|
---|
Category:Letter type:W
MONTHYEARW3F1-2023-0056, Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242023-12-19019 December 2023 Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2023-0055, Reply to a Notice of Violation2023-12-14014 December 2023 Reply to a Notice of Violation W3F1-2023-0052, Core Operating Limits Report (COLR) - Cycle 26, Revision O2023-11-0707 November 2023 Core Operating Limits Report (COLR) - Cycle 26, Revision O W3F1-2023-0049, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal2023-09-28028 September 2023 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal W3F1-2023-0048, Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-09-25025 September 2023 Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program W3F1-2023-0036, Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-05-0404 May 2023 Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0032, Annual Radioactive Effluent Release Report (ARERR) 20222023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) 2022 W3F1-2023-0033, Submittal of Annual Radiological Environmental Operating Report - 20222023-04-27027 April 2023 Submittal of Annual Radiological Environmental Operating Report - 2022 W3F1-2023-0025, Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.22062023-04-11011 April 2023 Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.2206 W3F1-2023-0018, Updated Final Supplemental Response to NRC Generic Letter 2004-022023-03-30030 March 2023 Updated Final Supplemental Response to NRC Generic Letter 2004-02 W3F1-2023-0022, Registration of Dry Fuel Storage Cask Use2023-03-22022 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0021, Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days2023-03-17017 March 2023 Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0016, Registration of Dry Fuel Storage Cask Use2023-03-0303 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0014, Reply to a Notice of Violation; EA-22-1192023-02-20020 February 2023 Reply to a Notice of Violation; EA-22-119 W3F1-2023-0013, Notification of Readiness for Supplemental Inspection2023-02-15015 February 2023 Notification of Readiness for Supplemental Inspection W3F1-2023-0007, Registration of Dry Fuel Storage Cask Use2023-02-0606 February 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0010, Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days2023-01-25025 January 2023 Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0002, SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days2023-01-0505 January 2023 SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days W3F1-2022-0067, Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-022022-12-20020 December 2022 Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-02 W3F1-2022-0054, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability2022-11-0101 November 2022 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability W3F1-2022-0063, Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 372022-10-27027 October 2022 Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 37 W3F1-2022-0059, Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-5052022-10-13013 October 2022 Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-505 W3F1-2022-0058, Reply to a Notice of Violation; EA-22-0332022-10-12012 October 2022 Reply to a Notice of Violation; EA-22-033 W3F1-2022-0049, Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-5052022-08-19019 August 2022 Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 W3F1-2022-0037, Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242022-08-0808 August 2022 Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2022-0044, SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-07-0606 July 2022 SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0042, SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-06-27027 June 2022 SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0015, Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf.2022-05-16016 May 2022 Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf. W3F1-2022-0026, Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 20222022-04-28028 April 2022 Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 2022 W3F1-2022-0028, Annual Radiological Environmental Operating Report - 20212022-04-26026 April 2022 Annual Radiological Environmental Operating Report - 2021 W3F1-2022-0029, Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.22062022-04-26026 April 2022 Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.2206 W3F1-2022-0009, Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2022-04-25025 April 2022 Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors W3F1-2022-0031, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-2842022-04-25025 April 2022 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-284 W3F1-2022-0020, Review of Preliminary Accident Sequence Precursor Report2022-04-11011 April 2022 Review of Preliminary Accident Sequence Precursor Report W3F1-2022-0017, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20212022-04-0707 April 2022 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2021 W3F1-2022-0019, WAT-2022-02 Post Exam Analysis2022-03-0909 March 2022 WAT-2022-02 Post Exam Analysis W3F1-2022-0011, Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-02-0808 February 2022 Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0008, SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days2022-02-0101 February 2022 SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days W3F1-2021-0074, Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-022021-12-16016 December 2021 Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-02 W3F1-2021-0064, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 2842021-11-30030 November 2021 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 W3F1-2021-0061, Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-10-14014 October 2021 Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0063, Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery2021-10-12012 October 2021 Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt W3F1-2021-0060, Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-09-30030 September 2021 Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0039, Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years2021-08-25025 August 2021 Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years W3F1-2021-0055, Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual2021-08-20020 August 2021 Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual W3F1-2021-0057, (Waterford 3) - Emergency Plan Revision 0522021-08-18018 August 2021 (Waterford 3) - Emergency Plan Revision 052 W3F1-2021-0054, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 20202021-07-29029 July 2021 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 2020 W3F1-2021-0051, Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator2021-07-19019 July 2021 Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator 2023-09-28
[Table view] Category:Technical Specifications
MONTHYEARML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22075A1022022-04-29029 April 2022 Issuance of Amendment No. 264 to Relocate Chemical Detection System Technical Specifications to Technical Requirements Manual ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement ML21148A0522021-06-0808 June 2021 Correction to License Amendment 214 Request to Support Next Generation Fuel; Review and Approval of Revised ECCS Performance Analysis; and Review and Approval of Supplement to the ECCS Performance Analysis ML21116A1432021-04-26026 April 2021 (Waterford 3) - Revision to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual ML20148M1062020-06-22022 June 2020 Corrections to Technical Specifications Issued in Amendments Nos. 102 and 225 and with the Renewed License ML20113E8362020-04-23023 April 2020 Summary of March 19, 2020, Category 1 Public Meeting with Entergy Operations Inc. a Planned LAR to Install Digital Systems in Accordance with Di&C ISG-06 Revision 2, Licensing Processes at Waterford Steam Electric Station ML19175A0422019-09-11011 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 ML19022A3372019-02-13013 February 2019 Issuance of Amendment No. 253 to Revise Section 15.4.3.1 of the Updated Final Safety Analysis Report to Account for Fuel Misload ML17192A0072017-07-27027 July 2017 Issuance of Amendment No. 250 Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3 ML16077A2702016-05-10010 May 2016 Issuance of Amendment No. 247 Regarding Cyber Security Plan Milestone 8 Full Implementation Schedule W3F1-2016-0010, Responses to Request for Additional Information Regarding the Risk-Informed Surveillance Requirements License Amendment Request (LAR)2016-03-0303 March 2016 Responses to Request for Additional Information Regarding the Risk-Informed Surveillance Requirements License Amendment Request (LAR) ML15289A1432015-11-13013 November 2015 Redacted - Issuance of Amendment No. 246 Changes to Technical Specification 3.1.3.4 Regarding Control Element Assembly Drop Times ML15244B3862015-09-0303 September 2015 Correction to Issuance of Amendment Extension of the Integrated Leak Rate Testing to 15 Years ML15139A4832015-08-31031 August 2015 Issuance of Amendment No. 245 Change to Updated Final Safety Analysis Report Clarifying Pressurizer Heaters Function for Natural Circulation at the Onset of a Loss of Offsite Power ML15217A1432015-08-24024 August 2015 Issuance of Amendment No. 244 Extension of the Integrated Leak Rate Testing to 15 Years ML15138A4402015-08-14014 August 2015 Orders Approving Transfer of Facility Operating Licenses and Indirect Transfer, Draft Conforming Amendment, and Safety Evaluation W3F1-2015-0061, Provides Supplement to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.42015-08-14014 August 2015 Provides Supplement to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.4 ML15174A2272015-07-29029 July 2015 Issuance of Amendment of Technical Specifications s 3.9.6 and 3.9.7 to the Technical Requirements Manual ML14321A7132014-12-10010 December 2014 Issuance of Amendment No. 241, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date W3F1-2014-0052, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2014-08-28028 August 2014 License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications W3F1-2012-0084, Technical Specification Change for Dry Cooling Tower Fans Out of Service for Ultimate Heat Sink2012-10-0808 October 2012 Technical Specification Change for Dry Cooling Tower Fans Out of Service for Ultimate Heat Sink W3F1-2012-0028, Supplement 2 of License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train2012-05-22022 May 2012 Supplement 2 of