurance(i)thattheactivitiesauthorized i
and safety of the public, and (ii) that such activities will be l
conducted in compliance with the Comission's regulations; l
D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and 1
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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 paranraph 2.C.(21 of Facility Operating License flo. DPR-30 is i
hereby amended to read as follows:
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l (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
85, 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 s
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 25, 1985 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 85 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-265 Revise Appendix A Technical Specifications by removing page 3.5/4.5-10 and inserting revised page 3.5/4.5-10.
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Quad Cities DPR-30 within the prescribed limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the reactor shall be brought to the cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.
Maximum allowable LHGR for all 8X8 fuel types is 13.4 KW/ft.*
K.
Minimum Critical Power Ratio (MCPR)
K.
Minimum Critical Power (MCPR)
During steady-state operation at rated core flow, MCPR shall be greater than The HCPR shall be determined daily during or equal to:
steady-state power operation above 25%
of rated thermal power.
1.34 for) ave 6 0.73 secs 1,39 forTave 2 0.86 secs 0.385'fave+1.059 for 0.73</Yave < 0.86 secs where" Pave = mean 20% scram insertion time for all surveillance data from Specification 4.3.C which has been gene-rated in the current cycle.
For core flows other than rated, these nominal values of HCPR shall be increased by a factor 3
of kr where kr is as shown in Figure 3.5.2.
If any time during operation it is determined by normal surveillance that the limiting value for MCPR is being exceeded, action shall be initiated within 15 minutes to restore operation to within the prescribed limits.
state MCPR is not returned to within theIf the steady-prescribed limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the reactor shall be brought to the cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
action shall continue until reactor operationSurveillance and corresponding is within the prescribed limits.
- For the purpose of the end of Cycle 7 Barrier Fuel Ramp Test, the stead the Barrier Ramp Cell fuel may exceed the maximum allowable LHOR ide Specification 3.5.] by no more than 12 percent (15.0 KW/ft), effective from the test until the end of Cycle 7 shutdown.
Amendment No. 51, 69, 79, 80, 85 3.5/4.5-10 6312N
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