ML19260A481
| ML19260A481 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 10/30/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19260A478 | List: |
| References | |
| FOIA-80-162 NUDOCS 7911210249 | |
| Download: ML19260A481 (5) | |
Text
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o UNITED STATES 8
k NUCLEAR REGULATORY COMMISSION y
WASHidGTON, D. C. 20555
\\...**/
CONSUMERS POWER COMPANY DOCKET NO. 50-155 BIG ROCK POINT NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 30 License No..DPR-6 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated Septaber 28, 1979, complies with the standards and requirments 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 (1) 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 Comission'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 L'.
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.
1382 196 7911210 2
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attactraent to this license amendment and paragraph 2.C(2) of Facility Operating License No. DPR-6 is hereby amended to read as follows:
(2) Te,chnical Specifications The Technical Specifications contained in Appendix A, as iwised through Amendment No. 30, 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 fAJCLEAR REGULATORY COMMISSION d h ?!a%y Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: October 30, 1979 1382 197
ATTACffiENT TO LICENSE AMENDMENT NO. 30 FACILITY OPERATING LICENSE NO. DPR-6 DOCKET NO. 50-155 Revise Appendix A Technical Specifications by renoving pages 4-3 and 4-6 and inserting the enclosed pages 4-3 and 4-6, These revised pages include the captioned amendment number and contain a vertical line indicating the area of change, 1382 198
4.1.1 (Contd)
(i) Operating Recuirements 1.
The average rate of vessel temperature change during normal heatup or cooldown should not exceed 100*F/1 when averaged over a one-hour period.
2.
Control rod withdrawal during power operation shall be such that the average rate-of-change of reactor power is less than 50 MWt per minute when power is less than 120 MW '
t less than 20 MW and 200 MW, an$ per minute when power is between 120 MW t
t 10 MWt per minute when power is between 200 MWt and 240 MW '
t 3.
Reactor vessel pressure shall be limited in accordance with Figure 4.1.
4.
The reactor shall not be made critical, with the exception
~
of physics testing, at' temperatures below the criticality limit shown on Figure 4.1.
5.
The reactor water level shall not be permitted to decrease below the reactor vessel low water level set point at which reactor safety systems are actuated (Section 6.1.2) wher.ever fuel is in the reactor vessel. This requirement shall be considered a safety limit ud decreases in reactor vessel water level below this set point shall be subject to tne requirements of Section 10, Administrative Controls, Sub-section 6.7, " Safety Limit Violation."
4.1.2 Primary Coolant Recirculation Systen The primary coolant recirculation systen shall consist of the reactor vessel, the steam drum, the reactor recirculation pumps, the interconnecting piping and valves, and the safety relief valves.
(a) Design Features Shall Be as Follows:
Number of Recirculation Loops 2
Number of Recirculation Pumps per Loop 1
Approximate Internal Volume of 3830 System Excluding Reactor Core and Internals to Isolation Valves, Cubic Feet Approximate Volume of Coolant in 2689 System During 157 Mwt Operation, Cubic Feet j3g}
}o(;
Steam Drum:
Length, Overall, Feet 40 Inside Diameter, Inches 78 Wall Thickness, Excluding Cladding, 4-3/8 Inches Cladding Thickness, Minimum, Inches 5/32 Design Pressure, Psia 1700 Design Temperature, *F 650 4-3 Amendment No.)d, 30
4.1.2 (Contd)
Minimum Time To Put System 30 in Full Operation Following Signal, Seconds Core Spray Systen:
Type Sparger Ring With Spray Nozzle Capacity of Sprays, Gpm 400 Nozzle Pressure, Psia 115 Backup Core Spray Systen:
Type Sparger Nozzle Centered Over Core Capacity of Sparger, Gpm 470 Nozzle Pressure, Psia 115 Core Spray System Recirculation:
Number Pumps 2
Number Heat Exchanger 1
6 Heat Removal Capacity, Btu /h 8 x 10
@ 28.4 F Log Mean Temperature Difference (b) Operating Requirements A minimum of one reactcr recirculating loop shall be used during all reactor power operations (ie, recirculating pump suction valve and 20" discharge valve shall renain open and pump shall be running).
The maximum operating pressure and temperature shall be the same as the reactor vessel.
The controlled rate of change of temperature in the reactor vessel shall be limited to 100*F per hour. All other components in the system shall be capable of following this temperature change rate. The safety relief valves shall be set appropriately for all planned reactor operating pressures so that the allowable pressure of 1870 psia (1700 plus 10%) in the nuclear steam supply systen is not exceeded.
The energency condenser shall be ooerable and ready for service at all times during power operation.
However, should one emergency condenser tube bundle develop a leak during power operation, it will be pennissible to isolate the leaking tube bundle until the next outage.
Both bundles of the emergency condenser shall be available for service during cold to hot plant heatup for oower production.
The shutdown cooling system shall be ready for service during power operations with the a80 volt circuit breakers for isolation valves MO-7056, M0-7057, M0-7058 and M0-7059 checked "open" when reactor pressure is above 300 psig.
The shutdown cooling system shall be operable and ready for service during refueling operations and the breakers for MO-7070 and M0-7071 shall be tagged "open".
The primary coolant shall be sampled and analyzed daily during 1382 200 Chan e do. W r
4-6 Amenbmentd.,
1/, J8, 30