Letter Sequence RAI |
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MONTHYEARML0331000472003-10-30030 October 2003 Sign-in Sheet for 10/30/2003 Meeting with ENVY and ENO Re to Discuss Arts/Mellla, Alternate Source Term, and Extended Power Uprate Aplications Project stage: Meeting ML0330403972003-10-30030 October 2003 Meeting Handouts for Meeting with Entergy Re Issues for Alternate Source Term, Power Uprate & Acts/Mellla Application Project stage: Meeting ML0331000232003-11-19019 November 2003 10/30/2003 Meeting with Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc Regarding Arts/Mellla, Alternate Source Term, and Extended Power Uprate Applications Project stage: Meeting ML0330902512003-12-0101 December 2003 Alternative Source Term Request for Additional Information Project stage: RAI ML0400606952004-01-0606 January 2004 Draft Request for Additional Information Project stage: Draft RAI ML0403000882004-01-30030 January 2004 Draft Request for Additional Information Project stage: Draft RAI ML0402002262004-02-0202 February 2004 Request for Withholding Information from Public Disclosure, Calculation Psat 3019CF.QA.04, Post LOCA (loss-of-coolant Accident) Suppression Pool Ph for Vermont Yankee Project stage: Withholding Request Acceptance ML0404800772004-02-17017 February 2004 Draft Request for Additional Information Project stage: Draft RAI ML0404902362004-02-18018 February 2004 Draft Request for Additional Information Project stage: Draft RAI ML0413101722004-11-12012 November 2004 Environmental Assessment and Finding of No Significant Impact Related to the Issuance of Exemption to 10 CFR Part 50, Appendix J Project stage: Approval ML0413103592005-03-17017 March 2005 Issuance of Exemption from 10 CFR Part 50, Appendix J Project stage: Approval ML0412804902005-03-29029 March 2005 License Amendment, Alternative Source Term Project stage: Acceptance Review ML0509003992005-03-29029 March 2005 Technical Specification Pages Re Alternative Source Term Project stage: Acceptance Review 2004-11-12
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Category:Letter
MONTHYEARBVY 24-005, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-01-30030 January 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-004, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-01-23023 January 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-003, Nuclear Onsite Property Damage Insurance2024-01-0404 January 2024 Nuclear Onsite Property Damage Insurance BVY 24-001, Pre-Notice of Disbursement from Decommissioning Trust2024-01-0202 January 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-030, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-12-20020 December 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-029, Proof of Financial Protection2023-12-12012 December 2023 Proof of Financial Protection BVY 23-028, Pre-Notice of Disbursement from Decommissioning Trust2023-11-28028 November 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-027, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-11-21021 November 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-026, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-11-13013 November 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-025, Pre-Notice of Disbursement from Decommissioning Trust2023-11-0202 November 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-023, License Amendment Request Addition of License Condition 3.K, License Termination Plan; Proposed Change No. 3172023-10-10010 October 2023 License Amendment Request Addition of License Condition 3.K, License Termination Plan; Proposed Change No. 317 IR 07200059/20234012023-10-0505 October 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200059/2023401 BVY 23-022, Pre-Notice of Disbursement from Decommissioning Trust2023-08-23023 August 2023 Pre-Notice of Disbursement from Decommissioning Trust IR 05000271/20230012023-08-15015 August 2023 Northstar Nuclear Decommissioning Company, Llc., Vermont Yankee Nuclear Power Station, - NRC Inspection Report 05000271/2023001 BVY 23-021, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-08-0202 August 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-020, Pre-Notice of Disbursement from Decommissioning Trust2023-08-0202 August 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-019, Update to 2022 Radiological Effluent Release Report2023-07-24024 July 2023 Update to 2022 Radiological Effluent Release Report BVY 23-018, Update to Nuclear Onsite Property Damage Insurance2023-07-12012 July 2023 Update to Nuclear Onsite Property Damage Insurance BVY 23-017, Pre-Notice of Disbursement from Decommissioning Trust2023-06-29029 June 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-015, Report of Investigation Pursuant to 1O CFR 20, Appendix G2023-06-0505 June 2023 Report of