ML052780111: Difference between revisions

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| issue date = 10/03/2005
| issue date = 10/03/2005
| title = Y020050190 - Alex Marion Ltr Re. NEI 97-06, Steam Generator Program Guidelines, Revision 2
| title = Y020050190 - Alex Marion Ltr Re. NEI 97-06, Steam Generator Program Guidelines, Revision 2
| author name = Bateman W H
| author name = Bateman W
| author affiliation = NRC/NRR/DE/EMCB
| author affiliation = NRC/NRR/DE/EMCB
| addressee name = Marion A
| addressee name = Marion A

Revision as of 02:51, 14 July 2019

Y020050190 - Alex Marion Ltr Re. NEI 97-06, Steam Generator Program Guidelines, Revision 2
ML052780111
Person / Time
Issue date: 10/03/2005
From: Bateman W
NRC/NRR/DE/EMCB
To: Marion A
Nuclear Energy Institute
Karwoski K, EMCB/DE, 415-2752
Shared Package
ML052780120 List:
References
NEI 97-06, TAC MC8354, Y020050190
Download: ML052780111 (2)


Text

October 3, 2005Mr. Alex Marion, Senior DirectorEngineering/Nuclear Generation Division Nuclear Energy Institute 1776 I Street, NW Suite 400 Washington, DC 20006-3708

SUBJECT:

NEI 97-06, STEAM GENERATOR PROGRAM GUIDELINES, REVISION 2

Dear Mr. Marion:

By letter dated September 9, 2005 (ML052710007), you provided NEI 97-06, "Steam GeneratorProgram Guidelines," Revision 2 for the Nuclear Regulatory Commission (NRC) staff's information. The NRC staff agrees with your observation that NEI 97-06, Revision 2, is consistent with Technical Specification Task Force Traveler (TSTF) 449, Revision 4, "Steam Generator Tube Integrity." As you know, this latter document was approved by the staff on May 2, 2005 (ADAMS Accession No. ML051160106) and was published in the Federal Register on May 6, 2005 (Volume 70, Number 87, Page 24126-24127).The adoption of TSTF-449 by all pressurized water reactors (PWRs) will result in an improvedregulatory framework. We hope that you encourage all PWRs to adopt TSTF 449, Revision 4, by May 2006 (consistent with the Federal Register notice). Currently, the NRC has received applications to adopt technical specifications similar to what is contained in TSTF-449 fromapproximately 15 PWR units. In a public meeting on August 12, 2005, my staff was informed that a survey was conducted on when plants were planning to submit their TSTF-449 applications. For planning purposes, it would be beneficial if the results of the survey were shared with us.As you know, TSTF 449 and NEI 97-06 are performance based. As a result, we will continue tomonitor steam generator performance at each plant consistent with our review and oversight processes. If we identify any issues with NEI 97-06 or the associated Electric Power Research Institute (EPRI) guidelines as a result of these activities, we will notify you or your staff so that you can evaluate the need to update your guidance documents. Sincerely, /(RA by William H. Bateman)/ William H. Bateman, Chief Materials and Chemical Engineering Branch Division of Engineering Office of Nuclear Reactor Regulationcc: J. Riley, NEI

ML051160106) and was published in the Federal Register on May 6, 2005 (Volume 70, Number 87, Page 24126-24127).The adoption of TSTF-449 by all pressurized water reactors (PWRs) will result in an improvedregulatory framework. We hope that you encourage all PWRs to adopt TSTF 449, Revision 4, by May 2006 (consistent with the Federal Register notice). Currently, the NRC has received applications to adopt technical specifications similar to what is contained in TSTF-449 fromapproximately 15 PWR units. In a public meeting on August 12, 2005, my staff was informed that a survey was conducted on when plants were planning to submit their TSTF-449 applications. For planning purposes, it would be beneficial if the results of the survey were shared with us.As you know, TSTF 449 and NEI 97-06 are performance based. As a result, we will continue tomonitor steam generator performance at each plant consistent with our review and oversight processes. If we identify any issues with NEI 97-06 or the associated Electric Power Research Institute (EPRI) guidelines as a result of these activities, we will notify you or your staff so that you can evaluate the need to update your guidance documents. Sincerely, /(RA by William H. Bateman)/ William H. Bateman, Chief Materials and Chemical Engineering Branch Division of Engineering Office of Nuclear Reactor Regulationcc: J. Riley, NEIDistribution

LLundKKarwoskiRidsNrrDeCGrimesRidsNrrWPCMailNRR Mailroom(Y020050190)Accession Nos.:Y020050190Package ML052780120 Incoming ML052640257 Response ML052780111INDICATE IN BOX: "C"=COPY W/O ATTACHMENT/ENCLOSURE, "E"=COPY W/ATT/ENCL, "N"=NO COPYOFFICEDE:EMCBEDE:SC:EMCBNDE:BC:EMCBNNAMEKKarwoskiLLundWBatemanDATE09/28/200510/03/200510/03/2005