ML19326C155

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Requests Addl Info Re Util 761201 Reload Analysis Supplementing NRC 770121 Request.Response Required by 770212
ML19326C155
Person / Time
Site: Arkansas Nuclear 
Issue date: 02/04/1977
From: Ziemann D
Office of Nuclear Reactor Regulation
To: Phillips J
ARKANSAS POWER & LIGHT CO.
References
NUDOCS 8004210655
Download: ML19326C155 (3)


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ARKANSAS NUCLEAR ONE ' UNIT NO.1 (ANO-1)7[%.

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We are continuing review of your December 1,1976 reload analysis for A'!0-1 and have detemined that the additional information described in. the attactament isimgu4 red.Qhis request, which.was previously

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Arkansas Power & Light Company February 4,1977 cc w/ enclosure:

Horace Jewell, Esquire House, Holms & Jewell.

1550 Tower Building Little Rock, Arkansas 72201 Phillip K. Lyon, Esouf re House, Holms & Jewell 1550 Tower Building Little Rock, Arkansas 72201 Mr. Donald Rue ter Manager, Licensing Arkansas Pcwer & Light Company Post Office Box 551 Little Rock, Arkansas 72201 Arkansas Polytechnic College Russellville, Arkansas 72801 f

ARKAMSAS POWER & LIGHT COMPANY ARKANSAS NUCLEAR ONE - UNIT NO. 1 (ANO-1)

DOCKET ~NO. 50-313 REQUEST FOR ADDITIONAL INFORMATION A.

Supply piping physicals (or spool drawings) which indicate Safety Injection System (as-built) configuration and potential for submergence under LOCA conditions. This information is required in order to complete the Appendix K review.

B.

The following questions refer to your letter 1-017-3 of January 13, 1977, which incorporated the Babcock and Wilcox proposed Rod Bow Model into parameter modifications required for Cycle 2 operation.

1.

With respect to fuel rod densification:

(a) Provide the assumptions used for the fuel rod densification analysis.

(b) Were the analyses the same as that of the Fuel Densification Report, Reference 6 of BAW 1433?

(c) Was the 140.49 inch densified fuel rod length assumed for all rods in the core or were different densified lengths applied to the appropriate batch locations?

2.

With respect to fuel rod bow:

(a) Discuss the conservatisms applied in the rod bow penalty evaluation.

(b) Was the " maximum three-cycle rod bow DNBR penalty" applied for the analysis of " Pressure-Temperature Limit Evaluation" (page 6-3 of BAW 1433)?

(c) What are the predicted burnups for E0C's 2 and 3?

(d) Provide a list of the fuel rod bow conservatisms and credits as discussed in our December 30, 1976 letter to you.

Providing quantitative values for each, discuss the credits which were previously taken, which are currently applied, and which are yet to be taken for each of the thermal margins of our letter.