Letter Sequence RAI |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: BVY 06-009, 2006/01/25-Vermont Yankee Nuclear Power Station Applicant'S Environmental Report Operating License Renewal Stage, Appendix E, BVY 06-076, 2006/08/10-Vermont Yankee - License Renewal Application, Amendment 8, BVY 06-079, 2006/08/22-Vermont Yankee License Renewal Application, Amendment 11, BVY 06-083, 2006/09/05-Vermont Yankee License Renewal Application, Amendment 12, BVY 06-095, E-mail: (PA-LR) Copy of SAMA Response, BVY 06-096, 2006/10/20-Vermont Yankee - License Renewal Application, Amendment No. 17, BVY 06-097, 2006/10/31-Vermont Yankee License Renewal Application, Amendment 19, BVY 06-098, E-mail: (PA-LR) Copy of Vhs RAI Response, BVY 07-003, Email: (PA-LR) Vermont Yankee Nuclear Power Station License Renewal Commitment List, Rev. 5, BVY 07-009, License Renewal Application, Amendment 24, BVY 07-018, License Renewal Application, Amendment 26, BVY 07-034, License Renewal Application Annual Update, BVY 07-035, (PA-LR) Bvy 07-035 VY Lr SER Comments, BVY 07-047, License Renewal Application, Amendment 27, Submitted on January 25, 2006, BVY 07-058, License Renewal Application, Amendment 29, BVY 07-062, License Renewal Application, Amendment 30, BVY 07-066, License Renewal Application, Amendment 31, BVY 08-016, (PA-LR) Emailing Bvy 08-016 Final SER Review Comments, BVY 10-069, License Renewal Application Annual Update Information, ML060950195, ML060950215, ML060950218, ML060950220, ML060950224, ML060950235, ML060950250, ML060950258, ML060950262, ML060950269, ML060950271, ML060950277, ML060950279, ML060950284, ML060950290, ML060950301, ML060950311, ML060950323, ML060950328, ML060950331, ML060950347, ML060950351, ML060950356, ML060950364, ML060950370, ML060950372, ML060950375, ML060950540, ML060950549, ML060950559, ML060950567... further results
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MONTHYEARML0629203681987-12-31031 December 1987 VY Annual Ecological Studies of the CT River Report 16-final.pdf Project stage: Other ML0629203651989-12-31031 December 1989 VY Annual Ecological Reports from the 1980's (1989) Project stage: Other ML0609503511998-02-28028 February 1998 GALL AMP: XI.M12, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) (Audit Worksheet GALL Report AMP) Project stage: Other BVY 06-009, 2006/01/25-Vermont Yankee Nuclear Power Station Applicant'S Environmental Report Operating License Renewal Stage, Appendix E2006-01-25025 January 2006 2006/01/25-Vermont Yankee Nuclear Power Station Applicant'S Environmental Report Operating License Renewal Stage, Appendix E Project stage: Other ML0609505792006-03-22022 March 2006 GALL AMP: XI.M24, Compressed Air Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506202006-03-22022 March 2006 GALL AMP: XI.M31, Reactor Vessel Surveillance (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505962006-03-22022 March 2006 GALL AMP: XI.M27, Fire Water System (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502792006-03-22022 March 2006 GALL AMP: XI.M3, Reactor Head Closure Studs (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609506292006-03-22022 March 2006 GALL AMP: XI.M33, Selective Leaching of Materials (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506372006-03-22022 March 2006 GALL AMP: XI.M36, External Surfaces Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502842006-03-22022 March 2006 GALL AMP: XI.M4, BWR Vessel Id Attachment Welds (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502202006-03-22022 March 2006 GALL AMP: X.S1, Concrete Containment Tendon Prestress (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001472006-03-22022 March 2006 GALL AMP: XI.S8, Protective Coating Monitoring and Maintenance Program (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001342006-03-22022 March 2006 GALL AMP: XI.S5, Masonry Wall Progam (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502182006-03-22022 March 2006 GALL AMP: X.M1, Metal Fatigue of Reactor Coolant Pressure Boundary (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609505592006-03-22022 March 2006 GALL AMP: XI.M20, Open-Cycle Cooling Water System (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503472006-03-22022 March 2006 GALL AMP: XI.M11A, Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of Pressurized Water Reactors Project stage: Other ML0609505402006-03-22022 March 2006 GALL AMP: XI.M18, Bolting Integrity (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505672006-03-22022 March 2006 GALL AMP: XI.M21, Closed-Cycle Cooling Water System (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001012006-03-22022 March 2006 GALL AMP: XI.S2, ASME Section XI, Subsection Iwl (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505732006-03-22022 March 2006 GALL AMP: XI.M23, Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506102006-03-22022 March 2006 GALL AMP: XI.M29, Aboveground Steel Tanks (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502902006-03-22022 March 2006 GALL AMP: XI.M5, BWR Feedwater Nozzle (Audit Worksheet, GALL Report AMP) Project stage: Other ML0610001382006-03-22022 March 2006 GALL AMP: XI.S6, Structures Monitoring Program (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001262006-03-22022 March 2006 GALL AMP: XI.S4, 10 CFR 50, Appendix J (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502242006-03-22022 March 2006 GALL AMP: XI.E1, Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506062006-03-22022 March 2006 GALL AMP: XI.M28, Buried Piping and Tanks Surveillance (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502152006-03-22022 March 2006 GALL AMP: X.E1. Environmental Qualification (EQ) of Electric Components (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503752006-03-22022 March 2006 GALL AMP: XI.M17, Flow-Accelerated Corrosion (Audit Worksheet GALL Report AMP) Project stage: Other ML0610000782006-03-22022 March 2006 GALL AMP: XI.M38, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505702006-03-22022 March 2006 GALL AMP: XI.M22, Boraflex Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503722006-03-22022 March 2006 GALL AMP: XI.M16, PWR Vessel Internals (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503642006-03-22022 March 2006 GALL AMP: XI.M14, Loose Part Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502772006-03-22022 March 2006 GALL AMP: XI.M2, Water Chemistry (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609506242006-03-22022 March 2006 GALL AMP: XI.M32, One-Time Inspection (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503112006-03-22022 March 2006 GALL AMP: XI.M7, BWR Stress Corrosion Cracking (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502352006-03-22022 March 2006 GALL AMP: XI.E2, Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506342006-03-22022 March 2006 GALL AMP: XI.M35, One-Time Inspection of ASME Code Class 1 Small Bore Piping (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502502006-03-22022 March 2006 GALL AMP: XI.E3, Inaccessible Medium-Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001432006-03-22022 March 2006 GALL AMP: XI.S7, Rg 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505492006-03-22022 March 2006 GALL AMP: XI.M19, Steam Generator Tube Integrity (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505872006-03-22022 March 2006 GALL AMP: XI.M26, Fire Protection (Audit Worksheet GALL Report AMP) Project stage: Other ML0609501952006-03-22022 March 2006 GALL AMP: Plant-Specific (Audit Worksheet - GALL Report AMP) Project stage: Other ML0609503702006-03-22022 March 2006 GALL AMP: XI.M15, Neutron Noise Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503012006-03-22022 March 2006 GALL AMP: XI.M6, BWR Control Rod Drive Return Line Nozzle (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503282006-03-22022 March 2006 GALL AMP: XI.M9, BWR Vessels Internals (Audit Worksheet GALL Report AMP) Project stage: Other ML0610000962006-03-22022 March 2006 GALL AMP: XI.S1, ASME Section XI, Subsection IWE (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502692006-03-22022 March 2006 GALL AMP: XI.E6, Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609502622006-03-22022 March 2006 GALL AMP: XI.E5, Fuse Holder (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503312006-03-22022 March 2006 GALL AMP: XI.M10, Boric Acid Corrosion (Audit Worksheet GALL Report AMP) Project stage: Other 1998-02-28
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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] 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
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,Richarqd'Eýmch - SAMA RAls for Vermont Yankee Pa Pag*e 1!]
