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| | page count = 16 | | | page count = 16 |
| | project = TAC:MC0761 | | | project = TAC:MC0761 |
| | stage = Acceptance Review | | | stage = Approval |
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| K. Minimum Critical Power Ratio When operating at thermal power greater than 1593 megawatts thermal, the safety limit minimum critical power ratio (SLMCPR) shall be established by adding 0.02 to the cycle-specific SLMCPR value calculated using the NRC-approved methodologies documented in General Electric Licensing Topical Report NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel," as amended, and documented in the Core Operating Limits Report. | | K. Minimum Critical Power Ratio When operating at thermal power greater than 1593 megawatts thermal, the safety limit minimum critical power ratio (SLMCPR) shall be established by adding 0.02 to the cycle-specific SLMCPR value calculated using the NRC-approved methodologies documented in General Electric Licensing Topical Report NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel," as amended, and documented in the Core Operating Limits Report. |
| L. Transient Testing | | L. Transient Testing |
| : 1. During the extended power uprate (EPU) power ascension test program and prior to exceeding [[estimated NRC review hours::168 hours]] of plant operation at the nominal full EPU reactor power level, with feedwater and condensate flow rates stabilized at approximately the EPU full power level, Entergy Nuclear Operations, Inc. shall confirm through performance of transient testing that the loss of one condensate pump will not result in a complete loss of reactor feedwater. | | : 1. During the extended power uprate (EPU) power ascension test program and prior to exceeding 168 hours of plant operation at the nominal full EPU reactor power level, with feedwater and condensate flow rates stabilized at approximately the EPU full power level, Entergy Nuclear Operations, Inc. shall confirm through performance of transient testing that the loss of one condensate pump will not result in a complete loss of reactor feedwater. |
| : 2. Within 30 days at nominal full-power operation following successful performance of the test in (1) above, through performance of additional transient testing and/or analysis of the results of the testing conducted in (1) above, confirm that the loss of one reactor feedwater pump will not result in a reactor trip. | | : 2. Within 30 days at nominal full-power operation following successful performance of the test in (1) above, through performance of additional transient testing and/or analysis of the results of the testing conducted in (1) above, confirm that the loss of one reactor feedwater pump will not result in a reactor trip. |
| M. Potential Adverse Flow Effects This license condition provides for monitoring, evaluating, and taking prompt action in response to potential adverse flow effects as a result of power uprate operation on plant structures, systems, and components (including verifying the continued structural integrity of the steam dryer). | | M. Potential Adverse Flow Effects This license condition provides for monitoring, evaluating, and taking prompt action in response to potential adverse flow effects as a result of power uprate operation on plant structures, systems, and components (including verifying the continued structural integrity of the steam dryer). |
| : 1. The following requirements are placed on operation of the facility above the original licensed thermal power (OLTP) level of 1593 megawatts thermal (MWt): | | : 1. The following requirements are placed on operation of the facility above the original licensed thermal power (OLTP) level of 1593 megawatts thermal (MWt): |
| : a. Entergy Nuclear Operations, Inc. shall monitor hourly the 32 main steam line (MSL) strain gages during power ascension above 1593 MWt for increasing pressure fluctuations in the steam lines. | | : a. Entergy Nuclear Operations, Inc. shall monitor hourly the 32 main steam line (MSL) strain gages during power ascension above 1593 MWt for increasing pressure fluctuations in the steam lines. |
| : b. Entergy Nuclear Operations, Inc. shall hold the facility for [[estimated NRC review hours::24 hours]] at 105%, | | : b. Entergy Nuclear Operations, Inc. shall hold the facility for 24 hours at 105%, |
| 110%, and 115% of OLTP to collect data from the 32 MSL strain gages required by Condition M.1.a, conduct plant inspections and walkdowns, and evaluate steam dryer performance based on these data; shall provide the evaluation to the NRC staff by facsimile or electronic transmission to the NRC project manager upon completion of the evaluation; and shall not increase power above each hold point until [[estimated NRC review hours::96 hours]] after the NRC project manager confirms receipt of the transmission. | | 110%, and 115% of OLTP to collect data from the 32 MSL strain gages required by Condition M.1.a, conduct plant inspections and walkdowns, and evaluate steam dryer performance based on these data; shall provide the evaluation to the NRC staff by facsimile or electronic transmission to the NRC project manager upon completion of the evaluation; and shall not increase power above each hold point until 96 hours after the NRC project manager confirms receipt of the transmission. |
| : c. If any frequency peak from the MSL strain gage data exceeds the limit curve established by Entergy Nuclear Operations, Inc. and submitted to the NRC staff prior to operation above OLTP, Entergy Nuclear Operations, Inc. shall return the facility to a power level at which the limit curve is not exceeded. Entergy Nuclear Operations, Inc. shall resolve the uncertainties in the steam dryer analysis, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power. | | : c. If any frequency peak from the MSL strain gage data exceeds the limit curve established by Entergy Nuclear Operations, Inc. and submitted to the NRC staff prior to operation above OLTP, Entergy Nuclear Operations, Inc. shall return the facility to a power level at which the limit curve is not exceeded. Entergy Nuclear Operations, Inc. shall resolve the uncertainties in the steam dryer analysis, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power. |
