ML21179A036
| ML21179A036 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/21/2021 |
| From: | Gullott D Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML21179A042 | List:
|
| References | |
| RS-21-066 | |
| Download: ML21179A036 (15) | |
Text
~,* Exelon Generation0 RS-21-066 10 CFR 50.71(e) 10 CFR 50.59 10 CFR 54.37(b)
June 21, 2021 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Dresden Nuclear Power Station, Units 1, 2, and 3 Facility Operating License Nos. DRP-2, (Renewed) DPR-19 and DPR-25 NRC Docket Nos.50-010, 50-237, and 50-249
Subject:
Dresden Updated Final Safety Analysis Report (UFSAR), Revision 14 and Fire Protection Report (FPR), Amendment 23 In accordance with the requirements of 10 CFR 50.71, "Maintenance of records, making of reports," Paragraph (e)(4), Exelon Generation Company (EGC), LLC submits Revision 14 to the Updated Final Safety Analysis Report (UFSAR) for Dresden Nuclear Power Station, Amendment 23 to the Fire Protection Report (FPR), summaries of evaluations conducted pursuant to 10 CFR 50.59, "Changes, tests, and experiments," 10 CFR 54.37(b), "Additional records and recordkeeping requirements," and NEI 99-04, "Guidelines for Managing NRC Commitment Changes."
The UFSAR is being submitted on Optical Storage Media (OSM) in its entirety, including documents incorporated by reference (Technical Specifications Bases, Technical Requirements Manual (TRM) and FPR). UFSAR pages changed as a result of this update are delineated with "Rev. 14 -June 2021" in the page header. FPR pages changed as a result of this update are delineated with "Amendment 23" in the page header.
Attachment A provides a brief summary of the changes incorporated into UFSAR Revision 14.
Attachment 8 provides a brief summary of the changes incorporated into FPR Amendment 23.
Attachment C provides the summary report pursuant to 10 CFR 50.59(d)(2).
Attachment D provides a summary of changes to the TRM.
Attachment E provides a summary of regulatory commitment changes.
Attachment F provides the summary report pursuant to 10 CFR 54.37(b).
fioo?,
Attachment G contains the directory path, filename, and size of each individual file.
- 4-D53 NfJf 55DI
- J;f I
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RS-21-066 June 21, 2021 U.S. Nuclear Regulatory Commission Page2 One (1) OSM is included in this submission. The OSM labeled, "Exelon Generation - Dresden Nuclear Power Station UFSAR Revision 14, June 2021 contains the following four components:
001 DRE UFSAR REV 14.pdf, 87.2 megabytes (MB) 002 DRE FPR AMEND 23.pdf, 186MB 003 DRE TRM.pdf, 2.32 MB 004 DRE TECH SPEC BASES.pdf, 2.19 MB As required by 10 CFR 50.71 (e)(2)(i), I certify that to the best of my knowledge, the information contained in the enclosure and-attachments to this *letter accurately reflect information and analyses submitted to the NRC or prepared pursuant to NRC requirements, and changes made under the provisions of 10 CFR 50.59.
There are no commitments made in this document. Should you have any questions concerning this letter, please contact:
Amy Hambly Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 Phone: (630) 657-2808 E-mail: amy.hambly@exeloncorp.com Respectfully, Gullott, David;,-1Dav1dM.
