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| | issue date = 01/16/2015 | | | issue date = 01/16/2015 |
| | title = Draft RAIs License Amendment Request for Change to TS 3.4.10 P/T Limits (TAC Nos. MF4597 and MF45980) | | | title = Draft RAIs License Amendment Request for Change to TS 3.4.10 P/T Limits (TAC Nos. MF4597 and MF45980) |
| | author name = Whited J A | | | author name = Whited J |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
| | addressee name = | | | addressee name = |
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| | document type = Request for Additional Information (RAI) | | | document type = Request for Additional Information (RAI) |
| | page count = 2 | | | page count = 2 |
| | project = TAC:MF4598, TAC:MF4597 | | | project = TAC:MF4597, TAC:MF4598 |
| | stage = RAI | | | stage = Draft RAI |
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| {{#Wiki_filter: DRAFT DRAFT REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION LICENSE AMENDMENT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATION 3.4.10 PPL SUSQUEHANNA, LLC SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 DOCKET NOS. 50-387 AND 50-388 By letter dated August 11, 2014,1 PPL Susquehanna, LLC (PPL, the licensee) submitted a license amendment request to revise Technical Specification 3.4.10, "RCS Pressure and Temperature (P/T) Limits," for the Susquehanna Steam Electric Station (SSES), Units 1 and 2. | | {{#Wiki_filter:DRAFT REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION LICENSE AMENDMENT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATION 3.4.10 PPL SUSQUEHANNA, LLC SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 DOCKET NOS. 50-387 AND 50-388 By letter dated August 11, 2014,1 PPL Susquehanna, LLC (PPL, the licensee) submitted a license amendment request to revise Technical Specification 3.4.10, RCS Pressure and Temperature (P/T) Limits, for the Susquehanna Steam Electric Station (SSES), Units 1 and 2. |
| Specifically, the licensee proposed to revise the P/T Limits curves to extend them into the vacuum region to address vacuum fill operations. To complete its review, the Nuclear Regulatory Commission (NRC) staff requests a response to the questions below. | | Specifically, the licensee proposed to revise the P/T Limits curves to extend them into the vacuum region to address vacuum fill operations. To complete its review, the Nuclear Regulatory Commission (NRC) staff requests a response to the questions below. |
| RAI 1 BACKGROUND Title 10 of the Code of Federal Regulations Part 50, Appendix G, "Fracture Toughness Requirements," requires that P/T limits be developed to bound all ferritic materials in the reactor vessel (RV). Further, Sections I and IV.A of 10 CFR Part 50, Appendix G specify that all ferritic reactor coolant pressure boundary (RCPB) components outside of the RV must meet the applicable requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section III, "Rules for Construction of Nuclear Facility Components." ISSUE As clarified in Regulatory Information Summary (RIS) 2014-11,2 "Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components," P/T limit calculations for ferritic RV components other than those materials with the highest reference temperature, may define curves that are more limiting than those calculated for the RV beltline shell materials because the consideration of stress levels from structural discontinuities (such as nozzles) may produce a lower allowable pressure.
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| REQUEST Describe how the P/T limit curves for SSES Units 1 and 2 consider all ferritic pressure boundary components of the reactor vessel that are predicted to experience a neutron fluence exposure greater than 1x1017 n/cm2 (E > 1 MeV) at the end of the licensed operating period. 1 Agencywide Documents Access and Management System (ADAMS) Accession Number ML14223A780. 2 ADAMS Accession No. ML14149A165. | | ===RAI 1=== |
| DRAFT If the current P/T limit curves do not consider all ferritic pressure boundary components of the reactor vessel that are predicted to experience a neutron fluence exposure greater than 1x1017 n/cm2 (E > 1 MeV) at the end of the licensed operating period, provide appropriately revised P/T limit curves to the NRC staff for review. | | BACKGROUND Title 10 of the Code of Federal Regulations Part 50, Appendix G, Fracture Toughness Requirements, requires that P/T limits be developed to bound all ferritic materials in the reactor vessel (RV). Further, Sections I and IV.A of 10 CFR Part 50, Appendix G specify that all ferritic reactor coolant pressure boundary (RCPB) components outside of the RV must meet the applicable requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section III, Rules for Construction of Nuclear Facility Components. |
| RAI 2 BACKGROUND 10 CFR 50.36(b) states, in part, that: "The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to § 50.34."
