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| | number = ML15033A422 | | | number = ML15033A422 |
| | issue date = 02/18/2015 | | | issue date = 02/18/2015 |
| | title = Waterford Steam Electric Station, Unit 3 - Request for Additional Information Regarding the Request to Permanently Extend the Integrated Leak Rate Test Frequency to 15 Years (TAC No. MF4727) | | | title = Request for Additional Information Regarding the Request to Permanently Extend the Integrated Leak Rate Test Frequency to 15 Years |
| | author name = Orenak M D | | | author name = Orenak M |
| | author affiliation = NRC/NRR/DORL/LPLIV-2 | | | author affiliation = NRC/NRR/DORL/LPLIV-2 |
| | addressee name = | | | addressee name = |
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| | docket = 05000382 | | | docket = 05000382 |
| | license number = NPF-038 | | | license number = NPF-038 |
| | contact person = Orenak M D | | | contact person = Orenak M |
| | case reference number = TAC MF4727 | | | case reference number = TAC MF4727 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 6 | | | page count = 6 |
| | project = TAC:MF4727 | | | project = TAC:MF4727 |
| | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Vice President, Operations Entergy Operations, Inc. Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 February 18, 2015 SUBJECT: WATERFORD STEAM ELECTRIC STATION, UNIT 3 -REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REQUEST TO PERMANENTLY EXTEND THE INTEGRATED LEAK RATE TEST FREQUENCY TO 15 YEARS (TAC NO. MF4727) Dear Sir or Madam: By letter dated August 28, 2014 (Agencywide Documents Access and Management System *(ADAMS) Accession No. ML 14241A305), Entergy Operations, Inc., submitted a license amendment request (LAR) for Waterford Steam Electric Station, Unit 3, to change Technical Specification 6.15, "Containment Leakage Rate Testing Program," to allow a permanent extension of the Type A containment integrated leak rate test frequency from 1 O years to 15 years. The U.S. Nuclear Regulatory Commission staff has reviewed the LAR and has determined that additional information is needed to complete the review. Please provide the additio_nal information requested in the enclosure within 60 days of receipt of this letter. If you have any questions, please contact me at 301-415-3229 or via e-mail at Michael. Orenak@nrc.gov. Docket No. 50-382 Enclosure: Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, rJ} (NJv Michael D. Orenak, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE AMENDMENT REQUEST TO PERMANENTLY EXTEND THE INTEGRATED LEAK RATE TEST FREQUENCY TO 15 YEARS ENTERGY OPERATIONS, INC. WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382 By letter dated August 28, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14241A305), Entergy Operations, Inc. (Entergy, the licensee), submitted a license amendment request (LAR) to change Technical Specification (TS) 6.15, "Containment Leakage Rate Testing Program," for the Waterford Steam Electric Station, Unit 3 (WF3). The proposed change would allow a permanent extension of the Type A primary containment integrated leak rate test frequency from 1 O years to 15 years. The following questions were developed as a result of the U.S. Nuclear Regulatory Commission (NRC) staff's review of the licensee's LAR. NRC Regulatory Issue Summary 2007-06 dated March 22, 2007 (ADAMS Accession No. ML070650428), states that the NRC staff expects that the licensees fully address all scope elements with Regulatory Guide (RG) 1.200, Revision 2, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment [PRA] Results for Risk-Informed Activities," dated March 2009 (ADAMS Accessiqn No. ML090410014), by the end of its implementation period (i.e., one year after the issuance of Revision 2 of RG 1.200). Revision 2 of RG 1.200 endorses, with exceptions and clarifications, the combined American Society of Mechanical Engineers (ASME)/American Nuclear Society (ANS) PRA standard ASME/ANS RA-Sa-2009, "Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications." Given that the implementation date of RG 1.200, Revision 2, was April 2010, and the LAR was submitted in August 2014, identify any gaps between the WF3 internal events PRA model used in this application and RG 1.200, Revision 2, requirements that are relevant to this LAR. Additionally, address the technical adequacy requirements of RG 1.200, Revision 2, that are applicable to this LAR, or explain why addressing the requirements would have no impact on this application. Enclosure | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 18, 2015 Vice President, Operations Entergy Operations, Inc. |
| -2 -Section 4.5.2 of the LAR states, in part, that "[t]he WF3 Fire PRA (FPRA) model has undergone a Reg. Guide 1.200 Peer Review against Sections 2 and 3 of the ASME PRA Standard." The ASME PRA Standard RA-Sa-2009 contains ten parts, each with several sections. Clarify whether the above statement from the LAR refers to Sections 2 and 3 of Part 4, "Requirements for Fire At-Power PRA." If the Fire PRA has not been peer-reviewed against ASME/ANS RA-Sa-2009, clarify how the fire PRA was determined to be of sufficient quality for this application. Section 4.5.2 of the LAR states, in part, that "(t]he industry peer review of the updated PRA model has been performed. The updated PRA model meets ASME Capability Category II requirements by addressing gaps identified by the peer review." Provide a list of all supporting requirements from the peer-review relevant to this LAR for which the PRA did not meet the ASME/ANS RA-Sa-2009 Capability Category 1 supporting requirements. Explain why these gaps would not impact this specific application. For gaps that did not impact another application (e.g., National Fire Protection Association NFPA-805), describe why the finding does not impact this LAR. In the LAR, the licensee proposed to revise WF3, TS 6.15, as follows: A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(0) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in NEI 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR 50, Appendix J," dated October. 2008, except that the next Type A test performed after the May 21, 2005 Type A test shall be performed no later than May 20. 2020. The term "except that" in the above proposed TS wording gives the appearance that the extension of the next Type A test is an exception to the guidelines contained in NEI 94-01, Revision 2A (ADAMS Accession No. ML 100620847). Provide clarification for the term "except that." The NRC staff notes that this was identified for similar applications previously submitted for the NRC review and Entergy had provided clarification in letters dated January 20, 2011, for Arkansas Nuclear One, Unit 2, and March 11: 2014, for Arkansas Nuclear One, Unit 1 (ADAMS Accession Nos. ML 110210971 and ML 14070A399, respectively). RAI 5 Sections 4.0 and 4.3 of the LAR state that the ASME Boiler and Pressure Vessel (BPV) Code, Section XI, Subsection IWL, does not apply to WF3.
| | Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 |
| -3 -As described in Section 3.8 of the WF3 final s*afety analysis report, both the shield building and the containment vessel are supported on a common reinforced concrete foundation mat. The containment vessel is supported on the concrete fill, which transfers the loads by bearing to the foundation mat below. Subsection IWL provides the examination requirements for reinforced concrete Class CC . components. Considering that the containment vessel is supported on a concrete fill and a reinforced concrete foundation mat, provide clarification regarding the LAR's statement of Subsection IWL not being applicable to WF3. -Please provide information of instances, during implementation of the WF3 containment inservice inspection program, where existence of, or potential for, degraded conditions in inaccessible areas were identified and evaluated based on conditions found in accessible areas, as required by 10 CFR 50.55a(b)(2)(viii)(E) and 10 CFR 50.55a(b)(2)(ix)(A). lfthere were any instances of such conditions, discuss the findings and corrective actions taken to disposition the findings. Section 9.2.3.2 of NEI 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," and Condition 2 in Section 4.1 of the NRC safety evaluation for NEl 94-01, Revision 2, require supplemental general visual inspections of accessible interior and exterior surfaces of the containment for structural deterioration that may affect the containment leak-tight integrity. These inspections must be conducted prior to each Type A test and during at least three other outages before the next Type A test if the interval for the Type A test has been extended to 15 years. Provide a schedule for a typical 15-year interval (between the last Type A test in 2005 and the proposed next Type A test in 2020), in a tabular format, of inservice inspections that were and will be performed on the containment vessel, and explain how it meets the requirements in Section 9.2.3.2 of NEI 94-01, Revision 2-A, and Condition 2 in Section 4.1 of the NRC safety evaluation NEI 94-01, Revision 2. Please include the inservice inspection intervals with the start date and end date of each inspection period, and the corresponding refueling outages. The LAR states that WF3 has three periods during each 10-year inservice inspection interval. Table 4-2 of the LAR presents the ASME BPV Code, Section XI, Subsection IWE, inspection results from 2003 to 2014. Please provide the following: a. The edition of the ASME BPV Code associated with each WF3 inservice i,nspection interval. b. It is not clear from the review of Table 4-2 of the LAR that 100 percent of the containment vessel accessible surface areas and the interior and exterior moisture barriers have been inspected since 2005. Please clarify or supplement the information
| | |
| -4 -in Table 4-2 to demonstrate that the requirements of Table IWE-2500-1 of the ASME BPV Code have been satisfied. Attachment 4 of the LAR states that Table 4-1 presents summaries of the results from the WF3 shield building interior and exterior structural inspections, which were performed during each refueling shutdown and prior to any integrated leak test. Contrary to this statement, Section 4.3 . of the LAR states that Table 4-1 presents summaries of the results from the WF3 containment building interior and exterior structural inspections, which were performed every three years and the shield building inspection was performed prior to any integrated leak test. Also, the dates included in Table 4-1 do not appear to support the statement in Attachment 4 that the WF3 shield building was inspected during each refueling outage. Please provide clarification. RAI 10 Table 4-2 of the LAR includes the results of the inspection of the containment vessel interior coating performed in 2003. Please discuss the highlights of findings from WF3 recent inspections of the containment vessel coating and actions taken to disposition them. RAI 11 Please discuss NRC Information Notice 2014-07, "Degradation of Leak-Chase Channel Systems for Floor Welds of Metal Containment Shell and Concrete Containment Metallic Liner," dated May 5, 2014 (ADAMS Accession No. ML 14070A114), as it may apply to.WF3. If applicable, discuss the operating experience, inspection results, and any corrective actions taken.
| | ==SUBJECT:== |
| * RAI 12 Please provide the following information: a. Percent of the total number of Type B tested components that are on 120-month extended performance-bas*ed test interval. b. Percent of the total number of Type C tested components that are on 60-month extended performance-based test interval.
| | WATERFORD STEAM ELECTRIC STATION, UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REQUEST TO PERMANENTLY EXTEND THE INTEGRATED LEAK RATE TEST FREQUENCY TO 15 YEARS (TAC NO. MF4727) |
| * Vice President, Operations Entergy Operations, Inc. February 18, 2015 Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 SUBJECT: | | |
| * WATERFORD STEAM ELECTRIC STATION, UNIT 3 -REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE AMENDMENT REQUEST TO PERMANENTLY EXTEND THE INTEGRATED LEAK RATE TEST FREQUENCY TO 15 YEARS (TAC NO. MF4727) Dear Sir or Madam: By letter dated August 28, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14241A305), Entergy Operations, Inc., submitted a license amendment request (LAR) for Waterford Steam Electric Station, Unit 3, to change Technical Specification 6.15, "Containment Leakage Rate Testing Program," to allow a permanent extension of the Type A primary containment integrated leak rate test frequency from 1 O years to 15 years.
