ML19323C749
| ML19323C749 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/13/1974 |
| From: | Goller K US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19323C736 | List: |
| References | |
| FOIA-80-162 NUDOCS 8005190125 | |
| Download: ML19323C749 (6) | |
Text
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UNITED STATES
.5 ATOMIC ENERGY COMMISSION A
WASHINGTON, D.C. 20$45
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CONSLNERS POWER COPANY I
DOCKET NO. 50-155 t
l AMEN [fENT TO FACILITY OPERATING LICENSE hiendment No. 7 License No. DPR-6 2
1.
The Atomic Energy Comissio". (the Comission) has found that:
I j
A.
The application for amendment by Censumers Power Company (the licensee) dated June 28, 1974, and supplement dated July 15, 1974, comply with the standards and requirements of the Atomig Energy Act of 1954, as amended (the Act), and the Comission's mies and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) 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 comon defense and security or to the health and safety of the public; and E.
Prior public notice of this amendment is not required since the amendment does not involve a significant hazards consideration.
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-6 is hereby amended to read as follows:
) "B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, as revised by issued changes thereto through Change No. 44."
3.
This license amendment is effective as of the date of its issuance.
FOR THE ATWIC EhTEY CCtMISSION Karl R. Goller, Assistant Director for Operating. Reactors Directorate of Licensing Attachment; Change No. 44 to Appendix A Technical Specifications Date of Issuance: August 13, 1974 1
I
ATTACH:EIT TO LICE:!3E A:"C :'c.T 7. 7 CHA"GE ti0. 44 TO TECH?ilCAL SPECIFMATIT 5 (ADPEiiOIX A)
FACILITY 0?ERATI:G LICEi.SE : 0. D?3-6 s
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The, Technical Specifications contained in Appendix A attached to l '
Facility Operating License ilo. DPR-6 are revised as follows:
i 1.
Replace the table contained in Section 5.2.l(b) wit 5 the attached table.
e 2.
Replace Table 8.2 with the attached Table.
I 3.
Change Section 4.1.2(b) to read as follows:
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"4.1.2(b) Operatino Requirements l
A minimum of one reactor recirculating loop or its equivalent shall be used during all reactor
, power operations when reactor power level is above 1.0 init.
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 press 6re of 1870 psia (1700 plus 104) in the nuclear steam supply system is not exceeded.
The e.T.ergency condenser, core spray and backup core spray systems shall be operable and ready for service at all times i
during power operation.
however, should one emergency condenser tube bundle develop a leak during pcwer operation, it will be permissible to isolate the leaking tube bundle until tha next outage.
Both bundles of the emergency condenser shall be available for service during cold to hot plant heat up for power production.
The core spray system, shutdown cooling system and the firewater make up system to the condenser hot well shall be operable and ready ?:-
service.at all tir.es during power operation.
The prirwy coolant shall be sampled and analyzed daily durino periods of power operction.
The follouing are absolute linits which if exceed 2d shall necessitate I
reactor shutdown.
Corrective action uill neccessarili
~
be taken et nore string 2nt limits to ninimize the possibili t/ of t5 esc shschite liniits ever being rene ed."
. 3.s C:nduc tivi ty (Micrcmhc/cm)
Maximum 5
Maximum transient
- 10
. i, pH (Lower and Upper limits) 4.0 anc 10.0 Chloride Ion (Ppm) 140 Equilibrium Halogen Radioactivity (uc/ml) 35 Boron (Ppm) 100 i
Changed areas are shown by narainal lines.
l t
- Co.iductivity is expected to increase temporarily af ter startups fro shutdown.
The maximum transient value here stated is the r3xinum permissible and applies only to the period subsequent to a cold shutinz-between criticality and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching 20% rated power.
)
TABLE 8.2
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I Centereelt
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EE1 UO -pug 3 Intermediate Advanced NFS-EA 2
Minimum Core Burnout Ratio at Over-power 1*5*
1*5*
1 5*
15 Transient Minimum Burnout Ratio in Event of Loss of Recirculation From Rated Power 15 15 15 15 Maximum He t Flux _at Overpower, Btu /h-Ft 500,0N h02,000 MaximumStgadyStateHeatFlux, Btu /h-Ft 410,000 500,000 500,000 329,000 Maximum Average Planer Linear Heat Generation Rate, Steady State, kW/Ft '
7.56 S'. ability Criterion: Maximum Measured Zero-to-Peak Flux Amplitude, Percent of Average Operating Flux 20 20 Maximum Steady State Power Level, MW 240 i
240 M ximum Value of Average Core Power Operation, Psig 1,485 1,485 Minimum Recirculation Flow Rate, Lb/h
.(Except During Pump Trip Tests or Natural Circulation Tests as Out-Lined in Section 8) 6 x 10 6 x 10 Maximum MWD /T of / Contained Uranium for an Individual Bundle 23,500 23,500 Number of Bundles:
Pellet UO2 1
3 l
Powder UO 2
1 2
R-te-of-Change-of-Reacter Power During Power Operation:
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Control rod withdrawal during power operation shall be such that the average rate-of-change-of-reactor power is less than 50 W 120 MW, less Gan 20 W t Per minute when power is less than cinute when power is between 200 and 240 MW *Per minute when power is between t
t Per t
t
- B: sed upon critical heat flux correlation, APED-5286.
oO No'lon6er used in reactor.
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(Table to Section 5..l(b))
Reload E-G and l
F, J-l & J-2 Relcad G j
Minimum Core Burnout Ratio at Overpower 1 5*
1 5
[
Transient Minimum Burnout Ratio in Event of Loss of Recirculation Pumps From Rated y
i f
f Power 15 15 Maximum Heat Flux at Overpower, Btu /h-ft 500,000 395,000 Maximum Steady-State Heat Flux, Btu /h-ft h10,000 32h,000 I.
l Maximum Average Planar Linear Heat 7.32 Generation Rate, Steady State kw/ft 10.o Stability Cr!terion: Maximum Measured i
Zero-to-Peak Flux Amplitude, Percent of Average Operating Flux 20
- 20 i
Maximum Steady-State Power Level, MW 2h0 2h0 t
i Maximum Value of Average Core Power Density @ 2h0 MW, kW/L h6 h6 t
j Maximum Reactor Pressure During Power f
Operation, Psig 1,h85 1,h85 l
Minimum Recirculation Flow Rate, Lb/h (Except During Pump Trip Tests or Natural 6
6 Circulation Tests as Outlined in Section 8) 6 x 10 6 x 10 Maximum mwd /T of Contained Uranium for an Individual Bundle 23,500 23.,500 Rate-of-Change-of-Reactor Power During Power Operation:
Control rod withdrawal during power operation shall be such that the average rate-of-change-of-reactor power is less than 50 Wt Per minute when power is less than 120 W, less than 20 MWt per minute when power is between 120 and t
200 MW, and 10 MW per minute when power is between 200 and 240 MW
- t t
- Based on correlation given in " Design Basis for Critical Heat Flux Condition in Boiling Water Reactors," by'J. M. Healzer, J. E. Hench, E. Janssen and S. Levy, September 1966 (APED 5286 and APED 5286, Part 2).
- Based on Exxon Nuclear Corporation Synthesized Hench Levy.
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