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Category:Letter type:RBG
MONTHYEARRBG-48315, Reply to a Notice of Violation, NRC Inspection Report 05000458/2023003 Supplement2024-09-24024 September 2024 Reply to a Notice of Violation, NRC Inspection Report 05000458/2023003 Supplement RBG-48306, Report of Changes and Errors to 10CFR50.462024-09-24024 September 2024 Report of Changes and Errors to 10CFR50.46 RBG-48311, Reply to a Notice of Violation, NRC Inspection Report 05000458/20240022024-08-28028 August 2024 Reply to a Notice of Violation, NRC Inspection Report 05000458/2024002 RBG-48308, Notification of Readiness for Supplemental Inspection2024-07-31031 July 2024 Notification of Readiness for Supplemental Inspection RBG-48276, 2023 Annual Radioactive Effluent Release Report2024-04-23023 April 2024 2023 Annual Radioactive Effluent Release Report RBG-48288, Louisiana Pollutant Discharge Elimination System Permit Renewal2024-04-15015 April 2024 Louisiana Pollutant Discharge Elimination System Permit Renewal RBG-48277, 2023 Annual Radiological Environmental Operating Report2024-04-10010 April 2024 2023 Annual Radiological Environmental Operating Report RBG-48278, 2023 Spent Fuel Storage Radioactive Effluent Release Report2024-02-27027 February 2024 2023 Spent Fuel Storage Radioactive Effluent Release Report RBG-48286, Revision to Owners Activity Report Form (OAR) for Cycle 222024-02-27027 February 2024 Revision to Owners Activity Report Form (OAR) for Cycle 22 RBG-48274, Notification of Readiness for Supplemental Inspection2024-02-0505 February 2024 Notification of Readiness for Supplemental Inspection RBG-48271, Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk2024-01-12012 January 2024 Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk RBG-48267, Reply to a Notice of Violation, NRC Inspection Report 05000458/20230032023-12-0707 December 2023 Reply to a Notice of Violation, NRC Inspection Report 05000458/2023003 RBG-48264, Core Operating Limits Report (COLR) - Cycle 23, Revision 12023-11-0606 November 2023 Core Operating Limits Report (COLR) - Cycle 23, Revision 1 RBG-48260, Notification of Readiness for Supplemental Inspection2023-10-12012 October 2023 Notification of Readiness for Supplemental Inspection RBG-48258, Notification of Readiness for Supplemental Inspection2023-10-0505 October 2023 Notification of Readiness for Supplemental Inspection RBG-48259, Revision to Reply to Notice of Violation; EA-23-0552023-10-0303 October 2023 Revision to Reply to Notice of Violation; EA-23-055 RBG-48254, Report of Changes and Errors to 10CFR50.462023-09-21021 September 2023 Report of Changes and Errors to 10CFR50.46 RBG-48249, Reply to a Notice of Violation, EA-23-0712023-09-14014 September 2023 Reply to a Notice of Violation, EA-23-071 RBG-48253, Submittal of Owner'S Activity Report Form for Cycle 222023-09-12012 September 2023 Submittal of Owner'S Activity Report Form for Cycle 22 RBG-48247, Reply to Notice of Violation; EA-23-0552023-08-21021 August 2023 Reply to Notice of Violation; EA-23-055 RBG-48226, Core Operating Limits Report (COLR) - Cycle 23, Revision 02023-05-31031 May 2023 Core Operating Limits Report (COLR) - Cycle 23, Revision 0 RBG-48237, Response to NRC Integrated Inspection Report 05000458/20230012023-05-25025 May 2023 Response to NRC Integrated Inspection Report 05000458/2023001 RBG-48221, 2022 Annual Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Radiological Environmental Operating Report RBG-48220, Submittal of 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report RBG-48143, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-02-27027 February 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors RBG-48142, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSFT-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-27027 February 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSFT-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RBG-48198, Report of Changes and Errors to 10CFR50.462022-09-22022 September 2022 Report of Changes and Errors to 10CFR50.46 RBG-48187, Notification of Spent Fuel Cask Use2022-08-15015 August 2022 Notification of Spent Fuel Cask Use RBG-48184, Notification of Spent Fuel Cask Use2022-07-18018 July 2022 Notification of Spent Fuel Cask Use RBG-48178, Notification of Spent Fuel Cask Use2022-06-29029 June 2022 Notification of Spent Fuel Cask Use RBG-48166, Supplement to Special Report for Tritium Discovered