| : d. In addition to evaluating the MSL strain gage data, Entergy Nuclear Operations, Inc. shall monitor reactor pressure vessel water level instrumentation or MSL piping accelerometers on an hourly basis during power ascension above OLTP. | | : d. In addition to evaluating the MSL strain gage data, Entergy Nuclear Operations, Inc. shall monitor reactor pressure vessel water level instrumentation or MSL piping accelerometers on an hourly basis during power ascension above OLTP. |
Letter Sequence Approval |
|---|
|
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
|
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
[Table View] |
|
|---|
Category:Federal Register Notice
MONTHYEARML21159A0522021-06-29029 June 2021
VY and CR Indirect License Transfer Order FRN
ML21077A2772021-05-0404 May 2021
Final Ea/Fonsi for 20.2002 Alternate Disposal Request (License DPR-28, Docket No. 50-271)
ML21064A1402021-03-29029 March 2021
(License DPR-28, Docket Nos. 50-271 and 72-59) - Notice of Consideration, Request for Indirect License Transfer
ML18274A2492018-10-17017 October 2018
Exemption Issuance FRN
ML18249A3622018-10-15015 October 2018
Federal Register Notice Announcing Approval of License Transfer Request (License DPR-28, Docket Nos. 50-271 and 72-59)
NRC-2018-0216, Federal Register Notice Announcing Approval of License Transfer Request (License DPR-28, Docket Nos. 50-271 and 72-59)2018-10-15015 October 2018
Federal Register Notice Announcing Approval of License Transfer Request (License DPR-28, Docket Nos. 50-271 and 72-59)
ML18248A0962018-10-11011 October 2018
Order Approving License Transfer Request (License DPR-28, Docket Nos. 50-271 and 72-59)
NRC-2018-0226, FRN Ea/Fonsi for Exemption for Northstar to Use the Nuclear Decommissioning Trust for Spent Fuel Management Re Request for Direct and Indirect License Transfers from Entergy to Northstar2018-10-0303 October 2018
FRN Ea/Fonsi for Exemption for Northstar to Use the Nuclear Decommissioning Trust for Spent Fuel Management Re Request for Direct and Indirect License Transfers from Entergy to Northstar
ML18257A2832018-10-0303 October 2018
FRN Ea/Fonsi for Exemption for Northstar to Use the Nuclear Decommissioning Trust for Spent Fuel Management Re Request for Direct and Indirect License Transfers from Entergy to Northstar
NRC-2018-0140, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/20182018-07-0505 July 2018
Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/2018
ML18180A2182018-07-0505 July 2018
Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/2018
NRC-2018-0020, Federal Register Notice: Exemption: Issuance - Availability of Exemption for Entergy Operations, Inc., Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation2018-02-0808 February 2018
Federal Register Notice: Exemption: Issuance - Availability of Exemption for Entergy Operations, Inc., Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation
ML17298A1582018-02-0808 February 2018
Federal Register Notice: Exemption: Issuance - Availability of Exemption for Entergy Operations, Inc., Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation
ML18017B0492018-01-19019 January 2018
Correction Notice for EA and Fonsi
NRC-2017-0134, Federal Register Notice: Notice of Availability of Environmental Assessment and Finding of No Significant Impact for Entergy Nuclear Operation, Inc., Vermont Yankee Nuclear Power Station ISFSI Exemption Request2018-01-16016 January 2018
Federal Register Notice: Notice of Availability of Environmental Assessment and Finding of No Significant Impact for Entergy Nuclear Operation, Inc., Vermont Yankee Nuclear Power Station ISFSI Exemption Request
ML17249A2442018-01-16016 January 2018
Federal Register Notice: Notice of Availability of Environmental Assessment and Finding of No Significant Impact for Entergy Nuclear Operation, Inc., Vermont Yankee Nuclear Power Station ISFSI Exemption Request
NRC-2017-0175, Biweekly Sholly Report - Federal Register Notice Fr Publication Date: August 15, 20172017-08-0404 August 2017
Biweekly Sholly Report - Federal Register Notice Fr Publication Date: August 15, 2017
ML17213A1842017-08-0404 August 2017
Biweekly Sholly Report - Federal Register Notice Fr Publication Date: August 15, 2017
ML17143A1562017-06-0606 June 2017
Enclosufederal Register Notice-Notice of Availability of Exemption for Entergy Energy Operations, Inc., Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation
ML17045A5322017-05-25025 May 2017
Enclosufrn - Notice of Availability of Environmental Assessment and Finding of No Significant Impact for Entergy Nuclear Operations, Inc., Vermont Yankee Nuclear Power Station, Independent Spent Fuel Storage Installation Exemption Request
ML17013A2572016-12-12012 December 2016
Draft Final EA
ML16012A1572016-04-15015 April 2016
FRN: Exemption from the Requirements of 10 CFR Part 140, Section 140.11(a)(4) Concerning Primary and Secondary Liability Insurance
NRC-2016-0017, FRN: Exemption from the Requirements of 10 CFR Part 50, Section 50.54(w)(1) Concerning Insurance for Post-Accident Site Decontamination2016-04-15015 April 2016
FRN: Exemption from the Requirements of 10 CFR Part 50, Section 50.54(w)(1) Concerning Insurance for Post-Accident Site Decontamination
ML16012A1972016-04-15015 April 2016
FRN: Exemption from the Requirements of 10 CFR Part 50, Section 50.54(w)(1) Concerning Insurance for Post-Accident Site Decontamination
NRC-2015-0200, OEDO-15-00251 - FRN for Final Director'S Decision 2.206 - Ultrasonic Inspection Test or Best Available Flaw Detection Technology for USA Reactor Plants Similar to the Thousands of Cracks Discovered in Belgium Nuclear Power Plants2016-03-29029 March 2016
OEDO-15-00251 - FRN for Final Director'S Decision 2.206 - Ultrasonic Inspection Test or Best Available Flaw Detection Technology for USA Reactor Plants Similar to the Thousands of Cracks Discovered in Belgium Nuclear Power Plants
ML16054A6912016-03-29029 March 2016
OEDO-15-00251 - Letter to Petitioner for Final Director'S Decision 2.206 - Ultrasonic Inspection Test or Best Available Flaw Detection Technology for USA Reactor Plants Similar to the Thousands of Cracks Discovered in Belgium Nuclear Power
ML16054A7312016-03-29029 March 2016