From: Richard Emch To: rbuckle@entergy.com Date: Wed, May 10, 2006 2:00 PM
Subject:
SAMA RAIs for Vermont Yankee Rick Buckley, Attached are the NRC staff's requests for additional information to support the review of the Severe Accident Mitigation Alternatives analysis. These RAIs will be sent to by formal letter soon, but I wanted to give you as much time as possible to respond to the RAIs because I believe the responses to some of the requests may involve a significant amount of effort. I plan to request your responses by August 11 in the letter.
Rich Emch CC: Blake Purnell; Rani Franovich; Robert Palla; Robert Schaaf; Samuel Hernandez-Quinones
1
[ cAter-ri0\GW)00001.TMP PageI Page 1 II I'c:\temp\GW}OOOO1 .TMP Mail Envelope Properties (44622A42.633: 12: 35320)
Subject:
SAMA RAIs for Vermont Yankee Creation Date Wed, May 10, 2006 2:00 PM From: Richard Emch Created By: RLE@nrc.gov Recipients Action Date & Time entergy.com Transferred 05/10/06 2:00 PM rbuckle (rbuckle@entergy.com) nrc.gov OWGWPOO2.HQGWDO01 Delivered 05/10/06 2:00 PM RLF2 CC (Rani Franovich) Opened 05/11/06 7:00 AM nrc.gov TWGWPO01.HQGWDO01 Delivered 05/10/06 2:01 PM BAPI CC (Blake Pumell) Opened 05/10/06 4:31 PM RLP3 CC (Robert Palla) Opened 05/10/06 2:23 PM SHQ CC (Samuel Hemandez-Quinones) Opened 05/10/06 2:02 PM nrc.gov TWGWPO02.HQGWDO01 Delivered 05/10/06 2:00 PM RGS CC (Robert Schaaf) Opened 05/10/06 3:02 PM Post Office Delivered Route entergy.com OWGWPOO2.HQGWDOO1 05/10/06 2:00 PM nrc.gov TWGWPO01.HQGWDOO1 05/10/06 2:01 PM nrc.gov TWGWPO02.HQGWDOO1 05/10/06 2:00 PM nrc.gov Files Size Date & Time MESSAGE 981 Wednesday, May 10, 2006 2:00 PM VY SAMA RAI.wpd 87778 Wednesday, May 10, 2006 1:46 PM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard ReplyRequested: No Return Notification: None
f c:\temp\GW}O0001 .TMP Page 2 [I Concealed
Subject:
No Security: Standard To Be Delivered: Immediate Status Tracking: Delivered & Opened
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Request for Additional Information Regarding the Analysis of Severe Accident Mitigation Alternatives (SAMAs) for the Vermont Yankee Nuclear Power Station (VYNPS)
- 1. The SAMA analysis is said to be based on the most recent version of the VYNPS Probabilistic Safety Analysis (PSA) (VY04R1). Provide the following information regarding these PSA models:
- a. Table E.1 -8 indicates that the core damage frequency (CDF) associated with station blackout sequences (Classes IBE and IBL) is 1.2E-06 per year. This is considerably more than the CDF due to loss of offsite power (LOOP) (7.2E-7 per year in Table E.1 -2) and is comparable to the total CDF due to LOOP and loss of alternating current (ac) bus initiating events. Provide the station blackout (SBO)
CDF frequency along with its derivation.
- b. The VYNPS extended power uprate (EPU) application and response to EPU requests for additional information indicate that the VY02R6 model had a CDF of 7.77E-06 per year and that this increased to 8.1 E-06 for EPU conditions. This is different from the current value of 5E-06. Provide a summary of the major Levels 1 and 2 PSA versions and their CDFs from the individual plant examination (IPE) to the present, including the version reviewed by the Boiling Water Reactors Owners Group (BWROG). Also, indicate the major changes to each version from the prior version and the major reasons for changes in the CDF.
- c. Discuss the overall conclusion of the BWROG peer review relative to the use of the VYNPS PSA.
- d. Internal flooding initiating events are the dominant contributors to CDF at VYNPS. Briefly describe the internal flooding analysis and its evolution, including internal and external peer reviews, the results of these reviews, and any subsequent model updates. It is noted that the BWROG A and B facts and observations did not include internal flooding. Clarify whether the internal flooding analysis was covered in the BWROG peer review.
