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MONTHYEARML20217J3751999-10-15015 October 1999 Informs That Applicable Portions of NEDC-32778P, Safety Analysis Rept for River Bend 5% Power Uprate, Marked as Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) Project stage: Other ML0232502012002-11-15015 November 2002 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Reactor Pressure Vessel Pressure-Temperature Limits and Request for Exemption from Requirements of 10 CFR 50.60 Project stage: Request ML0236501962002-12-31031 December 2002 Additional Questions Re 11/15/02 Amendment Request Project stage: Other ML0302900562003-01-15015 January 2003 Transmittal of Neutron Transport Calculations Benchmarking Report Project stage: Request ML0311401882003-04-23023 April 2003 P-T Limits Amendment Project stage: Other ML0311402082003-04-24024 April 2003 NMP1 P-T Limits Curve Amendment - Issues for Discussion Project stage: Other ML0312603012003-05-0606 May 2003 Request for Additional Information - Amendment Application Pressure-Temperature Limit Curves Project stage: RAI ML0314001372003-05-16016 May 2003 Current Active Action List Project stage: Other ML0317702342003-06-18018 June 2003 Change to Commitment Date for Response to Request for Additional Information - Amendment Application Pressure-Temperature Limit Curves (TAC No.MB6687 & MB6703) Project stage: Response to RAI ML0320504542003-07-24024 July 2003 Issuance of License Amendment No. 136, Reactor Vessel Material Surveillance Program Project stage: Approval ML0322505952003-07-31031 July 2003 Response to Request for Additional Information Pressure-Temperature Limit Curves Project stage: Response to RAI ML0326810102003-09-15015 September 2003 Transmittal of Revised Neutron Transport Calculations Benchmarking Report Project stage: Request ML0327606962003-10-27027 October 2003 License Amendment, Issuance of Amendment Re. Pressure Temperature Limit Curves Project stage: Approval RBG-46368, Additional Information Regarding River Bend Station Fluence Calculations2004-12-0808 December 2004 Additional Information Regarding River Bend Station Fluence Calculations Project stage: Other 2003-04-24
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Category:Letter type:RBG
MONTHYEARRBG-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-48220, Submittal of 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report RBG-48221, 2022 Annual Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Radiological Environmental Operating Report 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-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-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-48149, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022 2021 Annual Radioactive Effluent Release Report RBG-48148, 2021 Annual Radiological Environmental Operating Report2022-04-27027 April 2022 2021 Annual Radiological Environmental Operating 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-48082, 2020 Annual Radiological Environmental Operating Report2021-04-20020 April 2021 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-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 RBG-48054, Application to Adopt GL 86-10 Standard License Condition for Fire Protection Program2020-11-0202 November 2020 Application to Adopt GL 86-10 Standard License Condition for Fire Protection Program RBG-48049, Reply to a Notice of Violation; EA-20-0582020-10-26026 October 2020 Reply to a Notice of Violation; EA-20-058 RBG-48038, Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Offsite Exercise Requirements Due to Covid 19 Pandemic2020-10-0606 October 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Offsite Exercise Requirements Due to Covid 19 Pandemic RBG-48042, Submittal of Rev. 48 to Emergency Plan2020-09-22022 September 2020 Submittal of Rev. 48 to Emergency Plan RBG-48039, Report of Changes and Errors to 10CFR50.462020-09-16016 September 2020 Report of Changes and Errors to 10CFR50.46 RBG-48033, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-0404 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RBG-48023, Submittal of Revs. 46 and 47 to Emergency Plan and Revised Emergency Implementing Procedures2020-06-0909 June 2020 Submittal of Revs. 46 and 47 to Emergency Plan and Revised Emergency Implementing Procedures RBG-48019, 2019 Annual Radioactive Effluent Release Report2020-04-30030 April 2020 2019 Annual Radioactive Effluent Release Report RBG-48020, Annual Radiological Environmental Operating Report2020-04-30030 April 2020 Annual Radiological Environmental Operating Report RBG-48018, Withdrawal of License Amendment Request to Extend the RBS Emergency Plan Implementation Date2020-04-24024 April 2020 Withdrawal of License Amendment Request to Extend the RBS Emergency Plan Implementation Date 2024-01-12
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Entergy Operations, Inc.