OEDO-15-00251 - Final Director'S Decision 2.206 - Ultrasonic Inspection Test or Best Available Flaw Detection Technology for USA Reactor Plants Similar to the Thousands of Cracks Discovered in Belgium Nuclear Power Plants
ML16054A8032016-03-29029 March 2016
OEDO-15-00251 - FRN for Final Director'S Decision 2.206 - Ultrasonic Inspection Test or Best Available Flaw Detection Technology for USA Reactor Plants Similar to the Thousands of Cracks Discovered in Belgium Nuclear Power Plants
ML15286A2722016-01-12012 January 2016
OEDO-15-00251: Proposed Director'S Decision 2.206 - Emergency Ultrasonic Inspection Test or Best Available Flaw Detection Technology for USA Reactor Plants Similar to the Thousands of Cracks Discovered in Belgium Nuclear Power Plants
ML15356A5992015-12-29029 December 2015
Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 5, 2016
ML15344A2432015-12-22022 December 2015
Letter, FRN for Partial Exemption from Recordkeeping Requirements
ML15344A2572015-12-22022 December 2015
FRN for Partial Exemption from Recordkeeping Requirements
ML15180A0542015-12-10010 December 2015
LTR, Exemptions from Certain Emergency Planning Requirements and Related Safety Evaluation
ML15180A0472015-12-10010 December 2015
FRN - Exemptions from Certain Emergency Planning Requirements and Related Safety Evaluation
ML15261A6662015-11-10010 November 2015
Withdrawal of an Amendment Request Regarding Deletion of Operating License Conditions Related to the Decommissioning Trust Provisions
ML15261A6712015-11-10010 November 2015
FRN - Withdrawal of an Amendment Request Regarding Deletion of Operating License Conditions Related to the Decommissioning Trust Provisions
ML15162A6902015-08-27027 August 2015
G20130211 - Transmittal Letter to Petitioner Judson Regarding Final Director'S Decision for James A. FitzPatrick Power Plant, Pilgrim Nuclear Power Station and Vermont Yankee Nuclear Power Station
ML15181A1092015-08-20020 August 2015
OEDO-15-00251 - FRN Regarding 2.206 - Emergency Ultrasonic Inspection Test or Best Available Flaw Detection Technology for USA Reactor Plants Similar to the Thousands of Cracks Discovered in Belgium Nuclear Power Plants
ML15180A0692015-07-31031 July 2015
Issuance of Environmental Assessment and Finding of No Significant Impact Related to Request for Exemptions from Certain Emergency Planning Requirements
ML15128A1942015-06-17017 June 2015
Exemptions from the Requirements of 10 CFR Part 50, Sections 50.82(a)(8)(i)(A) and 50.75(h)(1)(iv)
ML15103A4192015-04-24024 April 2015
Letter and Draft Environmental Assessment and Finding of No Significant Impact Related to Request for Exemptions from Certain Emergency Planning Requirements
ML15103A4002015-04-24024 April 2015
Draft Environmental Assessment and Finding of No Significant Impact Related to Request for Exemptions from Certain Emergency Planning Requirements
ML14266A3872015-02-12012 February 2015
Letter, Exemption from Requirements of 10 CFR Part 73 Related to Suspension of Security Measures in an Emergency or During Severe Weather
ML14266A4172015-02-12012 February 2015
FRN, Exemption from Requirements of 10 CFR Part 73 Related to Suspension of Security Measures in an Emergency or During Severe Weather
NRC-2015-0034, FRN, Exemption from Requirements of 10 CFR Part 73 Related to Suspension of Security Measures in an Emergency or During Severe Weather2015-02-12012 February 2015
FRN, Exemption from Requirements of 10 CFR Part 73 Related to Suspension of Security Measures in an Emergency or During Severe Weather
ML15008A1092015-01-22022 January 2015
FRN Reopening of Public Comment Period for Permanently Defueled Emergency Plan and Emergency Action Level Scheme Change Amendment Request
ML15012A2012015-01-22022 January 2015
Correction and Reopening of Public Comment Period for Permanently Defueled Emergency Plan and Emergency Action Level Scheme Change Amendment Request
ML14335A6302015-01-15015 January 2015
G20110262 - Final Response to Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units
ML14335A6482015-01-15015 January 2015
G20110262 - FRN - Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units
NRC-2015-0009, G20110262 - FRN - Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units2015-01-15015 January 2015
G20110262 - FRN - Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units
2021-06-29
[Table view]
Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
BVY 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
IR 05000271/20240012024-06-28028 June 2024
NRC Inspection Report No. 05000271/2024001, Northstar Nuclear Decommissioning Company, LLC, Vermont Yankee Nuclear Power Station, Vernon, Vermont
ML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
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
ML24053A2572024-03-0101 March 2024
Withdrawal of Requested Licensing Action for a License Amendment Submitted for Approval of the License Termination Plan
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 24-007, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-02-26026 February 2024
Report of Investigation Pursuant to 10 CFR 20, Appendix G
IR 05000271/20230022024-02-20020 February 2024
NRC Inspection Report Nos. 05000271/2023002 and 07200059/2023001, Northstar Nuclear Decommissioning Company, LLC, Vermont Yankee Nuclear Power Station, Vernon, Vermont
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
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 23-011, 2022 Radiological Effluent Release Report2023-05-10010 May 2023
2022 Radiological Effluent Release Report
BVY 23-013, 2022 Radiological Environmental Operating Report2023-05-10010 May 2023
2022 Radiological Environmental Operating 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
2024-09-18
[Table view]
Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML19175A0422019-09-11011 September 2019
Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules
ML18347B3592019-01-11011 January 2019
12-13-18-License Transfer Conforming Amendment Markup
ML18347B3602019-01-11011 January 2019
Letter: Vermont Yankee Nuclear Power Station - Issuance of Amendment Application for Order Approving Direct and Indirect Transfer of Renewed Facility Operating License and Independent Spent Fuel Storage Installation General License.