License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train W3F1-2011-0067, License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train.2011-10-13013 October 2011 License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train. ML1125103192011-09-20020 September 2011 Correction of an Error in Amendment No. 226, Administrative Changes to Technical Specifications 6.9.1.11 and 6.9.1.11.1 Relating to Core Operating Limits Report ML1109501232011-04-0404 April 2011 Attachment 2 to W3F1-2011-0021, Proposed Operating License Change (Mark-up) and Attachment 3, Revised Operating License Page ML1021001582010-09-13013 September 2010 Issuance of Amendment No. 228, Modify Technical Specification Tables 2.2-1 and 3.3-1 to Clarify Notes and Actions ML1021504662010-09-13013 September 2010 Issuance of Amendment No. 227, Modify Technical Specification 3/4.9.7, Crane Travel - Fuel Handling Building to Permit Certain Operations Needed for Dry Cask Storage of Spent Nuclear Fuel W3F1-2010-0065, Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition2010-08-12012 August 2010 Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition W3F1-2010-0047, License Amendment Request for Proposed Change to Technical Specification 3.7.1.2, Emergency Feedwater System.2010-07-20020 July 2010 License Amendment Request for Proposed Change to Technical Specification 3.7.1.2, Emergency Feedwater System. 2CAN051001, Response to Request for Additional Information Associated with Core Operating Limits Report References2010-05-17017 May 2010 Response to Request for Additional Information Associated with Core Operating Limits Report References ML1011100352010-04-22022 April 2010 Correction to Technical Specification Page 3/4 3-10 Issued with Amendment No. 225 Technical Specification Change to Relocate Steam Generator Level - High Trip Function W3F1-2010-0011, License Amendment Request, Technical Specification Change Regarding Steam Generator Program2010-02-22022 February 2010 License Amendment Request, Technical Specification Change Regarding Steam Generator Program ML1005504632010-02-22022 February 2010 Request for Amendment to Technical Specification Table 3.4-1 Isolation Valve Addition W3F1-2009-0045, License Amendment Request to Modify Technical Specification Information for Table 2.2-1 and Table 3.3-12009-10-22022 October 2009 License Amendment Request to Modify Technical Specification Information for Table 2.2-1 and Table 3.3-1 W3F1-2009-0021, License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit2009-06-0303 June 2009 License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit W3F1-2008-0051, Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 32009-01-0808 January 2009 Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 3 ML0819904722008-07-30030 July 2008 License and Technical Specification Pages, Issuance of Amendment No. 216, Modify Diesel Generator Fuel Oil Testing Surveillance Requirements ML0812700362008-05-0909 May 2008 Tech Spec Page for Correction to Amendment 214 Request to Support Next Generation Fuel; Review & Approval of Revised ECCS Performance Analysis; & Review & Approval of Supplement to ECCS Performance Analysis ML0803800062008-04-16016 April 2008 License Page 4 and Technical Specification Page 5-5, Issuance of Amendment No. 215 Use of Optimized ZIRLO-TM Fuel Rod Cladding ML0808800152008-04-15015 April 2008 Tech Spec Pages for Amendment 214, Request to Support Next Generation Fuel; Review and Approval of ECCS Performance Analysis; and Review and Approval of Supplement to ECCS Performance Analysis ML0804401272008-02-12012 February 2008 2/12/2008 E-mail from Licensee Enclosing Markup of Technical Specification Page 5-5, Supplement to 4/24/2007 License Amendment Request Use of Optimized ZIRLO-TM Fuel Rod Cladding W3F1-2008-0001, License Amendment Request NPF-38-275, Containment Isolation Valves.2008-01-0202 January 2008 License Amendment Request NPF-38-275, Containment Isolation Valves. W3F1-2007-0033, License Amendment Request NPF-38-273 to Modify Requirements Regarding Control Room Envelope Habitability2007-08-16016 August 2007 License Amendment Request NPF-38-273 to Modify Requirements Regarding Control Room Envelope Habitability ML0711603482007-04-24024 April 2007 License Amendment Request to Allow the Use of Optimized Zirlo Fuel Rod Cladding ML0706803372007-03-19019 March 2007 Tech Spec Pages for Amendment 212 Reactor Coolant System Leakage Detection Instrumentation ML0703704312007-02-0606 February 2007 Technical Specifications, Issuance of Amendment No. 211 to Facility Operating License Removal of Vendor Recommended Diesel Generator Surveillance Requirement 2023-07-26
[Table view] |
Text
Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504-739-6660 Fax 504-739-6698 djacob2@entergy.com Donna Jacobs Vice President, Operations Waterford 3 W3F1-2012-0084 October 8, 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
License Amendment Request Technical Specification Change for Dry Cooling Tower Fans Out of Service for Ultimate Heat Sink Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38
Dear Sir or Madam:
Pursuant to 10 CFR 50.90, Entergy Operations, Inc. (Entergy) hereby requests a license amendment to the Waterford Steam Electric Station, Unit 3 (Waterford 3) Technical Specifications (TS). The proposed amendment will modify TS 3/4.7.4, "Ultimate Heat Sink."
