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| | number = ML110460388 | | | number = ML110460388 |
| | issue date = 02/23/2011 | | | issue date = 02/23/2011 |
| | title = Oconee Nuclear Station, Units 1, 2, & 3, Generic Letter 2008-01 Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Request for Additional Information | | | title = Generic Letter 2008-01 Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Request for Additional Information |
| | author name = Stang J F | | | author name = Stang J |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Gillespie T P | | | addressee name = Gillespie T |
| | addressee affiliation = Duke Energy Carolinas, LLC | | | addressee affiliation = Duke Energy Carolinas, LLC |
| | docket = 05000269, 05000270, 05000287 | | | docket = 05000269, 05000270, 05000287 |
| | license number = DPR-038, DPR-047, DPR-055 | | | license number = DPR-038, DPR-047, DPR-055 |
| | contact person = Stang J F, NRR/DORL, 415-1345 | | | contact person = Stang J, NRR/DORL, 415-1345 |
| | case reference number = TAC MD7852, TAC MD7853, TAC MD7854 | | | case reference number = TAC MD7852, TAC MD7853, TAC MD7854 |
| | document type = Request for Additional Information (RAI), Letter | | | document type = Request for Additional Information (RAI), Letter |
| | page count = 4 | | | page count = 4 |
| | | project = TAC:MD7852, TAC:MD7853, TAC:MD7854 |
| | | stage = RAI |
| }} | | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 23, 2011 Mr. Preston Gillespie Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672 |
| | |
| | ==SUBJECT:== |
| | OCONEE NUCLEAR STATION, UNITS 1,2, AND 3, GENERIC LETTER 2008-01, "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS," REQUEST FOR ADDITIONAL INFORMATION (RAI) (TAC NOS. MD7852, MD7853, AND MD7854) |
| | |
| | ==Dear Mr. Gillespie:== |
| | |
| | Generic Letter (GL) 2008-01, "Managing Gas Accumulation In Emergency Core Cooling, Decay Heat Removal, And Containment Spray Systems," requests licensees to submit information to demonstrate that the emergency core cooling, decay heat removal, and containment spray systems are in compliance with the applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance. |
| | The Nuclear Regulatory Commission (NRC) has concluded that additional information is required to demonstrate that the subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance as stated in GL 2008-01. The NRC staff's RAI is enclosed. Unless otherwise agreed to, please submit all responses to these RAI questions within 30 days. |
| | If you have any questions, please call me at 301-415-1345. |
| | Sincerely, ~ |
| | C\ \L, ~ |
| | r ~::g, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287 |
| | |
| | ==Enclosure:== |
| | |
| | RAI cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION (RAI) |
| | GENERIC LEITER (Gl) 2008-01. "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING. DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" OCONEE NUCLEAR STATION. UNITS 1.2. AND 3 There have been several public meetings with Nuclear Energy Institute (NEI) and industry on the topic of GL 2008-01 "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Contain Spray Systems." The U.S. Nuclear Regulatory Commission (NRC) staff has continued to update its guidance to inspectors as new information becomes available; the most recent revision is Reference 3. At a June 2, 2010, public meeting (Meeting Summary, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML101650201)) and in Reference 4, the NRC and industry agreed on various void criteria including the Froude numbers required to credit dynamic venting. |
| | Reference 3, Section 1.4.3 states, "At NFR::; 0.65, some gas may be transported and if NFR ~ 2.0, all gas will be carried out of a pipe with the flowing water. Time to clear gas from a pipe for 0.8 < |
| | NFR < 2.0 is a function of flow rate. Dynamic venting may not be assumed effective for NFR < 0.8. |
