RS-19-098, Submittal of Revision 15 to Updated Final Safety Analysis Report, and Revision 24 to Fire Protection Report

From kanterella
Jump to navigation Jump to search
Submittal of Revision 15 to Updated Final Safety Analysis Report, and Revision 24 to Fire Protection Report
ML19298C430
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 10/21/2019
From: Gullott D
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML19298C434 List:
References
RS-19-098
Download: ML19298C430 (7)
v • d • e


Text

4300 Winfield Road Exelon Generation Wa rrenville, IL 60555 630 657 2000 Office RS-19-098 10 CFR 50.71 (e) 10 CFR 54.37(b)

October 21, 2019 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Quad Cities Updated Final Safety Analysis Report (UFSAR), Revision 15 and Fire Protection Report (FPR) , Revision 24 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 15 to the Updated Final Safety Analysis Report (UFSAR) for Quad Cities Nuclear Power Station ,

Revision 24 to the Fire Protection Report (FPR) , and a summary of evaluations conducted pursuant to 10 CFR 54.37(b), "Additional records and recordkeeping requirements." Summary of evaluations conducted pursuant to 10 CFR 50.59 "Changes, tests , and experiments," are submitted under separate cover.

The UFSAR is being submitted on Optical Storage Media (OSM) in its entirety, including documents incorporated by reference (Technical Requirements Manual, Technical Specifications Bases, and the FPR) . UFSAR pages changed as a result of this update are delineated with "Revision 15, October 2019" in the page footer.

Attachment A provides a brief summary of the changes incorporated into UFSAR Revision 15.

Attachment B provides a brief summary of the changes incorporated into FPR Revision 24.

Attachment C provides the summary report pursuant to 10 CFR 54.37(b) .

Attachment D contains the directory path, filename, and size of each individual file included on - J1 11 1)/p the OSM. _JtV fv6-3

/V /ZR_

October 21, 2019 U. S. Nuclear Regulatory Commission Page 2 One (1) OSM is enclosed in this submission. The OSM labeled , "Exelon Generation - Quad Cities Nuclear Power Station - UFSAR Revision 15 - FPR Revision 24 - October 2019", contains the following components:

001 QDC UFSAR Rev 15.pdf, 50.6 MegaBytes (MB) 002 QDC FPR Rev 24.pdf, 3.44 MB 003 QDC TRM .pdf, 2.80 MB 004 QDC Tech Spec Bases.pdf, 2.23 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 requ irements , and changes made under the provisions of 10 CFR 50.59.

There are no new comm itments made in this document. Should you have any questions concerning this letter, please contact:

Amy Hambly Exelon Generation 4300 Winfield Road Warrenville , IL 60555 Phone: (630) 657-2808 amy.hambly@exeloncorp.com Respectfully, David M. Gullatt Director - Licensing

Enclosure:

OSM - Exelon Generation - Quad Cities Nuclear Power Station - UFSAR Revis ion 15 -

FPR Revision 24 - October 2019 Attachments :

Attachment A- Updated Final Safety Analysis Report (UFSAR) - Revision 15 Change Summary Report Attachment B- Fire Protection Report (FPR) - Revision 24 Change Summary Report Attachment C- 10 CFR 54.37(b) Aging Management Review Summary Attachment D- OSM Directory Structure cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Quad Cities Nuclear Power Station NRC Project Manager, NRR - Quad Cities Nuclear Power Station

QUAD CITIES STATION Attachment A Updated Final Safety Analysis Report (UFSAR)

Revision 15 Change Summary Report 17-R15-001, Revision to UFSAR Tables 6.2-7 and 6.4-1 Revised to add a new Primary Containment Isolation Valve , argon and nitrogen gas volumes installed as part of the Hardened Containment Vent System (HCVS) .

17-R15-003, Revision to UFSAR Section 7.3 Revised to add information about the bypass installed on the RCIC high steam flow isolation signal.

17-R15-004, Revision to UFSAR Section 11.4 Revised to add information about allowing Reactor wastes and processed fuel channels that may be packaged to the Interim Radwaste Storage Facility for temporary storage.

17-R15-005, Revision to UFSAR Section 4.6 Revised to add information about the use of a slightly different control blade type. The new blade type is different in neutron absorber configuration only.

17-R15-006, Revision to UFSAR Section 7.3 Revised to add information about the bypass installed on the RCIC high steam flow isolation signal.

