Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: BVY 06-014, E-mail, Meyer, Entergy, to Ennis, NRR, VY EPU, BVY 06-019, Vermont Yankee, Extended Power Uprate - Regulatory Commitment Information Regarding Steam Dryer Monitoring and Fiv Effects, BVY 06-031, Revision 1 to Steam Dryer Monitoring Plan, BVY 06-039, Vermont Yankee Nuclear Power Station Revision 2 to Steam Dryer Monitoring Plan, BVY 06-051, Vermont Yankee - Summary of Reactor Feedwater Pump Trip Analysis, BVY 06-056, Submittal of Vermont Yankee Report on the Results of Steam Dryer Monitoring, BVY 06-080, Vermont Yankee, Extended Power Uprate - License Amendment No. 229 Clarifications to Nrc'S Final Safety Evaluation, BVY 06-087, Update to Information Related to 10CFR50.63 Licensing Basis, ML033140025, ML033160187, ML040080573, ML040090411, ML041810022, ML041810433, ML042180463, ML042650265, ML042680087, ML043020494, ML050060086, ML050280310, ML050450423, ML050940230, ML050940242, ML052080154, ML053490030, ML053530148, ML060330490, ML060410119, ML061290566, ML061870277
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MONTHYEARML0323403792003-08-31031 August 2003 Technical Assessment of Quad Cities Unit 2, Steam Dryer Failure - Determination of Root Cause & Extent of Condition Project stage: Request ML0328104472003-10-0101 October 2003 Vermont Yankee - Technical Specification Proposed Change No. 263, Supplemental No. 1 Regarding Extended Power Uprate, Technical Review Guidance Project stage: Request 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 ML0331000472003-10-30030 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 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 ML0334403992003-12-0808 December 2003 Technical Specification Proposed Change No. 263 Regarding Extended Power Uprate - State of Vermont Questions Project stage: Request ML0331800882003-12-15015 December 2003 Vermont Yankee Nuclear Power Station - Extended Power Uprate Acceptance Review Project stage: Acceptance Review ML0331601872003-12-16016 December 2003 Vermont Yankee Nuclear Power Station, Withholding from Public Disclosure, NEDC-33090P, Revision 0, Project stage: Other ML0430204942003-12-24024 December 2003 NRR Work Request to IEPB-A Project stage: Other ML0336401382003-12-30030 December 2003 Vermont Yankee, Draft Request for Additional Information Project stage: Draft RAI ML0400805732004-01-0707 January 2004 NPSH for BWR Extended Power Upgrades (EPU) Project stage: Other ML0400904112004-01-0909 January 2004 NPSH for BWR Extended Power Upgrades (EPU) Project stage: Other BVY 04-009, Vermont Yankee - Technical Specification Proposed Change No. 263, Supplement No. 4 Regarding Extended Power Uprate, NRC Acceptance Review2004-01-31031 January 2004 Vermont Yankee - Technical Specification Proposed Change No. 263, Supplement No. 4 Regarding Extended Power Uprate, NRC Acceptance Review Project stage: Supplement ML0404001612004-02-19019 February 2004 Vermont Yankee Nuclear Power Station, Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML0405003022004-02-20020 February 2004 Vermont Yankee Nuclear Power Station - Extended Power Uprate Acceptance Review Project stage: Acceptance Review ML0406306032004-02-27027 February 2004 G20040138/LTR-04-0107 - Sen. James Jeffords & Patrick Leahy Ltr Proposed Power Uprate at Vermont Yankee Project stage: Request ML0408500762004-03-15015 March 2004 G20040206/LTR-04-0168 - Ltr. Rep. Michael Dworkin Independent Safety Asessment of Vermont Yankee Project stage: Request ML0404100222004-03-19019 March 2004 Vermont Yankee Nuclear Power Station, Withholding from Public Disclosure, Responses to Request for Additional Information (Attachment 1 to Letter Bvy 04-008) Project stage: RAI ML0411007042004-03-31031 March 2004 Enclosure 1, March 31, 2004, Vermont Yankee Annual Assessment Meeting Power Up-Rate Public Meeting Attendance List Project stage: Meeting ML0411203582004-03-31031 March 2004 Transcription Meeting Summary, 03/31/2004 Category 3 Meeting with Public to Discuss Proposed Power Uprate, Pages 1-124. Project stage: Meeting ML0410603312004-05-17017 May 2004 Enclosures 3 - 13, 03/31/2004 Meeting Summary for Vermont Yankee Project stage: Meeting ML0411201272004-05-17017 May 2004 Category 3 Public Meeting Summary with Entergy Nuclear Operations Inc. to Discuss Proposed Power Uprate for Vermont Yankee Nuclear Power Station Project stage: Meeting ML0411203682004-05-17017 May 2004 Enclosure 14, 03/31/2004 Meeting Summary for Vermont Yankee. Slides Presentation Proposed Power Uprate Project stage: Meeting ML0414500202004-05-28028 May 2004 Vermont Yankee - Request for Additional Information - Extended Power Uprate Project stage: RAI ML0418100222004-06-25025 June 2004 Compliance with NRC Regulatory Compliance Project stage: Other ML0331400252004-06-25025 June 2004 Vermont, Notice of Consideration of Issuance of Amendment to