| | Time to clear gas as a function of time will be addressed in a later revision of this document when we have received and evaluated test data that supports clearance behavior." |
| | Reference 1 states, "Dynamic venting is credited (Froude number of > 0.55 for horizontal piping runs and >1.0 for vertical piping runs)." |
| | Reference 2 clarifies this by stating, "The criterion used was derived from WCAP-16631-NP." |
| | Reference 2 went on to say, "It is also recognized that gas may be removed from piping at lower Froude numbers if given sufficient duration. As ongoing validation, Post Dynamic Flush Ultrasonic Test (UTs) and/or Program Monitoring UTs are conducted at numerous points on the subject systems to verify the dynamically flushed piping remains sufficiently full." |
| | RAI 1: Please provide justification for crediting dynamic venting with Froude numbers between 0.55 and 0.8. |
| | RAI 2: Please verify the statement that UT is used to verify that dynamically flushed piping remains sufficiently full with respect to such areas as vertical U-tube heat exchangers and valve internal configurations where UT cannot be used if dynamic flushing involves these locations. If dynamic flushing is not used for these areas, then describe how they are determined to be sufficiently full. |
| | REFERENCES |
| | : 1. Harrall, T., "Duke Energy Carolinas, LLC (Duke); Oconee Nuclear Station, Units 1,2 & 3, Docket Nos. 50-269, 50-270, 50-287; McGuire Nuclear Station, Units 1 & 2, Docket Nos. |
| | 50-369,50-370; Catawba Nuclear Station, Units 1 & 2, Docket Nos. 50-413, 50-414; Generic Letter 2008-01, 9-Month Response," Letter to Document Control Desk, NRC, Enclosure |
| | |
| | - 2 from Vice President, Plant Support, Duke Energy Carolinas. LLC. , October 13. 2008 (ADAMS Accession No. ML082900490). |
| | : 2. Baxter. Dave, "Generic Letter 2008-01 RAI Response." Letter from Vice President Oconee Nuclear Station. September 24, 2010 (ADAMS Accession No. ML102720395). |
| | : 3. "Guidance To NRC/NRRlDSS/SRXB Reviewers for Writing TI Suggestions for the Region Inspections." December 6.2010 (ADAMS Accession No. ML103400347). |
| | : 4. Lyon. Warren. "Interim Clean Section 1 4 (3)." e-mail toJamesRiley.NEI. June 7, 2010 (ADAMS Accession No. ML102090074). |
| | |
| | ML110460388 *By Memo Dated OFFIC E NRR/LPL2-1/PM NRR/LPL2-1/LA NRRISRXB/BC NRRlLPL2-1/BC NRRlLPL2-lIPM NAME JStang MO'Brien AUlses |
| | * GKulesa JStang DATE 2/23/11 2123111 02108/11 2123111 2123111}} |
Letter Sequence RAI |
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MONTHYEARML0816905942008-07-0808 July 2008 GL-08-001, Managing Gas Accumulation in Emergency Core Cooling Decay Heat Removal Project stage: Other ML0825405162008-09-25025 September 2008 Generic Letter 2008-01. Managing Gas Accumulation in Emergency Core Cooling Decay Heat Removal and Containment Spray Project stage: Other ML1023600532010-08-25025 August 2010 Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Request for Additional Information (RAI) Project stage: RAI ML1104603882011-02-23023 February 2011 Generic Letter 2008-01 Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Request for Additional Information Project stage: RAI 2008-09-25
[Table View] |
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Category:Request for Additional Information (RAI)
MONTHYEARML24197A2302024-07-15015 July 2024 Request for Additional Information - Oconee SLRA - Annual Update ML24192A1312024-07-15015 July 2024 Licensed Operator Positive Fitness-For-Duty Test ML24190A0462024-07-0505 July 2024 Notification of Inspection and Request for Information ML24086A3772024-03-26026 March 2024 Request for Additional Information License Amendment Request to Revise Technical Specification 5.5.2 ML23284A3322023-10-11011 October 2023 Request for Additional Information Alternative Request (RA-22-0174) (L-2022-LLR-0060) ML23178A0682023-07-0303 July 2023 Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1 ML23156A2452023-06-0505 June 2023 Audit Summary and RAI-RCI - Revised Enclosure ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23095A0052023-04-0404 