Letter Sequence RAI |
|---|
|
|
MONTHYEARML0515302672005-06-0303 June 2005
6/3/05, Beaver Valley, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors
Project stage: RAI
L-05-123, Response to Request for Additional Information on Generic Letter 2004-022005-07-22022 July 2005
Response to Request for Additional Information on Generic Letter 2004-02
Project stage: Response to RAI
ML0603803422006-02-0909 February 2006
Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors TAC Nos. MC4665 and MC4666
Project stage: RAI
ML0613802732006-05-18018 May 2006
Request for Scheduler Extension from Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors (TAC No. MC46666)
Project stage: Other
L-08-054, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Corrective Actions2008-02-14014 February 2008
Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Corrective Actions
Project stage: Request
L-08-035, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors2008-02-29029 February 2008
Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors
Project stage: Supplement
ML0812301162008-02-29029 February 2008
Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors,...
Project stage: Other
L-08-257, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Request for Extension of Completion Date for Corrective Actions2008-08-28028 August 2008
Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Request for Extension of Completion Date for Corrective Actions
Project stage: Request
ML0827402412008-09-30030 September 2008
Extension Request Approval Letter Generic Letter 2004--02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors.
Project stage: Other
L-08-321, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2008-10-29029 October 2008
Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
Project stage: Supplement
L-09-056, Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Injection System Pumps2009-03-11011 March 2009
Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Injection System Pumps
Project stage: Other
ML0909001932009-03-31031 March 2009
Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors,
Project stage: Other
ML0910501002009-04-21021 April 2009
Correction Letter Extension Request Approval to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
Project stage: Other
L-09-131, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Additional Corrective Actions2009-04-30030 April 2009
Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Additional Corrective Actions
Project stage: Request
ML0912400302009-05-0505 May 2009
Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors.
Project stage: Other
L-09-152, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2009-06-30030 June 2009
Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
Project stage: Supplement
ML1002903182010-02-18018 February 2010
RAI, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
Project stage: RAI
ML1008407562010-03-31031 March 2010
Notice of Teleconference Meeting with Firstenergy Nuclear Operating Company Regarding Mutual Understanding of NRR Staff'S Request for Additional Information and to Discuss Generic Letter 2004-02
Project stage: RAI
ML1013206652010-05-18018 May 2010
Summary of Category 1 Teleconference with Firstenergy Nuclear Operating Company to Discuss NRC Request for Additional Information Regarding Generic Letter 2004-02
Project stage: RAI
L-13-176, Generic Safety Issue 191 Resolution Plan2013-05-16016 May 2013
Generic Safety Issue 191 Resolution Plan
Project stage: Other
2009-03-11
[Table View] |
|
|---|
Category:Letter
MONTHYEARML24025A0922024-01-25025 January 2024
Requalification Program Inspection
L-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023
Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615
IR 05000334/20230112023-12-0404 December 2023
Age-Related Degradation Inspection Report 05000334/2023011 and 05000412/2023011
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
IR 05000334/20233012023-11-27027 November 2023
Initial Operator Licensing Examination Report 05000334/2023301
L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
IR 05000334/20230032023-11-0606 November 2023
Integrated Inspection Report 05000334/2023003 and 05000412/2023003
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
ML23279A0612023-10-0505 October 2023
Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs)
ML23198A3592023-10-0202 October 2023
Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary
IR 05000334/20234022023-09-29029 September 2023
Security Baseline Inspection Report 05000334/2023402 and 05000412/2023402 (Cover Letter Only)
ML23237B4222023-09-28028 September 2023
Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments
ML23269A1242023-09-27027 September 2023
Request for Withholding Information from Public Disclosure
IR 05000334/20234012023-09-21021 September 2023
Cybersecurity Inspection Report 05000334/2023401 and 05000412/2023401 (Cover Letter Only)
ML23263A0192023-09-20020 September 2023
Operator Licensing Examination Approval
ML23243A9272023-09-19019 September 2023
Review of the Fall 2022 Steam Generator Tube Inspection Report
ML23249A1842023-09-18018 September 2023
Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06
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
IR 05000334/20230052023-08-31031 August 2023
