ML20211K298
| ML20211K298 | |
| Person / Time | |
|---|---|
| Issue date: | 08/31/1999 |
| From: | Wen P NRC (Affiliation Not Assigned) |
| To: | Carpenter C NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9909070182 | |
| Download: ML20211K298 (16) | |
Text
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..g UNITED STATES j
NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 2005H001
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August 31, 1999 MEMORANDUM TO: Cynthia A. Carpenter, Chief Generic lasues, Environmental, Financial.
and Rulemaking Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation Peter C. Wen, Project Manager]& C. W FROM:
Generic Issues, Environmental, Financial and Rulemaking Branch.
^
Division of Regulatory Improvement Programs
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Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF AUGUST 20,1999, MEETING WITH THE NUCLEAR f
ENERGY INSTITUTE REGARDING INSPECTION OF HIGH PRESSURE SAFETY INJECTION CLASS 1 PIPING On August 20,1999, representatives of the Nuclear Energy Institute (NEI), Electric Power Research Institute (EPRI), and utilities met with Nuclear Regulatory Commission (NRC) staff at the NRC offices in Rockville, Maryland. - Attachment i lists attendees at the meeting.
This meeting was requested by the NRC staff to discuss with industry, various options for
" interim" activities regarding the inspection of high pressure safety injection (HPSI) piping prior to the conclusion of the EPRl's Materials Reliability Project (MRP) program on thermal fatigue of primary system piping, The MRP is a body representing member utilities pressurized water reactors (PWRs), EPRI, and NEl for the purpose of dealing generically with PWR-specific technical issues. In this context, interim refers to the time period prior to the completion of the MRP's two-year program to assess thermal fatigue issues in primary system piping.
In a letter to Kurt Cozens (NEI) dated August 17,1999, the staff had proposed to pursue an option whereby licensees would be able to substitute the volumetro inspection of less than 4-inch diameter Class 1 HPSI piping for ASME Code mandated inspections of less risk significant larger diameter Class 1 piping. The staff was pursuing this option from the perspective of allowing licensees to reallocate inspection resources from less risk-significant y
large diameter piping to more risk-significant small diameter piping. This exchange appears to I
be consistent with risk-informed in-service inspection programs submitted to the staff.
The NRC began the meeting with opening comments which stated the staff's intent with this proposal and the potential regulatory mechanisms for enacting it. A representative from the EPRI then made a technical presentation (Attachment 2 contains a copy of the viewgraphs) to explain the industry's position that no effective interim inspection activities could be undertaken
. at this time. The principle technical constraints presented were (1) small-diameter thick-walled 79YN piping presents a very difficult geometry for ultrasonic inspection; (2) the ability to reliably and effectively detect cracking typical of thermal fatigue damage has not been demonstrated and would require additional training and certification of inspectors; (3) the lack of appropriate o ut-1 N G 1 EA"$E0$$ 58*gc g g gg g w
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C. Carpenter August 31, 1999 weld preparation for the welds in question would require a significant amount of grinding work to remove weld crowns in order to meet ASME Code inspection requirements and may lead to additional " indications" during inspection; (4) the inability to size indications (for analytic disposition) in this geometry would result in licensees having to replace piping upon indication detection; and (5) if indications were found, licensees would be required to expand their inspection scope, possibly far beyond that originally intended by this NRC proposal. The industry representatives also noted that part of the ongoing MRP program on thermal fatigue calls for the assessment of the inspection option and the development of procedures and guidelines for performing inspections on such small diameter pipe if inspection is determined to
- be a viable option. -This assessment would consider the technical problems noted above and determine if appropriate solutions could be developed by refining existing ultrasonic examination techniques or through the use of other, currently-experimental volumetric examination techniques. Finally, the industry representatives pointed out that there could be j
many more welds in these lines than the staff had originally assumed, leading to the possibility of licensees replacing the inspection of most or all large diameter piping welds with small diameter piping inspections.
2 After caucusing, the NRC staff concluded the meeting by acknowledging that, in light of the new '
information presented by the industry, the initial staff proposal appeared to be oversimplified.