April 2023 002 Radiation Safety Baseline Inspection Information Request ML23086C0362023-03-27027 March 2023 Request for Additional Information Steam Generator Tube Inspection Report (03R31) ML23039A1632023-02-0808 February 2023 Requalification Program Inspection ML23038A1832023-02-0707 February 2023 Request for Additional Information Alternative Request (RA-22-0174) to Use ASME Code Case N-752 ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final ML22251A2902022-09-0808 September 2022 Request for Additional Information Additional Mode Change Limitations Applicable to the Adoption of Technical Specifications Tasks Force Traveler (TSTF) No. 359, Revision 9 ML22234A0052022-08-30030 August 2022 SLRA - Feedback for RAI B2.1.7-4a to Duke - August 16, 2022 ML22157A0042022-06-0606 June 2022 10 CFR 50.59 Inspection Initial Information Request ML22157A0012022-06-0101 June 2022 Email from NRC (Angela Wu) to Duke (Paul Guill) - Oconee SLRA - Additional NRC Comments on RAI 4.6.1-1a ML22154A2122022-06-0101 June 2022 SLRA - 2nd Round RAI B2.1.7-4b ML22124A1632022-05-0303 May 2022 (Public) Oconee SLRA - 2nd Round RAI B2.1.7-4a ML22124A1612022-05-0303 May 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B2.1.7-4a ML22122A0182022-04-28028 April 2022 Attachment: Oconee SLRA - 2nd Round RAI B2.1.9-2a ML22122A0192022-04-28028 April 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B2.1.9-2a ML22122A1312022-04-27027 April 2022 (Public) Oconee SLRA - 2nd Round RAIs - Trp 76 (Irradiation Structural) - FE 3.5.2.2.2.6 Redacted ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22112A0072022-04-20020 April 2022 Email from Marieliz Johnson (NRC) to Steve Snider (Duke) - Oconee SLRA - Request for Confirmation of Information 3.5.2.2.2.6-L ML22113A0092022-04-20020 April 2022 Attachment: Oconee SLRA - Final RAI 3.1.2-1 ML22081A0062022-03-21021 March 2022 Attachment: Oconee SLRA - 2nd Round RAI B4.1-3 ML22081A0052022-03-21021 March 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B4.1-3 ML22080A0772022-03-16016 March 2022 SLRA - RAI Set 4 (2nd Round Rais) ML22069A0012022-03-0808 March 2022 Attachment: Oconee SLRA - Final Requests for Confirmation of Information - Set 4 ML22063A4502022-03-0404 March 2022 Request for Additional Information Application to Revise TS 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required Inoperable LPSW Pump RA-22-0036, Responses to NRC Request for Additional Information Set 22022-02-14014 February 2022 Responses to NRC Request for Additional Information Set 2 ML22019A1032022-01-18018 January 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Requests for Additional Information - Set 3 ML22019A2442022-01-18018 January 2022 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000269/2022010, 05000270/2022010, 05000287/2022010) and Request for Information (RFI) ML22019A1042022-01-18018 January 2022 Attachment: Oconee SLRA - Final Requests for Additional Information - Set 3 ML22012A0422022-01-11011 January 2022 SLRA - Final Requests for Additional Information - Set 2 ML22010A1132022-01-0505 January 2022 SLRA - RCIs - Set 3 ML21333A0392021-11-29029 November 2021 RP Inspection Document Request ML21327A2782021-11-23023 November 2021 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Final RAIs (Set 1 and 2nd Round RAI B2.1.27-1a) ML21327A2792021-11-23023 November 2021 SLRA - Final Requests for Additional Information - Set 1 ML21327A2802021-11-23023 November 2021 SLRA - Final 2nd Round RAI - RAI B2.1.27-1a ML21330A0192021-11-23023 November 2021 Attachment: Oconee SLRA - Final Requests for Confirmation of Information - Set 2 ML21313A2342021-11-0404 November 2021 Attachment: Oconee SLRA - Final Requests for Confirmation of Information - Set 1 ML21274A0682021-10-0101 October 2021 Request for Additional Information Alternative Request (RA-20-0334) Regarding Use of an Alternative to the ASME Code Case N-853 Acceptance Criteria ML21273A0492021-09-30030 September 2021 Request for Additional Information Alternative Request (ON-RPI-OMN-28) to Use Code Case OMN-28 ML21271A5892021-09-28028 September 2021 SLRA - RAI B2.1.27-1 (Draft) ML21271A5902021-09-28028 September 2021 SLRA - RAI B2.1.27-1 (Final) ML21271A5882021-09-22022 September 2021 SLRA - Request for Additional Information B2.1.27-1 - Email from Angela Wu (NRC) to Steve Snider (Duke) ML21217A1912021-08-0505 August 2021 Request for Additional Information Alternative Request (RA-20-0334) Regarding Use of an Alternative to the ASME Code Case N-853 Acceptance Criteria 2024-07-05
