ML081770161

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LTR-08-0352 - NRCs Oyster Creek Bend Before Break Criterion
ML081770161
Person / Time
Site: Oyster Creek
Issue date: 06/20/2008
From: Lochbaum D
Union of Concerned Scientists
To: Collins S
Region 1 Administrator
References
LTR-08-0352
Download: ML081770161 (1)


Text

OFFICE OF THE SECRETARY CORRESPONDENCE CONTROL TICKET Date Printed: Jun 23, 2008 15:50 PAPER NUMBER:

ACTION OFFICE:

AUTHOR:

AFFILIATION:

ADDRESSEE:

SUBJECT:

ACTION:

DISTRIBUTION:

LETTER DATE:

ACKNOWLEDGED SPECIAL HANDLING:

LTR-08-0352 EDO David Lochbaum UCS Samuel Collins NRC's Oyster Creek "Bend before Break" cr LOGGING DATE: 06/23/2008

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.r..2 Appropriate RF 06/20/2008 No Made publicly available in ADAMS via EDO/DPC NOTES:

FILE LOCATION:

ADAMS DATE DUE:

DATE SIGNED:

Union of Concerned Scientists Citizens and Scientists for Environmental Solutions June 20; 2008 Samuel J. Collins, Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415

Subject:

NRC's Oyster Creek "Bend before Break" Criterion

Dear Mr. Collins:

Janet Tauro of the Grandmothers, Mothers, and More for Energy Safety (GRAMMES) copied me on her letter to you dated June 6, 2008. Ms. Tauro raised two points in her letter that caught my attention:

1. During the May 2008, annual assessment meeting, the NRC staff was reported to have assured the public that the NRC staff had determined that current drywell conditions met the 2.0 safety factor margin, but no documents existed to support that determination.

How did the NRC reach an undocumented determination? Was it via the straw poll process that worked so well in fall 2001 on Davis-Besse?

2. Mr. Richard Conte of your staff was reported to have informed Ms. Tauro that NRC inspectors "would stop refueling in October if they saw the drywell begin to buckle."

I'm familiar with the "leak before break" criterion for reactor coolant pressure boundary integrity and the studies supporting it. This "bend before break" criterion is new to me.

Could you point me to studies, analyses, or even straw polls that provide the technical and/or regulatory basis for it?

Sincerely, David Lochbaum Director, Nuclear Safety Project Washington Office: 1825 K Street NW Suite 800 e Washington DC 20006-1232 s 202-223-6133

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