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MONTHYEARML22034A3952022-02-16016 February 2022 Enclosure 3 - IP 96001 CY2021 - IR 8 Baseline Inspection Completion ML22034A3972022-02-16016 February 2022 Enclosure 2 - IP 92707 CY2021 - IR 8 Baseline Inspection Completion ML22034A3992022-02-16016 February 2022 Enclosure 1 - IP 71130.03 Cy 2021 - IR 8 Baseline Inspection Completion ML21161A2922021-06-0404 June 2021 NRC-2020-000299 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed ML20332A1092020-11-24024 November 2020 NRC-2020-000299 - Resp 1 - Interim, Agency Records Subject to the Request Are Enclosed (Part 1 of 6) ML20332A1102020-11-24024 November 2020 NRC-2020-000299 - Resp 1 - Interim, Agency Records Subject to the Request Are Enclosed (Part 2 of 6) ML20332A1112020-11-24024 November 2020 NRC-2020-000299 - Resp 1 - Interim, Agency Records Subject to the Request Are Enclosed (Part 3 of 6) ML20332A1122020-11-24024 November 2020 NRC-2020-000299 - Resp 1 - Interim, Agency Records Subject to the Request Are Enclosed (Part 4 of 6) ML20332A1132020-11-24024 November 2020 NRC-2020-000299 - Resp 1 - Interim, Agency Records Subject to the Request Are Enclosed (Part 5 of 6) ML20332A1142020-11-24024 November 2020 NRC-2020-000299 - Resp 1 - Interim, Agency Records Subject to the Request Are Enclosed (Part 6 of 6) RS-20-140, Proposed Changes to Decommissioning Trust Agreements2020-10-30030 October 2020 Proposed Changes to Decommissioning Trust Agreements ML20160A3512020-06-0505 June 2020 Document Request for IP 71111.17T (10 CFR 50.59) Team Inspection ML20008D2232020-01-0808 January 2020 NRC Region I Twitter Feeds 10-1 to 12-31-2019 ML19009A3282019-01-0808 January 2019 NRC-2017-000688 - Resp 4 - Interim, Agency Records Subject to the Request Are Enclosed (Limerick Generating Station, Units 1 and 2, FHRR - Released Set) ML17152A1692017-05-22022 May 2017 Annual Assessment Meeting Attendance List ML16145A0662016-05-23023 May 2016 Aam Attendance Lists ML15147A0772015-05-21021 May 2015 Aam Attendence Sheet May 21, 2015 RA-15-019, Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2015-03-0202 March 2015 Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML15071A1192015-03-0202 March 2015 Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML15041A6172015-02-13013 February 2015 Public Notice - NRC Staff Proposes to Amend Operating License at the Limerick Generating Station, Unit 2 ML15020A2082015-01-20020 January 2015 Limerick Public Meeting 2014 Feedback Form #2 from Alliance for a Clean Environment ML15020A1902015-01-20020 January 2015 Public Mtg 2014 Feedback Form #4 from D. Cuthbert, Alliance for a Clean Environment ML14132A2392014-05-0707 May 2014 Annual Assessment Meeting Attendance List for May 7, 2014 ML15120A2292014-03-11011 March 2014 NRC Comments on Fpra FAQ 14-0007, Transient Fire Frequency Likelihood (4/30/2015) ML14029A6452014-01-27027 January 2014 Agency Docketing Statement-Case No. 13-1311 ML13364A2832013-12-30030 December 2013 Announcement of 2014 Generic Fundamentals Examination Administration Dates-Letter Dated Dec 30, 2013 ML13220A0672013-08-0707 August 2013 LTR-13-0660 - Edward Calabrese, University of Massachusetts Email Two Papers Entitled Origin of the Linearity No Threshold Dose-Response Concept and How the Us National Academy of Sciences Misled the World Community on Cancer Risk Assessmen ML13143A3312013-06-0606 June 2013 Operating Boiling-Water Reactor Licensees with Mark 1 and Mark 2 Containments Addresses List - Enclosure 2 ML13143A2702013-05-23023 May 2013 ACE Comments at LIM Aam March 21 2013 ML13087A4282013-03-28028 March 2013 Aam Attendee Sign in Sheet - PII Redacted ML12130A1522012-05-0909 May 2012 ACE - Response to Issues Discussed Between NRC and ACE ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1114307272011-05-18018 May 2011 Aam Attendance List, May 18, 2011 ML1014701432010-05-25025 May 2010 Aam Sign-in Attendance List Sheets for Annual Assessment Meeting May 25, 2010 ML1010302182010-04-12012 April 2010 Attachment to E-mail Limerick Mur Acceptance Review - Supplemental Information Needed, Proposed License Amendment Request Regarding Measurement Uncertainty Recapture Power Uprate Request ML1008503992010-03-25025 March 2010 Attachment 4: NRC Regulatory Issue Summary 2002-03 Cross-Reference RIS 2002-03, Attachment 4: NRC Regulatory Issue Summary 2002-03 Cross-Reference2010-03-25025 March 2010 Attachment 4: NRC Regulatory Issue Summary 2002-03 Cross-Reference ML1008504012010-03-25025 March 2010 Attachment 5: Summary of Regulatory Commitments ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions ML0620804052006-07-10010 July 2006 Enclosure 2 - Draft (7/10/2006) on the Nrc'S Concerns and Exelon'S Response to the June 13, 2006 Public Meeting on Exelon'S 5b Submittal ML0613001042006-04-20020 April 2006 Sign-In Sheet for Limerick Annual Assessment Meeting 2022-02-16
