ML083520067: Difference between revisions

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#REDIRECT [[JAFP-08-0128, James A. FitzPatrick Nuclear Power Plant - Revised Submittal Date for the Stress Analysis Summary for the N2C-SE Weld Overlay]]
{{Adams
| number = ML083520067
| issue date = 12/04/2008
| title = James A. FitzPatrick Nuclear Power Plant - Revised Submittal Date for the Stress Analysis Summary for the N2C-SE Weld Overlay
| author name = Dorman E
| author affiliation = Entergy Nuclear Northeast, Entergy Nuclear Operations, Inc
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000333
| license number = DPR-059
| contact person =
| case reference number = JAFP-08-0128
| document type = Letter
| page count = 2
}}
 
=Text=
{{#Wiki_filter:S' Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.James A. Fitzpatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315-342-3840 JAFP-08-0128 December 4, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
 
==SUBJECT:==
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59
 
==REFERENCES:==
 
Revised Submittal Date for the Stress Analysis Summary for the N2C-SE Weld Overlay 1) Entergy Letter to NRC, JAFP-08-0102, "James A. FitzPatrick Request for Relief (RR-7 Revision 1) -Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs", dated October 1, 2008
 
==Dear Sir or Madam:==
Enclosure 2 of reference 1 documented a commitment to submit to the NRC, within sixty days of the completion of the Refueling Outage 18, a stress analysis summary demonstrating that the N-2C nozzle to safe-end DMW will perform its intended design function after weld overlay installation.
Due to concerns with the use of certain information contained in an EPRI Boiling Water Reactor Vessel Internals Project (BWRVIP) document, JAF will be submitting the stress analysis summary later than committed to in Reference
: 1. The stress analysis Summary will be submitted not later than December 17, 2008, 70 days after the completion of the refueling outage.There are no new commitments made in this letter If you have any questions or require additional information, please contact Mr. Eugene Dorman, Acting Licensing Manager, at 315-349-6810.
Sincerely, Eugene Dorman Acting Licensing Manager ED/ed cc: next page 46c47 KJ4A cc: Mr. Samuel J. Collins, Regional Administrator U.S. Nuclear Regulatory Commission, Region 475 Allendale Road King of Prussia, PA 19406-1415 Office of NRC Resident Inspector James A. Fitzpatrick Nuclear Power Plant P.O. Box 136 Lycoming, New York 13093 Mr. Paul Tonko, President New York State Energy Research and Development Authority 17 Columbia Circle Albany, New York 12203-6399 Mr. Bhalchandra Vaidya, Project Manager Plant Licensing Branch U.S. Nuclear Regulatory Commission Mail Stop O-8-C2A Washington, DC 20555 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Mr. Paul Eddy New York State Department of Public Services 3. Empire State Plaza Albany, New York 12223-1350}}

Revision as of 08:13, 19 March 2019

James A. FitzPatrick Nuclear Power Plant - Revised Submittal Date for the Stress Analysis Summary for the N2C-SE Weld Overlay
ML083520067
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 12/04/2008
From: Eugene Dorman
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-08-0128
Download: ML083520067 (2)
v • d • e


Text

S' Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.James A. Fitzpatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315-342-3840 JAFP-08-0128 December 4, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59

REFERENCES:

Revised Submittal Date for the Stress Analysis Summary for the N2C-SE Weld Overlay 1) Entergy Letter to NRC, JAFP-08-0102, "James A. FitzPatrick Request for Relief (RR-7 Revision 1) -Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs", dated October 1, 2008

Dear Sir or Madam:

Enclosure 2 of reference 1 documented a commitment to submit to the NRC, within sixty days of the completion of the Refueling Outage 18, a stress analysis summary demonstrating that the N-2C nozzle to safe-end DMW will perform its intended design function after weld overlay installation.

Due to concerns with the use of certain information contained in an EPRI Boiling Water Reactor Vessel Internals Project (BWRVIP) document, JAF will be submitting the stress analysis summary later than committed to in Reference

1. The stress analysis Summary will be submitted not later than December 17, 2008, 70 days after the completion of the refueling outage.There are no new commitments made in this letter If you have any questions or require additional information, please contact Mr. Eugene Dorman, Acting Licensing Manager, at 315-349-6810.

Sincerely, Eugene Dorman Acting Licensing Manager ED/ed cc: next page 46c47 KJ4A cc: Mr. Samuel J. Collins, Regional Administrator U.S. Nuclear Regulatory Commission, Region 475 Allendale Road King of Prussia, PA 19406-1415 Office of NRC Resident Inspector James A. Fitzpatrick Nuclear Power Plant P.O. Box 136 Lycoming, New York 13093 Mr. Paul Tonko, President New York State Energy Research and Development Authority 17 Columbia Circle Albany, New York 12203-6399 Mr. Bhalchandra Vaidya, Project Manager Plant Licensing Branch U.S. Nuclear Regulatory Commission Mail Stop O-8-C2A Washington, DC 20555 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Mr. Paul Eddy New York State Department of Public Services 3. Empire State Plaza Albany, New York 12223-1350

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