ML19183A103
| ML19183A103 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/21/2019 |
| From: | Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19177A213 | List: |
| References | |
| RS-19-067 | |
| Download: ML19183A103 (11) | |
Text
Attachment A Dresden Nuclear Power Station UFSAR Revision 13 Change Summary Report 15-012 Revision to UFSAR Section 6.2 Revised Table 6.2-10 to reflect installation of Primary Containment Isolation Valve for additional test taps on the Unit 2 Feedwater 'A' Loop per Engineering Change (EC) 339633.16-001 Revision to UFSAR Section 6.2 Revised Table 6.2-11 to reflect installation of Primary Containment Isolation Valve for additional test taps on the Unit 3 Feedwater 'A' Loop per EC 407115.16-015 Revision to UFSAR Section 9.4.7 Revised page 9.4-1 O to reflect reconfiguration of the Unit 2/3 Emergency Diesel Generator (EOG) ventilation dampers and related items to fail open on a loss of Instrument air per EC 405449.16-016 Revision to UFSAR Section 8.3.1.4.3 Revised page 8.3-8 to reflect replacement of the Unit 3 Essential Services System (ESS) uninterruptable power supply (UPS) equipment per EC 404638.16-019 Revision to UFSAR Section 8.3 Revised Table 8.3-1, Figure 8.3-6, and Figure 8.3-7 to reflect replacement of the Unit 2/3 EOG fuel oil transfer pump motor per EC 405079.16-020 Revision to UFSAR Section 8.3 Revised Table 8.3-1 and Figure 8.3-4 to reflect replacement of the Unit 2 EOG fuel oil transfer pump motor per EC 406492.16-024 Revision to UFSAR Section 8.3 Revised Figure 8.3-3 to reflect installation of a modification to bypass the Unit 2 ESS UPS to supply power directly to the ESS Bus per EC 406339.17-002 Revision to UFSAR Section 8.3.1.4.3 Revised page 8.3-8 to reflect replacement of the Unit 2 ESS UPS equipment per EC 403381 .17-003 Revision to UFSAR Section 9.3.1.2.1 Revised page 9.3-2 and 9.3-3 to reflect replacement of Unit 2 'A' instrument air compressor and downstream dryer and filters per EC 617285.17-004 Revision to UFSAR Section 7.6.1.3.2 Revised page 7.6-3 to reflect replacement of Unit 2 recorders and removal of selector switches for Intermediate Range Monitor (IRM), Average Power Range Monitor (APRM), Rod Block Monitor, and Startup Range Monitor per EC 617910.17-006 Revision to UFSAR Section 3.0, 3.5, 6.2, 6.4, 8.3, and 11.3 Revised pages 3.ii, 3.v, 3.5-8 through 3.5-12, 3.5-17, 3.5-18, 6.2-67, 6.4-1, 8.3-23, 11.3-1, 11.3-18; and table 3.5-3 to clarify and reinstate the intent of original FSAR plant licensing bases.