Facility Operating License for Extended Power Uprate and Opportunity for Hearing Project stage: Other ML0418104332004-06-29029 June 2004 Vermont Yankee, 06/29/04 E-mail - Compliance with NRC Regulatory Compliance Project stage: Other ML0417400392004-07-0606 July 2004 Vermont Nuclear Power Station, Request for Additional Information, Extended Power Uprate. TAC No. MC0761 Project stage: RAI BVY 04-081, Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263 - Supplement No. 11 Extended Power Uprate - Response to Request for Additional Information2004-08-12012 August 2004 Vermont Yankee Nuclear Power Station, Technical Specification Proposed Change No. 263 - Supplement No. 11 Extended Power Uprate - Response to Request for Additional Information Project stage: Supplement ML0421804632004-08-31031 August 2004 Vermont Yankee Nuclear Power Station, Withholding from Public Disclosure, Project stage: Other ML0424405372004-09-0101 September 2004 Vermont Yankee Nuclear Power Station, Request for Additional Information - Extended Power Uprate Project stage: RAI ML0425103952004-09-0202 September 2004 Attachments 1 Through 4 of 07/21/2004 & 07/22/2004 Summary of Meeting with Entergy Nuclear Operations, Inc., on Steam Dryer Analysis Project stage: Meeting ML0422200222004-09-0202 September 2004 07/21/2004 & 07/22/2004 Summary of Meeting with Entergy Nuclear Operations, Inc., on Steam Dryer Analysis Project stage: Meeting BVY 04-097, Vermont Yankee Nuclear Power Station - Technical Specification Proposed Change No. 263 - Supplement No. 13 Extended Power Uprate - Response to Steam Dryer Action Items2004-09-14014 September 2004 Vermont Yankee Nuclear Power Station - Technical Specification Proposed Change No. 263 - Supplement No. 13 Extended Power Uprate - Response to Steam Dryer Action Items Project stage: Supplement BVY 04-098, Vermont Yankee - Technical Specification Proposed Change No. 263 - Supplement No. 14 Extended Power Uprate - Response to Request for Additional Information2004-09-15015 September 2004 Vermont Yankee - Technical Specification Proposed Change No. 263 - Supplement No. 14 Extended Power Uprate - Response to Request for Additional Information Project stage: Supplement BVY 04-100, Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 - Supplement No. 15 Extended Power Uprate - Response to Steam Dryer Action Item No. 22004-09-23023 September 2004 Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 - Supplement No. 15 Extended Power Uprate - Response to Steam Dryer Action Item No. 2 Project stage: Supplement ML0505901452004-09-29029 September 2004 Vermont Yankee Attendance List for Sept. 29, 2004 Meeting Steam Dryer Analysis Project stage: Meeting BVY 04-113, Vermont Yankee Nuclear Power Station - Proposed Technical Specification Change No. 263 - Supplement No. 20 Extended Power Uprate - Meeting on Steam Dryer Analysis Meeting Presentation Slides2004-09-29029 September 2004 Vermont Yankee Nuclear Power Station - Proposed Technical Specification Change No. 263 - Supplement No. 20 Extended Power Uprate - Meeting on Steam Dryer Analysis Meeting Presentation Slides Project stage: Supplement BVY 04-101, Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 - Supplement No. 16 Extended Power Uprate - Additional Information Related to Request for Additional Information EMEB-B-52004-09-30030 September 2004 Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 - Supplement No. 16 Extended Power Uprate - Additional Information Related to Request for Additional Information EMEB-B-5 Project stage: Supplement BVY 04-107, Vermont Yankee - Technical Specification Proposed Change No. 263 - Supplement No. 17 Extended Power Uprate - Response to Request for Additional Information Related to the 10 CFR 50 Appendix R Timeline2004-09-30030 September 2004 Vermont Yankee - Technical Specification Proposed Change No. 263 - Supplement No. 17 Extended Power Uprate - Response to Request for Additional Information Related to the 10 CFR 50 Appendix R Timeline Project stage: Supplement BVY 04-106, Vermont Yankee - Technical Specification Proposed Change No. 263 - Supplement No. 18 Extended Power Uprate - ECCS Pump Net Positive Suction Head Margin2004-10-0505 October 2004 Vermont Yankee - Technical Specification Proposed Change No. 263 - Supplement No. 18 Extended Power Uprate - ECCS Pump Net Positive Suction Head Margin Project stage: Supplement BVY 04-109, Vermont Yankee Nuclear Power Station - Technical Specification Proposed Change No. 263 - Supplement No. 19 Extended Power Uprate - Initial Plant Test Program2004-10-0707 October 2004 Vermont Yankee Nuclear Power Station - Technical Specification Proposed Change No. 263 - Supplement No. 19 Extended Power Uprate - Initial Plant Test Program Project stage: Supplement ML0426800872004-10-13013 October 2004 Vermont Yankee Nuclear Power Station- Technical Audit of Steam Dryer