Onsite2022-05-12012 May 2022 Supplement to Special Report for Tritium Discovered Onsite RBG-48148, 2021 Annual Radiological Environmental Operating Report2022-04-27027 April 2022 2021 Annual Radiological Environmental Operating Report RBG-48149, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022 2021 Annual Radioactive Effluent Release Report RBG-48134, Inservice Testing Program Relief Request VRR-RBS-2021-1 Pressure Isolation Valve Testing Frequency2021-11-29029 November 2021 Inservice Testing Program Relief Request VRR-RBS-2021-1 Pressure Isolation Valve Testing Frequency RBG-48136, Additional Information for the 2020 Annual Radioactive Effluent Release Report2021-11-12012 November 2021 Additional Information for the 2020 Annual Radioactive Effluent Release Report RBG-48137, Additional Information for the 2019 Annual Radioactive Effluent Release Report2021-11-12012 November 2021 Additional Information for the 2019 Annual Radioactive Effluent Release Report RBG-48128, Reply to a Notice of Violation; EA-21-017, 030 and 0502021-10-29029 October 2021 Reply to a Notice of Violation; EA-21-017, 030 and 050 RBG-48129, Payment of a Civil Penalty2021-10-21021 October 2021 Payment of a Civil Penalty RBG-48112, Report of Changes and Errors to 10CFR50.462021-09-16016 September 2021 Report of Changes and Errors to 10CFR50.46 RBG-48110, Core Operating Limits Report (COLR) - Cycle 22, Revision 12021-08-19019 August 2021 Core Operating Limits Report (COLR) - Cycle 22, Revision 1 RBG-48104, Fitness for Duty Blind Quality Assurance Specimen Testing Error2021-06-30030 June 2021 Fitness for Duty Blind Quality Assurance Specimen Testing Error RBG-48099, Submittal of Owner'S Activity Report Form for Cycle 212021-06-16016 June 2021 Submittal of Owner'S Activity Report Form for Cycle 21 RBG-48083, Application to Add License Condition Concerning Receipt, Possession, and Use of Byproduct Materials2021-06-15015 June 2021 Application to Add License Condition Concerning Receipt, Possession, and Use of Byproduct Materials RBG-48093, Corrected 2020 Annual Radiological Environmental Operating Report2021-05-20020 May 2021 Corrected 2020 Annual Radiological Environmental Operating Report RBG-48081, 2020 Annual Radioactive Effluent Release Report2021-04-20020 April 2021 2020 Annual Radioactive Effluent Release Report RBG-48082, 2020 Annual Radiological Environmental Operating Report2021-04-20020 April 2021 2020 Annual Radiological Environmental Operating Report RBG-48078, Core Operating Limits Report (COLR) - Cycle 22, Revision 02021-03-14014 March 2021 Core Operating Limits Report (COLR) - Cycle 22, Revision 0 RBG-48075, Notification of Deviation from BWRVIP Guidelines2021-02-24024 February 2021 Notification of Deviation from BWRVIP Guidelines RBG-48074, Spent Fuel Storage Radioactive Effluent Release Report for 20202021-02-22022 February 2021 Spent Fuel Storage Radioactive Effluent Release Report for 2020 RBG-48061, One-Time Schedular Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency2020-12-0303 December 2020 One-Time Schedular Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency 2024-09-24
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 – Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23159A2302023-06-0808 June 2023 Response to Request for Additional Information Concerning Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2020-00021, Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-0192020-11-0909 November 2020 Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-019 CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary RBG-47919, Response to Request for Additional Information for License Amendment Request, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2018-12-17017 December 2018 Response to Request for Additional Information for License Amendment Request, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) RBG-47906, Response to Request for Additional Information for License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62018-10-18018 October 2018 Response to Request for Additional Information for License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 ML18283A0822018-10-0909 October 2018 Supplemental Information Related to License Renewal Application NRC Request for Additional Information to Clarify Response to RAI 2.3.3.16-1 Set 11 RBG-47903, Response to Request for Additional Information License Amendment Request to Correct a Non-Conservative