Dig~llysignedbyGullott, M* / .:Date:2021.06.2113:56:07
-05'00' David M. Gullatt Director - Licensing
Enclosure:
OSM - Dresden Nuclear Power Station UFSAR, Revision 14 Attachments: Attachment A, "UFSAR Revision 14 Change Summary Report" Attachment B, "FPR Amendment 23 Change Summary Report" Attachment C, "1 O CFR 50.59 Evaluation Summary Report" Attachment D, "Technical Requirements Manual Change Summary Report" Attachment E, "Summary of Regulatory Commitment Changes" Attachment F, "10 CFR 54.37(b) Aging Management Review Summary" Attachment G, "OSM Directory Structure" cc: Regional Administrator- NRC Region Ill NRC Senior Resident Inspector - Dresden Nuclear Power Station
Attachment A Dresden Nuclear Power Station UFSAR Revision 14 Change Summary Report 15-006 Revision to UFSAR Section 5.4 Revised Section 5.4.1.2.2 to indicate all four Reactor Recirculation pumps have the fourth-generation impellers per Engineering Change (EC) 399512.17-005 Revision to UFSAR Section 8.3 Figures Revised Figures 8.3-4, 8.3-5, 8.3-6, and 8.3-7 to add a note that electrical loading is tracked in a load tracking database and supported design analyses.17-009 Revision to UFSAR Section 9.1 Revised Sections 9.1.4.2.1 and 9.1.4.2.1.1 to reflect increased maximum motion speeds of the Unit 2 Refuel Bridge main hoist, bridge, and trolley per EC 617941.18-001 Revision to UFSAR Section 9.1 Revised Sections 9.1.4.2.1 and 9.1.4.2.1.1 to reflect increased maximum motion speeds of the Unit 3 Refuel Bridge main hoist, bridge, and trolley per EC 617942.18-006 Revision to UFSAR Sections 1.2. 3.1. 8.2. and 8.2 Figures Revised Sections 1.2.2.10, 1.2.2.11, 3.1.2.2.8, 8.2.1.1.1, 8.2.1.3.2, and 8.2.2.2; and Figures 8.2-1 and 8.2-2 to reflect changes to the switchyard transmission line 93505 per EC 620184.19-001 Revision-to UFSAR Sections 8.3. 11.3. and 15.7 Revised Sections 8.3.1.5.2, 11.3.2.1.2.11, and 15:7.1 to replace operational convenience wording.19-002 Revision to UFSAR Sections 1.2. 3.1, 8.2. and 8.2 Figures Revised Sections 1.2.2.10; 1.2.2.11, 3.1.2.2.8, 8.2.1.1.1, 8.2.1.3.2, and 8.2.2.2; and Figures 8.2-1 and 8.2-2 to reflect interim changes supporting the UFSAR change 18-006 for the switchyard transmission line chang~s.19-004 Revision to UFSAR Section 3.5 Revised Sections 3.5.4 and 3.5. 7 to clarify design basis information for the type of missiles that Dresden is committed to protect against in the event of natural phenomena, to add reference to the Dresden Individual Plant Examination of External Events for Severe Accident Vulnerabilities Submittal Report (IPEEE), and to add reference to the NRC review of the IPEEE.19-006 Revision to UFSAR Sections 6.2, 6.3, 6.3 Tables, and 15.0 Revised Sections 6.2.8, 6.3, 6.3.2.1.1, 6.3.2.1.4.2, 6.3.2.1.4.2, 6.3.2.2.2, 6.3.2.2.3.1, 6.3.2.2.3.4, 6.3.2.3, 6.3.2.3.3.2, 6.3.2.4.2, 6.3.3.1.3.1, 6.3.3.1.4, 6.3.3.1.4.2, 6.3.3.2.1.1, 6.3.3.3.2, 6.3.3.3.2.2, 6.3.3.3.5.1, 6.3.3.3.5.3, 6.3.3.3.6.3, 6.3.3.3.7 .3, 6.3.3.4.1, 6.3.5, 15.0.1.1, 15.0.1.2, ,
15.0.1.3, 15.0.2.2, and 15.0.2.4; and Tables 6.3-1, 6.3-4b, 6.3-12e, 6.3-13c, 6.3-19c, and 6.3-20b to reflect the new Loss of Coolant Accident (LOCA) and Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) analysis with increased Automatic Depressurization System flow and to support use of the Infrequent Event categorization for loss parts capable for causing high percentage of flow orifice blockage.19-007 Revision to UFSAR Section 6.2 Revised Section 6.2.3.4 to indicate secondary containment leak rate testing is in accordance with the surveillance frequency control program.
Page 1 of 3
Attachment A Dresden Nuclear Power Station UFSAR Revision 14 Change Summary Report 19-008 Revision to UFSAR Section 10.4 Revised Section 10.4.7 to reflect the installation of suction strainers on the Unit 2 Reactor Feed Pumps per EC 628890.