Analysis in Support of Extended Power Uprate Request Project stage: Other ML0426502652004-10-15015 October 2004 Vermont Yankee Nuclear Power Station - Extended Power Uprate Review Schedule Project stage: Other ML0500600862004-11-12012 November 2004 Content of VY Steam Dryer Audit Report, Non-Proprietary Project stage: Other ML0431303472004-12-0101 December 2004 Request for Withholding Information from Public Disclosure, Vermont Yankee Project stage: Withholding Request Acceptance ML0431303182004-12-0101 December 2004 Request for Withholding Information from Public Disclosure, Vermont Yankee Project stage: Withholding Request Acceptance BVY 04-131, Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 - Supplement No. 22 Extended Power Uprate - 10 CFR 50 Appendix R Timeline Verification2004-12-0808 December 2004 Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 - Supplement No. 22 Extended Power Uprate - 10 CFR 50 Appendix R Timeline Verification Project stage: Supplement BVY 04-129, Vermont Yankee - Technical Specification Proposed Change No. 263 - Supplement No. 21 Extended Power Uprate - Steam Dryer Power Ascension Testing2004-12-0909 December 2004 Vermont Yankee - Technical Specification Proposed Change No. 263 - Supplement No. 21 Extended Power Uprate - Steam Dryer Power Ascension Testing Project stage: Supplement ML0433700492004-12-21021 December 2004 Vermont Yankee, Request for Additional Information, Extended Power Uprate, Project stage: RAI 2004-12-09
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Category:Letter type:BVY
MONTHYEARBVY 24-024, Pre-Notice of Disbursement from Decommissioning Trust2024-07-30030 July 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-023, Pre-Notice of Disbursement from Decommissioning Trust2024-07-0202 July 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-022, Pre-Notice of Disbursement from Decommissioning Trust2024-05-30030 May 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-020, Biennial Update of Quality Assurance Program Manual2024-05-22022 May 2024 Biennial Update of Quality Assurance Program Manual BVY 24-019, 2023 Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Radiological Environmental Operating Report BVY 24-017, Pre-Notice of Disbursement from Decommissioning Trust2024-05-0606 May 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-018, 2023 Radiological Effluent Release Report2024-05-0505 May 2024 2023 Radiological Effluent Release Report BVY 24-016, 2023 Individual Monitoring NRC Form 5 Report2024-04-18018 April 2024 2023 Individual Monitoring NRC Form 5 Report BVY 24-014, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-04-0101 April 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-015, Pre-Notice of Disbursement from Decommissioning Trust2024-04-0101 April 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-012, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-03-14014 March 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-011, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-03-0606 March 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-010, Pre-Notice of Disbursement from Decommissioning Trust2024-03-0505 March 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-009, Withdrawal of License Amendment Request to Add License Condition 3.K, “License Termination Plan;” Proposed Change No. 3172024-02-27027 February 2024 Withdrawal of License Amendment Request to Add License Condition 3.K, “License Termination Plan;” Proposed Change No. 317 BVY 24-008, ISFSI, Annual Radioactive Effluent Release Report2024-02-26026 February 2024 ISFSI, Annual Radioactive Effluent Release Report BVY 24-006, Pre-Notice of Disbursement from Decommissioning Trust2024-02-0606 February 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 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 BVY 23-022, Pre-Notice of Disbursement from Decommissioning Trust2023-08-23023 August 2023 Pre-Notice of Disbursement from Decommissioning Trust BVY 23-020, Pre-Notice of Disbursement from Decommissioning Trust2023-08-0202 August 2023 Pre-Notice of Disbursement from Decommissioning Trust 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 23-019, 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 23-016, 10 CFR 72.48 Report2023-06-0505 June 2023 10 CFR 72.48 Report 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 23-014, 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 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 23-006, 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 23-007, 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 23-005, 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 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 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 2024-07-30
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Text
Entergy Nuclear Operations, Inc.