| | ==Dear Sir or Madam:== |
| * The U.S. Nuclear Regulatory Commission staff has reviewed the LAR and has determined that additional information is needed to complete the review. Please provide the additional information requested in the enclosure within 60 days of receipt of this letter. If you have questions, please contact me at 301-415-3229 or via e-mail at Michael.Orenak@nrc.gov. Docket No. 50-382 Enclosure: Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL4-2 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDorllp14-2 Resource RidsNrrPMWaterford Resource ADAMS Accession No MLML 15033A422 OFFICE NRR/DORL/LPL4-2/PM NAME MOrenak DATE 2/10/15 OFFICE NRR/DE/EMCB/BC* NAME Tluoold DATE 1/28/15 Sincerely, IRA/ Michael D. Orenak, Project Manager PJant Licensing IV-2 and Dec9mmissioning Transition Branch . Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrLAPBlechman Resource. RidsRgn4MailCenter Resource RidsNrrDorlDpr Resource CFong, NRR FFarzam, NRR *via memo NRR/DORL/LPL4-2/LA NRR/DRA/APLA/BC* PBlechman HHamzehee 2/9/15 1/26/15 NRR/DORL/LPLIV-2/BC NRR/DORL/LPL4-2/PM MKhanna MOrenak 2/12/15 2/18/15 OFFICIAL RECORD COPY
| | |
| }} | | By letter dated August 28, 2014 (Agencywide Documents Access and Management System |
| | *(ADAMS) Accession No. ML14241A305), Entergy Operations, Inc., submitted a license amendment request (LAR) for Waterford Steam Electric Station, Unit 3, to change Technical Specification 6.15, "Containment Leakage Rate Testing Program," to allow a permanent extension of the Type A p~imary containment integrated leak rate test frequency from 1O years to 15 years. |
| | The U.S. Nuclear Regulatory Commission staff has reviewed the LAR and has determined that additional information is needed to complete the review. Please provide the additio_nal information requested in the enclosure within 60 days of receipt of this letter. |
| | If you have any questions, please contact me at 301-415-3229 or via e-mail at Michael. Orenak@nrc.gov. |
| | Sincerely, |
| | ~ rJ} (NJv Michael D. Orenak, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
| | |
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE AMENDMENT REQUEST TO PERMANENTLY EXTEND THE INTEGRATED LEAK RATE TEST FREQUENCY TO 15 YEARS ENTERGY OPERATIONS, INC. |
| | WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382 By letter dated August 28, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14241A305), Entergy Operations, Inc. (Entergy, the licensee), |
| | submitted a license amendment request (LAR) to change Technical Specification (TS) 6.15, "Containment Leakage Rate Testing Program," for the Waterford Steam Electric Station, Unit 3 (WF3). The proposed change would allow a permanent extension of the Type A primary containment integrated leak rate test frequency from 1O years to 15 years. |
| | The following questions were developed as a result of the U.S. Nuclear Regulatory Commission (NRC) staff's review of the licensee's LAR. |
| | NRC Regulatory Issue Summary 2007-06 dated March 22, 2007 (ADAMS Accession No. ML070650428), states that the NRC staff expects that the licensees fully address all scope elements with Regulatory Guide (RG) 1.200, Revision 2, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment [PRA] Results for Risk-Informed Activities," dated March 2009 (ADAMS Accessiqn No. ML090410014), by the end of its implementation period (i.e., one year after the issuance of Revision 2 of RG 1.200). Revision 2 of RG 1.200 endorses, with exceptions and clarifications, the combined American Society of Mechanical Engineers (ASME)/American Nuclear Society (ANS) PRA standard ASME/ANS RA-Sa-2009, "Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications." |
| | Given that the implementation date of RG 1.200, Revision 2, was April 2010, and the LAR was submitted in August 2014, identify any gaps between the WF3 internal events PRA model used in this application and RG 1.200, Revision 2, requirements that are relevant to this LAR. |
| | Additionally, address the technical adequacy requirements of RG 1.200, Revision 2, that are applicable to this LAR, or explain why addressing the requirements would have no impact on this application. |
| | Enclosure |
| | |
| | Section 4.5.2 of the LAR states, in part, that "[t]he WF3 Fire PRA (FPRA) model has undergone a Reg. Guide 1.200 Peer Review against Sections 2 and 3 of the ASME PRA Standard." The ASME PRA Standard RA-Sa- 2009 contains ten parts, each with several sections. Clarify whether the above statement from the LAR refers to Sections 2 and 3 of Part 4, "Requirements for Fire At-Power PRA." If the Fire PRA has not been peer-reviewed against ASME/ANS RA-Sa-2009, clarify how the fire PRA was determined to be of sufficient quality for this application. |
| | Section 4.5.2 of the LAR states, in part, that "(t]he industry peer review of the updated PRA model has been performed. The updated PRA model meets ASME Capability Category II requirements by addressing gaps identified by the peer review." Provide a list of all supporting requirements from the peer-review relevant to this LAR for which the PRA did not meet the ASME/ANS RA-Sa-2009 Capability Category 1 supporting requirements. Explain why these gaps would not impact this specific application. For gaps that did not impact another application (e.g., National Fire Protection Association NFPA-805), describe why the finding does not impact this LAR. |
| | In the LAR, the licensee proposed to revise WF3, TS 6.15, as follows: |
| | A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(0) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in NEI 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR 50, Appendix J," dated October. 2008, except that the next Type A test performed after the May 21, 2005 Type A test shall be performed no later than May 20. 2020. |
