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| | number = ML14202A518 | | | number = ML14202A518 |
| | issue date = 07/21/2014 | | | issue date = 07/21/2014 |
| | title = Limerick Generating Station, Units 1 and 2, Draft Request for Additional Information (Tac Nos. MF3085 and MF3086) | | | title = Draft Request for Additional Information (Tac Nos. MF3085 and MF3086) |
| | author name = Ennis R B | | | author name = Ennis R |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
| | addressee name = Schaaf R G | | | addressee name = Schaaf R |
| | addressee affiliation = NRC/NRR/DORL/LPLI-2 | | | addressee affiliation = NRC/NRR/DORL/LPLI-2 |
| | docket = 05000352, 05000353 | | | docket = 05000352, 05000353 |
| | license number = NPF-039, NPF-085 | | | license number = NPF-039, NPF-085 |
| | contact person = Ennis R B | | | contact person = Ennis R |
| | case reference number = TAC MF3085, TAC MF3086 | | | case reference number = TAC MF3085, TAC MF3086 |
| | document type = Memoranda, Request for Additional Information (RAI) | | | document type = Memoranda, Request for Additional Information (RAI) |
| | page count = 4 | | | page count = 4 |
| | project = TAC:MF3085, TAC:MF3086 | | | project = TAC:MF3085, TAC:MF3086 |
| | stage = | | | stage = Draft RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 21, 2014 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 21, 2014 MEMORANDUM TO: Robert G. Schaaf, Acting Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /RA/ |
| | | Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
| MEMORANDUM TO: Robert G. Schaaf, Acting Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /RA/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LIMERICK GENERATING STATION, UNITS 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MF3085 AND MF3086) | | LIMERICK GENERATING STATION, UNITS 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MF3085 AND MF3086) |
| | | The enclosed draft request for additional information (RAI) was transmitted on July 21, 2014, to Mr. Frank Mascitelli of Exelon Generation Company, LLC (Exelon, the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensees amendment request for Limerick Generating Station (LGS), Units 1 and 2 dated November 15, 2013. The proposed amendment would revise the Technical Specification requirements related to the response time for the main steam line flow-high isolation function. |
| The enclosed draft request for additional information (RAI) was transmitted on July 21, 2014, to Mr. Frank Mascitelli of Exelon Generation Company, LLC (Exelon, the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee's amendment request for Limerick Generating Station (LGS), Units 1 and 2 dated November 15, 2013. The proposed amendment would revise the Technical Specification requirements related to the response time for the main steam line flow-high isolation function. | | The draft RAI was sent to Exelon to ensure that the questions are understandable, the regulatory basis for the questions is clear, and to determine if the information was previously docketed. This memorandum and the enclosure do not convey or represent an NRC staff position regarding the licensee's request. |
| | | Docket Nos. 50-352 and 50-353 |
| The draft RAI was sent to Exelon to ensure that the questions are understandable, the regulatory basis for the questions is clear, and to determine if the information was previously docketed. This memorandum and the enclosure do not convey or represent an NRC staff position regarding the licensee's request. | |
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| Docket Nos. 50-352 and 50-353 | |
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| ==Enclosure:== | | ==Enclosure:== |
| Draft RAI | | Draft RAI |
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| July 21, 2014 MEMORANDUM TO: Robert G. Schaaf, Acting Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /RA/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | July 21, 2014 MEMORANDUM TO: Robert G. Schaaf, Acting Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /RA/ |
| | Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LIMERICK GENERATING STATION, UNITS 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MF3085 AND MF3086) | | LIMERICK GENERATING STATION, UNITS 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MF3085 AND MF3086) |
| | | The enclosed draft request for additional information (RAI) was transmitted on July 21, 2014, to Mr. Frank Mascitelli of Exelon Generation Company, LLC (Exelon, the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensees amendment request for Limerick Generating Station (LGS), Units 1 and 2 dated November 15, 2013. The proposed amendment would revise the Technical Specification requirements related to the response time for the main steam line flow-high isolation function. |