| | ISSUE As clarified in Regulatory Information Summary (RIS) 2014-11,2 Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components, P/T limit calculations for ferritic RV components other than those materials with the highest reference temperature, may define curves that are more limiting than those calculated for the RV beltline shell materials because the consideration of stress levels from structural discontinuities (such as nozzles) may produce a lower allowable pressure. |
| ISSUE Page 3 of 7 of the licensee's application states, in part, that:
| | REQUEST Describe how the P/T limit curves for SSES Units 1 and 2 consider all ferritic pressure boundary components of the reactor vessel that are predicted to experience a neutron fluence exposure greater than 1x1017 n/cm2 (E > 1 MeV) at the end of the licensed operating period. |
| The absolute maximum vacuum is assumed to be no greater than 15 psig Whereas the licensee's proposed Technical Specifications (TS) change on TS Figures 3.4.10-1 thru 3 shows P/T limit curves are extended to -100 psig. Any TS change should be consistent with technical justification.
| | 1 Agencywide Documents Access and Management System (ADAMS) Accession Number ML14223A780. |
| | 2 ADAMS Accession No. ML14149A165. |
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| REQUEST Please provide a justification for an extension of the P/T curves to -100 psig, or, TS Figures 3.4.10-1 through 3.4.10-3 should be revised to reflect the maximum vacuum of -15 psig as described in the submittal (i.e., adjusting the axis to end at -15 psig, terminating the P/T curves at -15 psig on the current scale, etc.). | | If the current P/T limit curves do not consider all ferritic pressure boundary components of the reactor vessel that are predicted to experience a neutron fluence exposure greater than 1x1017 n/cm2 (E > 1 MeV) at the end of the licensed operating period, provide appropriately revised P/T limit curves to the NRC staff for review. |
| }} | | |
| | ===RAI 2=== |
| | BACKGROUND 10 CFR 50.36(b) states, in part, that: "The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to § 50.34." |
| | ISSUE Page 3 of 7 of the licensee's application states, in part, that: |
| | The absolute maximum vacuum is assumed to be no greater than 15 psig Whereas the licensee's proposed Technical Specifications (TS) change on TS Figures 3.4.10-1 thru 3 shows P/T limit curves are extended to -100 psig. Any TS change should be consistent with technical justification. |
| | REQUEST Please provide a justification for an extension of the P/T curves to -100 psig, or, TS Figures 3.4.10-1 through 3.4.10-3 should be revised to reflect the maximum vacuum of -15 psig as described in the submittal (i.e., adjusting the axis to end at -15 psig, terminating the P/T curves at -15 psig on the current scale, etc.). |
| | DRAFT}} |
Letter Sequence Draft RAI |
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MONTHYEARPLA-7181, Submittal of Request for Amendment to the Technical Specification 3.4.10, RCS Pressure and Temperature (Pit) Limits.2014-08-11011 August 2014 Submittal of Request for Amendment to the Technical Specification 3.4.10, RCS Pressure and Temperature (Pit) Limits. Project stage: Request ML15016A2742015-01-16016 January 2015 Draft RAIs License Amendment Request for Change to TS 3.4.10 P/T Limits (TAC Nos. MF4597 and MF45980) Project stage: Draft RAI ML15016A2722015-01-16016 January 2015 E-mail from J. Whited to D. Filchner Draft RAIs License Amendment Request for Change to TS 3.4.10 P/T Limits (TAC Nos. MF4597 and MF45980) Project stage: Draft RAI ML15008A4702015-01-30030 January 2015 Request for Additional Information Request to Revise Technical Specification 3.4.10, RCS Pressure and Temperature (P/T) Limits. Project stage: RAI PLA-7299, Response to Request for Additional Information on Technical Specification Changes to RCS Pressure and Temperature (P/T) Limits2015-04-0606 April 2015 Response to Request for Additional Information on