| | The term "except that" in the above proposed TS wording gives the appearance that the extension of the next Type A test is an exception to the guidelines contained in NEI 94-01, Revision 2A (ADAMS Accession No. ML100620847). Provide clarification for the term "except that." |
| | The NRC staff notes that this was identified for similar applications previously submitted for the NRC review and Entergy had provided clarification in letters dated January 20, 2011, for Arkansas Nuclear One, Unit 2, and March 11: 2014, for Arkansas Nuclear One, Unit 1 (ADAMS Accession Nos. ML110210971 and ML14070A399, respectively). |
| | |
| | ===RAI 5=== |
| | Sections 4.0 and 4.3 of the LAR state that the ASME Boiler and Pressure Vessel (BPV) Code, Section XI, Subsection IWL, does not apply to WF3. |
| | |
| | As described in Section 3.8 of the WF3 final s*afety analysis report, both the shield building and the containment vessel are supported on a common reinforced concrete foundation mat. The containment vessel is supported on the concrete fill, which transfers the loads by bearing to the foundation mat below. |
| | Subsection IWL provides the examination requirements for reinforced concrete Class CC . |
| | components. Considering that the containment vessel is supported on a concrete fill and a reinforced concrete foundation mat, provide clarification regarding the LAR's statement of Subsection IWL not being applicable to WF3. - |
| | Please provide information of instances, during implementation of the WF3 containment inservice inspection program, where existence of, or potential for, degraded conditions in inaccessible areas were identified and evaluated based on conditions found in accessible areas, as required by 10 CFR 50.55a(b)(2)(viii)(E) and 10 CFR 50.55a(b)(2)(ix)(A). lfthere were any instances of such conditions, discuss the findings and corrective actions taken to disposition the findings. |
| | Section 9.2.3.2 of NEI 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," and Condition 2 in Section 4.1 of the NRC safety evaluation for NEl 94-01, Revision 2, require supplemental general visual inspections of accessible interior and exterior surfaces of the containment for structural deterioration that may affect the containment leak-tight integrity. These inspections must be conducted prior to each Type A test and during at least three other outages before the next Type A test if the interval for the Type A test has been extended to 15 years. |
| | Provide a schedule for a typical 15-year interval (between the last Type A test in 2005 and the proposed next Type A test in 2020), in a tabular format, of inservice inspections that were and will be performed on the containment vessel, and explain how it meets the requirements in Section 9.2.3.2 of NEI 94-01, Revision 2-A, and Condition 2 in Section 4.1 of the NRC safety evaluation NEI 94-01, Revision 2. Please include the inservice inspection intervals with the start date and end date of each inspection period, and the corresponding refueling outages. |
| | The LAR states that WF3 has three periods during each 10-year inservice inspection interval. |
| | Table 4-2 of the LAR presents the ASME BPV Code, Section XI, Subsection IWE, inspection results from 2003 to 2014. Please provide the following: |
| | : a. The edition of the ASME BPV Code associated with each WF3 inservice i,nspection interval. |
| | : b. It is not clear from the review of Table 4-2 of the LAR that 100 percent of the containment vessel accessible surface areas and the interior and exterior moisture barriers have been inspected since 2005. Please clarify or supplement the information |
| | |
| | in Table 4-2 to demonstrate that the requirements of Table IWE-2500-1 of the ASME BPV Code have been satisfied. |
| | Attachment 4 of the LAR states that Table 4-1 presents summaries of the results from the WF3 shield building interior and exterior structural inspections, which were performed during each refueling shutdown and prior to any integrated leak test. Contrary to this statement, Section 4.3 |
| | . of the LAR states that Table 4-1 presents summaries of the results from the WF3 containment building interior and exterior structural inspections, which were performed every three years and the shield building inspection was performed prior to any integrated leak test. Also, the dates included in Table 4-1 do not appear to support the statement in Attachment 4 that the WF3 shield building was inspected during each refueling outage. Please provide clarification. |
| | |
| | ===RAI 10=== |
| | Table 4-2 of the LAR includes the results of the inspection of the containment vessel interior coating performed in 2003. Please discuss the highlights of findings from WF3 recent inspections of the containment vessel coating and actions taken to disposition them. |
| | |
| | ===RAI 11=== |
| | Please discuss NRC Information Notice 2014-07, "Degradation of Leak-Chase Channel Systems for Floor Welds of Metal Containment Shell and Concrete Containment Metallic Liner," |
| | dated May 5, 2014 (ADAMS Accession No. ML14070A114), as it may apply to.WF3. If applicable, discuss the operating experience, inspection results, and any corrective actions taken. * |
| | |
| | ===RAI 12=== |
| | Please provide the following information: |
| | : a. Percent of the total number of Type B tested components that are on 120-month extended performance-bas*ed test interval. |
| | : b. Percent of the total number of Type C tested components that are on 60-month extended performance-based test interval. |
| | * MLML15033A422 *via memo OFFICE NRR/DORL/LPL4-2/PM NRR/DORL/LPL4-2/LA NRR/DRA/APLA/BC* |
| | NAME MOrenak PBlechman HHamzehee DATE 2/10/15 2/9/15 1/26/15 OFFICE NRR/DE/EMCB/BC* NRR/DORL/LPLIV-2/BC NRR/DORL/LPL4-2/PM NAME Tluoold MKhanna MOrenak DATE 1/28/15 2/12/15 2/18/15}} |
|
|---|
Category:Letter
MONTHYEARIR 05000382/20244022024-10-10010 October 2024
Security Baseline Inspection Report 05000382/2024402 Public
