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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 = 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. | |
| | |
| 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.
| |
| 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 |
|---|
|
|
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)
MONTHYEARML24274A2372024-10-0707 October 2024
– Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Primary Containment Leakage Technical Specifications
ML24199A1842024-07-15015 July 2024
RAI-LAR for Limerick EPID: L-2024-LLA-0079- Use This Version
ML24197A0162024-07-12012 July 2024
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591
ML24150A0242024-05-29029 May 2024
Notification of Commercial Grade Dedication Inspection (05000352/2024012 and 05000353/2024012) and Request for Information
ML24079A2922024-03-21021 March 2024
Draft Request for Additional Information Regarding Limerick Digital Instrumentation and Controls License Amendment Request (EPID L-2022-LLA-0140) - Non-Proprietary
ML23276B4642023-10-0303 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
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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.