River Bend Station wEnterVgy 5485 U. S. Highway 61N St. Francisville, LA 70775 Fax 225 635 5068 RBG-46368 December 8, 2004 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Additional Information Regarding River Bend Station Fluence Calculations Docket No. 50-45 8 License No. NPF-47
References:
- 1. Amendment 114 to Facility Operating License No. NPF-47 (TAC No.
MA6185), dated October 6,2000, "Increase in Maximum Allowable Thermal Power to 3039 Megawatts Thermal," RBC-49387
- 2. Letter from R. J. King to U.S. NRC Document Control Desk, dated May 9, 2003, Supplement to License Amendment Request (LAR) 2002-23, "Request for a Change to the Reactor Vessel Material Surveillance Program" RBG-46046
- 3. Letter 2003-173 from the BWRVIP (Boiling Water Reactor Vessel and Internals Project) to the U.S. NRC Document Control Desk, dated June 10, 2003, "River Bend 183 Degree Surveillance Capsule Report"
- 4. Amendment 136 to Facility Operating License No. NPF-47 (TAC No.
MB6140), dated July 24, 2003, "Reactor Vessel Material Surveillance Program," RBC-50059
- 5. Report Number MPM-904779, "Neutron Transport Analysis for River Bend Station," MPM Technologies, Inc., November 2004.
- 6. Calculation No. QR-779-17, Revision 1, "Update to the Adjusted RTndt (ART) Values for the RBS Reactor Vessel Using Available BWRVIP ISP Data and Updated Fluence.
- 7. "Nine Mile Point Nuclear Station, Unit No. I - Issuance of Amendment RE: Pressure-Temperature Limit Curves and Tables," (TAC No MB6687), October 27, 2003.
Dear Sir or Madam:
In the Reference I Safety Evaluation Report, the NRC staff approved the use of the River Bend Station (RBS) Pressure-Temperature (P-T) limit curves designated as 32 EFPY (effective full power years) curves, with a limitation that they only be used through 16 EFPY of operation. For continued operation beyond 16 EFPY, the staff required submittal of JVOD
RBG-46368 Page 2 of 3 additional information regarding the adequacy of RBS fluence calculations or submittal of an amendment to the P-T limit curves.
In Reference 2, RBS committed to:
Perform new fluence analysis in accordance with the guidance of Regulatory Guide 1.190 and incorporate the reactor pressure vessel (RPV) surveillance capsule testing results/data that will be available in 2003 from the BWRVIP ISP. Based on the new fluence analysis and surveillance capsule data, evaluate the current P-T Limit Curves for their "As-Is" acceptance, or revise accordingly.
In June 2003, a report containing RBS surveillance capsule testing results (Reference 3) was submitted to the NRC. One of the conclusions in the report (see Section 7) is that reported fluence is significantly lower than the fluence used to calculate the current P-T limits.
The NRC approved changes (Reference 4) to the RBS Updated Safety Analysis Report (USAR) revising the reactor vessel surveillance program to incorporate the Boiling Water Reactor Vessel Internals Project Integrated Surveillance Program (BWRVIP ISP) into the licensing basis (USAR Section 5.3.1.6.1, "Compliance with Reactor Vessel Material Surveillance Program Requirements"). The Reference 4 Safety Evaluation restates the Reference 2 commitment and credits the commitment when concluding the changes are acceptable.