17-R15-007, Revision to UFSAR Table 7.3-1 Revised to change the Group 1 Steam line high flow analytical limit from 140% to 130% of rated flow.

17-R15-008, Revision to UFSAR Sections 1.2, 3.9, 4.1 , 4.3, 4.4, 4.6, 5.2, 6.2, 6.3, 7.6, 7.8, 15.0, 15.1, 15.2, 15.3, 15.4, 15.5, 15.7 and 15.8. Also revises Table 1.2-3, Tables 4.1-1 &

4.1-3, and Table 5.1-1 Revised to add information associated with the AREVA ATRIUM 10XM fuel transition from License Amendment 259 for Unit 2.

17-R15-009, Revision to UFSAR Table 8.3-1 Revised to add information on the 4.16 kV Bus 24 incoming feeder breakers .

17-R15-010, Revision to UFSAR Table 6.4-1 Revised to add Argon and Nitrogen gas volumes in the Hardened Containment Vent System (HCVS) bottles.

17-R15-011, Revision to UFSAR Section 9.2 Revised to change the description on the number discharge check valves installed to be consistent with UFSAR Section 3.4.1.2 .1.2.

17-R15-012, Revision to UFSAR Section 11.5 and Figure 11.5-1 Revised the failure position of the Off-Gas Isolation (holdup) valve 1-5406 from fail-closed to fail-open.

1 of 2

QUAD CITIES STATION Attachment A Updated Final Safety Analysis Report (UFSAR)

Revision 15 Change Summary Report 17-R15-013, Revision to UFSAR Section 6.3 Revised the automatic operation of the HPCI steam supply valves to be consistent with statements in another part of the same section and the design basis of the plant.

17-R15-014, Revision to UFSAR Sections 5.2 and 6.6, and Appendix A Revised to update the references regarding license renewal CASS exams.

17-R15-015, Revision to UFSAR Section 9.5 Revised to remove exact details of the radio communication system since it was modified.

17-R15-016, Revision to UFSAR Table 8.3-1 Revised to reflect the change from SF6 to vacuum for Bus 14 breakers.

17-R15-017, Revision to UFSAR Section 6.3 Revised to another leakage source which will include Core Spray P4D weld repair clamp for U1 only.

17-R15-018, Revision to UFSAR Section 6.6 Revised to change snubber testing reference from TRM 3.7.h to TRM 5.5.15.

17-R15-019, Revision to UFSAR Section 3.9 Revised to add a new paragraph and reference in regard to ASME code reconciliation for use of higher allowable stresses.

17-R15-020, Revision to UFSAR Sections 3.2, 5.4, 6.3 and 9.2 Revised to clarify the applicable codes of construction between the RHR main pumps and the RHR service water pumps.

17-R15-021, Revision to UFSAR Sections 4.6 and 15.4 and Table 4.1-2 Revised to remove the outdated rod speed requirement associated with a Rod Withdraw Error (RWE), with the Optima 1OXM fuel transition.

17-R15-022, Revision to UFSAR Section 7.3 Revised to include a description of two keylock switches added to Panel 901-15 and 17 to defeat the Primary Containment Isolation System (PCIS) Group 1 signal.

17-R15-023, Revision to various UFSAR Sections Revised to make miscellaneous editorial changes. Among the editorial changes is adding the words "now Framatome" because AREVA has officially changed its name to Framatome.

17-R15-024, Revision to UFSAR Section 6.4-4 Revised to delete the specific differential pressure number for the Main Control Room Envelope area.

2 of 2

QUAD CITIES STATION Attachment B Fire Protection Report (FPR)

Revision 24 Change Summary Report FPR-R24-002, Revision to FPR Volume 2, Section 3.1 .6.1, Page 3-7 The safe shutdown analysis currently mentions that the SBOs have enough fuel to run for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of operation. However, the requirement is only 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, allowing enough time for a truck to replenish the supply. SBO performance was re-evaluated under EC 621461 assuming less fuel initially. Therefore , the statement that the SBOs have enough fuel for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> was removed from the safe shutdown analysis.

FPR-R24-003, Revision to FPR Volume 1, Section 2.1, Table 2.1-2, Page 2.1-12 EC 620686 installs a new trolley beam/hoist assembly above the elevation 595' floor hatch on the bottom flange of the structural steel supporting the Turbine Building (TB) mezzanine floor slab at elevation 611 '-6". The trolley beam/hoist assembly will be used to remove the floor plug at elevation 595' and to lower/lift the 2B core spray motor from elevation 595' to elevation 554'.

