ML22292A061
Text
PROPRIETARY INFORMATION -WITHHOLD PURSUANT TO 10 CFR 2.390 Appendix 6D of the USAR contains proprietary information in Enclosure 1; upon separation the remaining USAR information is decontrolled.
200 Exelon Way
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~,-- Constellation. Kennett Square, PA 19348 www.constellation.com 10 CFR 50.71 (e) 10 CFR 54.37(b) 10 CFR 50.59(d) 10 CFR 72.48(d)
NMP2L2821 October 5, 2022 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Power Station, Unit 2 Renewed Facility Operating License No. NPF-69 NRC Docket No. 50-41 O
Subject:
Submittal of Revision 25 to the Nine Mile Point Unit 2 Updated Safety Analysis Report (USAR) and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, Technical Specifications Bases, Technical Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review Pursuant to the requirements of 10 CFR 50.71 (e), 10 CFR 50.59(d)(2), 10 CFR 54.37(b),
10 CFR 72.48(d)(2) and the Nine Mile Point Unit 2 (NMP2) Technical Specifications Bases Control Program (TS 5.5.10), Constellation Energy Generation, LLC (CEG) hereby submits the following information for NMP 2:
- NMP2 USAR, Revision 25
- NMP2 USAR, Revision 25, Reference Figures
- NMP2 Technical Specifications Bases, Revision 69
- NMP2 10 CFR 50.59 Evaluation Summary Report
- NMP2 10 CFR 72.48 Evaluation Summary Report
- NMP2 TRM, Revision 48
- NMP2 10 CFR 54.37(b) Aging Management Review Two copies of the USAR, Revision 25, are provided on Digital Video Disc (DVD). USAR, Revision 25, with proprietary information is provided on DVD as Enclosure 1. A non-proprietary version of the USAR is provided on DVD as Enclosure 2. Proprietary status per 10 CFR 2.790 was granted by the Nuclear Regulatory Commission (NRC) for USAR Appendix 6D in your letter dated May 11, 1994 (Ascension No. 9405170218). For the PROPRIETARY INFORMATION -WITHHOLD UNDER 10 CFR 2.390 Appendix 6D of the USAR contains proprietary information in Enclosure 1; upon separation the remaining USAR information is decontrolled.
U.S. Nuclear Regulatory Commission NMP2 USAR, Revision 25 October 5, 2022 Page 2 reasons stated in Niagara Mohawk letters dated October 29, 1993, and April 28, 1994, and supporting affidavits, and as accepted by the NRC in its letter dated May 11, 1994, the material contained in the NMP2 USAR Appendix 6D should be withheld from public disclosure pursuant to 10 CFR 2.390. The NMP2 USAR Appendix 6D has not been changed but is included in the submittal of USAR, Revision 25. In addition, one copy of the complete Technical Specifications Bases, Revision 69 {Enclosure 3), is provided as a combined pdf-file on DVD and incorporates changes made since September 2020. The NMP2 revised Technical Requirements Manual, Revision 48 {Enclosure 4), is also provided on DVD.
This USAR revision contains changes made since the NMP2 2020 refueling outage and through the 2022 refueling outage. Attachment 1 provides the Summary of Changes NMP2 USAR and Attachment 2 provides the Electronic File Directory Structure, Revision 25. , NMP2 10 CFR 50.59 Evaluation Summary Report, which covers changes made since the NMP2 2020 refueling outage and through the end of September 2022, contains a brief description of changes, tests, and experiments, included in a summary of each associated 50.59 evaluation. Attachment 4, NMP2 10 CFR 72.48 Evaluation Summary Report, covers evaluations performed to the Independent Spent Fuel Storage Installation license since 2020.
In addition, pursuant to the requirements of 10 CFR 54.37(b) and the guidance specified in Regulatory Issue Summary 2007-16, Revision 1, "Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses," the USAR update required by 10 CFR 50.71 (e) must include any Structures, Systems, or Components (SSCs) newly identified that would have been subject to an aging management review or evaluation of time-limited aging analyses in accordance with 10 CFR 54.21. The USAR update must describe how the licensee will manage the effects of aging in order to effectively maintain the intended function(s) of newly-identified SSCs. An evaluation was completed to determine whether any newly-identified SSCs existed in support of submitting USAR, Revision 25. This evaluation involved reviewing pertinent documentation for the period subsequent to the last NMP2 biennial USAR revision. As a result of this review, there were no newly-identified SSCs for which aging management reviews or time-limited aging analyses would apply.
As required by 10 CFR 50. 71 (e)(2)(i), I certify that to the best of my knowledge, the information contained in the Enclosures and Attachments to this letter accurately reflects information and analyses submitted to the NRC, or prepared pursuant to NRC requirements as described above.