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Attachment A Dresden Nuclear Power Station UFSAR Revision 13 Change Summary Report 17-008 Revision to UFSAR Section 2.4.8.2 Revised page 2.4-4 and 2.4-5 to reflect revision to Illinois Environmental Protection Agency, National Pollutant Discharge Elimination System (NPDES) permit.17-012 Revision to UFSAR Section 7.3.2 Revised pages 7.3-37 and 7.3-47 to reflect installation of keylock switches to defeat Main Steam Line Valve (MSIV) Group 1 isolation prior to reaching -59" Reactor Water Level for Unit 2 per EC 397320.17-014 Revision to UFSAR Chapters 3, 4, 5, 6, 7, and 15 Revised pages 3.9-43, 4.1-1 , 4.1-2, 4.2-1, 4.2-2, 4.2-4, 4.2-4a, 4.2-15, 4.2-15a, 4.3-11, 4.3-12, 4.3-13, 4.3-14, 4.3-16, 4.3-18, 4.4-7, 4.4-8, 4.4-10, 4.4-11 , 4.4-12, 4.6-21, 5.2-1 a, 5.2-2, 5.2-4, 6.2-19, 6.2-104a, 6.3-1, 6.3-9, 6.3-16a, 6.3-36, 6.3-59 , 6.3-66, 6.3-68, 6.3-69, 6.3-70, 6.3-76a, 6.3-87a, 6.3-87b, 7-1, 7.1-1a, 7.1-4, 7.2-3a, 7.2-27, 7.3-1, 7.3-2, 7.3-50, 7.6-18e, 7.6-26, 7.7-29, 7.7-31, 7.8-2, 7.8-3, 7.8-6, 7.8-7, 15-ii, 15-iii, 15-iv, 15-v, 15-vii, 15-viii, 15.0-1 , 15.0-1a, 15.0-4, 15.0-5, 15.1-1, 15.1-1 a, 15.1-1, 15.1-2, 15.1-3, 15.1-4, 15.1-5, 15.1-6, 15.1-8, 15.2-1, 15.2-3, 15.2-6, 15.2-7, 15.2-8, 15.2-8a, 15.2-9, 15.2-10, 15.2-11, 15.2-12, 15.2-13, 15.2-13a, 15.2-14, 15.2-15, 15.2-16, 15.3-1, 15.3-6, 15.3-8, 15.4-1, 15.4-2a, 15.4-5, 15.4-6, 15.4-7, 15.4-7a, 15.4-8, 15.4-9, 15.~-10, 15.4-18, 15.4-19, 15.5-1, 15.5-1a, 15.5-2, 15.6-11, 15.6-24, 15.7-7, 15.7-9, 15.7-12, 15.8-1 , 15.8-1a, 15.8-2, 15.8-3, 15.8-12, 15.8-13; tables 1.2-1, 5.1 -1, 5.2-1 ,
15.4-3, 15.4-3d, 15.6-10, 15. 7-4d; and figure 4.2-5 to reflect nuclear fuel transition to AREVA ATRIUM 10XM and other minor changes to include clarification on top of active fuel per EC 393279, EC 407062, License Amendment 251 for Dresden Unit 2, License Amendment 160 for Dresden Unit 2, and License Amendment 155 for Unit 3.17-015 Revision to UFSAR Section 2.2 Revised table 2.2-7 to reflect Dresden Unit 1 fuel oil transfer system replacement per EC 618606.17-016 Revision to UFSAR Section 7.3 Revised pages 7.3-37 and 7.3-47 to reflect replacement and relocation of keylock switches for Main Steam Isolation Valve group 1 isolation circuitry per EC 397320 and EC 620398.18-002 Revision to UFSAR Sections 2.4.3 and 3.4.1.1 Revised pages 2.4-2, 3.4-1, and 3.4-2 to reflect specifying the lowest opening leading to safety related equipment in the event of a flood per EC 623268.18-004 Revision to UFSAR Section 6.2.3.4 Revised page 6.2-67 to reflect removal of referring to Operations with a Potential for Draining the Reactor Vessel (OPDRV) per License Amendment 256 for Dresden Unit 2 and License Amendment 249 for Dresden Unit 3.18-007 Addition of UFSAR Section 8.3.1.8 Revised page 8.3-18a to add additional details describing station blackout diesel generator system per Issue Report 4113898 .
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Attachment A Dresden Nuclear Power Station UFSAR Revision 13 Change Summary Report 18-009 Revision to UFSAR Section 4.6, 6.3, and 15.4 Revised pages 4.6-13, 4.6-15, 4.6-21, 6.3-1, 6.3-9, 6.3-12 , 6.3-13, 6.3-14, 6.3-16, 6.3-17, 6.3-20, 6.3-26, 6.3-34, 6.3-35, 6.3-36, 6.3-60, 6.3-61, 6.3-65, 6.3-66, 6.3-68, 6.3-69, 15.4-2, 15.4-2a, 15.4-3, 15.4-5, 15.4-7, 15.4-7a, 15.4-8, 15.4-10, 15.4-11, 15.4-14, 15.4-14a; tables 6.3-4b, 6.3-5, 6.3-12e, 6.3-13c, 6.3-19c, 6.3-20b, 6.3-21 b, 15.4-3, and 15.4-3d to address AREVA changing their name to Framatome and a small number of updates for Dresden Unit 3 Refuel 25 Framatome fuel loading per EC 622013.