Vermont Yankee P 0 Box 0500
._En tergy 185 Old Ferry Road Brattleboro, VT 05302-0500 Tel 802 257 5271 June 5, 2006 Docket No. 50-271 BVY 06-051 TAC No. MC0761 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Vermont Yankee Nuclear Power Station Summary of Reactor Feedwater PumDo TrID Analysis
References:
- 1) Letter, Entergy to USNRC, "Vermont Yankee Nuclear Power Station, License No. DPR-28 (Docket No. 50-271), Technical Specification Proposed Change No. 263, Extended Power Uprate," BVY 03-80, dated September 10, 2003
- 2) Letter, USNRC to Entergy, "Vermont Yankee Nuclear Power Station -
Issuance of Amendment RE: Extended Power Uprate (TAC No.
MC0761 ),"NVY 06-028, dated March 2, 2006 This letter provides information pursuant to a License Condition established in connection with the application by Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (Entergy) for a license amendment (Reference 1, as supplemented and approved by Reference 2) to increase the maximum authorized power level of the Vermont Yankee Nuclear Power Station from 1593 megawatts thermal (MWt) to 1912 MWt.
License Condition 31L.2 requires that within 30 days at nominal full-power operation following successful performance of the transient test discussed in License Condition 31L.1, that Entergy, through performance of additional testing and/or analysis of the testing results, confirm that the loss of one reactor feedwater pump will not result in a reactor trip. includes a summary of the analysis performed to satisfy License Condition 31L.2. Entergy's analysis has concluded that the loss of a feedwater pump will not result in a reactor trip and based on this no additional testing is planned.
BVY 06-051 Docket No. 50-271 Page 2 of 2 There are no new regulatory commitments contained in this submittal.
If you have any questions or require additional information, please contact Mr. James DeVincentis at (802) 258-4236.
Sincerely, Ted A. Sullivan Site Vice President Vermont Yankee Nuclear Power Station Attachment (1) - Summary of Reactor Feedwater Pump Trip Analysis cc: Mr. Samuel J. Collins Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Richard B. Ennis, Project Manager Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8B13 Washington, DC 20555 USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC P.O. Box 157 Vernon, Vermont 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620-2601
Docket 50-27 1 BVY 06-051 Attachment 1 Vermont Yankee Nuclear Power Station Summary Reactor Feedwater Pump Trip Analysis
BVY 06-05 1 / Attachment 1 / Page 1 of 5 License Condition 3.L.2 requires that within 30 days at nominal full-power operation following successful performance of the transient test discussed in License Condition 31L.1, that Entergy, through performance of additional testing and/or analysis of the testing results, confirm that the loss of one reactor feedwater pump will not result in a reactor trip.
The following discussion summarizes the results of the analysis which confirms that the loss of one reactor feedwater pump will not result in a reactor trip at the plant's new power rating of 1912 MWt. The analysis summary is presented in three parts:
- Summary of Condensate Pump Trip test performed in accordance with License Condition 31L.1.
- Benchmarking of Dynamic Analysis Model using Condensate Pump Trip Test data.
" Analysis of Feedwater Pump Trip using benchmarked Dynamic Analysis Model.
Summary of Condensate Pump Trip To ensure acceptable performance during a condensate or reactor feedwater pump trip at the new 1912 MWt power rating, Entergy implemented the following modifications:
- The Reactor Recirculation Controller was modified to initiate an automatic runback of recirculation flow, and thereby rapidly reduce reactor power, upon detection of a pump trip at high reactor power levels.
- The Reactor Feedwater Pump (REP) suction pressure trip protection was enhanced by installing a staggered pump trip scheme and revised trip setpoints. This modification is intended to reduce the chance of inadvertent loss of all feedwater pumps.
- The "B" REP trip scheme was modified to automatically trip the "B" REP if any Condensate pump trips while at high power levels. This modification is intended to increase margin to the REP suction pressure trip setpoints for the remaining two operating REPs, thereby reducing the chance of a loss of all feedwater pumps for this event.
" Einally, the Reactor Eeedwater Level Controller was tuned to improve the responsiveness of the feedwater regulating valves, and the controller logic was modified to automatically reduce the level controller setpoint by approximately 5 inches upon initiation of a reactor recirculation runback due to a pump trip. This modification improves margin to the high reactor water level turbine trip setpoint during a pump trip event and thus is intended to reduce the chance of a reactor scram on a pump trip.
