Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: BVY 06-009, 2006/01/25-Vermont Yankee Nuclear Power Station Applicant'S Environmental Report Operating License Renewal Stage, Appendix E, BVY 06-076, 2006/08/10-Vermont Yankee - License Renewal Application, Amendment 8, BVY 06-079, 2006/08/22-Vermont Yankee License Renewal Application, Amendment 11, BVY 06-083, 2006/09/05-Vermont Yankee License Renewal Application, Amendment 12, BVY 06-095, E-mail: (PA-LR) Copy of SAMA Response, BVY 06-096, 2006/10/20-Vermont Yankee - License Renewal Application, Amendment No. 17, BVY 06-097, 2006/10/31-Vermont Yankee License Renewal Application, Amendment 19, BVY 06-098, E-mail: (PA-LR) Copy of Vhs RAI Response, BVY 07-003, Email: (PA-LR) Vermont Yankee Nuclear Power Station License Renewal Commitment List, Rev. 5, BVY 07-009, License Renewal Application, Amendment 24, BVY 07-018, License Renewal Application, Amendment 26, BVY 07-034, License Renewal Application Annual Update, BVY 07-035, (PA-LR) Bvy 07-035 VY Lr SER Comments, BVY 07-047, License Renewal Application, Amendment 27, Submitted on January 25, 2006, BVY 07-058, License Renewal Application, Amendment 29, BVY 07-062, License Renewal Application, Amendment 30, BVY 07-066, License Renewal Application, Amendment 31, BVY 08-016, (PA-LR) Emailing Bvy 08-016 Final SER Review Comments, BVY 10-069, License Renewal Application Annual Update Information, ML060950195, ML060950215, ML060950218, ML060950220, ML060950224, ML060950235, ML060950250, ML060950258, ML060950262, ML060950269, ML060950271, ML060950277, ML060950279, ML060950284, ML060950290, ML060950301, ML060950311, ML060950323, ML060950328, ML060950331, ML060950347, ML060950351, ML060950356, ML060950364, ML060950370, ML060950372, ML060950375, ML060950540, ML060950549, ML060950559, ML060950567... further results
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MONTHYEARML0629203681987-12-31031 December 1987 VY Annual Ecological Studies of the CT River Report 16-final.pdf Project stage: Other ML0629203651989-12-31031 December 1989 VY Annual Ecological Reports from the 1980's (1989) Project stage: Other ML0609503511998-02-28028 February 1998 GALL AMP: XI.M12, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) (Audit Worksheet GALL Report AMP) Project stage: Other BVY 06-009, 2006/01/25-Vermont Yankee Nuclear Power Station Applicant'S Environmental Report Operating License Renewal Stage, Appendix E2006-01-25025 January 2006 2006/01/25-Vermont Yankee Nuclear Power Station Applicant'S Environmental Report Operating License Renewal Stage, Appendix E Project stage: Other ML0609506372006-03-22022 March 2006 GALL AMP: XI.M36, External Surfaces Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503642006-03-22022 March 2006 GALL AMP: XI.M14, Loose Part Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506322006-03-22022 March 2006 GALL AMP: XI.M34, Buried Piping and Tanks Inspection (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506292006-03-22022 March 2006 GALL AMP: XI.M33, Selective Leaching of Materials (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506202006-03-22022 March 2006 GALL AMP: XI.M31, Reactor Vessel Surveillance (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502792006-03-22022 March 2006 GALL AMP: XI.M3, Reactor Head Closure Studs (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609505962006-03-22022 March 2006 GALL AMP: XI.M27, Fire Water System (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505872006-03-22022 March 2006 GALL AMP: XI.M26, Fire Protection (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505822006-03-22022 March 2006 GALL AMP: XI.M25, BWR Reactor Water Cleanup System (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505792006-03-22022 March 2006 GALL AMP: XI.M24, Compressed Air Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505592006-03-22022 March 2006 GALL AMP: XI.M20, Open-Cycle Cooling Water System (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505402006-03-22022 March 2006 GALL AMP: XI.M18, Bolting Integrity (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503702006-03-22022 March 2006 GALL AMP: XI.M15, Neutron Noise Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502182006-03-22022 March 2006 GALL AMP: X.M1, Metal Fatigue of Reactor Coolant Pressure Boundary (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609501952006-03-22022 March 2006 GALL AMP: Plant-Specific (Audit Worksheet - GALL Report AMP) Project stage: Other ML0610001472006-03-22022 March 2006 GALL AMP: XI.S8, Protective Coating Monitoring and Maintenance Program (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001432006-03-22022 March 2006 GALL AMP: XI.S7, Rg 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001382006-03-22022 March 2006 GALL AMP: XI.S6, Structures Monitoring Program (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001342006-03-22022 March 2006 GALL AMP: XI.S5, Masonry Wall Progam (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001262006-03-22022 March 2006 GALL AMP: XI.S4, 10 CFR 50, Appendix J (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001012006-03-22022 March 2006 GALL AMP: XI.S2, ASME Section XI, Subsection Iwl (Audit Worksheet GALL Report AMP) Project stage: Other ML0610000962006-03-22022 March 2006 GALL AMP: XI.S1, ASME Section XI, Subsection IWE (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503232006-03-22022 March 2006 GALL AMP: XI.M8, BWR Penetrations (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609503112006-03-22022 March 2006 GALL AMP: XI.M7, BWR Stress Corrosion Cracking (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503012006-03-22022 March 2006 GALL AMP: XI.M6, BWR Control Rod Drive Return Line Nozzle (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502902006-03-22022 March 2006 GALL AMP: XI.M5, BWR Feedwater Nozzle (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609503472006-03-22022 March 2006 GALL AMP: XI.M11A, Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of Pressurized Water Reactors Project stage: Other ML0609503722006-03-22022 March 2006 GALL AMP: XI.M16, PWR Vessel Internals (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503752006-03-22022 March 2006 GALL AMP: XI.M17, Flow-Accelerated Corrosion (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505492006-03-22022 March 2006 GALL AMP: XI.M19, Steam Generator Tube Integrity (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502772006-03-22022 March 2006 GALL AMP: XI.M2, Water Chemistry (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609505672006-03-22022 March 2006 GALL AMP: XI.M21, Closed-Cycle Cooling Water System (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505702006-03-22022 