View source for LR-N09-0296, Response to Request for Additional Information Related to Relief Requests S1-13R-93, S2-13R-94, and SC-13R-95 (Tacs: ME1478, ME1479, ME1480, ME1481)

{{Adams
| number = ML100040070
| issue date = 12/23/2009
| title = Response to Request for Additional Information Related to Relief Requests S1-13R-93, S2-13R-94, and SC-13R-95 (Tacs: ME1478, ME1479, ME1480, ME1481)
| author name = Keenan J
| author affiliation = PSEG Nuclear, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000272, 05000311
| license number = DPR-070, DPR-075
| contact person = 
| case reference number = LR-N09-0296, S1-13R-93, S2-13R-94, SC-13R-95, TAC ME1478, TAC ME1479, TAC ME1480, TAC ME1481
| document type = Letter type:LR
| page count = 4
| project = TAC:ME1478, TAC:ME1479, TAC:ME1480, TAC:ME1481
| stage = Response to RAI
}}

=Text=
{{#Wiki_filter:PSEG Nuclear LLC
: 1.                           P.O. Box 236,, Hancocks Bridge, NJ 08038-0236 0 PSEG NuclearL.L. C.
DEC 2 3 2009 10 CFR 50.55a LR-N09-0296 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Salem Nuclear Generating Station, Units 1 and 2 Facility Operating License Nos. DPR-70 and DPR-75 NRC Docket Nos. 50-272 and 50-311

==Subject:==
Response to Request for Additional Information Related to Relief Requests S1-13R-93, $2-13R-94, AND SC-13R-95 (TACs: ME1478, ME1479, ME1480, ME1481)

==Reference:==
: 1) Letter from Jeffrie Keenan (PSEG Nuclear, LLC) to USNRC, dated June 11, 2009
: 2) Email from USNRC to Jeffrie Keenan (PSEG Nuclear LLC), dated November 23, 2009 In Reference 1, PSEG Nuclear LLC submitted relief requests $1-13R-93, $2-13R-94, and SC-13R-95 as alternatives to certain requirements specified in Section Xl of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2. In Reference 2, the NRC requested additional information. Attachment 1 to this letter provides the requested information. There are no regulatory commitments in this letter.
Should you have any questions regarding this submittal, please contact Mrs. Erin West at 856-339-5411.
Sincerely, Manager   - Licensing

*"LR-1q09-0296                                                  DEC .23 2009 Page 2 Attachments:
: 1. Response to Request for Additional Information cc:   S. Collins, Regional Administrator - NRC Region I R. Ennis, Project Manager - Salem, USNRC NRC Senior Resident Inspector - Salem P. Mulligan, Manager IV,NJBNE L. Marabella, Corporate Commitment Tracking Coordinator H. Berrick, Commitment Tracking Coordinator

ATTACHMENT 1 Salem Generating Stations Facility Operating License Nos. DPR-70 and DPR-75 NRC Docket Nos. 50-272 and 50-311 Response to Request for Additional Information Related to Relief Requests S1-13R-93, $2-13R-94, AND SC-13R-95 (TACs: ME1478, ME1479, ME1480, ME1481)
In Reference 1, PSEG proposed alternatives to certain requirements specified in Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Salem Nuclear Generating Station, Unit Nos. 1 and 2. In Reference 2, the NRC requested additional information.
NRC Request for Additional Information Table 3, "Details of TWCF [through-wall cracking frequency] Calculation for 42 EFPY [effective full power years] of Operation," of Relief Request S1-13R-93 for Salem Unit No. 1 and Table 3, "Details of TWCF Calculation for 50 EFPY of Operation," of Relief Request $2-13R-94 for Salem Unit No. 2 contain values for copper (Cu), nickel (Ni), and chemistry factor (CF). These compositions are not Illconsistent with docketed NRC r'ecords. Identify a docketed reference "containing these values, or provide a technical basis for the change from        :K previous composition values.
PSEG's Response The values for copper (Cu), nickel (Ni), and chemistry factor (CF) used in the TWCF calculations for Salem Units 1 and 2 are consistent with the values in Table 4.2.3-1 (Unit 1) and Table 4.2.3-2 (Unit 2) of the license renewal application (Reference 1) with one exception. The chemistry factor (CF) value for the Salem Unit 1 circumferential weld (9-042), is identified in S1-13R-93 as 196.6 F whereas the value identified in Reference 3 is 188.5. As identified in 51-13R-93, the Regulatory Guide 1.99, Revision 2, position for the chemistry factor is Position 1.1. For Position 1.1, the chemistry factor is calculated based on the copper and nickel content of the material using Tables 1 and 2 of R.G. 1.99. Per Table 1 of R.G. 1.99, Revision 1, for welds, the chemistry factor that corresponds to the copper and nickel values in S1-13R-93 and Reference 3 is 188.5 F.
Therefore, the value of 188.5 F in Reference 3 is the appropriate value. The use of 196.6 F in the TWCF calculations in Table 3 of S1-13R-93 is conservative.
Even with the use of the more conservative CF value, intermediate shell plate B-2402-1 is the controlling material for RTMAx-Cw. Therefore, the use of either CF value would have no impact on the value of TWCF calculated for Salem Unit 1.

References
: 1) Letter from Jeffrie Keenan (PSEG Nuclear, LLC) to USNRC, dated June 11,2009
: 2) Email from USNRC to Jeffrie Keenan (PSEG Nuclear LLC), dated November 23, 2009
: 3) Letter from Carl Fricker (PSEG Nuclear, LLC) to USNRC, dated August 18, 2009}}