| The enclosed draft request for additional information (RAI) was transmitted on July 21, 2014, to Mr. Frank Mascitelli of Exelon Generation Company, LLC (Exelon, the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee's amendment request for Limerick Generating Station (LGS), Units 1 and 2 dated November 15, 2013. The proposed amendment would revise the Technical Specification requirements related to the response time for the main steam line flow-high isolation function. | | The draft RAI was sent to Exelon to ensure that the questions are understandable, the regulatory basis for the questions is clear, and to determine if the information was previously docketed. This memorandum and the enclosure do not convey or represent an NRC staff position regarding the licensee's request. |
| | | Docket Nos. 50-352 and 50-353 |
| The draft RAI was sent to Exelon to ensure that the questions are understandable, the regulatory basis for the questions is clear, and to determine if the information was previously docketed. This memorandum and the enclosure do not convey or represent an NRC staff position regarding the licensee's request. | |
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| Docket Nos. 50-352 and 50-353 | |
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| ==Enclosure:== | | ==Enclosure:== |
| Draft RAI | | Draft RAI DISTRIBUTION PUBLIC GThomas, NRR/DSS/SRXB LPL1-2 R/F RidsNrrDorlLpl1-2 Resource RidsNrrDorlDpr Resource RidsNrrPMLimerick Resource ACCESSION NO.: ML14202A518 OFFICE LPL1-2/PM NAME REnnis DATE 7/21/14 OFFICIAL RECORD COPY |
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| DISTRIBUTION PUBLIC GThomas, NRR/DSS/SRXB LPL1-2 R/F RidsNrrDorlLpl1-2 Resource RidsNrrDorlDpr Resource RidsNrrPMLimerick Resource ACCESSION NO.: ML14202A518 OFFICE LPL1-2/PM NAME REnnis DATE 7/21/14 OFFICIAL RECORD COPY DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT MAIN STEAM LINE FLOW-HIGH ISOLATION RESPONSE TIME EXELON GENERATION COMPANY, LLC LIMERICK GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 | |
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| By application dated November 15, 2013, as supplemented by letter dated April 16, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML13322A448 and ML14106A642, respectively), Exelon Generation Company, LLC (Exelon, the licensee), submitted a license amendment request for Limerick Generating Station (LGS), | | DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT MAIN STEAM LINE FLOW-HIGH ISOLATION RESPONSE TIME EXELON GENERATION COMPANY, LLC LIMERICK GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 By application dated November 15, 2013, as supplemented by letter dated April 16, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. |
| Units 1 and 2. The proposed amendment would revise the Technical Specification (TS) requirements related to the response time for the main steam line flow-high isolation function. | | ML13322A448 and ML14106A642, respectively), Exelon Generation Company, LLC (Exelon, the licensee), submitted a license amendment request for Limerick Generating Station (LGS), |
| | Units 1 and 2. The proposed amendment would revise the Technical Specification (TS) requirements related to the response time for the main steam line flow-high isolation function. |
| | The Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal. |
| | : 1. Section 3.0 of Attachment 1 to the application dated November 15, 2013, states that the current analysis of record for the LGS main steam line break (MSLB) loss-of-coolant accident peak cladding temperature response is documented in General Electric topical report NEDC-32170P, Revision 2, day May 1995. If this topical report has already been submitted to the NRC, please identify the document which submitted the report, otherwise submit the report. |
| | : 2. Section 4.1 of Attachment 1 to the application lists 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 46 as Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors. That title pertains to 10 CFR 50.46, not GDC 46. |
| | Please clarify the applicable regulatory requirements/criteria that pertain to this amendment request. |
| | : 3. As discussed in Section 3.0 of Attachment 1 to the application, GE Hitachi Nuclear Energy (GEH) performed a MSLB outside of containment (STMO) analysis using the evaluation model SAFER04A. The licensee stated that the SAFER simulation of the analysis provides fuel heat-up and long-term cooling system response. The NRC staff requests that the licensee provide additional information to support the following statement in the submittal: |
| | This methodology is more accurate than the current method which is based on simplifying assumptions as described in UFSAR [Updated Final Safety Analysis Report] Section 15.6.4. In addition, Attachment 4 to the application, GEH document 0000-0158-9651-NP, states on page 3 that: |
| | Enclosure |
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| The Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal.
