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Category:Letter
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 27, 2017 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT 2 - REVIEW OF STEAM DRYER INSPECTION RESULTS (CAC NO. MF7742)
Dear Mr. Hanson:
By letter dated August 1, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16222A388), Exelon Generation Company, LLC (Exelon, the licensee) submitted information (1) summarizing the steam dryer inspection results for the second refueling outage (RFO) post-extended power uprate (EPU) for the Nine Mile Point Nuclear Station, Unit 2 (NMP2), (2) describing the long-term steam dryer inspection plan for NMP2, and (3) providing information to support resolution of two open items from the U.S. Nuclear Regulatory Commission (NRC) staff's review of the steam dryer inspection results for the first RFO post-EPU for NMP2. The purpose of this letter is to provide the results of the NRC staff's review of the steam dryer inspection results and the information to support resolution of the two open items. The NRC staff will provide separate correspondence regarding the NRC staff's review of the long-term steam dryer inspection plan.
The NMP2 license included the following two license conditions (i.e., requirements) concerning EPU:
License Condition 2.C.(20)(f):
During the first two scheduled refueling outages after reaching 120 percent OLTP [original licensed thermal power] conditions, a visual inspection shall be conducted of all accessible, susceptible locations of the steam dryer in accordance with BWRVIP [Boiling Water Reactor Vessel and Internals Project] -139 inspection guidelines. In addition, a visual inspection of all accessible welds that were analyzed using embedded models shall be conducted. In addition, a visual inspection of the existing indications in the upper support ring, the drain channel to skirt weld, the tie bar-to-hood weld heat affected zone, and vertical support plates shall be conducted.
License Condition 2.C.(20)(g):
The results of the visual inspections of the steam dryer shall be reported to the NRC staff within 90 days following startup from the respective refueling outage.
B. Hanson Consistent with the requirements listed above, Exelon provided the steam dryer inspection results, including a description of the scope of the inspection in its August 1, 2016, letter. The NRC staff reviewed the steam dryer inspection results for the second RFO post-EPU. The NRC staff's review of the licensee's steam dryer inspection results revealed no EPU-related service induced cracking.
A regulatory audit was conducted on February 18, 2016 at Continuum Dynamics Inc. in Ewing Township, New Jersey, as part of the NRC staff's review of the steam dryer inspection results for the first RFO post-EPU for NMP2. The purpose of the audit was to assess the validity and applicability of a new loading component that was used in the NMP2 steam dryer stress analysis. A summary of the audit dated June 24, 2016, is available at ADAMS Accession No. ML16146A211. The NRC staff completed the audit with two open items:
- 1. The staff found the information provided does not substantiate the application of velocity induced loading {VIL) as proposed by the licensee in its letters dated July 28, 2014, and October 8, 2015 (ADAMS Accession Nos. ML14216A347 and ML15288A248, respectively). Therefore, the minimum alternating stress ratio computed without the use of VIL damping is representative of the actual alternating stress state of the NMP2 dryer.
- 2. In addition, the staff found that the reexamination of the NMP2 revised dryer loads presented in Appendix C of Report No.14-09P, Revision 1, "Acoustic and Low Frequency Hydrodynamic Loads at 115% CLTP Target Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1 R," dated May 2014 (ADAMS Accession No. ML15022A662), show much lower than expected pressure loading spectra based on experience with similar sized plants and dryers. The licensee has agreed to check the accuracy of the plots provided in the report.
To address the first open item concerning VIL, the licensee performed steam dryer stress analysis without VIL considered (letter dated May 4, 2016; ADAMS Accession No. ML16131A653). The licensee's stress analysis results, without VIL considered, show that all the steam dryer locations have an alternating stress ratio greater than the NMP2 licensing basis American Society of Mechanical Engineers (ASME) code minimum ratio of 1.0. The stress ratios indicate that the dryer maximum alternating stress is less than 9,714 pounds per square inch (psi), which corresponds to an alternating stress ratio of 1.4 and is, therefore, below the ASME fatigue endurance limit of 13,600 psi for austenitic stainless steel. Furthermore, a qualitative review by the NRC staff of the fatigue usage for the locations, with alternating stress ratios below 2.0 when discounting the VIL mechanism, shows the minimum number of fatigue cycles experienced at NMP2 post-EPU is greater than 109 cycles during its 4 years of operation under EPU conditions without fatigue cracking. Thus, the NMP2 steam dryer has sufficiently demonstrated that fatigue cracking is unlikely under EPU conditions.
To address the second open item concerning revised dryer loads, the licensee performed three checks:
- 1. A comparison between a representative measured outer bank hood pressure loading on the Quad Cities Unit 2 (QC2) dryer and the computed pressure loading at a similar location on the NMP2 outer bank hood at a similar main steam line Mach number. The conclusion is that the loading definition for NMP2 is consistent with the load measured on the QC2 dryer.
B. Hanson 2. An independent check of the design record file of the calculation supporting the load definition was completed, and no errors or inconsistencies were found in the analysis.
- 3. The loads were compared to a similar size plant and dryer evaluated with the Continuum Dynamics Inc. Acoustic Circuit Model and the pressure loading spectra considered to be in the same order of magnitude.
The NRC staff has reviewed the checks provided by the licensee and finds them acceptable because the checks demonstrated that the revised dryer loads were accurate.
Based on a review of the information provided, the NRC staff concludes that the licensee has provided the information required by License Conditions 2.C.(20)(f) and 2.C.(20)(g). Also, the NRC staff determined that there are no technical issues that warrant additional followup action regarding the steam dryer inspection results for the second RFO post-EPU or the information to support resolution of two open items from the staff's review of the steam dryer inspection results for the first RFO post-EPU.
Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 cc: Distribution via Listserv
B. Hanson
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT 2 - REVIEW OF STEAM DRYER INSPECTION RESULTS (CAC NO. MF7742) DATED MARCH 27, 2017 DISTRIBUTION:
Public LPL 1 R/F RidsNrrDorlLpl 1 RidsRgn1 MailCenter RidsACRS_MailCTR RidsNrrLALRonewicz RidsNrrPMNineMilePoint RidsNrrDeEmcb ITseng, NRR ADAMS Accession Number: ML17080A439 OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DE/EMCB/BC DORL/LPL 1/BC DORL/LPL 1/PM NAME MMarshall LRonewicz JQuichocho JDanna MMarshall DATE 03/22/2017 03/22/2017 03/22/2017 03/27/2017 03/27/2017 OFFICIAL RECORD COPY