ML18253A2022018-10-11011 October 2018
Conforming License Amendment Approval of License Transfer Request(License DPR-28, Docket 50-271 and 72-59)
ML18156A1812018-08-15015 August 2018
ISFSI Only Tech Spec Amendment Package
ML18165A4232018-07-25025 July 2018
Issuance of Amendment to Change the Physical Security Plan to Reflect an ISFSI-Only Configuration
ML18053A1122018-03-30030 March 2018
Issuance of Amendment to Change the Emergency Plan and Emergency Action Level Scheme to Reflect an ISFSI-Only Configuration
ML16014A1692016-03-14014 March 2016
Vermont Yankee Nuclear Power Station - Issuance of Amendment No. 265 to Renewed Facility Operating License Re: Cyber Security Plan Implementation Schedule (CAC No. MF6403)
ML15233A1662015-12-11011 December 2015
Issuance of Amendment No. 264 to Renewed Facility Operating License Changes to the Emergency Plan and Emergency Action Levels
ML15117A5512015-10-0707 October 2015
Issuance of Amendment for Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
ML14304A5882015-02-12012 February 2015
Issuance of Amendment No. 261, Revise Technical Specifications to Eliminate Certain Requirements During Movement of Irradiated Fuel and Core Alterations Consistent with TSTF-51
ML14346A0652015-02-0404 February 2015
Issuance of Amendment No. 261, Revise Site Emergency Plan for Permanently Defueled Condition to Reflect Change in On-Shift Staffing and Emergency Response Staffing
ML14217A0722014-12-22022 December 2014
Issuance of Amendment No. 260, Revise and Remove Certain Requirements from Technical Specification Section 6.0, Administrative Controls, No Longer Applicable for Its Permanently Defueled Condition
ML14206A7102014-11-12012 November 2014
Issuance of Amendment No. 259, Revise Operating License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date
ML13212A2012013-08-15015 August 2013
Issuance of Amendment No. 258 Change to Licensing Basis Regarding Station Blackout
ML13105A1752013-04-26026 April 2013
Issuance of Amendment No. 257 Request to Revise Requirement of the Recirculation Pump Discharge Bypass Valves
ML13042A2722013-04-17017 April 2013
Issuance of Amendment 256 Revision to License Condition 3.P and 3.S
ML13025A3062013-03-14014 March 2013
ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Correction to Amendments Issued on 12/28/12, Revise QA Program Manual and Staff Qualification Technical Specifications
ML1300903212013-01-30030 January 2013
Issuance of Amendment Rod Worth Minimizer Bypass Allowance TS Change (TAC No. Me 7927)
ML1300902152013-01-30030 January 2013
Issuance of Amendment Change to Suppression Chamber Drywell Leak Rate Test Surveillance Frequency
ML12261A2922012-11-13013 November 2012
Issuance of Amendment to Renewed Facility Operating License Cyber Security Plan Implementation Schedule Milestone
ML1127904592011-11-0404 November 2011
Issuance of Amendment Revised Reactor Vessel Pressure-Temperature Limitation Curves
ML1127205902011-09-30030 September 2011
Issuance of Emergency Amendment Modification of Technical Specification for Single Loop Operation
ML1121014312011-08-25025 August 2011
Issuance of Amendment Elimination of Technical Specification Provisions Allowing HPCI and RCIC Suctions to Be Aligned to the Suppression Pool
ML11152A0132011-07-20020 July 2011
License Amendment, Cyber Security Plan
ML0921100542011-03-21021 March 2011
Renewed Facility Operating License DPR-28
ML1103400782011-02-23023 February 2011
Issuance of Amendment Control Rod Block Actuation Logic System Functional Test
ML1100601792011-02-0909 February 2011
Issuance of Amendment Regarding Modification to Technical Specification 4.12 as Result of Changes Made by License Amendment Nos. 230 and 239 and to Revise Wording in TS 3.7.A.8
ML1025717732010-10-0606 October 2010
License Amendment, Issuance of Amendment Scram Discharge Volume Vent and Drain Valves
ML1004316132010-03-0808 March 2010
Issuance of Amendment Safety Limit Minimum Critical Power Ratio Change
ML1001203062010-01-26026 January 2010
Issuance of Amendment Revision to Requirements for Inoperable Containment Isolation Valves
ML0933604432010-01-0404 January 2010
License Amendment 241 Revision of High Radiation Area Controls
ML0928906522009-10-28028 October 2009
Issuance of Amendment Extension of Appendix J, Type a Integrated Leakage Rate Test Interval
ML0917400402009-07-13013 July 2009
License Amendment, Relocation of Reactor Building Crane Technical Specification
ML0916102242009-07-0606 July 2009
Issuance of Amendment Testing and Inspection of Suppression Chamber-To-Drywell Vacuum Breakers
ML0915505702009-06-17017 June 2009
License Amendment, Main Steam Isolation Valve Surveillance Requirements
ML0914103582009-06-12012 June 2009
License Amendment, Issuance of Amendment Instrumentation Technical Specifications
ML0903704562009-02-26026 February 2009
License Amendment, Issuance of Amendment Sale of Lease of Property within the Exclusion Boundary
ML0901206582009-02-11011 February 2009
Issuance of Amendment Battery Systems
ML0833001292009-01-0707 January 2009
Issuance of Amendment Control Rod Systems
ML0815701872008-06-23023 June 2008
