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Category:E-Mail
MONTHYEARML23349A0362023-12-14014 December 2023 NRR E-mail Capture - Draft Request for Additional Information Re Quad Cities Emergency Amendment Related to Unit 1 Diesel Generator Inoperability ML23338A1192023-11-21021 November 2023 NRR E-mail Capture - Draft Request for Additional Information Quad Cities Relief Request I5R-26 ML23268A0022023-09-22022 September 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-264-A, Revision 0 ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23262A7432023-09-19019 September 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 Acceptance of Relief Request I5R-26 ML23186A1482023-07-0505 July 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt 10 CFR 50.69 ML23186A1412023-07-0505 July 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-505 ML23163A2292023-06-12012 June 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-580, Revision 1 ML23118A1652023-04-28028 April 2023 NRR E-mail Capture - Request for Additional Information Quad Cities, Unit 2, Alternative Request I6R-11 ML23083B9572023-03-24024 March 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-564 ML23055A0392023-02-24024 February 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Amendment to Adopt TSTF-416 ML23052A0772023-02-21021 February 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance Timely Renewal Exemption Request ML22357A0392022-12-23023 December 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of I6R-10 Related to Repair of Penetration N-11B ML22354A2622022-12-20020 December 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Request to Use Certain Provisions of the 2019 Edition of the ASME BPV Code, Section XI ML23004A0262022-12-16016 December 2022 NRR E-mail Capture - Draft Request for Additional Information - Quad Cities Alternative RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves (EPD L-2022-LLR-0070) ML22348A0452022-12-14014 December 2022 NRR E-mail Capture - Draft Request for Additional Information Regarding Quad Cities Alternative I6R-09 ML22301A0902022-10-28028 October 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-301, Revision 2 ML22290A0662022-10-17017 October 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-04 Related to HPCI Drain Pot Solenoid Valve Testing ML23079A0272022-10-0505 October 2022 Licensee Outline Submittal Email (Quad Cities, 2023) ML22256A0112022-09-12012 September 2022 NRR E-mail Capture - Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage ML22224A0222022-08-12012 August 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative I6R-09 Related to Use of Certain 2013 Edition ASME Code Requirements ML22200A0782022-07-19019 July 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request to Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22206A0352022-07-13013 July 2022 NRR E-mail Capture - Draft RAI Quad Cities Alternative Related to Sblc Nozzle Inspection ML22193A0412022-07-11011 July 2022 NRR E-mail Capture - RAI Quad Cities License Amendment to Expand the Use of Prime Methods ML22187A1832022-07-0606 July 2022 NRR E-mail Capture - Completion of Activities Related to EPID L-2022-LLD-003, Quad Cities Potential NOED ML22182A1992022-07-0101 July 2022 NRR E-mail Capture - RAI Alternative RV-11, Code Case OMN-28 ML22164A7852022-06-13013 June 2022 NRR E-mail Capture - RAI Quad Cities Amendment for Spent Fuel Pool Storage Analysis ML22164A8562022-06-13013 June 2022 NRR E-mail Capture - RAI Quad Cities Alternative RV-08, Safety Relief Valves ML22164A8582022-06-13013 June 2022 NRR E-mail Capture - RAI Alternative RV-09, MSSVs ML22101A0932022-04-11011 April 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Relief I6R-01 Related to SLC Nozzle Inner Radius Inspection ML22077A4122022-03-18018 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-06 Related to MSSV Setpoint Testing ML22076A0322022-03-17017 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-03 Related to PIV Leak Test Frequency ML22075A0752022-03-16016 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-07 Related to MSIV Stroke Testing ML22068A0062022-03-0909 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-11 Related to OMN-28, Valve Position Verification ML22068A0552022-03-0909 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-09 Related to MSSV Testing ML22068A1512022-03-0909 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-10 Related to Code Case OMN-28, MOV Testing ML22067A2172022-03-0808 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative Related to MSRV Testing ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22039A2042022-02-0808 February 2022 NRR E-mail Capture - Public Meeting Dresden/Quad