|
|
Line 3: |
Line 3: |
| | issue date = 07/24/2013 | | | issue date = 07/24/2013 |
| | title = Supplemental Request for Additional Information - Relief Request ISI-03 | | | title = Supplemental Request for Additional Information - Relief Request ISI-03 |
| | author name = Guzman R V | | | author name = Guzman R |
| | author affiliation = NRC/NRR/DORL/LPLI-1 | | | author affiliation = NRC/NRR/DORL/LPLI-1 |
| | addressee name = Couture P | | | addressee name = Couture P |
Line 9: |
Line 9: |
| | docket = 05000271 | | | docket = 05000271 |
| | license number = DPR-028 | | | license number = DPR-028 |
| | contact person = Guzman R V | | | contact person = Guzman R |
| | case reference number = TAC MF1196 | | | case reference number = TAC MF1196 |
| | document type = Request for Additional Information (RAI), E-Mail | | | document type = Request for Additional Information (RAI), E-Mail |
|
---|
Category:Request for Additional Information (RAI)
MONTHYEARML19224A4722019-08-26026 August 2019 VY Report on Status of Decommissioning Funding for Shutdown Reactors Enclosure ML18094B0922018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to B. S. Ford RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for ISFSI Docket Nos.: 72-43, 72-51, 72-1044, 72-07, 72-12, and 72-59) ML18045A8172018-04-0505 April 2018 Request for Additional Information on Vermont Yankee License Transfer Request (License DPR-28, Docket No. 50-271) ML17341A3842017-12-14014 December 2017 Request for Additional Information Regarding License Amendment Request to Change Physical Security Plan to Reflect an ISFSI-Only Configuration ML17313A4312017-11-0303 November 2017 NRC Request for Additional Information Regarding the Request for Direct and Indirect License Transfers from Entergy to Northstar ML17279B1452017-10-24024 October 2017 Request for Additional Information Regarding the License Amendment Request to Change the Emergency Plan and Emergency Action Level Scheme to Reflect an ISFSI-Only Configuration ML17244A0982017-10-12012 October 2017 NRC Request for Additional Information Regarding the Request for Direct and Indirect License Transfers from Entergy to Northstar ML17229B4842017-08-16016 August 2017 Request for Supplemental Documentation to Support Review of the Physical Security Plan ML16090A0292016-04-0505 April 2016 Request for Additional Information Related to Proposed Changes to Quality Assurance Program Manual, Vermont Yankee Nuclear Power Station ML16077A3452016-03-22022 March 2016 Request for Additional Information Related to 10 CFR 20.2002 Alternate Waste Disposal Request For Vermont Yankee Nuclear Power Station (CAC No. L53116) ML16069A0952016-03-0303 March 2016 Request for 20.2002 Disposal, Request for Additional Information CNRO-2015-00008, Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company2015-02-18018 February 2015 Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company ML14318A4002014-12-17017 December 2014 Vermont Yankee Nuclear and Big Rock Point - Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company (Tac Nos. MF3218 - MF3221) ML14289A3942014-11-21021 November 2014 Redacted, Request for Additional Information, Review of Revision 14 to the Physical Security Plan, Safeguards Contingency Plan, and Training and Qualification Plan Pursuant to 10 CFR 50.54(p)(2) BVY 14-069, Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E - Supplement 22014-10-21021 October 2014 Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E - Supplement 2 ML14192A8352014-08-19019 August 2014 Request for Additional Information, Exemption from 10 CFR 50.47 and Appendix E to Allow Reduced Emergency Plan Requirements and Revise Radiological Emergency Response Plan Consistent with Permanently Defueled Reactor ML14231A0172014-08-13013 August 2014 Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 4 ML14163A5902014-07-0101 July 2014 Request for Additional Information, Round 2, Amendment Request to Revise Site Emergency Plan for Permanently Defueled