18-01 O Revision to UFSAR Section 3.9 Revised pages 3.9-1 and 3.9-43 to add use of later ASME Code Editions and Addenda per EC 623180.18-011 Revision to UFSAR Section 3.11 Revised page 3.11-5, page 3.11-6 and table 3.11-2 to take an exception to the post-accident mild temperature criterion of less than or equal to 120 degrees Fahrenheit per EC 625940.
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Attachment B Dresden Nuclear Power Station FPR Amendment 22 Change Summary Report 12-006 Revision to FPR, Volume 1, Section 4.15.8 and 5.6.18 Revised pages 4.15-8 and 5.6-22 to add methane detection and fast-acting isolation valves to the boiler house fire hazard analysis and BTP compliance.16-001 Revision to FPR, Volume 2, Appendix B Revised pages B-6, B-11, and B-30 to reflect a motor operated valve changed to a manual valve and to indicate the manual valve has no spurious operation concern.17-005 Revision to FPR, Volume 1, Section 4.7.1, 4.8.5, and 4.10.7; Volume 2, Section 3.1 Revised pages 3.1-19, 3.1-28, 3.1-32, 3.1-33, 3.1-36, 3.1 -39, 3.1-42, 4.7-1 , 4.8-7, and 4.10-9 to remove flow indicators that are not required for safe shutdown.17-006 Revision to FPR, Volume 1, Section 3.6 Revised pages 3.6-9 and 3.6-10 to replace recommended actions with implemented measures for beam fire protection.17-007 Revision to FPR, Volume 2, Section 7.6.1.4 and 7.6.2 Revised page 7.6-3 to provide updates to communication capabilities during post-fire safe shutdown.17-008 Revision to FPR , Volume 4 Revised page IV-2-1 and added Tab J to include the reference, " Evaluation of Dresden Station Combustible Loading Limits," dated 10-26-1994.17-009 Revision to FPR, Volume 2, Section 3.1, 4.2, 4.5, 4.7, 4.8, 4.9, 4.10, 4.12, 4.13, 6.2, 7.3 Revised pages 3.1-2, 3.1-6, 4.2-1 , 4.5-1 , 4.7-1 , 4.8-1, 4.9-1 , 4.10-1 , 4.12-1 , 4.13-1 , 4.13-2, 6.2-3, 6.2-7, 7.3-2, 7.3-13; and figure 3.1-2 sheet 1 and 2 to add information on fire water providing backup cooling for CRD pumps.18-001 Revision to FPR, Volume 2, Section 3.1.1.1.3 and 3.1.1.1.5 Revised pages 3.1-4, 3.1-5, 3.1-19, 3.1-23, 3.1-28, 3.1-32, 3.1-36, 3.1-46, 3.1-50 to update the FPR on Clean Demin Tank Level indication .18-004 Revision to FPR, Volume 4 Revised page IV-2-1 and added Tab K to reference an 86-1 O Fire Protection Evaluation, "Evaluation on Fire Barrier Through-Wall Bolts."
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Attachment C Dresden Nuclear Power Station 10 CFR 50.59 Evaluation Summary Report Safety Evaluation Number: 2018-10-01 Type of Safety Evaluation: Temporary Alteration Evaluation Reference Number: EC 625972
Title:
Temporary Disable Trip Circuits for RAT TR32 & TR22 Open Phase Detection
==
Description:==
The proposed activity to temporary disable the trip circuits on the open phase protective relays is being performed to mitigate inadvertent plant tripping due to a false trip signal. This will allow additional time to monitor the open phase protective relays.