Issuance of Amendment Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Limits
ML0808003342008-04-17017 April 2008
Issuance of Amendment Emergency Diesel Generator Fuel Oil Tank Volume, Fuel Oil Testing and Reactor Building Crane Inspections
ML0723302302007-08-23023 August 2007
Revised Pages of Facility Operating License DPR-28 B.5.b
ML0705301592007-03-26026 March 2007
Issuance of Amendment Adoption of Technical Specification Task Force (TSTF) Change TSTF-372, the Addition of Limiting Condition for Operation (LCO) 3.0.8 on the Inoperability of Snubbers
ML0600500222006-03-0202 March 2006
Vermont Yankee, License Amendment 229 Regarding Extended Power Uprate
ML0523600022005-09-20020 September 2005
License Amendment, Drywell Spray Header and Nozzle Air Test Frequency
ML0520000032005-08-31031 August 2005
License Amendment, Revise One-Time Extension of Integrated Leak Rate Test Interval
ML0519201382005-08-15015 August 2005
Issuance of License Amendment 226 Administrative Changes
ML0516700622005-07-0707 July 2005
License Amendment, Extend Intermediate Range Monitor Surveillance Test Frequencies
ML0504201652005-06-0101 June 2005
License Amendment, Relocation of Inservice Testing Requirements to a Licensee - Controlled Program
2019-09-11
[Table view] |
Text
March 2, 2006 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
VERMONT YANKEE NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: EXTENDED POWER UPRATE (TAC NO. MC0761)
Dear Mr. Kansler:
The Commission has issued the enclosed Amendment No. 229 to Facility Operating License No. DPR-28 for the Vermont Yankee Nuclear Power Station (VYNPS), in response to your application dated September 10, 2003, as supplemented by letters dated October 1, and October 28 (2 letters), 2003; January 31 (2 letters), March 4, May 19, July 2, July 27, July 30, August 12, August 25, September 14, September 15, September 23, September 30 (2 letters),
October 5, October 7 (2 letters), December 8, and December 9, 2004; February 24, March 10, March 24, March 31, April 5, April 22, June 2, August 1, August 4, September 10, September 14, September 18, September 28, October 17, October 21 (2 letters), October 26, October 29, November 2, November 22, and December 2, 2005; January 10, and February 22, 2006.
The amendment increases the maximum authorized power level for VYNPS from 1593 megawatts thermal (MWt) to 1912 MWt, which is an increase of approximately 20 percent. The increase in power level is considered an extended power uprate (EPU). The amendment includes revisions to the VYNPS Operating License and Technical Specifications that are necessary to implement the EPU.
The related Safety Evaluation (SE) has been determined to contain proprietary information pursuant to Title 10 of the Code of Federal Regulations, Section 2.390. Accordingly, the NRC staff has prepared a redacted, publicly-available, non-proprietary version of the SE. Copies of the proprietary and non-proprietary versions of the SE are enclosed.
M. Kansler A copy of the Notice of Issuance of Amendment to Facility Operating License and Final Determination of No Significant Hazards Consideration, which is being forwarded to the Office of the Federal Register for publication, is also enclosed.
Sincerely,
/RA/
Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-271
Enclosures:
- 1. Amendment No. 229 to License No. DPR-28
- 2. Non-proprietary SE
- 3. Proprietary SE
- 4. Notice cc w/encls 1, 2, and 4: See next page
M. Kansler A copy of the Notice of Issuance of Amendment to Facility Operating License and Final Determination of No Significant Hazards Consideration, which is being forwarded to the Office of the Federal Register for publication, is also enclosed.
Sincerely,
/RA/
Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-271
Enclosures:
- 1. Amendment No. 229 to License No. DPR-28
- 2. Non-proprietary SE
- 3. Proprietary SE
- 4. Notice cc w/encls 1, 2, and 4: See next page DISTRIBUTION: See next page Accession Nos.:
Package: ML060050024 Cover letter, Amendment, and Notice: ML060050022 License and TS pages: ML060390107 Non-proprietary SE: ML060050028 Proprietary SE: ML060050051 *Cover letter only OFFICE LPL1-2/PM CM Tech Editor* LPL1-1/LA OGC NAME REnnis HChang SLittle STurk DATE 2/27/06 1/5/06 2/27/06 2/28/06 OFFICE LPL1-2/BC DORL/D NRR/D NAME DRoberts CHaney JDyer DATE 3/1/06 3/1/06 3/2/06 The following provided safety evaluation input by memos dated**
OFFICE EEIB-A/SC EEIB-B/SC EMCB-A/SC EMCB-B/SC EMCB-C/SC NAME EMarinos RJenkins SCoffin TChan LLund DATE** 9/27/04 7/1/04, 12/15/05, 11/24/04 8/9/04 9/9/04 9/29/04 OFFICE EMEB/SC IPSB-A/SC IPSB/BC IROB-B/SC SPLB-A/SC(A)
NAME KManoly DThatcher TQuay DTrimble SJones DATE** 9/30/05 9/29/05 11/10/04 1/24/05 9/30/05 OFFICE SPLB-B/SC SPSB-A/SC SPSB-C/SC SRXB-A/SC NAME SWeerakkody MRubin RDennig FAkstulewicz DATE** 7/31/04 10/3/05 10/4/04, 10/6/04, 9/30/05, 9/30/05 10/11/05 OFFICIAL RECORD COPY
Distribution for letter dated: March 2, 2006
SUBJECT:
VERMONT YANKEE NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: EXTENDED POWER UPRATE (TAC NO. MC0761)
DISTRIBUTION:
