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Category:Letter type:RS
MONTHYEARRS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023 Supplemental Information Related to Request for Partial Site Release RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023 Application to Adopt TSTF-332, ECCS Response Time Testing RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-121, Notice of Intent to Pursue Subsequent License Renewal Applications2022-11-0909 November 2022 Notice of Intent to Pursue Subsequent License Renewal Applications RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-107, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2022-09-29029 September 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-089, Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-07-25025 July 2022 Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock RS-22-061, Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves RS-22-060, Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling RS-22-068, Constellation Radiological Emergency Plan Addendum Revision2022-05-19019 May 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-055, Submittal of Preliminary Decommissioning Cost Estimate and Spent Fuel Management Plan2022-04-18018 April 2022 Submittal of Preliminary Decommissioning Cost Estimate and Spent Fuel Management Plan RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-020, Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-04-0707 April 2022 Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021 Proposed Changes to Decommissioning Trust Agreements and Master Terms RS-21-102, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-09-29029 September 2021 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021 Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes RS-21-087, Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-08-31031 August 2021 Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021 Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel RS-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021 Application to Adopt TSTF-273, Safety Function Determination Program Clarifications RS-21-070, Proposed Alternative to Utilize Code Case N-8932021-06-30030 June 2021 Proposed Alternative to Utilize Code Case N-893 RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-069, Third Inservice Inspection Interval Relief Request I3R-182021-06-28028 June 2021 Third Inservice Inspection Interval Relief Request I3R-18 RS-21-054, Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations2021-04-29029 April 2021 Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments RS-21-037, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 22021-03-23023 March 2021 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 2 RS-21-028, Fitness for Duty Performance Data Reports - Annual 20202021-02-26026 February 2021 Fitness for Duty Performance Data Reports - Annual 2020 RS-21-032, Amended Decommissioning Trust Agreements2021-02-25025 February 2021 Amended Decommissioning Trust Agreements RS-21-014, License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency2021-02-24024 February 2021 License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency RS-21-030, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2021-02-24024 February 2021 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-21-005, Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-01-20020 January 2021 Request for License Amendment to Revise Degraded Voltage Relay Allowable Values RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping 2023-09-07
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Exellon Exelon Nuclear 4300 Winfield Road www.exeloncorp .co m Nuclear Warrenville, IL 60555 10 CFR 50.55a RS-09-058 May 5, 2009 U . S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No . 50-461
Subject:
Request for Proposed Alternative to 10 CFR 50.55a Post Weld Heat Treatment Requirements for Piping Replacements (Relief Request No. 1203)
In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (a)(3)(i), Exelon Generation Company, LLC (EGC), hereby requests approval to use an alternative to the requirements of the 1989 Edition of American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code Section XI, Article IWA-4000, for repair and replacement activities at Clinton Power Station (CPS), Unit 1 .
Relief Request Number 1203 proposes to use the requirements of Table NB-4622.7(b)-1, "Exemptions to Mandatory PWHT," of the 2006 Addenda to ASME Section III, Subsection NB for the repair/replacement of certain piping . That piping will be installed in the twelfth refueling outage (i.e., C1 R12) scheduled to begin January 11, 2010. The proposed alternative provides an acceptable level of quality and safety in accordance with 10 CFR 50.55a(a)(3)(i). Since 10 CFR 50.55a references only up to the 2004 ASME Code, use of the 2006 Addenda requires NRC approval. The basis for this alternative is discussed in the attached relief request.
We request your review and approval by January 11, 2010 to support refueling outage C1 R12 .
There are no regulatory commitments contained in this letter. If you have any questions concerning this letter, please contact Mr. Timothy A. Byam at (630) 657-2804 .
Attachment - 10 CFR 50 .55a Request Number 1203
ATTACHMENT 10 CFR 50.55a Request Regarding Alternative Provides Acceptable Level of Quality and Safety (10 CFR 50.55a(a)(3)(i))
Page 1 of 3 10 CFR 50.55a Request Number 1203 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)
Alternative Provides Acceptable Level of Quality or Safety
- 1. ASME Code Component(s) Affected Code Class: 1 Component Numbers: Reactor Water Cleanup (RT) System Piping Line Numbers 1 RT01 AA-4", 1 RT01 AB-4", 1 RT01 EC-4", 1 RT01 ED-4"
- 2. App licable Code Edition and Addenda Clinton Power Station (CPS), Unit 1, is currently in the second 10-year Inservice Inspection Program interval and complies with the 1989 Edition of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.
3. Applicable Code Requirement
Repair and replacement activities are governed by Articles IWA-4000, IWB-4000, IWA-7000 and IWB-7000 of Section XI of the ASME Boiler and Pressure Vessel Code. These Articles make reference to the code of construction, which for the subject piping is ASME Section III, Subsection NB, 1974 Edition through Summer 1974 Addenda. The code of construction required CPS to perform post-weld heat treatment (PWHT) of the subject piping welds due to the piping outside diameter being 4.5 inches . These articles also allow using later Editions and Addenda of ASME Section III, either in their entirety or portions thereof, provided they have been approved by the regulatory authorities. The version of the Section III ASME Boiler and Pressure Vessel Code incorporated by reference in 10 CFR 50.55a is the 2004 Edition .