The new trolley beam/hoist assembly and the adjacent (in-place) trolley beam obstruct the distribution of water from a sprinkler nozzle to the floor area below. A new deviation was added to Table 2.1-2 for NFPA 13.

FPR-R24-004, Revision to FPR Volume 1, Section 4.3, Pages 4.3-154, 4.3-155, 4.3-157, 4.3-168, 4.3-171, 4.3-17 4 The extinguishers in the heater bays cannot be inspected monthly per NFPA 1O during power operation . Therefore , the FPR is revised to allow the staging of extinguishers outside the heater bays during power operation.

FPR-R24-005, Revision to FPR Volume 2, Section 5.2.1.5.1, Pages 5-6 The circuit analysis (QDC-0000-E-1038) was added as a reference to the MSIV section of the SSD report.

1 of 1

QUAD CITIES STATION Attachment C 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 ag ing 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 June 1, 2017 to August 1, 2019. The review included :

  • Interviews of Program Managers/SME's,
  • Engineering Changes that were installed or completed since the last UFSAR update,
  • UFSAR pending change descriptions and revised text,
  • Licensing Correspondence to and from the NRC.

A total of 16 Environmental Qualification program "newly identified" components requiring evaluation of TLAA's were identified in accordance with the License Renewal Rule. A LS-AA-107 UFSAR Change Request to update the UFSAR to document these newly identified SSCs will be processed and tracked under Passport ATI 04074584-37. No other "newly identified" SSCs requ iring aging management were identified as a result of this review.

1 of 1

QUAD CITIES STATION Attachment D OSM Directory Structure Directory Path File Name Size 001 QDC UFSAR Rev 15 000 List of Effective Pages.pdf 205 KB 001 QDC UFSAR Rev 15 001 Chap 01 lntroduction .pdf 374 KB 001 QDC UFSAR Rev 15 002 Chap 02 Site Characteristics.pdf 1630 KB 001 QDC UFSAR Rev 15 003 Chap 03 Design of Structs, Compnts , Equip.pdf 7917 KB 001 QDC UFSAR Rev 15 004 Chap 04 Reactor.pdf 6128 KB 001 QDC UFSAR Rev 15 005 Chap 05 Reactor Coolant Sys.pdf 2502 KB 001 QDC UFSAR Rev 15 006 Chap 06 Engineered Safety Features.pdf 13022 KB 001 QDC UFSAR Rev 15 007 Chap 07 Instrumentation and Controls.pdf 3765 KB 001 QDC UFSAR Rev 15 008 Chap 08 Electric Power.pdf 737 KB 001 QDC UFSAR Rev 15 009 Chap 09 Auxiliary Systems.pdf 7648 KB 001 QDC UFSAR Rev 15 010 Chap 10 Steam and Power Conversion .pdf 569 KB 001 QDC UFSAR Rev 15 011 Chap 11 Radioactive Waste Mgmt.pdf 1815 KB 001 QDC UFSAR Rev 15 012 Chap 12 Radiation Protection .pdf 450 KB 001 QDC UFSAR Rev 15 013 Chap 13 Conduct of Operations .pdf 661 KB 001 QDC UFSAR Rev 15 014 Chap 14 Initial Test Program .pdf 1441 KB 001 QDC UFSAR Rev 15 015 Chap 15 Accident and Transient Analyses .pdf 2708 KB 001 QDC UFSAR Rev 15 016 Chap 16 Technical Specifications.pdf 36 KB 001 QDC UFSAR Rev 15 017 Chap 17 Quality Assurance .pdf 49 KB 001 QDC UFSAR Rev 15 018 Appendix A.pdf 149 KB 002 QDC FPR Rev 24 001 QDC FPR VOL 1.pdf 2594 KB 002 QDC FPR Rev 24 002 QDC FPR VOL 2.pdf 935 KB 003 QDC TRM 001 QDC TRM .pdf 2875 KB 004 QDC Tech Spec Bases 001 QDC Tech Spec Bases.pdf 2291 KB 1 of 1

Retrieved from "https://kanterella.com/w/index.php?title=RS-19-098,_Submittal_of_Revision_15_to_Updated_Final_Safety_Analysis_Report,_and_Revision_24_to_Fire_Protection_Report&oldid=2075701"