Entergy will be replacing the two Waterford 3 steam generators (SGs) and the reactor vessel closure head (RVCH) during the 18th refueling outage (RF18). In order to create a construction opening for replacement of the steam generators and RVCH, the construction of a temporary work platform (TWP) was necessary above Train B of the Waterford 3 dry cooling tower (DCT) of the ultimate heat sink (UHS). Due to a small increase in airflow restriction to the Train B DCT while the TWP is installed in Modes 1 thru 4, an administrative control was determined to be appropriate to limit the number of Train B DCT fans that can be out of service to no more than two fans. Waterford TS Table 3.7-3 allows having up to three DCT fans to be out of service in plant Modes 1 through 4 with dry bulb temperatures < 91°F. This amendment request proposes to modify the requirements for the number of DCT fans needed for Operability of the ultimate heat sink (UHS) contained in Table 3.7-3 of Waterford 3 TS 3/4.7.4.
Entergy has a pending license amendment request (TAC No. ME7342) under NRC review that also revises information contained in TS Table 3.7-3. Proposed changes in that amendment request are not reflected in this request.
This request is a one time TS change in support of RF18 which is scheduled to commence on October 17, 2012. This technical specification change will only be applicable for the period of time while the TWP is installed until Mode 5 is entered at the beginning of RF18.
A description of the TS proposed change is provided in Attachment 1. A markup of the affected TS page is contained in Attachment 2.
W3F1 -2012-0084 Page 2 The proposed change has been evaluated in accordance with 10 CFR 50.91 (a)(1) using criteria in 10 CFR 50.92(c) and it has been determined that the changes involve no significant hazards consideration.
The proposed change involves no new commitments.
This amendment request is neither emergency nor exigent, but your prompt review is requested. Please contact Michael Mason at 504-739-6673 if there are any questions regarding this amendment request.
I declare under penalty of perjury that the foregoing is true and correct. Executed on October 8, 2012.
Sincerely, Attaclfments:
- 1. Analysis of Proposed Technical Specification Change
- 2. Proposed Technical Specification Changes (mark-up)
W3F1 -2012-0084 Page 3 cc: Mr. Elmo E. Collins, Jr. RidsRgn4MailCenter@nrc.gov Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 E. Lamar Blvd.
Arlington, TX 76011-4511 NRC Senior Resident Inspector Marlone. Davis@nrc.gov Waterford Steam Electric Station Unit 3 Dean.Overland@nrc.gov P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Kaly.Kalyanam@nrc.gov Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001 Louisiana Department of Environmental Quality Ji.Wiley@LA.gov Office of Environmental Compliance Surveillance Division P.O. Box 4312 Baton Rouge, LA 70821-4312
Attachment I to W3F1-2012-0084 Analysis of Proposed Technical Specification Change to W3F1 -2012-0084 Page 1 of 6 Analysis of Proposed Waterford 3 Technical Specification Change for Restriction on Train B Dry Cooling Tower Fans Out of Service
1.0 DESCRIPTION
This letter is a request to amend Operating License NPF-38 for the Waterford Steam Electric Station, Unit 3 (Waterford 3). Entergy will be replacing the two Waterford 3 steam generators (SGs) and reactor vessel closure head (RVCH) during the 1 8 th refueling outage (RF18) which is scheduled to commence on October 17, 2012. In order to create a construction opening for replacement of the SGs and RVCH, the construction of a temporary work platform (TWP) was necessary above the Waterford 3 Train B dry cooling towers (DCT) of the ultimate heat sink (UHS). Due to a small increase in airflow restriction to the Train B DCT while the TWP is installed in plant Modes 1 thru 4, an administrative control was determined to be appropriate to limit the number of DCT fans that can be out of service (OOS). As a result, a change to Technical Specification 3/4.7.4, "Ultimate Heat Sink," is being requested.
2.0 PROPOSED CHANGE
A one-time technical specification change is being requested to.
