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| | number = ML100190320 | | | number = ML100190320 |
| | issue date = 01/26/2010 | | | issue date = 01/26/2010 |
| | title = Arkansas Nuclear One, Units 1 & 2 - Generic Letter 2004-02 Supplemental Response | | | title = Generic Letter 2004-02 Supplemental Response |
| | author name = Kalyanam N K | | | author name = Kalyanam N |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = | | | addressee name = |
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| | page count = 3 | | | page count = 3 |
| | project = TAC:MC4663, TAC:MC4664 | | | project = TAC:MC4663, TAC:MC4664 |
| | stage = Supplement | | | stage = Other |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:}} | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 26, 2010 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc. |
| | 1448 S.R. 333 Russellville, AR 72802 SUB~IECT: ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 - GENERIC LETTER 2004-02 SUPPLEMENTAL RESPONSE (TAC NOS. MC4663 AND MC4664) |
| | |
| | ==Dear Sir or Madam:== |
| | |
| | By letters dated February 28, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML080710544), September 15,2008 (ADAMS Accession No. ML082700499), and September 24,2009 (ADAMS Accession No. ML092720684), you submitted supplemental responses to U.S. Nuclear Regulatory Commission's (NRC's) Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors," for Arkansas Nuclear One, Units 1 and 2 (ANO 1 and 2). The NRC staff has reviewed your submittals with a process that involved a detailed review by a team of 10 subject matter experts, with a focus on the review as described in the NRC's "Content Guide for Generic Letter 2004-02 Supplemental Responses" (ADAMS Accession No. ML073110389). The review process also included, as necessary, a separate "holistic" review of your submittal informed by inputs from the subject matter experts that focused on whether you have demonstrated overall that your corrective actions for GL 2004-02 are adequate. |
| | We have no further questions at this time regarding your completion of corrective actions for GL 2004-02. In large part this conclusion is based on your September 24,2009, submittal, which addressed the NRC staff's request for additional information conveyed by letter dated May 21,2009 (ADAMS Accession No. ML071190322). |
| | As you may be aware, we have not yet issued a final safety evaluation (SE) on Westinghouse Electric Corporation Topical Report, WCAP-16793-NP, "Evaluation of Long-Term Cooling Considering Particulate, Fibrous, and Chemical Debris in the Recirculating Fluid." Because your GL 2004-02 response refers to and relies on this topical report, we plan to defer issuance of a closure letter to ANO 1 and 2 for GL 2004-02 until the SE isissued for WCAP-16793 later in 2010 and we have assurance that the in-vessel downstream effects issue has been addressed for ANO 1 and 2. We request that you inform us, within 90 days of issuance of that SE, whether ANO 1 and 2 are bounded by the conditions and limitations in the topical report and the corresponding SE. If either ANO 1 or ANO 2 is not bounded by those documents, your submittal should describe actions you plan to take to satisfactorily address in-vessel downstream effects at the affected unit(s). |
| | |
| | -2 If you have any questions, please contact me at 301-415-1480 or via e-mail at kaly.kalyanam@nrc.gov. |
| | Sincerely, q~ |
| | N. Kaly Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-313 and 50-368 cc: Distribution via Listserv |
| | |
| | ML100190320 OFFICE NRRlLPL4/PM NRRlLPL4/LA NRRlDSS/SSIB/BC NRR/LPL4/BC NRRlLPL4/PM NAME NKalyanam .IBurkhardt MScott MMarkley CFLyon for NKalyanam DATE 1/21/10 1120/10 1/21/10 1/26/10 1/26/10}} |
Latest revision as of 04:32, 12 March 2020