March 2006 GALL AMP: XI.M22, Boraflex Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505732006-03-22022 March 2006 GALL AMP: XI.M23, Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506062006-03-22022 March 2006 GALL AMP: XI.M28, Buried Piping and Tanks Surveillance (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506102006-03-22022 March 2006 GALL AMP: XI.M29, Aboveground Steel Tanks (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506242006-03-22022 March 2006 GALL AMP: XI.M32, One-Time Inspection (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506342006-03-22022 March 2006 GALL AMP: XI.M35, One-Time Inspection of ASME Code Class 1 Small Bore Piping (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503562006-03-22022 March 2006 GALL AMP: XI.M13, Thermal Aging and Neutron Irradiation Embrittlement of Cast Austenitic Stainless Steel (CASS) (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502502006-03-22022 March 2006 GALL AMP: XI.E3, Inaccessible Medium-Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet GALL Report AMP) Project stage: Other ML0610000782006-03-22022 March 2006 GALL AMP: XI.M38, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502152006-03-22022 March 2006 GALL AMP: X.E1. Environmental Qualification (EQ) of Electric Components (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502202006-03-22022 March 2006 GALL AMP: X.S1, Concrete Containment Tendon Prestress (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502242006-03-22022 March 2006 GALL AMP: XI.E1, Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502352006-03-22022 March 2006 GALL AMP: XI.E2, Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502692006-03-22022 March 2006 GALL AMP: XI.E6, Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet, GALL Report AMP) Project stage: Other 1998-02-28
[Table View] |
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Category:2.206 Acknowledgment Letter
MONTHYEARML15286A2652016-01-20020 January 2016 OEDO-15-00251: Letter to Vermont Yankee 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 ML15275A1992015-10-0202 October 2015 Letter from Annette Vietti-Cook to Timothy Judson Regarding Declination of Commission Review of DD-15-08 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 ML13154A3132013-08-0707 August 2013 G20130211 Letter to Timothy Judson 2.206 Financial Qualifications Fitzpatrick/Vermont Yankee/Pilgrim ML1125503832011-09-19019 September 2011 G20110477/LTR-11-0368/EDATS: SECY-2011-0376 - Response to 2.206 Petitioner Thomas Saporito in Regards to Entergy/Palisades, Vermont Yankee and J. Wayne Leonard ML1114502092011-06-0202 June 2011 G201101191/EDATS: OEDO-2011-0206 - Ltr to Michael Mullligan 2.206 Vermont Yankee Construction Defects ML1106012622011-03-28028 March 2011 G20110043/EDATS: OEDO-2011-0058 - Thomas Saporito Regarding: 2.206 - Vermont Yankee Nuclear Power Station--Acknowledgement Letter ML1014500042010-06-25025 June 2010 G20100027/EDATS: OEDO-2010-0022/G20100074/EDATS: OEDO-2010-0087/G20100098/LTR-10-0069/EDATS: OEDO-2010-0145 - 2.206 Petitioners Letters Vermont Yankee Tritium Leaks ML0729201902007-11-0606 November 2007 G20070597/LTR-07-0568 - Raymond Shadis Letter, 2.206 Petition from the New England Coalition (NEC) Dated August 27, 2007, Addressed to Mr. Luis A. Reyes, Executive Director for Operations of the Nuclear Regulatory Commission ML0629204232006-10-0303 October 2006 (E-Mail) Cooling Tower Report for VY ML0531401972005-12-0707 December 2005 G20050706 - Jonathan M. Block Ltr 2.206 Acknowledgement Letter - Vermont Yankee Emergency Evacuations ML0526304112005-10-20020 October 2005 G20050379 - Paul Gunter Ltr 2.206 Inoperable Hemyc/Mt Fire Protection Systems, Proposed Directors Decision ML0501400172005-01-26026 January 2005 G20040831 - Raymond Shadis Ltr. Re. Degraded Emergency Notification System at Vermont Yankee Nuclear Power Station (2.206 Petition) ML0414003172004-05-28028 May 2004 G20040284 /LTR-04-0249 - Vermont Yankee, 2.206 Acknowledgment Letter, Request to Halt All Fuel Movement at Vermont Yankee ML0234605632002-12-20020 December 2002 G20020602 - Raymond Shadis Ltr. 2.206 - Vermont Yankee Personnel Unfamiliar with Plant Design 2016-01-20
[Table view] Category:E-Mail
MONTHYEARML21075A1582021-03-15015 March 2021 E-mail from T. Silko to J. Parrott, NMSS, Vermont Yankee on the State of Vermont Comments on the Review of the Draft Final SER and EA for 20.2002 Alternate Disposal Request ML21006A0242020-12-22022 December 2020 E-mail from J. Parrott to J. Tierney and N. Creed Vermont Yankee Request to NRC for Alternate Disposal of Wastewater ML20358A0702020-12-22022 December 2020 E-mail Acceptance Review for Request for Indirect License Transfer (License DPR-28, Docket No. 50-271) ML20175A2122020-06-23023 June 2020 Acceptance Review of Request for Alternate Disposal of Wastes Under 10 CFR 20.2002 (License DPR-28, Docket No. 50-271) ML19289A1292019-10-11011 October 2019 Email from Daniel Doyle to Mark Leyse Status of PRM-50-93 and PRM-50-95 ML19288A0292019-10-11011 October 2019 NRC Acceptance Review - Northstar Request for Exemption from 10 CFR 20, App G, Section Iii.E (License DPR-28, Docket No. 50-271) ML19198A2512019-06-20020 June 2019 Alternate Disposal Request - Rail Shipments (License DPR-28, Docket No. 50-271) ML19059A1782019-02-28028 February 2019 Acceptance Review Results for Relief Request No. EN-19-RR-1 to Use ASME Code Case N-831-1 for Entergy Fleet ML18289A3622018-10-11011 October 2018 Email from Daniel Doyle to Mark Leyse Status of PRM-50-93 and PRM-50-95 ML18127A5582018-04-25025 April 2018 Email to State of Vermont on Vermont Yankee Nuclear Power Station - Forthcoming Issuance of a License Amendment Regarding the Requirement for the VYNPS to Have a Cyber Security Plan ML18045A0862018-01-25025 January 2018 Email Request for Review of the Draft Safety Evaluation for Implementation of a Revised Emergency Plan at Vermont Yankee to Reflect an ISFSI-only Configuration ML17353A0092017-12-18018 December 2017 E-Mail from William Irwin, Vermont Department of Health to Y. Chen/Dsfm Response: Draft Environmental Assessment: Exemption Request for Vermont Yankee Independent Spent Fuel Storage Installation ML17289A4222017-10-16016 October 2017 E-Mail from Y. J. Chen to W. Irwin Draft Environmental Assessment Exemption Request for Vermont Yankee Independent Spent Fuel Storage Installation ML17257A0022017-09-14014 September 2017 Email to VY Shpo W Ltr Re VYNPS Exemption Load Campaign - Sept 2017 ML17229B4842017-08-16016 August 2017 Request for Supplemental Documentation to Support Review of the Physical Security Plan ML17219A0472017-08-0303 August 2017 8/03/2017, E-Mail