If you have any questions or require further information, please contact Ron Reynolds at ronnie.reynolds@constellation.com.
Respectfully, V
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David P. Helker Sr. Manager - Licensing Constellation Energy Generation, LLC
U.S. Nuclear Regulatory Commission NMP2 USAR, Revision 25 October 5, 2022 Page 3
Enclosures:
(1) DVD, NMP2 USAR, Revision 25 and Reference Figures- Proprietary (2) DVD, NMP2 USAR, Revision 25 and Reference Figures- Non-Proprietary (3) DVD, NMP2 Technical Specification Bases, Revision 69 (4) DVD, NMP2 Revised Technical Requirements Manual, Revision 48 Attachments: (1) Summary of Changes - NMP2 USAR Revision 25 (2) Electronic File Directory Structure (3) NMP2 10 CFR 50.59 Evaluation Summary Report (4) NMP2 10 CFR 72.48 Evaluation Summary Report cc: NRC Regional Administrator, Region 1 w/Enclosures & Attachments NRC Resident Inspector II NRC Project Manager "
A. L. Peterson, NYSERDA w/Enclosures 2, 3, 4, & Attachments
Attachment 1 Summary of Changes - NMP2 USAR Revision 25 10 CFR 50.71(e)(2)(ii) requires that revisions to the USAR include changes made under the provisions of 10 CFR 50.59. Accordingly, the list below identifies plant changes and projects included in Revision 25 of the Updated Safety Analysis Report.
Change Number Brief Title 2-14-UFS-01Q Revise Figure 10.1-5b to add Condensate Booster Pump Discharge Header Vent Isolation Valves 2CNM-V197A and 2CNM-V197B.
2-17-UFS-009 Revise Chapters 1, 6A, 7, 11, and 18, to reflect Plant Process Computer upgrades.
2-19-UFS-012 Revise Figures 9.5-6, 9.5-7, and 9.5-35, to reflect installation of new communication equipment.
2-19-UFS-014 Revise Section 7. 7 to describe new digital Feedwater control system.
Also, revised applicable Chapter 7 and Chapter 1O Figures.
2-19-UFS-016 Revise Section 8.3 to describe connection of the normal 13.BkV buses to their alternate reserve power sources. Also, revised Figure 8.3-1.
2-19-UFS-018 Revise Section 9.2 and Figure 9.2-9a to describe changes to the Sewage Lift Station.
2-20-UFS-017 Revised figures in Chapters 5, 9, and 11, to reflect Reactor Water Cleanup System replaced with a new digital control system.
2-20-UFS-019 Revise Sections 6, 12, and 15 to reflect revised increased MSIV leakage as documented in the revised LOCA dose analysis.
2-21-UFS-001 Revise Section 9A to change Fire Zones 395XL, 612XL and 613XL to 395NL, 612NL, and 613NL.
2-21-UFS-002 Revise Section 9A, Table 9A.3-4, to correct typographical error.
2-21-UFS-006 Revise Sections 6, 13, and 15 to update reference from BWROG EPG revision 4 to BWROG EPG/SAG Revision 4.
2-21-UFS-005 Revise Sections 1, 9, and 12 to include Holtec HI-STORM FW spent fuel storage system.
2-21-UFS-007 Revise Section 9A, Fire Pump Surveillance Requirements, from "once per 31 days" to "once per 92 days."
Attachment 1 Summary of Changes - NMP2 USAR Revision 25 Change Number Brief Title 2-21-UFS-009 Revise Section 6.2 to reflect replacement of Nitrogen Supply Inboard Solenoid Valve replacement with check valve.
2-21-UFS-010 Revise Section 6.3.4.2 to add "Surveillance Frequency Control Program."
2-21-UFS-010.1 Revise Chapters 12 and 15 to reflect vital area dose rates as a result of CAVEX source term.
2-21-UFS-010.2 Provides administrative clarification to changes in packages 2 UFS-010 and 2-21-UFS-010.1 2-21-UFS-011 Revise Figure 9.3-17a to add flow indication and an isolation valve.
2-21-UFS-012 Revise Section 98 to update Control Room Evacuation timeline for Feedwater disconnect from <90 seconds to 5 minutes.
2-21-UFS-013 Update Figures 5.1-2A, 5.4-28, and 5.4-2C to add new computer points vessel level indication.
2-21-UFS-014 Revise Section 9.1 to describe receipt of new GNF3 fuel assemblies to be introduced during NMP2 next refuel outage.
2-21-UFS-015 Revise Figure 4.6-05a to restore line breaks and add back a section of line that was inadvertently removed from figure.