IR 05000382/20244032024-10-0909 October 2024
Security Baseline Inspection Report 05000382/2024403
IR 05000382/20240112024-10-0101 October 2024
State Fire Protection Team Inspection Report 05000382/2024011
IR 05000382/20230042024-09-27027 September 2024
Amended Integrated Inspection Report 05000382/2023004
ML24229A1042024-09-25025 September 2024
Integrated Inspection Report 05000382/2023004, Disputed Non-Cited Violation Revised
ML24268A1132024-09-24024 September 2024
Acknowledgment of Response to NRC Inspection Report 05000382/2024013, and Notice of Violation
ML24255A8642024-09-0606 September 2024
Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification
ML24239A3972024-08-23023 August 2024
Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243
IR 05000382/20240052024-08-21021 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2024005
ML24220A2642024-08-20020 August 2024
Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment
IR 05000382/20240132024-08-20020 August 2024
Notice of Violation; NRC Inspection Report 05000382/2024013
ML24228A2612024-08-20020 August 2024
Notice of Violation; NRC Inspection Report 05000382/2024013
05000382/LER-2024-004, Automatic Reactor Trip Due to Lightning Strike2024-08-15015 August 2024
Automatic Reactor Trip Due to Lightning Strike
IR 05000382/20240022024-08-0808 August 2024
Integrated Inspection Report 05000382/2024002
ML24164A2512024-08-0707 August 2024
Issuance of Amendment No. 271 Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program
ML24213A1632024-08-0101 August 2024
2024 Waterford Notification of Biennial Problem Identification and Resolution Inspection and Request for Information
ML24208A0962024-07-25025 July 2024
57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification
05000382/LER-2024-003, Automatic EFAS Actuation During Surveillance Test2024-07-10010 July 2024
Automatic EFAS Actuation During Surveillance Test
ML24150A3852024-06-0404 June 2024
Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000382/2024011) and Request for Information
ML24060A2192024-05-30030 May 2024
Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752
ML24141A1012024-05-20020 May 2024
Amended Integrated Inspection Report 05000382/2023004
05000382/LER-2024-002, Automatic Reactor Trip Due to Transformer Failure2024-05-16016 May 2024
Automatic Reactor Trip Due to Transformer Failure
05000382/LER-2024-001, Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure2024-05-15015 May 2024
Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure
ML24128A0422024-05-0707 May 2024
License Amendment Request to Remove Obsolete License Conditions
IR 05000382/20240012024-05-0606 May 2024
Integrated Inspection Report 05000382/2024001
ML24067A1032024-04-25025 April 2024
Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ML24101A3882024-04-10010 April 2024
Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair
ML24089A2262024-03-29029 March 2024
Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams
IR 05000382/20244012024-03-18018 March 2024
Material Control and Accounting Program Inspection Report 05000382/2024401
ML24074A3742024-03-15015 March 2024
Acknowledgement of Response to NRC Inspection Report 05000382/2023004 and Disputed Non-Cited Violation
ML24075A1712024-03-15015 March 2024
Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))
ML24074A2892024-03-14014 March 2024
Proof of Financial Protection (10 CFR 140.15)
ML24032A0032024-03-0606 March 2024
– Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0053 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
IR 05000382/20230062024-02-28028 February 2024
Annual Assessment Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2023006
ML24039A1992024-02-12012 February 2024
– Integrated Inspection Report 05000382/2023004
IR 05000382/20230102024-01-31031 January 2024
Comprehensive Engineering Team Inspection Report 05000382/2023010
IR 05000382/20230032024-01-23023 January 2024
Acknowledgment of Reply to a Notice of Violation NRC Inspection Report 05000382/2023003
ML24012A1962024-01-12012 January 2024
Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 – Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and
ML23340A2292023-12-28028 December 2023
Withdrawal of an Amendment Request to Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability (EPID L-2022-LLA-0169)-LTR
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
ML23340A1592023-12-13013 December 2023
Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment
ML23352A0292023-12-13013 December 2023
Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection
ML23333A1362023-11-29029 November 2023
Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23325A1442023-11-21021 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23312A1832023-11-14014 November 2023
Integrated Inspection Report 05000382/2023003 and Notice of Violation
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
IR 05000382/20234012023-10-0404 October 2023
Cyber Security Inspection Report 05000382/2023401 (Cover Letter Only)
IR 05000382/20230052023-08-21021 August 2023
Updated Inspection Plan for Waterford Steam Electric Station, Unit 3 - (Report 05000382/2023005)
IR 05000382/20233012023-08-15015 August 2023
NRC Initial Operator Licensing Examination Approval 05000382/2023301
2024-09-06
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24150A3852024-06-0404 June 2024
Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000382/2024011) and Request for Information
ML24088A0092024-03-27027 March 2024
NRR E-mail Capture - Entergy Fleet - Final Request for Confirmation of Information (RCI) Re Alternative Request EN-RR-22-001 Concerning ASME Code Case N-752 (L-2022-LLR-0054)
ML23348A1222023-12-14014 December 2023
NRR E-mail Capture - Grand Gulf, River Bend, and Waterford, Unit 3 - 2nd Round of Official RAIs for RR EN-RR-22-001, Use ASME Code Case N-752, Risk Informed Categorization for Class 2 and 3 Systems