Technical Specification Figure 3.4,11 -1 Minimum Temperature Required Vs, RCS Pressure by Replacing with 54 Effective Full Power2018-10-0404 October 2018 Response to Request for Additional Information License Amendment Request to Correct a Non-Conservative Technical Specification Figure 3.4,11 -1 Minimum Temperature Required Vs, RCS Pressure by Replacing with 54 Effective Full Power RBG-47895, Supplement to the Response to License Amendment Request (LAR) for Review and Approval of Relocation of the Reactor Core Isolation Cooling (RCIC) Injection Point NRC Request for Additional Information (RAI)2018-08-15015 August 2018 Supplement to the Response to License Amendment Request (LAR) for Review and Approval of Relocation of the Reactor Core Isolation Cooling (RCIC) Injection Point NRC Request for Additional Information (RAI) RBG-47876, Response to License Amendment Request (LAR) for Review and Approval of Relocation of the Reactor Core Isolation Cooling (RCIC) Injection Point NRC Request for Additional Information (RAI)2018-06-21021 June 2018 Response to License Amendment Request (LAR) for Review and Approval of Relocation of the Reactor Core Isolation Cooling (RCIC) Injection Point NRC Request for Additional Information (RAI) ML18143B6862018-05-24024 May 2018 RBS Draft Response (Operating Experience) to Draft RAI 3-0-5 Received 052318 ML18136A7052018-05-16016 May 2018 RBS Draft Response to LRA Review RAI 4.7.3-1a Fluence Effects for Rv Internals ML18136A8212018-05-16016 May 2018 Draft Response to RAI 3.6.2.2.2.2-1a High Voltage Insulators - RBS LRA Review RBG-47867, Response to License Renewal Application NRC Request for Additional Information RAI 3.2.2.2-1a Supplement2018-05-16016 May 2018 Response to License Renewal Application NRC Request for Additional Information RAI 3.2.2.2-1a Supplement RBG-47852, Response to License Renewal Application NRC Request for Additional Information Set 132018-05-10010 May 2018 Response to License Renewal Application NRC Request for Additional Information Set 13 RBG-47860, Response to License Renewal Application NRC Request for Supplemental Information2018-05-10010 May 2018 Response to License Renewal Application NRC Request for Supplemental Information ML18121A2942018-05-0101 May 2018 Draft Response to NRC Request for Additional Information (RAI) 4.6-1a Generated from Staffs Review on the River Bend License Renewal Application RBG-47853, Response to License Renewal Application NRC Request for Additional Information Supplement to B.1.35-12018-04-26026 April 2018 Response to License Renewal Application NRC Request for Additional Information Supplement to B.1.35-1 RBG-47859, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-04-26026 April 2018 Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control ML18115A0612018-04-25025 April 2018 Draft Response on RAI B1.21-1 Flow Accelerated Corrosion ML18115A0722018-04-25025 April 2018 Draft Response on RAI B.1.25-1(Internal Surfaces in Miscellaneous Piping and Ducting Components) RBG-47850, Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement2018-04-0404 April 2018 Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement RBG-47846, Response to License Renewal Application NRC Request for Additional Information (RAI) Set 122018-04-0303 April 2018 Response to License Renewal Application NRC Request for Additional Information (RAI) Set 12 RBG-47851, Response to License Amendment Request (LAR) Technical Specification 3.7.7, Control Building Air Conditioning (Cbac) System NRC Request for Additional Information (RAI)2018-03-28028 March 2018 Response to License Amendment Request (LAR) Technical Specification 3.7.7, Control Building Air Conditioning (Cbac) System NRC Request for Additional Information (RAI) RBG-47849, Response to License Renewal Application NRC Request for Additional Information Set 4 Supplement2018-03-27027 March 2018 Response to License Renewal Application NRC Request for Additional Information Set 4 Supplement RBG-47835, Submittal of Response to License Renewal Application NRC Request for Additional Information Set 102018-03-26026 March 2018 Submittal of Response to License Renewal Application NRC Request for Additional Information Set 10 RBG-47842, Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement2018-03-22022 March 2018 Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement ML18059A8222018-03-0808 March 2018 Summary of Public Telephone Conference Call Held on February 27, 