RS-13-045, Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval

Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval

ML13028A263
Person / Time
Site:	Quad Cities
Issue date:	01/25/2013
From:	Gullott D Exelon Generation Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
RS-13-045
Download: ML13028A263 (2)

Text

oon RS-13-04510 CFR 50.55a January 25, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval

Reference:

Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.

S.NRC,"Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval," dated February 15, 2012 In the referenced letter, Exelon Generation Company, LLC (EGC) requested NRC approval of relief requests associated with the fifth 10-year inservice testing (IST) program interval for Quad Cities Nuclear Power Station (QCNPS). EGC's submittal included relief request RV-06, which is related to main steam safety valve testing. In an email dated January 16, 2013, the NRC requested additional information that is needed to complete the review of relief request RV-06.

In response to this request, EGC is providing the attached information.

There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803.

Respectfully, David M. Gullott Manager - Licensing

Attachment:

Response to Request for Additional Information cc:NRC Regional Administrator, Region III NRC Senior Resident Inspector, Quad Cities Nuclear Power Station 1 RS-13-045 January 25, 2013 u.s. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265 10 CFR 50.55a

Subject:

Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval

Reference:

Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, "Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval," dated February 15, 2012 In the referenced letter, Exelon Generation Company, LLC (EGC) requested NRC approval of relief requests associated with the fifth 10-year inservice testing (1ST) program interval for Quad Cities Nuclear Power Station (QCNPS). EGC's submittal included relief request RV-06, which is related to main steam safety valve testing. In an email dated January 16, 2013, the NRC requested additional information that is needed to complete the review of relief request RV-06. In response to this request, EGC is providing the attached information.

There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803.

Respectfully, David M. Gullott Manager -Licensing

Attachment:

Response to Request for Additional Information cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector, Quad Cities Nuclear Power Station ATTACHMENT Response to Request for Additional Information NRC Request Request RV-06 states, in Section 5, "If more than one safety valve fails, the sample expansion criteria of Appendix I, 1350(c) will be implemented." Section 1-1350 of Mandatory Appendix I is for Class 2 and 3 pressure relief valves. Section 1-1320 is for Class 1 pressure relief valves.

Also, Request RV-05 is requesting the use of Code Case OMN-17. Please discuss whether, if RV-05 is approved, Code Case OMN-17, primarily Paragraph (1)(c)(2), would also apply to Request RV-06.

Response The original Relief Request RV-06 transmitted in Reference 1 contained an incorrect code reference (i.e., 1-1350 should have been 1-1320, which refers to Class 1 relief valves). This error was corrected in a revised relief request that was submitted to the NRC in Reference 2.

Relief Request RV-05 requests relief from test frequency requirements for Class 1 pressure relief valves, based on the guidance of ASME Code Case OMN-1 7. Upon approval of RV-05, Exelon Generation Company, LLC would also apply Code Case OMN-17, Paragraph (1)(c)(2), to Request RV-06. It is noted that that the requirements of Code Case OMN-17, Paragraph (1)(c)(2), and ASME OM Code, Appendix I, I-1320(c)(2) are functionally equivalent.

References 1.Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, "Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval," dated February 15, 2012 2.Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, "Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval," dated September 13, 2012 Page 1 ATTACHMENT Response to Request for Additional Information NRC Request Request RV-06 states, in Section 5, "If more than one safety valve fails, the sample expansion criteria of Appendix I, 1350(c) will be implemented." Section 1-1350 of Mandatory Appendix I is for Class 2 and 3 pressure relief valves. Section 1-1320 is for Class 1 pressure relief valves. Also, Request RV-05 is requesting the use of Code Case OMN-17. Please discuss whether, if RV-05 is approved, Code Case OMN-17, primarily Paragraph (1)(c)(2), would also apply to Request RV-06. Response The original Relief Request RV-06 transmitted in Reference 1 contained an incorrect code reference (Le., 1-1350 should have been 1-1320, which refers to Class 1 relief valves). This error was corrected in a revised relief request that was submitted to the NRC in Reference

2. Relief Request RV-05 requests relief from test frequency requirements for Class 1 pressure relief valves, based on the guidance of ASME Code Case OMN-17. Upon approval of RV-05, Exelon Generation Company, LLC would also apply Code Case OMN-17, Paragraph (1)(c)(2), to Request RV-06. It is noted that that the requirements of Code Case OMN-17, Paragraph (1)(c)(2), and ASME OM Code, Appendix I, 1-1320(c)(2) are functionally equivalent.

References

1. Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, "Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval," dated February 15, 2012 2. Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, "Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval," dated September 13,2012 Page 1