| | LGS UFSAR 15.6.4.4.f: Level rise time is conservatively assumed to be 1 second. Mixture quality is conservatively taken to be a constant 7% (steam weight percentage) during mixture flow. This assumption is not necessary. |
| : 1. Section 3.0 of Attachment 1 to the application dated November 15, 2013, states that the current analysis of record for the LGS main steam line break (MSLB) loss-of-coolant accident peak cladding temperature response is documented in General Electric topical report NEDC-32170P, Revision 2, day May 1995. If this topical report has already been submitted to the NRC, please identify the document which submitted the report, otherwise submit the report.
| | SAFER is a systems code and can calculate the time varying two phase break flow during the STMO event. |
| : 2. Section 4.1 of Attachment 1 to the application lists 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 46 as "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors." That title pertains to 10 CFR 50.46, not GDC 46.
| | The original and the newly submitted analysis are based on SAFER evaluation model. Why is the above assumption not necessary now? Describe the SAFER code changes, if any, to justify the deletion of this key assumption. |
| Please clarify the applicable regulatory requirements/criteria that pertain to this amendment request.
| | Confirm whether or not the following assumptions currently listed in UFSAR Section 15.6.4.4, and discussed in Attachment 1 to the application, will be revised as part of the implementation of the proposed amendment: |
| : 3. As discussed in Section 3.0 of Attachment 1 to the application, GE Hitachi Nuclear Energy (GEH) performed a MSLB outside of containment (STMO) analysis using the evaluation model SAFER04A. The licensee stated that the SAFER simulation of the analysis provides fuel heat-up and long-term cooling system response. The NRC staff requests that the licensee provide additional information to support the following statement in the submittal:
| | : d. Isolation valves start to close at 0.5 seconds on high flow signal and are fully closed at 5.5 seconds. |
| "This methodology is more accurate than the current method which is based on simplifying assumptions as described in UFSAR [Updated Final Safety Analysis Report] Section 15.6.4." In addition, Attachment 4 to the application, GEH document 0000-0158-9651-NP, states on page 3 that:
| | : f. Level rise time is conservatively assumed to be 1 second. Mixture quality is conservatively taken to be a constant 7% (steam weight percentage) during mixture flow.}} |
| Enclosure
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| - 2 - LGS UFSAR 15.6.4.4.f: "Level rise time is conservatively assumed to be 1 second. Mixture quality is conservatively taken to be a constant 7% (steam weight percentage) during mixture flow." This assumption is not necessary.