19-01 O Revision to UFSAR Appendix A Revised Appendix A section A.1.1 O to add guidance from BWRVIP-234-A and EPRI Letter 2017-030.19-013 Revision to UFSAR Section 9.5 Revised Section 9.5 to reflect standardized radiological emergency plan organization staffing requirement changes.19-014 Revision to UFSAR Section 15.6 and 15.6 Tables Revised Sections 15.6.5.5.3.1 and 15.6.6; and Table 15.6-14 to reflect post LOCA dose analysis changes per EC 626918.19-015 Revision to UFSAR Section 5.4 Revised Section 5.4.6.4 to reflect changing* design heat removal testing from 5 years to 10-years.20-001 Revision to UFSAR Sections 6.2. 6.3, 15.6, and 15.6 Tables Revised Sections 6.2.2.1, 6.2.2.2, 6.2.3.2.4, 6.2.3.3, 6.3.2.2, 6.3.3.4.1, 6.5.3, 15.6.5.5.3, and 15.6-10, and 15.6-11; and Tables 15.6-12, 15.6-13, 15.6-14, 15.6-1515.6.5.5.4 to reflect increased main steam isolation valves (MSIV) limits and separates total containment leakage allowable from MSIV leakage as related to the*Appendix J testing per EC 628318 and adopted Technical Specification changes associated with TSTF-561.
20-'002 Revision to UFSAR Section 15.6 and 15.6 Tables Revised Section 15.6.6 and Table 15.6-17 to reflect post LOCA dose analysis changes per EC 627861.20-003 Revision to UFSAR Section 6.2 Revised Section 6~2.4.4 to indicate MSIV testing is in accordance with the surveillance frequency control program.20-004 Addition of UFSAR Section 13.1 Revised Section 13.1.8 to reflect Quality Assurance Topical Report (QATR) commitment to ANSI/ANS 3.1-2014.20-006 Revision to UFSAR Section 9.2 Revised Sections 9.2.5, 9.2.5.3, and 9.2.5.3.1 to reflect description of the plant response and actions following failure of the Dresden Lock and Dam.20-007 Revision to UFSAR Section 3.9 Tables Revised Tables 3.9-2 and 3.9-14 to reflect editorial changes.
Page 2 of 3
Attachment A Dresden Nuclear Power Station UFSAR Revision 14 Change Summary Report 20-009 Revision to UFSAR Chapters 1, 4, 6, 7. 10, 15 Revised Sections 3.9.5.3.4, 4.1, 4.2.1.1, 4.2.2, 4.2.2.1, 4.2.2.3.2, 4.2.2.3.3, 4.2.3, 4.2.3.1.1, 4.2.3.1.2, 4.2.3.1.3, 4.2.3.3.4, 4.4.1.1, 4.4.1.3.3, 4.4.4.1.1, 4.4.4.1.2, 4.4.4.2.3, 4.4.4,2.4, 5.4.8.1, 5.4.16, 6.2, 6.3, 6.3.2.1.1, 6.3.2.1.4.1, 6.3.2.1.4.2, 6.3.2.2.2, 6.3.2.2.3.1, 6.3.2.2.3.4, 6.3.2.3, 6.3.2.3.3.2, 6.3.3.1.3.1, 6.3.3.1.4, 6.3.3.1.4.2, 6.3.3.2.1.1, 6.3.3.3.2, 6.3.3.3.2.2, 6.3.3.3.5.1, 6.3.3.3.6.3, 6.3.3.3.7.3, 6.3.3.4.1, 7.8.1, 10.4.7.2.1, and 15.0; and Tables 1.2-1, 4.1-1, 4.1-3, 6.3-4b, 6.3-12e, 6.3-13c, 6.3-19c, and 6.3-20b to reflect changes and implementation of a new LOCA and MAPLHGR analysis for Unit 3.
20-01 O Revision to UFSAR Section 6.3 and 6.3 Figures Revised Sections 6.3.3.4.3.3 and 6.3.3.4.3.4; and Figures 6.3-83 and 6.3-84 to reflect changes regarding the Wetwell pressure response to a long-term design basis accident LOCA and the containment pressure required to maintain adequate net positive suction head for the Core Spray and* Low Pressure Core Injection pumps, The UFSAR was* updated, to match the values in the current licensing basis and revised calculations.20-011 Revision to UFSAR Sections 3.4. 3.5, 3:6, 3.11 Revised Sections 3.4.3, 3.5.7, 3.6.3, and 3.11.6 to reflect adding new Technical Specification limiting condition for operation 3.0.1 O.21-002 Revision to UFSAR Section 8.3 Revised* Sections 8.3.2.1.1 and 8.3.2.2.1 to correct a legacy error wording related to 250-volt and 125-volt systems.