from Y. J. Chen/Nmss to T. B. Silko/Vermont Yankee Regarding Need for Additional Information Entergy'S Exemption Request for Vermont Yankee ISFSI, Dated May 16, 2017 (ML17142A358) ML17144A0452017-05-23023 May 2017 5/23/2017, E-Mail to I. William/Vermont Dept. of Health from Y. Chen/Nrc Response: Draft Environment Assessment: Exemption Request for Vermont Yankee Independent Spent Fuel Storage Installation (W/Attachment Ltr to Address Comments on EA) ML17080A4752017-03-16016 March 2017 3/16/2017, E-Mail from I. William/Vermont Department of Health to Yen-Ju Chen/Dsfm/Sflb, Providing Comments on Draft Environmental Assessment for Entergy/Vermont Yankee'S Exemption from Requirement of 10 CFR 72.7 for CoC No. 72-1014, Amendm ML17055A6262017-02-24024 February 2017 Cover Email from VY Shpo W Concurrence on No Effects Determination ML17040A3372017-02-0909 February 2017 Email and Letter to Vermont Shpo ISFSI Exemption No Effects Determination ML17038A4682017-02-0707 February 2017 2/07/2017, E-mail from Yen-Ju Chen/NRC-DSFM to W. Irwin/Vermont Dept. of Health Draft Environment Assessment for Entergy/Vermont Yankee'S Exemption from Requirement of 10 CFR 72.7 for Certificate of Compliance No. 72-1014, Amendment 10 ML17012A2472017-01-11011 January 2017 E-mail - State of Vermont Comments Regarding Vermont Yankee'S 10 CFR 20.2002 Request ML16349A2492016-12-13013 December 2016 E-Mail to T. B. Silko/Entergy from Yen-Ju Chen/Dsfm Regarding Need for Supplemental Information for Entergy'S Exemption Request for Vermont Yankee ISFSI, Dated November 9, 2016 (ML16319A102) ML17013A2502016-12-12012 December 2016 Email Requesting Review of Draft EA and SER for Vermont Yankee Request to NRC for Alternate Disposal of Waste ML16231A0282016-08-11011 August 2016 Response to NRC Questions Related to Request for 20.2002 Disposal of Contaminated Water ML16231A2192016-07-28028 July 2016 Follow-up Questions Related to Entergy Request for 20.2002 Disposal of Contaminated Water ML16069A0952016-03-0303 March 2016 Request for 20.2002 Disposal, Request for Additional Information ML16053A5152016-02-17017 February 2016 Comment (037) of Emma Stamas on ANPR-26, 50, 52, 73, and 140 - Regulatory Improvements for Decommissioning Power Reactors ML15329A1802015-11-24024 November 2015 E-mail from J. Whited Draft RAIs Re Duke License Amendment Request to Adopt TSTF-523 (CAC Nos. MF6413 Through MF6422) ML15295A2132015-10-21021 October 2015 NRR E-mail Capture - VY RAI for Off-site Insurance Exemption (10 CFR 140.11) - MF3980 ML15289A6002015-09-24024 September 2015 La 3 - Vermont Yankee Draft Responses or Edits 9 24 15.docx ML15289A6012015-09-23023 September 2015 La 3 - Nrr_Vermont Yankee Nuclear Power Station Decommissioning Status.Docx ML15288A3532015-09-21021 September 2015 La 3 - VY Dtf LAR - Status ML15257A6172015-09-14014 September 2015 La 3 - Testing the New Profile for Vermont Yankee La 3 - Public ML15195A3592015-07-14014 July 2015 NRR E-mail Capture - Acceptance Review for Vermont Yankee Amendment -Revise Cyber Security Plan Implementation ML15289A0022015-06-17017 June 2015 La 3 - Question from Ma ML15289A5982015-06-0909 June 2015 La 3 - FW: Docket No. 50-271 (Vermont Yankee); June 5 2015 Letter from Vermont, Vynpc, and Gmp to NRC Attached ML15289A0072015-06-0505 June 2015 La 3 - Information Regarding Vermont Yankee Decommissioning Trust Fund Exemption ML15289A2432015-06-0404 June 2015 La 3 - FW: Docket No. 50-271 (Vermont Yankee); June 4 2015 Vermont Letter to NRC Attached ML15289A0062015-06-0404 June 2015 La 3 - FW: Information Regarding Vermont Yankee Decommissioning Trust Fund Exemption ML15288A3592015-06-0101 June 2015 La 3 - Vermont Yankee LA3 - Availability for Oral Argument ML15288A3602015-06-0101 June 2015 La 3 - Vermont Yankee LA3 - Availability for Oral Argument ML15288A3622015-06-0101 June 2015 La 3 - Vermont Yankee LA3 - Availability for Oral Argument ML15288A4822015-05-22022 May 2015 La 3 - Vermont Reply to NRC & Entergy Answers Re VY LA-3 ML15289A0042015-05-19019 May 2015 La 3 - New Proposal Dates for Phone Call with VT ML15289A0052015-05-11011 May 2015 La 3 - ML Numbers for Disbursement Letters for Vermont Yankee ML15289A5992015-05-0808 May 2015 La 3 - Call with State of VT ML15289A0032015-05-0707 May 2015 La 3 - Other than for Comanche Peak, ML15289A1252015-05-0606 May 2015 La 3 - FRN Review - VY Dtf Exemption ML15128A0232015-04-27027 April 2015 NRR E-mail Capture - Petitioners Response to Request for Comments on the Proposed Director'S Decision on the 2.206 Petition Regarding Financial Qualifications of Entergy 2021-03-15
[Table view] Category:Report
MONTHYEARML21075A1772021-03-15015 March 2021 Response to Vermont Yankee on the State of Vermont Comments on the Review of the Draft Final SER and EA for 20.2002 Alternate Disposal Request BVY 20-026, Defueled Safety Analysis Report, Revision 22020-09-23023 September 2020 Defueled Safety Analysis Report, Revision 2 BVY 19-020, 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 20192019-06-20020 June 2019 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 2019 ML19198A2522019-06-20020 June 2019 Alternate Disposal Request - Rail Shipments (License DPR-28, Docket No. 50-271) ML16176A3392016-10-28028 October 2016 Decommissioning Lessons Learned Report and Transmittal Memorandum ML15266A4302015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 24, Flow Diagram Instrument Air System. Sheet 2 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191595, Control Room Bldg. Ext. Wall Elevs.-M.2015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191595, Control Room Bldg. Ext. Wall Elevs.-M. ML15266A4452015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191163, Rev. 51, Flow Diagram Fire Protection System Inner Loop. Sheet 2 ML15266A4442015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191163, Rev. 51, Flow Diagram Fire Protection System Inner Loop. Sheet 1 ML15266A4402015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 8 ML15266A4362015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 7 ML15266A4352015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 6 ML15266A4342015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 5 ML15266A4332015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 4 ML15266A4322015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 31, Flow Diagram Instrument Air System. Sheet 3 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 22015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 2 ML15266A4292015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 37, Flow Diagram Instrument Air System. Sheet 1 ML15266A4282015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191159, Rev. 100, Flow Diagram Service Water