View source for NL-20-0538, Second Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate

{{Adams
| number = ML20129J876
| issue date = 05/08/2020
| title = Second Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate
| author name = Gayheart C
| author affiliation = Southern Nuclear Operating Co, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000348, 05000364
| license number = 
| contact person = 
| case reference number = NL-20-0538
| document type = Letter type:NL, Response to Request for Additional Information (RAI)
| page count = 4
| project = 
| stage = Response to RAI
}}

=Text=
{{#Wiki_filter:3535 Colonnade Parkway Cheryl A. Gayheart Birmingham, AL 35243 Regulatory Affairs Director 205 992 5316 tel 205 992 7601 fax cagayhea@southernco.com May 8, 2020 10 CFR 50.90 Docket Nos.: 50-348                                                                 NL-20-0538 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Units 1 and 2 Second Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate Ladies and Gentlemen:
By {{letter dated|date=October 30, 2019|text=letter dated October 30, 2019}}, Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) to the Joseph M. Farley Nuclear Plant (FNP) Unit 1 Renewed Facility Operating License (NPF-2), and the Unit 2 Renewed Facility Operating License (NPF-8) to allow for a measurement uncertainty recapture power uprate (MUR-PU). This MUR-PU LAR would increase FNPs authorized core power from 2775 megawatts thermal (MWt) to 2821 MWt (ML19308A761).
By email dated March 23, 2020 (ML20084G527), the U.S. Nuclear Regulatory Commission (NRC) staff notified SNC that additional information is needed for the staff to complete their review. By {{letter dated|date=April 22, 2020|text=letter dated April 22, 2020}} (ML20113E970), SNC responded to the Request for Additional Information.
By email dated April 29, 2020 (ML20121A147), the NRC staff notified SNC that additional information is needed regarding RAI EMIB No. 1 as discussed during a clarification call on April 28, 2020.
The enclosure to this letter provides the SNC response to the second NRC request for additional information (RAI).
This letter contains no NRC commitments.
In accordance with 10 CFR 50.91, SNC is notifying the state of Alabama of this license amendment RAI response by transmitting a copy of this letter to the designated state official.
If you have any questions, please contact Jamie Coleman at 205.992.6611.

U. S. Nuclear Regulatory Commission NL-20-0538 Page 2 I declare under penalty of perjury that the foregoing is true and correct.
Executed on May 8, 2020.
C. A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Company CAG/was/scm

==Enclosure:==
SNC Second Response to Request for Additional Information (RAI) cc:   NRC Regional Administrator NRC NRR Project Manager - Farley 1&2 NRC Senior Resident Inspector - Farley 1 & 2 Alabama - State Health Officer for the Department of Public Health SNC Document Control R-Type: CFA04.054

Joseph M. Farley Nuclear Plant - Units 1 and 2 Second Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate ENCLOSURE SNC Second Response to Request for Additional Information (RAI)

SNC Second Response to Request for Additional Information (RAI)
NL-20-0538 Follow-up RAI for EMIB RAI No. 1 The EMIB RAI No. 1 response specifies that the Farley ASME Codes of Record for Inservice Testing (IST) and Inservice Inspection (ISI) are ASME OM Code (2004 Edition thru 2006 Addenda) and ASME BPV Code, Section XI (2007 Edition thru 2008 Addenda), respectively.
The NRC regulations at 10 CFR 50.55a(a)(3)(v)(B) state, in part, that licensees must comply with the provisions for examination and testing of snubbers in Subsection ISTD of the ASME OM Code  when using the 2006 Addenda and later editions and addenda of Section XI of the ASME BPV Code. Please clarify why ASME BPV Code, Section XI, is used for the ISI program for snubbers at Farley.
SNC Response:
The original response to EMIB RAI No. 1 omitted the word supports. ASME Section XI Code 2007 Edition through 2008 Addenda, for the ISI program, applies to the snubber supports. The IST program for snubbers complies with ASME OM Code 2004 Edition through the 2006 Addenda. The original response to EMIB RAI No. 1 should be revised as shown below.
The Farley MUR uprate evaluation and review of the IST program was based on the fifth ten-year interval IST Program Plan which complies with the requirements of the ASME OM Code 2004 Edition through the 2006 Addenda. The fifth ten-year interval began on December 1, 2017 and concludes on November 30, 2027. A copy of the IST Program was transmitted to the NRC via letter NL-17-2005, dated March 11, 2019 (ML19070A247). The IST Snubber Program Plan was submitted separately under NL-19-0347, dated April 10, 2019 (ML19100A437).
The inservice examination and testing of snubbers is in alignment with the plant IST program.
The IST program for examination, testing, and service life monitoring of snubbers, pin to pin inclusive, uses the same ASME OM Code Edition and Addenda discussed above. The ISI program for snubber supports uses ASME Section XI Code 2007 Edition through 2008 Addenda which is the ISI program code for the fifth ten-year interval.
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