Condition to Reflect Change in On-Shift Staffing and Emergency Response Staffing ML14115A0292014-05-0505 May 2014 Request for Additional Information Regarding License Amendment Request for Emergency Plan Change ML14024A0412014-01-29029 January 2014 Request for Additional Information Regarding Entergy Request for Rescission of and Scheduler Relief from Order EA-13-109 on Reliable Hardened Containment Vents ML13311B0772013-11-26026 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13218A0122013-08-0606 August 2013 E-mail from R.Guzman to P.Couture, Request for Additional Information - Relief Requests ISI-04 Dated March 27, 2013 - Bvy 13-018 ML13205A1762013-07-24024 July 2013 Supplemental Request for Additional Information - Relief Request ISI-03 ML13179A4622013-07-0505 July 2013 Entergy Nuclear Operations, Inc., Decommissioning Funding Status Report Request for Additional Information Regarding the Decommissioning Funding Status Report ML13186A1142013-07-0505 July 2013 Email from R. Guzman to P.Couture Request for Additional Information - Relief Request ISI-02, Application of Code Case N-716 ML13165A2792013-06-20020 June 2013 Request for Additional Information Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (NRC Order EA-12-051) ML13163A2582013-06-17017 June 2013 Request for Additional Information - Response to March 12, 2012, Commission Order EA-12-049 to Modify Licenses Requirements for Mitigating Strategies for Beyond Design Basis External Events ML13149A2652013-05-28028 May 2013 Email from R. Guzman to P. Couture - Request for Additional Information Relief Request ISI-05 (TAC No. MF1194) -Updated RAI-2 (Revision 2) ML13130A0562013-05-0909 May 2013 E-mail from R.Guzman to P.Couture Request for Additional Information - Relief Request RR-P02 Dated February 1, 2013 - Bvy 13-008 ML13130A0472013-05-0808 May 2013 Email from R.Guzman to P.Couture Request for Additional Information - Relief Requests ISI-01 and ISI-03 Dated March 27, 2013 - Bvy 13-018 (TAC Nos. MF1196/1198) ML13119A2462013-04-29029 April 2013 Request for Additional Information, E-mail from R. Guzman to P. Couture Relief Request ISI-05 ML13097A0032013-04-0808 April 2013 Request for Additional Information Change to 10 CFR 50.63 Licensing Basis - SBO EDG ML13087A3922013-04-0202 April 2013 Request for Additional Information to Support the Review of Relief Request RR-P-01 ML13081A7522013-03-22022 March 2013 Email from R.Guzman to P.Couture Request for Additional Information for License Amendment Request to Change 10 CFR 50.63 Licensing Basis ML13077A2062013-03-20020 March 2013 Request for Additional Information Regarding 10 CFR 50.33 Financial Qualification Review ML13067A0912013-03-0808 March 2013 Request for Additional Information Change to TS 3.3.B Inoperable Control Rods ML13050A4692013-02-21021 February 2013 Request for Additional Information Change to Licensing Basis for Station Blackout Diesel Generator ML13018A4592013-01-15015 January 2013 Request for Additional Information - E-mail from R.Guzman to P.Couture Relief Request ISI-PT-02 Alternative to the System Leakage Test for Rv Head Flange Leakoff Lines ML1228403332012-10-10010 October 2012 Request for Additional Information - E-mail from R. Guzman to P. Couture License Amendment Request to Revise License Condition 3.P and 3.Q ML12278A3862012-10-0404 October 2012 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2, and 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford, Request for Additional Information, Round 2, Amendment Request to Revise QA Program Manual and Staff Qualification TSs ML13070A2032012-09-17017 September 2012 Email from R. Guzman to R. Wanczyk and P. Outure Draft Request for Additional Information - LAR to Revise License Renewal Commitments One Time Inspection Program ML13070A1742012-09-10010 September 2012 Email from R. Guzman to R. Wanczyk Draft Request for Additional Information - LAR to Revise License Renewal Commitments Selective Leaching Program ML12122A8072012-05-0707 May 