ML20138J648
| ML20138J648 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 12/05/1985 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Central ICWA Power Cooperative, Corn Belt Power Cooperative, Iowa Electric Light & Power Co |
| Shared Package | |
| ML20138J652 | List: |
| References | |
| DPR-49-A-127 NUDOCS 8512170599 | |
| Download: ML20138J648 (6) | |
Text
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NUCLEAR REGULATORY COMMISSION 3
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IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL ICWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.127 License No. OPR-49 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Iowa Electric Light and Power Company, et al, dated July 18, 1985, 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 (i) that ine 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 nct 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 Commission'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 OPR-49 is hereby amended to read as follows:
hA PD P
W
. 0 (2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.127, 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 Ak W
Daniel R. Muller, Director BWR Project Directorate 82 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 5,1985
ATTAC5 MENT TO LICENSE AMENDMENT NO.127 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Pages 3.2-11 3.5-9 3.5 92
g TABLE 3.2-B (Cont inued) h INSTRLMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAlfMENT COOLING SYSTEMS l
Minimin No.
4 l
of Operable O
Instrument Number of
?
Channels Per Instrunent Channels Trip System (1)
Trip Function Trip Level Setting Provided by Design Remarks 1
Auto Blowdown Timer 120 sec 15sec 2 timers In conjunction with Low l
Reactor Water level and LPCI or Core Spray Pump running interlock, initiates Auto Blowdown 2
RHR (LPCI) Pump 125125 psig 4 channels Defers ADS actuation Discharge Pressure pending confirmation of Interlock F
Low Pressure core cooling
(
7 system operation (LPCI or l
C Core Spray Planp running interlock) 2 Core Spray Pump 145120 psig 4 channels Discharge Pressure Interlock l
l 1
RHR (LPCI) Trip Not applicable (6) 2 Inst. Channels Relay which continuously l
System bus power monitors availability of l
monitor power to logic systems and annunciates upon loss of power 1
Core Spray Trip Not applicable (6)
System bus power mor.itor 4
DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT F.
Automatic Depressurization F.
Automatic Depressurization System (ADS)
System (ADS) 1.
The Automatic 1.
During each operating cycle Depressurization Subsystem the following tests shall be shall be operable whenever performed on the ADS:
there is irradiated fuel in the reactor vessel and the a.
A simulated automatic reactor pressure is greater actuation test shall be than 100 psig and prior to a performed prior to startup startup from a Cold after each refueling outage.
Condition, except as specified in 3.5.F.2 below, b.
During each refueling outage the ADS Nitrogen Accumulator 2.
From and after the date that check valves will be leak one valve in the automatic tested for a maximisn depressurization subsystem is acceptable system leakage made or found to be rate of 25 sec/ minute, inoperable for any reason, continued reactor operation 2.
When it is determined that one is permissible only during valve of the ADS is inoperable, the succeeding thirty days the ADS subsystem actuation logic unless such valve is sooner for the other ADS valves and the made operable, provided that HPCI subsystem shall be-during such thirty days the demonstrated to be operable HPCI subsystem is operable.
imediately and at least daily
,t hereaf ter.
3.
If the requirements of 3.5.F cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall be reduced to at least 100 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
G.
Minimum Low Pressure Cooling G.
Minimum Low Pressure Cooling and Diesel Generator and Diesel Generator Availability Availability 1.
-During any period when one 1.
When it is determined that diesel generator is one diesel generator is inoperable, continued reactor inoperable, all low pressure operation is permissible
. core cooling and containment only during the succeeding cooling subsystems shall be seven days unless such diesel demonstrated to be operable generator is sooner made immediately and daily operable, provided thereafter.
In 3.5-9 Amendment No. 175, 127 m
DAEC-1 Because the Automatic Depressurization System does not provide makeup to the reactor primary vessel, no credit is taken for the steam cooling of the core caused by the system actuation to provide further conservatism to the CSCS. Performance analysis of the Automatic Depressurization System is considered only with respect to its depressurizing effect in conjunction with LPCI and Core Spray and is based on 3 valves. There are four valves in the ADS and each has a capacity of approximately 810,000 lb/hr at a set pressure of 1125 psig.
The allowable out-of-service time for one ADS valve is determined as thirty days because of the redundancy and because the HPCIS is demonstrated to be operable during this period.
Therefore, redundant protection for the core with a small break in the nuclear system is still available.
The ADS test circuit permits continued surveillance on the operable relief valves to assure that they will be available if required.
The Nitrogen Supply to the ADS utilizes accumulators and inlet check valves to ensure the operability of the ADS in the event that a break occurs in the nonseismic portion of the nitrogen supply piping. The accumulators are sized to allow the ADS to operate at least 5 times after a period of 100 days post accident with a maximum system leakage rate of 30 sec/ minute. To provide an additional margin of safety, the leakage test allows for a maximum acceptable leakage rate of 25 sec/ minute.
3.5-22 Amendment No. 115, 127 E5L