Investigation Pursuant to 1O CFR 20, Appendix G BVY 23-016, 10 CFR 72.48 Report2023-06-0505 June 2023 10 CFR 72.48 Report BVY 23-014, Pre-Notice of Disbursement from Decommissioning Trust2023-05-31031 May 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-013, 2022 Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Radiological Environmental Operating Report BVY 23-011, 2022 Radiological Effluent Release Report2023-05-10010 May 2023 2022 Radiological Effluent Release Report BVY 23-012, Pre-Notice of Disbursement from Decommissioning Trust2023-05-0202 May 2023 Pre-Notice of Disbursement from Decommissioning Trust ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment BVY 23-009, 2022 Individual Monitoring NRC Form 5 Report2023-04-24024 April 2023 2022 Individual Monitoring NRC Form 5 Report BVY 23-008, Pre-Notice of Disbursement from Decommissioning Trust2023-04-0606 April 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-007, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-03-29029 March 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 23-006, Status of Decommissioning and Spent Fuel Management Fund for Year Ending 20222023-03-29029 March 2023 Status of Decommissioning and Spent Fuel Management Fund for Year Ending 2022 BVY 23-005, Nuclear Onsite Property Damage Insurance2023-03-13013 March 2023 Nuclear Onsite Property Damage Insurance BVY 23-004, Pre-Notice of Disbursement from Decommissioning Trust2023-03-0202 March 2023 Pre-Notice of Disbursement from Decommissioning Trust ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000271/20220022023-02-22022 February 2023 Northstar Nuclear Decommissioning Company, LLC, Vermont Yankee Nuclear Power Station - NRC Inspection Report No. 05000271/2022002 BVY 23-003, Pre-Notice of Disbursement from Decommissioning Trust2023-01-31031 January 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-030, Documentary Evidence of Performance Bond2022-12-30030 December 2022 Documentary Evidence of Performance Bond ML22347A2792022-12-21021 December 2022 Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022 IR 05000271/20224012022-12-15015 December 2022 NRC Inspection Report No. 05000271/2022401, Northstar Nuclear Decommissioning Company, LLC, Vermont Yankee Nuclear Power Station, Vernon, Vermont (Letter Only) BVY 22-028, Re Proof of Financial Protection2022-11-28028 November 2022 Re Proof of Financial Protection BVY 22-027, Bvy 22-027; Pre-Notice of Disbursement from Decommissioning Trust for Vermont Yankee Nuclear Power Station2022-11-11011 November 2022 Bvy 22-027; Pre-Notice of Disbursement from Decommissioning Trust for Vermont Yankee Nuclear Power Station BVY 22-026, Pre-Notice of Disbursement from Decommissioning Trust2022-10-31031 October 2022 Pre-Notice of Disbursement from Decommissioning Trust ML22273A1492022-10-0404 October 2022 Review of Decommissioning Funding Status 2022 BVY 22-025, Pre-Notice of Disbursement from Decommissioning Trust2022-10-0404 October 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-023, Pre-Notice of Disbursement from Decommissioning Trust2022-09-0101 September 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-022, Report of Investigation Pursuant to 10 CFR 20, Appendix G2022-08-22022 August 2022 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 22-021, Report of Investigation Pursuant to 10 CFR 20, Appendix G2022-08-16016 August 2022 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 22-020, Pre-Notice of Disbursement from Decommissioning Trust2022-08-0101 August 2022 Pre-Notice of Disbursement from Decommissioning Trust IR 05000271/20220012022-08-0101 August 2022 NRC Inspection Report No. 05000271/2022001, Northstar Nuclear Decommissioning Company, LLC, Vermont Yankee Nuclear Power Station, Vernon, Vermont BVY 22-019, Pre-Notice of Disbursement from Decommissioning Trust2022-07-0606 July 2022 Pre-Notice of Disbursement from Decommissioning Trust BVY 22-013, Notification of Revised Decommissioning Cost Estimate2022-06-17017 June 2022 Notification of Revised Decommissioning Cost Estimate 2024-01-04
[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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Text
December 1, 2003 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
VERMONT YANKEE NUCLEAR POWER STATION - ALTERNATIVE SOURCE TERM REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MC0253)
Dear Mr. Kansler:
By letter dated July 31, 2003, as supplemented on October 10, 2003, Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (the licensees) submitted an amendment application to incorporate an Alternative Source Term methodology into the Vermont Yankee Nuclear Power Station licensing basis. In order for the staff to complete its review of this application, we are requesting a response to the questions provided in the enclosure.