Technical Specification Changes to RCS Pressure and Temperature (P/T) Limits Project stage: Response to RAI PLA-7360, Supplemental Information to License Amendment Request for Changes in RCS Pressure and Temperature (P/T) Limits2015-07-16016 July 2015 Supplemental Information to License Amendment Request for Changes in RCS Pressure and Temperature (P/T) Limits Project stage: Supplement ML15202A2292015-07-23023 July 2015 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing (Enclosure) Project stage: Request ML15202A2252015-07-23023 July 2015 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing Project stage: Other ML15243A1402015-09-30030 September 2015 Issuance of Amendments Revisions to Technical Specification 3.4.10, Reactor Coolant System Pressure and Temperature (P/T) Limits Project stage: Approval 2015-04-06
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Category:Request for Additional Information (RAI)
MONTHYEARML24150A3362024-05-29029 May 2024 Request for Confirmation of Information Relief Request 1RR06 (Proposed Alternative) Susquehanna Nuclear, LLC Susquehanna Steam Electric Station (Susquehanna), Unit 1 Docket No. 50-387 IR 05000387/20244042024-05-0707 May 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000387/2024404 and 05000388/2024404 ML24102A1252024-04-10010 April 2024 Request for Additional Information for Susquehanna, Unit 1 Alternative Request 4RR-11 ML23334A1502023-11-30030 November 2023 NRC Request for Additional Information Re. Susquehanna Relief Request RR-02 ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information ML23013A2082023-01-13013 January 2023 Request for Additional Information ML22146A1022022-05-26026 May 2022 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000387/2022404 and 05000388/2022404 ML22146A0742022-05-25025 May 2022 NRR E-mail Capture - NRC Request for Additional Information - Susquehanna License Amendment Request ML22111A3132022-04-21021 April 2022 NRR E-mail Capture - NRC Request for Additional Information - Susquehanna License Amendment Request ML22041A1562022-02-10010 February 2022 Information Request for a Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000387/2022013 and 05000388/2022013 ML21316A1242021-11-18018 November 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Emergency Core Cooling Technical Specifications ML20056E4392020-02-21021 February 2020 Ti 2515/194 Inspection Documentation Request ML20010D2012020-01-0909 January 2020 Request for Additional Information Related to Request to Allow Application of Framatome Analysis Methodologies Necessary to Support a Planned Transition to Atrium 11 Fuel Under Maximum ML19319A0092019-11-14014 November 2019 NRR E-mail Capture - Draft RAI for SSES Units 1 and 2 LAR to Replace ESW Piping ML19319B1922019-11-14014 November 2019 NRR E-mail Capture - RAI for Susquehanna, 1 and 2 License Amendment Request - Replace the Emergency Service Water System and Residual Heat Removal Service Water System ML19128A0232019-05-0707 May 2019 Request for Additional Information: Susquehanna Steam Electric Station, Units 1 and 2 License Amendment Request for ESW Piping Replacement ML18352B1832018-12-13013 December 2018 Enclosurequest for Additional Information (Letter to K. Cimorelli Request for Additional Information Regarding Susquehanna Nuclear, Llc'S Decommissioning Funding Plan Update for Susquehanna Steam Electric Station Independent Spent Fuel Stor ML17180A2002017-07-0707 July 2017 Request for Additional Information Regarding License Amendment Request to Revise Diesel Generator Surveillance Requirements with New Steady State Voltage and Frequency Limits ML17059D2142017-03-0606 March 2017 Susquehanna Steam Electric Station - Supplemental Information Needed for Acceptance of Requested Licensing Action Re: License Amendment Request to Revise Diesel Generator Surveillance Requirements with New Steady State Voltage Frequency Limits ML16251A0652016-09-0909 September 2016 Susquehanna Steam Electric Station, Unit 2 - RAI Regarding