ML23191A4562023-07-10010 July 2023
Notification of Comprehensive Engineering Team Inspection (050003822023010) and Request for Information
ML23097A0412023-04-0606 April 2023
June 2023 Emergency Preparedness Exercise Inspection - Request for Information
ML23076A0552023-03-13013 March 2023
EP Program Inspection RFI Hjs 10132022
ML23052A0882023-02-17017 February 2023
Inspection Request for Information
ML22290A0442022-10-13013 October 2022
December 2022 Emergency Preparedness Program Inspection - Request for Information
ML22206A0172022-07-22022 July 2022
NRR E-mail Capture - Request for Additional Information: Waterford 3 - License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505
ML22209A1082022-07-15015 July 2022
NRR E-mail Capture - Draft RAIs to License Amendment Request for Application to Adopt 10 CFR 50.69 and Revise Technical Specifications to Adopt TSTF-505, Revision 2
ML22103A1712022-04-13013 April 2022
LAR to Revise TS to Adopt TSTF-505_NRC Request for Additional Information
ML22012A1592022-01-0505 January 2022
WF3 2022 EP Exercise Inspection RFI Sdh 010522
ML21285A0242021-10-0505 October 2021
Digital Instrumentation and Control Modification Inspection Request for Information
ML21280A0812021-10-0505 October 2021
Email 10-5-21 - Request for Information_ Waterford EP Inspection (71114.04 & 71151) - Nov-Dec 2021
ML22112A1512021-08-0606 August 2021
NRR E-mail Capture - for Review: Draft RAIs to LAR to Relocate Chemical Detection Systems Technical Specifications (TS) to Technical Requirements Manual (TRM)
ML21216A4562021-08-0404 August 2021
WF3 2021 EP Exercise Inspection Request for Information (RFI)
ML21218A0402021-07-26026 July 2021
NRR E-mail Capture - Final RAIs to Entergy Operations, Waterford Steam Electric Station, Unit 3 LAR to Adopt 10 CFR 50.69
ML21196A5302021-07-19019 July 2021
Wat 2021010 RFI Letter 21N_05 Gap
ML21195A0692021-07-13013 July 2021
Staton, Unit 3 - Notification of Digital Instrumentation and Control Modification Inspection and Request for Information
ML21125A6522021-05-0606 May 2021
Wat 2021003 Brq RFI- Md, Waterford Steam Electric Station, Unit 3, Notification of Inspection (NRC Inspection Report 05000382/2021003) and Request for Information
ML21112A2542021-04-29029 April 2021
Request for Additional Information Digital Upgrade to the Core Protection and Control Element Assembly Calculator System (EPID L 2020 Lla 0164) - Redacted Version
ML20288A2082020-10-0808 October 2020
8Oct2020 Email - Request for Information (RFI) to Support and Prepare for the Emergency Preparedness (EP) Program Inspection at the Waterford 3 Station Scheduled to Occur the Week of December 7, 2020
ML20289A3502020-10-0505 October 2020
NRR E-mail Capture - NRC Request for Additional Information - WF3 EAL Scheme Change - L-2020-LLA-0122
ML20125A3212020-05-0404 May 2020
WAT2020410 Inspection Document Request
ML20086M3852020-04-0101 April 2020
Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4 8.1, A.C. Sources Operating
W3F1-2020-0014, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding Application for Technical Specification Change to Control Room Air Conditioning System2020-03-20020 March 2020
Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding Application for Technical Specification Change to Control Room Air Conditioning System
ML20049A4102020-02-20020 February 2020
Request for Additional Information Regarding License Amendment Request to Revise Surveillance Requirement 4.7.6.1.d, Control Room Air Filtration System
ML19262H0362019-09-0404 September 2019
Ti 2515/194 Request for Information and Email
ML19274D4932019-07-24024 July 2019
Request for Information IR 05000382 2019-003 Occupational Radiation Safety Inspection
ML19203A0062019-07-19019 July 2019
NRR E-mail Capture - Waterford 3 - Final Request for Additional Information (Rais) Re Relief Request WF3-RR-19-2: Alternate Repair of Degraded Drain Line of Chemical and Volume Control System
ML19151A6102019-06-0404 June 2019
Non-Proprietary Second Round RAI Regarding License Amendment Request for Use of the Tranflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Internal Components
ML19172A0852019-05-24024 May 2019
NRR E-mail Capture - Waterford 3 - Final Request for Additional Information (Rais) Re Relief Request W3-ISI-032: Volumetric Examination Requirements
ML19035A0412019-02-0101 February 2019
NRR E-mail Capture - Waterford 3 - Final Request for Information Regarding Relief Request WF3-RR-19-001 for Application of Dissimilar Metal Weld Full Structural Weld Overlay
ML19018A0102019-01-28028 January 2019
Request for Additional Information Regarding License Amendment Request for Revision of Technical Specification 3/4.7.4,Ultimate Heat Sink
ML18320A0902018-11-26026 November 2018
Request for Additional Information Regarding License Amendment Request for Use of the Transflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Internal Components
ML18318A4352018-11-14014 November 2018
NRR E-mail Capture - Waterford 3 - Final Request for Additional Information Regarding Request for Alternative to ASME Code Case N-770-2
ML18299A0862018-11-0707 November 2018
Draft Request for Additional Information License Amendment Request Regarding the Revision of UFSAR Section 3.9
ML18262A0412018-09-25025 September 2018
Request for Additional Information Regarding License Amendment Request to Revise Section 15.4.3.1 of the Waterford 3 Updated Final Safety Analysis Report to Account for Fuel Misload
ML18145A2652018-06-0101 June 2018
Supplemental Information Needed for Acceptance of Request for Licensing Action Use of Tranflow Code for Determining Pressure Drops Across Steam Generator Secondary Side Components
ML18085A6942018-03-26026 March 2018
Ref: Waterford Steam Electric Station, Unit 3, License Renewal Application - RAI Set 18
ML18058A0572018-02-23023 February 2018
Enclosurequest for Additional Information (Letter to J. Giddens Request for Additional Information Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update)