Page 3 of 3
AMENDMENT 23 April 2021 Attachment B Dresden Nuclear Power Station FPR Amendment 23 change Summary Report Revision Summary:
Fire Protection Report Change Packages19-002, 19-003,20-001, 20-002 & 21-001 update Amendment 23 of the Fire Protection Report. The revisions associated with this update include:
Volume 1 (Fire Hazards Analysis):
- 1. Change 19-002: EC 628992-edited the description of the Reactor Building Roofing System to reflect the original/current configuration, which is a built-up roofing on top of pre-cast concrete panels. (Sections 4.2.6 & 4.5.6).
- 2. Change 20-002: EC 633231-edited to reflect remoyal of fire hose at frre hose stations and use ofHigh-Rise Packs. (Sections 1.4, 2.1.2, 2.4.4.1, 5.5 and 5.6)
Volume 2 (Safe Shutdown Report):
- 1. Change 20-001: IR4304481-added clarification to the 2/3 Diesel Generator Cooling Water Pump firewrap (Section 6.3.5 on p.6.3-15).
Volume 4 (Interim Measures/Exemption Requests):
- 1. Change 19-003: EC 629568-added evaluation on the acceptability of Smoke Detector 2-4135-323 in the MCR kitchen being in close proximity to a supply air duct. (Section IV, p.IV-2-i and added Tab L).
- 2. Change 21-001: ECs 630156/633234 & 631956--added eval~tions of failed sprinkler head analyses and their impact on DRE96-0145 and DRE97-0256.
(Section IV, p.IV-2-i and added Tabs Mand N).
- 3. Change 20-002: EC 633231-added evaluation on replacing stationary fire hoses at hose stations with portable High-Rise Packs. (Section IV, p.IV-2-i and added TabO).
Page 1 of 1
Attachment C Dresden Nuclear Power Station 10 CFR 50.59 Evaluation Summary Report Safety Evaluation Number: 2019-04-001 Type of Safety Evaluation: Modification Evaluation Reference Number: EC 627310 and EC 627311
Title:
Modify Fuel Pool Cooling Pump Trips
==
Description:==
These modifications affect several trips associated with the Fuel. Pool Cooling (FPC) Pumps 2(3)-1902A/B. Specifically, these modifications change the pressure switch style utilized for the low pump suction pressure trip (2(3)-1901-108A/B) to a more reliable design and removes the trips associated with FPC Skimmer Surge Tank low-low level (2(3)-1901-106) and Fuel Pool Filter high inlet pressure (2(3)-1901-700) for the 2(3)A & B FPC Pumps.
Safety Evaluation Number: 2019-09-001 Type of Safety Evaluation: Temporary Alteration Evaluation Reference Number: EC 629532 / WO 4964530
Title:
Defeat the Automatic Turbine Trip from the 2C Moisture Separator Level Switch 2-3451-54C
==
Description:==
Temporary configuration change package (TCCP) issued to provide guidance and documentation for forcing the logic bit in the digital electro-hydraulic control (DEHC) for the 2-3451-.:54C high level alarm switch. This prevents a spurious trip of the Unit 2 turbine due to the degraded condition of the level switch circuit.
Safety Evaluation Number: 2019-09-002 Type of Safety Evaluation: Modification Evaluation Reference Number: EC 628890
Title:
Installation of a Reactor Feed Pump (RFP) Suction Strainers on Unit 2
==
Description:==
Each of the three (3) Reactor Feed Pumps (RFP) are equipped with a 2'-7" long flanged spool piece in the 20" suction supply piping that was originally installed to accommodate a temporary strainer. These flanged spool pieces will be removed and replaced with flanged strainer assemblies equipped with a removable basket with a 20 mesh screen liner (which has 0.0331 inch openings). The new strainers are equipped with 3/4" differential pressure taps and a differential pressure indicator will be installed on a stand locally near the added strainers.
Page 1 of 3
Attachment C Dresden Nuclear Power Station 10 CFR 50.59 Evaluation Summary Report Safety Evaluation Number: 2019-12-001 Type of Safety Evaluation: Temporary Alteration Evaluation Reference Number: EC624702
Title:
Provide Temp Hydrogen and Oxygen Supply During Relocation of Supply Lines
==
Description:==
Provides details to implement temporary alternate supply of Hydrogen and Oxygen gas to Turbine Generator Casing Hydrogen cooling and Hydrogen Water Chemistry subsystems at Dresden while the normal supply from the Hydrogen/Oxygen tank farm is removed from service for maintenance performed under a separate activity.