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MONTHYEARML0515202862005-06-0202 June 2005 Request for Additional Information (RAI) Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors Project stage: RAI ML0603806242006-02-0909 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. Project stage: RAI ML0603805752006-02-0909 February 2006 RAI Re 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 ML0726904102007-11-0808 November 2007 Staff Observations of Arkansas Nuclear One, Unit 2, Strainer Testing for Generic Safety Issue 191 During August 13-14, 2007, Trip to Fauske and Associates (TAC No. MC4663 and MC4664) Project stage: Other 0CAN090801, GL 2004-02 Final Supplemental Response2008-09-15015 September 2008 GL 2004-02 Final Supplemental Response Project stage: Request ML0911903222009-05-21021 May 2009 Request for Additional Information, 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 ML0917508322009-06-26026 June 2009 Notice of Conference Call with Entergy Operations, Inc. to Discuss Draft Request for Additional Information for GL-2004-02 Sent to Arkansas Nuclear One, Units 1 and 2 on June 22, 2009 Project stage: Draft RAI ML0923706572009-09-0303 September 2009 Summary of Conference Call with Entergy Operations, Inc. on Draft Response to the RAI for GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Project stage: Draft RAI 0CAN090901, Arkansas, Units 1 and 2, Generic Letter 2004-02 Final Supplemental Response to Request for Additional Information2009-09-24024 September 2009 Arkansas, Units 1 and 2, Generic Letter 2004-02 Final Supplemental Response to Request for Additional Information Project stage: Supplement ML0932004602009-11-23023 November 2009 Request for Withholding Information from Public Disclosure - 8/3/2009 Affidavit Executed by J. Gresham, Westinghouse Project stage: Withholding Request Acceptance ML1001903202010-01-26026 January 2010 Generic Letter 2004-02 Supplemental Response Project stage: Other 2009-11-23
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Category:Letter
MONTHYEARML24295A1202024-10-21021 October 2024 Relief Request ANO2-RR-24-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 71 ML24185A2602024-10-0404 October 2024 Issuance of Amendment No. 335 to Revise Typographical Errors in Technical Specifications IR 05000368/20253012024-09-0909 September 2024 Notification of NRC Initial Operator Licensing Examination 05000368/2025301 ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification IR 05000313/20240112024-09-0505 September 2024 Comprehensive Engineering Team Inspection Report 05000313/2024011 and 05000368/2024011 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 ML24198A0722024-08-21021 August 2024 Correction to Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b IR 05000313/20240052024-08-21021 August 2024 Updated Inspection Plan for Arkansas Nuclear One – Units 1 and 2 (Report 05000313/2024005, 05000368/2024005) ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 IR 05000313/20240022024-08-0606 August 2024 Integrated Inspection Report 05000313/2024002 and 05000368/2024002 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification 05000313/LER-2024-001, Source Range Nuclear Instrument Failure Resulting in Condition Prohibited by Technical Specifications2024-07-0101 July 2024 Source Range Nuclear Instrument Failure Resulting in Condition Prohibited by Technical Specifications ML24101A1792024-06-25025 June 2024 Issuance of Amendment No. 333 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24143A0632024-05-22022 May 2024 Notification of Inspection (NRC Inspection Report 05000368/2024003) and Request for Information IR 05000313/20240012024-05-0808 May 2024 Integrated Inspection Report 05000313/2024001 and 05000368/2024001 ML24128A2472024-05-0808 May 2024 Project Manager Assignment ML24017A2982024-04-18018 April 2024 Summary of Regulatory Audit Regarding the License Amendment Request to Revise Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML24107A0282024-04-17017 April 2024 Notification of Comprehensive Engineering Team Inspection (05000313/2024011 and 05000368/2024011) and Request for Information ML24086A5412024-04-10010 April 2024 Authorization of Request for Alternative ANO1-ISI-037 Regarding Extension of Reactor Vessel Inservice Inspection Interval IR 05000313/20244042024-04-0808 April 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000313/2024404 and 05000368/2024404) IR 05000313/20244022024-04-0808 April 2024 Security Baseline Inspection Report 05000313/2024402 and 05000368/2024402 (Full Report) ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24031A6442024-03-14014 March 2024 Issuance of Amendment No. 282 to Modify Technical Specification 3.3.1, Reactor Pressure System (RPS) Instrumentation, Turbine Trip Function on Low Control Oil Pressure ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24102A1342024-03-12012 March 2024 AN1-2024-03 Post Exam Submittal IR 05000313/20230062024-02-28028 February 2024 Annual Assessment Letter for Arkansas Nuclear One- Units 1 and 2 Report 05000313/2023006 and 05000368/2023006 IR 05000313/20230042024-02-0808 February 