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Category:Memoranda
MONTHYEARML24215A3602024-08-20020 August 2024 Summary of July 30, 2024 Meeting Between the NRC and TMI2Solutions Staff ML24214A1402024-08-0505 August 2024 July 24, 2024, Summary of the Public Meeting Regarding Clinton Power Station, Unit 1, Partial Site Release ML24152A1852024-06-0404 June 2024 Summary of March 28, 2024, Closed Hybrid Pre-Submittal Meeting Between Constellation Energy Generation, LLC and the U.S. Nuclear Regulatory Commission Regarding a Future Amendment Request for Fuel Transition ML24135A3712024-05-21021 May 2024 Memo from Awaldron to Skoenick Transmitting Meeting Summary ML23324A4332024-01-23023 January 2024 10/16-17/2023 Summary of Routine NRC Site Visit at the Oyster Creek Nuclear Generating Station to Discuss License Termination Plans and Other Technical Topics ML23276A6522023-10-11011 October 2023 Pre-submittal Meeting Summary, September 14, 2023 ML23102A0382023-04-10010 April 2023 Occupational Radiation Exposure Annual Report ML23044A3662023-02-15015 February 2023 Calendar Year 2022 Reactor Oversight Process Baseline Inspection Program Completion - Region III ML22300A0842022-11-10010 November 2022 Pressure and Temperature Limits Report (Ptlr), Revision 8 ML22308A2392022-11-0808 November 2022 Documentation of Approval for Longer Review Period for Limerick Digital Instrumentation and Control License Amendment Requests Acceptance Review CLI-22-04, Change Letter to Peach Bottom Subsequent Renewed Licenses March 17 2022 Rev 12022-03-25025 March 2022 Change Letter to Peach Bottom Subsequent Renewed Licenses_March 17 2022_Rev 1 ML22073A2442022-03-16016 March 2022 TMI NMSS Memo for ISFSI PSP Review Completion, Staff Review of the Three Mile Island Independent Spent Fuel Storage Installation Physical Security Plan (Rev.0) and License Amendment Request (Cac/Epid No: 000078/05000289/L-2021-SPR-0004) ML22074A0922022-03-15015 March 2022 TMI: 1 ISFSI Only PSP Rev. 0 Notice of Safeguards Memo ML22034A3932022-02-16016 February 2022 Calendar Year 2021 Security Baseline Completion Memo ML21349A1062021-12-15015 December 2021 Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273 ML21309A5482021-11-15015 November 2021 NSIR Staff Review of the Wolf Creek Generating Stations Security Plan Training & Qualification Plan & Safeguards Contingency Plan for the Verification of ASM EA 20 091 Incorporation 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 ML21243A4492021-09-0202 September 2021 ISFSI Technical Assistance Request - Review of Physical Security Plan ML21218A0082021-08-10010 August 2021 NSIR Review of the Three Mile Island Physical Security Plan Revision 24 for the Verification of ASM 20-103 Incorporation ML21166A1182021-06-15015 June 2021 Technical Assistance Request - Review of Physical Security Plan for the Three Mile Island Unit 1 Power Station Independent Spent Fuel Storage Installation ML20150A2862020-11-23023 November 2020 Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Exelon Generation Co., LLC Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for LaSalle ISFSI ML20155K6862020-11-23023 November 2020 Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Exelon Corporation LLC Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Braidwood ISFSI ML20155K6802020-11-23023 November 2020 Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Exelon Corporation, LLC, Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Byron ISFSI ML20150A3252020-11-23023 November 2020 Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Exelon Generation Co., LLC Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Oyster Creek ISFSI ML20150A2812020-11-23023 November 2020 Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Exelon Generation Co., LLC Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Dresden ISFSI ML20150B3182020-11-23023 November 2020 Memo to File: Environmental Assessment and Finding of No Significant Impact and NRC Financial Analysis for Exelon Generation Co., LLC Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and (C) for Quad Cities ISFSI ML20212L7682020-10-29029 October 2020 Memo to File: Final Environmental Assessment, Finding of No Significant Impacts, NRC Financial Analysis for Exelon Generation Company, Initial Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(B) for Clinton Power Stati ML20296A3342020-10-21021 October 2020 ISI Remote Inspection - Supplemental Request for Information ML20239A8322020-08-25025 August 2020 Summary of the August 4, 2020 Public Webinar to Discuss the NRC 2019 End-of-Cycle Plant Performance Assessment of LaSalle County Station, Units 1 and 2 ML20239A8252020-08-25025 August 2020 Summary of the August 4, 2020 Public Webinar to Discuss the NRC 