[Table view] Category:Letter
MONTHYEAR05000269/LER-2022-001-01, Ultrasonic Examination Indication Identifies Degraded Reactor Coolant System Pressure Boundary2024-11-0707 November 2024 Ultrasonic Examination Indication Identifies Degraded Reactor Coolant System Pressure Boundary ML24305A1492024-11-0404 November 2024 Review of the Fall 2023 Steam Generator Tube Inspection Report (O2R31) IR 05000269/20240032024-10-31031 October 2024 Integrated Inspection Report 05000269/2024003 and 05000270/2024003 and 05000287/2024003 (2) ML24255A3322024-10-16016 October 2024 SLRA - Revised SE Letter ML24297A6172024-10-11011 October 2024 PCA Letter to NRC Oconee Hurricane Helene ML24269A0912024-10-0909 October 2024 Request for Withholding Information from Public Disclosure IR 05000269/20240052024-08-26026 August 2024 Updated Inspection Plan for Oconee Nuclear Station, Units 1, 2 and 3 (Report 05000269/2024005, 05000270/2024005, and 05000287-2024005) ML24145A1782024-08-26026 August 2024 Issuance of Amendment Nos. 430, 432, and 431, to TS 5.5.2, Containment Leakage Rate Testing Program for a one-time Extension of the Type a Leak Rate Test Frequency ML24220A1092024-08-0808 August 2024 – Operator Licensing Examination Approval 05000269/2024301, 05000270/2024301, and 05000287/2024301 05000287/LER-2024-001, Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation2024-08-0202 August 2024 Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation IR 05000269/20240022024-07-25025 July 2024 Integrated Inspection Report 05000269/2024002 and 05000270/2024002 and 05000287/2024002 ML24192A1312024-07-15015 July 2024 Licensed Operator Positive Fitness-For-Duty Test ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24183A2352024-06-29029 June 2024 Update 3 to Interim Report Regarding a Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 ML24179A1102024-06-27027 June 2024 Submittal of Updated Final Safety Analysis Report Revision 30, Technical Specifications Bases Revisions, Selected Licensee Commitment Revisions, 10 CFR 50.59 Evaluation Summary Report, and 10 CFR 54.37 Update, and Notification ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000269/20240012024-05-0303 May 2024 Integrated Inspection Report 05000269/2024001, 05000270/2024001 and 05000287/2024001 IR 05000269/20244022024-04-24024 April 2024 Security Baseline Inspection Report 05000269/2024402 and 05000270/2024402 and 05000287/2024402 ML24108A0792024-04-16016 April 2024 EN 57079 Paragon Energy Solutions Email Forwarding Part 21 Interim Report Re Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 IR 05000269/20244012024-03-28028 March 2024 – Security Baseline Inspection Report 05000269-2024401 and 05000270-2024401 and 05000287-2024401 ML24088A3052024-03-25025 March 2024 Fws to NRC, Agreement with Nlaa Determination for Tricolored Bat for Oconee Lr 05000287/LER-2023-002, Passive Containment Isolation Device Inoperability Results in Operation or Condition Prohibited by Technical Specifications2024-02-29029 February 2024 Passive Containment Isolation Device Inoperability Results in Operation or Condition Prohibited by Technical Specifications 05000270/LER-2023-001, Inappropriate Procedural Guidance for Planned Online Maintenance Results in Event or Condition That Could Have Prevented Fulfillment of a Safety Function Licensee2024-02-29029 February 2024 Inappropriate Procedural Guidance for Planned Online Maintenance Results in Event or Condition That Could Have Prevented Fulfillment of a