View source for RS-09-050, Requests for Relief for Alternate Examination Frequency Under ASME Code Case N-729-1 and from Requirements for Limited Examination of Reactor Vessel Head Penetration Welds in Accordance with 10 CFR 50.55a(a)(3)(i)

{{Adams
| number = ML091030444
| issue date = 04/02/2009
| title = Requests for Relief for Alternate Examination Frequency Under ASME Code Case N-729-1 and from Requirements for Limited Examination of Reactor Vessel Head Penetration Welds in Accordance with 10 CFR 50.55a(a)(3)(i)
| author name = Simpson P
| author affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000455
| license number = NPF-066
| contact person = 
| case reference number = N-729-1, RS-09-050
| document type = Letter type:RS
| page count = 2
| project = 
| stage = Other
}}

=Text=
{{#Wiki_filter:Exelon Nuclear                      www.exeloncorp.com ExeIkn.
4300 Winfield Road                                                                          Nuclear Warrenville, IL60555 RS-09-050                                                                            10 CFR 50.55a April 2, 2009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit 2 Facility Operating License No. NPF-66 NRC Docket No. STN 50-455

==Subject:==
Requests for Relief for Alternate Examination Frequency Under ASME Code Case N-729-1 and from Requirements for Limited Examination of Reactor Vessel Head Penetration Welds in accordance with 10 CFR 50.55a(a)(3)(i)
In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (a)(3)(i), Exelon Generation Company, LLC, (EGC) is requesting NRC approval of relief requests 13R-1 6 and 13R-1 7 for the Byron Station, Unit 2. These relief requests are for the third 10-year interval inservice inspection (ISI) interval. The details of these requests are enclosed in Attachments 1 and 2. The attached relief requests evaluate the proposed alternatives and conclude they provide an acceptable level of quality and safety.
In addition, EGC conducted a pre-submittal meeting with the NRC on February 13, 2008, regarding the proposed relief in Attachment 1. Attachment 1 addressed the considerations raised by the NRC during the meeting, including the Byron Station Unit 2 inspection results.
EGC requests approval of these relief requests by April 2, 2010, in support of the Byron Unit 2 spring 2010 refueling outage (B2R15).
There are no regulatory commitments contained in this letter. If you have any questions concerning this letter, please contact Ms. Lisa A. Schofield at (630) 657-2815.
Patrick R. Simpson Manager - Licensing A-17

April 2, 2009 U. S. Nuclear Regulatory Commission Page 2 Attachments:
: 1. 10 CFR 50.55a Relief Request 13R-16
: 2. 10 CFR 50.55a Relief Request 13R-17
: 3. Byron Unit 2 - Technical Basis for Reactor Pressure Vessel Head Inspection Relaxation
: 4. Evaluation of Crack Growth of a Postulated Flaw in Byron Unit 2 CRDM Nozzles by Primary Water Stress Corrosion Cracking
: 5. Metallurgical Evaluations of a 'Boat' Sample from the #68 CRDM Penetration on Byron Unit 2}}