Safety Evaluation Number. 2020-05-001
- Type of Safety Evaluation: Modification Evaluation Reference Number: EC 630570
Title:
Installation of a Reactor Feed Pump (RFP) Suction Strainers on Unit 3
==
Description:==
Each of the three (3) Reactor Feed Pumps (RFP) are equipped with a 2'-7" long flanged spool piece in the 20" suction supply piping that was originally installed to accommodate a temporary strainer. These flanged spool pieces will be removed and replaced with flanged strainer assemblies equipped with a removable basket with a 20 mesh screen liner (which has 0.0331 inch openings). The new strainers are equipped with 3/4" differential pressure taps and a differential pressure indicator will be installed on a stand locally near the added strainers.
Safety Evaluation Number: 2020-02-001 Rev O and 2020-02-001 Rev 1 (2020-06-001)
Type of Safety Evaluation: FSAR Change Evaluation Reference Number: UFSAR Change DFL 20-006
Title:
Update to UFSAR Section 9.2.5.3.1, DOA 0010-01, and DTS 4450-04
==
Description:==
The change to the UFSAR that is being evaluated is the description of the UHS water inventory in Section 9.2.5.3.1, "Dam Failure During Normal Plant Operation." There are no physical changes that are being made to the topography or structure of the UHS. This change is being made to account for the variation in the annual determination of the trapped volume of water in the Dresden Intake canal. that would be available for use for after a dam failure event.
Page 2 of3
Attachment C Dresden Nuclear Power Station 10 CFR 50.59 Evaluation Summary Report Safety Evaluation Number: 2020-08-001 Type of Safety Evaluation: Modification Evaluation Reference Number: EC 631971 and EC 631972
Title:
Install Switches to Bypass the Fuel Pool Cooling Pump Trips
==
Description:==
The proposed activity modifies the Low Suction Pressure Trips associated with the Fuel Pool Cooling(FPC) Pumps 2(3)-1902-A/R Specifically, the modifications install two switches (one for each pump) for each Unit to bypass trips associated with the Fuel Pool Cooling Low Suction Pressure Trips during 'Refueling Outage as needed to reduce the potential for loss of the Fuel Pool Cooling (FPC) system.
Safety Evaluation Number: 2021-03-01 Type of Safety Evaluation: Temporary Alteration Evaluation Reference Number: EC 633771
Title:
Temporary Force Unit 2 DEHC Logic Point
==
Description:==
This proposed Temporary Change activity is forcing Digital Electrohydraulic Control (DEHC) Main Steam Throttle Pressure Control input sensor "A" digital point P1\bp_msp1 to a flXed value.
Page 3 of3
Attachment D Dresden Nuclear Power Station Technical Requirements Manual Change Summary Report 16-004 Revision to TRM Section 3.7.m and Bases Revised TRM 3.7.m to reflect changing TRM Surveillance Requirement (TSR) related to safe shutdown lighting emergency light batteries testing and replacement.19-006 Revision to TRM Section 3.7.j Revised TRM 3. 7 .j to reflect updates to a tiered fire watch frequency based on the risk of each individual suppression system poses to the station when impaired.19-012 Revision to TRM Appendix A Revised TRM Appendix A to reflect removing valves from the Primary Containment Isolation Valve list.19-013 Revision to TRM Section 3.7.i Revised TRM 3.7.j to reflect changing TSR frequencies related to fire protection water suppression systems.19-026 Revision to TRM Section 3.3.a Revised TRM 3.3.a to reflect changing TSR frequencies related to control rod block instrumentation channel functional test and calibration.19-032 Revision to TRM Appendix E Updated Appendix E to include Dresden 2 COLR Revision 18 for D2C27.19-033 Revision to TRM Section 3.7.m Revised TRM 3.7.m to reflect reclassifying a safe shutdown light.19-034 Revision to TRM Section 3. 7.i Revised TRM 3. 7.i to reflect removing a TSR related to fire protection water supply system.20-002 Revision to TRM Section 3. 7.1 Revised TRM 3.7.1 to reflect changing TSR frequency related to fire protection hose stations.20-003 Revision to TRM Section 3.6.a and Appendix I Removed TRM 3.6.a to reflect the new Technical Specification 3.6.2.6, Drywell Spray.