Temporary Change of Unit 2, Technical Specifications 3.7.1 & 3.8.7 to Allow Replacement of Unit 1, 480 Volt Engineered Safeguard System Load Center Transformers(CAC No. MF7298) ML16245A2052016-09-0101 September 2016 Draft Request for Additional Information Replacement of Load Center Transformers ML16243A0952016-08-30030 August 2016 Draft Request for Additional Information Application for Approval of Indirect Transfer of Control of Licenses ML16060A2302016-03-24024 March 2016 Acceptance of Requested Licensing Action License Amendment Request for Temporary Change of Unit 2 Technical Specifications 3.71 and 3.87 to Allow Replacement of Unit 1 480V Ess Load Center Transformers ML15316A5632015-11-13013 November 2015 Request for Additional Information Regarding Proposed Relief Requests for the Third 10-Year Inservice Inspection Interval(Cac Nos. MF6302 Through MF6307) ML15292A1782015-10-15015 October 2015 TSTF-425 LAR Draft 3rd RAIs ML15230A0802015-08-26026 August 2015 Request for Additional Information Regarding License Amendment Request to Adopt NEI 99-01, Revision 6, EAL Scheme Change ML15209A9742015-08-24024 August 2015 Request for Additional Information License Amendment Request to Adopt Technical Specifications Task Force Traveler (TSTF)-425 ML15230A0462015-08-17017 August 2015 Draft RAIs SSES EAL Scheme Change LAR in Accordance with NEI 99-01 Rev 6 ML15229A2092015-08-17017 August 2015 SSES Draft Request for Additional Information Licensee Request to Adopt TSTF-425 ML15229A2002015-08-17017 August 2015 E-mail from J. Whited to J. Jennings SSES Draft TSTF-425 RAIs ML15183A3502015-07-0202 July 2015 SSES Relief Requests 3RR-19, 3RR-20, and 3RR-21 Draft Identified Information Insufficiencies (TAC Nos. MF6302 Through MF6307) ML15103A3962015-05-22022 May 2015 Request for Additional Information License Amendment Request to Adopt Technical Specifications Task Force Traveler (TSTF)-425 (TAC Nos. MF5151 and MF5152) ML15128A5092015-05-0808 May 2015 E-mail from J. Whited to D. Filchner SSES Draft Request for Additional Information LAR for Implementation of TSTF-425 ML15128A5162015-05-0808 May 2015 SSES Draft Request for Additional Information LAR for Implementation of TSTF-425 ML15008A4702015-01-30030 January 2015 Request for Additional Information Request to Revise Technical Specification 3.4.10, RCS Pressure and Temperature (P/T) Limits. ML15016A2742015-01-16016 January 2015 Draft RAIs License Amendment Request for Change to TS 3.4.10 P/T Limits (TAC Nos. MF4597 and MF45980) ML15016A2722015-01-16016 January 2015 E-mail from J. Whited to D. Filchner Draft RAIs License Amendment Request for Change to TS 3.4.10 P/T Limits (TAC Nos. MF4597 and MF45980) ML14343A9842015-01-0808 January 2015 Request for Additional Information Relief Request 4RR-01 ML14345A2412014-12-16016 December 2014 Request for Additional Information Request for Order Approving Indirect Transfer of Control and Conforming License Amendments ML14346A4022014-12-12012 December 2014 Draft RAIs Relief Request 4RR-01 ML14346A4012014-12-12012 December 2014 E-mail from J. Whited to D. Filchner Susquehanna Steam Electric Station Draft RAIs Relief Request 4RR-01 ML14346A1022014-12-12012 December 2014 Draft License Transfer Revised 2nd RAIs ML14346A1002014-12-12012 December 2014 E-mail from J. Whited to R. Sgarro Susquehanna Steam Electric Station Draft License Transfer Revised 2nd RAIs ML14342A8132014-12-0808 December 2014 SSES Units 1 and 2 Draft RAIs Application for Approval of Indirect Transfer of Control of Licenses ML14342A8082014-12-0808 December 2014 E-mail from J. Whited to R. Sgarro (PPL) SSES Units 1 and 2 Draft RAIs Application for Approval of Indirect Transfer of Control of Licenses ML14233A2772014-08-27027 August 2014 Request for Additional Information License Amendment Request to Change the Low Pressure Safety Limit ML14233A3392014-08-21021 August 2014 Draft RAIs for Susquehanna Steam Electric Station Units 1 and 2 License Amendment Request for Changes to the Low Pressure Safety Limits