PUBLIC LPL1-2 Reading JDyer RBorchardt BSheron BBoger CHaney CHolden EHackett DRoberts REnnis JShea CRaynor SLittle TAlexion QNguyen OGC ACRS GHill (2)
CAnderson, RGN I STurk, OGC VBucci, OIG HGarg NTrehan APal BElliot RDavis KParczewski TScarbrough PSekerak CWu RPettis RPedersen JCai JBongarra DReddy RGallucci MStutzke RLobel HWalker MHart MRazzaque ZAbdullahi GThomas LWard THuang
Vermont Yankee Nuclear Power Station cc:
Regional Administrator, Region I Ms. Carla A. White, RRPT, CHP U. S. Nuclear Regulatory Commission Radiological Health 475 Allendale Road Vermont Department of Health King of Prussia, PA 19406-1415 P.O. Box 70, Drawer #43 108 Cherry Street Mr. David R. Lewis Burlington, VT 05402-0070 Pillsbury, Winthrop, Shaw, Pittman, LLP 2300 N Street, N.W. Mr. James M. DeVincentis Washington, DC 20037-1128 Manager, Licensing Vermont Yankee Nuclear Power Station Mr. David OBrien, Commissioner P.O. Box 0500 Vermont Department of Public Service 185 Old Ferry Road 112 State Street Brattleboro, VT 05302-0500 Montpelier, VT 05620-2601 Resident Inspector Mr. James Volz, Chairman Vermont Yankee Nuclear Power Station Public Service Board U. S. Nuclear Regulatory Commission State of Vermont P.O. Box 176 112 State Street Vernon, VT 05354 Montpelier, VT 05620-2701 Director, Massachusetts Emergency Chairman, Board of Selectmen Management Agency Town of Vernon ATTN: James Muckerheide P.O. Box 116 400 Worcester Rd.
Vernon, VT 05354-0116 Framingham, MA 01702-5399 Operating Experience Coordinator Jonathan M. Block, Esq.
Vermont Yankee Nuclear Power Station Main Street 320 Governor Hunt Road P.O. Box 566 Vernon, VT 05354 Putney, VT 05346-0566 G. Dana Bisbee, Esq. Mr. John F. McCann Deputy Attorney General Director, Licensing 33 Capitol Street Entergy Nuclear Operations, Inc.
Concord, NH 03301-6937 440 Hamilton Avenue White Plains, NY 10601 Chief, Safety Unit Office of the Attorney General Mr. Gary J. Taylor One Ashburton Place, 19th Floor Chief Executive Officer Boston, MA 02108 Entergy Operations 1340 Echelon Parkway Jackson, MS 39213
Vermont Yankee Nuclear Power Station cc:
Mr. John T. Herron Ms. Stacey M. Lousteau Sr. VP and Chief Operating Officer Treasury Department Entergy Nuclear Operations, Inc. Entergy Services, Inc.
440 Hamilton Avenue 639 Loyola Avenue White Plains, NY 10601 New Orleans, LA 70113 Mr. Oscar Limpias Mr. Raymond Shadis Vice President, Engineering New England Coalition Entergy Nuclear Operations, Inc. Post Office Box 98 440 Hamilton Avenue Edgecomb, ME 04556 White Plains, NY 10601 Mr. James P. Matteau Mr. Christopher Schwarz Executive Director Vice President, Operations Support Windham Regional Commission Entergy Nuclear Operations, Inc. 139 Main Street, Suite 505 440 Hamilton Avenue Brattleboro, VT 05301 White Plains, NY 10601 Mr. William K. Sherman Mr. Michael J. Colomb Vermont Department of Public Service Director of Oversight 112 State Street Entergy Nuclear Operations, Inc. Drawer 20 440 Hamilton Avenue Montpelier, VT 05620-2601 White Plains, NY 10601 Mr. Michael D. Lyster Mr. Travis C. McCullough 5931 Barclay Lane Assistant General Counsel Naples, FL 34110-7306 Entergy Nuclear Operations, Inc.
440 Hamilton Avenue Ms. Charlene D. Faison White Plains, NY 10601 Manager, Licensing 440 Hamilton Avenue Mr. Jay K. Thayer White Plains, NY 10601 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. James H. Sniezek 5486 Nithsdale Drive Salisbury, MD 21801
ENTERGY NUCLEAR VERMONT YANKEE, LLC AND ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 229 License No. DPR-28
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment filed by Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (the licensee) on September 10, 2003, as supplemented by letters dated October 1, and October 28 (2 letters), 2003; January 31 (2 letters), March 4, May 19, July 2, July 27, July 30, August 12, August 25, September 14, September 15, September 23, September 30 (2 letters), October 5, October 7 (2 letters), December 8, and December 9, 2004; February 24, March 10, March 24, March 31, April 5, April 22, June 2, August 1, August 4, September 10, September 14, September 18, September 28, October 17, October 21 (2 letters), October 26, October 29, November 2, November 22, and December 2, 2005; January 10, and February 22, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 229, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
In addition, the license is amended to revise paragraph 3.A of Facility Operating License No. DPR-28 to reflect the new maximum licensed reactor core power level of 1912 megawatts thermal. The licensee is also amended to add new license conditions 3.K, 3.L, and 3.M as follows:
K. Minimum Critical Power Ratio When operating at thermal power greater than 1593 megawatts thermal, the safety limit minimum critical power ratio (SLMCPR) shall be established by adding 0.02 to the cycle-specific SLMCPR value calculated using the NRC-approved methodologies documented in General Electric Licensing Topical Report NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel," as amended, and documented in the Core Operating Limits Report.