Please provide your response to these questions by December 30, 2003.
If you have any questions please contact me at (301) 415-3016.
Sincerely,
/RA/
Robert M. Pulsifer, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-271
Enclosure:
As stated cc w/encl: See next page
REQUEST FOR ADDITIONAL INFORMATION ALTERNATE SOURCE TERM ENTERGY NUCLEAR VERMONT YANKEE, LLC VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271
- 1. In the application dated July 31, 2003, on page 54 of Attachment 5, it is indicated that seismic criteria were used to evaluate the ruggedness of the alternative leakage treatment pathways and boundary piping, equipment, and supports. Describe the seismic criteria used.
- 2. Provide a list of the outliers and their resolution.
- 3. Please provide a copy of reference 28, specified in your July 31, 2003 submittal on page 51 of Attachment 5.
- 4. The values of certain containment volumes used in the pH calculations (page 9 of the analysis) appear to differ from the design values given in the Updated Final Safety Analysis Report (UFSAR), Revision 17, Table 1.7.4. These values were for suppression pool volume, drywell volume, and torus airspace. Please explain the values selected for the pH calculations.
- 5. The amount of water added with the sodium borate from the Standby Liquid Control System to the suppression pool is not specified (i.e., the borate concentration). This additional water may affect the pH calculation. Please identify the amount of water added to the suppression pool with the borate, and discuss its potential effect on the pH calculations.
- 6. In the Safety Assessment (Attachment 5) for this amendment request, on page 8 it states that an assumed post-isolation unfiltered inleakage rate equal to the pre-isolation unfiltered intake rate (3700 cubic feet per minute(cfm)) into the control room is used for the analyses. No credit was taken for manually placing the control room ventilation system into recirculation mode after the accident. Control room isolation is only achieved through manual initiation. In effect, these assumptions imply no credit for control room isolation after a design basis accident (DBA).
- a. Have you performed control room envelope inleakage testing? If so, what was the result, and how does that compare to the assumption of 3700 cfm of unfiltered inleakage?
- b. Have you determined how the dose results of each of the postulated DBAs would be affected by assuming manual control room isolation occurs with a lesser unfiltered inleakage rate than currently assumed? A greater unfiltered inleakage rate?
- 7. You propose to take credit for drywell spray removal of iodine. Do the drywell sprays meet requirements given in Title 10 of the Code of Federal Regulations, Part 50, Appendix A, General Design Criteria 41, 42 and 43 with regard to containment atmosphere cleanup systems? Can the drywell sprays perform their safety function with
a single failure? Have you verified the capability of the system to deliver the assumed spray flow?
- 8. With respect to Attachment 5, please provide a detailed description of all inputs and assumptions for all relative concentration (X/Q) values not previously approved by the U.S. Nuclear Regulatory Commission (NRC). This appears to include the exclusion area boundary ground level reactor building (RB) bypass and siding, and stack 2-8 and 8-24 hour X/Q values; the low population zone (LPZ) ground level main steam isolation valve (MSIV) and ground level RB bypass and siding X/Q values; and the control room X/Q values for the loss-of-coolant accident (LOCA), main steam line break (MSLB), and fuel handling accidents. Note 3 of Table 2-6 states that control rod drop accident ground level release LPZ X/Q values are documented in the UFSAR. Were these values previously approved by the NRC? If so, please provide a reference citation.
