ML20212H225

From kanterella
Jump to navigation Jump to search
Amend 228 to License DPR-49,revising DAEC TS SR Section 3.4.3.1, Safety/Relief Valves & Safety Valves
ML20212H225
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 09/22/1999
From: Craig C
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20212H221 List:
References
NUDOCS 9909300246
Download: ML20212H225 (4)


Text

L la ne:

}#

UNITED STATES j

NUCLEAR REGULATORY COMMISSION

(

WASMNGTON, D.C. 20066-0001

%...../

IES UTILITIES INC.

CENTRAL lOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 228 License No. DPR-49

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by IES Utilities Inc., et al., dated April 30,1999, 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 (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 Specifcations 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:

9909300246 990922 PDR ADOCK 05000331 P

PDR

. (2). Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 228 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 of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Qlld (0 k

KUC Claudia M. Craig, Chief, Section 1 Project Directorate lll Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

September 22, 1999 4

i

i ATTACHMENT TO LICENSE AMENDMENT NO. 228 FACluTY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Replace the following page of the Appendix A Technical Specifications with the attached revhed page. The revised areas are identified by amendment number and contain marginal lines indicating the areas of change.

Remove insert 3.4-7 3.4-7 1

I i

1 SRVs and SVs 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY l

SR 3.4.3.1 Verify the safety function lift setpoints In accordance of the SRVs and SVs are as follows:

with the Inservice l

Number of Setpoint Testing Program l

SRVs (osia) 1 1110 i 33.0 l

1 1120 33.0

)

l 2

1130 1 33.0 2

1140 33.0 Number of Setpoint i

SVs (osia) 2 1240 36.0 4

Following testing, lift settings shall be within i 1%.

j i

SR 3.4.3.2


NOTE---------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify each SRV opens when manually 24 months actuated.

DAEC 3.4-7 Amendment No. 228