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| SAFER is a systems code and can calculate the time varying two phase break flow during the STMO event. The original and the newly submitted analysis are based on SAFER evaluation model. Why is the above assumption not necessary now? Describe the SAFER code changes, if any, to justify the deletion of this key assumption. Confirm whether or not the following assumptions currently listed in UFSAR Section 15.6.4.4, and discussed in Attachment 1 to the application, will be revised as part of the implementation of the proposed amendment: | |
| d. Isolation valves start to close at 0.5 seconds on high flow signal and are fully closed at 5.5 seconds. | |
| f. Level rise time is conservatively assumed to be 1 second. Mixture quality is conservatively taken to be a constant 7% (steam weight percentage) during mixture flow. | |
| }} | |
Letter Sequence Draft RAI |
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MONTHYEARML13322A4482013-11-15015 November 2013 License Amendment Request - Main Steam Line Flow-High Isolation Response Time Change from <0.5 Seconds to <1.0 Seconds Project stage: Request ML14010A1562014-01-10010 January 2014 Acceptance Review for TACs MF3085 & MF3086 - Limerick, Units 1 and 2 - MSL Flow-High Isolation Response Time Project stage: Acceptance Review ML14066A0972014-03-0707 March 2014 Draft Request for Additional Information Project stage: Draft RAI ML14106A6422014-04-16016 April 2014 Response to Request for Additional Information - License Amendment Request Main Steam Line Flow-High Isolation Response Time Change High Isolation Response Time Change from 0.5 Seconds to 1.0 Seconds Project stage: Response to RAI ML14202A5182014-07-21021 July 2014 Draft Request for Additional Information (Tac Nos. MF3085 and MF3086) Project stage: Draft RAI ML14255A0882014-09-11011 September 2014 Response to Draft Request for Additional Information - License Amendment Request - Main Steam Line Flow-High Isolation Response Time Change from ≪ 0.5 Seconds to ≪ 1.0 Seconds Project stage: Draft Request ML14311A8922014-11-0707 November 2014 Response to Draft Request for Additional Information- License Amendment Request - Main Steam Line Flow-High Isolation Response Time Change from ≪ 0.5 Seconds to ≪ 1.0 Seconds Project stage: Draft Request ML14311A2902014-11-0707 November 2014 10 CFR 20.46 Annual Report Project stage: Request ML14344A6812015-01-0707 January 2015 Issuance of Amendments - Main Steam Line Flow-High Isolation Response Time Project stage: Approval 2014-03-07
[Table View] |
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Category:Memoranda
MONTHYEARML22308A2392022-11-0808 November 2022 Documentation of Approval for Longer Review Period for Limerick Digital Instrumentation and Control License Amendment Requests Acceptance Review ML22034A3932022-02-16016 February 2022 Calendar Year 2021 Security Baseline Completion Memo ML21277A2472021-11-0505 November 2021 Notification of Significant Licensing Action - Proposed Issuance of Order Approving the Transfer of Licenses for Which a Hearing Has Been Requested - Exelon Generation Company, LLC; Et. Al ML18138A3442018-05-22022 May 2018 2018 Limerick Summary of Public Meeting and Attendance List ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML17037B8502017-02-0606 February 2017 08/21/1975 Notice of Meeting with Architect Engineers of Mark II Owners to Discuss Load Combinations and Analytical Techniques for Determining Stresses in Mechanical Components and Structures of Mark II Containments ML16344A2192016-12-12012 December 2016 Safety Evaluation for Limerick, Units 1 and 2, Proposed License Amendment to Revise the Technical Specifications to Address the High-Pressure Coolant Injection Operability Requirement Under Low Reactor Pressure Conditions ML16221A6712016-08-0808 August 2016 Draft Request for Additional Information ML16221A6122016-08-0808 August 2016 Draft Request for Additional Information ML16174A2982016-06-22022 June 2016 Draft Request for Additional Information ML16166A0862016-06-14014 June 2016 Draft Request for Additional Information ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16085A0252016-03-24024 