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Attachment D Dresden Nuclear Power Station Technical Requirements Manual Change Summary Report 15-002 Revision to TRM Appendix A Revised page A-11 to add Unit 2 Feedwater test taps piping to improve the reliability and success of Local Leak Rate Testing (LLRT).15-013 Revision to TRM Appendix A and Appendix B Revised pages A-28 and B-2 to add new Unit 3 Primary and Secondary Containment isolation valves and rupture disc.16-001 Revision to TRM Appendix A Revised page A-25 to add Unit 3 Feedwater test taps piping to improve the reliability and success of LLRT.16-006 Revision to TRM Appendix B Revised page B-2 to add new Unit 2 Secondary Containment isolation valves and rupture disc.17-001 Revision to TRM Appendix A Revised page A-15 to add new Primary Containment isolation valve.17-002 Revision to TRM Section 3.4.a Revised page 3.4.a-1 to remove Required Actions A.3 and A.4.17-003 Revision to TRM Section 3.3.d Revised page 3.3.d-3 to revise the Allowable Value for Unit 2 Reactor Vessel Water Level Low.17-005 Revision to TRM Section 3.3.d Revised page 3.3.d-3 to revise the Allowable Value for Unit 3 Reactor Vessel Water Level Low.17-008 Revision to TRM Appendix B Revised pages B-2 and B-3 to list new secondary containment barrier blind flanges and isolation valves.17-009 Revision to TRM Section 3.0, B3.0, B3.7.j, and 83.7.k Revised pages 3.0-2, 83.0-7, 83.0-8, 83.0-9, 83.0-10, 83.0-11, B3.0-12, B3.0-13, B3.7.j-1, B3.7.j-2, B3.7.k-1 , B3.7.l-1, and B3.7.n-1 for editorial and formatting corrections.17-010 Revision to TRM Section 3.7.a, 3.7.c, and B3.7.a Revised pages 3.7.a-1, 3.7.c-1, and 83.7.a-1 to revise Applicability.17-015 Revision to TRM Appendix E Updated Appendix E to include Dresden 2 COLR Revision 17 for D2C26.17-016 Revision to TRM Section 3.7.j and 3.7.o Revised pages 3.7.j-2, 3.7.j-3, 3.7.o-2, 3.7.o-3, and 3.7.o-4 for editorial and formatting corrections.
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Attachment D Dresden Nuclear Power Station Technical Requirements Manual Change Summary Report 18-002 Revision to TRM Section 3.7.f Revised page 3.7.f-1 to remove Condition B.18-004 Revision to TRM Section 1.3 1 3.0 1 and B3.0 Revised pages 1.3-1, 1.3-2, 1.3-3, 1.3-4, 3.0-3, B3.0-1, B3.0-3, B3.0-4, B3.0-7, B3.0-12, and B3.0-13 to revise wording similar to Technical Specification Change through License Amendment 255 (Unit 2) and 248 (Unit 3).18-005 Revision to TRM Section 5.0.b Revised page 5.0.b-4 to remove reference to a procedure that is no longer active.18-007 Revision to TRM Section 3.3.d Revised page 3.3.d-2 to extend the frequency of TSR from 24 months to 48 months.18-009 Revision to TRM Appendix F Updated Appendix F to include Dresden 3 COLR Revision 16 for D3C26.18-013 Revision to TRM Section 3.7.h. 5.0.b, and B3.7.h Revised pages 3.7.h-1, 3.7.h-2, 5.0.b-4, B3.7.h-1, and B3.7.h-2 to remove Conditions and Required Actions from the TRM since Technical Specification LCO 3.0.8 was issued to address conditions and actions for snubbers support function(s).19-001 Revision to TRM Section B3.0 Revised pages B3.0-2 and B3.0-12 to delete the term "operational convenience."19-004 Revision to TRM Section 3.7.i Revised pages 3.7.i-5 to change TSR 3.7.i.14 frequency from 36 months to 60 months.19-007 Revision to TRM Section 3.7.n Revised pages 3.7.n-3, 3.7.n-5, and 3.7.n-6 to extend inspections from 18 months to 36 months.
Revisions to TRM Appendix I as part of the Surveillance Frequency Control Program 17-004: SRs 3.3.1.1.5 and 3.3.1.1.8 extended from 31 days to 92 days. SR 3.1.4.2 extended from 120 days to 200 days.
17-006: SR 3.8.4.4 extended from 24 months to 48 months.
17-007: SR 3.7.4.1 extended from 31 days to 92 days.
17-01 O: Added new SRs for 3.3.5.1 and 3.5.2. Renumbered SR from 3.3.5.2 to 3.3.5.3.
17-011: SR 3.3.5.1.2 functions 4.d, 4.e, 5.d, 5.e extended from 92 days to 184 days.