ML18039A9722018-02-0808 February 2018
Notification of Evaluations of Changes, Tests, and Experiments Inspection (05000382/2018002) and Request for Information
ML17233A2402017-08-14014 August 2017
NRR E-mail Capture - Draft RAI for Waterford Unit 3 Regarding License Amendment Request to Adopt TSTF-501 Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
ML17170A3012017-06-16016 June 2017
Notification of Inspection (NRC Integrated Inspection Report 05000382/2017003) and Request for Information
ML17101A4432017-04-17017 April 2017
Requests for Additional Information for the Review of the Waterford Steam Electric Station, Unit 3, License Renewal Application - Set 17
ML17086A5852017-03-28028 March 2017
Request for Additional Information for the Environmental Review of Waterford 3
ML17072A0102017-03-14014 March 2017
Requests for Additional Information for the Review of the Waterford Steam Electric Station, Unit 3, License Renewal Application Set - 15
ML17272A3352017-03-0101 March 2017
Request for Additional Information for the Review of the Waterford Steam Electric Station, Unit 3, License Renewal Application - Set 14
ML17040A5382017-02-14014 February 2017
Requests for Additional Information for the Review of the Waterford Steam Electric Station, Unit 3, License Renewal Application - Set 13
ML17018A3592017-01-26026 January 2017
Requests For Additional Information For The Review Of The Waterford Steam Electric Station, Unit 3, License Renewal Application Set 12 (CAC MF7492.)
2024-06-04
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 18, 2015 Vice President, Operations Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REQUEST TO PERMANENTLY EXTEND THE INTEGRATED LEAK RATE TEST FREQUENCY TO 15 YEARS (TAC NO. MF4727)
Dear Sir or Madam:
By letter dated August 28, 2014 (Agencywide Documents Access and Management System
- (ADAMS) Accession No. ML14241A305), Entergy Operations, Inc., submitted a license amendment request (LAR) for Waterford Steam Electric Station, Unit 3, to change Technical Specification 6.15, "Containment Leakage Rate Testing Program," to allow a permanent extension of the Type A p~imary containment integrated leak rate test frequency from 1O years to 15 years.
The U.S. Nuclear Regulatory Commission staff has reviewed the LAR and has determined that additional information is needed to complete the review. Please provide the additio_nal information requested in the enclosure within 60 days of receipt of this letter.
If you have any questions, please contact me at 301-415-3229 or via e-mail at Michael. Orenak@nrc.gov.
Sincerely,
~ rJ} (NJv Michael D. Orenak, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE AMENDMENT REQUEST TO PERMANENTLY EXTEND THE INTEGRATED LEAK RATE TEST FREQUENCY TO 15 YEARS ENTERGY OPERATIONS, INC.
WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382 By letter dated August 28, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14241A305), Entergy Operations, Inc. (Entergy, the licensee),
submitted a license amendment request (LAR) to change Technical Specification (TS) 6.15, "Containment Leakage Rate Testing Program," for the Waterford Steam Electric Station, Unit 3 (WF3). The proposed change would allow a permanent extension of the Type A primary containment integrated leak rate test frequency from 1O years to 15 years.
The following questions were developed as a result of the U.S. Nuclear Regulatory Commission (NRC) staff's review of the licensee's LAR.
NRC Regulatory Issue Summary 2007-06 dated March 22, 2007 (ADAMS Accession No. ML070650428), states that the NRC staff expects that the licensees fully address all scope elements with Regulatory Guide (RG) 1.200, Revision 2, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment [PRA] Results for Risk-Informed Activities," dated March 2009 (ADAMS Accessiqn No. ML090410014), by the end of its implementation period (i.e., one year after the issuance of Revision 2 of RG 1.200). Revision 2 of RG 1.200 endorses, with exceptions and clarifications, the combined American Society of Mechanical Engineers (ASME)/American Nuclear Society (ANS) PRA standard ASME/ANS RA-Sa-2009, "Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications."
Given that the implementation date of RG 1.200, Revision 2, was April 2010, and the LAR was submitted in August 2014, identify any gaps between the WF3 internal events PRA model used in this application and RG 1.200, Revision 2, requirements that are relevant to this LAR.
Additionally, address the technical adequacy requirements of RG 1.200, Revision 2, that are applicable to this LAR, or explain why addressing the requirements would have no impact on this application.
Enclosure
Section 4.5.2 of the LAR states, in part, that "[t]he WF3 Fire PRA (FPRA) model has undergone a Reg. Guide 1.200 Peer Review against Sections 2 and 3 of the ASME PRA Standard." The ASME PRA Standard RA-Sa- 2009 contains ten parts, each with several sections. Clarify whether the above statement from the LAR refers to Sections 2 and 3 of Part 4, "Requirements for Fire At-Power PRA." If the Fire PRA has not been peer-reviewed against ASME/ANS RA-Sa-2009, clarify how the fire PRA was determined to be of sufficient quality for this application.
Section 4.5.2 of the LAR states, in part, that "(t]he industry peer review of the updated PRA model has been performed. The updated PRA model meets ASME Capability Category II requirements by addressing gaps identified by the peer review." Provide a list of all supporting requirements from the peer-review relevant to this LAR for which the PRA did not meet the ASME/ANS RA-Sa-2009 Capability Category 1 supporting requirements. Explain why these gaps would not impact this specific application. For gaps that did not impact another application (e.g., National Fire Protection Association NFPA-805), describe why the finding does not impact this LAR.