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SUPPLEMENTAL INFORMATION NEEDED PROPOSED LICENSE AMENDMENT REQUEST REGARDING MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE REQUEST LIMERICK GENERATING STATION, UNIT NOS 1 AND 2 DOCKET NOS. 50-352 AND 50-353
By letter dated March 25, 2010, Exelon Generation Company, LLC submitted a license amendment request (LAR) regarding a measurement uncertainty recapture (MUR) power uprate for Limerick Generating Station (LGS), Units 1 and 2 (Agencywide Documents Access and Management System, Accession No. ML100850380). The MUR uprate request includes a proposed modification to the standby liquid control system (SLCS) that is required for the implementation of the requested uprate. The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing the LAR and has concluded that the information delineated below is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed license amendment in terms of regulatory requirements and the protection of public health and safety and the environment.
- 1. The NRC staff is assessing two-pump SLCS operation for conformance to Title 10 of the Code of Federal Regulations (10 CFR), paragraph 50.62(c)(4), which requires a system capable of injecting the equivalent of 86-gallons per minute of 13 weight-percent sodium pentaborate decahydrate solution at the natural boron-10 isotope abundance into a 251-inch inside diameter reactor pressure vessel for a given core design. To establish this equivalency, the reactor vessel inside diameter is required. Please provide the reactor vessel inside diameter for LGS, Units 1 and 2.
- 2. Criterion 4 of 10 CFR 50.36(c)(2)(ii) requires the establishment of a Limiting Condition for Operation (LCO) for structures, systems or components which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
This requirement applies to the SLCS, as reflected in the current LGS Unit 1 and 2 Technical Specifications. Because the proposed changes result in an LCO that allows any two pumps to remain operable to meet the LCO, the same degree of assurance should be provided that each pump can meet the specified requirements. Verify that system surveillance, testing, inspection, and maintenance requirements for the 'C' standby liquid control system pump will remain the same as those for the 'A' and 'B' pumps, thereby providing the same degree of assurance exists regarding the operability of the 'C' pump, should it need to be placed in service.
- 3. The Anticipated Transient Without Scram (ATWS) definition in 10 CFR 50.62(b) describes an anticipated operational occurrence followed by a failure of the reactor trip system, for which systems must be in place to mitigate. In this case, the SLCS is demonstrated to perform its reactivity control function under the conditions of a postulated main steamline isolation valve closure. Although injection against the predicted peak pressure is not necessary, the system must perform its function when required. Please provide additional details regarding the selection of the required injection pressure:
- a. Confirm that the selected pressure corresponds to the pressure predicted at an appropriate time after receipt of an injection signal to account for the system automatic initiation delay.
- b. Under conditions indicative of the limiting ATWS pressurization event, what is the average operator time to initiate the SLCS manually?
- c. How many pumps would the operator be instructed to start under ATWS conditions?
- d. What is the pressurization effect of an operator initiating a single pump, followed by an automatic initiation?
- e. Is the possibility described in Item d, above, included in the evaluation of SLCS injection pressures presented in the LAR? If not, why not?