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Forwards Justification for Extension of Applicability of 890807 SER Re Acceptance of BAW-10175, Rod Exchange Methodology Topical Rept.
	ML19327B249
Person / Time
Site:	Mcguire, Catawba, McGuire, 05000000
Issue date:	10/06/1989
From:	Taylor J; BABCOCK & WILCOX CO.
To:	Norberg J; Office of Nuclear Reactor Regulation
References
	JHT-89-204, NUDOCS 8910270260
	Download: ML19327B249 (7)
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Babcock & Wiwox u i , ro r oivi.i.n

' a McDermott company 3315 Old Forest Road j s

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P.O. Oox 10935 Lynchburg. VA 24506 0935 (804) 3'j5-2000 JHT/89-204 A

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October 6, 1989 jf 3 ..

' Mr. J::mes A. Norberg, Special Assistan.: I Division of Engineering and 5Lystem Technology

' Office of Nuclear Reactor Regulation W .U. S. Nuclear Regulatory Commission

!: Washington, D.C. 20555-L

, Subj ect: Rod Exchange Methodology Topical Report, BAW 10175

References:

1. .J. H. Taylor to J. A. ' Norberg, JHT/89-98, May 22,1989.

2. A. C. Thadani to J. H. Taylor, Acceptance for Referencing of . Topical Report BAW-10175, " Rod Exchange Methodology",

August 7, 1989.

Dear Mr. Norberg:

TReference 1 transmitted ' the subject topical report to the NRC for review.

Subsequently, l Reference 2 provided the Safety Evaluation Report (SER) and E' ' approval for that application. Thio SER concludes that the rod exchange

, nethodology is. acceptable for use by BWFC for McCuire Units 1 and 2 ' and

. Catawba Units 1 and 2. B&W requests that the SER be revised to include applicability to all other Westinghouse PWEs. Justification for this extended applicability is included with the attachment to this letter.

y trul. yours

.1 . 'ay1 Manager, Licensing Services

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cc: w/ attach R.B. Borsum ,

T.I.. Baldwin '

D.B. Fieno, NRC [D[g R.C. Jones, NRC

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.: 8910270260 DR 392006 7

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.p ADOCK 05000367 ij -

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Application of the Rod Exchange Methodology e

to Other Westinghouse PWRs e The ability to calculate the necessary information to support control rod worth measurements by rod enchange centers on accurately determining calculated individual bank worths and integral bank worth shapes. This calculational process basically consists of three inter-cormected analytical techniques: 1) the development of specific fuel nuclear cross sections; 2) the development of specific control rod cross-sections; and 3) the development of a core model for calculations of individual control rod bank worths and integral rod worth shapes. BWFC has successfully demonstrated the ability to calculate the information required to support control rod worth measurementu using the rod exchange method for Westinghouse-designed plants o in BAW-10175.

Presented on the following page are calculated and measured rod worthe for three cycles each of two different Westinghouse-designed plants and for the three most recent E&W 177 F.A. plant reloads. Also attached are representative examples of measured integral rod worth versus predicted integral worth for three different types of plants. Measured rod worths were determined by the standard boron exchange method. This data demonstrates that BWFC has the' ability to accurately calculate control rod worths and integral worth shapes for a variety of fuel types, control rod types, and core designs.

The techniques approved in BAW-10175 are insensitive to global parameters that may differ in Uestinghouse-designed pressurized water reactors (PWRs) other than the McGuire and Catawba units, such as the number of reactor l coolant system loops, the fuel assembly design (eg,, 15x15 vs. 17x17), and the number of fuel assemblies in the core (eg., Westinghouse 157 vs.

Westinghouse 193). Since BWFC can accurately determine individual control rod bank worths (and integral shapes), and since BWFC has demonstrated technical support for control rod worth measurements by the rod exchange method, the applicability for BA9-10175 should be extended to any Westinghouse reactors which BWFC may support in the future.

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McGuiro-1 Cy 2' McGuire-1 Cy 3 McGuire-1 Cy 4 L BAnh ERAA EIid %Diff lank 11 EAR EIgd %Diff EADh lira 1 EIld %Diff f'

[ .CC 788 801 -1.6 SB 779 844 -7.7 CC 778 819 -5.0 CD 586' 656 -10.7 CD 483 509 5.1 CD 580 573 +1.2

% Diff Mean - 4.8% "

[ Std. Dev. - 4.2%

Conn Yankee Cy 12 Conn Yankee Cy 13 Conn Yankee Cy 14 ZADh licas Erid %Diff Bank ligag Ergd %Diff EADh litaa EInd %Diff CD 2068 2050 +0.9 CD 2319 2122 +9.3 CD 2114 2183 3.2 CA 1813 1818 -0.3 CA- 1872 1813 +3.3 CA 1929 2008 -3.9 ;

CB 767 776~ -1.2 CB 802 748 +7.2 CB 929 961 -3.3

% Diff Mean - 1.0%

1 Std. Dev. - 4.7%

TMI-1 Cy 7 D B Cy 6 ANO-1 Cy 9 EADh linAs Ermd %Diff EADE liEAR Ergd %Diff EADh !!1A1 EIRd %Diff 5 1220 1208 +1.0 5 1445 1326 +9.0 5 1380 1294 +6.6 6- 934 971 -3.8 6 1083 1111 -2.5 6 1012 1057 -4.3 2

7 926 978 5.3 7 954 943 +1.2 7 825 867 -4.8

% Diff Mean - 0.3% ,

Std. Dev. - 5.2%

NOTES: 1) All Predicted rod worths calculated by B&W/BWFC.

2).All rod worths presented above are in units of PCM.

3) % Diff - (M-P)/P x 100%

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References:

Dear Mr. Norberg:

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