System. Sheet 2 ML15266A4272015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191159, Rev. 92, Flow Diagram Service Water System. Sheet 1 ML15266A4262015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191152, Rev. 14, General Arrangement Radwaste Building Section. ML15266A4252015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191151, Rev 19, General Arrangement Radwaste Building Plans. ML15266A4242015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191150, Rev. 20, General Arrangement Reactor Building Section. ML15266A4232015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191149, Rev. 27, General Arrangement Reactor Building Plans Sheet 2. ML15266A4222015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191148, Rev. 23, General Arrangement Reactor Building Plans Sheet 1. ML15266A2722015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report - List of Effective Pages BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 52015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 5 ML15266A2832015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, DSAR Drawing List BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191529, Reactor Building Reactor Vessel Pedestal Mat - M&R.2015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191529, Reactor Building Reactor Vessel Pedestal Mat - M&R. ML15266A2712015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, DSAR Changes ML15266A2732015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, UFSAR to DSAR Conversion Matrix ML15267A6092015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 125V DC One Line Diagram, Sheet 3 BVY 15-046, Rev. 0 to Defueled Safety Analysis Report, Drawing G-200347, Circulating Water System Aerating Structure-MAS & Reinf.2015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-200347, Circulating Water System Aerating Structure-MAS & Reinf. ML15267A6612015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191595, Control Room Bldg. Ext. Wall Elevs.-M. ML15267A6592015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191592, Control Room Building Fl Plan El 248.50 & Fdn Plan-R, Sheet 1 ML15267A6562015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191529, Reactor Building Reactor Vessel Pedestal Mat - M&R. ML15267A6542015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191483, Reactor Building Foundation Mat Plan - M&R. ML15267A6512015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191463, Circulating Water System Discharge Structure Reinf, Sheet 2 ML15267A6492015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191461, Circulating Water System Discharge Structure - Sections, Sheet 1 ML15267A6472015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191453, Circulating Water System Intake Structure-M, Sheet 3 ML15267A6452015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191452, Circulating Water System Intake Structure-V, Sheet 2 ML15267A6412015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191451, Circulating Water System Intake Structure-M, Sheet 1 ML15267A6112015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 5 ML15267A6102015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 120/240V Vital AC and Instrument AC One Line Diagram, Sheet 4 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 12015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 1 ML15267A6082015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 125V DC One Line Diagram, Sheet 2 ML15267A6072015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 1 ML15267A6062015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 2 ML15267A6052015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 30, 480V Aux. One Line Diagram Swgr BUS-9, MCC-9A, 9C. Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191461, Circulating Water System Discharge Structure - Sections, Sheet 12015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191461, Circulating Water System Discharge Structure - Sections, Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191483, Reactor Building Foundation Mat Plan - M&R.2015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191483, Reactor Building Foundation Mat Plan - M&R. 2021-03-15
[Table view] Category:Miscellaneous
MONTHYEARML21075A1772021-03-15015 March 2021 Response to Vermont Yankee on the State of Vermont Comments on the Review of the Draft Final SER and EA for 20.2002 Alternate Disposal Request BVY 19-020, 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 20192019-06-20020 June 2019 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 2019 ML16176A3392016-10-28028 October 2016 Decommissioning Lessons Learned Report and Transmittal Memorandum BVY 15-049, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2015-08-19019 August 2015 Submittal of 10 CFR 71.95 Report Involving 8-120B Cask BVY 15-018, Transmittal of Biennial 10 CFR 50.59 Report2015-03-0202 March 2015 Transmittal of Biennial 10 CFR 50.59 Report BVY 14-085, Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb)2014-12-19019 December 2014 Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb) BVY 14-011, Revision to Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima ...2014-02-25025 February 2014 Revision to Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima ... BVY 13-090, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2013-10-0202 October 2013 Submittal of 10 CFR 71.95 Report Involving 8-120B Cask BVY 12-081, Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-21021 November 2012 Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML12160A3732012-06-11011 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to the Fukushima Daichii Nuclear Plant Accident TAC No. ME8747) ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants BVY 07-079, Update of Aging Management Program Audit Q&A Database2007-11-14014 November 2007 Update of Aging Management Program Audit Q&A Database BVY 07-004, Emergency Response Data System (ERDS) Data Point Library Update2007-06-21021 June 2007 Emergency Response Data System (ERDS) Data Point Library Update ENOC-07-00002, Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 20062007-02-28028 February 2007 Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 2006 L-87-005, Various CRS 08/09/2005 to 02/08/20072007-02-0808 February 2007 Various CRS 08/09/2005 to 02/08/2007 ML0706703802007-02-0101 February 2007 NDE Reports 07-001 Thru 07-008 ML0701705912007-01-0909 January 2007 VYNPS - SEIS Web Reference - Us Census Glossary ML0701701982006-12-15015 December 2006 VYNPS - SEIS Web Reference - Connecticut River Migratory Fish Counts 1967-2005 ML0629204232006-10-0303 October 2006 (E-Mail) Cooling Tower Report for VY ML0629203422006-09-18018 