L. Transient Testing
- 1. During the extended power uprate (EPU) power ascension test program and prior to exceeding 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> of plant operation at the nominal full EPU reactor power level, with feedwater and condensate flow rates stabilized at approximately the EPU full power level, Entergy Nuclear Operations, Inc. shall confirm through performance of transient testing that the loss of one condensate pump will not result in a complete loss of reactor feedwater.
- 2. Within 30 days at nominal full-power operation following successful performance of the test in (1) above, through performance of additional transient testing and/or analysis of the results of the testing conducted in (1) above, confirm that the loss of one reactor feedwater pump will not result in a reactor trip.
M. Potential Adverse Flow Effects This license condition provides for monitoring, evaluating, and taking prompt action in response to potential adverse flow effects as a result of power uprate operation on plant structures, systems, and components (including verifying the continued structural integrity of the steam dryer).
- 1. The following requirements are placed on operation of the facility above the original licensed thermal power (OLTP) level of 1593 megawatts thermal (MWt):
- a. Entergy Nuclear Operations, Inc. shall monitor hourly the 32 main steam line (MSL) strain gages during power ascension above 1593 MWt for increasing pressure fluctuations in the steam lines.
- b. Entergy Nuclear Operations, Inc. shall hold the facility for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 105%,
110%, and 115% of OLTP to collect data from the 32 MSL strain gages required by Condition M.1.a, conduct plant inspections and walkdowns, and evaluate steam dryer performance based on these data; shall provide the evaluation to the NRC staff by facsimile or electronic transmission to the NRC project manager upon completion of the evaluation; and shall not increase power above each hold point until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRC project manager confirms receipt of the transmission.
- c. If any frequency peak from the MSL strain gage data exceeds the limit curve established by Entergy Nuclear Operations, Inc. and submitted to the NRC staff prior to operation above OLTP, Entergy Nuclear Operations, Inc. shall return the facility to a power level at which the limit curve is not exceeded. Entergy Nuclear Operations, Inc. shall resolve the uncertainties in the steam dryer analysis, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power.
- d. In addition to evaluating the MSL strain gage data, Entergy Nuclear Operations, Inc. shall monitor reactor pressure vessel water level instrumentation or MSL piping accelerometers on an hourly basis during power ascension above OLTP.
If resonance frequencies are identified as increasing above nominal levels in proportion to strain gage instrumentation data, Entergy Nuclear Operations, Inc.
shall stop power ascension, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power.
- e. Following start-up testing, Entergy Nuclear Operations, Inc. shall resolve the uncertainties in the steam dryer analysis and provide that resolution to the NRC staff by facsimile or electronic transmission to the NRC project manager. If the uncertainties are not resolved within 90 days of issuance of the license amendment authorizing operation at 1912 MWt, Entergy Nuclear Operations, Inc. shall return the facility to OLTP.
- 2. As described in Entergy Nuclear Operations, Inc. letter BVY 05-084 dated September 14, 2005, Entergy Nuclear Operations, Inc. shall implement the following actions:
- a. Prior to operation above OLTP, Entergy Nuclear Operations, Inc. shall install 32 additional strain gages on the main steam piping and shall enhance the data acquisition system in order to reduce the measurement uncertainty associated with the acoustic circuit model (ACM).
- b. In the event that acoustic signals are identified that challenge the limit curve during power ascension above OLTP, Entergy Nuclear Operations, Inc. shall evaluate dryer loads and re-establish the limit curve based on the new strain gage data, and shall perform a frequency-specific assessment of ACM uncertainty at the acoustic signal frequency.
- c. After reaching 120% of OLTP, Entergy Nuclear Operations, Inc. shall obtain measurements from the MSL strain gages and establish the steam dryer flow-induced vibration load fatigue margin for the facility, update the dryer stress report, and re-establish the steam dryer monitoring plan (SDMP) limit curve with the updated ACM load definition and revised instrument uncertainty, which will be provided to the NRC staff.
- d. During power ascension above OLTP, if an engineering evaluation is required in accordance with the SDMP, Entergy Nuclear Operations, Inc. shall perform the structural analysis to address frequency uncertainties up to +/-10% and assure that peak responses that fall within this uncertainty band are addressed.
- e. Entergy Nuclear Operations, Inc. shall revise the SDMP to reflect long-term monitoring of plant parameters potentially indicative of steam dryer failure; to reflect consistency of the facilitys steam dryer inspection program with General Electric Services Information Letter 644, Revision 1; and to identify the NRC Project Manager for the facility as the point of contact for providing SDMP information during power ascension.
- f. Entergy Nuclear Operations, Inc. shall submit the final extended power uprate (EPU) steam dryer load definition for the facility to the NRC upon completion of the power ascension test program.
- g. Entergy Nuclear Operations, Inc. shall submit the flow-induced vibration related portions of the EPU startup test procedure to the NRC, including methodology for updating the limit curve, prior to initial power ascension above OLTP.
- 3. Entergy Nuclear Operations, Inc. shall prepare the EPU startup test procedure to include the (a) stress limit curve to be applied for evaluating steam dryer performance; (b) specific hold points and their duration during EPU power ascension; (c) activities to be accomplished during hold points; (d) plant parameters to be monitored; (e) inspections and walkdowns to be conducted for steam, feedwater, and condensate systems and components during the hold points; (f) methods to be used to trend plant parameters; (g) acceptance criteria for monitoring and trending plant parameters, and conducting the walkdowns and inspections; (h) actions to be taken if acceptance criteria are not satisfied; and (i) verification of the completion of commitments and planned actions specified in its application and all supplements to the application in support of the EPU license amendment request pertaining to the steam dryer prior to power increase above OLTP. Entergy Nuclear Operations, Inc. shall provide the related EPU startup test procedure sections to the NRC by facsimile or electronic transmission to the NRC project manager prior to increasing power above OLTP.
