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| {{#Wiki_filter:;ý: ý,! r, Entergy Nuclear South Entergy Operations, Ina 17265 River Road Killona, LA 70057-3093 Tel 504-739-6660 Fax 504-739-6678 i kowalehenterav.coM Joseph A. Kowalewski W3F1-2011-0008 Vice President, Operations Waterford 3 January 19, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 | | {{#Wiki_filter:;ý: ý,! r, Entergy Nuclear South Entergy Operations, Ina 17265 River Road Killona, LA 70057-3093 Tel 504-739-6660 Fax 504-739-6678 ikowalehenterav.coM Joseph A. Kowalewski W3F1-2011-0008 Vice President, Operations Waterford 3 January 19, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38 | | Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38 |
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| ==REFERENCES:== | | ==REFERENCES:== |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
| Pursuant to 10 CFR 50.90, Entergy Operations, Inc. (Entergy) submitted a license amendment | | |
| [Reference 1] to the Waterford Steam Electric Station, Unit 3 (Waterford 3)Technical Specifications (TS) to modify TS 3/4.9.4, "Containment Building Penetrations." The NRC identified during the review that Entergy had requested the NRC to review and approve a change to TS Index page IX to show that TS 3/4.9.9 "Containment Purge Isolation System" had been deleted. The TS Index had been previously moved to the licensee control under TS Amendment 200 [Reference 2] and does not require NRC review and approval.The TS Index change included in reference 1 is for information only and will be controlled via the Waterford 3 10CFR50.59 program. The NRC is not requested to approve this TS Index change.The letter contains no new commitments. | | Pursuant to 10 CFR 50.90, Entergy Operations, Inc. (Entergy) submitted a license amendment [Reference 1] to the Waterford Steam Electric Station, Unit 3 (Waterford 3) |
| If you have any questions or require additional information, please contact William J. Steelman at 504-739-6685. | | Technical Specifications (TS) to modify TS 3/4.9.4, "Containment Building Penetrations." |
| Sincere S B | | The NRC identified during the review that Entergy had requested the NRC to review and approve a change to TS Index page IX to show that TS 3/4.9.9 "Containment Purge Isolation System" had been deleted. The TS Index had been previously moved to the licensee control under TS Amendment 200 [Reference 2] and does not require NRC review and approval. |
| | The TS Index change included in reference 1 is for information only and will be controlled via the Waterford 3 10CFR50.59 program. The NRC is not requested to approve this TS Index change. |
| | The letter contains no new commitments. If you have any questions or require additional information, please contact William J. Steelman at 504-739-6685. |
| | Sincere SB |
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| ==Attachment:== | | ==Attachment:== |
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| | W3F1-2011-0008 Page 2 cc: Mr. Elmo E. Collins, Jr. |
| W3F1-2011-0008 Page 2 cc: Mr. Elmo E. Collins, Jr.Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Waterford Steam Electric Station, Unit 3 P.O. Box 822 Killona, LA 70066-0751 U.S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam MS 0-07 D1 Washington, DC 20555-0001}} | | Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Waterford Steam Electric Station, Unit 3 P.O. Box 822 Killona, LA 70066-0751 U.S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam MS 0-07 D1 Washington, DC 20555-0001}} |
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MONTHYEARML1009707752010-04-0707 April 2010 Acceptance Review E-mail, License Amendment Request, Modify Technical Specification 3/4.9.4, Containment Building Penetrations, to Allow Alternative Means of Penetration Closure During Refueling Operations Project stage: Acceptance Review ML1009707482010-04-0707 April 2010 Acceptance Review E-mail, License Amendment Request, Delete Operating License Condition 2.C.14, Fuel Movement in the Fuel Handling Building Project stage: Acceptance Review ML1029902562010-10-26026 October 2010 Request for Additional Information Email, License Amendment Request, Modify TS 3/4.9.4, Containment Building Penetrations, to Allow Alternative Means of Penetration Closure During Refueling Operations Project stage: RAI W3F1-2011-0008, Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations2011-01-19019 January 2011 Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations Project stage: Other ML1101400262011-02-23023 February 2011 Issuance of Amendment No. 231, Modify Technical Specification 3/4.9.4, Containment Building Penetrations, to Allow Alternative Means of Penetration Closure During Refueling Operations Project stage: Approval 2010-04-07
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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] |
Text
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- ý,! r, Entergy Nuclear South Entergy Operations, Ina 17265 River Road Killona, LA 70057-3093 Tel 504-739-6660 Fax 504-739-6678 ikowalehenterav.coM Joseph A. Kowalewski W3F1-2011-0008 Vice President, Operations Waterford 3 January 19, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38
REFERENCES:
- 1. W3F1-2010-0010, Technical Specification Change Regarding Containment Building Penetrations During Refueling Operations, February 22, 2010 [ADAMS Accession No. ML100550136].
- 2. NRC Letter, ISSUANCE OF AMENDMENT RE: MODIFICATION OF TECHNICAL SPECIFICATION (TS) 5.3.1, FUEL ASSEMBLIES, TS 5.6.1, CRITICALITY, TS 6 9.1.11.1, CORE OPERATING LIMITS REPORTS, AND DELETION OF TS INDEX, May 9, 2005 [ADAMS Accession No. ML051290368]..
Dear Sir or Madam:
Pursuant to 10 CFR 50.90, Entergy Operations, Inc. (Entergy) submitted a license amendment [Reference 1] to the Waterford Steam Electric Station, Unit 3 (Waterford 3)
Technical Specifications (TS) to modify TS 3/4.9.4, "Containment Building Penetrations."
The NRC identified during the review that Entergy had requested the NRC to review and approve a change to TS Index page IX to show that TS 3/4.9.9 "Containment Purge Isolation System" had been deleted. The TS Index had been previously moved to the licensee control under TS Amendment 200 [Reference 2] and does not require NRC review and approval.
The TS Index change included in reference 1 is for information only and will be controlled via the Waterford 3 10CFR50.59 program. The NRC is not requested to approve this TS Index change.
The letter contains no new commitments. If you have any questions or require additional information, please contact William J. Steelman at 504-739-6685.
Sincere SB
Attachment:
None 0c)
W3F1-2011-0008 Page 2 cc: Mr. Elmo E. Collins, Jr.
Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Waterford Steam Electric Station, Unit 3 P.O. Box 822 Killona, LA 70066-0751 U.S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam MS 0-07 D1 Washington, DC 20555-0001