2012 Request for Additional Information Regarding Physical Security, Safeguards Contingency and Training and Qualification Plan, Revision 11 ML1300902982012-04-10010 April 2012 E-mail from J. Kim to J. Devincentis Request for Additional Information - Rod Worth Minimizer Bypass Allowance Amendment ML1209604492012-04-0505 April 2012 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Request for Additional Information, Revise Quality Assurance Program Manual and Staff Qualification Technical Specificat ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0502012-03-12012 March 2012 Enclosure 4 - Recommendation 2.3: Flooding ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic 2019-08-26
[Table view] Category:E-Mail
MONTHYEARML21075A1582021-03-15015 March 2021 E-mail from T. Silko to J. Parrott, NMSS, Vermont Yankee on the State of Vermont Comments on the Review of the Draft Final SER and EA for 20.2002 Alternate Disposal Request ML21006A0242020-12-22022 December 2020 E-mail from J. Parrott to J. Tierney and N. Creed Vermont Yankee Request to NRC for Alternate Disposal of Wastewater ML20358A0702020-12-22022 December 2020 E-mail Acceptance Review for Request for Indirect License Transfer (License DPR-28, Docket No. 50-271) ML20175A2122020-06-23023 June 2020 Acceptance Review of Request for Alternate Disposal of Wastes Under 10 CFR 20.2002 (License DPR-28, Docket No. 50-271) ML19289A1292019-10-11011 October 2019 Email from Daniel Doyle to Mark Leyse Status of PRM-50-93 and PRM-50-95 ML19288A0292019-10-11011 October 2019 NRC Acceptance Review - Northstar Request for Exemption from 10 CFR 20, App G, Section Iii.E (License DPR-28, Docket No. 50-271) ML19198A2512019-06-20020 June 2019 Alternate Disposal Request - Rail Shipments (License DPR-28, Docket No. 50-271) ML19059A1782019-02-28028 February 2019 Acceptance Review Results for Relief Request No. EN-19-RR-1 to Use ASME Code Case N-831-1 for Entergy Fleet ML18289A3622018-10-11011 October 2018 Email from Daniel Doyle to Mark Leyse Status of PRM-50-93 and PRM-50-95 ML18127A5582018-04-25025 April 2018 Email to State of Vermont on Vermont Yankee Nuclear Power Station - Forthcoming Issuance of a License Amendment Regarding the Requirement for the VYNPS to Have a Cyber Security Plan ML18045A0862018-01-25025 January 2018 Email Request for Review of the Draft Safety Evaluation for Implementation of a Revised Emergency Plan at Vermont Yankee to Reflect an ISFSI-only Configuration ML17353A0092017-12-18018 December 2017 E-Mail from William Irwin, Vermont Department of Health to Y. Chen/Dsfm Response: Draft Environmental Assessment: Exemption Request for Vermont Yankee Independent Spent Fuel Storage Installation ML17289A4222017-10-16016 October 2017 E-Mail from Y. J. Chen to W. Irwin Draft Environmental Assessment Exemption Request for Vermont Yankee Independent Spent Fuel Storage Installation ML17257A0022017-09-14014 September 2017 Email to VY Shpo W Ltr Re VYNPS Exemption Load Campaign - Sept 2017 ML17229B4842017-08-16016 August 2017 Request for Supplemental Documentation to Support Review of the Physical Security Plan ML17219A0472017-08-0303 August 2017 8/03/2017, E-Mail from Y. J. Chen/Nmss to T. B. Silko/Vermont Yankee Regarding Need for Additional Information Entergy'S Exemption Request for Vermont Yankee ISFSI, Dated May 16, 2017 (ML17142A358) ML17144A0452017-05-23023 May 2017 5/23/2017, E-Mail to I. William/Vermont Dept. of Health from Y. Chen/Nrc Response: Draft Environment Assessment: Exemption Request for Vermont Yankee Independent Spent Fuel Storage Installation (W/Attachment Ltr to Address Comments on EA) ML17080A4752017-03-16016 March 2017 3/16/2017, E-Mail from I. William/Vermont Department of Health to Yen-Ju Chen/Dsfm/Sflb, Providing Comments on Draft Environmental Assessment for Entergy/Vermont Yankee'S Exemption from Requirement of 10 CFR 72.7 for CoC No. 72-1014, Amendm ML17055A6262017-02-24024 February 2017 Cover Email from VY Shpo W Concurrence on No Effects