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

1 oon RS-13-045 10 CFR 50.55a January 25, 2013 u.s.

U.S. Nuclear Nuclear Regulatory Regulatory Commission Commission ATTN:

A TIN: Document ControlControl Desk Washington,DC Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. Nos. DPR-29 DPR-29 and and DPR-30 DPR-30 NRC Docket Nos. 50-254 and 50-265 50-265

Subject:

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

Reference:

from D. M. Gullott Letter from Gullott (Exelon Generation Company, Company, LLC) to U. U.S.S. NRC, "Submittal of "Submittal of Relief Relief Requests Associated with the Fifth Inservice Testing Interval," dated Interval," dated February February 15, 15, 2012 In the In the referenced letter, letter, Exelon Exelon Generation Generation Company, Company,LLC LLC (EGC)

(EGC) requested requestedNRC NRCapproval approvalofof relief requests relief requests associated associatedwith withthe thefifth fifth 10-year 10-yearinservice inservice testing testing(IST)

(1ST) program programinterval interval for for Quad Quad Cities Nuclear Power Station (QCNPS).

Cities (QCNPS). EGC's EGC'ssubmittal submittal included included relief relief request requestRV-06, RV-06, which which isis related to related to main main steam steam safety valve valve testing.

testing. In In an email dated January January 16,16, 2013, 2013, thethe NRC NRC requested requested additional additional information needed to information that is needed to complete complete thethereview review ofof relief relief request request RV-06.

RV-06.

In response In response toto this this request, request, EGC EGCisisproviding providing the the attached attachedinformation.

information.

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

Respectfully,

~0~

David M. Gullott Manager -- Licensing Licensing

Attachment:

Response

ResponsetotoRequest Request forforAdditional AdditionalInformation Information cc: NRC Regional Administrator, Administrator, Region III III NRC Senior Resident Inspector, Inspector, Quad Quad Cities Cities Nuclear Nuclear Power Power Station Station

ATTACHMENT Response to Request for for Additional Additional Information Information NRC Request Request RV-06 states, Request RV-06 states, inin Section Section 5, 5, "If "If more than one safety safety valve valve fails, the sample sample expansion expansion criteria of Appendix Appendix I,I, 1350(c) will willbebe implemented." Section1-1350 implemented." Section 1-1350 of of Mandatory Mandatory Appendix Appendix II isis for Class 2 and for and 33 pressure pressurerelief relief valves.

valves. Section Section1-1320 1-1320isisfor for Class Class11pressure pressurerelief reliefvalves.

valves.

Also, Also, Request RV-05RV-05 isis requesting requesting thethe use use ofof Code Code Case Case OMN-17.

OMN-17. PleasePlease discuss discusswhether, whether, ifif RV-05 RV-05 is is approved, Code Code Case CaseOMN-17, OMN-17,primarily primarily Paragraph Paragraph(1)(c)(2),

(1)(c)(2), would would also alsoapply applyto to Request RV-06.

Request RV-06.

Response

The original original Relief Relief Request Request RV-06 transmitted in in Reference 11 contained contained an anincorrect incorrectcode code reference (i.e.,

(Le., 1-1350 1-1350 should should have been been 1-1320, 1-1320, which which refers to Class 11 relief relief valves). This This error error was corrected corrected in in aa revised revised relief relief request request thatthat was wassubmitted submittedto to the theNRC NRC in in Reference Reference2. 2.

Relief Relief Request RV-05 requests relief Request RV-05 relief from from test test frequency frequency requirements for for Class pressure Class 1 pressure relief relief valves, valves, based on on the the guidance guidanceof ofASME ASME CodeCode Case CaseOMN-1 OMN-17. Upon approval

7. Upon approvalof of RV-05, RV-05, Exelon Exelon Generation Company, LLC LLC would would alsoalso apply apply Code Code Case OMN-17, Paragraph Case OMN-17, Paragraph(1)(c)(2),

(1)(c)(2),

to Request Request RV-06.

RV-06. ItIt isis noted noted that that that that the the requirements requirements of of Code Code Case CaseOMN-17, OMN-17, Paragraph Paragraph (1)(c)(2),

(1)(c)(2), and ASME OM Code, Appendix Appendix I,I, I-1320(c)(2) 1-1320(c)(2) are arefunctionally functionally equivalent.

equivalent.

References

1. Letter Letter from from D. D. M.

M. Gullott Gullott(Exelon (Exelon Generation Generation Company, LLC) to U.S. NRC, NRC, "Submittal "Submittal of Requests Associated Relief Requests Associatedwith withthe theFifth FifthInservice InserviceTesting TestingInterval,"

Interval," dated dated February February 15, 15, 2012 Letter from

2. Letter from D.D. M.

M. Gullott Gullott(Exelon (Exelon Generation Generation Company, LLC) LLC) to U.S. NRC, "Response to Request for Request for Additional InformationRegarding Additional Information RegardingRelief ReliefRequests Requests Associated Associated with with the Fifth Fifth Inservice Testing Interval," dated September Interval," dated September 13,2012 13, 2012 Page Page 11