New updated fluence calculations for the RPV have been subsequently performed in accordance with the guidance of Regulatory Guide 1.190 (Reference 5). This analysis was performed consistent with the methods described in reference 7. Both RBS cycles I and 9 dosimetry was evaluated by this analysis resulting in average C/M ratios of 1.04 and 0.94 respectively. These results support the 17.8 % vessel fluence uncertainty determined by the fluence analysis. Using the new updated fluence analysis and the latest RPV surveillance capsule testing results/data available from the BWRVIP ISP as inputs, the current P-T Limit Curves (for use to 32 EFPY of operation) have been evaluated and found to be "Acceptable As Is" and do not need to be revised (reference 6). Thus, the 16 EFPY operating limit restriction on the current P-T Limit Curves is being removed and the full 32 EFPY operating period restored. The current P-T curves will not be revised at this time.
Reference 6 updates the Adjusted Reference Temperature (ART) and evaluates impacts to the current P-T Limit Curves using the new updated fluence analysis for the RPV. The updated ART incorporates the new vessel surveillance material data available from the BWRVIP ISP testing results and satisfies the guidelines established in Reg. Guide 1.190. The calculation was developed to comply with Appendix G to 10CFR50 and with Reg. Guide 1.99, Rev. 2, as well as to implement the utility responsibilities outlined in Sections 3.2.5 and 3.2.6 of BWRVIP-102, and Section 6.1 of BWRVIP-86A. These documents also require an assessment and evaluation to determine the effects on plant operations (e.g., P-T Limits)
RBG-46368 Page 3 of 3 based on review of updated or current reactor vessel material surveillance data and test results that are available through the BWRVIP ISP.
The calculation concludes that the limiting updated ART value (95.80 F) is lower than the limiting current ART value (1020 F), which is the basis for the current RBS P-T Limit Curves. The ART evaluation applies to the RPV beltline region and estimates the effect on the integrity of the materials from neutron radiation embrittlement, which results in decreased fracture toughness over time. The evaluation shows that since the updated ART value is lower than the current ART value, the current P-T Limit Curves are not impacted and remain bounding (conservative) to the full 32 EFPY of operation for RBS. Therefore, the current P-T Limit Curves are Acceptable As-Is and do not need to be revised. The updated data and information is provided in the Attachment to this letter.
We are processing changes to incorporate the new information into our USAR and to remove the 16 EFPY operating restriction from our Technical Requirements Manual (TRM). These changes will be made under the RBS I OCFR 50.59 program.
There are no commitments in this letter. If you have any questions, please contact me at 225-381-4157.
Sipcerely, David N. Lorfing Manager Licensing - Acting DNL/wjf Attachment cc: U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Senior Resident Inspector P. 0. Box 1050 St. Francisville, LA 70775 U.S. Nuclear Regulatory Commission Attn: Mr. Michael K. Webb MS 0-7D1 Washington, DC 20555-0001
