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| | issue date = 01/25/2013 | | | issue date = 01/25/2013 |
| | title = Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval | | | title = Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval |
| | author name = Gullott D M | | | author name = Gullott D |
| | author affiliation = Exelon Generation Co, LLC | | | author affiliation = Exelon Generation Co, LLC |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter: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 | | {{#Wiki_filter: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 |
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| ==Subject:== | | ==Subject:== |
| Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval | | Additional Information Additional Information Regarding Regarding Relief Relief Request Request RV-06 RV-06 Associated Associatedwith with the theFifth Fifth Inservice Testing Interval Interval |
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| ==Reference:== | | ==Reference:== |
| Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.
| | 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) |
| 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. | | (EGC) requested requestedNRC NRCapproval approvalofof relief requests relief requests associated associatedwith withthe thefifth fifth 10-year 10-yearinservice inservice testing testing(IST) |
| In response to this request, EGC is providing the attached information. | | (1ST) program programinterval interval for for Quad Quad Cities Nuclear Power Station (QCNPS). |
| 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. | | 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. |
| Respectfully, David M. Gullott Manager - Licensing | | 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 |
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| ==Attachment:== | | ==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
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| ==Subject:== | | ==Attachment:== |
| Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval
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| ==Reference:== | | ===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 |
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| 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.
| | 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. |
| 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.
| | valves. Section Section1-1320 1-1320isisfor for Class Class11pressure pressurerelief reliefvalves. |
| Respectfully, David M. Gullott Manager -Licensing
| | valves. |
| | | : Also, Also, Request RV-05RV-05 isis requesting requesting thethe use use ofof Code Code Case Case OMN-17. |
| ==Attachment:==
| | 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. |
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| 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. | | ===Response=== |
| 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.
| | The original original Relief Relief Request Request RV-06 transmitted in in Reference 11 contained contained an anincorrect incorrectcode code reference (i.e., |
| 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.
| | (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 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. | | 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 |
| 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
| | : 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), |
| : 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.
| | (1)(c)(2), |
| References | | to Request Request RV-06. |
| : 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}} | | 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}} |
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MONTHYEARRS-12-026, Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval2012-02-15015 February 2012 Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval Project stage: Request ML12240A0562012-09-12012 September 2012 Request for Additional Information Related to Relief Request RV-01, RV-03, RV-05, and RV-06 Project stage: RAI RS-12-149, Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval2012-09-13013 September 2012 Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval Project stage: Response to RAI RS-12-179, Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval2012-10-0808 October 2012 Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval Project stage: Response to RAI ML12325B1122012-12-0303 December 2012 Request for Additional Information Related to Relief Request, RV-04, from ASME OM Code ISTC-5150, Solenoid-Operated Valves Associated with the Fifth Inservice Testing Project stage: RAI RS-12-210, Additional Information Regarding Relief Request RV-04 Associated with the Fifth Inservice Testing Interval2012-12-0707 December 2012 Additional Information Regarding Relief Request RV-04 Associated with the Fifth Inservice Testing Interval Project stage: Request ML13018A1882013-01-16016 January 2013 NRR E-mail Capture - Quad Cities RAI for Relief Request RV-06, (TAC Nos. ME7992 & ME7993) Project stage: RAI RS-13-045, Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval2013-01-25025 January 2013 Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval Project stage: Request ML13042A3482013-02-14014 February 2013 IST Relief Request ME7981-88 and ME7990-95 Project stage: Other 2012-09-12
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Category:Letter type:RS
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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:
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