CPS is planning to replace portions of the RT system piping with P-Number 5A (P5A) material . ASME Section III, Subsection NB, Article NB-4000, Table NB-4622.7(b)-1, "Exemptions to Mandatory PWHT," provides exemption criteria from mandatory post weld heat treatment (PWHT). Up to and including the 2004 Edition of the ASME Section III, Subsection NB, Table NB-4622.7(b)-1, P5A material with outside diameter (OD) of 4 inches or less is exempt from PWHT. The current installation at CPS consists of 4-inch nominal pipe size (NPS) piping with an OD of 4.5 inches, which requires PWHT after welding .
ATTACHMENT 10 CFR 50 .55a Request Regarding Alternative Provides Acceptable Level of Quality and Safety (10 CFR 50.55a(a)(3)(i))
Page 2 of 3
- 4. Reason for Req uest During the next refueling outage (i.e ., C1 R12), CPS intends to replace a portion of the RT system piping with P5A material versus the originally installed P1 material .
A literal interpretation of Table NB-4622.7(b)-1, "Exemptions to Mandatory PWHT,"
of up to and including the 2004 Edition of the ASME Boiler and Pressure Vessel Code Section III, Subsection NB, would preclude NPS 4-inch piping with an outside diameter of 4.5 inches from being exempt from PWHT. However, Table NB-4622 .7(b)-1 of the 2006 Addenda of ASME Section III, Subsection NB, was revised to clarify and correct the inconsistencies between older versions of the piping codes. Specifically, this table was revised to correct the references to piping with a nominal OD of 4 inches . The table was revised to include NPS 4-inch piping with a nominal OD of 4.5 inches .
The piping within the scope of this request is being replaced in C1 R12. The welds that will be made in support of the piping replacement meet the exemption requirements of the 2006 Addenda of the ASME Code Section III, Subsection NB, Table NB-4622.7(b)-1 . Due to the location of the piping in the CPS Drywell and the number of field welds that are required due to space limitations, there would be a significant radiological dose savings (i.e ., approximately 2 Rem) by not having to set up and remove equipment for post weld heat treatment of the affected welds .
- 5. Proposed Alternative and Basis for Use CPS proposes to use ASME Section III, Subsection NB, Table NB-4622.7(b)-1, as provided in the 2006 Addenda of the ASME Code, to utilize an alternative to the requirement for a PWHT of the replacement piping . This Table was revised in the 2006 Addenda to clarify the referenced sizes for pipes and tube OD's. In particular, this table was revised to correct the references to piping with a nominal OD of 4 inches . The table was revised to include NPS 4-inch piping with a nominal OD of 4.5 inches, as long as the piping wall thickness did not exceed 0.5 inches and carbon content did not exceed 0.15%. This revision was documented in a change to the 2006 Addenda of the ASME Section III, Subsection NB Code, under record number BC-05-489. This change recognizes that piping normally produced by piping manufacturers is based on nominal pipe sizes.
The components within the scope of this relief request are the circumferential butt welds associated with replacement piping on the reactor water cleanup system piping system . The affected lines are NIPS 4-inch (4.5 inch outside diameter),
schedule 120 piping (0.437 inch wall thickness) . The material of the piping is SA-335, Grade P22, with a maximum chromium content of 2.6%, and a maximum carbon content of 0 .15%. The material of the fittings is SA-234, Grade WP22 Class 1, with a maximum chromium content of 2.6% and a maximum carbon content of 0 .15% . EGC plans on replacing a valve as part of the piping
ATTACHMENT 10 CFR 50.55a Request Regarding Alternative Provides Acceptable Level of Quality and Safety (10 CFR 50.55a(a)(3)(i))
Page 3 of 3 replacement covered by this relief request. The replacement valve has not yet been manufactured, however, the valve body material has been specified as SA-217, Grade WC9, with a maximum chromium content of 2.75% and an allowable carbon content of 0.18%. While the specified allowable carbon content is above the 0.15% maximum for carbon allowed by Table NB-4622.7(b)-1, the actual valve body carbon content may actually be less than 0.15% once the valve body is actually poured. All of the above materials, except for the valve body material, meet the requirements of ASME Section III, Subsection NB for Table NB-4622 .7(b)-1 as revised by the 2006 Addenda. Once the new valve has been manufactured, if the valve vendor certified material test records show that the carbon content of the valves is less than or equal to 0.15%, then the valve to pipe welds would also be included in the exemption .
- 6. Duration of Proposed Alternative CPS proposes use of this alternative during the second 10-year Inservice Inspection Program interval or until such time as the NRC incorporates the use of the 2006 Addenda of the ASME Section XI, Subsection NB Code by reference.