ML19256E344
| ML19256E344 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 10/18/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19256E343 | List: |
| References | |
| FOIA-80-162 NUDOCS 7911020201 | |
| Download: ML19256E344 (4) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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300R Dill 81WAL CC:'S'JMERS PC'-lER COMPANY DnCKET ';n. 50-155 BIG ROCK POINT NUCLEAR PLANT AMEND"iENT TO FACILITY OPERATRlr, LICO:SE Amendment No. 29 License No. DPR-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Cortany (the licensee) dated September 7,1979, conolies with the standards and recuirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and reculations 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 endangerina the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commirsion's regulations; 3.
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 ail aoplicable recuirements have been satisfied.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attach ent to this license a e c en and cc.racrach 2.C(2) of Facility Aceratire License
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R-6 is hereby amended to read as follcws:
(2) TecFnical S ecifications The Technical Specifications contair,ed in Appendix A, as revised through Amendment :;o. 29, are hereby incorporated in the license. The licensee shall ocerate the f3cility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0911SSION s
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Dennis L. Ziemann,. Chief Operating Reactors ' Branch *2 Division of Operatina Reactors Attachrnent:
Changes to the Technical Specifications Date of Issuance:
October 18, 1979 E00R DM8!NA!.
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ATTACfNENT TO LICENSE AMENDMENT NO. 29 FACILITY OPERATING LICENSE NO. DpR-6 DOCKET NO. 50-155 Revise Appendix A Technical Specifications by removing page 7-3b and inserting the enclosed page 7-3b.
This revised page includes the captioned amendment number and contains a vertical line indicating the area of change.
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(d) The log count rate meter shall indicate a minimum of three counts per second with a signal-to-noise ratio of 3 to 1.
This will be accomplished by withdrawing the startup chamber to a region of lower flux and observing the reduction in count rate.
In the event that neutron source strength is insufficient to produce the required count rate in Cycle 16, an approach to criticality for reactor startup shall be allowed provided that the following conditions are met.
This procedure shall also be used for any subsecuent startups in Cycle 16 as may be necessary until sufficient power operation has been accumulated to irradiate the antimony-beryllium sources sufficiently to produce the required count rate. -
(i) Prior to the first startup after develognent of the low source strength condition, a critical approach (es) with the reactor vessel head-off shall be perfonned to evaluate the out-of-vessel low-level detector response and the control rod withdrawal sequence. Two additional low-level detectors shall be tenporarily inserted in the vessel to monitor this head off critical approach (es). These addi-tional detectors shall indicate a minimum of 3 counts per second with a signal-to-noise ratio of 3 to 1.
(ii) Evaluation of instrument responses during the head-off critical approach (es) shall demonstrate that, by the time the estimated keff of the core reaches 0.995, each low-level out-of-core startuo detector is reading at least 3 cps with a 3 to 1 signal-to-noise ratio.
(iii) Critical approaches with the head on and without the tenporary in-vessel low-level detectors in service shall be permitted provided that the instrument response requirements of (ii) above have been demonstrated and provided that these same requirements are also met during each critical approach with the head on. Normal start-up may continue any time startup count rate is at least 3 counts per second with a minimum signal-to-noise ratio of 3 to 1.
(iv) The procedure of (i) and (ii) above shall be repeated by conducting an additional head-off critical approach (es) in the event of either a core configuration change or a significant change in that part of the control rod withdrawal sequence for which the minimum count rate and signal-to noise ratio specified above are not attainable.
(v ) The site reactor engineer or his alternate will be on site during all head-off critical approaches and instrument response evaluations and during the initial head-on startup followir.g head-off evalua-tions.
7-3 b Change No. /
Amendment No. 29 s #3 r,
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