Determination ML17040A3372017-02-0909 February 2017 Email and Letter to Vermont Shpo ISFSI Exemption No Effects Determination ML17038A4682017-02-0707 February 2017 2/07/2017, E-mail from Yen-Ju Chen/NRC-DSFM to W. Irwin/Vermont Dept. of Health Draft Environment Assessment for Entergy/Vermont Yankee'S Exemption from Requirement of 10 CFR 72.7 for Certificate of Compliance No. 72-1014, Amendment 10 ML17012A2472017-01-11011 January 2017 E-mail - State of Vermont Comments Regarding Vermont Yankee'S 10 CFR 20.2002 Request ML16349A2492016-12-13013 December 2016 E-Mail to T. B. Silko/Entergy from Yen-Ju Chen/Dsfm Regarding Need for Supplemental Information for Entergy'S Exemption Request for Vermont Yankee ISFSI, Dated November 9, 2016 (ML16319A102) ML17013A2502016-12-12012 December 2016 Email Requesting Review of Draft EA and SER for Vermont Yankee Request to NRC for Alternate Disposal of Waste ML16231A0282016-08-11011 August 2016 Response to NRC Questions Related to Request for 20.2002 Disposal of Contaminated Water ML16231A2192016-07-28028 July 2016 Follow-up Questions Related to Entergy Request for 20.2002 Disposal of Contaminated Water ML16069A0952016-03-0303 March 2016 Request for 20.2002 Disposal, Request for Additional Information ML16053A5152016-02-17017 February 2016 Comment (037) of Emma Stamas on ANPR-26, 50, 52, 73, and 140 - Regulatory Improvements for Decommissioning Power Reactors ML15329A1802015-11-24024 November 2015 E-mail from J. Whited Draft RAIs Re Duke License Amendment Request to Adopt TSTF-523 (CAC Nos. MF6413 Through MF6422) ML15295A2132015-10-21021 October 2015 NRR E-mail Capture - VY RAI for Off-site Insurance Exemption (10 CFR 140.11) - MF3980 ML15289A6002015-09-24024 September 2015 La 3 - Vermont Yankee Draft Responses or Edits 9 24 15.docx ML15289A6012015-09-23023 September 2015 La 3 - Nrr_Vermont Yankee Nuclear Power Station Decommissioning Status.Docx ML15288A3532015-09-21021 September 2015 La 3 - VY Dtf LAR - Status ML15257A6172015-09-14014 September 2015 La 3 - Testing the New Profile for Vermont Yankee La 3 - Public ML15195A3592015-07-14014 July 2015 NRR E-mail Capture - Acceptance Review for Vermont Yankee Amendment -Revise Cyber Security Plan Implementation ML15289A0022015-06-17017 June 2015 La 3 - Question from Ma ML15289A5982015-06-0909 June 2015 La 3 - FW: Docket No. 50-271 (Vermont Yankee); June 5 2015 Letter from Vermont, Vynpc, and Gmp to NRC Attached ML15289A0072015-06-0505 June 2015 La 3 - Information Regarding Vermont Yankee Decommissioning Trust Fund Exemption ML15289A2432015-06-0404 June 2015 La 3 - FW: Docket No. 50-271 (Vermont Yankee); June 4 2015 Vermont Letter to NRC Attached ML15289A0062015-06-0404 June 2015 La 3 - FW: Information Regarding Vermont Yankee Decommissioning Trust Fund Exemption ML15288A3592015-06-0101 June 2015 La 3 - Vermont Yankee LA3 - Availability for Oral Argument ML15288A3602015-06-0101 June 2015 La 3 - Vermont Yankee LA3 - Availability for Oral Argument ML15288A3622015-06-0101 June 2015 La 3 - Vermont Yankee LA3 - Availability for Oral Argument ML15288A4822015-05-22022 May 2015 La 3 - Vermont Reply to NRC & Entergy Answers Re VY LA-3 ML15289A0042015-05-19019 May 2015 La 3 - New Proposal Dates for Phone Call with VT ML15289A0052015-05-11011 May 2015 La 3 - ML Numbers for Disbursement Letters for Vermont Yankee ML15289A5992015-05-0808 May 2015 La 3 - Call with State of VT ML15289A0032015-05-0707 May 2015 La 3 - Other than for Comanche Peak, ML15289A1252015-05-0606 May 2015 La 3 - FRN Review - VY Dtf Exemption ML15128A0232015-04-27027 April 2015 NRR E-mail Capture - Petitioners Response to Request for Comments on the Proposed Director'S Decision on the 2.206 Petition Regarding Financial Qualifications of Entergy 2021-03-15
[Table view] |
Text
From: Guzman, Richard Sent: Wednesday, July 24, 2013 10:56 AM To: Couture III, Philip
Subject:
RE: [FOLLOW-UP] Request for Additional Information - Relief Requests ISI-01 and ISI-03 dated March 27, 2013 - BVY 13-018 (TAC Nos.