September 2006 (E-Mail) Air Emissions Inventory Report for 2005 and MSDS for Nalco H-550 ENOC-06-00018, Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 20062006-08-29029 August 2006 Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 2006 BVY 06-068, Cycle 25 Startup Test Report Following Power Ascension and Testing2006-08-0101 August 2006 Cycle 25 Startup Test Report Following Power Ascension and Testing CNRO-2006-00034, Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee2006-07-13013 July 2006 Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee ML0618803852006-05-22022 May 2006 Windham Regional Plan Draft, May 22, 2006 ML0704404852006-05-12012 May 2006 AMRM-16, Revision 0, Aging Management Review of the Instrument Air System. ML0704404832006-05-12012 May 2006 AMRM-15, Revision 0, Aging Management Review of the Fuel Oil System. ML0704404782006-05-12012 May 2006 AMRM-15, Aging Management Review of the Fuel Oil System ML0704404742006-05-12012 May 2006 AMRM-12, Aging Management Review of the Reactor Building Closed Cooling Water System ML0704404862006-05-11011 May 2006 AMRM-30, Rev. 01, Aging Management Review of Ns Systems Affecting Safety Systems BVY 06-033, Cycle 24 10 CFR 50.59 Report2006-04-24024 April 2006 Cycle 24 10 CFR 50.59 Report BVY 06-031, Revision 1 to Steam Dryer Monitoring Plan2006-03-26026 March 2006 Revision 1 to Steam Dryer Monitoring Plan ML0609503562006-03-22022 March 2006 GALL AMP: XI.M13, Thermal Aging and Neutron Irradiation Embrittlement of Cast Austenitic Stainless Steel (CASS) (Audit Worksheet GALL Report AMP) ML0609503642006-03-22022 March 2006 GALL AMP: XI.M14, Loose Part Monitoring (Audit Worksheet GALL Report AMP) ML0609502712006-03-22022 March 2006 GALL AMP: XI.M1, ASME Section XI Inservice Inspection, Subsections Iwb, Iwc, and Iwd (Audit Worksheet, GALL Report AMP) ML0609505492006-03-22022 March 2006 GALL AMP: XI.M19, Steam Generator Tube Integrity (Audit Worksheet GALL Report AMP) ML0609502772006-03-22022 March 2006 GALL AMP: XI.M2, Water Chemistry (Audit Worksheet, GALL Report AMP) ML0609502152006-03-22022 March 2006 GALL AMP: X.E1. 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Text
Richard Emch- Cooling Tower Report for VY c , 0 L_ .... Page1l From: "DeWald, Lynn" <Idewald@entergy.com>
To: <rle @ nrc.gov>, <david.s.miller@
anl.gov>Date: 10/03/2006 12:14:34 PM
Subject:
Cooling Tower Report for VY Attached is the VY Evaporative Loss Report, Revision 1, with twenty-one (21) 200 HP fans and one (1) 125 HP fan. This is the final as-installed configuration.
The report discusses drift and evaporative loss. Lynn CC: "BUCKLEY, RICKY N" <RBUCKLE@entergy.com>
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- Junk List is not enabled Junk Mail using personal address books is not enabled Block List is not enabled kEntergy EXTENDED POWER UPRATE COOLING TOWER EVAPORATIVE LOSS STUDY for VERMONT YANKEE NUCLEAR POWER STATION Prepared for Entergy Nuclear Vermont Yankee, LLC Revision 1 June 2003 Prepared by Sh-awm- Stone & Webster, Inc.
SEntergy EXTENDED POWER UPRATE COOLING TOWER EVAPORATIVE LOSS STUDY for VERMONT YANKEE NUCLEAR POWER STATION Prepared for Entergy Nuclear Vermont Yankee, LLC Revision 1 June 2003 Prepared by Shlaw" Stone & Webster, Ina Extended Power Uprate Cooling Tower Evaporative Loss Study Vermont Yankee Nuclear Power Station TABLE OF CONTENTS I OBJECTIVE
............................................................................................................................
I 2
SUMMARY
OF RESULTS ..................................................................................................
I 3 EVALUATION
........................................................................................................................
1 3.1 Methodology
....................................................................................................
1 Background
.................................................................................................................
1 Approach .....................................................................................................................
2 3.2 Inputs and Assumptions
...............................................................................
3 3.3 Evaluation of Summer Water Consumption Rates ......................................
4 3.4 Evaluation of W inter W ater Consumption Rates ..........................................
7 3.5 Minimum River Flow ....................................................................................
9 4 CONCLUSION
......................................................................................................................
10 5 REFERENCES
......................................................................................................................
10 APPENDIX A -SUPPLEMENTAL INFORMATION Figure A-1 Circulating Water, Condenser, Cooling Tower Network Figure A-2 Determination of Flow Rates Entergy Extended Power Uprate Cooling Tower Evaporative Loss Study Vermont Yankee Nuclear Power Station I OBJECTIVE The purpose of this report is to determine the Vermont Yankee Nuclear Power Station (VYNPS)cooling towers' increased water consumption rate due to evaporation and drift under Extended Power Uprate (EPU) conditions of 120% Reactor Thermal Power.* Safety Classification:
Non-Safety Related* Affected System: Circulating Water (CW)Revision 1 of this report incorporates new PEPSE heat balance runs,, which utilized 125 HP cooling tower fans. The PEPSE results of Table 3.3-3 were revised to bound the original 200 HP cases and new 125 HP cases. PEPSE was only used as a check on the evaluation method, and this revision confirms that there are no changes to the results or conclusions of the original study, assuming 125 HP to 200 HP fans. This revision supercedes the previous version of the report dated February 2003.2
SUMMARY
OF RESULTS Monthly average water consumption rates determined in this report are summarized on Figures 3.3-1 and 3.3-2 for summer cooling tower operation, Figures 3.4-1 and 3.4-2 for winter cooling tower operation, and Table 3.5-1 for minimum river flow conditions.
In the limiting case of minimum river flow, as given in Table 3.5-1, the evaporation and drift consumption is less than 1.5% of the minimum river flow value of 1250 cfs.3 EVALUATION 3.1 Methodology
Background
The VYNPS is currently licensed to operate at a core thermal power of 1593 MWt. This study evaluates the change in evaporative loss as a result of increasing the core power rating up to 1912 MWt, an increase of approximately 20%. Evaporative loss is the amount of water vapor evaporated and discharged from the cooling tower fans into the atmosphere.