ML13298A7582014-03-0707 March 2014 Request for Additional Information Regarding Request for Changes to Technical Specification Surveillance Requirements to Increase Diesel Generator Minimum Steady State Voltage (TAC ME9607 and ME960) ML13298A7812014-03-0707 March 2014 Request for Additional Information Regarding Request for Changes to Technical Specification Surveillance Requirement 3.8.1.19 to Increase Diesel Generator Minimum Steady State Frequency (TACs ME9609. ML14013A1502014-01-31031 January 2014 Request for Additional Information Regarding Relief Requests for the Fourth 10-Year Inservice Testing Interval 2024-05-07
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DRAFT REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION LICENSE AMENDMENT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATION 3.4.10 PPL SUSQUEHANNA, LLC SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 DOCKET NOS. 50-387 AND 50-388 By letter dated August 11, 2014,1 PPL Susquehanna, LLC (PPL, the licensee) submitted a license amendment request to revise Technical Specification 3.4.10, RCS Pressure and Temperature (P/T) Limits, for the Susquehanna Steam Electric Station (SSES), Units 1 and 2.
Specifically, the licensee proposed to revise the P/T Limits curves to extend them into the vacuum region to address vacuum fill operations. To complete its review, the Nuclear Regulatory Commission (NRC) staff requests a response to the questions below.
RAI 1
BACKGROUND Title 10 of the Code of Federal Regulations Part 50, Appendix G, Fracture Toughness Requirements, requires that P/T limits be developed to bound all ferritic materials in the reactor vessel (RV). Further, Sections I and IV.A of 10 CFR Part 50, Appendix G specify that all ferritic reactor coolant pressure boundary (RCPB) components outside of the RV must meet the applicable requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section III, Rules for Construction of Nuclear Facility Components.
ISSUE As clarified in Regulatory Information Summary (RIS) 2014-11,2 Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components, P/T limit calculations for ferritic RV components other than those materials with the highest reference temperature, may define curves that are more limiting than those calculated for the RV beltline shell materials because the consideration of stress levels from structural discontinuities (such as nozzles) may produce a lower allowable pressure.
REQUEST Describe how the P/T limit curves for SSES Units 1 and 2 consider all ferritic pressure boundary components of the reactor vessel that are predicted to experience a neutron fluence exposure greater than 1x1017 n/cm2 (E > 1 MeV) at the end of the licensed operating period.
1 Agencywide Documents Access and Management System (ADAMS) Accession Number ML14223A780.
2 ADAMS Accession No. ML14149A165.
DRAFT
If the current P/T limit curves do not consider all ferritic pressure boundary components of the reactor vessel that are predicted to experience a neutron fluence exposure greater than 1x1017 n/cm2 (E > 1 MeV) at the end of the licensed operating period, provide appropriately revised P/T limit curves to the NRC staff for review.
RAI 2
BACKGROUND 10 CFR 50.36(b) states, in part, that: "The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to § 50.34."
ISSUE Page 3 of 7 of the licensee's application states, in part, that:
The absolute maximum vacuum is assumed to be no greater than 15 psig Whereas the licensee's proposed Technical Specifications (TS) change on TS Figures 3.4.10-1 thru 3 shows P/T limit curves are extended to -100 psig. Any TS change should be consistent with technical justification.
REQUEST Please provide a justification for an extension of the P/T curves to -100 psig, or, TS Figures 3.4.10-1 through 3.4.10-3 should be revised to reflect the maximum vacuum of -15 psig as described in the submittal (i.e., adjusting the axis to end at -15 psig, terminating the P/T curves at -15 psig on the current scale, etc.).
DRAFT