2019 End-Of-Cycle Plant Performance Assessment of Clinton Power Station, Unit 1 ML20234A4422020-08-21021 August 2020 Summary of the July 29, 2020 Public Webinar to Discuss the NRC 2019 End-Of-Cycle Plant Performance Assessment of Dresden Nuclear Power Station, Units 2 and 3 ML20234A4472020-08-21021 August 2020 Summary of the July 29, 2020 Public Webinar to Discuss the NRC 2019 End-Of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station, Units 1 and 2 ML20098G3132020-04-0707 April 2020 Actions Related to the Requirements for Work Hour Controls During the Coronavirus Disease 2019 Public Health Emergency ML19295G4922019-10-24024 October 2019 Summary of the October 3, 2019, Public Meeting Near the Oyster Creek Nuclear Generating Station Regarding the Establishment and Operation of Community Advisory Boards IR 05000461/20190122019-09-25025 September 2019 NRC Inspection of Temporary Instruction 2515/194, Implementation of Industry Initiative Associated with the Open Phase Condition Design Vulnerabilities in Electric Power Systems Report 05000461/2019012 ML19182A3562019-07-23023 July 2019 Quarterly Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 - April 1 to June 30, 2019 ML19088A0462019-03-26026 March 2019 Submittal of 2018 Occupational Exposure Report (1O CFR 20.2206(b) ML19044A3842019-02-0606 February 2019 Notification of the Facility Director Change for the Nuclear Regulatory Commission Regulated Independent Spent Fuel Storage Installations (CLNl90659) ML18288A1942018-10-25025 October 2018 Summary of the Site Visit Related to the Review of the Subsequent License Renewal Application for the Peach Bottom Atomic Power Station Units 2 and 3 ML18205A5502018-08-0606 August 2018 Memorandum to File - Public Feedback to 7/17/18 Public Meeting in Forked River, Nj, to Receive Public Comments on Post-Shutdown Decommissioning Activities Report and Site-Specific Decommissioning Cost Estimate ML18158A1702018-06-0707 June 2018 Special Inspection Team Charter for Inoperability of the Clinton Power Station Division 1 and Division 2 Emergency Diesel Generators ML18151A1632018-06-0404 June 2018 Summary of Peach Bottom Annual Assessment Meeting and Attendee List ML18138A3442018-05-22022 May 2018 2018 Limerick Summary of Public Meeting and Attendance List ML18100A2112018-04-26026 April 2018 Notice of Public Meeting May 24, 2018 ML18102A1072018-04-18018 April 2018 Annual Assessment Meeting Summary 2018 ML18093B1022018-04-0303 April 2018 Notice of Public Meeting with Exelon Generation Company, LLC, to Discuss the NRCs Assessment of Safety Performance at Three Mile Island Nuclear Station, Unit 1 for 2017, as Described in the Annual Assessment Letter Dated February 28, 2018 ML18044A1632018-02-20020 February 2018 01/18/2018 Summary of Pre-Application Meeting with Exelon Corporation Regarding the Peach Bottom, Units 2 and 3, Subsequent License Renewal Application ML17335A0442017-12-0404 December 2017 Tvel Lead Test Assembly 3rd Closed Meeting ML17271A0532017-09-29029 September 2017 2017 Summary of Annual Decommissioning Funding Status Reports for Reactors in Decommissioning ML17181A4552017-06-29029 June 2017 Memo 06/29/17 2017 Dresden Generating Station Emergency Response Exercise After-Action Report (Blb) 2024-08-05
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ATTENDANCE SHEET Exelon Licensing Meeting March 18, 2002 Name Organization Phc ne Number Chris Gratton NRC/NRR/DLPM 301 -415-1055 A-AII/-V ell;;
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RED d'o r4 Enclosure 1
Agenda
"*Introductions - All
"*Exelon Items Of Interest - Jeff Benjamin
"*Timeliness and Quality Of Submittals - Mike Gallagher
"*NRC Items Of Interest
"*Break-out Sessions
"* Submittals Planned For 2002 - Licensing Managers
"*Status Of Items Currently With NRC - Project Managers 2
Licensing Counterpart Meeting With NRC Exelon Licensing & Regulatory Affairs March 18, 2002 0
e (D
Exelon Items Of Interest
"- Key Accomplishments In 2001 mFacilitated By Excellent NRC Support
"- Exelon Regulatory Strategy
"* Risk Informed Submittals MISI, ILRT, PASS, AST
"- Regulatory Burden Reduction
- Radiation Protection, FFD, Reporting Requirements 3
a Timeliness and Quality Of Submittals
"*Outage Milestone Improvements
"*Results To Date
"*Precedent Review And Selection 4
NRC Items Of Interest 5
I Break-out Sessions
- Licensing Managers/Project Managers Meet To Discuss:
"*Submittals Planned For 2002 Status Of Items Currently With NRC 6
BACKGROUND
- NOED guidance has always required demonstration of at least "safety neutral" and at least a supporting qualitative risk assessment
- Part 9900 revision (12/12/00) and RIS 2001-10 (4/2/01) stated: "granting of this type of an NOED shall not involve an increase in radiological risk".
- Need to clarify current guidance re: no Increase in risk.
0 I
(1D REVISION in risk".
- At present cannot support quantitative threshold for "no increase
Section B.2.1 revised to read:
Granting this type of NOED shall not involve any net increase in radiological risk.
any Can be satisfied by at least a qualitative risk assessment, considering attendant to benefits of compensatory measures, and any identifiable risk complying with the TS action statement with degraded equipment.
EFFORT TO "RISK-INFORM" NOED PROCESS CONCEPT:
"* Review NOED database for past few years to identify categories of NOED requests.
"* Review historical data of risk-informed license amendments corresponding to the NOED categories (e.g.; AOT extensions, surveillance extensions, degraded equipment).
"* Review studies on transition and shutdown risks under degraded I inoperable conditions.
"* Attempt to envelope transition and shutdown risks, and compensatory measure benefits.
"* Develop risk-informed NOED guidance.
- Taken from letter dated 01/31/02 A. Randolph Blough to Charles H. Cruise (ADAMS accession no. ML020320050)
Mr. Charles H. Cruse 2 auxiliary pumps necessary for diesel generator operation. A root cause investigation pointed to an apparent problem with the lube oil drive gear be&ring that caused this gear to improperly mesh with the flexible drive assembly, generating excessive wear. You indicated that the other EDGs onsite had been recently tested successfully. The 1 B EDG was inspected for similar wear and this worn condition was not found. We understand that your staff was planning to inspect the 2B EDG once the 2A EDG was returned to service. The other two onsite EDGs are of a different design and thus are unaffected by this problem. A new flexible drive gear was being installed; however, installation of this gear required substantial disassembly of the diesel engine, engine reassembly, and post maintenance testing -- work that could not be completed in the existing Allowed Outage Time (AOT).
Your staff requested this NOED after consideration of the safety significance and potential consequences of such an action. Your staff concluded that remaining at power for an additional six-day period while completing the repairs to the 2A EDG would not result in an undue risk to the health and safety of the public. That conclusion was based on risk insights that qualitatively indicated no net increase in radiological risk as a result of having this EDG out of service for up to six additional days, as well as your confidence that the ongoing repairs to the EDG would be effective and would be completed within this discretionary period. Your staff's conclusion that this NOED was safety and risk neutral was, in part, based on a number of compensatory, risk management measures implemented while the 2A EDG was out-of service.
As compensatory measures during the period of the NOED, your staff committed to: (1) postpone any elective maintenance on the 2B EDG, (2) suspend any discretionary maintenance or testing on any Unit 2 safety-related equipment or the offsite power system, (3) ensure that all four offsite power circuits were available, even though only two were required to be operable by TSs, (4) shut down Unit 2 if threatened by severe weather with the potential to interrupt offsite power during the time the NOED was in effect, (5) train and station a dedicated operator to utilize the non-safety-related 5,400 kW 0C EDG to power either Unit 2 vital bus in the event of a loss of offsite power, as well as to cross-connect key motor control centers to provide power to necessary equipment, and (6) assign an operator to control the auxiliary feedwater flow control valves in the event that flow control was lost following a loss of offsite power.
The NRC's basis for this discretion considered: (1) the availability and recent satisfactory testing of the four other EDGs onsite; (2) the availability of all offsite electrical sources; (3) the absence of adverse weather or generation shortages that would impact the reliability of these power supplies; (4) the comprehensive list of compensatory actions undertaken to ensure that the extended LCO did not result in a net increase in radiological risk; (5) indications that your repairs to the 2A EDG would be successfully implemented during the discretionary period, and (6) the fact that the apparent root cause had been identified and that no failure mechanisms common to the EDGs were identified.
Based on the above considerations, the staff concluded that Criterion B.2.1.1 .a and the applicable criteria in Section C.4 to NRC Manual Chapter 9900, "Technical Guidance, Operation
- Notices of Enforcement Discretion" were met. Criterion B.2.1.1 .a states that for an operating plant, the NOED is intended to avoid unnecessary transients as a result of compliance with the license condition and, thus, minimize potential safety consequences and operational risks.
On the basis of the staff's evaluation of your request, we concluded that issuance of this NOED is consistent with the Enforcement Policy and staff guidance, and has no adverse impact on public health and safety. Therefore, it is our intention to exercise discretion not to enforce