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MONTHYEARML14254A1312014-09-0808 September 2014 NRR E-mail Capture - Peach Bottom & Quad Cities---RAI Questions for Relief Request I4R-55 TAC MF3799, Mf 3800, MF3801 and MF3802 Project stage: RAI RS-14-316, Response to RAI - Proposed Alternative to Utilize Code Case N-513-3, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1, at a Higher System Operating Pressure2014-10-29029 October 2014 Response to RAI - Proposed Alternative to Utilize Code Case N-513-3, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1, at a Higher System Operating Pressure Project stage: Response to RAI RS-15-068, Response to RAI - Proposed Alternative to Utilize Code Case N-513-3, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Divsion 1,.2015-02-0505 February 2015 Response to RAI - Proposed Alternative to Utilize Code Case N-513-3, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Divsion 1,. Project stage: Response to RAI ML15043A4962015-03-19019 March 2015 Relief from the Requirements of the ASME Code Project stage: Approval 2014-09-08
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Category:E-Mail
MONTHYEARML24002A7132023-12-29029 December 2023 Supplement - Peach Bottom Security Rule Exemption Request ISFSI Docket No. Reference (EPID L-2023-LLE-0032) (Updated) (Email) ML23352A3242023-12-18018 December 2023 Acceptance of Requested Licensing Action Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations (EPID L- 2023-LLN-0004) ML23349A0362023-12-14014 December 2023 NRR E-mail Capture - Draft Request for Additional Information Re Quad Cities Emergency Amendment Related to Unit 1 Diesel Generator Inoperability ML23331A9112023-11-22022 November 2023 Supplement - Peach Bottom Security Rule Exemption Request ISFSI Docket No. Reference ML23338A1192023-11-21021 November 2023 NRR E-mail Capture - Draft Request for Additional Information Quad Cities Relief Request I5R-26 ML23304A0182023-10-30030 October 2023 NRR E-mail Capture - Final RCI - Constellation Energy Generation, LLC - Peach Bottom 2 & 3 - Exemption from Security Rule (L-2023-LLE-0032) 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 ML23237B3972023-08-24024 August 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Alternative Request to Use Updated BWRVIP Guidelines 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 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 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 ML22325A0052022-11-18018 November 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-273-A, Revision 2 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 ML22118A3312022-04-28028 April 2022 NRR E-mail Capture - Peach Bottom - Formal RAI for Proposed Alternative I5R-14, Revision 1 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 ML22024A1852022-01-24024 January 2022 Acceptance for Review of Relief Request Associated with Reactor Pressure Vessel N-16A Nozzle Repair 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 ML21342A3402021-12-0808 December 2021 Acceptance Review: License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times ML21342A3842021-12-0808 December 2021 NRR E-mail Capture - Request for Additional Information: Quad Cities 1 & 2 License Amendment Request Transition to GNF3 Fuel 2023-09-22
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NRR-PMDAPEm Resource From: Wiebe, Joel Sent: Monday, September 08, 2014 1:59 PM To: Tom Loomis
Subject:
Peach bottom & Quad Cities---RAI questions for Relief Request I4R-55 TAC MF3799, MF 3800, MF3801 and MF3802
- Tom, By letter dated March 28, 2014 (Agencywide Documents and Access Management System (ADAMS)
Accession No. ML14090A140), Exelon Generation Company, LLC (the licensee) requested relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, at the Peach Bottom Atomic Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2. As documented in Relief Requests I4R-55 and I5R-12, the licensee proposed to use modified ASME Code Case N-513-3 for the repair of high pressure service water (HPSW) system piping at Peach Bottom and residual heat removal service water (RHRSW) system piping at Quad Cities. To complete its review, the Nuclear Regulatory Commission (NRC) requests the following additional information:
- 1. In the relief request, the licensee referenced several precedents. It does not appear to the NRC staff that the precedents provided address relief for a generic (addressing a future leak) long term (up to 18-24 months),
higher pressure (greater than 275 psi), and raw water application. Please discuss the applicability of the precedents to Relief Request I4R-55.
- 2. The concepts of what constitute moderate energy piping and the limitation of ASME Code Case N-513 to moderate energy systems is well established. The NRC staff believes that authorizing the proposed alternative may create confusion regarding these issues. It is not clear to the NRC that the justification provided for the proposed alternative is sufficient given the potential confusion which may be created. Please provide comments regarding this issue.
- 3. The NRC staff believes that authorization of the proposed alternative may establish precedent for the use of Code Case N-513 at pressures above the current limits for moderate energy piping at plants other than Peach Bottom and Quad Cities. The NRC staff believes that establishing such a precedent may have far reaching consequences, some of which may be adverse. Any information which is known by the licensee regarding the extent to which other plants and/or licensees may have piping systems which are similar to those for which relief is requested would be useful in the NRCs decision making process. The NRC is aware that the licensee may have no knowledge of such systems and is not asking the licensee to acquire such information. To the extent which information regarding similar piping systems at other locations is available, please provide a discussion of the extent to which similar piping systems exist within the industry.
