View source for JAFP-03-0179, Proposed Alternatives in Accordance with 10CFR50.55a(g)(6)(ii)(A)(5) and Relief from ASME Section XI Code Regarding Inspection of RPV Vertical Shell Welds, Per 10CFR50.55a(g)(6)(i)

{{Adams
| number = ML040070104
| issue date = 12/30/2003
| title = Proposed Alternatives in Accordance with 10CFR50.55a(g)(6)(ii)(A)(5) and Relief from ASME Section XI Code Regarding Inspection of RPV Vertical Shell Welds, Per 10CFR50.55a(g)(6)(i)
| author name = Sullivan T
| author affiliation = Entergy Nuclear Northeast
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000333
| license number = DPR-059
| contact person = 
| case reference number = JAFP-03-0179
| document type = Letter type:JAFP
| page count = 3
}}

=Text=
{{#Wiki_filter:Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP a Entegy                                                                             RO. Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 T.A. Sullivan Site Vice President - JAF December 30, 2003 JAFP-03-01 79 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station O-P1-17 Washington, DC 20555-0001

==SUBJECT:==
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Alternatives in Acordance with 10CFR503552(g)(6)(ii)(A)(5) and Relief from ASMY Section XI Code Regnrding Inspection of RPV Vertical Shell Welds nurcmiant to 10 CFR 50.55 ((6)(i)

==REFERENCE:==
: 1.      Entergy Letter (JAFP-03-0111) to NRC, "Proposed Alternatives in Accordance with I OCFR50.55a(g) (6)(ii)(A)(5) and Relief From ASME Section XI Code Regarding Inspection of RPV Vertical Shell Welds pursuant to IOCFR50.55a(g)(6)(i), August 4, 2003

==Dear Sir:==

Entergy proposed Relief Request #30 to the James A. FitzPatrick (JAF) Inservice Inspection Program (Reference 1). The NRC staff in a recent telephone conversation on December 10, 2003 requested that Entergy provide additional details from previous inspection results documented in Reference 1. This information is provided in Attachment I to this letter.
If you have any questions, please contact Mr. Andrew Halliday at 315-349-6055.
Very truly yours, Site Vice President Attachment Harq

A-t - .
cc: Regional Administrator U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Office of the Resident Inspector U. S. Nuclear Regulatory Commission P.O. Box 136 Lycoming,NY 13093 Mr. G. Vissing, Project Manager Project Directorate I Division of Licensing Project Management U. S. Nuclear Regulatory Commission Mail Stop OWFN 8C2 Washington, DC 20555 Mr. Peter R. Smith, Acting President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza Albany, NY 12223

Attachment 1 to JAFP-03-0179 Proposed Alternatives in Accordance with 10CFR50.55a(g)(6flhi)(A)(5) and Relief from ASME Section XI Code Regarding Inspection of RPV Vertical Shell Welds pursuant to 10 CFR 50.55a ()(6)(i)
From the standpoint of protecting the FitzPatrick RPV against pressurized thermal shock (PTS), the FitzPatrick RPV is a weld-limited vessel. The lower shell axial welds contain the material most susceptible to radiation-induced embrittlement in the RPV (i.e., the limiting material in the vessel). These welds, designated 2-233 A,B,C on vessel drawings and VV-4A, VV-4B and VV-4C on ISI documents, contain heat 27204/12008 (Reference
: 2) and have a RTndt @ End of Life (EOL) = 127.90 F (Reference 3 and 4).
Welds VV-4A and VV-4B were examined in RO1 5 (Phase I) from vessel OD side with 73% of total weld length coverage, including 91 % in the beltline region (Reference 1). A review of the ultrasonic examination data acquired on these welds revealed no recordable indications.
Lower shell weld VV-4C will be examined in RO16 (Phase II) from vessel ID side, also with 73% of total projected weld length coverage, and 100% in the beltline region (Reference 1).
Lower intermediate shell axial welds 1-233 A,B,C (heat 13253/12008, (Reference 2), and RTndt (0 EOL = 119.9 0 F) (Reference 3 and 4) corresponding to welds VV-3A, VV-3B and VV-3C will be examined in R016 (Phase II) from vessel ID side, with 41%, 86%
and 41% of total projected weld length coverage, respectively. These welds are less susceptible to radiation-induced embrittlement than are the limiting welds in the lower shell region of the vessel.

==References:==
: 1. Entergy Letter (JAFP-03-0 1) to NRC, "Proposed Alternatives in Accordance with 10CFR50.55a(g)(6)(ii)(A)(5) and Relief From ASME Section XI Code Regarding Inspection of RPV Vertical Shell Welds pursuant to I OCFR50.55a(g)(6)(i), dated August 4, 2003
: 2. GE Report DRF B1 1-00732-02, "Resolution of Comments for Report GE-NE-B1 100732-01, Rev. 1, Plant FitzPatrick RPV Surveillance Materials Testing and Analysis of 120 degree F Capsule at 13.4 EFPY."
: 3. NYPA Letter (JPN-99-035) to NRC, "Comments on the Reactor Vessel Integrity Database", dated October 15, 1999.
: 4. Interface Control Document No. JAF-ICD-RPV-03439, "Reactor Vessel Integrity Database (RVID) Comments and Corrections in Response to NRC Request dated July 6, 1999", dated October 8, 1999.}}