March 2016 Draft Request for Additional Information ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML15202A3782015-07-21021 July 2015 Draft Request for Additional Information ML15028A4502015-01-27027 January 2015 LG-15-014 Verification of Readiness for Supplemental Inspection at Limerick Generating Station ML15035A1122015-01-10010 January 2015 LTR-15-0061 Lewis Cuthbert, President, Alliance for a Clean Environment, ACE, Letter Lessons Learned from Fukushima Related to Limerick Nuclear Plant ML14267A0762014-09-23023 September 2014 Acknowledgement Letter: B. Shank and C. Shank Regarding Limerick Nuclear Power Plant ML14247A6482014-09-10010 September 2014 Supplemental Safety Evaluation Report ML14190A9442014-08-11011 August 2014 Forwarding of Supplement 1 to the Safety Evaluation Report Related to the License Renewal of Limerick Generating Station, Units 1 and 2, Docket Numbers 50-352 and 50-353, to the Advisory Committee on Reactor Safeguards ML14210A5762014-07-29029 July 2014 Draft Request for Additional Information (Tac Nos. MF3198 and MF3199) ML14202A5182014-07-21021 July 2014 Draft Request for Additional Information (Tac Nos. MF3085 and MF3086) ML14055A5322014-03-11011 March 2014 Summary of Telephone Conference Call Held on January 30, 2014. Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning Requests for Additional Information Pertaining to the Limerick Generating Station, ML14066A0972014-03-0707 March 2014 Draft Request for Additional Information ML14030A0942014-01-29029 January 2014 Draft Request for Additional Information (TAC Nos. MF1399 and MF1400) ML13309A0802013-12-11011 December 2013 Memorandum to File: Transcript for 10 CFR 2.206 Petition from Beyond Nuclear (Et Al) Regarding General Electric Mark I and Mark II Boiling-Water Reactors ML13190A3522013-07-10010 July 2013 Notice of Forthcoming Teleconference with Exelon Generation Company, LLC ML13156A0902013-06-26026 June 2013 Dseis Meeting Summary ML13109A5392013-05-0303 May 2013 5/23/2013 - Meeting Notice: Forthcoming Meeting to Discuss the Draft Supplemental Environmental Impact Statement for the License Renewal of Limerick Generating Station, Units 1 and 2 ML12348A6962012-12-17017 December 2012 1/3/2013 - Notice of Forthcoming Meeting with Exelon Generation Company, LLC, to Discuss Requests for Additional Information Regarding Exelon Physical Security Plans ML1227704332012-10-0101 October 2012 Minutes of the ACRS Plant License Renewal Subcommittee Meeting on September 5, 2012 (Open) ML12139A0612012-06-25025 June 2012 Summary of Telephone Conference Call Held on May 16, 2012, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC, Concerning Requests for Additional Information Pertaining to the Limerick Generating Station, Lice ML1210403072012-04-12012 April 2012 Draft Request for Additional Information ML12083A2112012-04-11011 April 2012 Summary of Telephone Conference Call Held on February 23, 2012 Between the U.S. Nuclear Regulatory Commission and Exelon Generating Company, LLC, Concerning Request for Additional Information Pertaining to the Limerickgenerating Station, Li ML1208602902012-03-26026 March 2012 Notice of Forthcoming Public Meeting with Exelon Generation to Discuss Future Fleet Submittal Regarding Licensed Operator Eligibility Requirements ML1135300442011-12-19019 December 2011 Electronic Transmission, Draft Request for Additional Information Regarding Proposed Technical Specification Safety Limit Minimum Critical Power Ratio Changes ML1133402312011-12-12012 December 2011 Request for Additional Information for Limerick Generating Station, Units 1 and 2 License Renewal Application-Scoping and Screening (TAC Nos. ME6555 and ME6556) ML11272A2372011-10-26026 October 2011 Summary of Public Scoping Meetings Related to the Review of the Limerick Generating Station, Units 1 and 2, LRA ML11251A0672011-09-12012 September 2011 Forthcoming Meeting to Discuss the License Renewal Process and Environmental Scoping for Limerick Generating Station, Units 1 and 2, License Renewal Application ML11245A0082011-09-0606 September 2011 09/22/2011 Notice of Forthcoming Meeting to Discuss the License Renewal Process and Environmental Scoping for Limerick