ML20107E839
| ML20107E839 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 02/05/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Corn Belt Power Cooperative, Central Iowa Power Cooperative, Iowa Electric Light & Power Co |
| Shared Package | |
| ML20107E841 | List: |
| References | |
| DPR-49-A-111 NUDOCS 8502250814 | |
| Download: ML20107E839 (6) | |
Text
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,og UNITED STATES
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g NUCLEAR REGULATORY COMMISSION 5
- j WASHINGTON, D. C. 20555
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IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 111 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 August 17, 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 conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 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 License No. DPR-49 is hereby amended to read as follows:
Pa**1M Mj!r P
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-2 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.111, are hereby 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 lk-Attachment-Changes to the Technical Specifications Date of Issuance: February 5,1985 e
1 f
4 i
j ATTACHMENT TO LICENSE AMENDMENT NO.111 FACILITY OPERATING LICENSE NO. DPR-49
{
DOCKET N0. 50-331 i
Replace 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 indicating the area of changes.
i AFFECTED PAGES i
3.1-4 3.1-6 3.1-21 1
A y
5-
TAfLE3.1-1(Continued)
REACitR PROTECTION SYSTEM (SOUN) INSTRlMNTATI(N REQJIREENT' k
E.
Minimun No.
3 of (5erable Modes in tidi * -
Nurber of 5
instrunent Function N st be Instrunent z
Channels Operable Channels
- for Trip Refuel Startup Run Provided Systen (1)
Trip Function Trip Level Setting (6)
By Design Action (1) 2 Hi@ Drywell Pressum
< 2.0 psig X(7)
X(8)
X 4 Instrunent A
Channels 2
Reactor Low Water
> +170" Indicated X
X X
4 Instrunent A
Level Tevel(15) mannels 2
Hi$ Water Level in
< 60 Gallons X(2)
X X
4 Instrunent A
g Scran Discharge Volune Channels 2
Main Stean Line
< 3 x Nonnal Rated X
X X
4 Instrunent A
{
Hi$ Radiation Tbwer Background
- Channels 4
Main Stean Line
< 101 Valve Closure X
X X(13) 8 Instrunent A or C Isolation Valve (3)(13) (3)(13)
Channels Closure 2
Turbine Contml Valve' Within 30 millis5conds X(4) 4 Instrunent A or D Fast Closure (Loss of the Start of Contml Gannels of Contml Oil Valve Fast Closure Pressure) 4 Turbine Stop Valve
<101 Valve Closum X(4) 8 Instrunent A or D Closum Channels 2
- First Stage Bypass below 155 psig X
X X
4 Instrunent A or D l
Gannels
- Alann setting <1.5 X Nonnal Rated Power Backgromd
^
~
DAEC-1 3.
A nain steam line isolation valve closure trip bypass is effective when the reactor mode switch is in the shutdown, refuel or startup positions.
4.
Bypassed when turbine first stage pressure is less than 155 psig (corresp~onding 'to 30% of rated core power). This value of first stage pressure assunes that the second stage reheaters are not in-service below 30% of rated core power..
5.
IRM's are bypassed when APRA's are on-scale and the reactor node switch is in the run position.
6.
When the reactor is subcritical and the reactor water temperature is less than 212*F, only the following trip functions need to be operable:
a.
Mode switch in shutdown b.
Manual scram c.
High flux IRM d.
Scram discharge-volume high level - may be bypassed in.the refuel and shutdown modes for the purpose of resetting the scram.
e.
APRM 15% flux
- ;;:- 2L k-
- Kmendment No. 111 3.1-6
- N:;
DAEC-1 to the Refuel mode during reactor power operation does not diminish the protection provided by the reactor protection system.
Turbine stop valve closure trip occurs at approxiinately 10% of valve closure. Below 155 psig turbine first stage' pressure (corresponding to 30%
of rated core power), the scram signal due to turbine stop valve closure is by-passed because the flux and pressure scrams are adequate to protect the
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reactor below 30% of rated core power.
Turbine Control valve fast closure scram trip shall initiate wichin 30 milliseconds of the start of control valve fast closure. The trip level i
setting is verified by measuring the time interval from energizing the f ast acting solenoid (from valve test switch) to pressure switch response; the measured result is compared to base line data taken during each refueling outage. Turbine control valve fast closure is sensed by measuring disc dump electro-hydraulic oil line pressure (Relay Emergency Trip Supply) which decreases rapidly upon generator load rejection. This scram is only.
~
. effective when turbine first stage pressure is above-155 psig (corresponding to 30% of rated core power).
The requirement that-the.IRM's be inserted 1.1 the core when'the APRM's read 5 as indicated on the scale in the Startup an'd Refuel modes ' assures that :
there is proper' overlap in the neutron monitoring system functions and thus, that adequate coverage is provided ty all: ranges of reactor. operation.-
Amendment No. 111'
- 3.1-21.
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