2018 Between the U.S. Nuclear Regulatory Commission and Entergy Regarding Requests for Additional Information Pertaining to the River Bend Station Unit 1 RBG-47819, Response to License Renewal Application NRC Request for Additional Information - Set 7 Supplement to RAI B.1.11-2a2018-02-26026 February 2018 Response to License Renewal Application NRC Request for Additional Information - Set 7 Supplement to RAI B.1.11-2a RBG-47828, Response to License Renewal Application NRC Request for Additional Information (RAI) Set 82018-02-20020 February 2018 Response to License Renewal Application NRC Request for Additional Information (RAI) Set 8 RBG-47818, Response to License Renewal Application NRC Request for Additional Information - Set 72018-02-0707 February 2018 Response to License Renewal Application NRC Request for Additional Information - Set 7 RBG-47812, Response to License Renewal Application (LRA) NRC Request for Additional Information (RAI) Set 42018-01-24024 January 2018 Response to License Renewal Application (LRA) NRC Request for Additional Information (RAI) Set 4 RBG-47822, Response to Request for Additional Information Re License Renewal Application Concerning Severe Accident Mitigation Alternatives2018-01-24024 January 2018 Response to Request for Additional Information Re License Renewal Application Concerning Severe Accident Mitigation Alternatives RBG-47813, Response to License Renewal Application (LRA) NRC Request for Additional Information Set 52018-01-24024 January 2018 Response to License Renewal Application (LRA) NRC Request for Additional Information Set 5 RBG-47807, Response to License Renewal Application NRC Requests for Additional Information Set 32018-01-10010 January 2018 Response to License Renewal Application NRC Requests for Additional Information Set 3 RBG-47805, Response to License Renewal Application NRC Request for Additional Information Set 22017-12-12012 December 2017 Response to License Renewal Application NRC Request for Additional Information Set 2 RBG-47803, Response to License Renewal Application (LRA) NRC Request for Additional Information, Severe Accident Mitigation Alternatives2017-12-0505 December 2017 Response to License Renewal Application (LRA) NRC Request for Additional Information, Severe Accident Mitigation Alternatives ML17353A0492017-12-0505 December 2017 Response to License Renewal Application NRC Request for Additional Information Re Environmental RBG-47709, Response to Request for Additional Information on Nineteenth Fuel Cycle Core Operating Limits Report2016-09-12012 September 2016 Response to Request for Additional Information on Nineteenth Fuel Cycle Core Operating Limits Report RBG-47695, Response to Request to Additional Information Regarding RBS License Amendment Request to Extend Type a and Type C Test Frequencies2016-07-27027 July 2016 Response to Request to Additional Information Regarding RBS License Amendment Request to Extend Type a and Type C Test Frequencies RBG-47675, Response to NRC Request for Additional Information - RBS LAR to Extend Type a and Type C Test Frequencies2016-04-19019 April 2016 Response to NRC Request for Additional Information - RBS LAR to Extend Type a and Type C Test Frequencies ML16071A4412016-03-0707 March 2016 Entergy Fleet Relief Request No. RR-EN-15-1-Proposed Alternative to Use ASME Code Case N-789-1 - E-mail from G.Davant to R.Guzman - Response to Second RAI (MF6340 - MF6349) CNRO-2016-00005, Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM)2016-02-25025 February 2016 Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2016-00002, Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Secti2016-01-29029 January 2016 Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section Xl, RBG-47634, High-frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10CER50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi..2015-12-0808 December 2015 High-frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10CER50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi.. CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 12015-12-0404 December 2015 Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1 RBG-47582, Response to Request for Information - Change to Technical Specification 3.8.1, AC Sources - Operating2015-07-16016 July 2015 Response to Request for Information - Change to Technical Specification 3.8.1, AC Sources - Operating 2024-04-10
[Table view] |
Text
Entergy Operations, Inc.
