ML20106G275
| ML20106G275 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 02/01/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Corn Belt Power Cooperative, Central Iowa Power Cooperative, Iowa Electric Light & Power Co |
| Shared Package | |
| ML20106G278 | List: |
| References | |
| DPR-49-A-110 NUDOCS 8502140307 | |
| Download: ML20106G275 (8) | |
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UNITED STATES d j,' 4,,
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NUCLEAR REGULATORY COMMISSION I I j
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WASHINGTON, D. C. 20555 IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IDWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.110 License No. DPR-49 1.
The Nuclear' Regulatory Comission (the Comission) has found that:
A.
The application 'for amendment by Iowa Electric Light & Power Company, et al,. dated October 5, 1984, complies with the standards 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 confomity '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 he 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.
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 Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating Lice.nse No. DPR-49 is hereby amended to read as follows:
8502140307 850201 DRADOCK05000g
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(2) Technical Specifications
' The' Technical Specifications contained in Appendices A and B, as revised through Amendment No.110, are her~eby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 1,1985 M
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ATTACHMENT TO LICENSE AMENDMENT NO.110
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FACILITY.0PERATING LICENSE NO. DPR-49
. DOCKET NO. 50-331 i
P.eplace the following pages of _the Appendix "A" Technical. Specifications with the enclosed pages. The revised pages are identified by Amendment number and contains vertical lines indi.cating the &rea of changes.
AFFECTED PAGES 1
3.2-8 3.2-10 3.2-11 l
3.2-27 3.2-33 l
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TABLE 3.2-8
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INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS I
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Minimian No.
i of Operable d
Instrument Number of Channels Per Instrtsnent Channels Trip System (1)
Trip Function Trip Level Setting Provided by Design Remarks 2
Reactor Low-Low
> + 119.5 in. Indicated 4 HPCI & RCIC
- Initiates HPCI & RCIC Water Level Tevel (4)
Instrument Channels
.c 2
Reactor Low-Low-Low > + 18.5 in. Indicated 4 Core Spray & RHR
- 1. In conjunction ~with Water Level Tevel (4)
Instrument Channels Low Reactor Pressure initiates Core Spray 4 ADS Instrianent and LPCI l,
Channels w
- 2. In conjuncti'n with o
- m In confirmatory low.
level, 120 second l
time delay and LPCI 3
or Core Spray pump l
interlock initiates l
Auto ' Blowdown (ADS) s
)
- 3. Initiates starting.
i of Diesel Generator 2
Reactor High Water
< + 211 in. Indicated 2 Instrument Channels
Level Tevel (4) turbines-i s
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TABLE,3.2-8 (Continued)
B INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS
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Minimun No.
c3 of Operable Instrument Number of Channels Per Instrument Channels Trip System (1)
Trip Function Trip Level Setting Provided by Design Remarks 1
Reactor Low Pressure p < 135 psig 2 Instrument Channels-In conjunction with PCIS signal permits closure of RHR (LPCI) injection u,
valves n>
2 Reactor Low Pressure
> 900 psig 4 Instrument Channels
Prevents actuation of i
J.
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LPCI break detection c) circuit (1 Recirc Pump Running) 1 Core Spray Pump 5 sec 2 timers In conjunction with loss Start Timer of power initiates the starting of CSCS punps.
1 LPCI Pump Start 10 sec 2 timers In conjunction with. loss Timer 15 sec 2 timers of power initiates the
starting of LPCI pumps.
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TABLE 3.2-B (Continued)
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l-INSTRUMENTATION THAT INITIATES OR CONTROLS THE CO
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8 Minimtsn No.
of Operable Instruent Channels Per Number of O
Trip System (1)
Trip Function Instrment Channels o
Trip Level Setting Provided by Design
, Remarks 1
Auto Blowdown Timer 120 sec + sec 2 timers In conjunction with Low Reactor Water Level and l
LPCI or Core Spray Pump 2
running interlock, initiates Auto Blowdown RHR (LPCI) Pump 125+25 psig 4 channels Discharge Pressure Interlock Defers ADS actuation pending confirmation of
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Low Pressure core cooling
?
system operation LPCI or Core Spray Pup ru(nning Core Spray Pump interlock) 2 Discharge Pressure 145+20 psig 4 channels Interlock 1
RilR (LPCI) Trip Not applicable' (6) 2 Inst. Channels System bus power monitor Relay which contiinuously monitors availability of power to logic systems and i
annunciates upon loss of 1
power Core Spray Trip System bus power Not applicable (6) a
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monitor
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- 1 TABLE 4.2-B (Continued)
MINIMUM TEST AND CALIBRATION F.REQUENCY FOR CSCS
$n Logic System Functional Test (4)a(6)
Calibration Frequency (9) 2*
1)
Core Spray Subsystem Once/6 months 5
2)
Low Pressure Coolant Injection Once/6 months Subsystem 3)
Containment Spray Subsystem Once/6 months
- 4) IIPCI Subsystem
'Once/6 months
- 5) IIPCI Subsystem Auto Isolation Once/6 months
- 6) ADS Subsystem (10)
Once/6 months l~
- 7) RCIC Subsystem Auto Isolation Once/6 months
- 8) Area Cooling for Safeguard System Once/6 months 9)
Low-Low Set Function Once/6 months G
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DAEC-1 These instrtsnent channels will be calibrated using simulated electrical signals.
- 4. -
Simulated automatic actuation shall be performed on,ce each operating cycle. Where possible, all logic system functional tests will be performed using the test jacks.
2 5.
Reactor low water level, high drywell pressure and high radiation main steam line tunnel are also included on Table 4.1-2.
6.
The logic system functional-tests shall include a calibration of time delay relays and timers necessary for proper functioning of'the trip systems.
7.
These signals are'not PCIS trip signals but isolate the Reactor Water Cleanup system only.
8.
This instrisnentation is excepted from the functional test definition.
The functional test will consist of comparing the analog signal of the active thermocouple element feeding the isolation logic to a redundant thermocouple element.
9.
Functional tests and calibrations are not required on the part of the system that is not required to be operable or is tripped. Functiorp1 tests shall be performed prior to returning the system to an operable status with a frequency not less than once per month. Calibrations shall be performed prior to returning the system to an operable status with a frequency not less than those defined in the applicable table.
However, if maintenance has been performed on those components, functional tests and calibration shall be performed prior to returning to service.
- 10. A functional test shall be performed for the ADS manual inhibit switches as part of the ADS subsystem tests.
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3.2-33 Amendment No. 110 4
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