Revise Waterford 3 TS Table 3.7-3 to add a note (2) to the Dry Cooling Tower Fan Requirements for the < 91OF dry bulb temperature. Note (2) states: "While the Temporary Work Platform is installed, 13 fans shall be OPERABLE for Train B of the DCT."
This technical specification change will only be applicable for the amount of time that is required for the plant to enter Mode 5 at the beginning of RF18.
Due to the limited time that this specification will be applicable, there are no TS Bases pages being proposed.
3.0 BACKGROUND
Waterford 3 is scheduled to commence RF18 on October 17, 2012 where the original SGs and RVCH will be replaced. The Waterford containment vessel contains a preexisting construction hatch barrel that will be removed for the replacement of the SGs and reactor vessel closure head. A Shield Building construction opening that coincides with the construction hatch barrel is required to access containment for the replacement activities. The construction opening is located above the Train B DCT of the UHS. The DCT To provide support for the construction equipment necessary for the removal and reinstallation of the Shield Building construction opening, a TWP is being erected above the air exhaust side of the two southernmost cells of Train B DCT. The TWP is being installed as a maintenance support structure under a 1 OCFR50.65(a)(4) risk assessment.
The TWP is designed to either withstand Waterford 3 design basis environmental loads or to not result in damage to the Train B DCT.
to W3F1 -2012-0084 Page 2 of 6 The TWP decking results in a small airflow restriction to the Train B DCT discharge. This restriction had to be considered for its impact on the UHS and the Technical Specifications under Specification 3/4.7.4. A 10CFR50.59 Evaluation was prepared by Waterford 3 in 2010 which determined that the installation of the TWP over the Train B DCT continued to satisfy the design basis of the UHS and assured TS Operability with no impact on DCT fan operability. The conclusions reached in this review are applicable for the current licensing and design basis assumptions. However, subsequent to that review, a Condition Report (CR-WF3-2012-02332) was written that identified a condition associated with the Waterford 3 UHS where the potential exists for additional discharge air recirculation beyond that assumed in the Updated Final Safety Analysis Report (FSAR). The condition report assumes a dry bulb temperature penalty of 9.5 0 F for discharge air recirculation which is greater than that reported in the Waterford 3 Updated FSAR of 1.91F. This increase in recirculation penalty impacts the heat dissipation capability of the DCTs. This has placed the UHS in an Operable, but Degraded or Nonconforming condition under 10CFR50, Appendix B, Criterion XVI. Under this condition, the placement of the TWP over the Train B DCT required additional analysis to show that there was no further reduction in performance margins while in this degraded/nonconforming condition.
Calculation 2012-07299 performed by Sargent & Lundy provided a comparative analysis of the Train B DCT performance with the presence of the TWP and designed airflow improvement features. The results of this analysis showed that Train B DCT performance was improved with the installation of the TWP and airflow enhancement features with all 15 DCT fans in service.
Waterford 3 TS Table 3.7-3 under TS 3/4.7.4 allows from 1 to 3 DCT fans to be OOS based on the dry bulb ambient temperature conditions. Each DCT consists of five cells having three fans in each cell. A separate evaluation was performed based upon the Sargent & Lundy calculation to determine if the comparative analysis bounds the additional fan operability allowances of TS Table 3.7-3. The results indicate that assumptions for Table 3.7-3 are bounding except when all three fans in the southernmost cell of DCT Train B would be out of service. This cell provides the greatest cooling efficiency since it was determined that there was no exhaust air recirculation for this cell with the TWP installed (including airflow enhancement features). Therefore, this DCT cell would require additional operational restriction if all three of its fans became OOS.
Waterford is conservatively restricting any combination of any three Train B DCT fans that are OOS. In accordance with the guidance of NRC Inspection Manual Part 9900, Operability Determinations, a control room administrative control was established to declare Train B DCT inoperable if more than any two fans are out of service while the TWP is installed during plant Modes 1 through 4. The TWP was recently installed along with the airflow enhancement features.
