ML20072K604
| ML20072K604 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/03/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co, Iowa Illinois Gas & Electric Company |
| Shared Package | |
| ML20072K608 | List: |
| References | |
| DPR-30-A-079 NUDOCS 8303300653 | |
| Download: ML20072K604 (4) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555 I
%,.....s COMn0NWEALTH EDISON C0t9ANY AND IOWA ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY CPERATING LICENSE Amendment No.
79 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 January 27, 1983 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's 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 anendnent can be conducted without endan.gering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Connission's regulations; D.
The issuance of this amendnent 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 anendaent is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license anendment and paragraph 3.B of Facility License No. DPR-30 is hereby anended to read.as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Anendnent No.79, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
0303300653 830303 PDR ADOCK 05000265 P
PDR 4
2 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 3,1983 9
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Attachment to License Amendment No. 79 l
To Facility Operating License 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.
0 i
.e QUAD CITIES DPR-30 ~
within the prese: hed Lmats within 2 ho,urs, the reactor sha!! be bicupt to the cold shut'down condition withm 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Sarveillance and ccm
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respondmg action s!.41 continue unts! resetor speration is wnha the presersbed hmi:.
MEXizum allowable LHGR for all 8x0 fuel types is 13.h KW/ft.*
I K.
Minimum Critical Power K.
Minimum Critical Power Ratia (MCPR)
Ratio (MCPR)
During s teady-s ta te opera tion The MCPR shall be determined at rated core flow, MCPR shall daily durinE steady-s ta te be greater than or equal to:
power operation above 25%
of rated thermal p wer.
1 37 for Tave ' 0 73 3eC3 1.h2 for T 2 3.86 secs ave 3 385 Tave + l 38 for 3.73 < 7,yg < 0.86 secs where Sve = mean 20% scram insertion time for all surveillance data from Soecificaticn 4.3.C. whicia nas been generated in the current cycle.
For core flows cther than rated, these nominal values,,of MCPR shall be increased oy a factor of kr where kr is as shown in Figure 3 5.2.
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If any time during opera tion 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 prescriced limits.
If the steady-sta te' MCPR is not returned to within the 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 braucnt to -he cold shutdown condition wfthin 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />.
Surveillance and correspond-ing action shall continue until reactor operation is within tho o,rescribed limits.
- For the purpose of the end-of-cycle 6 Barrier Fuel Ramp Test, the steady-state LHGR for the Barrier Ramp Cell fuel may exceed the maximum allowable LHGR identified
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in Technical Specification 3.5.J by no more than 10 percent (14.7KW/ft),hutdown.
s effective from initiation of the test until the end of operating Cycle 6 Amendment No. 51, pfi 79 3.5/4.5-10