- 2. Provide the following information relative to the Level 2 Analysis:
- a. Section E.1.2.2.5 implies that the binning of Level 1 results into plant damage states (PDSs) is the principal means of ensuring the proper Level 1 to Level 2 interface. Section 4.3 of the IPE states that binning is only used to summarize and report the results. Clarify the use of PDSs, including whether the containment event tree is directly linked to the Level 1 models (such that Level 1 failures are recognized by the Level 2 analysis).
- b. Provide the fission product release characteristics for each release category, including fission product release fractions, release times and duration, warning ENCLOSURE
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time, release elevation, and energy of release.
- c. Briefly describe the approach used to determine the source terms for each release category. Clarify whether new modular accident analysis program (MAAP) analyses were performed as part of the development of the current model and how the MAAP cases were selected to represent each release category (i.e., based on the frequency-dominant sequence in each category or on a conservative, bounding sequence).
- d. Clarify whether the Level 2 model was included in the BWROG peer review. If so, describe the conclusion relative to this element. If not, describe the internal and external reviews of the Level 2 analysis that have been performed, the results of these reviews, and any subsequent model updates..
- e. Approximately 75 percent of the CDF results in an "early" release. Explain this relatively high percentage and describe the containment failures/release modes that lead to these releases.
- 3. With regard to the treatment and inclusion of external events in the SAMA analysis:
- a. The environmental report (ER) uses the staff's conclusions from a prior SAMA evaluation to justify that the VYNPS fire CDF is conservative by a factor of three.
Provide a description of the conservatism in the dominant VYNPS fire CDF sequences (e.g., related to fire initiating event frequencies, severity factors, or recovery actions that were not credited) that would support this factor of three.
- b. The seismic CDF at VYNPS is not mentioned in the ER or included within in the multiplier used to account for additional SAMA benefits in external events.
Provide the estimated seismic CDF at VYNPS, and an assessment of the impact on the external event multiplier, and on the SAMA analysis results ifthe seismic CDF is included.
- c. Entergy's baseline evaluation of SAMA benefits considers only the risk reduction associated with internal events, and neglects the additional risk reduction that a SAMA could have in external events. Entergy does consider the potential for additional risk reduction in external events, but this is done in the context of an upper bound assessment in which the internal event benefits are increased by a factor of ten to account for the combined effect of external events and analysis uncertainties. The impact of external events should be reflected in the baseline evaluation, rather than combining the impact of external events with the uncertainty assessment. In this regard, provide a revised baseline evaluation (using a 7 percent discount rate) that accounts for risk reduction in both internal and external events, and an alternate case using a 3 percent discount rate.
(Note that the CDF for external events after Entergy's adjustment in the ER is 3.7 times higher than the internal events CDF. This would justify a multiplier of 4.7 or 5, rather than a multiplier of 4 as stated in the ER.)
- d. Provide an assessment of the impact on the baseline evaluation results (i.e., the revised baseline evaluation, which accounts for external events) if risk reduction
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estimates are increased to account for uncertainties in the analysis.
- 4. Provide the following information concerning the MACCS analyses:
- a. Annual meteorology data from the year 2002 were used in the MACCS2 analyses. Provide a brief statement regarding the acceptability of use of this year's data rather than a different year's data.
- b. For the emergency response assumptions, indicate what percentage of the population was assumed to evacuate.
- c. The MACCS2 analysis for VYNPS is based on a core inventory from a mid-1 980 analysis, scaled by the power level for VYNPS. Current boiling-water reactor BWR fuel management practices use longer fuel cycles (time between refueling) and result in significantly higher fuel burnups. The use of the older BWR core inventory, instead of a plant-specific cycle, could significantly underestimate the inventory of long-lived radionuclides important to population dose (such as Sr-90, Cs-1 34 and Cs-1 37), and thus impact the SAMA evaluation. Justify the adequacy of the SAMA cost benefit evaluation, given the fuel enrichment and burnup expected at VYNPS.
- 5. Provide the following with regard to the SAMA identification and screening processes:
- a. Section E.1.3.1 indicates that no simple cost-effective enhancements have been identified that will significantly improve the high confidence in low probability of failure (HCLPF) for the condensate storage tank (CST) of 0.25. Provide a cost-benefit analysis for the seismic improvement of the CST similar to that for the other SAMAs.