Drift is the water entrained in vapor discharged from the cooling tower. The evaporative loss plus drift represents a use of river water that is not recycled back to the river.During cold weather / winter periods from October 15 through May 15, the circulating water system is normally operated in straight open cycle. This means that the river water drawn into the plant intake is passed once through the condenser and returned to the river without using the cooling tower. With open cycle, there is no evaporative cooling and therefore no evaporative loss.During warmer weather / summer periods from May 16 to October 14, the cooling tower operates predominantly in hybrid mode. In hybrid mode, the cooling tower operation, or load on the cooling tower, varies as environmental conditions change consistent with NPDES thermal discharge limits. For example, when the river flow is high (greater than approximately 8000 cfs), the thermal capacity of the river is high and the cooling tower is either not needed, or is very lightly loaded. On the other hand, during extreme summer drought conditions when the river 1 Entergy Extended Power Uprate Cooling Tower Evaporative Loss Study Vermont Yankee Nuclear Power Station flow is low and the river temperature is high, the river's thermal capacity is minimal, and the evaporative cooling process of the cooling towers rejects most of the plant's heat load.The highest evaporation rate occurs when operating in closed cycle where the entire plant's heat load is handled by the cooling towers. At Vermont Yankee, the cooling tower is operated very rarely in closed-cycle mode (about once every 2 or 3 days per week in summer for only 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> while chlorination treatments are performed).
Approach Since the cooling tower operates primarily in hybrid mode, and the cooling tower heat load (and rate of evaporation) can vary widely each day, this evaluation determined monthly average evaporative loss values based on over 11 years of historical monthly average environmental conditions.
The evaporation rate was determined for the following operating conditions:
- 100% Power, Current NPDES, Summer* 120% Power, Current NPDES, Summer* 120% Power, Proposed NPDES, Summer* 120% Power, Current NPDES, Winter (only during winter months with <1500 cfs river flow)Heat transfer by the cooling tower is accomplished mostly by the evaporation of water. A small amount of this heat is also used to increase the sensible heat of air leaving the tower. This study estimated evaporative loss with the conservative assumption that all cooling tower heat transfer was by evaporation, calculated using the Latent Heat of Evaporation (Hfg) of water at the cooling tower Inlet.The monthly average cooling tower heat load was determined from heat balance data. Heat balances were performed using a Performance Evaluation of Power System Efficiencies (PEPSE) model (Ref. 1) of the plant, including the heat rejection system. The cooling tower performance characteristics used in the PEPSE model were based on the predictions in the Tower Performance, Inc (TPI) cooling tower report (Ref. 2).For PEPSE to calculate the cooling tower heat load, three boundary condition parameters were required (river flow, allowable river temperature rise, and wet bulb temperature).
The allowable river temperature rise was determined from the NPDES permit. Table 3.1-1 summarizes the available environmental data.Table 3.1-1 Available Environmental Data River Temperature River Flow Wet Bulb 1991 thru 1999 12 mos (2) 12 mos (2) 12 mos (1)2000 & 2001 12 mos (2) 12 mos (2) NA 2002 May -Dec. (2) May -Dec. (2) NA 1. National Climatic Data Center (NCDC) Source -actual data was dew point and drybulb temperatures from which wetbulb temperature was calculated (see Ref. 4).2. Normandeau Source (see Ref. 3) -Normandeau provided the mean monthly values in lieu of the raw hourly data. Note October 1996 data not available.
2 Entergy 2 Entergy Extended Power Uprate Cooling Tower Evaporative Loss Study Vermont Yankee Nuclear Power Station This report used a simplified method to calculate the cooling tower heat load that only required river flow data and allowable river temperature rise (not wet bulb temperature) by: 1. Assuming the condenser duty or heat rejection was a constant for each power level. The values chosen were based on bounding PEPSE runs. See Inputs and Assumptions Section 3.2 e.2. Calculating the river heat capacity based on river flow and allowable temperature differential from NPDES permit.3. Calculating the cooling tower heat load by subtracting the river heat capacity from the condenser duty.Using the simplified method, the evaporative loss for 1991 through 2002 period was calculated.
More detailed PEPSE model analyses were performed for several cases for comparison purposes.
This comparison confirmed that the simplified analyses were conservative.
For winter months that historically have had significant times (greater than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />) of river flow below 1500 cfs, evaporation rates were determined using the average river flow and the current winter NPDES permit limit. As shown in Appendix A, Figure A-2, 1500 cfs is the approximate minimum river flow required to accommodate the 120% heat load with current winter NPDES permit limit. Evaporation rates for such winter periods were estimated using a simplified analysis similar to the summer analysis.Comparison cases were also evaluated for a minimum river flow of 1250 cfs and the 7Q10 river flow rate of 1524 cfs. 7Q10 is a measure of the naturally recurring low river flow. It is the lowest flow that occurs for 7 consecutive days in a 10-year period.3.2 Inputs and Assumptions
- a. River Temperature and Flow data was obtained from Mark Mattson, Vice President, Normandeau Associates, Inc. (Ref. 3)b. Dew point and drybulb temperature data temperature data for Albany was obtained from the National Climatic Data Center (NCDC) (Ref. 4).c. The cooling tower performance predictions were obtained from Tower Performance Inc. (TPI). TPI Cooling Tower Report for Vermont Yankee (Ref. 2).d. PEPSE current and uprate heat balance models (Ref. 1) were used as input to this analysis.
These models are tuned to plant operating data. The uprate model incorporated the proposed new HP steam turbine.e. Heat rejection for the 100% case of 3712 x 106 Btu/hr and for the 120% case of 4443 x 106 Btu/hr was based upon 5 in. Hg condenser backpressure.
This was conservative, as the condenser will typically operate at a lower backpressure, resulting in less heat rejection (Ref. 1).f. This study utilized a 1.6 degree temperature increase in lieu of the current NPDES summer permit of 2 degree temperature increase to reflect current plant operational practice.
This was conservative because using a lower increase in river temperature resulted in greater calculated evaporation.
Likewise, a 2.6 degree temperature increase was used in lieu of the proposed NPDES summer permit of 3 degree temperature increase, which also resulted in greater calculated evaporation.
3 Entergy Extended Power Uprate Cooling Tower Evaporative Loss Study Vermont Yankee Nuclear Power Station g. The higher NPDES limits allowed during brief periods in the Spring and Fall due to lower river temperatures have been conservatively ignored. These higher limits would result in lower evaporation rates than determined in this study.h. Latent heat of evaporation, hfg, of 1031.4 Btu/Ib based upon a maximum estimated cooling tower inlet water temperature of 110 F.i. Winter study utilized a 13 degree allowable river temperature increase.