- 4. The licensee submitted both relief requests under Title 10, Code of Federal Regulations, Part 50 (10 CFR),
55a(a)(3)(i) which specifies that the proposed alternative provides an acceptable level of quality and safety.
This means that the proposed alterative would provide an equivalent level of quality and safety as that of an ASME Code repair. The NRC staff believes that the use of the proposed alternative, i.e., continued operation with through wall leakage provides a lower level of quality and safety when compared with an ASME Code compliant repair. The NRC staff believes that requesting the use of the proposed alternative under 10 CFR 50.55a(a)(3)(ii) may be more appropriate. Please justify it is appropriate to make this request under 10 CFR 50.55a(a)(3)(i) rather than 10 CFR 50.55a(a)(3)(ii).
- 5. The relief request states that the operating pressure is less than or equal to 375 psi for the HPSW and RHRSW system piping at Peach Bottom and Quad Cities, respectively. (a) Discuss the design pressure, design temperature and the maximum operating temperature of the HPSW and RHRSW systems. (b) Discuss any segment of the HPSW and RHRSW piping that is inaccessibility for visual and ultrasonic examinations (e.g., buried underground, covered with insulation, and interferences). In this discussion include how periodic 1
monitoring of the leakage of any inaccessible segment(s) can be conducted as required by Code Case N-513-
- 3. (c) Provide all pipe diameters and wall thickness of the HPSW and RHRSW to which the proposed alternative will be applicable.
- 6. The relief requests stated that both HPSW and RHRSW systems are used only during testing and plant shutdown. It appears that both systems will not be used during plant operation. The NRC staff understands that when both systems are needed to be functional during plant shutdown, performing an ASME Code repair would be a hardship. (a) However, if a leak occurs during the normal plant operation while the HPSW and RHRSW systems are not being used, discuss why the proposed alternative is needed and why an ASME Code repair cannot be performed. (b) Discuss whether these two piping systems are needed to be operable during an emergency condition. If yes, justify why the proposed alternative is permitted to be used during the emergency condition.
- 7. The Summary section of the relief requests states that the allowable leakage of the HPSW or RHRSW piping is 100 gallons per minute (gpm). This is a significant leak rate. The NRC staff notes that NRC Branch Technical Position 3-3, Revision 3, Protection Against Postulated Piping Failures in Fluid Systems Outside Containment, and Branch Technical Position 3-4, Revision 2, Postulated Rupture Locations in Fluid System Piping Inside and Outside Containment, of Standard Review Plan, NUREG-0800, provide guidance on flooding analysis. (a) Discuss whether a 100 gpm leak rate is within the design basis flooding analysis associated with the rooms, buildings, and compartments that HPSW and RHRSW piping are located in light of a significant allowable leak rate of 100 gpm. (b) Discuss whether the pumps of these two systems have the capacity to make up the mass flow to compensate for a 100 gpm leak rate to maintain the intended function of both HPSW and RHRSW systems. (c) If the leak rate exceeds 100 gpm, discuss corrective actions. (d) The NRC staff believes that an allowable leak rate of 100 gpm is too high of a limit. Provide either a justification for such a high allowable leak rate or lower the allowable leak rate.
- 8. Page 6 of Attachment 2 discussed the average cover thickness calculated for 275 psi and 375 psi pressure. The average cover thickness and average diameter equations as specified in Code Case N-513-3 are to demonstrate acceptability under the branch reinforcement requirements. Demonstrate that a leaking pipe with a leak rate of 100 gpm at a pressure of 375 psi will satisfy the branch reinforcement requirements of Code Case N-513-3.
- 9. Page 6 of Attachment 2 discusses the result of jet thrust force calculations between a pressure of 275 psi and 375 psi. Demonstrate that the jet thrust force calculated at a pressure of 375 psi will not be detrimental to the adjacent safety-related systems, structures and components.
- 10. Page 7 of Attachment 2 states that a pipe opening (hole) with a diameter of 0.5 inches will result in a leak rate of 90 gpm. Provide the detailed calculation to show how 90 gpm is derived from a 0.5-inch diameter hole.
2
Hearing Identifier: NRR_PMDA Email Number: 1563 Mail Envelope Properties (1A97AE0578A58B46BC77AA0B5DBD72020124996494A2)
Subject:
Peach bottom & Quad Cities---RAI questions for Relief Request I4R-55 TAC MF3799, MF 3800, MF3801 and MF3802 Sent Date: 9/8/2014 1:59:04 PM Received Date: 9/8/2014 1:59:00 PM From: Wiebe, Joel Created By: Joel.Wiebe@nrc.gov Recipients:
"Tom Loomis" <thomas.loomis@exeloncorp.com>
Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 7194 9/8/2014 1:59:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: