Similar Documents at Perry |
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Category:Letter type:L
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L-23-244, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023
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L-23-238, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 202023-11-10010 November 2023
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L-23-052, Submittal of the Updated Safety Analysis Report, Revision 232023-10-27027 October 2023
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L-23-206, Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD2023-09-12012 September 2023
Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD
L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023
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L-23-001, License Amendment Request to Remove the Table of Contents from the Technical Specifications2023-08-0707 August 2023
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L-23-174, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2023-07-19019 July 2023
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L-23-146, License Renewal Application for the Perry Nuclear Power Plant2023-07-0303 July 2023
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L-23-134, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-23023 May 2023
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L-22-272, Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis (EPID L-2021-LLA-0067) and Withdrawal of Exemption Requests (EPIDs L-2021-LLE-0022 and L-2021-LLE-0023)2022-12-16016 December 2022
Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis (EPID L-2021-LLA-0067) and Withdrawal of Exemption Requests (EPIDs L-2021-LLE-0022 and L-2021-LLE-0023)
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Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 19
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Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual
L-20-239, Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-08-0505 August 2022
Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
L-22-171, Response to Request for Additional Information Regarding Proposed Inservice Inspection Alternative IR-0632022-07-14014 July 2022
Response to Request for Additional Information Regarding Proposed Inservice Inspection Alternative IR-063
L-22-099, Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis2022-06-0101 June 2022
Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis
L-22-104, Annual Radiological Environmental Operating Report2022-04-28028 April 2022
Annual Radiological Environmental Operating Report
L-22-110, Response to Request for Additional Information Re 10CFR50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirement2022-04-28028 April 2022
Response to Request for Additional Information Re 10CFR50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirement
L-22-105, Annual Radiological Effluent Release Report2022-04-27027 April 2022
Annual Radiological Effluent Release Report
L-22-082, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-23023 March 2022
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L-22-056, Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage2022-03-22022 March 2022
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L-22-052, Deviation from BWRVIP-42 Revision 1-A, BWR Vessel and Internals Project, Low Pressure Coolant Injection (LPCI) Coupling Inspection and Flaw Evaluation Guidelines2022-03-16016 March 2022
Deviation from BWRVIP-42 Revision 1-A, BWR Vessel and Internals Project, Low Pressure Coolant Injection (LPCI) Coupling Inspection and Flaw Evaluation Guidelines
L-22-073, Submittal of the Decommissioning Funding Status Report for Perry Nuclear Power Plant2022-03-16016 March 2022
Submittal of the Decommissioning Funding Status Report for Perry Nuclear Power Plant
L-22-023, Retrospective Premium Guarantee2022-02-17017 February 2022
Retrospective Premium Guarantee
L-21-280, 10 CFR 50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirements2022-01-0505 January 2022
10 CFR 50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirements
L-21-282, Proposed Inservice Inspection Alternative IR-0632022-01-0505 January 2022
Proposed Inservice Inspection Alternative IR-063
L-21-259, 10 CFR 50.55a Requests Number VR-10 and VR-11, Inservice Valve Testing2021-12-28028 December 2021
10 CFR 50.55a Requests Number VR-10 and VR-11, Inservice Valve Testing
L-21-287, Submittal of Revision 22 to Updated Safety Analysis Report (Supplement Letter)2021-12-20020 December 2021
Submittal of Revision 22 to Updated Safety Analysis Report (Supplement Letter)
2024-01-24
[Table view]
Category:Operating Report
MONTHYEARL-19-201, Report of Facility Changes, Tests, and Experiments2019-10-0707 October 2019
Report of Facility Changes, Tests, and Experiments
L-19-050, Stations - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2019-03-0606 March 2019
Stations - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments
L-09-217, Submittal of Report of Facility Changes, Tests and Experiments2009-09-0808 September 2009
Submittal of Report of Facility Changes, Tests and Experiments
ML0617105072006-06-0808 June 2006
Corrected April 2006 Monthly Operating Report for NPDES
ML0617105032006-06-0808 June 2006
NPDES Monthly Report Forms for the Month of May 2006
ML0511702372005-04-21021 April 2005
Submission of Core Operating Limits Report
ML0234600122002-12-0505 December 2002
Transmittal of the NPDES Monthly Report Forms for the Month of November 2002
ML0229605202002-10-10010 October 2002
September 2002 NPDES Monthly Report Forms. No Violations Occurred During This Period
ML0223402132002-08-12012 August 2002
NPDES July 2002 Monthly Operating Report
ML0208403302002-03-0606 March 2002
NPDES Monthly Report Forms for the Month of February, 2002
2019-03-06
[Table view] |
Text
FENOC' ~
Perry Nuclear Power Plant PO. Box 97 10 Center Road Perry, Ohio 44081 FirstEnergy Nuclear Operating Company Frank Payne 440-280-5382 Vice President October 7, 2019 L-19-201 10 CFR 50.59(d)(2)
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Report of Facility Changes, Tests, and Experiments The FirstEnergy Nuclear Operating Company (FENOC) hereby submits the Perry Nuclear Power Plant Report of Facility Changes, Tests, and Experiments. The attached report covers the period from October 5, 2017 to October 6, 2019.
There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Phil H. Lashley, Acting Manager - Nuclear Licensing and Regulatory Affairs, at (330) 315-6808.
Attachment:
Perry Nuclear Power Plant Report of Facility Changes, Tests, and Experiments for the Period October 5, 2017 to October 6, 2019 cc: NRC Region Ill Administrator NRC Resident Inspector NRC Project Manager
Attachment L-19-201 Perry Nuclear Power Plant Report of Facility Changes, Tests, and Experiments for the Period October 5, 2017 to October 6, 2019 Page 1 of 2
Title:
Mitigation/Elimination of Reaching a Level 8 Post Scram Activity
Description:
A design modification added a logic block to the digital feedwater control system (DFWCS) to provide automatic actions that will prevent a reactor water Level 8 trip post-scram. A reactor water Level 8 trip results in a loss of normal feedwater and allows high-pressure injection to be stopped automatically on high level. If both reactor feedpump turbines (RFPTs) and the motor feedpump are available following a drop and a recovery in reactor water level, this new software logic block will trip the RFPT A through use of a spare digitally-controlled contact in parallel with the existing trip push button and transfers from three-element control to single-element control. These automatic actions will prevent a Level 8 trip, which would isolate the remaining feedwater pumps, without the need for expedited operator intervention.
Summary of Evaluation:
The as-modified digital feedwater control system will continue to provide normal reactor level control as the existing control system but with the addition of a new logic block to trip the RFPT A and transfer to single-element control during the level swings experienced post-scram at high power in order to prevent a subsequent Level 8 trip.
The evaluation was prepared using the guidance of NRC Regulatory Issue Summary (RIS) 2002-22, Use of EPRI/NEI Joint Task Force Report, Guideline on Licensing Digital Upgrades: EPRI TR-102348, Revision 1, NEI 01-01: A Revision of EPRI TR-102348 To Reflect Changes to the 10 CFR 50.59 Rule, as appropriate. The software change that this modification implemented in the DFWCS complies with FENOCs software quality assurance requirements and was extensively tested to ensure that it met the design requirements. The DFWCS does not directly control any SSC that mitigates the consequences of an accident. In the event of a failure of this new logic block, the SSCs that are credited with mitigating that failure are unaffected by this change. The failure modes of the new logic block in the DFWCS have been analyzed in the failure modes and effects analysis, which concluded there are no new failure effects that would initiate an accident or create an accident of a different type.
The feedwater system and the associated digital feedwater control system are important to safety systems as they provide the normal reactor water level control; however, any failure of the systems is already bounded by the loss of feedwater and overfeed transients analyzed in the Updated Safety Analysis Report (USAR).
Therefore, the as-modified DFWCS does not (1) increase the likelihood of occurrence of previously evaluated malfunctions of an SSC important to safety, (2) increase the
Attachment L-19-201 Page 2 of 2 consequences of a malfunction of an SSC important to safety, or (3) introduce a malfunction of an SSC important to safety with a different result.
In conclusion, the modification to the DFWCS does not require a departure from a method of evaluation described in the USAR, and the DFWCS does not interact directly or indirectly with a fission product barrier. The proposed activity does not meet any of the 10 CFR 50.59 (c)(2) criteria; therefore, a license amendment is not required.