MF1196/1198)
Phil, The NRC staff has reviewed the information provided in the Entergy RAI response letter dated June 27, 2013 (ADAMS Accession No. ML13183A065) regarding the subject Vermont Yankee relief request dated March 27, 2013 (ADAMS Accession No. ML13092A204), and has determined that follow-up additional information is needed to complete its review. See below supplemental RAI question RAI-4A. To support the staff's timely review, we request that you provide a formal response by August 30, 2013. Please let me know if you'd like to have a teleconference with the technical staff to discuss any clarifications necessary to address the question. Thanks, Rich Guzman Sr. Project Manager NRR/DORL US NRC 301-415-1030 Richard.Guzm an@nrc.gov
============================================================
============================================================
========================
REQUEST FOR ADDITIONAL INFORMATION PROPOSED ALTERNATIVE REQUESTS FOR RELIEF NO ISI-03 FIFTH TEN-YEAR INSPECTION INTERVAL NOZZLE-TO-VESSEL WELD, AND NOZZLE INNER RADIUS INSPECTIONS ENTERGY NUCLEAR OPERATIONS, INC.
VERMONT YANKEE NUCLEAR POWER STATION DOCKET NOS. 50-271 (TAC NO. MF1196)
RAI-4A In response to RAI-4, by letter dated June 27, 2013 (ADAMS Accession No. ML13183A065),
the licensee listed a number of nozzle-to-vessel welds and nozzle inner radii in which indications have been detected in previous inservice inspections (ISIs). The table in the attachment to the revised Relief Request ISI-03 provided in the letter dated June 27, 2013, provides the results of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI examinations of Vermont Yankee Nuclear Power Station (VYNPS) nozzle-to-vessel and nozzle inner radii from the Fourth Ten-Year ISI interval. In this table a number of nozzles have "Accept" in the results column. The NRC staff interprets "Accept" as implying that indications were detected but were acceptable under Section XI. A number of the nozzles having "Accept" in the results column are not nozzles mentioned in the response to RAI 4 as nozzles having previous indications. These are the N3A, N3B, N3D, N4A, N4B, N4C, and N4D nozzle-to-vessel welds, and N3A, N3B, N3C, and N3D inner radii. The RAI-4 response noted indications were detected during the Third Ten-Year ISI interval for the N4A and N4B nozzles but did not specify whether the indications were in the nozzle-to-vessel or nozzle inner radius. Therefore, it is not clear whether some of the nozzles with the result "Accept" have indications that have first been detected during the Fourth Ten-Year ISI interval.
The staff notes that if any indications were accepted by analytical evaluation in accordance with the ASME Code,Section XI, IWB-3142.4, these indications must be subsequently examined in accordance with IWB-2420 (b) and (c).
Requested Information:
- 1. Clarify the meaning of "Accept" in the results column of the table.
- 2. Reconcile the difference in the nozzle-to-vessel weld and nozzle inner radii examinations with the result "Accept" for the Fourth Ten-Year ISI interval examinations with those nozzle-to-vessel welds and nozzle inner radii listed in the RAI 4 response as having previous indications.
- 3. Identify any nozzle-to-vessel welds and nozzle inner radii which had new indications detected during the Fourth Ten-Year ISI interval, and whether subsequent examinations in accordance with IWB-2420 (b) and (c) are required for any of these nozzles.
============================================================
================================================================================================
From: Couture III, Philip [mailto:pcoutur@entergy.com
] Sent: Thursday, June 27, 2013 4:11 PM To: Guzman, Richard
Subject:
RE: Request for Additional Information - Re lief Requests ISI-01 and ISI-03 dated March 27, 2013 - BVY 13-018 (TAC Nos. MF1196/1198)
Rich, Attached is an advance copy of the RAI response.
Phil Couture Vermont Yankee Licensing 802-451-3193 From: Guzman, Richard [mailto:Richard.Guzman@nrc.gov
] Sent: Wednesday, May 08, 2013 1:39 PM To: Couture III, Philip
Subject:
Request for Additional Information - Relief Requests ISI-01 and ISI-03 dated March 27, 2013 - BVY 13-018 (TAC Nos. MF1196/1198)
Phil, The NRC staff has reviewed the information provided in the subject relief request letter dated March 27, 2013 (Agencywide Documents Access and Management System Accession No. ML13092A204), and has determined that additional information is needed to complete its review. Shown below is the NRC staff's request for additional information (RAI) questions. To support the staff's timely review, we request that you provide a formal response by June 28, 2013. Please contact me if you have any questions.
