Letter Sequence Response to RAI |
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MONTHYEARML0232505062002-11-22022 November 2002 RAI, Amendment Request to Allow Plant Operation with Associated Containment at Atmospheric Pressure (TAC Nos. MB5303 & MB5304) Project stage: RAI ML0233304922002-11-29029 November 2002 Draft Request for Additional Information (Rai), Regarding Amendment Request to Allow Plant Operation with Associated Containment at Atmospheric Pressure Project stage: Draft RAI L-02-115, Response to a Request for Additional Information in Support of License Amendment Requests Nos. 300 & 1722002-12-0202 December 2002 Response to a Request for Additional Information in Support of License Amendment Requests Nos. 300 & 172 Project stage: Response to RAI ML0301000742002-12-11011 December 2002 Responses to (Request for Additional Information) RAI Questions on MAAP5 Topical Report Project stage: Request ML0300906222003-01-0909 January 2003 Firstenergy Nuclear Operating Company an Application for a License Amendment to Allow FENOC to Convert the Beaver Valley Power Station Containments to Operate at Atmospheric Pressure Project stage: Other ML0312201452003-05-0202 May 2003 Request for Additional Information - Conversion from Subatmospheric to Atmospheric Containment Project stage: RAI ML0315601402003-06-0505 June 2003 (BVPS-1 and 2) - Request for Additional Information (RAI) - Conversion from Subatmospheric Containment Project stage: RAI ML0325302042003-09-10010 September 2003 Issuance of Amendment Nos. 257 & 139, Respectively, Approving Selective Implementation of Alternate Source Term and Control Room Habitability Techinical Specification Changes Project stage: Approval ML0325501732003-09-10010 September 2003 Technical Specification Pages for Amendment Nos. 257 & 139 to License Nos. DPR-66 & NPF-73, Respectively, Selective Implementation of Alternate Source Term & Control Room Habitability Project stage: Acceptance Review ML0323300032003-09-22022 September 2003 Summary of Meeting with Firstenergy Nuclear Operating Co Licensee'S MAAP5 Computer Code Modifications to Support Its Application for a License Amendment for Containment Conversion Project stage: Meeting 2003-01-09
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Category:Letter type:L
MONTHYEARL-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule L-24-182, Discharge 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2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024 CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological) L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024 Emergency Preparedness Plan L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024 L-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024 Withdrawal of Exemption Request L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-064, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152024-03-13013 March 2024 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report 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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 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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 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-FE O Beaver Valley Power Station Route 168 PO Box 4 FirstEnergyNuclearOperatingCompany Shtppngport, PA 15077-0004 724-682-5234 Mark B. Bezilla Fax- 724-643-8023 Site Vice President December 2, 2002 L-02-115 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Response to a Request for Additional Information in Support of License Amendment Requests Nos. 300 and 172 This letter provides FirstEnergy Nuclear Operating Company (FENOC) responses to the Section 1.0 questions provided in the November 22, 2002 NRC Request for Additional Information (RAI) regarding License Amendment Requests (LAR) 300 and 172. The LARs were submitted by FENOC letter L-02-069 dated June 5, 2002. The changes proposed by the LARs will revise the Beaver Valley Power Station Units 1 and 2 Technical Specifications to permit each unit to be operated with an atmospheric containment.
The RAI requested FENOC to respond to the Section 1.0 questions by December 3, 2002, in order to support a planned December 11, 2002 meeting with the NRC staff. As discussed in the RAI, FENOC plans on providing the responses to Section 2.0 questions regarding the radiological assessment by January 24, 2003.
A list of regulatory commitments associated with the containment conversion project was submitted with FENOC letter L-02-069. Commitment number 6 states that FENOC will provide marked-up Updated Final Safety Analysis Report (UFSAR) pages reflecting the necessary changes associated with the conversion to an atmospheric containment. The UFSAR mark-up package was to be provided to the NRC by December 5, 2002.
However, additional time is needed to complete the UFSAR mark-up package. FENOC will submit the UFSAR mark-up package to the NRC by January 31, 2003.
Attachment B contains the commitments made in this letter.
As stated in Letter L-02-069, FENOC requests approval of the proposed amendments by July 15, 2003, to support implementation following the next scheduled refueling outage for Unit 2; i.e., 2R10.