On the morning of May 8, 2006, while operating at the new power level of 1912 MWt, Entergy performed a Condensate Pump Trip Test in conformance with License Condition 31.1. The objective of the test was to demonstrate that at the new power rating, adequate reactor feedwater pump suction pressure remains available during this transient to preclude the loss of all feedwater pumps due to low suction pressure.
BVY 06-051 / Attachment 1 / Page 2 of 5 Figures 1 and 2 below illustrate the plant response during the test Figure 2 - Condensate Pump Trip Test Rx POWER _0 175 High Level Turbine Trip Setpoint (172 Inches) 170 ______0 r 60~
150: 50 1 e~145 _____40 140: 30 135: Low Level Scram Setpolnt (132 5 Inches) 2 1300 83950 8 40r2 840,50 84120 84150 84220 84250 843.20 84350 84420 Time
BVY 06-05 1 / Attachment 1 / Page 3 of 5 Figure 1 indicates that the minimum REP suction pressure, during the Condensate Pump Trip demonstration was approximately 180 psig. Therefore, there is ample margin to the 98 psig suction pressure trip setpoint. Figure 2 shows that the plant's reactor level response had ample margin to both the low level scram setpoint (132.5 inches) and the high level turbine trip setpoint (172 inches). This is as expected based upon the predicted plant response as discussed below.
Benchmarkinp of Dynamic Analysis Model A dynamic analysis model using RETRAN was developed to evaluate reactor level response during a condensate and/or feedwater pump trip event at 1912 MWt.
Prior to the condensate pump trip test, the RETRAN model was benchmarked to the plant data and the condensate pump trip test was simulated. The effect of uncertainties in various inputs was estimated to be approximately 2 to 3 inches. The predictions were within 2 inches of the low level and within less than 1 inch of the high level test results.
After the condensate pump trip test was performed, the RETRAN model was further refined for the dynamic level difference inside and outside the dryer skirt, and the initial conditions were revised to better represent the plant conditions at the time the condensate pump trip test was performed. The comparison of refined RETRAN model prediction to the measured level during actual condensate pump trip test is shown in Figure 3. Figure 3 shows good agreement between RETRAN model prediction and actual test data.
Figure 3 Benchmark Comparison of RETRAN Model to Condensate Pump Trip Test C
1b 175 --
170-165-r 155-
1 1
HIGH LEVEL TURBINE TRIP 1------ -T---- jP--LA-- T A A
-I150- ________ ______
145-______
140-135 -LOW LEVEL REACTOR TRIP 130F 100 150 200 250 300 350 400 TIME (seconds)
BVY 06-051 / Attachment 1 / Page 4 of 5 Analysis of Reactor Feedwater Pump Trip The same RETRAN model was used to simulate a feedwater pump trip. The calculated level for a feedwater-only pump trip is compared to the level calculated for the condensate and feedwater pump trip in Figure 4. It can be seen that the margin to the low level trip setpoint is higher in the case of a feedwater-only pump trip. This is a reasonable outcome since the reduction in the feedwater flow rate is less in the case of a feedwater pump trip than it is in the case of a condensate plus feedwater pump trip. The margin to the high level turbine trip setpoint is comparable in both cases. The magnitude of the level peak depends on the interaction between how aggressively the feedwater controller compensates for the flow rate decrease and how fast the level decreases as a result of the reduction in the feedwater flow rate. It is a reasonable outcome that the level peaks are comparable in both cases.
Figure 4 RETRAN Model Predictions for Both Condensate Pump Trip (with automatic FW Pump Trip) and Feedwater Pump Trip (without Condensate Pump Trip) 180-17-HIGH LEVEL TURBINE TRIP 170-UPTI 165--IEDAE 160-14 C 155 ____
150-
[ONDENSATE + FEEDWATER PUMP TRIP 145-E 140-135 FLOW LEVEL REACTOR TRIP 100 150 200 250 300 350 400 TIME (seconds)
BVY 06-051 / Attachment 1/Page 5 of 5 Conclusions The RETRAN analysis results in Figure 4 above show that the minimum level following a feedwater-only pump trip is 155 inches, and the peak level is 158 inches. There is a 14 inch margin to the high level turbine trip setpoint of 172 inches, and a 22.5 inch margin to the low level reactor scram setpoint of 132.5 inches. The uncertainties in the results are estimated to be approximately 2 to 3 inches. These results show ample margin to both the high level turbine trip setpoint and the low level reactor scram setpoint and therefore there is reasonable confidence that the loss of one reactor feedwater pump will not result in a reactor trip.