ML20070V682
| ML20070V682 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 02/09/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Corn Belt Power Cooperative, Central Iowa Power Cooperative, Iowa Electric Light & Power Co |
| Shared Package | |
| ML20070V683 | List: |
| References | |
| DPR-49-A-081 NUDOCS 8302170514 | |
| Download: ML20070V682 (6) | |
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,k UNITED STATES 8
NUCLEAR REGULATORY COMMISSION s
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IOWA ELECTRIC LIGHT AND POWER C09ANY CENTRAL IDWA POWER COOPERATIVE I
CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 l
DUANE ARNOLD ENERGY CENTER AMENDENT TO FACILITY OPERATING LICENSE Amendment No. 81 License No. DPR-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Iowa Electric Light & Power i
Company, et al, dated December 6,1982 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended l
(the Act), and the Commission's rules and regulations set forth
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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 l
conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the cannon 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 Speed;-
ifications, as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No' DPR-49 is' hereby es, ended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 81, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
B302170514 830209 PDR ADOCK 05000331 P
3.
Within 90 days after the effective date of this amendment, or such later time as the Commission may specify, the Licensee shall satisfy any applicable requirement of P. L.97-425 related to pursuing an agreement with the Secretary of Energy for the disposal of high-level radioactive waste and spent nuclear fuel.
4.
This license amendment is effective as of the date of its 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 9,1983 e
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ATTACHMENT TO LICENSE AMENDMENT N0.81 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Revise the Appendix A Technical Specifications by removing pages 3.5-10, and 3.7-32 and inserting revised pages 3.5-10, 3.5-10a and 3.7-32.
The revised area is identified by a vertical line.
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DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREPENT that all of the low pressure addition, the operable diesel
- core and containment cooling generator shall be demonstrated subsystems and the remaining to be operable imediately and diesel generator shall be daily thereafter..
If this requirement cannot be met, an orderly shutdown shall be initiated and the reactor shall be placed in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
Any combination of inoperable components in the core and containment cooling systems shall not defeat the capability of the remaining operable components to fulfill the cooling functions.
3.
When irradiated fuci is in the reactor vessel and the reactor is in the Cold Shutdown Condition, both core w spray systems, the LPCI and containment cooling subsystems may be inoperable, provided no work is being done which has the potential for draining the reactor
' vessel.
4.
During a refueling outage, refueling operations may continue with the suppression pool volume below the minimum I
values specified in Specification 3.7.A.1 provided all of the following conditions are met:
(a)
The reactor head is removed, the cavity is flooded, the spent fuel pool gates are removed and spent fuel pool I
water level is maintained within the limits of Specification 3.9.C.
1 3.5-10 Amendment No. 81 t
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT (b)
At least one core spray subsystem is operable with suction aligned to the condensate storage tank (s).
(c)
The condensate storage tanks contain at least 75,000 gallons of water
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which is available to the core spray subsystem.
Condensate storage tank (s) level shall be recorded at least every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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l Amendment No. 81 3.5-10a
DAEC-1 O
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to downcomer submergence, this specification is. adequate.
The' maximum temperature at the end of blowdown tested during the Humbolt Bay and Bodega Bay tests was 170*F and this is conservatively taken to be the limit for complete condensation of the reactor coolant, although condensation would occur for temperatures above 170*F.
Should it be necessary to drain the suppression chamber, this should only be done when there is no requirement for core standby cooling systems operability as explained in Basis 3.5.G or the requirements of Specificat. ion 3.5.G.4 are met.
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,pying a 50*F rise (Table 5.2-1, FSAR) in the suppression chamber water temperature and a minimum water volume of 58,900 ft3, the 170*F temperature which is used for complete condensation would be approached only if the suppression pool temperature is 12,0*F prior
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to the DBA-LOCA.
Maintaining a pool temperature of 95'F will assure that the 170*F limit is not approached.
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Inerting
. Safety Guide No. 7 assumptions for metal-water reactions r$sult to hydrogen concentrations in excess of the Safety 3.7-32 Amendment No. 81
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