The TRM Appendix I change is described below as part of the Surveillance Frequency Control Program.20-004 Revision to TRM Section 3. 7.1 Revised TRM 3.7.1 to reflect changing TSR frequency related to fire protection hose stations.20-009 Revision to TRM Appendix F Updated Appendix F to include Dresden 3 COLR Revision 17 for D3C27.
Page 1 of3
Attachment D Dresden Nuclear Power Station Technical Requirements Manual Change Summary Report Revisions to TRM Appendix I as part of the Surveillance Frequency Control Program (SFCP) 19-002: Frequency extended from 92 days to 12 months for SR 3.3.1.1.11 function 9.
19-003: Made an administrative correction to SR 3.3.6.1.2.
Frequency extended from 92 days to 24 months for SR 3.3.1.1.11.
19-008: Revised the description of SR 3.3.1.1.2.19-011 : Frequency extended from 92 days to 12 months for:
SR 3.3.6.1.2 function 3'.a
- SR 3.3.6.1.3 function 3.a 19-014: Frequency extended from 92 days to 12 months for:
SR 3.3.2.2.2 SR 3.3.2.2.3 SR 3.3.4.1.2 function a SR 3.3.4, 1.3 function a SR 3.3.5.1.2 function 1.a, 2.a, 3.a, 3.c, 4.a, and 5.a SR 3.3.5.1.3 function 1.a, 2.a, 3.a, 3.c, 4.a, and 5.a 19-015: Frequency extended from 92 days to 12 months for:
SR 3.3.1.1.11 functions 7.a and 7.b SR 3.3.1.1.12 functions 7.a and 7.b 19-016: Frequency extended from 92 days to 12 months for:
SR 3.3.1.1.11 function 4 SR 3.3.1.1.12 function 4 SR 3.3.5.2.2 functions 3.a and 4.a SR 3.3.6.1.2 functions 1.a, 2.a, 5.b, and 6.b SR 3.3.6.1.3 functions 1.a, 2.a, 5.b, and 6.b SR 3.3.6.2.2 function 1 SR 3.3.6.2.3 function 1 19-017: Frequency extended from 92 days to 12 months for:
SR 3.3.1.1.11 function 3 SR 3.3.1.1.12 function 3 19-018: Frequency extended from 92 days to 12 months for SR 3.3.3.1.2 function 4.b.
19-019: Frequency extended from 184 days to 24 months for SR 3.3.3.1.3 function1.
19-020: Frequency extended from 92 days to 12 months for:
SR 3.3.1.1.11 function 6 SR 3.3.1.1.13 function 6 SR 3.3.6.1.2 function 2.b SR 3.3.6.1.4 function 2.b SR 3.3.6.2.2 function 2 SR 3.3.6.2.4 function 2 Page 2 of 3
Attachment D Dresden Nuclear Power Station Technical Requirements Manual Change Summary Report 19-021: Frequency extended from 92 days to 12 months for:
SR 3.3.5.3.1 SR 3.3.5.3.2 19-022: Frequency extended from 92 days to 12 months for:
SR 3.3.6.1.2 function 3.c SR 3.3.6.1.3 function 3.c 19-023: Frequency extended from 92 days to 12 months for:
SR 3.3.5.1.2 functions 1.b, 2.b, 3.b; 4.b, and 5.b SR 3.3.5.1.4 functions 1.b, 2.b, 3.b, 4.b, and 5.b 19-024: Frequency extended from 92 days to 12 months for:
SR 3.3.4.1.2 function b SR 3.3.4.1.3 function b 19-025: Frequency extended from 92 days to 184 days for SR 3.3.1.1.11 function 8.
19-027: Frequency extended from92 days to 12 months for:
SR 3.3.6.1.2 function 1.b and 1.c SR 3.3.6.1.4 function 1.b 19-028: Frequency extended from 184 days to 12 months for SR 3.3.3.1.3 function 2.b.
19-029: Frequency extended from 92 days to 12 months for:
SR 3.3.5.1.2 function 1.d SR 3.3.5.1.3 function 1.d SR 3.3.5.2.2 function 1.b 19-030: Frequency extended from 24 months staggered to 48 months staggered for SR 3.6.4.1.3.
19-031: Frequency extended from 92 days to 12 months for SR 3.3.6.1.2 function 3.b.