Entergy River Bend Station 5485 U.S. Highway 61 N St. Franciaville, LA 70775 Tel 225-381-4157 N. Todd Brumfield Director - Regulatory & Performance Improvement RBG-47582 July 16, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Response
3.8.1, "AC to Request Sources for Information
- Operating"
- Change to Technical Specification River Bend Station, Unit 1 Docket No. 50-458 License No. NPF-47 References 1. Entergy letter, Application for Change to Technical Specification 3.8.1, "AC Sources - Operating" dated July 9, 2014 (RBG-47461)
- 2. NRC email, River Bend Station Unit 1 License Amendment Request for Change to Technical Specifications 3.8.1, "AC Sources - Operating" (MF4421) dated January 20, 2015
- 3. Entergy letter, Response to Request for Information - Change to Technical Specification 3.8.1, "AC Sources - Operating" dated May 7, 2015
- 4. NRC email, River Bend Station Unit I License Amendment Request for Change to Technical Specifications 3.8.1, "AC Sources - Operating" (MF4421) dated May 04, 2015
- 5. Entergy letter, Response to Request for Information - Change to Technical Specification 3.8.1, "AC Sources -- Operating" dated June 3, 2015
Dear Sir or Madam:
In Reference 1 Entergy submitted a request for an amendment to the Technical Specifications (TS) for River Bend Station (RBS), Unit 1, modifying the existing Surveillance Requirements (SRs) related to Technical Specification 3.8.1, "AC Sources -
Operating." References 3 and 5, are responses to NRC Staff requested additional information.
During the review an editorial changes to the numbering of the revised TS SRs was identified. The changes are for clarity and have no technical effect. The changes are identified in the attachment.
Aw1
~ff'~
RBG-47582 Page 2 of 3 The changes were discussed with the NRC Project Manager. These changes are in the Attachment.
There are not new commitments in this letter. Please contact Mr. J. A. Clark at (225) 381-4177, if you have any questions.
I declare under penalty of perjury that the foregoing is true and correct. Executed on July 16, 2015.
NTB/JAC/bmb
Attachment:
Revised Surveillance Requirement Numbering cc: Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Blvd.
Arlington, TX 76011-4511 NRC Senior Resident Inspector P. 0. Box 1050 St. Francisville, LA 70775 U. S. Nuclear Regulatory Commission Attn: Mr. Alan Wang MS O-8B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852
RBG-47582 Page 3 of 3 Department of Environmental Quality Office of Environmental Compliance Radiological Emergency Planning and Response Section Ji Young Wiley P.O. Box 4312 Baton Rouge, LA 70821-4312 Public Utility Commission of Texas Attn: PUC Filing Clerk 1701 N. Congress Avenue P. 0. Box 13326 Austin, TX 78711-3326 RBF1-15-0101 LAR 2014-02
AC Sources-Operating 3.8.1 SURVEILLANCEREQUIREMENTS_(continued)________
SURVEILLANCE FREQUENCY SR 3.8.1.11------------NOTES-------
- 1. All DG starts may be preceded by an engine prelube period.
- 2. This Surveillance shall not be performed in MODE 1, 2, or 3. (Not applicable to DG 1C)
However, credit may be taken for unpianned events that satisfy this SR.
