ML083220289

Correction of Amendment No. 271 Regarding Control Rod Notch Testing Frequency

ML083220289
Person / Time
Site:	Duane Arnold
Issue date:	11/21/2008
From:	Feintuch K Plant Licensing Branch III
To:	Richard Anderson Duane Arnold
Tam P
References
TAC MD7541
Download: ML083220289 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 November 21,2008 Mr. Richard L. Anderson Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785

SUBJECT:

DUANE ARNOLD ENERGY CENTER (DAEC) - CORRECTION OF AMENDMENT NO. 271 REGARDING CONTROL ROD NOTCH TESTING FREQUENCY (TAC NO. MD7541)

Dear Mr. Anderson:

On November 6, 2008, the Nuclear Regulatory Commission staff issued Amendment No. 271 to DAEC in response to DAEC's application for amendment dated December 20,2007. The amendment is regarding control rod notch testing frequency requirements.

Subsequently the NRC staff determined that because of inadvertent errors in DAEC's application, Page 3.1-8 of Amendment No. 271 was issued with typographical errors.

Specifically, various items on Page 3.1-8 in Amendment No. 271 had been assigned incorrect alphanumeric identifiers. Numbering of these items was not the subject of Amendment No. 271 ;

also, the marked-up Page 3.1-8 in the application does not convey such typographical errors.

Enclosed please find the corrected Page 3.1-8, with lines on the right margin indicating the areas of corrections. The corrections do not change the conclusion reached by the SE.

Sincerely, Karl D. Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331

Enclosure:

As stated cc: Distribution via ListServ

Control Rod OPERABILITY 3.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Perform SR 3.1.3.2 for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> each withdrawn from discovery of OPERABLE control Condition A rod. concurrent with THERMAL POWER greater than the Low Power Setpoint (LPSP) of the AND RWM.

A.4 Perform SR 3.1.1.1 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. Two or more B.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> withdrawn control rods stuck.

C. One or more control C.1 -----------NOTE-----------

rods inoperable for RWM may be reasons other than bypassed as allowed Condition A or B. by LCO 3.3.2.1, if required, to allow insertion of inoperable control rod and continued operation.

Fully insert inoperable 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> control rod.

AND (continued)

DAEC 3.1-8 Amendment 271 Corrected by letter dated 11/21/08

November 21, 2008 Mr. Richard L. Anderson Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785

SUBJECT:

DUAI\IE ARNOLD ENERGY CEI\ITER (DAEC) - CORRECTION OF AMENDMENT NO. 171 REGARDING CONTROL ROD NOTCH TESTING FREQUENCY (TAC NO. MD7541)

Dear Mr. Anderson:

On November 6, 2008, the Nuclear Regulatory Commission staff issued Amendment No. 271 to DAEC in response to DAEC's application for amendment dated December 20,2007. The amendment is regarding control rod notch testing frequency requirements.

Subsequently the NRC staff determined that because of inadvertent errors in DAEC's application, Page 3.1-8 of Amendment No. 171 was issued with typographical errors.

Specifically, various items on Page 3.1-8 in Amendment No. 171 had been assigned incorrect alphanumeric identifiers. Numbering of these items was not the subject of Amendment No. 171; also, the marked-up Page 3.1-8 in the application does not convey such typographical errors.

Enclosed please find the corrected Page 3.1-8, with lines on the right margin indicating the areas of corrections. The corrections do not change the conclusion reached by the SE.

Sincerely, lRAI Karl D. Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-331

Enclosure:

As stated cc: Distribution via ListServ Distribution:

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