Since the analyses performed for TWP installation was to address a degraded/
nonconforming condition under a maintenance rule configuration, Entergy believed that the administrative control to restrict having three Train B DCT fans being OOS did not result in an "improper or inadequate TS" in accordance with NRC Administrative Letter 98-10. The comparative analysis and supplemental evaluation were performed to show that further Train B DCT degradation would not occur while the UHS is in its current Operable, but Degraded/ Nonconforming condition with the TWP installed. These evaluations do not represent new or revised analyses to the analysis of record for the to W3F1 -2012-0084 Page 3 of 6 UHS in the Updated FSAR or the TS Bases. Therefore, in lieu of a specific analysis for compliance with Waterford's licensing basis, it was concluded that the administrative controls provided a conservative action and not a direct relationship to the TS allowances under TS Table 3.7-3. In further discussion with the NRC, it was determined that the administrative control could be interpreted as a nonconservative TS.
4.0 TECHNICAL ANALYSIS
As discussed in Section 9.2.5 of the Waterford 3 Updated FSAR the UHS must provide sufficient capacity to dissipate heat from the component cooling water system (CCWS) and auxiliary component cooling water system (ACCWS) during normal operation and after a design basis accident. This assumes a single active failure coincident with a loss of offsite power and the historically worst combination meteorological condition of 102 0 F dry bulb temperature and associated 78 0 F wet bulb temperature.
The Limiting Condition for Operation (LCO) for Waterford 3 TS 3.7.4 establishes the requirements to have two independent trains of UHS cooling towers in Modes 1 through 4 to be Operable. Operability consists of a train of both DCTs and wet cooling towers (WCT). LCO 3.7.4.c establishes the number of fans required to be Operable by TS Table 3.7-3. There are 15 fans associated with each DCT train.
TS Table 3.7-3 allows a reduction in fans to be OOS based on ambient wet and/or dry bulb temperatures for the associated DCTs or WCTs to protect the design basis of the UHS. For the DCTs, the following fan requirements have been established:
Ambient Condition Dry Bulb > 98 0 F < 981F Dry Bulb > 91°F < 91°F Dry Bulb Fan Requirements 15 14 12 With any of the above required UHS fan[s] inoperable comply with Action [3.7.4] d.
TS 3.7.4 Action "d" states that with any UHS fan inoperable determine the outside ambient temperature at least once every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and verify that the minimum fan requirements of Table 3.7-3 are satisfied. When the dry bulb temperature is < 910 F, the current TS fan requirements would allow up to three fans to be OOS. However, while the TWP is installed, Train B DCT will be restricted to have no more than two fans OOS. If not met, the train will be declared inoperable then the applicable shutdown LCO will be entered.
Operation with two Train B DCTs fans OOS will continue to meet its design heat load removal requirements with the installed TWP configuration. With the understanding that the comparative and supplemental analyses were performed to address the currently degraded or nonconforming condition, the control room administrative control is more conservative than those of Table 3.7-3 in TS 3.7.4. Entergy concludes that this action is appropriate to assure that Waterford 3 will not be operated outside these analyses for the duration that the TWP maintenance related configuration is installed under 10CFR50.65(a)(4) until Mode 5 is reached at the beginning of RF18.
to W3F1-2012-0084 Page 4 of 6
5.0 REGULATORY ANALYSIS
5.1 Applicable Regiulatory Requirements/Criteria Entergy Operations, Inc. (Entergy) proposes to modify the requirements for the number of Train B dry cooling tower (DCT) fans needed for Operability of the ultimate heat sink (UHS) contained in Waterford Steam Electric Station, Unit 3 (Waterford 3) Technical Specification (TS) 3/4.7.4, "Ultimate Heat Sink." TS 3.7.4 requires that two UHS trains to be Operable which consists of a combination of dry and wet cooling towers. TS Table 3.7-3 provides a limitation on the number of fans that can be allowed to be out of service based upon ambient dry and wet bulb temperatures. In order to create a construction opening for replacement of the steam generators and reactor vessel closure head, the construction of a temporary work platform (TWP) is necessary above Train B of the Waterford 3 UHS DCTs. The TWP creates a small increase in airflow restriction for Train B DCT while the TWP is installed in plant Modes 1 through 4. The small airflow restriction by the TWP installation on the DCT is offset by the design airflow improvement features.
However, an administrative control was determined to be appropriate to restrict no more than two Train B DCT fans out of service based upon a supplemental analysis. As a result, a change to TS Table 3.7-3 contained in TS 3/4.7.4 is requested during the time period that the TWP will be installed until entry into Mode 5 at the beginning of refueling outage 18.
