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Category:E-Mail
MONTHYEARML24298A0202024-10-24024 October 2024 NRR E-mail Capture - Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, Relief Request I4R-19 and I4-26, Associated with the Fourth and Fifth Inservice Inspection Intervals ML24282A7042024-10-0808 October 2024 NRR E-mail Capture - Acceptance Reviews of Relief Requests Associated with the Fifth Inservice Inspection Interval at Byron and Braidwood Stations ML24271A0282024-09-26026 September 2024 E-Mail - Dresden Nuclear Power Station, Unit 1 - Site Visit Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations ML24254A2082024-09-10010 September 2024 NRR E-mail Capture - Quad Cities, Unit Nos. 1 and 2 - Alternative to RV-08, Rev 1, SRV Testing Interval - Acceptance of Requested Licensing Action Re Relief Request Associated with Safety Relief Valve Testing Interval ML24250A1062024-09-0606 September 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - Proposed Alternative to Utilize Code Case OMN-32 (L-2024-LLR-0030) ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24234A2772024-08-21021 August 2024 NRR E-mail Capture - Final RAI - Constellation Energy, LLC - Fleet Request - Proposed Alternative Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds (L-2024-LLR-0031) ML24233A2472024-08-20020 August 2024 Acceptance of Requested Licensing Action Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations ML24228A1922024-07-29029 July 2024 Request for Additional Information Response Due Date Extension E-Mail String ML24199A1842024-07-15015 July 2024 RAI-LAR for Limerick EPID: L-2024-LLA-0079- Use This Version ML24197A0482024-07-12012 July 2024 Information Request for the Quad Cities Nuclear Station Biennial Problem Identification and Resolution Inspection ML24197A0162024-07-12012 July 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591 ML24185A1782024-07-0303 July 2024 NRC Email Response to Peach Bottoms Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations ML24180A0042024-06-28028 June 2024 NRR E-mail Capture - Acceptance Review for Braidwood and Byron - Request for Exemption from 10 CFR 50.46 and Appendix K (L-2024-LLE-0019) ML24180A0032024-06-28028 June 2024 NRR E-mail Capture - NRC Acceptance Review of Byron/Braidwood Amendment for Transition to Framatome Gaia Fuel (L-2024-LLA-0072) ML24306A0072024-06-26026 June 2024 NRR E-mail Capture - Verbal Relief for Byron, Unit 2, Three Specific Air-operated Valves in the Essential Service Water System (L-2024-LLR-0042) ML24192A3642024-06-21021 June 2024 State Rad Health Reply Email Re Draft Environmental Assessment for the Three Mile Island Unit 2 ML24176A0232024-06-21021 June 2024 NRR E-mail Capture - Dresden Nuclear Power Station, Units 2 and 3 - Acceptance Review of the Amendment Request to Adopt 10 CFR 50.69 ML24176A1292024-06-20020 June 2024 Estimated Completion Schedule Change Email ML24176A0182024-06-20020 June 2024 NRR E-mail Capture - NRC Acceptance Review of Byron/Braidwood Amendment to Remove Extraneous Detail Related to Beacon ML24170A3912024-06-18018 June 2024 NRR E-mail Capture - Revision of Estimated Hours to Complete Review of Byron/Braidwood Amendment to Revise TS 3.7.15, 3.7.16, and 4.3.1 (L-2023-LLA-0136) ML24159A0122024-06-0606 June 2024 NRR E-mail Capture - Dresden Nuclear Power Station, Units 2 and 3 - Acceptance of Licensing Amendment to Adopt TSTF-505 and TSTF-591 ML24156A0082024-05-31031 May 2024 NRR E-mail Capture - Constellation Energy, LLC - Fleet Request - Acceptance of Proposed Alternative Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds (L-2024-LLR-0031 ML24141A2452024-05-20020 May 2024 NRR E-mail Capture - NRC Acceptance Review of Byron/Braidwood Amendment to Delete Technical Specification 5.6.5.b.5 (L-2024-LLA-0055) ML24163A3522024-05-15015 May 2024 Meeting Feedback from May 14, 2024, Meeting with Constellation on Peach Bottom Atomic Power Station Units Nos. 2 and 3 ML24135A0182024-05-13013 May 2024 NRR E-mail Capture - Draft Request for Additional Information Quad Cities TSTF-505 Amendment ML24131A0612024-05-10010 May 2024 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Proposed Alternative to Utilize Code Case OMN-32 (L-2024-LLR-0030) ML24107A9192024-05-0808 May 2024 Email to Christian Williams Re Decision on the Limerick Exemption ML24222A4092024-05-0303 May 2024 NRR E-mail Capture - Request for Additional Information