- b. The individual plant examination of external events (IPEEE) found that the diesel fuel oil storage tank had a HCLPF of 0.29. The ER states that all improvements identified in NUREG-1742 (which include the diesel fuel oil storage tank) have been implemented. Describe the actions taken for the diesel fuel oil storage tank.
- c. The VYNPS IPEEE lists a number of seismic improvement opportunities that are not specifically included in NUREG-1742 (specifically, seismic items 3 (ii) and 7 of IPEEE Section 7.2.2). Confirm that these have been implemented.
- d. Describe any further efforts made to determine if any SAMA candidates exist to address seismic risk beyond those already identified in the IPEEE.
- e. The listing of "risk significant terms," provided in Table E.1-3, includes numerous different internal flooding initiators, and the SAMAs considered to address these initiators. For most of these initiators, various Phase I SAMAs are identified as having been implemented, and Phase II SAMA 47 was evaluated to further reduce the internal flooding contribution.
I. For each of the previously implemented changes, clarify whether the change is credited in the current PSA. If not, provide an assessment of the impact of the change on the internal flood CDF. If the change has already been credited, it would not appear to have been completely effective (as evidenced by the high residual risk of the initiating event) and additional SAMAs specific to the flooding event listed in the table
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could be cost-beneficial.
ii. Phase II SAMA 47 does not appear to address any of the specific internal flooding events listed in the table. Clarify which specific flooding scenario is addressed by SAMA 47.
- f. Provide the current status of the 14 opportunities for improvement identified in the IPEEE for internal flooding, indicating if they have been implemented and if credit is taken for them in the current PSA. For those not implemented, indicate their importance and why they should not be considered as SAMA candidates.
- g. The fire CDF, even after the factor of three reduction, is almost four times the internal events CDF. While the ER states that the improvements that address fire risk at VYNPS recommended in NUREG-1 742 have all been implemented, the fire CDF is still substantial. SAMA candidates based on internal risk contributors will not necessarily address the fire risk. For each fire area or dominant fire sequence, explain what measures were taken to further reduce risk, and explain why the fire CDFs can not be further reduced in a cost-effective manner.
- h. In Table E.1 -3, the entry for "Transient with [power conversion system] available
- initiating event" (risk reduction worth (RRW) of 1.0287) cites SAMA 046 to improve main steam isolation valve (MSIV) design. Explain how this impacts the initiator which must have the MSIV open.
As an alternative to Phase II SAMA 2, consider operating procedure revisions to provide additional space cooling via the use of portable equipment or blocking doors open.
Phase II SAMA 59 considers installing instruments for opening safety/relief valves (SRVs) for medium loss-of-coolant accidents (LOCAs). Explain why the benefits of this SAMA in small LOCAs and transients are not included in the benefit assessment.
- k. Table E.1 -3 indicates that failure of torus venting components has a RRW of 1.0948. Describe the failures considered in this assessment. Provide an assessment of the costs and benefits associated with: 1) adding redundant components, and 2) converting the vent system to a passive design.
The Table E.1 -3 entry for "Operator Action: Operator fails to start a [turbine building closed cooling water] (TBCCW) pump" indicates that no Phase II SAMAs were recommended. Provide an assessment of the costs and benefits of starting a TBCCW pump automatically.
- 6. Provide the following with regard to the Phase II cost-benefit evaluations:
- a. For a number of the Phase II SAMAs listed in Table E.2-1, the information provided does not sufficiently describe the associated modifications and what is included in the cost estimate. Provide a more detailed description of the modifications for Phase II SAMAs 6, 9, 10, 13, 23, 24, 33, 41, 52, 56, and 63.
