ML20073T309
| ML20073T309 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/29/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Iowa Electric Light & Power Co, Central Iowa Power Cooperative, Corn Belt Power Cooperative |
| Shared Package | |
| ML20073T310 | List: |
| References | |
| DPR-49-A-089 NUDOCS 8305110234 | |
| Download: ML20073T309 (10) | |
Text
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o UNITED STATES g
NUCLEAR REGULATORY COMMISSION o
E WASHINGTON, D. C. 20555 t;, o...
,o IOWA ELECTRIC LIGHT AND POWER COW ANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331
- 00ANEARNOLDENERGYCENTER s
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 License No. DPR-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
1 A.
The application for amendment by Iowa Electric Light & Power Company, et al, dated March 10, 1983 complies with the standards arai requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's j
rules and regulations set forth in 10 CFR Chapter I; I
B.
The facility will operate in confonnity with the application, i
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 Commission'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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements 4
have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec '
ifications 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 89, are hereby incorporated in the license. The l'icensee shall operate the facility 'in accordance with the Technical Specifications.
8305110234 830429 PDR ADOCK 05000331 P
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This license amendment is effective as of the date of its issuance.
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FOR THE NUCLEAR RE'GULATORY COMMISSION e
Domenic B. Vassallo Chief
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Operating Reactors Branch #2
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Division of Licensing
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Attachment:
Changes to the Technical Specifications t
Date of Issuance:
April 29,1983 e
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ATTACHMENT TO LICENSE AMENDMENT NO. 89 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Revise the Appendix A Technical Specifications by removing current pages and inserting revised pages listed below. The revised area is identified by a vertical line.
List of Affected Pages 3.1-6 3.2-5 3.2-Sa 3.2-7 3.2-37 3.2-39 3.7-27 b
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DAEC-1 9
3.
A main steam line isolation valve closure trip bypass is effective when the reactor mode switch is in'the shutdown, refuel or startup positions..
l 4.
Bypassed when turbine first stage pressure is less than 192 psig or less than 30% of rated.
P 5.
IRM's are bypassed when APRM's are on-scale and the reactor mode 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 Amendment No. 89 I
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3.1-6 l
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1 TAulE 3.2-A INSTRUMENTATION TifAT INITIATES PRIMARY CONTAINHENT ISOLATION
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$R Hinimum No.
Number of
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2 of Operable Instrument 3
Instrument Channels Valve Groups Channels Per g
Provided by Operated by-Trip System (1)
Instrument Trip Level Setting Design Siljnal Action (2)
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Reactor Low
>+170" Indicated Level 4
2,3,4,5 A
O Water Level (7)
(Sec.' Cont.,3 E)
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1 Reactor Low Pres-
< 135 psig 2
4 C
sure (Shutdown Cooling Isolation) t 2 ** "
Reactor Low-Low-Low At or above +18.5" 4
1 A
Water Level indicated level (3) 2 (6) liigh Drywell
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Pressure
-< 2.0 psig 4
2,J,4,8,9*
A (Sec. Cont., 3 E)
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- 2 liigh Radiation
< 3 X Normal Rated 4
1 8
1 Main Steam Line Power Background 4
Tunnel 2
Low Pressure Main
-> 850 psig (7) 4 1
8 Steam Line 2 (5) liigh Flow Main
< 140% of Rated 4
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Steam Line Steam Flow 2
Hain Steam Line
-< 200* F.
4 1
B Tunnel / Turbine Bldg.
liigh Temperature i
Reactor Cleanup
-< 40 gpmd 2
5.
D System liigh Dif f.
Flow
- Greetip 9 Vdives isolate on liigIn drywell giressiire combined with reactor steain supply low pressiere i
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TABLE 3.2-A k
INSTRLMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION (continued)
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R Minimum No.
Number of of Operable Instrument
- g Channels Valve Groups Instrument Channels Per Provided by Operated by cn Trip System (1)
Instrument Trip Level Setting Design Signal-Action (2) 1 Reactor Cleanup 130*F 3
5 D
Area Ambient High Temperature j
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Reactor Cleanup A 14*F*
3
.5 D
Area Differential High Temperature Loss of Main i 10 in Hg Vacuum 4
1 8
E (2
Condensor Vacuum R.
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'2 Reactor Low-Low At or above +119.5" 4
8 A
s Water Level indicated level (3)
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- Note: The actual setpoint shall be A14*F above the 1001 operation ambient temperature conditions as determined by DAEC Plant Test Procedure.
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DAEC-1 5.
Two required for each steam line.
6.
Th'ese signals also start SBGTS and initiate secondary containment,
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isolation..
7.
Only required in Ru Mode (interlocked with Mode Switch).
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. Amendment No. 89
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i DAEC-1 adequate to prevent uncovering the core in the case of a break in the largest line assuming a 60 second valve closing time.
Required closing times are less than this, i
The low-low reactor ' water level instrumentation is set to trip when reactor -
water level is 119.5" above top of the active fuel.
This trip initiates the HPCI and RCIC and trips the recirculation pumps. The low-low-low reactor water level instrumentation is set to trip when the water level is-18.5" above the top of the active fuel.
This trip activates the remainder of the CSCS subsystems, closes Group 7 valves, closes Main Steam Line Isolation Valves, Main Steam Drain Valves, Recirc Sample Valves (Group 1) and starts the emergency diesel generators.
These trip level settings were-chosen to be high enough to prevent spurious actuation but low enough to initiate CSCS operation and primary system isolation so that post accident cooling can be accomplished and the guidelines of 10 CFR 100 will not be exceeded.
For large breaks up to the complete circumferential break of a 22-inch recirculation line and with the trip setting given above, CSCS initiation and primary system isolation are initiated in time to meet the above criteria.
Reference Paragraph 6.5.4 FSAR.
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Amendment No. 89 3.2-37 l
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-i DAEC-1 i
Temperature monitoring instrumentation is. provided in the main steam line tunnel and turbina building to detect leaks in this area. Trips are provided on this instrumentation and when exceeded, cause closure of isolation valves. See Spec 3.7 for Valve Group. The setting is 200*F for the main steam line: tunnel detector. For large breaks, the high steam flow -
instrumentation is a backup to the temperature instrumentation.
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High radiation monitors in the main steam line tunnel have been provided to detect gross fuel failure as in the control rod drop accident. With the established setting of 6 times normal background, and main steam line isolation valve closure, fission product rel' ease is limited so that 10 CFR 100 guidelines are not exceeded for this accident. Reference Subsection 14.6.2 of the FSAR.
Pressure instrumentation is provided to close the main steam isolation valves in RUN Mode when the main steeam line pressure drops below 850 psig.
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The Reactor Pressure Vessel thermal transient due to an inadvertent opening of the turbine bypass valves when not in the RUN Mode is less severe,than the loss of feedwater analyzed in Subsection 14.5 of the FSAR, therefore, closure of the Main Steam Isolation valves for thermal transient protection when not in RUN Mode is not required.
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Amendment NO. 89 1
3.2-39
DAEC-1 NOTES FOR TABLE 3.7-3 9*
i 1.
Isolation Signals are as follows:
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Group 1:
i The valves in Group 1 are closea upon any one of the following conditions:
1.
Reactor vessel low-low-Idw water level.-
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2.
Main steam line high radiation.
3.
Main steam line high flow.
4.
Main steam line tunnel high temperature.
5.
Low main steam line pressure at turbine inlet (run mode only).
6.
Main condenser low vacuum.
Group 2:
l The valves in Group 2 are closed upon any of the following conditions:
1.
Reactor vessel low water level.
l 2.
High drywell pressure.
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3.7-27 Amendment No. 89
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