ML20077A581
| ML20077A581 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 11/18/1994 |
| From: | Hsia A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077A585 | List: |
| References | |
| NUDOCS 9411250059 | |
| Download: ML20077A581 (5) | |
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t UNITED STATES NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20666-0001
( '"**,f IES UTILITIES INC.
CENTRAL IOWA POWER COOPERATIVE l
CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DVANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 204 License No. DPR-49 I
1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment by IES Utilities Inc., et al.,
dated July 12, 1994, complies with the standards and requirements I
of the Atomic Energy Act of 1954, as amended (the Act), and the l
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 Specifi-cations 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:
I l
9411250059 941118 f
PDR ADOCK 0500 1
1
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 204, 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
./n b - QMA qr Anthony Hs'a Project Manager Project Di ettorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: November 18, 1994 i
i l
ATTACHMENT TO LICENSE AMENDMENT NO.204 FACILITY OPERATING _1.lCENSE NO. OPR-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 vertical lines.
Femove Insert 3.2-23 3.2-23 3.2-24 3.2-24
i Table 4.2-C
- t-y CONTROL 900 BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS fi OPERATIONAL CONDITIONS CHANNEL FOR WHICH 2
CHANNEL FUNCTIONAL CHANNEL SURVEILLANCE
.o TRIP FUNCTION CHECK TEST CALIBRATION (*)
REQUIRED Rod Block Monitor I
x d"* '
(*'
C Upscale D
S / d"* ),
SA 1*
Downscale(Power Referenced)D S/
3*'
SA 1*
Q Inoperative NA S / ' d" * ','
NA 1*
~
APRM x
L Ei l 710w Blased Upscale D
S
(
1 Upscale in Startup D
S C
25
- m g
Inoperative NA S
NA 1,f,5 l
Downscale D
S Q
1 Intermediate Range Monitors Detector not tull in NA S
,W R
2,5 Upscale D
S
,W Prior to Startup or Controlled Shutdown 2,5 Inoperative NA S
'W NA 2,5 wy Downscale D
S W
Prior to Startup or Controlled Shutdown 2,5 U
Source Ranae Monitors Detector not full in NA S
,W R
2,5 Upscale D
S
,W Prior to Startup or Controlled Shutdown 2,5 2
Inoperative NA S
W NA
,5 Downscale D
S (b), W Prior to Startup or Controlled Shutdown 2,5 Scram Discharae Volume i
Water Level-High NA Q
R 1,2,5**
I Recirculation Flou l
Upscale NA S
SA 1
(*)
{ ,,,
Inoperative NA S
NA 1
l Comparator NA S
3 SA 1
l Reactor Mode Switch -
NA R
NA 3,4 l
Shutdown Position l
l
DAE(-l Table 4.2-C (Continued)
CONTROL R0D BLOCK INSTRUMENTATION SVRVEILLANCE RE0VIREMENTS NOTES (a)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(b)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.
(c)
Includes reactor manual control multiplexing system input.
(d)
Prior to exceeding 30% RATED THERMAL POWER, if not performed within the previous 7 days.
(e)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entering RUN and prior to exceeding 25% RATED i
THERMAL POWER, if not performed within the previous 7 days.
With THERMAL POWER 2 30% of RATED THERMAL POWER.
With more than one control rod withdrawn.
Not applicable to control rods removed or withdrawn per Specification 3.9.A.
1 I
Amendment No. f>A,/23,//3,JES,/$3.
3.2-24 204
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