Generating Station, Units 1 and 2, License Renewal Application ML1124104422011-08-29029 August 2011 Corrected Transcript for 10 CFR 2.206 Petition Regarding Limerick Scrams - Second Teleconference with Petitioner ML1121606122011-08-0808 August 2011 Memorandum to File: Transcript for 10 CFR 2.206 Petition Regarding Limerick Scrams - Second Teleconference with Petitioner ML1117803082011-06-28028 June 2011 Memo to File Documenting Transcript for 10 CFR 2.206 Petition Regarding Limerick Scrams - Initial Teleconference with Petitioner ML1114403042011-05-24024 May 2011 Summary of Annual Assessment Meeting, Limerick Generating Station, on May 18, 2011 ML1103800542011-03-18018 March 2011 Summary of Telephone Conference Call Held on 1/28/11, Between the USNRC and Exelon Generation Company, LLC, Concerning the Proposed Limerick Generating Station, Units 1 and 2, License Renewal Application ML1105502222011-02-24024 February 2011 Electronic Transmission, Draft Request for Additional Information Regarding Proposed Technical Specification Allowed Outage Time Extensions to Support Residual Heat Removal Service Water (RHRSW) Maintenance ML1103304292011-02-0303 February 2011 Electronic Transmission, Draft Request for Additional Information Regarding Proposed Technical Specification Safety Limit Minimum Critical Power Ratio Changes ML1032004852010-11-16016 November 2010 Electronic Transmission, Draft Request for Additional Information Proposed Technical Specification Changes to High Pressure Coolant Injection Equipment Room Delta Temperature Trip Setpoint ML1032105082010-11-16016 November 2010 Units 1 & 2 - Electronic Transmission, Draft Request for Additional Information Regarding Request to Implement Emergency Action Level Scheme Change to NEI 99-01, Revision 5 2022-02-16
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23276B4642023-10-0303 October 2023 NRR E-mail Capture - NRC Request for Additional Information Limerick TSTF-477 LAR ML23269A0522023-09-26026 September 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000352/2023010 and 05000353/2023010 ML23208A1942023-07-27027 July 2023 NRR E-mail Capture - Limerick Generating Station - Audit Plan for TSTF-477 LAR Review (L-2022-LLA-0174) ML23202A0682023-07-21021 July 2023 NRR E-mail Capture - NRC Request for Additional Information Re. TSTF-477 LAR ML23201A1262023-07-18018 July 2023 Additional RAIs for Limerick Generation Station, Units 1 and 2 - LAR and Exemption Request for Digital I&C Installation Support ML23173A0632023-06-20020 June 2023 RAIs for Limerick Generation Station, Units 1 and 2 - LAR and Exemption Request for Digital I&C Installation Support ML22320A1132022-11-21021 November 2022 Generation Station, Units 1 and 2 - Supplemental Information Needed for Acceptance of Digital Instrumentation and Controls License Amendment Requests ML22172A0752022-06-17017 June 2022 Response: Review and Feedback on Draft Limerick Digital License Amendment Request (L-2020-LRM-0041) ML22136A0032022-05-13013 May 2022 NRR E-mail Capture - NRC Request for Additional Information - Limerick License Amendment Request (L-2021-LLA-0042) ML22124A2862022-05-0404 May 2022 Information Needed to Provide Substantive Feedback on Human Factors Engineering Supporting the Planned Limerick Digital I&C License Amendment Request ML22103A2542022-04-19019 April 2022 Draft Request for Additional Information ML22089A1172022-03-30030 March 2022 Additional Comments and Questions on Constellation'S March 31st Presentation ML22045A4822022-02-14014 February 2022 Notification of Conduct of a Fire Protection Team Inspection 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 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 ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21048A3402021-02-11011 February 2021 Request for Information for Relief Request I4R-24 Associated with Residual Heat Removal Heat Exchanger Category C-A and C-B Examinations ML21015A1852021-01-15015 January 2021 Temporary Instruction 2515/194 Inspection Documentation Request ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML20156A2992020-06-0404 June 2020 RAI for RR to Use Inservice Testing Program Safety Relief Valve Testing ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20149K7012020-05-28028 May 2020 Request for Additional Information for License Amendment Request to Use Inservice Testing Program Safety Relief Valve Testing ML20098C4342020-04-0606 April 2020 Draft Request for Additional Information - Limerick Generating Station, Unit 1 - Emergency LAR to Increase Allowable MSIV Leakage ML19344A0332019-12-10010 December 2019 Request for Additional Information License Amendment Request to Adopt TSTF-505, Revision 2 Risk Informed Completion Times Exelon Generation Company Limerick Generating Station, Units 1 and 2 Docket Nos. 50-352 and 50-353 ML19344A0242019-12-0909 December 2019 Request for Additional Information (RAI) - Limerick Units 1 and 2: TSTF-505, Use of Risk Informed Completion Times (Ricts) for Actions to Be Taken When Limiting Conditions for Operation (Lcos) Are Not Met ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML19192A0312019-07-10010 July 2019 NRR E-mail Capture - LIMERICK-REQUEST for Additional Information: Risk Informed Completion Times TSTF-505, Revison 2, Provide RISK-INFORMED Completion Times - RITSTF Initiative 4B ML19168A0882019-06-17017 June 2019 Letter to R. W. Libra Alternative Request Pertaining to Dry Shielded Canisters Equipped with Boral Neutron Absorber Plates - Supplemental Information Needed (W/Enclosursi) ML18276A0202018-10-0202 October 2018 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan for Limerick and Peach Bottom ML18081B0682018-03-26026 March 2018 Second Round RAI for Limerick, 10 CFR 50.69 ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML17354A0182017-12-19019 December 2017 E-mail Request for Information (Rai): Relief Request I3R-23 Regarding Limited Examination Coverage ML18040A9212017-11-0707 November 2017 Attachment - Limerick Generating Station, Units 1 and 2, Request for Additional Information Application to Revise TSs to Adopt TSTF-542, Revision 2 ML17207A0772017-07-31031 July 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Adoption of Title 10 of the Code of Federal Regulations Section 50.69 ML17137A1652017-05-16016 May 2017 Request for Additional Information for Relief Request Associated with Reactor Pressure Vessel Nozzle Repairs ML17062A4912017-03-0303 March 2017 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative to RPV Threads in Flange Examination (CAC Nos. MF8712-MF8729) ML17018A1932016-12-0909 December 2016 NRR E-mail Capture - (External_Sender) Limerick Flood MSA Question ML16221A6712016-08-0808 August 2016 Draft Request for Additional Information ML16221A6122016-08-0808 August 2016 Draft Request for Additional Information ML16174A2982016-06-22022 June 2016 Draft Request for Additional Information ML16166A0862016-06-14014 June 2016 Draft Request for Additional Information ML16085A0252016-03-24024 March 2016 Draft Request for Additional Information ML15202A3782015-07-21021 July 2015 Draft Request for Additional Information ML14324A8102014-11-18018 November 2014 Emails from ACE and NRC Response Re Limerick Higher Radiation Readings on Nov 18, 2014 ML14210A5762014-07-29029 July 2014 Draft Request for Additional Information (Tac Nos. MF3198 and MF3199) 2023-09-26
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 21, 2014 MEMORANDUM TO: Robert G. Schaaf, Acting Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /RA/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MF3085 AND MF3086)
The enclosed draft request for additional information (RAI) was transmitted on July 21, 2014, to Mr. Frank Mascitelli of Exelon Generation Company, LLC (Exelon, the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensees amendment request for Limerick Generating Station (LGS), Units 1 and 2 dated November 15, 2013. The proposed amendment would revise the Technical Specification requirements related to the response time for the main steam line flow-high isolation function.
The draft RAI was sent to Exelon to ensure that the questions are understandable, the regulatory basis for the questions is clear, and to determine if the information was previously docketed. This memorandum and the enclosure do not convey or represent an NRC staff position regarding the licensee's request.