20-001: Frequency extended from 60 months to 120 months for SR 3.5.3.4.
20-003: Added the following in support of new Technical Specification 3.6.2.6, Drywall Spray:
SR 3.6.2.6.1 SR 3.6.2.6.2 SR 3.6.2.6.3 20-006: Change reflects deleted SR 3.5.2.4.
20-007: Frequency extended from 92 days to 24 months for SR 3.6.1.8.2.
Page 3 of 3
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 is submitting a summary of commitments revised that can be changed with notification to the NRC submitted along the FSAR updates as required by 10 CFR 50.71 (e).
No commitment changes were processed requiring NRC notification during the period of June 1, 2019 through May 31, 2021.
Page 1 of 1
Attachment F Dresden Nuclear Power Station 10CFR 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 ofthe 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 April 1, 2019 to March 25, 2021. The review included:
- Engineering Changes that were installed or completed since the last UFSAR update,
- UFSAR pending change descriptions and revised text, and
- NRC Interim Staff Guidelines (ISGs) related to license renewal.
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.
Attachment G Dresden Nuclear Power Station CD-ROM Directory Structure Directoo,P,atb/ :> ,* ,,:,, '\:*-, :---File Na.rne j ,_.,,_ ,)_/ ?Y?>-.> : };,;) /-_,---__ \ _'.* :; ' _-:::-,.:: ;/'X . : Size>t c ; *_
D:\001 DRE UFSAR REV 14 000 Cover and List of Affected Pages.pdf 184 KB D:\001 DRE UFSAR REV 14 001 CHAP 01 lntroduction.pdf 432KB D:\001 DRE UFSAR REV 14 002 CHAP 02 Site Characteristics.pdf 1510 KB D:\001 DRE UFSAR REV 14 003 CHAP 03 Design of SCE.pdf 6076 KB D:\001 DRE UFSAR REV 14 004 CHAP 04 Reactor.pdf 3874 KB D:\001 DRE UFSAR REV 14 005 CHAP 05 Reactor Coolant Svs.pdf 2869 KB D:\001 DRE UFSAR REV 14 006 CHAP 06 Engineered Safety Features.pdf 9549 KB 0:\001 DRE UFSAR REV 14 007 CHAP 07 Instrumentation and Controls.pdf 6318 KB D:\001 DRE UFSAR REV 14 008 CHAP 08 Electrical Power.pdf 5322 KB 0:\001 DRE UFSAR REV 14 009 CHAP 09 Auxiliary Systems.pdf 5179 KB D:\001 DRE UFSAR REV 14 01 O CHAP 1O Steam and Power Conv Sys.pdf 398 KB D:\001 DRE UFSAR REV 14 011 CHAP 11 Radioactive Waste Mgmt.pdf 6868 KB D:\001 DRE UFSAR REV 14 012 CHAP 12 Radiation Protection.pdf 35615 KB D:\001 DRE UFSAR REV 14 013 CHAP 13 Conduct of Operations.pdf 279KB D:\001 DRE UFSAR REV 14 014 CHAP 14 Initial Test Program.pdf 597KB D:\001 DRE UFSAR REV 14 015 CHAP 15 Accident and Transient Analvsis.pdf 3895 KB D:\001 DRE UFSAR REV 14 016 CHAP 16 Technical Specifications.pdf 44KB D:\001 DRE UFSAR REV 14 017 CHAP 17 Quality Assurance.pdf 53 KB D:\001 DRE UFSAR REV 14 018 APPENDIX A UFSAR Supplement.pdf 301 KB
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D:\002 DRE FPR AMEND 23 000 FPR List of Affected Pages 127 KB D:\002 DRE FPR AMEND 23 001 FPR VOL 1 Updated Fire Hazards Analvsis.pdf 4810 KB D:\002 DRE FPR AMEND 23 002 FPR VOL 2 Safe Shutdown Analvsis.pdf 6115 KB D:\002 DRE FPR AMEND 23 003 FPR VOL 3.pdf 70018 KB D:\002 DRE FPR AMEND 23 004 FPR VOL 4.pdf 85888 KB D:\002 DRE FPR AMEND 23 005 FPR VOL 5.pdf 23917 KB
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D:\004 DRE TECH SPEC BASES 001 DRE Tech Spec Bases.pdf 2243 KB Page 1 of 1