Updated Inspection Plan for Beaver Valley Power Station Units 1 and 2 (Report 05000334/2023005 and 05000412/2023005)
L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023
Quality Assurance Program Manual
ML23129A1722023-08-25025 August 2023
Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1
IR 05000334/20230022023-08-0909 August 2023
Integrated Inspection Report 05000334/2023002 and 05000412/2023002
ML23219A0592023-08-0707 August 2023
Steam Generator Inspection Reports - Spring 2023 Spring Refueling Outrage
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
ML23188A0982023-07-17017 July 2023
Correction to the Safety Evaluation Issued Related to Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
ML23188A0672023-07-10010 July 2023
Project Manager Assignment
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
ML23157A1072023-06-0707 June 2023
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000334/2023011 and 05000412/2023011
ML23143A0272023-05-23023 May 2023
Licensed Operator Positive Fitness-For-Duty Test
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
ML23102A1472023-05-22022 May 2023
Issuance of Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
L-23-065, Annual Financial Report2023-05-22022 May 2023
Annual Financial Report
ML23135A7872023-05-19019 May 2023
Summary of Conference Calls Regarding the Spring 2023 Steam Generator Tube Inspections
L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
ML23124A1742023-05-17017 May 2023
Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1
L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023
Cycle 24 Core Operating Limits Report
ML23124A3882023-05-16016 May 2023
Summary of Regulatory Audit in Support of License Amendment Request to Revise Technical Specification 5.6.3, Core Operating Limits Reports (COLR) and TS 4.2.1 Fuel Assemblies
ML23129A0112023-05-16016 May 2023
Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter)
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
IR 05000334/20230012023-05-0808 May 2023
Integrated Inspection Report 05000334/2023001 and 05000412/2023001
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
ML23118A3812023-04-28028 April 2023
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
CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023
ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
ML23107A2502023-04-18018 April 2023
Requalification Program Inspection
2024-01-25
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML23143A0272023-05-23023 May 2023
Licensed Operator Positive Fitness-For-Duty Test
ML23125A1462023-05-0505 May 2023
NRR E-mail Capture - Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations
ML23125A1602023-05-0505 May 2023
NRR E-mail Capture - Correction to Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations
ML23122A0342023-05-0202 May 2023
NRR E-mail Capture - Beaver Valley - Request for Additional Information Regarding Unit 1 - 180 Day Steam Generator Tube Inspection Report
ML22312A5912022-11-0808 November 2022
NRR E-mail Capture - Beaver Valley Power Station, Units 1&2 - Request for Additional Information LAR to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
ML22278A0972022-10-0606 October 2022
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Fire Protection Program Changes
ML22178A1322022-06-24024 June 2022
Request for Additional Information for Beaver Valley Unit 2 Steam Generator Inspection Report - Fall 2021 Refueling Outage
ML22068A1822022-03-0909 March 2022
NRR E-mail Capture - Beaver Valley Power Station, Units 1 & 2 - Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5
ML22013A7512022-01-13013 January 2022
Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000334/2022010 and 05000412/2022010
ML21292A0482021-10-19019 October 2021
Ti 2515/194 Inspection Documentation Request
ML21259A1642021-09-16016 September 2021
NRR E-mail Capture - Request for Additional Information Regarding the LAR for Core Operating Limits
ML21124A1322021-05-0404 May 2021
Notification of Conduct of a Fire Protection Team Inspection
ML21102A1542021-04-0909 April 2021
Request for Additional Information (2nd Round) - Steam Generator Tube Sleeve LAR
ML21082A4942021-03-23023 March 2021
Final RAIs for GL 04-02 Closure (Email)
ML21068A3502021-03-0909 March 2021
Final Request for Additional Information for Reactor Coolant System (RCS) and Pressure and Tempature Limits Report(Ptlr) TS LAR
ML21053A0252021-02-20020 February 2021
NRR E-mail Capture - Request for Additional Information (Rais) - LaSalle Request for Exemption from Pre-Access Drug and Alcohol Testing
ML21015A5762021-01-14014 January 2021
Final RAIs for Steam Generator 180 Day Tube Inspection Report
ML21007A3732021-01-0707 January 2021
NRR E-mail Capture - (External_Sender) (External) Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff,
ML21004A1442020-12-30030 December 2020
NRR E-mail Capture - Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff
ML20290B0082020-10-0808 October 2020
Draft Request for Additional Information - Steam Generator Letter
ML20127H8672020-05-0606 May 2020
NRR E-mail Capture - Beaver Valley, Davis-Besse, and Perry - Request for Additional Information Regarding Request for Exemptions from Part 73 Security Requalification Requirements
ML20072N0402020-03-12012 March 2020
Request for Additional Information - Control Envelope Habitability LAR
ML19192A2222019-07-18018 July 2019
