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Category:Letter type:L
MONTHYEARL-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023
Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615
L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023
Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports
L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023
L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023
Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615
L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023
Twenty-Third Refueling Outage Inservice Inspection Summary Report
L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023
Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023
Quality Assurance Program Manual
L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023
Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023
Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615
L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023
Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report
L-23-055, Submittal of the Updated Final Safety Analysis Report, Revision 342023-05-23023 May 2023
Submittal of the Updated Final Safety Analysis Report, Revision 34
L-23-065, Annual Financial Report2023-05-22022 May 2023
Annual Financial Report
L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023
Cycle 24 Core Operating Limits Report
L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023
Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations
L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023
Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations
L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023
Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological
L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023
Discharge Monitoring Report (Npdes), Permit No. PA0025615
L-23-053, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-04-14014 April 2023
2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023
Submittal of the Decommissioning Funding Status Reports
L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023
180-Day Steam Generator Tube Inspection Report
L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023
Annual Notification of Property Insurance Coverage
L-23-036, Report of Facility Changes, Tests and Experiments2023-03-13013 March 2023
Report of Facility Changes, Tests and Experiments
L-23-086, Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0404 March 2023
Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair
L-23-087, Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027)2023-03-0404 March 2023
Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027)
L-23-073, Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0101 March 2023
Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair
L-23-016, Twenty-Eighth Refueling Outage Inservice Inspection Summary Report2023-02-21021 February 2023
Twenty-Eighth Refueling Outage Inservice Inspection Summary Report
L-23-064, Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-02-21021 February 2023
Discharge Monitoring Report, (NPDES) Permit No. PA0025615
L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023
Energy Harbor Nuclear Corp Retrospective Premium Guarantee
L-22-193, Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H2023-02-14014 February 2023
Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H
L-22-286, Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time2023-02-14014 February 2023
Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
L-23-032, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 20222023-01-23023 January 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 2022
L-22-281, Discharge Monitoring Report (NPDES) Permit No. PA00256152022-12-16016 December 2022
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-22-246, Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO2022-12-0707 December 2022
Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO
L-22-217, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-11-21021 November 2022
Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-22-226, Emergency Preparedness Plan2022-11-0404 November 2022
Emergency Preparedness Plan
L-22-222, Cycle 29-1 Core Operating Limits Report2022-10-31031 October 2022
Cycle 29-1 Core Operating Limits Report
L-22-228, Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2022-10-26026 October 2022
Independent Spent Fuel Storage Installation Changes, Tests, and Experiments
L-22-200, Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage2022-10-21021 October 2022
Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage
L-22-232, Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes2022-10-21021 October 2022
Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes
L-22-238, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-10-20020 October 2022
Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-22-227, Revised August 2022 Outfall 003 & 004 NPDES Discharge Monitoring Report (Dmr), Revised Daily Effluent Monitoring Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins2022-10-0303 October 2022
Revised August 2022 Outfall 003 & 004 NPDES Discharge Monitoring Report (Dmr), Revised Daily Effluent Monitoring Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins
L-22-219, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-09-26026 September 2022
Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-22-204, Submittal of Evacuation Time Estimates2022-09-0707 September 2022
Submittal of Evacuation Time Estimates
L-22-137, Request for Fire Protection Program Changes2022-09-0606 September 2022
Request for Fire Protection Program Changes
L-21-238, License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident2022-08-31031 August 2022
License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident
L-22-188, Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-08-22022 August 2022
Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage
L-22-191, Spent Fuel Storage Cask Registration2022-08-17017 August 2022
Spent Fuel Storage Cask Registration
2023-09-14
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FENOC FirstEnergyNuclear Operating Company James H. Lash 724-682-5234 Site Vice President Fax: 724-643-8069 March 28, 2007 L-07-053 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Emergency Response Data System In accordance with 10 CFR 50, Appendix E, Section VI, changes to the Beaver Valley Power Station (BVPS) Units No. 1 and No. 2 Data Point Libraries (DPL) for the Emergency Response Data System (ERDS) are provided in the Attachments.
Attachment 1 provides DPL pages for the data points that have been changed. Unit No. 1 DPL information associated with reactor vessel dynamic level high alarm limits was changed due to rescaling of the Reactor Vessel Level Indicating System dynamic head differential pressure levels. Changes for the Unit No. 2 DPL information associated with reactor coolant loop flow low alarm limits were implemented based on new defined operating limits. Attachment 2 provides a list of data points that have changed and a summary of the changes for each listed datapoint.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Henry L. Hegrat, Supervisor -
FENOC Fleet Licensing, at (330) 374-3114.