SR 3.3.5.1 functions 4.d, 4.e, 5.d, 5.e extended from 92 days to 184 days.
17-012: SR 3.8.4.4 extended from 24 months to 48 months.
17-013: SR 3.6.1.3.7 for DIS 0500-14, DIS 0500-15, DIS 0500-16, DIS 0500-17, DIS 0500-18, DIS 0500-22, and DIS 0500-28 extended from 24 months to 48 months.
17-014: SR 3.3.5.1.6 function 2.c and 2.d extended from 24 months to 48 months. SR 3.3.5.1.5 function 4.c and 5.c extended from 24 months to 48 months. SR 3.3.5.1.6 function 4.c and 5.c extended from 24 months to 48 months. SR 3.3.6.3.3 extended from 24 months to 48 months. SR 3.5.1.9 extended from 24 months to 48 months.
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Attachment D Dresden Nuclear Power Station Technical Requirements Manual Change Summary Report 18-001: SR 3.3.5.1.5 function 4.c and 5.c extended from 24 months to 48 months. SR 3.3.5.1.6 function 1.b, 2.a, 2.b, 2.c, 2.d, 2.e, 2.f, 2.g, 2.h, 2.i, 2.j, 2.k, 3.a, 3.b, 3.c, 3.d, 3.e, 3.f, 3.g, 4.c, and 5.c extended from 24 months to 48 months. SR 3.3.6.3.3 extended from 24 months to 48 months. SR 3.5.1.8 extended from 24 months to 48 months. SR 3.5.1.9 extended from 24 months to 48 months. SR 3.6.1.6.2 extended from 24 months to 48 months.
18-003: SR 3.1.3.3 extended from 31 days to 92 days.
18-006: SR 3.3.6.1.2 function 2.c and 6.a extended from 92 days to 12 months.
18-008: Added new SRs for 3.5.2.
19-009: SR 3.3.1.1.11 function 2.b, 2.c, and 2.d extended from 92 days to 12 months.
19-01 O: SR 3.3.5.1.2 function 3.f extended from 92 days to 12 months. SR 3.3.5.1.4 function 3.f extended from 92 days to 12 months.
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Attachment E Dresden Nuclear Power Station Summary of Regulatory Commitment Changes In accordance with the guidance provided in Nuclear Energy Institute (NEI) 99-04, Revision 0, "Guidelines for Managing NRC Commitment Changes," dated July 1999, Dresden Nuclear Power Station changed the following regulatory commitment during the period of January 1, 2015 through December 31, 2016, which requires notification to the NRC.
Commitment Original Commitment Revised Commitment Basis for Revision Revision No.
N/A Letter RS-04-046, dated Late performance of Based on review of VT-3 March 25, 2004, commitment. tests performed in the Additional Information applicable population of for the Review of the
Reference:
components subject to License Renewal Issue Report (IR) the environmental Applications for 4157186 and conditions specified in Dresden Nuclear Power IR 04164804 Aging Management Station, Units 2 and 3 Program B.2.9, it was and Quad Cities determined that the Nuclear Power Station , station failed to meet the Units 1 and 2 requirement of performing a VT-3 test on such a component NUREG 1796, Safety prior to the period of Evaluation Report extended operation on Related to the License U3, which began on Renewal of the Dresden January 12, 2011.
Nuclear Power Station, Units 2 and 3 and Quad WO 00881011-01 , under Cities Nuclear Power which a VT-3 inspection Station, Units 1 and 2 of AOV 3-2301-64 took
- Section 3.0.3.18, place, was performed on Periodic Inspection March 23, 2011.
of Components Additionally, it was Subject to Moist confirmed that the Environments original component to (B.2.9) have a VT-3 inspection performed to meet the requirement of the license renewal commitment, the 3-2301-STPV, received a VT-3 inspection under WO 99207970-01 on November 12, 2012.
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Attachment F Dresden Nuclear Power Station 10 CFR 54.37(b) Aging Management Review Summary In accordance with 10 CFR 54.37(b) and the guidance specified in Regulatory Issue Summary 2007-16, Revision 1, "Implementation of the Requirements of the 10 CFR 54.37(b) for Holders of Renewed Licenses," the UFSAR update required by 10 CFR 50.71 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. This UFSAR update must describe how the effects of aging will be managed such that the intended function(s) in 10 CFR 54.4(b) will be effectively maintained during the period of extended operation.