Cities - Proposed Alternative to Use ASME Code Case N-921 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21342A3842021-12-0808 December 2021 NRR E-mail Capture - Request for Additional Information: Quad Cities 1 & 2 License Amendment Request Transition to GNF3 Fuel ML21342A3402021-12-0808 December 2021 Acceptance Review: License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times ML21322A3112021-11-18018 November 2021 Acceptance Review: Quad Cities Units 1 and 2 - License Amendment Request New Fuel Vault Storage and Spent Fuel Pool Criticality Methodologies ML21312A5612021-11-0808 November 2021 Acceptance Review: Quad Cities, Units 1 and 2 - License Amendment Request Regarding Transition to GNF3 Fuel ML21301A0672021-10-28028 October 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-541 ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21252A0482021-09-0707 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Alternative Request for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21215A3502021-08-0303 August 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-554 ML21190A0192021-07-0808 July 2021 NRR E-mail Capture - Exelon Fleet - Request for Additional Information Regarding Adoption of TSTF-582 and TSTF-583-T ML21154A0112021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application 2023-09-22
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76" Lupold, Timothy From: Hills, David \Sent: Thursday, August 16,2012 9:13 AM To: Lupold, Timothy
Subject:
RE: DOEL 3 (BELGIUM)
-FLAW INDICATIONS IN THE REACTOR PRESSURE VESSEL Thanks Tim I Maybe then Bob will have more for us during next week's materials engineering counterparts call.-Dave From: Lupold,nTmothy Sent: Thursday, August 16, 2012 8:00 AM To: Hills, David
Subject:
RE: DOEL 3 (BELGIUM)
-FLAW INDICATIONS IN THE REACTOR PRESSURE VESSEL Bob Hardies is in Belgium today for a meeting to discuss the issue. We don't know if the indications are real or not at this point. The issue is more related to who supplied the forgings, assuming these are real indications.
Will know more once Bob returns from the meeting. About the only information we have at this point is information from the web. I've attached an email with a link to a French website. You may have to wait a bit for it to translate from French to English.From: Hills, David Sent: Monday, August 13, 2012 4:32 PM To: Rosenberg, Stacey; Lupold, Timothy Cc: Bilik, Tom; Bozga, John; Holmberg, Mel; Jones, Donald; Meghani, Vijay; Neurauter, James; Sanchez Santiago, Elba;Shaikh, Atif
Subject:
FW: DOEL 3 (BELGIUM)
-FLAW INDICATIONS IN THE REACTOR PRESSURE VESSEL FYI -See below regarding applicability to Quad Cities. Who in NRR has technical lead on this issue? Any additional details available?
-Dave From: Ring, Mark ,I Sent: Monday, August 13, 2012 2:13 PM To: Hills, David
Subject:
FW: DOEL 3 (BELGIUM)
-FLAW INDICATIONS IN THE REACTOR PRESSURE VESSEL Dave, I asked the Quad RIO to look into what the licensee knew and was doing on the Belgium NDE results indicating cracking in the vessel. Here's the reply I received from Jim McGhee. Please let me know if you need more or if you find out any more from NRC NDE folks. Thanks.-Mark From: McGhee, James Sent: Monday, August 13, 2012 1:45 PM To: Ring, Mark Cc: Draper, Jason; Elliott, Roy; Orlikowski, Robert; Cushman, Brian
Subject:
FW: DOEL 3 (BELGIUM)
-FLAW INDICATIONS IN THE REACTOR PRESSURE VESSEL The UFSAR quote below is from Section 5.3.1.2. It goes on to say I el Chicago Bridge and Iron (CB&I), which completed fabrication of the Unit 2 RPV prior to its shipment to the plant site, provided a certification comparable to the ASME Code N-I A form. The following footnote was included in that certification:
[5.3-3]"This unstamped vessel was built as a 'State Special' based on agreements between the State of Illinois and Commonwealth Edison Company. A portion of the vessel was fabricated by Rotterdam Dockyard Company. This vessel was not stamped because Rotterdam Dockyard Company does not hold an ASME certificate of authorization.
Procedures equivalent to the requirements of the ASME Code were used." From: McGhee, James Sent: Monday, August 13, 2012 1:38 PM To: Ring, Mark Cc: Cushman, Brian; Draper, Jason; Elliott, Roy; 'LUIS GASCO LEONARTE';
Orlikowskl, Robert
Subject:
RE: DOEL 3 (BELGIUM)
-FLAW INDICATIONS IN THE REACTOR PRESSURE VESSEL According to the licensee the affected unit is Unit 2. The following discussion comes from the Section 5.3.2 of the USFSAR: The Quad Cities Unit I RPV was fabricated entirely in the United States by Babcock &Wilcox (B&W). The Unit 2 RPV was fabricated by several different vendors, including one in Holland, as noted in the following paragraphs.
