ML20248A677

Submits Summary of 980311 Meeting W/Siemens Corp in Rockville,Md to Discuss Issues Re Revised Steamline Break Methodology.List of Attendees & Slides Presented by Licensee Encl

ML20248A677
Person / Time
Site:	Millstone
Issue date:	05/27/1998
From:	Wang E NRC (Affiliation Not Assigned)
To:	Essig T NRC (Affiliation Not Assigned)
References
NUDOCS 9806010013
Download: ML20248A677 (15)

Text

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May 27, 1998 MEMORANDUM TO:

Thomas H. Essig, Acting Chi:f go_gjf Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:

Egan Wang, Reactor Engineer Original Signed By:

Generic issues and Reguletory improvements Section Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation

SUMMARY

OF MEETING HELD ON MARCH 11,1998 WITH SIEMENS TO DISCUSS ISSUES RELATED TO REVISED STEAMLINE BREAK METHODOLOGY On May 21,1998, the staff held a public meeting with Siemens Power Corporation (SPC) at NRC headquarters in Rockville, Maryland. Utility representatives were also present for this meeting. The purpose of this meeting was to present to the staff proposed changes to SPC steamline break methodology. Attachment i lists meeting participants. Attachment 2 provides a set of slides presented by SPC during the meeting.

SPC presented an agenda for this meeting. Topics discussed in the meeting included summaries of approved and revised steamline break methodologies, power distribution I

determination, reactivity comparisons, and Doppler reactivity in ANF-RELAP.

l SPC stated that in addition to minimum departure from nuclear boiling ration, SPC also performs centerline melt evaluation because centerline melt generally results fuel failures. SPC i

noted a methodology change - iterations (20) to confirm power distribution convergence. In l

addition, SPC is taking consideration of moderator density distribution (as opposed to changing flow to simulate a moderator density distribution). SPC stated that all plants'steamline break i

analyses will be reperformed. For Millstone Unit 2, the analysis should be completed by the end of May. Plant specific application for Millstone Unit 2 is currently scheduled to be submitted in June or July. SPC also noted that Millstone Unit 2 needs this reanalysis to restart.

The staff questioned the restart schedule for Millstone Unit 2. The utility representative stated that it is tentatively scheduled for October 1998. The staff stated that review of such topical reports cannot be started until a license amendment is requested.

Attachments: As stated cc:

Mr. Jerry Holm Product Licensing Siemens Power Corporation 2101 Hom Rapid Road i,

P.O. Box 130 jt Richland, Washington 99352-0130

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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20566-0001 g., g May 27, 1998 MEMORANDUM TO:

Thomas H. Essig, Acting Chief Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:

Egan Wang, Reactor Engineer Generic Issues and Regulatory improvements Section Generic issues and Environmental Projects Branch Division of Reactor Program Managemer.t -

Office of Nuclear Reactor Regulation

SUMMARY

OF MEETING HELD ON MARCH 11,1998 WITH SIEMENS TO DISCUSS ISSUES RELATED TO REVISED STEAMLINE BREAK METHODOLOGY I

On May 21,1998, t_he staff held a public meeting with Sicmens Power Corporation (SPC) at NRC headquarters in Rockville, Maryland. Utility representatives were also present for this meeting. The purpose of this meeting was to present to the staff proposed changes to SPC i

steamline break methodology. Attachment 1 lists meeting participants.' Attachment 2 provides a set of slides presented by SPC during the meeting._

SPC presented an agenda for this meeting. Topics discussed in the meeting included F

summaries of approved and revised steamline break methodologies, power distribution determination, reactivity comparisons, and Doppler reactivity in ANF-RELAP.

i SPC stated that in addition to minimum departure from nuclear boiling ration, SPC also performs centerline melt evaluation because centerline melt generally rescits fuel failures. SPC noted a methodology change - iterations (20) to confirm power distribution convergence. In addition, SPC is taking consideration of moderator density distribution (as opposed to changing flow to simulate a moderator density distribution). SPC stated that all plants'steamline break analyses Wil be reperformed. For Millstone Unit 2, the analysis should be compleied by the end of May. Plant specific application for Millstone Unit 2 is currently scheduled to be submitted in June or July. SPC also noted that Millstone Unit 2 needs this reanalysis to restart.

The staff questioned the restart schedule'for Millstone Unit 2. The utility representative stated that it is tentatively scheduled for October 1998. The staff stated that review of such topical reports cannot be started until a license amendment is requested.

Attachments: As stated cc:

Mr. Jerry Holm Product Licensing Siemens Power Corporation 2101 Hom Rapid Road P.O. Box 130 -

Richland, Washington 99352-0130

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List of Attendees Name Organization Phone Number Egan Wang USNRC 301-415-1076 Joseph Staudenmeier USNRC 301-415-2869 S. E. Jensen SPC 509-375-8477 Summer Sun USNRC 301-415-2868 Daniel Denver SPC 509-375-8395 J. S. Holm SPC 509-375-8142 Daniel Mcdonald.

USNRC 301-415-1408 Ralph Caruso USNRC 301-415-1813 Martin Van Haltern Northeast Utilities 860-832-4776 Gregory Baustian Consumer Energy 616-764-2533 l

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