- 4. When operating above OLTP, the operating limits, required actions, and surveillances specified in the SDMP shall be met. The following key attributes of the SDMP shall not be made less restrictive without prior NRC approval:
- a. During initial power ascension testing above OLTP, each test plateau increment shall be approximately 80 MWt;
- b. Level 1 performance criteria; and
- c. The methodology for establishing the stress spectra used for the Level 1 and Level 2 performance criteria.
Changes to other aspects of the SDMP may be made in accordance with the guidance of NEI 99-04.
- 5. During each of the three scheduled refueling outages (beginning with the spring 2007 refueling outage), a visual inspection shall be conducted of all accessible, susceptible locations of the steam dryer, including flaws left as is and modifications.
- 6. The results of the visual inspections of the steam dryer conducted during the three scheduled refueling outages (beginning with the spring 2007 refueling outage) shall be reported to the NRC staff within 60 days following startup from the respective refueling outage. The results of the SDMP shall be submitted to the NRC staff in a report within 60 days following the completion of all EPU power ascension testing.
- 7. The requirements of paragraph 4 above for meeting the SDMP shall be implemented upon issuance of the EPU license amendment and shall continue until the completion of one full operating cycle at EPU. If an unacceptable structural flaw (due to fatigue) is detected during the subsequent visual inspection of the steam dryer, the requirements of paragraph 4 shall extend another full operating cycle until the visual inspection standard of no new flaws/flaw growth based on visual inspection is satisfied.
- 8. This license condition shall expire upon satisfaction of the requirements in paragraphs 5, 6, and 7 provided that a visual inspection of the steam dryer does not reveal any new unacceptable flaw or unacceptable flaw growth that is due to fatigue.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 120 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
J. E. Dyer, Director Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance: March 2, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 229 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Replace the following pages of the Facility Operating License and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Facility Operating License Remove Insert 3 3 9 9
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--- 13 Technical Specifications Remove Insert 3 3 6 6 7 7 10 10 12 12 13 13 14 14 15 15 17 17 21 21 24 24 30 30 83 83 90 90 92 92 94 94 97 97 98 98 135 135 136 136 137 137 138 138 142 142 224 224 225 225 226 226 228 228
7590-01-P U.S. NUCLEAR REGULATORY COMMISSION ENTERGY NUCLEAR VERMONT YANKEE, LLC AND ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-271 NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND FINAL DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION The U.S. Nuclear Regulatory Commission (Commission) has issued Amendment No. 229 to Facility Operating License No. DPR-28, issued to Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (the licensee), which revised the Technical Specifications (TSs) and License for operation of the Vermont Yankee Nuclear Power Station (VYNPS) located in Windham County, Vermont. The amendment was effective as of the date of its issuance.
The amendment increases the maximum authorized power level for VYNPS from 1593 megawatts thermal (MWt) to 1912 MWt, which is an increase of approximately 20 percent. The increase in power level is considered an extended power uprate.
The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations.
The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.
The Commission published a Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for a Hearing related to this action in the FEDERAL REGISTER on July 1, 2004 (69 FR 39976). This Notice provided 60 days for the public to
request a hearing. On August 30, 2004, the Vermont Department of Public Service and the New England Coalition filed requests for hearing in connection with the proposed amendment.
By Order dated November 22, 2004, the Atomic Safety and Licensing Board (ASLB) granted those hearing requests and by Order dated December 16, 2004, the ASLB issued its decision to conduct a hearing using the procedures in 10 CFR Part 2, Subpart L, Informal Hearing Procedures for NRC Adjudications.
The Commission published a Notice of Consideration of Issuance of Amendment to Facility Operating License and Proposed No Significant Hazards Consideration Determination related to this action in the FEDERAL REGISTER on January 11, 2006 (71 FR 1744). This Notice provided 30 days for public comment. The Commission received comments on the proposed no significant hazards consideration as discussed below.
Under its regulations, the Commission may issue and make an amendment immediately effective, notwithstanding the pendency before it of a request for a hearing from any person, in advance of the holding and completion of any required hearing, where it has determined that no significant hazards consideration is involved.
The Commission has applied the standards of 10 CFR 50.92 and has made a final determination that the amendment involves no significant hazards consideration. Public comments received on the proposed no significant hazards consideration determination were considered in making the final determination. The basis for this determination is contained in the Safety Evaluation related to this action. Accordingly, as described above, the amendment has been issued and made immediately effective and any hearing will be held after issuance.
The Commission published an Environmental Assessment related to the action in the FEDERAL REGISTER on January 27, 2006 (71 FR 4614). Based on the Environmental Assessment, the Commission concluded that the action will not have a significant effect on the
quality of the human environment. Accordingly, the Commission determined not to prepare an environmental impact statement for the proposed action.
For further details with respect to this action, see the application for amendment dated September 10, 2003, as supplemented by letters dated October 1, and October 28 (2 letters),
2003; January 31 (2 letters), March 4, May 19, July 2, July 27, July 30, August 12, August 25, September 14, September 15, September 23, September 30 (2 letters), October 5, October 7 (2 letters), December 8, and December 9, 2004; February 24, March 10, March 24, March 31, April 5, April 22, June 2, August 1, August 4, September 10, September 14, September 18, September 28, October 17, October 21 (2 letters), October 26, October 29, November 2, November 22, and December 2, 2005; January 10, and February 22, 2006, which is available for public inspection at the Commission's PDR, located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management System's (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, 301-415-4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 2nd day of March, 2006.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