Thanks, Rich Guzman Sr. Project Manager NRR/DORL/LPL1-1 US NRC 301-415-1030 REQUEST FOR ADDITIONAL INFORMATION PROPOSED ALTERNATIVE REQUESTS FOR RELIEF NOS. ISI-01AND ISI-03 FIFTH TEN-YEAR INSPECTION INTERVAL REACTOR PRESSURE VESSEL CIRCUMFERENTIAL WELD, NOZZLE-TO-VESSEL WELD, AND NOZZLE INNER RADIUS INSPECTIONS ENTERGY NUCLEAR OPERATIONS, INC.
VERMONT YANKEE NUCLEAR POWER STATION DOCKET NOS. 50-271 (TAC NOS. MF1196 AND MF1198)
By letter dated March 27, 2013 (ADAMS Accession No. ML13092A204), Entergy Nuclear Operations, Inc. (Entergy), the licensee for Vermont Yankee Nuclear Power Station (VYNPS), submitted requests for relief from American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI. The alternative proposed in Relief Request RR-01 would eliminate the requirement to inspect the circumferential welds except for the areas of intersection with the axial welds consistent with the guidance provided in Generic Letter 98-05 , "Boiling Water Reactor Licensee Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Welds, " dated November 10, 1998 (Ref. 1) and the NRC staff's safety evaluation (SE) for the report issued on July 28, 1998 (Ref.2).
The alternative proposed in Relief Request ISI-03 would allow a reduction in the percentage of nozzle-to-vessel welds and nozzle inner radii inspected during each ten-year inspection interval from 100% to 25%, in accordance with ASME Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds." The technical basis for ASME Code Case N-702 was documented in an Electric Power Res earch Institute (EPRI) report fo r the Boiling-Water Reactor Vessel and Internals Project (BWRVIP); BWR Vessel and Internals Project Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius (BWRVIP-108) (Ref. 3), which was approved by the NRC in a safety evaluation (SE) dated December 19, 2007 (Ref. 4). The staff's SE in Reference 4 specified plant-specific requirements which must be met by applicants proposing to use this alternative.
RAI 1 In Relief Request ISI-01, the licensee provided Table 4.2-5 reproduced from the VYNPS License Renewal Application (Ref. 5). The table provides the supporting data for the evaluation of the mean reference temperature (RTNDT)), for the VYNPS limiting circumferential weld at 32 and 54 effective full power years (EFPY), and the limiting generic circumferential weld for a reactor pressure vessel (RPV) fabricated by Chicago Bridge & Iron Company (CB&I) at 32 EFPY and 64 EFPY. The generic CB&I mean RTNDT values are from Table 2.6-4 and 2.6-5 of the staff's SE of BWRVIP-05 (Ref. 2). Note that the VYNPS 54 EFPY value is compared to the generic 64 EFPY value for additional conservatism. The licensee provided an "implied margin" value of 25.5 °F for the limiting CB&I weld at 64 EFPY and 16.5 °F for the limiting VYNPS circumferential weld at 54 EFPY. Note that for the analysis of limiting circumferential weld RTNDT to support relief from inspection of the circumferential welds in accordance with Generic Letter 98-05, the mean RT NDT is used rather than the upper bound RTNDT, which is typically used in other RPV integrity evaluations. As clarified in Reference 6, mean RTNDT means that the end-of-life RTNDT is based on the initial (unirradiated) RTNDT plus the shift in RT NDT due to irradiation, calculated as the product of the chemistry factor and fluence factor as defined in Regulatory Guide 1.99, Revision 2, without a margin term. Reference 6 also corrected Table 2.6-4 from the staff's SE of BWRVIP-05, to revise the chemistry factor for the limiting CB&I circumferential weld from the original value in Reference 1 of 109.5 °F to 134.9 °F.
The NRC staff requests that the licensee review References 5 and 6 and revise Table 4.2-5 accordingly. If the replied margin term is to be retained, please provide the basis for calculating the implied margin term and why it is necessary.