Request for Additional Information Regarding Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
ML19143A0732019-05-29029 May 2019
FENOC Fleet - Beaver Valley, Units 1 and 2; Davis-Besse, Unit 1, Perry, Unit 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action; Application for Order Consenting to License Transfer and Conforming Amendments
ML18242A3642018-08-29029 August 2018
Request for Additional Information (Final) -Steam Generator Technical Specification LAR
ML18102B0852018-04-12012 April 2018
NRR E-mail Capture - Follow-up Request for Additional Information (RAI) FENOC FLEET-- Exemption Request for a Physical Barrier Requirement for Beaver
ML18043A0102018-02-0909 February 2018
NRR E-mail Capture - FENOC--MG0010-MG0011, MG-0012, MG0013-- Request for Additional Information (RAI) - Exemption Request Security Barrier in Physical Plans
ML18024B3642018-01-24024 January 2018
NRR E-mail Capture - Beaver Valley 10 CFR 50.54(f) - NTTF 2.1 SPRA Review
ML18019A0722018-01-18018 January 2018
NRR E-mail Capture - Beaver Valley Unit No. 1: Request for Additional Information - Modified Rtpts Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule
ML17353A1582017-12-19019 December 2017
NRR E-mail Capture - Request for Additional Information: Beaver Valley Unit No. 1 - Proposed Alternative Request, 1-TYP-4-BA-01
ML17352B2612017-12-18018 December 2017
NRR E-mail Capture - Request for Additional Information: Beaver Valley Unit No. 1 - Proposed Alternative Request, 1-TYP-4-BA-01
ML17303B1582017-11-0707 November 2017
FENOC-Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, Perry Nuclear Power Plant Unit 1 - Generic Letter 2016-01, Request for Supplemental Information
ML17256A2502017-09-13013 September 2017
NRR E-mail Capture - Beaver Valley Power Station Units 1&2: Request for Additional Information for Emergency Plan EAL Change to Adopt NEI 99-01, Rev. 6,
ML17220A2342017-08-0808 August 2017
E-mail Regarding Request for Additional Information for NFPA 805 License Amendment Request
ML17093A7622017-04-10010 April 2017
Request for Additional Information Regarding Emergency Action Level Scheme Change License Amendment Request
ML17031A0362017-02-0303 February 2017
Request for Additional Information Regarding Relief Request Numbers PR6 and PR7
ML16333A0162016-12-0202 December 2016
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
ML16147A2842016-06-14014 June 2016
Request for Additional Infomation Regarding Fall 2015 Refueling Steam Generator Tube Inspections
ML16071A1222016-04-0707 April 2016
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
ML16084A8442016-03-30030 March 2016
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
ML16060A0122016-02-29029 February 2016
FENOC - Email RAI to Licensee Regarding LAR for Changes to TS 5.3.1 CAC Nos. MF7118, MF7119, and MF7120
ML15320A4132015-11-24024 November 2015
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
ML15280A0742015-10-0909 October 2015
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
ML15279A1252015-10-0505 October 2015
Licensed Operator Positive for Fitness-for-Duty-Test
ML15181A2142015-07-14014 July 2015
Request for Additional Information Regarding License Amendment Request to Revise Steam Generator Technical Specifications to Reflect TSTF-510 and to Revise Alloy 800 Sleeve Technical Specifications (TAC Nos. MF6054 & MF6055)
ML15125A4162015-05-11011 May 2015
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 (TAC Nos. MF3301 & MF3302)
ML15016A4392015-01-20020 January 2015
Draft Request for Additional Information
ML15007A5582015-01-15015 January 2015
Request for Additional Information Steam Generator Inspection Reports
ML14218A7622014-12-11011 December 2014
RAI Request to Implement 10 CFR 50.61a Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events
ML14316A3902014-11-14014 November 2014
Request for Additional Information Review of Licensee Security Plans
2023-05-05
[Table view] |
Text
June 3, 2005 Mr. L. William Pearce Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO GENERIC LETTER 2004-02, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS (TAC NOS. MC4665 AND MC4666)
Dear Mr. Pearce:
By letter dated March 4, 2005, FirstEnergy Nuclear Operating Company (the licensee) provided the 90-day response to U. S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02 for Beaver Valley Power Station, Units 1 and 2. The GL requested the licensee perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function. Additionally, addressees were requested to submit to the NRC the information specified in the GL.
The NRC staff has completed its preliminary review of your response and has determined it needs additional information requested in the enclosure to complete our review.
This RAI requests additional information about your overall plans and schedules and not any information on detailed plans or extensive analyses. In light of this, please provide the additional information requested in the enclosure within 45 days of receipt of this letter.
If you have any questions, please call me at (301) 415-1402.
Sincerely,
/RA/
Timothy G. Colburn, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412
Enclosure:
Request for Additional Information cc w/encl: See next page
June 3, 2005 Mr. L. William Pearce Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO GENERIC LETTER 2004-02, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS (TAC NOS.