The staff noted that the intent was not to replace all large diameter piping inspections with inspections of small diameter pipe. The staff also acknowledged that given the technical difficulties presented, additional staff consideration would need to be given to what reasonable solutions exist, if any, to be pursued in the interim. The staff reaffirmed that there is still interest on the staff's part in seeing the thermal fatigue issues addressed, particularly for these small diameter lines. The staff also acknowledged that no response to the August 17,1999 letter would be expected from NEl.
Attachments:- As stated cc w/atts: See next page H
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NRC/NEl MEETING ON HPSI PIPING INSPECTIONS LIST OF ATTENDEES August 20,1999 NAME ORGANIZATION Jack Strosnider NRR/DE Bill Bateman NRR/DE/EMCB Matthew Mitchell NRR/DE/EMCB David Terao NRR/DE/EMEB Kamal Manoly NRR/DE/EMEB Peter Wen NRR/ DRIP /RGEB Michael Mayfield RES/DET/MEB Noel Dudley ACRS Dave Modeen NEl Kud Cozens NEl John Carey EPRI Stan Walker EPRI Ernest Thrukmorton Va Power / ASME Michael Robinson Duke Power T.S. Baumstark Con Edison Sherm Shaw SCE Altheia Wyche Bechtel Power Corp.
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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 Suite 400 1776 I Street, NW 1776 l 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 l Street, NW Rockville, Maryland 20852 Washington, DC 20006-3708 Mr. David Modeen, Director Mr. H. A. Sepp, Manager Engineering Regulatory and Licensing Engineering Nuclear Energy institute Westinghouse Electric Company Suite 400 P.O. Box 355 1776 i Street, NW Pittsburgh, Pennsylvania 15230-0355 Washington, DC 20006-3708 Mr. Anthony Pietrangelo, Director Licensing Nuclear Energy Institute Suite 400 1776 l Street, NW Washington, DC 20006-3708 Mr. Jim Davis, Director Operations Nuclear Energy Institute Suite 400 -
1776 I Street, NW Washington, DC 20006-3708
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\\T-DISTRIBUTION: MTG. NOTICE W/MRP(NEI) DATED Auaust 31. 1999 Hard Coov
- Central File PUBLIC RGEB r/f
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SCollins/RZimmerman BSheron WKane DMatthews/SNewberry CCarpenter FAkstulewicz JStrosnider/RWessman W Bateman l
K Wichman M Mitchell KManoly DTerao
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1 M Mayfield N Dudley E 1mbro JBirmingham GTracy, OEDO PMNS OPA l
I e
T C. Carpenter August 31, 1999 weld preparation for the welds in question would require a significant amount of grinding work to rerscv3 weld crowns in order to meet ASME Code inspection requirements and may lead to additional " indications" during inspection; (4) the inability to size indications (for analytic disposition) in this geometry would result in licensees having to replace piping upon detection; j
and (5) if indications were found, licensees would be required to expand their inspection scope, J
possibly far beyond that originally intended by this NRC proposal. The industry representatives also noted that part of the onc-2ng MRP program on thermal fatigue calls for the assessment of j
the inspection option and the development of procedures and guidelines for performing inspections on such small diameter pipe. This assessment would consider the technical problems noted above and determine if appropriate solutions could be developed by refining
]
existing ultrasonic examination techniques or through the use of other, currently-experimental
{
volumetric examination techniques. Finally, the indu-try representatives pointed out that there 1
could be many more welds in these lines than the staff had originally assumed, leading to the possibility of licensees replacing the inspection of most or alllarge diameter piping welds with small diameter piping inspections.
After caucusing, the NRC staff concluded the meeting by acknowledging that, in light of the new information presented by the industry, the initial staff proposal appeared to be oversimplified.
The staff noted that the intent was not to replace all large diameter piping inspections with inspections of small diameter pipe. The staff also acknowledged that given the technical difficulties presented, additional staff consideration would need to be given to what reasonable solutions exist, if any, to be pursued in the interim. The staff reaffirmed that there is still interest on the staff's part in seeing the thermal fatigue issues addressed, particularly for these small diameter lines. The staff also acknowledged that no response to the August 17,1999 letter would be expected from NEl.
l Attachments: As stated cc w/atts: See next page
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