Safety Function Licensee IR 05000269/20230062024-02-28028 February 2024 Annual Assessment Letter for Oconee Nuclear Station Units 1, 2 and 3 - (NRC Inspection Report 05000269/2023006, 05000270/2023006, and 05000287/2023006) ML24045A3032024-02-16016 February 2024 Ltr. to John Creel Chief Edisto Natchez-Kusso Tribe of Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2952024-02-16016 February 2024 Ltr. to Chuck Hoskin, Jr, Principal Chief Cherokee Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3072024-02-16016 February 2024 Ltr. to Pete Parr Chief Pee Dee Indian Tribe Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3012024-02-16016 February 2024 Ltr. to Harold Hatcher Chief the Waccamaw Indian People Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3022024-02-16016 February 2024 Ltr. to Joe Bunch United Keetoowah Band of Cherokee Indians in Ok Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24030A0052024-02-16016 February 2024 Ltr. to Brian Harris, Chief, Catawba Indian Nation; Re., Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2972024-02-16016 February 2024 Ltr. to Dexter Sharp Chief Piedmont American Indian Assoc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2992024-02-16016 February 2024 Ltr. to Eric Pratt Chief the Santee Indian Organization Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2962024-02-16016 February 2024 Ltr. to David Hill Principal Chief Muscogee Creek Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3082024-02-16016 February 2024 Ltr. to Ralph Oxendine Chief Sumter Tribe of Cheraw Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3062024-02-16016 February 2024 Ltr. to Michell Hicks, Principal Chief Eastern Band of Cherokee Re Oconee Nuclear Station Units 1,2, and 3 Section 106 ML24045A3052024-02-16016 February 2024 Ltr. to Louis Chavis Chief Beaver Creek Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2942024-02-16016 February 2024 Ltr. to Carolyn Chavis Bolton Chief Pee Dee Indian Nation of Upper Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3042024-02-16016 February 2024 Ltr. to Lisa M. Collins Chief the Wassamasaw Tribe of Varnertown Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24030A5212024-02-13013 February 2024 Letter to Elizabeth Johnson, Director, SHPO; Re Oconee Nuclear Stations Units 1, 2, and 3 Section 106 ML24011A1482024-02-13013 February 2024 Letter to Steven M. Snider-Oconee Nuclear Sta, Unites 1,2 & 3 Notice of Avail of the Draft Site-Specific Supp. 2, 2nd Renewal to the Generic EIS for Lic. Renew of Nuclear Plants ML24011A1532024-02-13013 February 2024 Letter to Tracy Watson EPA-Oconee Nuclear Sta, Unites 1, 2 & 3 Notice of Avail of the Draft Site-Specific Supp. 2, 2nd Renewal to the Generic EIS for Lic. Renew of Nuclear Plants IR 05000269/20230042024-02-13013 February 2024 Integrated Inspection Report 05000269/2023004, 05000270/2023004, and 05000287/2023004; and Inspection Report 07200040/2023001 ML24019A1442024-02-13013 February 2024 Letter to Reid Nelson, Executive Director, Achp; Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staff’S Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000269/20243012024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000269/2024301, 05000270/2024301, and 05000287/2024301 ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 2024-08-08
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 23, 2011 Mr. Preston Gillespie Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1,2, AND 3, GENERIC LETTER 2008-01, "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS," REQUEST FOR ADDITIONAL INFORMATION (RAI) (TAC NOS. MD7852, MD7853, AND MD7854)
Dear Mr. Gillespie:
Generic Letter (GL) 2008-01, "Managing Gas Accumulation In Emergency Core Cooling, Decay Heat Removal, And Containment Spray Systems," requests licensees to submit information to demonstrate that the emergency core cooling, decay heat removal, and containment spray systems are in compliance with the applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance.