The 10 CFR 54.37(b) review of changes to the plant Current Licensing Basis covered the period of February 28, 2017 to April 1, 2019. The review included:
- Interviews of Program Managers/SME's,
- Engineering Changes that were installed or completed since the last UFSAR update ,
- Changes to component classifications,
- UFSAR pending change descriptions and revised text,
- NRC Interim Staff Guidelines (ISGs) related to license renewal , and
- Licensing Correspondence to and from the NRC.
No "newly identified" SSCs were identified that require aging management or evaluation of TLAA's in accordance with the License Renewal Rule. Therefore , there are no associated updates required to the Dresden UFSAR described Aging Management Programs.
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Attachment G Dresden Nuclear Power Station CD-ROM Directory Structure Directory Path File Name Size D:\001 DRE UFSAR REV 13 000 List of Affected Pages.pdf 112 KB D:\001 DRE UFSAR REV 13 001 CHAP 01 lntroduction.pdf 348 KB D:\001 DRE UFSAR REV 13 002 CHAP 02 Site Characteristics.pdf 1510 KB D:\001 DRE UFSAR REV 13 003 CHAP 03 Desiqn of SCE.pdf 7300 KB D:\001 DRE UFSAR REV 13 004 CHAP 04 Reactor.pdf 4833 KB D:\001 DRE UFSAR REV 13 005 CHAP 05 Reactor Coolant Sys.pdf 2375 KB D:\001 DRE UFSAR REV 13 006 CHAP 06 Enqineered Safety Features.pdf 6265 KB D:\001 DRE UFSAR REV 13 007 CHAP 07 Instrumentation and Controls.pdf 6249 KB D:\001 DRE UFSAR REV 13 008 CHAP 08 Electrical Power.pdf 7663 KB D:\001 DRE UFSAR REV 13 009 CHAP 09 Auxiliary Systems.pdf 3227 KB D:\001 DRE UFSAR REV 13 01 O CHAP 1O Steam and Power Conv Sys.pdf 384 KB D:\001 DRE UFSAR REV 13 011 CHAP 11 Radioactive Waste Mgmt.pdf 7676 KB D:\001 DRE UFSAR REV 13 012 CHAP 12 Radiation Protection.pdf 326 KB D:\001 DRE UFSAR REV 13 013 CHAP 12 Fiqures.pdf 35294 KB D:\001 DRE UFSAR REV 13 014 CHAP 13 Conduct of Operations.pdf 168 KB D:\001 DRE UFSAR REV 13 015 CHAP 14 Initial Test Program.pdf 596 KB D:\001 DRE UFSAR REV 13 016 CHAP 15 Accident and Transient Analysis .pdf 2740 KB D:\001 DRE UFSAR REV 13 017 CHAP 16 Technical Specifications.pdf 44 KB D:\001 DRE UFSAR REV 13 018 CHAP 17 Quality Assurance.pdf 53 KB D:\001 DRE UFSAR REV 13 019 APP A UFSAR Supplement.pdf 190 KB D:\002 DRE FPR AMEND 22 001 DRE FPR VOL 1 Updated Fire Hazards Analysis.pdf 5360 KB D:\002 DRE FPR AMEND 22 002 DRE FPR VOL 2 Safe Shutdown Analysis.pdf 5134 KB D:\002 DRE FPR AMEND 22 003 DRE FPR VOL 3 Part 1 of 2.pdf 33371 KB D:\002 DRE FPR AMEND 22 004 DRE FPR VOL 3 Part 2 of 2.pdf 37109 KB D:\002 DRE FPR AMEND 22 005 DRE FPR VOL 4.pdf 40822 KB D:\002 DRE FPR AMEND 22 006 DRE FPR VOL 5.pdf 23917 KB D:\002 DRE FPR AMEND 22 007 DRP FPR Affected Paqe List 63 KB D:\003 DRE TRM 001 DRE TRM.pdf 2614 KB D:\004 DRE TECH SPEC BASES 001 DRE Tech Spec Bases.pdf 2226 KB Page 1 of 1