ML20154G411
| ML20154G411 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 10/01/1998 |
| From: | Richard Laufer NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20154G415 | List: |
| References | |
| NUDOCS 9810130165 | |
| Download: ML20154G411 (5) | |
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UNITED STATES l
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NUCLEAR REGULATORY COMMISSION o,
WASHINGTON, D.C. 20666-0001 l
s IES UTILITIES INC.
l CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE l
DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No. 224 License No. DPR-49
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by lES Utilities Inc., et al., dated April 15,1998, complies with the standards and requirements of the Atomic Energy Act of1954, 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 (i) 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 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:
9810130165 981001 PDR ADOCK 05000331 p
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(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 224, 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 and shall be implemented within 30 days of the date ofissuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
I Richard J. Laufer, Project Manager Project Directorate lll-3 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: October 1, 1998 i
~ ATTACHMENT TO LICENSE AMENDMENT NO. 224 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 verticallines.
Remove Insert 3.4-21 3.4-21 3.4-24 3.4-24 1
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RCS P/T Limits 3.4.9 ACTIONS (continued) l
. CONDITION REQUIRED ACTION COMPLETION TIME l
C.
NOTE---------
C.1 Initiate action to Immediately Re uired Action C.2 restore parameter (s) sh 11 be completed if to within limits.
this Condition is entered.
BiQ C.2 Determine RCS is Prior to Requirements of the acceptable for entering MODE 2 LCO not met in other operation.
or 3.
than MODES 1, 2.
and 3.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1
NOTE--------------------
Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.
Verify:
30 minutes a.
RCS pressure and RCS temperature 're a
within the applicable limits in Figure 3.4.9-1.
b.
RCS heatup and cooldown rates are s 20*F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period during inservice leak and hydrostatic testing (Curve A).
c.
RCS heatup and cooldown rates are s 100'F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period during non-nuclear heating (Curve B) and nuclear heating (Curve C).
(continued)
DAEC 3.4-21 Amendment 224
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RCS P/T Limits 3.4.9 l
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I Curve A(EFPY) 1400 18.20,24.28.32 B
C A. System iydrotest Lirr rt with Fuel ir Vessel (20*F'br heatup/co >ldown rate)
B Nor>Nuc' ear Heating L imit, Valid to 32 EFPY(100*F/hr heatup/cooldown rate)
C - Nuclear i Core Critical) Limit. Valid ia 32 t:w niuu?Inr heatup/cooldown rate)
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50 100 150 200 250 300 350 Minimum Reactor Vessel Metal Temperature (F)
Figure 3.4.9-1 (page 1 of 1) l Pressure Versus Minimum Temperature Valid to Thirty-two Full Power Years, per Appendix G of 10CFR50 l
DAEC 3.4-24 Amendment 224