Beaver Valley Power Station, Unit No. 1 and No. 2 License Amendment Request Nos. 300 and 173 L-02-115 Page 2 If there are any questions concerning this matter, please contact Mr. Larry R. Freeland, Manager, Regulatory Affairs/Performance Improvement at 724-682-5284.
I declare under penalty of perjury that the foregoing is true and correct. Executed on December o*__, 2002.
Sincerely, 01,/./
0 I LOCA CASE8L-5_PP I 0o 0
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Attachment Attachment A (continued)
L-02-115 Item 1.2.5. Provide MAAP5 momentum-driven velocity time history profiles for compartments using representative MSLB and LOCA cases (as above).
Response to Item 1.2.5.
The MAAP5 momentum-driven transient velocities for all containment nodes are provided in the attached Figures for the two representative sequences. The large LOCA sequence is the double ended hot leg break (case 8L-5 PP) and is shown in Figure 16 and the MSLB case (case 15M_N13_PP) is shown in Figure 17.
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Attachment A (continued)
L-02-115 Item 1.2.6. How are the MAAP5 water and steam discharges modeled? For instance, is the modeling represented as a pressure flash assumption with a percentage of water fallout going to the MAAP aerosol model?
How is the water aerosol model initialized or seeded for added water from the discharge? How does the aerosol dropout compare to the LOCTIC model for liquid water removal from the atmosphere?
Response to Item 1.2.6.
For the analyses performed in support of the Beaver Valley application for containment conversion, as well as for the CVTR, HDR, Battelle-Frankfurt and CSTF experimental benchmarks, the discharge into containment is specified by either a separate design basis mass and energy release calculation or experimental measurements. As such, the water and steam discharge into the MAAP5 containment model is a time dependent boundary condition for the calculation. The discharged water is flashed based on the containment's total pressure. All evaluations assume a small fraction of the remaining water mass (typically 5% of the water flow rate), which is user specified, as becoming initially airborne. This water mass is added to the airborne mass evaluated by the MAAP aerosol model, which has been benchmarked with numerous experiments (including the ABCOVE tests). For the CVTR experiment, the incoming mass flow rate is 100% steam, and therefore, has no initial blowdown water mass added to the airborne aerosol mass.
The MAAP5 aerosol depletion (dropout) of the water mass is mechanistically calculated by the deposition models discussed in the MAAP User's Manual. The computer code LOCTIC does not have an aerosol dropout model. In LOCTIC, at the end of each time step, the containment atmosphere inventories of mass and energy are updated to reflect heat and mass transfers due to sprays, sinks, and blowdown during the time step. If these inventories are seen to correspond to a saturated state, all water mass in excess of what can be vaporized is deposited as liquid on the floor.
Item 1.2.7. Are liquid water (aerosol), gas and vapor masses summed to define a fluid density for the compartment flow equations and momentum driven velocity equations?
Response to Item 1.2.7.
Yes, the liquid water (aerosol), noncondensible gas and vapor masses are summed to define the fluid density for the compartment flow equations and the momentum-driven velocity calculations.
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Attachment Attachment A (continued)
L-02-115 Item 1.2.8. Are quantities set in the parameter files in British units converted to the International System of Units (SI) in the code? Comment on the form of the ideal gas equation used for determining the accumulator nitrogen gas mass when accumulator volumes and gas temperatures are set according to British units. (See files Ul_MINACCUM_N2 and CONTAINMENT_IAR _TABLE.)
Response to Item 1.2.8.
Yes, the quantities set in the parameter files in British units are converted to SI units in the MAAP5 code. All input values are converted to SI for code execution (pressure in Pa, temperature in K, etc.); this conversion occurs before accumulator nitrogen masses are computed. Hence, the ideal gas equation is correct as written, i.e. PV = nRT.
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Attachment B to L-02-115 Commitment List The following table identifies those actions committed to by FirstEnergy Nuclear Operating Company (FENOC) for Beaver Valley Power Station (BVPS) Unit Nos. 1 and 2 in this document. Any other actions discussed in the submittal represent intended or planned actions by FENOC. They are described only as information and are not regulatory commitments. Please notify Mr. Larry R. Freeland, Manager, Regulatory Affairs/Performance Improvement, at Beaver Valley on (724) 682-5284 of any questions regarding this document or associated regulatory commitments.
COMMITMENT REFERENCE DUE DATE
- 1. Submit UFSAR mark-up package FENOC Letter January31, 2003 to the NRC. L-02-115 B-1