Verify on an actual or simulated loss of offsite power 24 months signal:
- a. De-energization of emergency buses;
- b. Load shedding from emergency buses for Divisions I and II; and
- c. DC auto-starts from standby condition and:
- 1. energizes permanently connected loads in
_<10 seconds for DG IA and DG lB and
_<13 seconds for DC IC,
- 2. energizes auto-connected shutdown loads,
- 3. maintains steady state voltage i.forDGl1Aand DG1BŽ_>374OV and
<_4368 V, ii. forDGl1C>3740Vand_<4580V
- 4. maintains steady state frequency >_58.8 Hz and < 60.2 Hz, and
- 5. supplies permanently connected and auto-connected shutdown loads for
_>5 minutes.
(continued)
RIVER BEND 3.8-9 RIVE BED Amendment 38-9 No. 81!21!33 168, 187
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)________
SURVEILLANCE FREQUENCY SR 3.8.1.12 -------------- NOTES- ------
- 1. All DG starts may be preceded by an engine prelube period.
- 2. This Surveillance shall not be performed in MODEl1 or2. (Not applicable to DG 1C)
However, credit may be taken for unplanned events that satisfy this SR.
Verify on an actual or simulated Emergency Core 24 months Cooling System (ECCS) initiation signal each DG auto-starts from standby condition and:
- a. For DG 1C during the auto-start maintains voltage < 5400 V and frequency < 66.75 Hz;
- b. In < 10 seconds for DG 1A and DG lB and
_<13 seconds for DG IC after auto-start and during tests, achieves voltage _> 3740 V and frequency _>58.8 Hz.
- c. Achieves steady state voltage
- 1. ForDG 1Aand DG1BŽ>3740Vand
<*4368 V,
- 2. For DG 1CŽ_374OV and*<4580 V,and
- 3. For DG 1A, 1B, and IC, frequency of
_>58.8 and < 60.2 Hz; and
- d. Operates for _>5 minutes.
(contirnued)
I RIVER BEND I IVRBED3.8-10 Amendment No. 81121133**,.v 165, 168v, 187
Attachment 1 RBG-47582 Revised Surveillance Requirement Numbering Specification Page Note/Change SR 3.8.1.11 3.8-9 Subsection lettering/numbering SR 3.8.1.12 3.8-10 Subsection lettering/numbering SR 3.8.1.15 3.8-12 Subsection lettering/numbering SR 3.8.1.15 3.8-13 Relocation of SR 3.8.1.16 (no change to SR)
SR 3.8.1.19 3.8-14 Subsection lettering/numbering SR 3.8.1.20 3.8-15 Subsection lettering/numbering
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.13 -~~~NOTE--- --
This Surveillance shall not be performed in MODE 1, 2, or 3. (Not applicable to DG 1C)
However, credit may be taken for unplanned events that satisfy this SR.
Verify each DG's automatic trips are bypassed on 24 months an actual or simulated ECCS initiation signal except:
- a. Engine overspeed; and
- b. Generator differential current.
SR 3.8.1.14 -~~~~NOTES-------
- 1. Momentary transients outside the load and power factor ranges do not invalidate this test.
- 2. Credit may be taken for unplanned events that satisfy this SR.
Verify each DG operating at a power factor _<0.9, 24 months operates for _> 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
- a. For DG 1A and DG I1B loaded _> 3050 kW and *<3130 kW; and
- b. For DG 1C:
- 1. For_Ž2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> loaded Ž_2750 kW and
_<2850 kW, and
- 2. For the remaining hours of the test loaded Ž_2525 kW and
(continued)
RIVER BEND RIE ED3.8-11 Amendment No. 81 9"!,1211331!68, 187
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.15 -~~~NOTES--------
- 1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated > 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> loaded > 3050 kW and
- 3100 kW for DG 1A and DG 1B, and
>Ž2525 kW and *<2600 for DC lC, or operating temperatures have stabilized, which ever is longer.
Momentary transients outside of the load range do not invalidate this test.
- 2. All DG starts may be preceded by an engine prelube period.