RAI 2 Relief Request ISI-03 provides the calculations for the VYNPS values of the parameters for plant-specific applicability criteria 2, 3, 4, and 5 from the staff's final SE of BWRVIP-108. The staff checked the licensee's calculations of the parameters related to criteria 2, 3, 4, and 5. The staff independently verified the geometric parameters to the extent possible. The Updated Final Safety Evaluation Report (UFSAR) for VYNPS, Revision 25, Table 1.7-6, provided a RPV inside diameter of 17 feet 2 inches (206 inches), resulting in a RPV inner radius (r) of 103 inches, consistent with the licensee's value. UFSAR Table 1.7-6 provides a RPV wall thickness of 5.187 inches which includes 1/8 inch (0.125 inch) cladding. Subtracting the cladding thickness yields an RPV wall thickness (t) of 5.062 inches, which is inconsistent with the licensee's value of 5.625 inches. The staff recalculated the parameters for Criterion 2 and Criterion 4, which both have "t" as an input. Using t = 5.062 inches results in Criterion 4 not being met, while Criterion 2 is still met.
For the Recirculation Inlet Nozzles (N2):
(Criteria 2) (pr/t) / CRPV < 1.15 [(1010 x 103) / 5.062] / 19332 = 1.063 < 1.15 For Recirculation Outlet Nozzles (N1):
(Criteria 4) (pr/t) / CRPV < 1.15
[(1010 x 103) / 5.062] / 16171 = 1.27 > 1.15 The NRC staff therefore requests the licensee to provide a basis for use of a wall thickness of 5.625 inches for the Criterion 2 and Criterion 4 calculations, or revise the calculations to use a wall thickness consistent with that listed in the UFSAR.
RAI 3 Clarify whether the attachment to Relief Request ISI-03 contains only examinations conducted during the most recent ISI ten-year interval. Have all nozzle-to-vessel welds and nozzle inner radii been inspected at least once? If not, explain why some nozzles have had no prior inspections.
RAI 4
- a. For those nozzle-to-vessel welds and nozzle inner radii that had indications detected in previous ISI inspections, discuss whether these indications were determined to be fabrication defects or service-induced defects.
- b. Was any change in size of these indications noted in subsequent ISI examinations? If so, how was the change in size explained?
RAI 5 Provide the results of the 2010 Appendix VIII examination of the N5B nozzle-to-vessel weld, which is missing from the attachment.
References
- 1. EPRI TR-105697, "BWR Reactor Pressure Vessel Shell Weld Inspection Recommendations," Sept. 1995 (BWRVIP-05) (ADAMS Accession No. ML032200246)
- 2. "Evaluation by the Office of Nuclear Reactor Regulation Related to Review of the Topical Report by the Boiling Water Reactor Vessel and Internals Project: BWR Reactor Pressure Vessel Shell Weld Inspection Recommendations (BWRVIP-05)," Enclosure to Letter from Gus. C. Lainas to Carl Terry dated July 28, 1998,
Subject:
Final Safety Evaluation of the BWR Vessel and Internals Project BWRVIP-05 Report (TAC No. M93925); (ADAMS Accession No. 9808040037)
- 3. BWRVIP-108: BWR Vessel and Internals Project Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii, EPRI Technical Report 1003557, Final Report dated October 2002 (ADAMS Accession Nos. ML023360232 (Part 1) and ML023360234 (Part 2))
- 4. "Safety Evaluation Of Proprietary EPRI Report, "BWR Vessel and Internals Project, Technical Basis For The Reduction Of Inspection Requirements For The Boiling Water Reactor Nozzle-To-Vessel Shell Welds And Nozzle Inner Radius (BWRVIP-108)" transmitted via letter from Matthew A. Mitchell to Rick Libra dated December 19, 2007 (ADAMS Accession No. ML073600374)
- 5. 2006/01/25-Vermont Yankee Nuclear Power Station License Renewal Application, January 25, 2006, (ADAMS Accession No. ML060300085)
- 6. Supplement to Final Safety Evaluation of the BWR Vessel and Internals Project BWRVIP-05 Report dated March 7, 2000 (ADAMS Accession No. ML003690281)
- 7. Letter from R. J. Pascarelli to T.J. O'Connor dat ed February 8, 2011, Tr ansmitting Staff Safety Evaluation for Monticello, Request for Relief No. 17 Regarding Examination of Reactor Pressure Vessel Shell Circumferential Welds, (ADAMS Accession No. ML110200700)
- 8. Letter from M. Khanna to M. J. Pacilio dat ed January 24, 2012, Tran smitting Staff Safety Evaluation for Peach Bottom Atomic Power Station, Units 2 and 3 - Requests for Relief l4R-51 and l4R-52 (TAC Nos. ME5392, ME5393, ME5394 and ME5395). (ADAMS Accession No. ML112770217)