ML20244B059

Summary of 800604 Meeting W/Util in Bethesda,Md Re Cycle 4 Reload at Facility W/Westinghouse Fuel.List of Attendees & Agenda Encl

ML20244B059
Person / Time
Site:	Millstone
Issue date:	06/16/1980
From:	Conner E Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
Shared Package
ML19292H640	List: ML20244B059
References
TAC-11348, TAC-11561, TAC-12505, TAC-42846, NUDOCS 8007140027
Download: ML20244B059 (3)

Text

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[ **'t UNITED STATES NUCLEAR REGULATORY COMMISSION 'f

'{'* e WASHINGTON, D. C. 20555 q

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June 16, 1980 Docket No. 50-336 j I

LICENSEE: Northeast Nuclear Energy Company (NNECO)

FACILITY: Millstone Unit No. 2 g

SUMMARY

OFMEETINGHELDONDUNEI439001TODISCUSSTHECYCLE4 RELOAD OF MILLSTONE 2 WITH WESTINGHOUSE FUEL i

The meeting had been requested by the NRC staff to discuss: (1) core power  ;

distribution; (2) setpoint methodology; (3) uncertainty analysis; and, (4) j proposed Technical Specification (TS) changes for. the Cycle 4 reload with ,

Westinghouse (_W) designed fuel. The meeting was held at the NRC's offices  !

in Bethesda, Maryland. A list of attendees is given in Enclosure 1.

After introductions and opening remarks by the NRC (Conner and-Fieno) in which the recent reorganization of NRR was explained and the type of review '

discussed, NNECO (Grs5Kae4eh) passed out the Enclosure 2 agenda.

W (Alsop) presented the power' distribution methodology. The viewgraphs used TEnclosure3)-areconsideredProprietaryClass2byW. The analysis shows that the Cycle 3 (CE) peaking factors are within 0.5Y of the Cycle 4 (Wl, values and are less than TS limits. - W has followed the Millstone 2 core since Cycle

- 1 so they have the same data as if it was a W unit,_ j They plan to use the same rod insertion limits, have assumed all accidents originated from expected ~ conditions, and have developed 90,000 axial power shapes for use in the axial power shape methodology.

W (Miranda) described the setpoint calculations (see Proprietary Class 2 Enclosure 4). For DNB determination, they will be using the W-3 correlation with a 1.3 limit instead of the present CE-1 correlation with a 1.19 value.

The nuclear peaking factor uncertainties analysis was presented by Mr. Alsop of W (see Proprietary Class 2 Enclosure 5). He pointed out that Millstone 2 must be derated to 89% power level when the plant computer is out of service. .

The uncertainty analysis was presented in the addendum to the basis safety report.

The NRC (Fieno) indicated an interest in comparison of INCA differences between CE and W.

e $WA E. L. onner, Project Manager Operating Reactors Branch #3 Division of Licensing }lrm shM Q

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Enclosures:

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Enclosure 1

..NNECO & )[ MEETING ON MILLSTONE 2, CYCLE 4 RELOAD -

l' June 4,'1980 g

- NRC :NNECO

a. ' '

Joe Parillu LMonte Conner.

I' $. Diab Mike Cass

Larry Kopp. Byron Maddox -

'H. Richings-W. L. Brooks

Daniel . Fieno . }[

M. Dunenfeld B. H. Alsop

- D.' Powers Bob Steither.

Chang Li Gary. Jacob .

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L K> g- ' Joseph T. DiMarzo -

. Harry Balukjian

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Enclosure 2: -l

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4 MILLSTONE UNIT NO. 2 i MEETING AGENDA NNEC0/W/NRC MEETING,1980 REFUELING.

JUNE II, 1980' I ' AGENDA / INTRODUCTION MIKE CASS i

II. POWER DISTRIBUTIONS BRIAN ALSOP III. SET POINTS SAM fl!RANDA-BRIAN ALSor  !

IV. UNCERTAINTY ANALYSIS BRIAN ALSOP.

V. TECHNICAL SPECIFICATIONS filKE CASS VI.

SUMMARY

MIKE CASS ,

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