- 9. For the LOCA LPZ estimates, why is there a difference between the ground level MSIV and RB siding and bypass X/Q values? Is this only because the AEOLUS-3 methodology was used in some of the calculations and the SKIRON-II methodology used when making other estimates? Provide a description of the differences between the AEOLUS-3, SKIRON-II and Regulatory Guide (RG) 1.145, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants, methodologies and the expected impact of these differences on resultant estimated X/Q values.
- 10. What are the specifics of your MSLB puff calculation and calculational inputs and assumptions used in the comparison calculations with the puff methodology described in RG 1.194, Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants?
- 11. What is the distance between the turbine building release location and the control room ventilation intake location?
Vermont Yankee Nuclear Power Station cc:
Regional Administrator, Region I Mr. Raymond N. McCandless U. S. Nuclear Regulatory Commission Vermont Department of Health 475 Allendale Road Division of Occupational King of Prussia, PA 19406-1415 and Radiological Health 108 Cherry Street Mr. David R. Lewis Burlington, VT 05402 Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W. Manager, Licensing Washington, DC 20037-1128 Entergy Nuclear Vermont Yankee, LLC P.O. Box 0500 Ms. Christine S. Salembier, Commissioner 185 Old Ferry Road Vermont Department of Public Service Brattleboro, VT 05302-0500 112 State Street Montpelier, VT 05620-2601 Resident Inspector Vermont Yankee Nuclear Power Station Mr. Michael H. Dworkin, Chairman U. S. Nuclear Regulatory Commission Public Service Board P.O. Box 176 State of Vermont Vernon, VT 05354 112 State Street Montpelier, VT 05620-2701 Director, Massachusetts Emergency Management Agency Chairman, Board of Selectmen ATTN: James Muckerheide Town of Vernon 400 Worcester Rd.
P.O. Box 116 Framingham, MA 01702-5399 Vernon, VT 05354-0116 Jonathan M. Block, Esq.
Mr. Michael Hamer Main Street Operating Experience Coordinator P.O. Box 566 Vermont Yankee Nuclear Power Station Putney, VT 05346-0566 320 Governor Hunt Road Vernon, VT 05354 Mr. John Kelly Director, Nuclear Safety Assurance G. Dana Bisbee, Esq. Entergy Nuclear Operations, Inc.
Deputy Attorney General 440 Hamilton Avenue 33 Capitol Street White Plains, NY 10601 Concord, NH 03301-6937 Mr. Gary Taylor Chief, Safety Unit Chief Executive Officer Office of the Attorney General Entergy Operations One Ashburton Place, 19th Floor 1340 Echelon Parkway Boston, MA 02108 Jackson, MS 39213 Ms. Deborah B. Katz Box 83 Shelburne Falls, MA 01370
Vermont Yankee Nuclear Power Station cc:
Mr. John Herron Mr. Ron Toole Sr. VP and Chief Operating Officer BWR SRC Consultant Entergy Nuclear Operations, Inc. 605 West Horner Street 440 Hamilton Avenue Ebensburg, PA 15931 White Plains, NY 10601 Ms. Stacey Lousteau Mr. Dan Pace Treasury Department Vice President, Engineering Entergy Entergy Services, Inc.
Nuclear Operations, Inc. 639 Loyola Avenue, Mail Stop L-ENT-15E 440 Hamilton Avenue New Orleans, LA 70113 White Plains, NY 10601 Mr. Randall Edington Vice President, Operations Support Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Director of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. John M. Fulton Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Jay K. Thayer Site Vice President Entergy Nuclear Operations, Inc.
Vermont Yankee Nuclear Power Station P.O. Box 0500 185 Old Ferry Road Brattleboro, VT 05302-0500 Mr. Ken L. Graesser BWR SRC Consultant 38832 N. Ashley Drive Lake Villa, IL 60046 Mr. Jim Sniezek BWR SRC Consultant 14601 Layhill Road Silver Spring, MD 20906
ML033090251 OFFICE PDI-2/PM PDI-2/LA SPSB/SC PDI-2/SC EMCB/SC EMEB/SC NAME RPulsifer CRaynor RDennig JBoska for JClifford LLund KManoly DATE 11/13/03 11/07/03 11/24/03 11/25/03 11/20/03 11/13/03