ML20073K544
| ML20073K544 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/01/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Iowa Electric Light & Power Co, Central Iowa Power Cooperative, Corn Belt Power Cooperative |
| Shared Package | |
| ML20073K547 | List: |
| References | |
| DPR-49-A-085 NUDOCS 8304200329 | |
| Download: ML20073K544 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION a
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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. 85 License No. DPR-49 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Iowa Electric Light & Power Company, et al, dated November 18, 1982, complies with the standards and requirements 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 Commission's regulations; D.
The issuance of this amendment will not be 1'nimical 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 have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications 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. 85, are hereby incorpor-ated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8304200329 830401 PDR ADOCK 05000331 P
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3.
Tnis' license amendment is effective as of the date of issuance.
FOR THE NUC AR REGULATORY COMISSION Yf Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Speci fications Date of Issuance: April 1,1983 e
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O ATTACHMENT TO LICENSE AMENDMENT NO. 85 FACILITY OPERATING LICENSE NO. DPR-49
,00CKET NO. 50-331 Revise the Appendix A Technical Specifications by removing page 3.2-11 and inserting revised page 3.2-11.
The revised areas are identified by vertical lines.
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TABLE 3.2-8 (Cont inued I
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f INSTRLMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAIPNENT COOLING SYSTENS co, u
NInImum No.
of Operable In strtment Nseber of G ennels Per Instrtment Gannels Trip System (1)
Trip Function Trip Level Setting Wovided by Design Remarks 1
Auto Blondoen Timer 120 sec + sec 2 timers in conjunction with Low Reactor hier Level, High Wywell FYessure and LFCI or Core Spray Pump running Interlock, In1flates Auto Dimdoen O
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RHR (LICl) Pug 125*25 psig 4 channels Defers ADS actuation pending M
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4 Discharge Wessure amtIrmation of Low Pressure
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H Interlock core cooling system operation LICI or Core Sprey Pump running Interlock) 2 Core Spray Pump 145+20 psig 4 channels
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Discharge fYessure Interlock I
Rm (LfC1) Trip Not appilcable (6) 2 Inst. Gannels iblay which continuously System bus power sonitors availability of power to logic systems and monitor amunciates upon loss of poser
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1 I
tore Spray Trip Not applicable (6)
System bus peer mon 1 tor
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The RHR system operates in several different modes and the RHR suction relief valves set pressure is higher than the design head of the RHR pump. Accordingly, the ADS /RHR discharge pressure setpoint was based on reasonable margin below vessel pressure at the low pressure coolant injection (LPCI) pump shut-off condition, as recomended by General Electric and verified by the licensee. The licensee, also, states that the specified ADS /RHR discharge pressure setpoint is consistent with other BWRs which have a LPCI subsystem associated with the RHR system.
We also find the proposed setting for the RHR pressure switch satisfies
'the existing Technical Specification.
Based on the above, we conclude that the licensee's proposal to change the trip level setting requirements for the RHR and core spray pump discharge pressure interlock is acceptable.
- 3. 0 Environmental Consideration We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not resbit in any significant environmental impact. Having made this determi-nation, we have funther concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 51.5(d)(4), that an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
4.0 Conclusion We have concluded, based on the considerations discussed above, that: (1) because the amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated, does not create the possibility of an accident of a type different from any evaluated previously, and does not involve a significant reduction in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities j
will be conducted in compliance with the Comission's regulations and the l
issuance of the amendment will not be inimical to the comon defense and
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security or to the health and safety of the public.
Dated:
April 1, 1983.
Principal Contributor:
T. Collins
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