In the LAR, the licensee proposed to revise WF3, TS 6.15, as follows:
A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(0) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in NEI 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR 50, Appendix J," dated October. 2008, except that the next Type A test performed after the May 21, 2005 Type A test shall be performed no later than May 20. 2020.
The term "except that" in the above proposed TS wording gives the appearance that the extension of the next Type A test is an exception to the guidelines contained in NEI 94-01, Revision 2A (ADAMS Accession No. ML100620847). Provide clarification for the term "except that."
The NRC staff notes that this was identified for similar applications previously submitted for the NRC review and Entergy had provided clarification in letters dated January 20, 2011, for Arkansas Nuclear One, Unit 2, and March 11: 2014, for Arkansas Nuclear One, Unit 1 (ADAMS Accession Nos. ML110210971 and ML14070A399, respectively).
RAI 5
Sections 4.0 and 4.3 of the LAR state that the ASME Boiler and Pressure Vessel (BPV) Code,Section XI, Subsection IWL, does not apply to WF3.
As described in Section 3.8 of the WF3 final s*afety analysis report, both the shield building and the containment vessel are supported on a common reinforced concrete foundation mat. The containment vessel is supported on the concrete fill, which transfers the loads by bearing to the foundation mat below.
Subsection IWL provides the examination requirements for reinforced concrete Class CC .
components. Considering that the containment vessel is supported on a concrete fill and a reinforced concrete foundation mat, provide clarification regarding the LAR's statement of Subsection IWL not being applicable to WF3. -
Please provide information of instances, during implementation of the WF3 containment inservice inspection program, where existence of, or potential for, degraded conditions in inaccessible areas were identified and evaluated based on conditions found in accessible areas, as required by 10 CFR 50.55a(b)(2)(viii)(E) and 10 CFR 50.55a(b)(2)(ix)(A). lfthere were any instances of such conditions, discuss the findings and corrective actions taken to disposition the findings.
Section 9.2.3.2 of NEI 94-01, Revision 2-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," and Condition 2 in Section 4.1 of the NRC safety evaluation for NEl 94-01, Revision 2, require supplemental general visual inspections of accessible interior and exterior surfaces of the containment for structural deterioration that may affect the containment leak-tight integrity. These inspections must be conducted prior to each Type A test and during at least three other outages before the next Type A test if the interval for the Type A test has been extended to 15 years.
Provide a schedule for a typical 15-year interval (between the last Type A test in 2005 and the proposed next Type A test in 2020), in a tabular format, of inservice inspections that were and will be performed on the containment vessel, and explain how it meets the requirements in Section 9.2.3.2 of NEI 94-01, Revision 2-A, and Condition 2 in Section 4.1 of the NRC safety evaluation NEI 94-01, Revision 2. Please include the inservice inspection intervals with the start date and end date of each inspection period, and the corresponding refueling outages.
The LAR states that WF3 has three periods during each 10-year inservice inspection interval.
Table 4-2 of the LAR presents the ASME BPV Code,Section XI, Subsection IWE, inspection results from 2003 to 2014. Please provide the following:
- a. The edition of the ASME BPV Code associated with each WF3 inservice i,nspection interval.
- b. It is not clear from the review of Table 4-2 of the LAR that 100 percent of the containment vessel accessible surface areas and the interior and exterior moisture barriers have been inspected since 2005. Please clarify or supplement the information
in Table 4-2 to demonstrate that the requirements of Table IWE-2500-1 of the ASME BPV Code have been satisfied.
Attachment 4 of the LAR states that Table 4-1 presents summaries of the results from the WF3 shield building interior and exterior structural inspections, which were performed during each refueling shutdown and prior to any integrated leak test. Contrary to this statement, Section 4.3
. of the LAR states that Table 4-1 presents summaries of the results from the WF3 containment building interior and exterior structural inspections, which were performed every three years and the shield building inspection was performed prior to any integrated leak test. Also, the dates included in Table 4-1 do not appear to support the statement in Attachment 4 that the WF3 shield building was inspected during each refueling outage. Please provide clarification.
RAI 10
Table 4-2 of the LAR includes the results of the inspection of the containment vessel interior coating performed in 2003. Please discuss the highlights of findings from WF3 recent inspections of the containment vessel coating and actions taken to disposition them.
RAI 11
Please discuss NRC Information Notice 2014-07, "Degradation of Leak-Chase Channel Systems for Floor Welds of Metal Containment Shell and Concrete Containment Metallic Liner,"
dated May 5, 2014 (ADAMS Accession No. ML14070A114), as it may apply to.WF3. If applicable, discuss the operating experience, inspection results, and any corrective actions taken. *
RAI 12
Please provide the following information:
- a. Percent of the total number of Type B tested components that are on 120-month extended performance-bas*ed test interval.
- b. Percent of the total number of Type C tested components that are on 60-month extended performance-based test interval.
- MLML15033A422 *via memo OFFICE NRR/DORL/LPL4-2/PM NRR/DORL/LPL4-2/LA NRR/DRA/APLA/BC*
NAME MOrenak PBlechman HHamzehee DATE 2/10/15 2/9/15 1/26/15 OFFICE NRR/DE/EMCB/BC* NRR/DORL/LPLIV-2/BC NRR/DORL/LPL4-2/PM NAME Tluoold MKhanna MOrenak DATE 1/28/15 2/12/15 2/18/15