Sincerely, James H. Lash Attachments:
- 1. ERDS Data Point Library Changes
- 2. Summary Of Changes To Data Point Library (DPL) c: Ms. N. S. Morgan, NRR Project Manager (w/o enclosure)
Mr. P. C. Cataldo, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator Mr. D. J. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP) c2(0
L-07-053 Attachment 1 Page 1of 5 BEAVER VALLEY POWER STATION ERDS DATA POINT LIBRARY Date: 3/20/2007 Reactor Unit: BV1 Data Feeder: IPC NRC ERDS Parameter: REAC-VES-LV4 Point ID: L3212A Plant Spec Point Desc.: RX VESSEL DYNAMIC LEVEL - B Generic/Cond Desc.: REACTOR VESSEL WATER LEVEL Analog/Digital: A Engr Units/Dig States:
Engr Units Conversion: ICCM RVLIS ALGORITHM Minimum Instr Range: 0 Maximum Instr Range: 120 Zero Point
Reference:
N/A Reference Point Notes: N/A PROC or SENS: S Number of Sensors: 1 How Processed: N/A Sensor Location: SEE UNIQUE SYSTEM DESCRIPTION FIELD Alarm/Trip Set Points: SEE UNIQUE SYSTEM DESCRIPTION FIELD NI Detector Power Supply Cut-Off Power Level: N/A NI Detector Power Supply Turn-ON Power Level: N/A Instrument Failure Mode: LOW Temperature Compensation for DP Transmitters: Y Level Reference Leg: WET Unique System Desc.: Connections to the Reactor Vessel at the Incore Instrument Tubes sense Reactor Vessel core and internal DP. Reference line tubing runs from the instrument tubes to high volume sensors that isolate the RCS from the remainder of the RVLIS tubing. Capillary tubing runs from the high volume sensors thru the containment wall to hydraulic isolators. RTDs are installed on capillary lines for containment temperature compensation. ICCM receives transmitter output; this reading is invalid unless RCPs are running. LT-1 RC-1322 senses DP across Reactor Vessel and internals when any RCPs are running.
LOW ALARM =95% (Mode 1 thru 5)
HIGH ALARM =119.5% (Mode 1 thru 5)
No alarms in Mode 6
L-07-053 Attachment 1 Page 2 of 5 BEAVER VALLEY POWER STATION ERDS DATA POINT LIBRARY Date: 3/20/2007 Reactor Unit: BV1 Data Feeder: IPC NRC ERDS Parameter: REAC-VES-LV3 Point ID: L3206A Plant Spec Point Desc.: RX VESSEL DYNAMIC LEVEL -A Generic/Cond Desc.: REACTOR VESSEL WATER LEVEL Analog/Digital: A Engr Units/Dig States:
Engr Units Conversion: N/A Minimum Instr Range: 0 Maximum Instr Range: 120 Zero Point
Reference:
N/A Reference Point Notes: N/A PROC or SENS: S Number of Sensors: 1 How Processed: N/A Sensor Location: SEE UNIQUE SYSTEM DESCRIPTION FIELD Alarm/Trip Set Points: SEE UNIQUE SYSTEM DESCRIPTION FIELD NI Detector Power Supply Cut-Off Power Level: N/A NI Detector Power Supply Turn-ON Power Level: N/A Instrument Failure Mode: LOW Temperature Compensation for DP Transmitters: Y Level Reference Leg: WET Unique System Desc.: Connections to the Reactor Vessel at the Incore Instrument Tubes sense Reactor Vessel core and internal DP. Reference line tubing runs from the instrument tubes to high volume sensors that isolate the RCS from the remainder of the RVLIS tubing. Capillary tubing runs from the high volume sensors thru the containment wall to hydraulic isolators. RTDs are installed on capillary lines for containment temperature compensation. ICCM receives transmitter output; this reading is invalid unless RCPs are running. LT-1 RC-1312 senses DP across Reactor Vessel and internals when any RCPs are running.
LOW ALARM = 95% (Modes 1 thru 5)
HIGH ALARM =119.5% (Modes 1 thru 5)
No alarms in Mode 6
L-07-053 Attachment 1 Page 3 of 5 BEAVER VALLEY POWER STATION ERDS DATA POINT LIBRARY Date: 3/20/2007 Reactor Unit: BV2 Data Feeder: PCS NRC ERDS Parameter: CORE-FLOW1 Point ID: F0400A Plant Spec Point Desc.: RCL A FLW RCS-FT414 Generic/Cond Desc.: REACTOR COOLANT LOOP A FLOW Analog/Digital: A Engr Units/Dig States:
Engr Units Conversion: FLOW Minimum Instr Range: 0 Maximum Instr Range: 120 Zero Point
Reference:
N/A Reference Point Notes: N/A PROC or SENS: S Number of Sensors: 1 How Processed: N/A Sensor Location: SEE UNIQUE SYSTEM DESCRIPTION FIELD Alarm/Trip Set Points: HI ALM @ 100, LO ALM @ 95 NI Detector Power Supply Cut-Off Power Level: N/A NI Detector Power Supply Turn-ON Power Level: N/A Instrument Failure Mode: LOW Temperature Compensation for DP Transmitters: N Level Reference Leg: N/A Unique System Desc.: 2RCS-FT414 senses RCS Loop A flow and provides a signal to the computer, SSPS, and the Main Control Board. The Reactor Coolant Pump design flow rate is 95,230 GPM at 542F and 2250 PSIG. 100% flow in Loop A is approximately 3.5E7 LBM/HR. 2RCS-FT414 senses flow at the Reactor Coolant Pipe Elbow at SG A Outlet. Ref: 10080-TLD-006-045; RM-406-1; RM-406-3; 2BVT 1.6.1.