The Nuclear Regulatory Commission (NRC) has concluded that additional information is required to demonstrate that the subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance as stated in GL 2008-01. The NRC staff's RAI is enclosed. Unless otherwise agreed to, please submit all responses to these RAI questions within 30 days.
If you have any questions, please call me at 301-415-1345.
Sincerely, ~
C\ \L, ~
r ~::g, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287
Enclosure:
RAI cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION (RAI)
GENERIC LEITER (Gl) 2008-01. "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING. DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" OCONEE NUCLEAR STATION. UNITS 1.2. AND 3 There have been several public meetings with Nuclear Energy Institute (NEI) and industry on the topic of GL 2008-01 "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Contain Spray Systems." The U.S. Nuclear Regulatory Commission (NRC) staff has continued to update its guidance to inspectors as new information becomes available; the most recent revision is Reference 3. At a June 2, 2010, public meeting (Meeting Summary, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML101650201)) and in Reference 4, the NRC and industry agreed on various void criteria including the Froude numbers required to credit dynamic venting.
Reference 3, Section 1.4.3 states, "At NFR::; 0.65, some gas may be transported and if NFR ~ 2.0, all gas will be carried out of a pipe with the flowing water. Time to clear gas from a pipe for 0.8 <
NFR < 2.0 is a function of flow rate. Dynamic venting may not be assumed effective for NFR < 0.8.
Time to clear gas as a function of time will be addressed in a later revision of this document when we have received and evaluated test data that supports clearance behavior."
Reference 1 states, "Dynamic venting is credited (Froude number of > 0.55 for horizontal piping runs and >1.0 for vertical piping runs)."
Reference 2 clarifies this by stating, "The criterion used was derived from WCAP-16631-NP."
Reference 2 went on to say, "It is also recognized that gas may be removed from piping at lower Froude numbers if given sufficient duration. As ongoing validation, Post Dynamic Flush Ultrasonic Test (UTs) and/or Program Monitoring UTs are conducted at numerous points on the subject systems to verify the dynamically flushed piping remains sufficiently full."
RAI 1: Please provide justification for crediting dynamic venting with Froude numbers between 0.55 and 0.8.
RAI 2: Please verify the statement that UT is used to verify that dynamically flushed piping remains sufficiently full with respect to such areas as vertical U-tube heat exchangers and valve internal configurations where UT cannot be used if dynamic flushing involves these locations. If dynamic flushing is not used for these areas, then describe how they are determined to be sufficiently full.
REFERENCES
- 1. Harrall, T., "Duke Energy Carolinas, LLC (Duke); Oconee Nuclear Station, Units 1,2 & 3, Docket Nos. 50-269, 50-270, 50-287; McGuire Nuclear Station, Units 1 & 2, Docket Nos.
50-369,50-370; Catawba Nuclear Station, Units 1 & 2, Docket Nos. 50-413, 50-414; Generic Letter 2008-01, 9-Month Response," Letter to Document Control Desk, NRC, Enclosure
- 2 from Vice President, Plant Support, Duke Energy Carolinas. LLC. , October 13. 2008 (ADAMS Accession No. ML082900490).
- 2. Baxter. Dave, "Generic Letter 2008-01 RAI Response." Letter from Vice President Oconee Nuclear Station. September 24, 2010 (ADAMS Accession No. ML102720395).
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ML110460388 *By Memo Dated OFFIC E NRR/LPL2-1/PM NRR/LPL2-1/LA NRRISRXB/BC NRRlLPL2-1/BC NRRlLPL2-lIPM NAME JStang MO'Brien AUlses
- GKulesa JStang DATE 2/23/11 2123111 02108/11 2123111 2123111