Attachment to RBG-46368 Updated Adjusted Reference Temperature (ART) Evaluation for the River Bend Reactor Vessel Beitline Materials at the 1/4Thickness and 3/4Thickness Locations Applicable to 32 EFPY with Power Uprates MaeilDsrpinChemical 32 EFPY Peak Fluernce, nlcm2 AIRTNDT. F (AARTNDT, F MaeilDsrpinComposition (E>l1.0 Mev.) at 32 EFPY (4) I Margin at 32 EFPY Vessel Material Cu INi Initial Chemistry Inside 114 T J 3/4 T 1/4 T 3/4 T 114T j 3/4T Bltcline Material Identification J(8)
%%I% wt%1/ RTNOT Factor (CF)
WVettcd Surface (2)
Location (3)
Location (3)
Location Location rD 'AT
%/T
'AT
'AT Location Location j___
Regulatory Guide 1.99, Revision 2, PositionI C3138-2 (8) 0.075 0.615 0 47.5 5.07E+ 18 3.50E3+18 1.8313+18 33.7 26.0 0 16.9 33. 67.5 52.1 Plate 13.0 26.0 C3054.1 (8) 0.085 0.685 -20 54.5 5.071E+18 3.5013-18 1.8312+18 38.7 29.9 0 17.0 34.0 52.7 39.8 Plate 14.9 29.9 C3054-2 (7) 0.08 0.673 10 51.0 5.07E+ 18 3.501E+18 1.8313+18 36.2 28.0 0 17.0 34.0 80.2 65.9 Plate (1) 14.0 28.0 492L4871/A4211327AE (8) 0.04 0.95 -60 54.0 5.0723+18 3.5013+18 1.8312+18 38.4 29.6 0 19.2 38.4 16.7 -0.8 WVeld 29.6 114.8 492LA87I/A4211B27AF (8) 0.03 0.98 -50 41.0 5.0713+18 3.50OE+18 1.8312+18 29.1 22.5 0 14.6 29.1 8.3 -5.0 Weld 11.2 22.5 WVeld (1) 5P6756/0342 Tandem Wire Proc. (7) 0.084 0.938 -50 113.6 5.07E+18 3.5013+18 1.83r2+18 80.7 62.3 0 28.0 56.0 86.7 68.3 28.0 56.0 5P6756/0342 Single Wire Proc. (7) 0.084 0.938 -60 113.6 5.07E3+18 3.50E3+18 1.83E+18 80.7 62.3 0 28.0 56.0 76.7 58.3 Weld (1) 28.0 56.0 Regulatory Guide 1.99, Revision 2, Position2 Weld (I) 5P6756/0342 Tandem WVire Proc. (7) See See -50 165.85 5.07E+18 3.5023+18 1.8312+18 117.8 91.0 0 14.0 28.0 195.8 1 69.0 note note (5) 14.0 28.0 (7) (7) (6) (6) 5P6756/0342 Single Wire Process (7) See See -60 165.85 5.0713+18 3.501E+18 1.8312+18 117.8 91.0 0 14.0 28.0 85.8 59.0 Weld (1) note note (5) 14.0 128.0
_ _ _ _ _ _ _ _ _ _ _ (7) (7) __ _ _ __ _ __ 1 __ _ _ _(6) 1 (6)
.1 Attachment to RBG-46368 (continued)
Notes:
- 1) Material Heat from which surveillance specimens were taken.
- 2) Calculated Peak Fluence (See Ref. 5 & 6).
- 3) Attenuated Peak Fluence using Reg. Guide 1.99, Rev. 2 (See Ref. 5 & 6).
- 4) Reg. Guide 1.99, R/2, Fluence Factor (FF) to determine ARTNDT (CF x FF) for all materials: 1/4t = 0.71 and 3/4t = 0.548 (See Ref. 6).
- 5) Vessel and Surveillance-based CF Adjusted for the vessel beltline WELDS using the BWRVIP ISP surveillance data with the ratio procedure of Reg.
Guide 1.99, R12, Position 2 (See Ref. 6).
- 6) Reduced terms for credible surveillance data, Ref. Reg. Guide 1.99, R/2, Position 2 (See Ref. 6).
- 7) Plate - Chemical compositions based on Best Estimate Average Chemistry values for the vessel materials - Plate Heat C3054-2 (Cu = 0.08 %, Ni = 0.673 %) (See Ref. 6).
Production Welds - Chemical composition based on the Weld Best Estimate Coil Weighted Average Chemistry values for vessel production Weld -
Material - Heat 5P6756/0342 is Vessel Coil Weighted Average excluding surveillance data (Cu = 0.084 %, Ni = 0.938 %) (See Ref. 6).
Surveillance Welds - Chemical compositions based on the Best Estimate Vessel Average Chemistry values for the vessel Surveillance Weld Material -
The chemistry values are from the average of all unique measurements of the available surveillance data sets for Weld Material Heat 5P6756 (Cu =
0.06 %, Ni = 0.93 %) (See Ref. 6).
- 8) VESSEL Chemical Composition and Initial RTNDT (See Ref. 6).
[ ] Controlling value of the Adjusted Reference Temperatures (ART).