ML20210A628
| ML20210A628 | |
| Person / Time | |
|---|---|
| Issue date: | 07/19/1999 |
| From: | Carpenter C NRC (Affiliation Not Assigned) |
| To: | Modeen D NUCLEAR ENERGY INSTITUTE (FORMERLY NUCLEAR MGMT & |
| References | |
| PROJECT-689 TAC-MA0695, NUDOCS 9907220158 | |
| Download: ML20210A628 (3) | |
Text
.,
July 19, 1999 Mr. DCvid J. Modeen '
DirGctor, Engineering.
Nuclear Generation Division Nuclear Energy Institute 1776 i Street, NW, Suite 400 Washington, DC,20006-3708
SUBJECT:
REVIEW OF EPRI TECHNICAL REPORT TR-108812, " RESPONSE OF ISOLATED PIP!NG TO THERMALLY INDUCED OVERPRESSURIZATION DURING A LOSS OF COOLANT ACCIDENT" (TAC NO. MA0695)
Dear Mr. Modeen:
The Nuclear Energy Institute (NEI) submitted Electric Power Research Institute (EPRI) report TR-108812. " Response of isolated Piping to Thermally Induced Overpressurization During a Loss of Coolant Ac-ident," to the NRC staff for review. zThe report was developed to provide technical support for a proposed American Society of Mechanical Engineers (ASME) code case addressing the issue of thermal overpressurization of isolated sections of piping raised in NRC Generic Letter 96-06,
- Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions." By letter dated February 23,1998, the staff provided NEl comments regarding EPRI report TR-108812. NEl transmitted EPRI's written response to the staff comments as an attachment to a June 15,1998, letter. The staff commented on the EPRI response in the enclosure to its October 1,1998, letter to NEl. Your April 30,1999, letter provides your response to the October 1 staff letter.
As indicated in your April 30 letter, the ASME Code is no longer pursuing a code case to -
address the issue of thermal overpressurization of isolated sections of piping. As a consequence, resolution of the technical issues contained in the staff October 1,1998, letter is no longer necessary. In the October 1,1998, letter, the staff indicated that the EPRI testing did not provide a sufficiel,t technical basis to support the strain limits that were contained in the proposed code' case. The staff opinion remains the same.
Sincerely, g
yg l
/s/
Cynthia A. Carpenter, Chief Generic issues, Environmental, Financial I
and Rulemaking Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation Project No. 6 Qjgtr'bution (File Center /PUBU Wetzel SMagruder *SEE PREVIOUS CONCURRENCES DOLUMENT NAME: G:\\EMEB\\ FAIR \\GL9606.LTR INDICATE IN aOX: *C"= COPY W/O ATTACHMENTIENCLOSURE *E"= COPY WlATTIENCL,"N"=NO COPY OFFICE EMEB:DE EMEB:DE EMEB:DE RGEB:NRR N
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' Mr. David J. Modeen 4
Director, Engineering Nuclear Generation Division
- Nuclear Energy institute 1776 i Street, NW, Suite 400 Washington, DC,20006-3708
SUBJECT:
REVIEW OF EPRI TECHNICAL REPORT TR-108812 " RESPONSE OF ISOLATED PIPING TO THERMALLY INDUCED OVERPRESSURIZATION DURING A LOSS OF COOLANT ACCIDENT"(TAC NO.
0695)
Dear Mr. Modeen:
The Nuclear Energy Institute (NEI) submitted Electric Power R earch Institute (EPRI) report TR-108812, " Response of Isolated Piping to Thermally Induc Overpressurization During a Loss of Coolant Accident," to the NRC staff for review. The eport was developed to provide technical support for a proposed American Society of Mec anical Engineers (ASME) code case addressing the issue of thermal overpressuization of isol ed sections of piping raised in NRC Generic Letter 96-06, " Assurance of Equipment Opera ity and Containment Integrity During Design-Basis Accident Conditions." By letter dated F oruary 23,1998, the staff provided NEl comments regarding EPRI report TR-108812. NEl t nsmitted EPRI's written response to the staff comments as an attachment to a June 15,19 8, letter. The staff commented on the EPRI
' response in the enclosure to its October 1,1998, etter to NEl. Your April 30,1999, letter provides your response to the October 1 staff i er.
As indicated in your April 30 letter, the ASM ode is no longer pursuing a code case to address the issue of thermal overpressuiza on of isolated sections of piping. As a consequence, resolution of the technicali ues contained in the staff October 1,1998, letter is no longer necessary. In the October 1,1 98, letter, the staff Indicated that the EPRI testing did not provide a sufficient technical basis support the strain limits that were contained in the proposed code case. The staff opinio remains the same.
Cynthia A. Carpenter, Chief Generic Issues, Environmental, Financial
& Rulemaking Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation bi0tbik:'FNbenter/PD BWetzel SMagruder DOCUMENT NAME: G:\\E B\\ FAIR \\GL9606.LTR INDICATE IN BOX:"C"= COPY We TTACHMENT/ ENCLOSURE. *E"=CO' y&(, _. L, "N" NO COPY h
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1 Nuclear Energy Institute Project No. 689 cc:
Mr. Ralph Beedle Ms. Lynnette Hendricks, Director Senior Vice President Plant Support and Chief Nuclear Officer Nuclear Energy Institute Nuclear Energy Institute Suite 400 Oite 400 1776 i Street, NW 1776 i Street, NW Washington, DC 20006-3708 Washington, DC 20006-3708 Mr. Alex Marion, Director Mr. Charles B. Brinkman, Director Programs Washington Operations Nuclear Energy Institute ABB-Combustion Engineering, Inc.
Suite 400 12300 Twinbrook Parkway, Suite 330 1776 i Street, NW Rockville, Maryland 20852 Washington, DC 20006-3708 Mr. David Modeen, Director Engineering Nuclear Energy Institute Suite 400 1776 i Street, NW Washington, DC 20006-3708 Mr. Anthony Pietrangelo, Director Licensing Nuclear Energy Institute i
Suite 400 1776 i Street, NW Washington, DC 20006-3708 Mr. Nicholas J. Liparuto, Manager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230 i
Mr. Jim Davis, Director Operations Nuclear Energy Institute Suite 400 1776 i Street, NW Washington, DC 20006-3708 I