- b. Several of the cost estimates provided were drawn from previous SAMA analyses for a dual-unit site (e.g., Peach Bottom). As such, many of those cost estimates reflect the cost for implementation in two units. Since VYNPS is a
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single-unit site, some of the cost estimates should be one-half of what has been cited (i.e., Phase II SAMAs 29, 35, 40, 49, 50, 51, 52, 53, and 54) while others are specific to a plant's design, such as the number of valves or batteries that need to be replaced or added (i.e., Phase II SAMAs 46, 55, and 60). For these cases, provide appropriate (specific to VYNPS) cost estimates. (Note that Phase II SAMAs 49, 50, 51, 53, and 54 are close to being potentially cost-beneficial when a 3 percent real discount rate is used.)
- c. Phase II SAMA 27 uses the same analysis case (Strengthen Containment) as Phase II SAMAs 13, 18, and 19 to evaluate the benefit. Yet, Table E.2-1 lists SAMA 27 as having a CDF reduction of 0.0 percent, while all other SAMAs for this analysis case list a CDF reduction of 7.36 percent. Explain this discrepancy.
- d. For Phase II SAMA 28 and 29 (and others) a 3 percent reduction in CDF was estimated by changing the time available to recover off-site power before high-pressure coolant injection/reactor core isolation coolant (RCIC) are lost from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. According to Table E.1-8, late SBO sequences (Class IBL) contribute about 17 percent of the total CDF. Explain why only a 3 percent reduction in CDF was estimated for this SAMA.
- e. For Phase II SAMA 42, a 1.3 percent reduction in offsite dose was estimated by reassigning the interfacing-systems loss-of-coolant accident (ISLOCA) sequences to the same end states as medium LOCAs. For Phase II SAMA 43, a 1.2 percent reduction in offsite dose was obtained by eliminating the CDF contribution due to ISLOCA. One would expect the dose reduction for SAMA 43 to be greater than that for SAMA 42. Also, the CDF contribution from ISLOCA is given in Table E.1 -2 as 0.32 percent, while the CDF reduction from SAMA 43 is given as 0.83 percent. Explain these apparent discrepancies.
- f. Phase II SAMA 57 is stated to include items which reduce the contribution of anticipated transient without scram. Indicate which items are included.
- g. Phase II SAMA 59 involves providing instrument signals to open SRVs for medium LOCA. Discuss whether the signals already exist in the automatic depressurization system.
- h. Phase II SAMA 63, Control Containment Venting Within a Narrow Band of Pressure, is intended to eliminate failures associated with successful venting.
The benefit of this SAMA was determined by reducing the operator failure to vent by a factor of three. It is not clear that reducing the failure to vent probability is related to the actual benefit from this SAMA. Also, the cost of $250,000 appears high for what appears to be a procedure and training issue. Justify the benefit and cost for this SAMA.
Phase II SAMA 64, Provide Cross Tie from the residual heat removal service water (RHRSW) System to residual heat removal Loop B, has an estimated CDF reduction of 0.2 percent. The description given in Table E.1 -3 for term diesel fire pump and John Deere Diesel for Alternate Injection, though, indicates that this term involves a cross tie for fire protection to RHRSW and has a RRW of 1.0584. Describe this SAMA more completely and indicate why the reduction in CDF is so small relative to the RRW.
In Table E.2-1, the percent change in CDF and population dose is reported for each analysis case. However, the change in the offsite economic cost risk
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(OECR) is not reported. Provide the change in the OECR for each analysis case.
- 7. For certain SAMAs considered in the ER, there may be lower-cost alternatives that could achieve much of the risk reduction at a lower cost. In this regard, discuss whether any lower-cost alternatives to those Phase II SAMAs considered in the ER would be viable and potentially cost-beneficial. Evaluate the following SAMAs (previously found to be potentially cost-beneficial at other plants), or indicate ifthe particular SAMA has already been considered. Ifthe latter, indicate whether the SAMA has been implemented or has been determined to not be cost-beneficial at VYNPS:
- a. Use portable generator to extend the coping time in loss of ac power events (to power battery chargers.
- b. Enhance direct current (dc) power availability (provide cables from diesel generator or another source to directly power battery chargers).
- c. Provide alternate dc feeds (using a portable generator) to panels supplied only by dc bus.
- d. Modify procedures and training to allow operators to cross-tie emergency ac buses under emergency conditions which require operation of critical equipment.
- e. Develop guidance/procedures for local, manual control of RCIC following loss of dc power.