Regarding Reactor Water Cleanup (RWCU) Pump Rooms - L-2023-LLA-0118 ML24107A9202024-05-0303 May 2024 Email to Christian Williams Re Availability of Environmental Assessment for the Limerick Exemption ML24122C6742024-05-0101 May 2024 Response to a Request from NRC Review of a Draft EA for an Exemption for the Limerick Generating Station ML24122B5072024-05-0101 May 2024 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-591, Revision 0 ML24086A5182024-04-30030 April 2024 E-mail to Christian Williams Decision on the Exemption Request for Quad Cities ML24122C6702024-04-29029 April 2024 Request from NRC Review of a Draft EA for an Exemption for the Limerick Generating Station ML24086A4782024-04-24024 April 2024 Email to Christian Williams Availability of Environmental Assessment for the Quad Cities Exemption ML24114A1702024-04-15015 April 2024 Request for State Review of the Quad Cities HI-STORM Exemption Request Environmental Assessment ML24102A2422024-04-10010 April 2024 NRR E-mail Capture - Draft Request for Additional Information Quad Cities TSTF-505 and 50.69 Amendments ML24066A0802024-04-0101 April 2024 Email to Christian Williams Decision on the Exemption Request for Dresden Nuclear Power Station Unit 2 and Unit 3 Independent Spent Fuel Storage Installation in Morris, Illinois ML24089A0102024-03-29029 March 2024 NRR E-mail Capture - Quad Cities Unit Nos. 1 and 2 - Alternative to Core Spray Pump Testing - Acceptance of Requested Licensing Action Relief Request Associated with the Sixth Inservice Testing Interval ML24088A3192024-03-28028 March 2024 Audit Plan Associated with Peach Bottom, Unit 1 - 10 CFR 50.82(a)(3) Alternate Decommissioning Schedule ML24065A4892024-03-28028 March 2024 Email to Christian Williams Availability of Environmental Assessment for the Exemption Request for Dresden Nuclear Power Station Unit 2 and Unit 3 Independent Spent Fuel Storage Installation in Morris, Illinois ML24078A3772024-03-15015 March 2024 Email to the State of Illinois Requesting Review of the Dresden Exemption Request Environmental Assessment ML24066A1532024-03-0606 March 2024 NRR E-mail Capture - Request for Additional Information TSTF-505, R2, Provide Risk-Informed Extended Completion Times, RITSTF (Risk-Informed Technical Specification Task Force) Initiative 4b and 10 CFR 50.69 License Amendments ML24066A0872024-03-0404 March 2024 NRR E-mail Capture - Dresden 2 and 3 - Request for Additional Information for Alternative Request I5R-22 ML24067A1242024-03-0101 March 2024 Email to Christian Williams: Request for Additional Information Regarding Dresden Relief Request Dated February 23, 2024 ML24065A2922024-02-28028 February 2024 2/28/24 Email from Constellation: Clarifying Information Regarding Dresden Relief Request Dated February 23, 2024 ML24053A3382024-02-22022 February 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds (L-2023-LLR-0062) ML24051A0652024-02-16016 February 2024 Digital I&C LAR RAIs Re HFE (Email) ML24064A1222024-02-0606 February 2024 Biennial Problem and Identification Inspection Request for Information ML24030A0022024-01-30030 January 2024 NRR E-mail Capture - NRC Acceptance Review for Braidwood Station, Units 1 and 2, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators 2024-09-06
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1 NRR-PMDAPEm Resource From: Wiebe, Joel Sent: Wednesday, November 06, 2013 2:50 PM To: Tom Loomis
Subject:
Preliminary Additional RAI Questions Regarding Use of Code Case N-786 Tom, Let me know if you need a clarifying phone call regarding these additional RAIs. A response is requested within 30 days.
Joel By letter dated February 27, 2013 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML13059A498) as supplemented on June 24, 2013 (ADAMS Accession No. ML13176A143), Exelon Generation Company (Exelon) requested relief from the requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, IWA-4000, for the repair of degraded Class 2 and 3 moderate-energy carbon steel piping systems at Braidwood Station Units 1 and 2, Byron Station Units 1 and 2, Clinton Power Station Unit 1, Dresden Nuclear Power Station Units 2 and 3, LaSalle County Stations Units 1 and 2, Limerick Generating Station Units 1 and 2, Oyster Creek Nuclear Generating Station, Peach Bottom Atomic Power Station Units 2 and 3, Quad Cities Nuclear Power Station Units 1 and 2, and Three Mile Island Nuclear Station Unit 1.