[5.3-2]Fabrication work on the Unit 2 bottom head assembly and lower shell course was performed by the Rotterdam Dockyard Company (RDM) in Rotterdam, Holland. These two pieces were seam-welded together and returned to the United States as a fully completed subassembly including control rod drive (CRD) stub tubes, shroud support skirt, and vessel support skirt.According to the licensee, the component steel was fabricated in the US by Babcock & Wilcox. These were sent to RDM where they were "bent" to shape and welded together.
Final assembly of the vessel was performed in the US. Without looking further, I can't determine if the beltline region was included in the RDM work.As far as inspection, they only look at the seam welds. According to the ISI guys, the only other inspection they ever did after initial construction was a VT3 on the inner clad surface and that was stopped after it was determined to have no value.They had the initial communication on the issue and are currently waiting for more specific information from the utility before determining what they need to do. The sites understanding is that the components in question at the Belgian facility were manufactured in total at the RDM facility as opposed to being assembled there as was Unit 2. I will follow up as more information comes available.
Jim From: Ring, Mark Sent: Monday, August 13, 2012 11:24 AM To: McGhee, James
Subject:
RE: DOEL 3 (BELGIUM)
-FLAW INDICATIONS IN THE REACTOR PRESSURE VESSEL Good. Thanks.2 From: McGhee, James Sent: Monday, August 13, 2012 11:06 AM To: Ring, Mark Cc: Cushman, Brian; Orlikowski, Robert; Draper, Jason; Elliott, Roy
Subject:
RE: DOEL 3 (BELGIUM)
-FLAW INDICATIONS IN THE REACTOR PRESSURE VESSEL Checking to verify manufacture of Unit 1 RPV and any beltline inspections performed that could show this type defect.Jim From: Ring, Mark Sent: Monday, August 13, 2012 9:40 AM To: Cushman, Brian; McGhee, James; Ray, Teresa Cc: LUIS GASCO LEONARTE; Draper, Jason; Elliott, Roy; Orlikowski, Robert
Subject:
FW: DOEL 3 (BELGIUM)
-FLAW INDICATIONS IN THE REACTOR PRESSURE VESSEL FYI From: Lara, Julio Sent: Monday, August 13, 2012 9:30 AM To: Casto, Chuck; Pederson, Cynthia; Shear, Gary; Reynolds, Steven; OBrien, Kenneth; Skokowski, Richard Cc: Cameron, Jamnes; Daley, Robert; Dickson, Billy; Duncan, Eric; Giessner, John; Hills, David; Kunowski, Michael;Peterson, Hironori; Riemer, Kenneth; Ring, Mark; Skokowskl, Richard; Stone, AnnMarie
Subject:
FW: DOEL 3 (BELGIUM)
-FLAW INDICATIONS IN THE REACTOR PRESSURE VESSEL From: Bernardo, Robert Sent: Monday, August 13, 2012 9:26 AM To: Taylor, Ryan Cc: Brand, Javier; Lara, Julio; Powers, Dale
Subject:
DOEL 3 (BELGIUM)
-FLAW INDICATIONS IN THE REACTOR PRESSURE VESSEL Good morning, We wanted to pass this along to the regional OpE POC's, since there are POTENTIALLY US plants that might be affected (mostly region 2): We'll keep you informed as we get more information.
IRS 8244P -DOEL 3 (BELGIUM)
-FLAW INDICATIONS IN THE REACTOR PRESSURE VESSEL Doel 3 is a PWR that commenced operation in 1982. In July, UT examinations to detect possible under-clad defects of the reactor vessel belt region instead found indications of fabrication flaws. This was the first time this type of testing had been performed on this portion of the vessel. The flaws appear to be laminar in nature, running parallel to the inside and outside surfaces being examined.
The vessel rings containing the flaws were forged in the early 1980's at the Rotterdam Dockyards, which also forged reactor vessel rings for several plants in the U.S., including Catawba 1, McGuire 2, North Anna 1 & 2, Quad Cities 1, Sequoyah I & 2, Surry 1& 2, and Watts Bar 1. Staff are in communication with the Belgian regulator to exchange information and review pending results from follow-up testing.Bob Bernardo 3 Reactor Systems Engineer US Nuclear Regulatory Commission NRR/DIRS/IOEB O-7D17; MS O-7C02A 301-415-2621 Robert.Bernardo@nrc.gov 4