Docket Nos. 50-352 and 50-353
Enclosure:
Draft RAI
July 21, 2014 MEMORANDUM TO: Robert G. Schaaf, Acting Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /RA/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MF3085 AND MF3086)
The enclosed draft request for additional information (RAI) was transmitted on July 21, 2014, to Mr. Frank Mascitelli of Exelon Generation Company, LLC (Exelon, the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensees amendment request for Limerick Generating Station (LGS), Units 1 and 2 dated November 15, 2013. The proposed amendment would revise the Technical Specification requirements related to the response time for the main steam line flow-high isolation function.
The draft RAI was sent to Exelon to ensure that the questions are understandable, the regulatory basis for the questions is clear, and to determine if the information was previously docketed. This memorandum and the enclosure do not convey or represent an NRC staff position regarding the licensee's request.
Docket Nos. 50-352 and 50-353
Enclosure:
Draft RAI DISTRIBUTION PUBLIC GThomas, NRR/DSS/SRXB LPL1-2 R/F RidsNrrDorlLpl1-2 Resource RidsNrrDorlDpr Resource RidsNrrPMLimerick Resource ACCESSION NO.: ML14202A518 OFFICE LPL1-2/PM NAME REnnis DATE 7/21/14 OFFICIAL RECORD COPY
DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT MAIN STEAM LINE FLOW-HIGH ISOLATION RESPONSE TIME EXELON GENERATION COMPANY, LLC LIMERICK GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 By application dated November 15, 2013, as supplemented by letter dated April 16, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Nos.
ML13322A448 and ML14106A642, respectively), Exelon Generation Company, LLC (Exelon, the licensee), submitted a license amendment request for Limerick Generating Station (LGS),
Units 1 and 2. The proposed amendment would revise the Technical Specification (TS) requirements related to the response time for the main steam line flow-high isolation function.
The Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal.
- 1. Section 3.0 of Attachment 1 to the application dated November 15, 2013, states that the current analysis of record for the LGS main steam line break (MSLB) loss-of-coolant accident peak cladding temperature response is documented in General Electric topical report NEDC-32170P, Revision 2, day May 1995. If this topical report has already been submitted to the NRC, please identify the document which submitted the report, otherwise submit the report.
- 2. Section 4.1 of Attachment 1 to the application lists 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 46 as Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors. That title pertains to 10 CFR 50.46, not GDC 46.
Please clarify the applicable regulatory requirements/criteria that pertain to this amendment request.
- 3. As discussed in Section 3.0 of Attachment 1 to the application, GE Hitachi Nuclear Energy (GEH) performed a MSLB outside of containment (STMO) analysis using the evaluation model SAFER04A. The licensee stated that the SAFER simulation of the analysis provides fuel heat-up and long-term cooling system response. The NRC staff requests that the licensee provide additional information to support the following statement in the submittal:
This methodology is more accurate than the current method which is based on simplifying assumptions as described in UFSAR [Updated Final Safety Analysis Report] Section 15.6.4. In addition, Attachment 4 to the application, GEH document 0000-0158-9651-NP, states on page 3 that:
Enclosure
LGS UFSAR 15.6.4.4.f: Level rise time is conservatively assumed to be 1 second. Mixture quality is conservatively taken to be a constant 7% (steam weight percentage) during mixture flow. This assumption is not necessary.
SAFER is a systems code and can calculate the time varying two phase break flow during the STMO event.
The original and the newly submitted analysis are based on SAFER evaluation model. Why is the above assumption not necessary now? Describe the SAFER code changes, if any, to justify the deletion of this key assumption.
Confirm whether or not the following assumptions currently listed in UFSAR Section 15.6.4.4, and discussed in Attachment 1 to the application, will be revised as part of the implementation of the proposed amendment:
- d. Isolation valves start to close at 0.5 seconds on high flow signal and are fully closed at 5.5 seconds.
- f. Level rise time is conservatively assumed to be 1 second. Mixture quality is conservatively taken to be a constant 7% (steam weight percentage) during mixture flow.