In conclusion, Entergy has determined that the proposed changes do not require any exemptions or relief from regulatory requirements and does not adversely affect systems, structures, and components described in the Waterford 3 Updated Final Safety Analysis Report (FSAR).
5.2 No Sigqnificant Hazards Consideration Entergy Operations, Inc. has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The design basis of the UHS as discussed in Waterford 3 Updated FSAR is to assure that sufficient capacity exists in the wet and dry cooling towers to dissipate heat load from the component cooling water system (CCWS) and auxiliary component cooling water system (ACCWS) during normal operation and after a design basis accident.
The action to limit the number of DCT fans to be OOS is a conservative measure that further assures the Operability of the UHS under normal and design basis accidents.
The probability of an accident is not increased since the UHS will continue to be Operable under assumed design basis conditions. The consequences of an accident are still mitigated within design and accident basis assumptions since sufficient cooling will continue to be provided to remove the worst case assumed CCWS/ACCWS heat loads. Additionally, this change does not affect any accident initiators and thus does not increase the probability of an accident.
to W3F1 -2012-0084 Page 5 of 6 Therefore, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
There are no changes to plant equipment or additional heat loads being applied to the CCWS/ACCWS and there is no change to the requirements to remove heat from the UHS. The manner in which the UHS functions is also not being changed by the proposed TS revision. The accidents assumed in the Updated FSAR are not changed and there are no new accidents created by restricting the number of fans allowed to be out of service for TS Table 3.7-3. There are also no new potential equipment malfunctions that are created from the proposed change.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No.
The margins of safety for the UHS are provided in Waterford 3 design basis calculations that support assuring that sufficient heat is removed from the CCW/ACCW systems by the UHS. The supplemental analysis performed which conservatively restricts having no more than two Train B DCT fans out of service is based upon a comparative analysis for addressing a current degraded/nonconforming condition under 10CFR50, Appendix B, Criterion XVI. The results of these analyses for restricting no more than two Train B DCT fans out of service while the TWP is installed continues to protect the margins of safety established by the UHS design basis.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, Entergy concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
5.3 Environmental Considerations The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
to W3F1-2012-0084 Page 6 of 6 6.0 PRECEDENCE Administrative actions to assure plant safety beyond that required by the technical specifications are addressed in NRC Administrative Letter 98-10. Even though this guidance results in license amendment applications that are either permanently or temporarily changed, Entergy is not citing any specific licensee application that is of a similar nature.
7.0 REFERENCES
- 1. Calculation 2012-07299, "Evaluation of Train B Dry Cooling Air Recirculation with Temporary Work Platform", Sargent & Lundy.
- 2. Waterford 3 Engineering Change Notice 38086 to Engineering Change 8427, "Containment Wall Opening for the SG/RVCH Replacement", Attachment 9, "Waterford 3 Dry Cooling Tower 'B' Train Fans Out of Service Examination"
- 3. NRC Inspection Manual Part 9900, "Operability Determinations & Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality."
- 4. NRC Administrative Letter 98-10, Dispositioning of Technical Specifications that are Insufficient to Assure Plant Safety, December 29, 1998.
Attachment 2 to W3F1 -2012-0084 Proposed Technical Specification Changes (mark-up)
ULTIMATE HEAT SINK MINIMUM FAN REQUIREMENTS PER TRAIN AMBIENT CONDITION DRY BULB Z 980 F < 98°F DRY BULB )_91OF < 91OF DRY BULB I Fan 15 14" Requirements("
WET COOILING TOWER AMBIENT CONDITION WET BULB Z 75°F < 75°F WET BULB _ 70OF WET BULB < 70°F Fan e 7" 4" Requirementst)
(1) With any of the above rouired UHS fan ino7emble conit!v with ACTION d.
- WMh a tornado watch IneffecL all 9 DCT fans under the missile protected nortion of the DCT shall be OPERABLE
- With any WCT fan(s) out-of-service In any cel. covers must be in rnace on the out-of-serice fan(s) or the entire cell fI.e- 4 (2) Whilethbe Tempoary Wok- Iffour fansted, 13f shal bueO eRa Be fors Tdoinot have to be IsTed WATERFORD - UNIT 3 314 7-14 AMENDMENT NO. 954M3,1 39 6