Verify each DG starts and achieves:
24 months
- 1. In <l0 seconds for DG1A and DG1B and
< 13 seconds for DC IC voltage Ž>3740 V and frequency _> 58.8 Hz, and
- 2. Steady state voltage a) ForDGI1Aand DG1BŽ>_374OV and
- <4368 V b) For DG1CŽ>3740Vand_<4580Vand c) For DC 1A, 1B, and 1C frequency
> 58.8 Hz and _< 60.2 Hz.
(continued)
RIVER BEND RIVR BND3.8-12 Amendment No. 81!21!33 165 168, 187
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.16 ----------- NOTE- -------
This Surveillance shall not be performed in MODE 1, 2, or 3. (Not applicable to DG 1C) However, credit may be taken for unplanned events that satisfy this SR.
Verify each DG: 24 months
- a. Synchronizes with offsite power source while loaded with emergency loads upon a simulated restoration of offsite power;
- b. Transfers loads to offsite power source; and
- c. Returns to ready-to-load operation.
SR 3.8.1.17 -------- NOTE---------------..... 1 ..
This Surveillance shall not be performed in MODE 1, 2, or 3. (Not applicable to DG 1C) However, credit may be taken for unplanned events that satisfy this SR.
Verify, with a DG operating in test mode and 24 months connected to its bus, an actual or simulated ECCS initiation signal overrides the test mode by:
- a. Returning DG to ready-to-load operation; and
- b. Automatically energizing the emergency loads from offsite power.
SR 3.8.1.18-----------NOTE-------
This Surveillance shall not be performed in MODE 1, 2, or 3. (Not applicable to DG lC) However, credit may be taken for unplanned events that satisfy this SR.
Verify sequence time is within + 10% of design for each 24 months load sequencer timer.
(continued)
RIVER BEND RIVR BND3.8-13 Amendment No. 81 95 121 133 168, 187
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)________
SURVEILLANCE FREQUENCY SIR 3.8.1.19----------NOTES- ------
- 1. All DG starts may be preceded by an engine prelube period.
- 2. This Surveillance shall not be performed in MODE 1,2, or 3. (Not applicable to DG 1C)
However, credit may be taken for unplanned events that satisfy this SR.
Verify, on an actual or simulated loss of offsite power 24 months signal in conjunction with an actual or simulated ECCS initiation signal:
- a. De-energization of emergency buses;
- b. Load shedding from emergency buses for Divisions I and II; and
- c. DG auto-starts from standby condition and:
- 1. energizes permanently connected loads in
_<10 seconds for DG 1A and DG lB and
_<l3 seconds for DG 1C,
- 2. energizes auto-connected emergency loads,
- 3. achieves steady state voltage
- i. forDGl1Aand DG1BŽ>_3740 Vand
_<4368 V, ii.for DG 1CŽ>_374OV and*_<4580V,
- 4. achieves steady state frequency >_58.8 Hz and < 60.2 Hz, and
- 5. supplies permanently connected and auto-connected emergency loads for
_>5 minutes.
(continued)
RIVER BEND 3.8-14 RIVE BED Amendment 3-14 No. 81!21 133 168, 187
AC Sources-Operating 3.8.1 SURVEILLANCE REQU IREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.20 _-..............-.NOTE-----------..........
All DG starts may be preceded by an engine prelube period.
Verify, when started simultaneously from standby 10 years condition, each DG achieves:
- 1. In_<l0 seconds for DG 1Aand DG1B and
< 13 seconds for DG 1C voltage Ž_3740 V and frequency > 58.8 Hz, and
- 2. Steady state voltage a) For DG 1A and DG 1BŽ->374OV and
<*4368 V, b) For DG IC Ž 3740 V and
- 4580 V, and c) For DG IA, I1B, and IC frequency_Ž 58.8 Hz and _<60.2 Hz.
RIVER BEND 3.8-15 RIVER BED 3.8-15Amendment No. &1-12'1--65 187