L-07-053 Attachment 1 Page 4 of 5 BEAVER VALLEY POWER STATION ERDS DATA POINT LIBRARY Date: 3/20/2007 Reactor Unit: BV2 Data Feeder: PCS NRC ERDS Parameter: CORE-FLOW2 Point ID: F0421A Plant Spec Point Desc.: RCL B FLW RCS-FT425 Generic/Cond Desc.: REACTOR COOLANT LOOP B FLOW Analog/Digital: A Engr Units/Dig States:
Engr Units Conversion: FLOW Minimum Instr Range: 0 Maximum Instr Range: 120 Zero Point
Reference:
N/A Reference Point Notes: N/A PROC or SENS: S Number of Sensors: 1 How Processed: N/A Sensor Location: SEE UNIQUE SYSTEM DESCRIPTION FIELD Alarm/Trip Set Points: HI ALM @ 100, LO ALM @ 95 NI Detector Power Supply Cut-Off Power Level: N/A NI Detector Power Supply Turn-ON Power Level: N/A Instrument Failure Mode: LOW Temperature Compensation for DP Transmitters: N Level Reference Leg: N/A Unique System Desc.: 2RCS-FT425 senses RCS Loop B flow and provides a signal to the computer, SSPS, and the Main Control Board. The Reactor Coolant Pump design flow rate is 95,230 GPM at 542F and 2250 PSIG. 100% flow in Loop B is approximately 3.5E7 LBM/HR. 2RCS-FT425 senses flow at the Reactor Coolant Pipe Elbow at SG B Outlet. Ref: 10080-TLD-006-062; RM-406-1; RM-406-3; 2BVT 1.6.1.
L-07-053 Attachment 1 BEAVER VALLEY POWER STATION Page 5 of 5 ERDS DATA POINT LIBRARY Date: 3/20/2007 Reactor Unit: BV2 Data Feeder: PCS NRC ERDS Parameter: CORE-FLOW3 Point ID: F0442A Plant Spec Point Desc.: RCL C FLW RCS-FT436 Generic/Cond Desc.: REACTOR COOLANT LOOP C FLOW Analog/Digital: A Engr Units/Dig States:
Engr Units Conversion: FLOW Minimum Instr Range: 0 Maximum Instr Range: 120 Zero Point
Reference:
N/A Reference Point Notes: N/A PROC or SENS: S Number of Sensors: 1 How Processed: N/A Sensor Location: SEE UNIQUE SYSTEM DESCRIPTION FIELD Alarm/Trip Set Points: HIALM@100, LOALM@95 NI Detector Power Supply Cut-Off Power Level: N/A NI Detector Power Supply Turn-ON Power Level: N/A Instrument Failure Mode: LOW Temperature Compensation for DP Transmitters: N Level Reference Leg: N/A Unique System Desc.: 2RCS-FT436 senses RCS Loop C flow and provides a signal to the computer, SSPS, and the Main Control Board. The Reactor Coolant Pump design flow rate is 95,230 GPM at 542F and 2250 PSIG. 100% flow in Loop C is approximately 3.5E7 LBM/HR. 2RCS-FT436 senses flow at the Reactor Coolant Pipe Elbow at SG C Outlet. Ref: 10080-TLD-006-079; RM-406-1; RM-406-3; 2BVT 1.6.1.
L-07-053 Attachment 2 Page 1 of 1
SUMMARY
OF CHANGES TO DATA POINT LIBRARY (DPL)
Reactor DPL Description of Change(s)
Unit Point BVI L3212A Date: Changed to "3/20/2007" Plant Spec Point Desc.: Replaced "RX VESSEL DYNAMIC RANGE -B" with "RX VESSEL DYNAMIC LEVEL -B" Unique System Desc.: Corrected typographical error "internals" in the last sentence.
Replaced the "HIGH ALARM = 115 % (Modes 1 thru 5)" with a "HIGH ALARM = 119.5 % (Modes 1 thru 5)"
L3206A Date: Changed to "3/20/2007" Unique System Desc.: Replaced the "HIGH ALARM = 115 % (Modes 1 thru 5)" with a "HIGH ALARM = 119.5 % (Modes 1 thru 5)"
BV2 F0400A Date: Changed to "3/20/2007" Alarm/Trip Set Points.: Replaced the "HI ALM @ 100, LO ALM @ 97" with "HI ALM @ 100, LO ALM @ 95" F0421A Date: Changed to "3/20/2007" Alarm/Trip Set Points.: Replaced the "HI ALM @ 100, LO ALM @ 97" with "HI ALM @ 100, LO ALM @ 95" F0442A Date: Changed to "3/20/2007" Alarm/Trip Set Points.: Replaced the "HI ALM @ 100, LO ALM @ 97" with "HI ALM @ 100, LO ALM @ 95"