This is conservatively lower than the 13.4 degree rise contained in the current NPDES winter permit to account for operating margin.j. The minimum river flow utilized for a comparison case was 1250 cfs. This flow is for comparison only and not based upon recorded data.k. The 7Q10 comparison case utilized a river flow of 1,971,129,600 gpd (1524 cfs)based upon Vermont Water Quality Standards and Reference 5.1. The cooling tower drift was 183 gpm (total for both towers) based upon 0.05% of the total circulating water flow of 366,000 gpm as described in Reference
- 2. The drift was added to the evaporation to obtain total water consumption.
The increase in drift due to higher horsepower cooling tower fan motors was considered to be negligible.
The drift was assumed to be 183 gpm for both summer and winter evaluations, even though winter operation may potentially utilize lower Circulating Water flows, which would result in less drift.3.3 Evaluation of Summer Water Consumption Rates The simplified approach described in Section 3.1 was utilized to calculate monthly average evaporation rates. Using the average monthly river flow supplied by Normandeau for May through October for the years 1991 through 2002, the cooling tower heat load was determined by subtracting the allowable heat rejection to the river from the condenser duty. The evaporative loss was calculated using the Latent Heat of Evaporation, hfg. Three different cases were evaluated:
100% power with current NPDES permit, 120% power with current NPDES permit, and 120% power with proposed NPDES permit. The calculated evaporation rates are shown on Figures 3.3-1 and 3.3-2 in terms of gpm and as percent of river flow. As stated in Assumption (I), drift of 183 gpm was added to the calculated evaporation to determine total water consumption.
4 Entergy Extended Power Uprate Cooling Tower Evaporative Loss Study Vermont Yankee Nuclear Power Station Figure 3.3-1 1991 -2002 Average Monthly Water Consumption 0.45% 18000 0.40% 16000 0.35% 14000 S0.3D% 12000 0.25% 100009 CC rU.000 0.15%6000 0.10%. 4000 0.05%. 2000 0.0016 0 May June July August September October Month 1in100% Current NPDES I=120% Current NPDES =120% Proposed NPDES -RiverFlowi Figure 3.3.2 1991 -2002 Average Monthly Water Consumptionion 16000 6000 14000~12000 a-400 10000U 1000 May June July August "September October Month FiM1-00% Current NPOES =120% Current NPDES 120% Proposed NPDES -River Flow Note the difference in evaporation rates between 120% Current NPDES and 120% Proposed NPDES cases. The proposed I1 F higher river temperature rise reduced the load on the cooling tower, and thereby reduced evaporation.
When river flow is above approximately 3800 cfs (see Appendix A, Figure A-2), the 120% case at the proposed NPDES has less evaporation than 5 Entergy 5 Entergy Extended Power Uprate Cooling Tower Evaporative Loss Study Vermont Yankee Nuclear Power Station both the 120% and 100% cases with the current NPDES limits. Tables 3.3-1 and 3.3-2 give the 1991-2002 Average Monthly Consumption for % river flow and gpm, respectively.
TABLE 3.3-1 1991 -2002 Average Monthly Water Consumption
(% River Flow)100% Current 120% Current 120% Proposed River Flow NPDES NPDES NPDES (CFS)May 0.01% 0.01% 0.00% 15931 June 0.06% 0.10% 0.04% 7922 July 0.17% 0.22% 0.16% 5369 August 0.28% 0.36% 0.27% 3773 September 0.31% 0.40% 0.31% 3536 October 0.13% 0.18% 0.11% 5909 TABLE 3.3-2 1991 -2002 Average Monthly Water Consumption (gpm)100% Current 120% Current 120% Proposed River Flow NPDES NPDES NPDES (CFS)May 460 878 205 15931 June 2227 3460 1545 7922 July 4000 5300 3759 5369 August 4754 6172 4530 3773 September 4919 6337 4960 3536 October 3503 4733 2841 5909 The tuned PEPSE model incorporated the cooling tower, the river, and the necessary splitters, mixers, and source components to simulate the various modes of CW System operation (Open Cycle, Closed Cycle, and Hybrid Cycle). The PEPSE model was used to spot check the results of the simplified analysis, and it was found that the latter produces reasonably accurate results that slightly overpredict the evaporation rate. Table 3.3-3 presents the comparison of the simplified analysis versus the PEPSE analyses results.6 Entergy 6 Entergy Extended Power Uprate Cooling Tower Evaporative Loss Study Vermont Yankee Nuclear Power Station TABLE 3.3-3 Comparison between Simplified (hfg) Method and PEPSE Mean Wet Evaporation Rate Month River Bulb Reactor River NPDES Simplified PEPSE Difference Flow Temp. Thermal Temp. (OF) (hfg) method N (cfs) (OF) (OF) method (gpm)(gmeto gm Aug-98 5050 64.9 120 73.1 2 4403 4218 4.21 Sep-98 3828 58.6 120 68.7 3 3802 3583 5.76 Jun-99 3212 62 120 70.7 1.6 6561 6465 1.47 Jul-99 3300 66.7 120 76.1 2.6 5065 4926 2.74 Aug-98 5050 64.9 100 73.1 2 2986 2762 7.52 Jun-99 3212 62 100 70.7 1.6 5144 5034 2.13 3.4 Evaluation of Winter Water Consumption Rates The cooling tower is not presently used in the winter. For power uprate with the current NPDES permit, occasional use of the cooling towers will be required when river flow is low.The winter evaporation was evaluated for the months of November through March using historical river flow data from the years 1991 through 1995. To be considered, at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> when the flow was less than 1500 cfs had to be recorded in a given month. Based upon data supplied by Normandeau, nine months over the 1991 -1995 Winter period met this criterion.
The months and the average flow are given in Table 3.4-1.TABLE 3.4-1 Low River Flow Winter Months Month / Year Average River Flow (cfs)November 1991 1315.48 December 1992 1387.52 February 1993 1411.86 March 1993 1425.96 January 1994 1439.93 February 1994 1443.86 November 1994 1361.37 February 1995 1458.96 December 1995 1355.66 The evaporation for these months was calculated using the simplified method previously described in the Summer evaluation.
Based upon 120% heat rejection, river flow, and a 13 degree increase in river temperature, the amount of evaporation was calculated.
Per Assumption (I), drift of 183 gpm is added to the evaporation.