MC4665 AND MC4666)
Dear Mr. Pearce:
By letter dated March 4, 2005, FirstEnergy Nuclear Operating Company (the licensee) provided the 90-day response to U. S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02 for Beaver Valley Power Station, Units 1 and 2. The GL requested the licensee perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function. Additionally, addressees were requested to submit to the NRC the information specified in the GL.
The NRC staff has completed its preliminary review of your response and has determined it needs additional information requested in the enclosure to complete our review.
This RAI requests additional information about your overall plans and schedules and not any information on detailed plans or extensive analyses. In light of this, please provide the additional information requested in the enclosure within 45 days of receipt of this letter.
If you have any questions, please call me at (301) 415-1402.
Sincerely,
/RA/
Timothy G. Colburn, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC PDI-1 R/F RidsOgcRp RidsAcrsAcnwMailCenter RidsNrrDlpmLpdi1 (RLaufer) RidsNrrPMTColburn RidsNrrLADBaxley RidsRgnIMailCenter DCullison/DSolorio RidsNrrDlpmDpr RidsNrrDssaDpr MWebbRidsNrrLAMOBrien Accession No.: ML051530267 *RAI input from SPLB without any major change OFFICE PDIV-1/PM PDIV-1/LA DSSA/SPLB/SP PDI-1/PM PDIV-1/SC PDIII-2/PM PDIII-2/SC NAME MWebb/JHopkins DBaxley DCullison/DSolorio* TColburn DTerao/
GSuh DATE 6/2/2005 6/2/05 5/23/05 6/3/05 6/3/05 OFFICIAL RECORD COPY
Beaver Valley Power Station, Unit Nos. 1 and 2 cc:
Mary OReilly, Attorney Rich Janati, Chief FirstEnergy Nuclear Operating Company Division of Nuclear Safety FirstEnergy Corporation Bureau of Radiation Protection 76 South Main Street Department of Environmental Protection Akron, OH 44308 Rachel Carson State Office Building P.O. Box 8469 FirstEnergy Nuclear Operating Company Harrisburg, PA 17105-8469 Regulatory Affairs/Performance Improvement Mayor of the Borough of Shippingport Larry R. Freeland, Manager P O Box 3 Beaver Valley Power Station Shippingport, PA 15077 Post Office Box 4, BV-A Shippingport, PA 15077 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Commissioner James R. Lewis 475 Allendale Road West Virginia Division of Labor King of Prussia, PA 19406 749-B, Building No. 6 Capitol Complex Resident Inspector Charleston, WV 25305 U.S. Nuclear Regulatory Commission Post Office Box 298 Director, Utilities Department Shippingport, PA 15077 Public Utilities Commission 180 East Broad Street FirstEnergy Nuclear Operating Company Columbus, OH 43266-0573 Beaver Valley Power Station ATTN: R. G. Mende, Director Director, Pennsylvania Emergency Work Management (BV-IPAB)
Management Agency Post Office Box 4 2605 Interstate Dr. Shippingport, PA 15077 Harrisburg, PA 17110-9364 FirstEnergy Nuclear Operating Company Ohio EPA-DERR Beaver Valley Power Station ATTN: Zack A. Clayton Mr. B. F. Sepelak Post Office Box 1049 Post Office Box 4, BV-A Columbus, OH 43266-0149 Shippingport, PA 15077 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 J. H. Lash, Plant Manager (BV-IPAB)
FirstEnergy Nuclear Operating Company Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077
REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 2004-02, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-334 AND 50-412 By letter dated March 4, 2005, FirstEnergy Nuclear Operating Company (the licensee) provided the 90-day response to U. S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02 for Beaver Valley Power Station, Units 1 and 2. The GL requested that addressees perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function. Additionally, addressees were requested to submit to the NRC the information specified in the GL. The staff has completed its preliminary review of your response and has determined it needs the following additional information to complete our review:
As a result of the review of the 90-day responses for all licensees and recent discussions with industry, the staff is concerned that some licensees may be delaying the evaluation of chemical and downstream effects until after the September 1, 2005, due date for the next response to the GL. This would result in an incomplete response and is not in accordance with the schedule in the GL. Your 90-day response indicated that your analysis will be completed by September 1, 2005, but did not discuss the evaluation of chemical and downstream effects.
Although the GL did not specifically request that the evaluation of chemical and downstream effects be discussed in the 90-day response, please discuss your plans and schedule for evaluating chemical and downstream effects and verify whether your September 1, 2005, response will include an evaluation of these effects.
ENCLOSURE