To complete its review, the Nuclear Regulatory Commission (NRC) staff requests the following additional information:
- 1. Exelon's proposed alternative to allow the use of sleeves in lieu of the requirements of the ASME code for the repair of degraded class 2 and 3 moderate energy piping appears to be based primarily on the premise of identifying the corrosion mechanism involved and assuming a corrosion rate of twice the measured corrosion rate at the degraded pipe location or four times the corrosion rate as identified by other means or in other pipe locations (
Reference:
Exelon's response to RAI Questions Nos. 9 and 10 dated June 24, 2013). However, it is not clear:
(a). how the corrosion mechanism will be determined, i.e., what testing will be conducted and if inside diameter sampling will be conducted to identify the corrosion mechanism such as microbiologically influenced corrosion (MIC); (b). how the corrosion rate will be determined once the corrosion mechanism is identified, i.e., will the identified corrosion rate be based on literature data, other plant data, or on system-specific experimental data; (c). how the corrosion rate will be determined if the corrosion mechanism is not conclusively determined, i.e., if the corrosion mechanism is not conclusively identified will the mechanism with the highest corrosion rate (probably MIC) be used; (d). whether the same standards for the determination of corrosion rates be applied to temporary repairs (Type A and partial-structural Type B sleeves) and permanent repairs (full-structural Type B sleeves).
Provide additional information to address issues (a) to (d) above.
- 2. The proposed alternative requires examinations of permanent repairs (full-structural Type B sleeves) on the first two refueling outages following repairs and then every fourth refueling outage. It appears that the purpose of these examinations is to verify that the degradation has not spread laterally beyond the sleeve or radially through the sleeve. It also appears that these measurements are proposed as being a means of validating the assumed corrosion rates. The NRC staff does not understand how the proposed ultrasonic examination of the surface of the full-structural Type B sleeve and its welds will fully accomplish the desired purpose. It does not appear that the ultrasonic examination will accurately measure the corrosion rate of the pipe because ultrasonic testing techniques will not likely penetrate the interface between pipe and sleeve as would be required to me asure a corrosion rate of the pipe, especially for localized corrosion. Describe (a) how the proposed ultrasonic examination of the full-structural Type B sleeve will accurately 2identify the corrosion rate occurring at the site of the repair, especially if the corrosion mechanism is a localized corrosion mechanism such as MIC; and (b) why an alternate corrosion rate measurement technique is not required or proposed. Alternate techniques could include but are not limited to: use of corrosion coupons in the same piping system, volumetric examination of an area of the pipe which is adjacent to the repair which is undergoing the same form of degradation, or inline inspection of the pipe by robotic means.
- 3. The relief request is not clear regarding whether the proposed alternative repair or an ASME Code repair will be made if the pipe degradation is discovered during an outage. Discuss, for the buried pipe and above ground pipe, whether an ASME Code repair or the proposed alternative repair will be performed if degradation is identified during a scheduled refueling outage or an outage other than a scheduled refueling outage.
- 4. Page 4 of the relief request states that "-Exelon will remove full-structural Type B reinforcing sleeves and perform an ASME Code repair or replacement prior to the time that inservice monitoring indicates that structural integrity could be impaired based on measured degradation between monitoring activities-". The NRC staff notes that, especially for localized corrosion, leak-tight integrity and structural integrity may not be identical. Please provide additional information as to how the proposed alternative addresses leak-tight integrity of piping, especially piping carrying licensed material or environmentally sensitive material.
- 5. Localized corrosion is a significant issue in many raw water systems. Localized corrosion often occurs in these piping systems in many locations which are spaced fairly closely. It appears that examination of a somewhat larger area may be required when performing pre-installation and post-installation pipe inspection in order to identify whether additional corrosion is occurring in nearby locations. Justify why it is not necessary to examine the pipe for at least a fixed distance e.g., X pipe diameters or Y sleeve lengths in each direction from the point of degradation during the pre- and post-installation inspection.
- 6. In response to RAI Question 1(1) da ted June 24, 2013, the licensee stated that
"-Type B reinforcing sleeves could include new integral branch connections (weldolet or socket welded or threaded half-coupling) when required by design, such as for vent or fill conne ctions for pressure testing, or to replace a degraded section of piping containing a branch connection-"
The above statement appears to imply that a branch connection could be attached to a Type B sleeve as part of the repair. However, Code Case N-786 does not specify such a design or configuration. Justify why a branch connection could be attached to a Type B sleeve as part of the proposed repair.
Hearing Identifier: NRR_PMDA Email Number: 903 Mail Envelope Properties (Joel.Wiebe@nrc.gov20131106144900)
Subject:
Preliminary Additional RAI Questions Regarding Use of Code Case N-786 Sent Date: 11/6/2013 2:49:49 PM Received Date: 11/6/2013 2:49:00 PM From: Wiebe, Joel Created By: Joel.Wiebe@nrc.gov Recipients: "Tom Loomis" <thomas.loomis@exeloncorp.com>
Tracking Status: None Post Office: Files Size Date & Time MESSAGE 6707 11/6/2013 2:49:00 PM
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