Monthly averages of data points in Table 3.4-1 were computed and the results are shown on Figures 3.4-1 and 3.4-2 and Tables 3.4-2 and 3.4-3. The evaporation rates shown below are reflective of when the cooling towers are operating in the winter, which is expected to be less than 20% of the winter period.7 Entergy 7 Entergy Extended Power Uprate Cooling Tower Evaporative Loss Study Vermont Yankee Nuclear Power Station Figure 3.4-1 1991 -1995 Average Winter Water Consumption for Low River Flow 0.25% 1460 1440 0.20% 1420 0 LL.1400>.2."0.15~1380.. 0 ,.E 1360 , S0.10%-10 0 1340 U~1320 0.05%1300 0.00% r 1280 November December January February March[1MM 120% Current NPDES -River FlowI Figure 3.4.2 1991 -1995 Average Winter Water Consumption for Low River Flow 1400 -1460 1440 1200 1420 1400 C,= 1380 ~.E 600. 1360 " 1340 4001 1320 200O 1300 0- *1280 November December January February March Month=' 120% Current NPDES -Rivor Flow 8 Entergy Extended Power Uprate Cooling Tower Evaporative Loss Study Vermont Yankee Nuclear Power Station TABLE 3.4-2 1991 -1995 Average Winter Water Consumption for Low River Flow (% River Flow)120% Current River Flow Month NPDES (cfs)November 0.20% 1338 December 0.17% 1372 January 0.10% 1440 February 0.10% 1438 March 0.11% 1426 TABLE 3.4-3 1991 -1995 Average Winter Water Consumption for Low River Flow (gpm)120% Current River Flow NPDES (cfs)November 1227 1338 December 1039 1372 January 653 1440 February 662 1438 March 732 1426 3.5 Minimum River Flow To provide a basis for comparison, the evaporation with the minimum river flow of 1250 cfs and the 7Q10 Indirect Discharge Permit (Reference
- 5) flow of 1524 cfs was calculated for the 100%power level with the current NPDES permit, 120% power with the current NPDES permit, and 120% power with the proposed NPDES permit. The cooling tower drift of 183 gpm was added to determine total water consumption.
The results are shown in Table 3.5-1. The highest monthly average consumption (September) from Tables 3.3-1 and 3.3-2 is repeated in Table 3.5-1 for comparison purposes.TABLE 3.5-1 Average Water Consumption for Minimum River and 7Q10 Indirect Discharge Permit Flow Evaporation and Drift Consumption River 100% Current 120% Current 120% Proposed Flow Flow NPDES NPDES NPDES Condition Sf)l % River % River gpm River gpm Flow gpm Flow Flow Minimum River 1250 6511 1.16 7928 1.41 7384 1.32 River Flow 7Q10 ID Pemi Fo 1524 6320 0.92 7738 1.13 7074 1.03 Permit Flow September Monthly 3536 4919 0.31 6337 0.40 4960 0.31 Average Flow _1 9 Entergy Extended Power Uprate Cooling Tower Evaporative Loss Study'Vermont Yankee Nuclear Power Station 4 CONCLUSION The above evaluation shows that the monthly average evaporation rates and corresponding water consumption rates are small compared to the average river flow. In the limiting case of minimum river flow, as shown in Table 3.5-1, the evaporation and drift consumption is less than 1.5% of the minimum river flow value of 1250 cfs.5 REFERENCES
- 1. VYNPS PEPSE Heat Balance Models: Runl01EVL.mdl Runl02EVL.mdl Runl03EVL.mdl Runl04EVL.mdl Runl05EVL.mdl Runl06EVL.mdl Runl07EVL.mdl Runl08EVL.mdl Runl09EVL.mdl Run11OEVL.mdl Run111EVL.mdl Run 112EVL.mdl 2-5-2003 2-5-2003 2-5-2003 2-5-2003 2-5-2003 2-5-2003 6-2-2003 6-2-2003 6-2-2003 6-2-2003 6-2-2003 6-2-2003 2. Tower Performance, Inc (TPI) Cooling Tower Report, TPI Reference No."Vermont Yankee Cooling Tower Study", dated December 10, 2002.3. River flow and temperature data from Normandeau Associates,"FlowandTemp96-02_new".
TP-1 0202, Excel file 4. National Climatic Data Center (NCDC) Wet Bulb Temperature for Albany, NY 1990-1999.
- 5. Entergy Nuclear Vermont Yankee Indirect Discharge Permit, ID-9-0036-1A, June 10, 2002." 10 Entergy 10 Entergy Extended Power Uprate Cooling Tower Evaporative Loss Study Vermont Yankee Nuclear Power Station Appendix A Supplemental Information A-1 Entergy Extended Power Uprate Cooling Tower Evaporative Loss Study Vermont Yankee Nuclear Power Station Figure A-1 Circulating Water, Condenser, Cooling Tower Network Service Water Return A-2 Entergy A-2 Entergy Extended Power Uprate Cooling Tower Evaporative Loss Study Vermont Yankee Nuclear Power Station Figure A-2 Determination of Flow Rates Winter Flow: The minimum river flow required to accommodate the 120% heat load of 4443 x 106 Btu/hr with the current winter NPDES allowable temperature rise of 13.4"F is calculated using: Q = mCPAT Where: Q = Heat load = 4443 x 106 Btu/hr (Reference 1)m = river mass flow rate (Ibm/hr)Cp = Specific heat of water -1.00 BTU/(Ibm "F)AT = 13.4"F m = Q/(CpAT)m = 4443 x 106 Btu/hr /[(1.00 Btu/(Ibm 'F) x (13.4°F)]m = 3.3157 x 106 Ibm/hr m = 3.3157 x 106 Ibm/hr x (ft 3/62.4 Ibm) x (hr/ 3600 sec)m -1500 cfs Summer Flow: Increasing the current Summer NPDES permit of 2" to 3"F was evaluated to determine the river flow where the heat load on the cooling towers at 120% would be less than the current 100%load. Using the maximum differential heat load rejected from the Condenser between the 100%and 120% power levels and a temperature increase of 1F, the capability of the river to absorb this heat load was evaluated.
Q 1 2 0 = 120% Heat load at 5 in. Hg condenser pressure = 4443 x 106 Btu/hr (Ref. 1)Q1oo =100% Heat load at 1 in. Hg condenser pressure = 3584 x 106 Btu/hr (Ref. 1)Q = Q120 -Q100= (4443 x 106) -(3584 x 106) = 859 x 106 Btu/hr AT = 3 0 F -2F= 1OF Cp = Specific heat of water -1.00 Btu/(Ibm "F)m = Q/(CpAT)m = 859 x 106 Btu/hr/[(1.00 Btu/(Ibm "F) x (I"F)]m = 859 x 106 Ibm/hr m = 859 x 106 Ibm/hr x (ft 3/62.4 Ibm) x (hr/ 3600 sec)m -3800 cfs A-3 Entergy A-3 Entergy