2-21-UFS-016 Revise Sections 8.2, 8.3, and Figure 8.3-1 to reflect changes from replacement of main power transformers.
2-21-UFS-019 Revise Section 9A to align several fire protection system preventive maintenances and testing from 18-month intervals to 24 month intervals.
2-21-UFS-022 Revise Section 9A to update calorific values for 9A.3.1.2.3 and Table 9A.3-4.
2-21-UFS-023 Introduction of New GNF3 fuel and Cycle 19 Reload Updates.
2-21-UFS-024 Revise Figures 11.2-1 f and 11.2-1 h to add note that valves are mechanically held closed.
2-22-UFS-002 Revise Figure 8.3-2 to add Note indicating that the off-site supply breaker for 2ENS*SWG 102 could be located in either 2ENS*SWG102-4 or ENS*SWG102-5.
Attachment 1 Summary of Changes - NMP2 USAR Revision 25 Change Number Brief Title 2-22-UFS-003 Revise Figures 8.3-6, Sht. 25 and 9.2-2, Shts. 2 and 3 to remove 18
' second lock out logic that is activated on the start of service water pumps.
2-22-UFS-006 Revise Table 8.3-4 to reflect change from replacing 2RCS*MOV1 OB-Actuator, 2RCS-MOV1 OB-ACT.
2-22-UFS-007 Revise Figure 8.3-3, Sht. 2, to reflect change to permanently bypass voltage regulating transformers 2SCI-REG1 and 2SCI-REG2 which will be de-energized and abandoned in place.
2-22-UFS-010 Revise Table 8.3-4 to remove Division 2 space heater 2EGT*H1 from table and abandon equipment in place.
2-22-UFS-011 Revise Section 9B.8.2.2 and 9B.8.2.4 to reflect nuclear fuel transition to GNF3 fuel.
2-22-UFS-012 Revise Figure 9.4-1 d to correct alarm and computer point numerical errors.
2-22-UFS-014 Revise Table 12.3-1 to remove radiation monitor 2RMS-RE109.
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Attachment 3 NMP210 CFR 50.59 Evaluation Summary Report Nine Mile Point Nuclear Station Unit 2 Renewed Facility Operating License No. NPF-69 This report is issued pursuant to reporting requirements of 10 CFR 50.59(d)(2)
TiUe: NMP2 Feedwater Digital Controls Upgrade (2019-02)
Units Affected: Unit2 Brief
Description:
The existing reactor feedwater control (FWC) system is obsolete.
Modification ECP-17-000688 will replace the analog feedwaterlevel control system with a Westinghouse Digital Feedwater Control System {DFWCS).
The DFWCS is based on the Ovation Platform manufactured by Emerson Process Management. The function of the feedwater control system is to control the flow of feedwater into the reactor vessel to maintain the vessel water level within predetermined limits during all normal plant operating modes.
Title:
Increased Core Average Exposure (2021-01)
Units Affected: Unit2 Brief
Description:
The results of the 50.59 screening are that the use of increased core average discharge exposure (CA VEX) as design input to the Fuel Handling Accident (FHA) and Control Rod Drop Accident (CRDA) analyses, and the change in consequences for the FHA, CRDA and the increase in vital area post-accident dose and dose rates (including post-LOCA) are considered to be adverse effects on USAR described design functions, and so are the focus of this 50.59 evaluation.
Attachment 4 NMP210 CFR 72.48 Evaluation Summary Report Nine Mile Point Nuclear Station Unit 2 Renewed Facility Operating License No. NPF-69 This report is issued pursuant to reporting requirements of 10 CFR 72.48(d)
Title:
ECP-19-000186 72.48 Evaluation 2019-01, Design and Install of HI-STORM Canister Transfer Pit (72.48-2019-01)
Brief
Description:
A Canister Transfer Pit (CTP) will be constructed near the existing ISFSI at NMP to facilitate transfer of the Holtec Multi-Purpose Canister {MPC) between the Holtec transfer cask (HI-TRAC) and the Holtec HI-STORM FW XL overpacks. Also, the Haul Path section between the CTP and the ISFSI approach apron will be removed and replaced by a stronger and wider section. The CTP construction will require the temporary excavation and
'removal of substrate (soil ditch) to a depth of approximately 11 feet over an area of approximately 37 feet by 70 feet. Additionally, the proposed activity will temporarily demolish part of the haul path which provides access to the ISFSI.
ENCLOSURES DVD 1} N MP2 USAR, Revision 25 and Reference Figures - Proprietary 2} NMP2 USAR, Revision 25 and Reference Figures - Non-Proprietary 3} NMP2 -Technical Specifications Bases, Revision 69
- 4) NMP2 - Revised Technical Requirements Manual, Revision 48