2024 Integrated Inspection Report 05000313/2023004 and 05000368/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023002 ML24012A0502024-02-0202 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0054 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24017A1582024-01-17017 January 2024 Submittal of Emergency Plan Revision 50 IR 05000313/20234202024-01-10010 January 2024 Security Baseline Inspection Report 05000313/2023420 and 05000368/2023420 IR 05000313/20234022024-01-0202 January 2024 Security Baseline Inspection Report 05000313/2023402 and 05000368/2023402 ML23354A0022023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment IR 05000313/20234052023-12-12012 December 2023 – Security Baseline Inspection Report 05000313/2023405 and 05000368/2023405 ML23341A0832023-12-11011 December 2023 – Material Control and Accounting Program Inspection Report 05000313/368/2023404- Cover Letter ML23305A0922023-12-0707 December 2023 – Summary of Regulatory Audit Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23325A1412023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000313/20230032023-11-21021 November 2023 Revised - ANO Revised Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/ 2023001 ML23324A0172023-11-16016 November 2023 Submittal of Amendment 31 to Safety Analysis Report ML23243B0452023-11-13013 November 2023 Request for Withholding Information from Public Disclosure ML23313A0962023-11-13013 November 2023 Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023001 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV 2024-09-09
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 26, 2010 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 SUB~IECT: ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 - GENERIC LETTER 2004-02 SUPPLEMENTAL RESPONSE (TAC NOS. MC4663 AND MC4664)
Dear Sir or Madam:
By letters dated February 28, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML080710544), September 15,2008 (ADAMS Accession No. ML082700499), and September 24,2009 (ADAMS Accession No. ML092720684), you submitted supplemental responses to U.S. Nuclear Regulatory Commission's (NRC's) Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors," for Arkansas Nuclear One, Units 1 and 2 (ANO 1 and 2). The NRC staff has reviewed your submittals with a process that involved a detailed review by a team of 10 subject matter experts, with a focus on the review as described in the NRC's "Content Guide for Generic Letter 2004-02 Supplemental Responses" (ADAMS Accession No. ML073110389). The review process also included, as necessary, a separate "holistic" review of your submittal informed by inputs from the subject matter experts that focused on whether you have demonstrated overall that your corrective actions for GL 2004-02 are adequate.
We have no further questions at this time regarding your completion of corrective actions for GL 2004-02. In large part this conclusion is based on your September 24,2009, submittal, which addressed the NRC staff's request for additional information conveyed by letter dated May 21,2009 (ADAMS Accession No. ML071190322).
As you may be aware, we have not yet issued a final safety evaluation (SE) on Westinghouse Electric Corporation Topical Report, WCAP-16793-NP, "Evaluation of Long-Term Cooling Considering Particulate, Fibrous, and Chemical Debris in the Recirculating Fluid." Because your GL 2004-02 response refers to and relies on this topical report, we plan to defer issuance of a closure letter to ANO 1 and 2 for GL 2004-02 until the SE isissued for WCAP-16793 later in 2010 and we have assurance that the in-vessel downstream effects issue has been addressed for ANO 1 and 2. We request that you inform us, within 90 days of issuance of that SE, whether ANO 1 and 2 are bounded by the conditions and limitations in the topical report and the corresponding SE. If either ANO 1 or ANO 2 is not bounded by those documents, your submittal should describe actions you plan to take to satisfactorily address in-vessel downstream effects at the affected unit(s).
-2 If you have any questions, please contact me at 301-415-1480 or via e-mail at kaly.kalyanam@nrc.gov.
Sincerely, q~
N. Kaly Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-313 and 50-368 cc: Distribution via Listserv
ML100190320 OFFICE NRRlLPL4/PM NRRlLPL4/LA NRRlDSS/SSIB/BC NRR/LPL4/BC NRRlLPL4/PM NAME NKalyanam .IBurkhardt MScott MMarkley CFLyon for NKalyanam DATE 1/21/10 1120/10 1/21/10 1/26/10 1/26/10